... vi. DOE/RL-96-62, Rev. 0 07/ INTRODUCTION FACILITY LOCATION RESPONSIBLE MANAGER (Requirement 2)... 4
|
|
- Junior Floyd
- 5 years ago
- Views:
Transcription
1
2
3 CONTENTS TERMS v METRIC CONVERSION CHART vi 1.0 INTRODUCTION FACILITY LOCATION RESPONSIBLE MANAGER (Requirement ) TYPE OF PROPOSED ACTION (Requirement 3) STATE ENVIRONMENTAL POLICY ACT (Requirement 4) PROCESS DESCRIPTION (Requirements 5 end 7) ANNUAL POSSESSION QUANTITY AND PHYSICAL FORM (Requirents 8,,, end 1) CONTROL SYSTEM (Requirement 6) MONITORING SYSTEM (Requirement ) RELEASE RATES (Requirement ) OFFSITE IMPACT (Requirements and ) FACILITY LIFETIME (Requirement ).. 1.O TECHNOLOGY STANDARDS (Requirement ) DISCUSSION OF BEST AVAILABLE RADIONUCLIDE CONTROL TECHNOLOGY....0 REFERENCES FIGURES Hanford Site Plutonium Finishing Plant Complex Process Flow Diagram of the Vertical Calciner Appl icable Control Technology Components iii
4 1 TABLES Isotopic Distribution for Weapons Grade Production Plutonium Potential Annual Unabated Emissions Potential Annual Abated Emissions , Radionuclide Air Emissions Data for the 1--1 Stack (PFP) Potential Annual Unabated Offsite Dose Potential Annual Abated Offsite Dose iv
5 1 3 TERMS 4 ALARA as low as reasonably achievable 6 BARCT best available radionuclide control technology 5 7 a CFR DCG Code o f Federal Regulations derived concentration guide1 ines 1 DF decontamination factor EPA U.S. Environmental Protection Agency HEPA high-effici ency particulate air ME1 1 0 NOC 1 PFP 3 4 SEPA 5 6 WAC maximally exposed individual notice of construction Plutonium Finishing Plant Complex State Environmental P o l i c y Act o f I71 Washington Administrative Code V
6 Into metr-ic units METRIC CONVERSION CHART Out of metric units gal 1 ons 1 i ters 1 i ters cubic cubic meters meters cubic yards cubic meters cubic meters cubic yards Temperature Temperature Fahrenheit subtract 3 then multiply Celsius Celsius multiply by /5ths, Fahrenheit by 5/ths then add 3 Force Force pounds per square inch 6.85 ki 1 opascal s ki 1 opascal s x pounds per square inch Source: Engineering Unit Conversions, M. R. Lindeburg, PE., Second Ed.,, Professional Publications, Inc., Belmont, California Vi
7 RADIOACTIVE AIR EMISSIONS NOTICE OF CONSTRUCTION FOR VERTICAL CALCINER OPERATION AT THE PLUTONIUM FINISHING PLANT 1.0 INTRODUCTION This document serves as a notice of construction (NOC) for construction, installation, and operation of a vertical calciner to stabilize plutonium at the Plutonium Finishing Plant (PFP) Complex, pursuant to the requirements of Washington Administrative Code (WAC) The PFP Complex is located in the 00 West Area of the Hanford Site (Figure 1). The PFP Complex consists of several large and small buildings that are grouped to form the processing complex (Figure ). The PFP Complex activities are focused on the cleanout and stabilization of plutonium residue left from plutonium weapons material processing activities. Approximately 4,800 liters of plutonium and transuranic solutions are stored at the PFP Complex, predominantly in -liter stainless steel vessels and some -liter polyethylene bottles, normally filled to 8.5 liters of solution. The total mass of plutonium and americium contained within this volume is approximately 335 kilograms. The polyethylene containers used to store the plutonium solutions were not designed for extended storage, and currently the polyethylene bottles are degrading. Plutonium solutions are acidic and corrosive and can damage the stainless steel vessels now used for storage, leading to leakage. Other potential vulnerabilities associated with the plutonium-bearing containers include the potential for radiolytic damage, hydrogen generation, and plutonium precipitation. The solutions are stored in containers with a favorable geometrical shape to prevent criticality. Historically, the PFP Complex processed pl utoni um-based chemical solutions and converted these solutions into purified oxide and metal by way of a precipitation and filtration process, which yielded an acidic filtrate containing more plutonium than could be discarded. The prime purpose of the vertical calciner is to convert plutonium acid solutions to a more stable plutonium oxide. A test calciner has been developed and put in place in Room 8 of the 34-5 Building. Development testing of this vertical calciner is ongoing. A new vertical calciner will be assembled for actual stabilization operation in Room 30C of the 34-5 Building. The test calciner in Room 8 may be upgraded or replaced as an alternative to building a new calciner in Room 30C..0 FACILITY LOCATION (Requirement 1) U.S. Department of Energy, Richland Operations Office Hanford Site 00 West Area, Plutonium Finishing Plant Complex Richland, Washington 35.
8 Figure 1. Hanford Site. T
9 DOE/RL-6-6, Rev, 0 Figure. Plutonium Finishing Plant Complex. 6O7.77 7
10 DOE/RL-6-6, The geodetic coordinates for the main stack, 1--1 are as follows: Rev. 0 Latitude:. 46' 3 ' 5" North 3.0 Longitude: RESPONSIBLE MANAGER ' 3 7 ' 5" West (Requirement ) Mr. J. E. Mecca, Director, Transition Program Division U.S. Department of Energy, Richland Operations Office P.O. Box 550 Richland, Washington 35 (50) TYPE OF PROPOSED ACTION (Requirement 3 ) The proposed action is a modification of the existing process within the PFP Complex. It is proposed that a vertical calciner be constructed and installed in Room 30C of the 34-5 Building and operated to stabilize the plutonium. A potential increase in emissions will occur at emission point Historically, the emissions at this point have remained relatively constant whether or not there were any processes operating. No actual increase in emissions is anticipated from the operation of the vertical calciner. 5.0 STATE ENVIRONMENTAL POLICY ACT (Requirement 4) The Washington State Department of Health has determined that this activity is categorically exempt from the State Environmental Po7icy Act (SEPA) o f 1 process. Separately, under the National Environmental Policy Act (NEPA) o f, the U.S. Department of Energy, Richland Operations Office (DOE-RL) has included the activity in the PFP Stabilization Environmental Impact Statement (EIS) (DOE-RL ). A Record of Decision was issued by DOE-RL on June 5,, which included a pretreatment ion exchange process and vertical calcination as part of the preferred alternative for stabi 1 ization of pl utonium-bearing solutions. 6.0 PROCESS DESCRIPTION (Requirements 5 and 7) A vertical calciner was tested at the PFP Complex during the early ' s as a method to continuously convert plutonium nitrate solution to plutonium dioxide. This method has advantages over more complex stabilization methods involving precipitation, filtration, and calcination steps because this involves only the calcination step
11 B VACUUM VACUUM TRAP DEMISTER. 0 0 m r W I W CLEANOUI ROD PUNO~ FEED TANK m I m N W I D.O-44 m 0 W
12 a za The vertical calciner design (Figure 3) proposed for stabilizing the plutonium solutions under the EIS (Section 5.0) is similar to the calciner tested in the 0's-. The temperatures in the calciner will be 00 to 1O5O0C, appreciably higher than those employed historically. The 0's model vertical calciner was operated at temperatures that completely decomposed the plutonium nitrate while preserving plutonium reactivity for purposes of subsequent weapons processing. The higher temperatures of the current design will minimize plutonium reactivity. Other operational improvements have been made that primarily improve the handling methods of the effluents from the process. Approximately 75 percent of the plutonium-bearing solutions, containing roughly a third of the source term, will require a pretreatment ion exchange process in Room 8A of the 34-5 Building. The vertical calciner will be assembled in a glovebox in the 34-5 Building. The equipment will be sized to process 1 to liters per hour of solution for concentrated feeds and 3 to 4 liters per hour for dilute feeds. The feed rate is variable to ensure the plutonium introduced into the vertical calciner has sufficient residence time to produce a suitable oxide. The plutonium solutions will be slowly introduced into a stirred bed of previously generated product solids. This feed material will be slowly metered into the bottom of the vertical calciner. The feed rate will depend on the concentration of plutonium in the solution being processed. The feed will be roughly 1 to liters per hour for concentrated feeds (>5 grams plutonium per liter) and 3 to 4 liters per hour for dilute feeds (<5 grams plutonium per liter). The vertical calciner is a combination calciner and a -micron offgas filter. Plutonium solutions are calcined in the lower unit and the vapors are filtered in the upper unit. The calcination unit can be described as two concentric pipes. Calcination takes place in the annular space between these two pipes. As the liquid feed is introduced into the calciner, the feed rapidly evaporates in the hot powder bed, subsequently undergoing drying, denitration, and final heat treatment to a stable impure plutonium oxide powder. Heat is supplied to the calcination unit by heaters wrapped around the outer pipe wall and inside the inner pipe wall. The heaters maintain the cal ciner temperature between 00 and 50 C. These temperatures are considerably higher than required for decomposition of nitrate (0 to 5OC). The higher temperature serves to greatly reduce the plutonium reactivity, to promote complete formation of plutonium dioxide, and to facilitate a packageabl e plutonium product. During calcination, the hot plutonium powder bed is stirred continuously by a U-shaped agitator that fits over the inner, capped pipe. The agitator speed affects both the particle size of the plutonium dioxide powder and the rate of heat transfer between the powder and the calciner wall. During the thermal denitration, solutions containing alkaline metal nitrates (i.e., potassium nitrate) tend to become increasingly viscous and 6O7. 6
13 DOE/RL-6-6, Rev. 0 p a s t y b e f o r e d e c o m p o s i t i o n. These mastic-phase f o r m a t i o n s a r e u n d e s i r a b l e, as t h e s e f o r m a t i o n s can form h a r d d e p o s i t s on equipment s u r f a c e s and on p a r t i c u l a t e m a t e r i a l. t h r o u g h t h e r e a c t i o n zone. M a s t i c f o r m a t i o n i s a v o i d e d b y c o n v e r t i n g t h e f e e d s o l u t i o n t o d r y o x i d e as q u i c k l y as p o s s i b l e, o r by removing t h e i m p u r i t i e s t h r o u g h t h e i o n exchange p r e t r e a t m e n t p r o c e s s. The slow feed r a t e i n t o the c a l c i n e r w i l l f a c i l i t a t e a r a p i d t r a n s i t i o n t o oxide and a v o i d problems w i t h t h e m a s t i c phase f o r t h o s e s o l u t i o n s which do n o t undergo t h e p r e t r e a t m e n t i o n exchange process. The p l u t o n i u m o x i d e p r o d u c t i s d i s c h a r g e d i n t o a p r o d u c t r e c e i v e r as d e s c r i b e d i n t h e f o l l o w i n g paragraphs. The p l u t o n i u m o x i d e i s c o l l e c t e d as i t o v e r f l o w s t h r o u g h a s l o t i n t h e i n n e r p i p e. The p r o d u c t powder c o n s i s t s o f r e l a t i v e l y l a r g e, u n i f o r m p a r t i c l e s. The g r i n d i n g a c t i o n o f t h e a g i t a t o r p r e v e n t s t h e o x i d e p a r t i c l e s f r o m becoming t o o l a r g e. The o x i d e proceeds down an o v e r f l o w t u b e and i n t o a p r o d u c t bed r e c e i v e r v e s s e l. The h e i g h t o f t h e o v e r f l o w t u b e can be a d j u s t e d t o c o n t r o l t h e bed volume w i t h i n t h e c a l c i n e r. When t h e p r o d u c t r e c e i v e r v e s s e l i s f u l l, t h e o x i d e w i l l be bagged o u t o f t h e g l o v e b o x. I f t h e p l u t o n i u m p r o d u c t does n o t meet r e q u i r e m e n t s o f t h e U. S. Department o f Energy l o n g - t e r m s t o r a g e s t a n d a r d 30-4 (DOE ), i t w i l l be t r a n s f e r r e d t o a m u f f l e f u r n a c e c a p a b l e o f m e e t i n g t h e nominal l,ooo C f i r i n g t e m p e r a t u r e r e q u i r e d by t h e s t a n d a r d. A f t e r t h e r m a l s t a b i l i z a t i o n i n t h e m u f f l e f u r n a c e i s completed, a sample o f t h e o x i d e w i l l be s e n t t o t h e e n g i n e e r i n g l a b o r a t o r y t o v e r i f y t h a t t h e l o s s on i g n i t i o n i s <0.5 w e i g h t p e r c e n t. F o l l o w i n g t h i s f i n a l v e r i f i c a t i o n, t h e p l u t o n i u m p r o d u c t w i l l be t r a n s f e r r e d t o t h e PFP Complex v a u l t s u n t i l a f i n a l p l u t o n i u m d i s p o s i t i o n d e c i s i o n i s made. The c a l c i n e r o f f g a s stream c o n s i s t s o f a m i x t u r e o f a i r, water, n i t r i c and a small component o f o r g a n i c i m p u r i t i e s. a c i d, o x i d e s o f n i t r o g e n (NO,), Aqueous h y d r o c h l o r i c s o l u t i o n s r u n t h r o u g h t h e c a l c i n e r w i l l y i e l d c h l o r i d e i n t h e o f f g a s, w h i c h w i l l be scrubbed o u t as sodium c h l o r i d e. I n a d d i t i o n, f i n e p l u t o n i u m o x i d e powder c o u l d be e n t r a i n e d i n t h e o f f g a s stream. The o f f g a s stream i s r u n t h r o u g h two m i c r o n f i l t e r s t o remove t h e e n t r a i n e d o x i d e powder. The f i l t e r s p e r i o d i c a l l y a r e blown back with compressed a i r t o knock p a r t i c l e s f r o m t h e f i l t e r back i n t o t h e base o f t h e c a l c i n e r. The f i l t e r s a r e blown back a l t e r n a t e l y so t h a t one f i l t e r i s always i n o p e r a t i o n. A vacuum a p p l i e d t o t h e f i l t e r s draws o f f vapors t h a t a r e r u n t h r o u g h a combined condenser and s c r u b b e r. T h i s removes t h e m a j o r i t y o f water and n i t r i c a c i d i n t h e o f f g a s and any p l u t o n i u m t h a t m i g h t pass t h e f i l t e r s. A b a s i c s c r u b b i n g s o l u t i o n removes a c i d gases such as hydrogen c h l o r i d e as w e l l as n i t r o g e n o x i d e s. The nonreacted, n o n c o m b u s t i b l e o f f g a s e s r e m a i n i n g a f t e r t h e s c r u b b e r / c h i l l e r p r o c e s s i n g proceed t h r o u g h two e x i s t i n g stages o f h i g h - e f f i c i e n c y p a r t i c u l a t e a i r (HEPA) f i l t r a t i o n b e f o r e b e i n g r e l e a s e d o u t t h e 1--1 main s t a c k. The offgases c o n s i s t o f w a t e r and a i r, w i t h o n l y t r a c e amounts o f NO,. The r e s u l t a n t aqueous s c r u b s o l u t i o n c o n s i s t s o f sodium h y d r o x i d e, w a t e r, sodium c h l o r i d e, sodium n i t r a t e, and sodium n i t r i t e. 607.
14 DOE/RL-6-6, Rev. 0 ANNUAL POSSESSION QUANTITY AND PHYSICAL FORM (Requirerents 8,., and 1) The t o t a l amount o f r a d i o a c t i v e m a t e r i a l i n t h e p l u t o n i u m n i t r a t e s o l u t i o n s i s e s t i m a t e d a t 335 k i l o g r a m s (DOE-RL ). To d e t e r m i n e t h e annual p o s s e s s i o n q u a n t i t y, t h e i s o t o p i c d i s t r i b u t i o n i n T a b l e 1 (WHC ) was appl ied t o 335 k i 1ograms. Both f u e l s g r a d e and weapons grade m a t e r i a l were processed a t t h e PFP Complex. Because t h e f e e d s o l u t i o n s t o t h e c a l c i n e r a r e a s s o c i a t e d w i t h weapons g r a d e p l u t o n i u m, d i s t r i b u t i o n o f i s o t o p e s f o r weapons grade m a t e r i a l was used t o e s t i m a t e a c o n s e r v a t i v e p o t e n t i a l - t o - e m i t and o f f s i t e dose f o r t h e a c t i v i t y. A l l i s o t o p e s i n t h e i n v e n t o r y o f each r a d i o n u c l i d e a r e presumed t o be i n l i q u i d form. Abundance* (weight percent) Radioisotope 1 0 Pu Pu Pu Pu I Am CONTROL SYSTEM (Requirement 6 ) No a d d i t i o n a l emission c o n t r o l equipment i s planned f o r t h e main s t a c k as t h e e x i s t i n g p l a n t equipment i s adequate ( F i g u r e 4 ). There a r e no v o l a t i l e r a d i o i s o t o p e s i n t h e i n v e n t o r y and a l l o f t h e m a t e r i a l i s i n s o l u t i o n. The HEPA f i l t e r system i n t h e b u i l d i n g i s accepted as b e s t a v a i l a b l e r a d i o n u c l i d e c o n t r o l t e c h n o l o g y (BARCT) i n t h e absence o f v o l a t i l e substances. T h i s was c o n f i r m e d b y Washington S t a t e Department o f H e a l t h i n 1 (Moon 1)
15 r- Figure 4 Applicable Control Technology Components 607.
16 .0 MONITORING SYSTEM (Requirement ) The 1--1 main stack is equipped with a stack sampler consisting of an alpha continuous air monitor and a record sampler. The Washington State Department of Health, Radiation Protection Division, inspected this unit during a comprehensive inspection in July. There were no findings specific to the system and the system meets the requirement for continuous sampling as required by 40 CFR 61, Subpart H. Radioisotope Pu-38 Pu-3 Pu-40 Pu-41 Am-41.0 RELEASE RATES (Requirement ) The emissions noted in Table were calculated based on the total inventory of approximately 335 kilograms. The emission of a given isotope is the product of the total inventory amount multiplied by the abundance percentage and the activity rate and adjusted by the release factor of for liquids (based on the discussion in Section 7.0 of the release form of each radionuclide). This is illustrated typically as follows using Pu-38: (335 kg) x (00 g/kg) x (.0001) x (.1 Ci/g) x = 5.73E-01 Cilyr. Table. Potential Annual Unabated Emissions. Weight Activity rate Release Unabated (grams) (curies per fraction emissions gram) (curies per Year) 3.35 Et Et01 1 E E Et E-0 1 E Et01 1. Et04.30 E-01 1 E EtOO.05 Et0 1. Et0 1 E-03.5 Et Et0 3.0 EtOO 1 E-03. EtOO The abated emissions were calculated from the unabated emissions listed in Table and the decontamination factor (WHC, page 5). A decontamination factor of,000 was used in the calculations based on the.5 percent efficient HEPA filter. The abated emissions equals the unabated emissions divided by the decontamination factor. The potential annual abated emissions from the activity are shown in Table 3.
17 Rad i o i sot ope Pu-38 Pu-3 Pu-40 Pu-41 Am-41 Pu-38 Pu-3 Pu-40 Pu-41 Am-41 Radioisotope Unabated Decontamination Abated emissions Emissions factor (curies per (curies per year) year) 5.73 E-01.0 Et03.86 E Et01.0 Et03.74 E Et01.0 Et03. E-0.5 Et01.0 Et E-0. Et00.0 Et E-03 The air emissions data for the 1--1 stack listed in Table 4 were taken from the Radionuclide Air Emissions Report for the Hanford Site, Calendar Year (DOE-RL a, page -4). Annual emissions (curies) 1.5 E E-04.0 E E E-05.0 OFFSITE IMPACT (Requirements and ) This section contains information regarding the total effective dose equivalents (TEDE) to the maximally exposed individual (MEI) offsite resulting from unabated and abated emissions from the activity. The ME1 is located 4 kilometers west of the 00 West Area. The potential unabated and abated TEDE to the ME1 of 6.6 and millirem per year, respectively, are summarized in Table 5 and Table 6. The unit dose factors included in the tables were submitted previously to the Washington State Department of Health. 607.
18 1 The information required t o develop the unit dose factors was from the "Clean Air Act Assessment Package 8" computer code (WHC ). 5 Table 5. Potential Annual Unabated Offsite Dose Table 6. Potential Annual Abated Offsite Dose. Radioisotope Pu-38 Pu-3 Pu-40 Pu-41 Am-41 Total dose Abated emissions (curie per year).86 E E-03. E E E-03 WA Unit dose factor (millirem per curie) N/A 1.0 FACILITY LIFETIME Abated dose (millirem per year) 6.1 E E E-03.4 E E E-0 (Requirement ) Stabilization of plutonium solutions using the calciner is estimated to require 1 to years to complete. The lifetime of the PFP Complex and this vertical calciner will depend on the future mission as determined by t h e DOE-RL
19 .0 TECHNOLOGY STANDARDS (Requirement ) The 1--1 stack is a registered stack with the Washington State Department of Health. The stack design and operation will not be modified to complete the stabilization of the plutonium solution using the vertical calciner process The U.S. Environmental Protection Agency (EPA), Headquarters, was requested to approve the 1--1 stack sampl ing/monitoring system as compliant with 40 CFR 61, Subpart H, on September 8, (DOE-RL b). On September 1,, the EPA approved the 1--1 stack to be in compliance with the requirements of 40 CFR 61, Subpart H (DOE-RL ~)..0 DISCUSSION OF BEST AVAILABLE RADIONUCLIDE CONTROL TECHNOLOGY The HEPA filter system in the building is considered BARCT in the absence of volatile substances. The Washington State Department of Health, Radiation Protection Division, inspected this unit during a comprehensive inspection in July. There were no findings specific to the system. 607.
20 DOE/RL-6-6, Rev. 0 REFERENCES DOE,, Criteria for Safe Storage o f Plutonium Metal and O x i d e s, DOE-STD DOE-RL, a, Radionuclide Air Emissions Report for the Hanford Site, Calendar Year, DOE/RL-5-4, U.S. Department o f Energy, R i c h l a n d O p e r a t i o n s O f f i c e, R i c h l and, Washington. DOE-RC, b, L e t t e r, "Request f o r Approval f o r t h e 1--1 S t a c k Sampl i n g / M o n i t o r i n g System", d a t e d September 8,, U.S. Department o f Energy, R i c h l a n d O p e r a t i o n s O f f i c e, R i c h l a n d, Washington. DOE-RL, c, L e t t e r, R i c h a r d W. Poeton, EPA, t o James E. Rasmussen, DOE-RL, d a t e d September,, L e t t e r # AT-08, U.S. E n v i r o n m e n t a l P r o t e c t i o n Agency, Region, S e a t t l e, Washington. DOE-RL,, Plutonium Finishing Plant Stabilization Final Environmental Impact Statement, DOE/EIS-044-F, U.S. Department o f Energy, R i c h l a n d O p e r a t i o n s O f f i c e, R i c h l and, Washington. Moon, T. W., 1, October 5, 1, Telephone Conference Memorandum, t o K. F o x - W i l l i a m s o f t h e S t a t e o f Washington Department o f H e a l t h, A i r & Water P e r m i t t i n g, memo , Westinghouse H a n f o r d Company, R i c h l and, Washington. WHC,, Unit Dose Calculation Methods and Summary of Facility Effluent Monitoring Plan Determinations, WHC-EP-048, Westinghouse H a n f o r d Company, R i c h l a n d, Washington. WHC, a, Hanford Site Radionuclide National Emission Standards for Hazardous Air Pollutants Registered and Unregistered Stack (Powered Exhaust) Source Assessment, WHC-EP-084, Westinghouse H a n f o r d Company, R i c h l a n d, Washington. WHC,, Plutonium Finishing Plant Safety Analysis Report, WHC-SD-CP-SAR-01, Rev. OC, Westinghouse H a n f o r d Company, R i c h l and, Washington. 607.
21 DOE/RL-6-6, Rev. 0 DISTRIBUTION OFFSITE A. W. C o n k l i n, Head A i r Emissions and Defense Waste S e c t i o n D i v i s i o n o f Radiation P r o t e c t i o n S t a t e o f Washington Department o f H e a l t h A i r d u s t r i a l P a r k B u i l d i n g 5, LE-I3 Olympia, Washington ' J. L e i t c h, C h i e f R a d i a t i o n and I n d o o r A i r S e c t i o n U.S. Environmental P r o t e c t i o n Agency Region 0 S i x t h Avenue S e a t t l e, Washington 81 J. Wilkinson Confederated T r i b e s o f t h e U m a t i l l a Indian Reservation P. 0. Box 638 Pendleton, Oregon 7801 D. Powaukee Nez Perce T r i b e P. 0. Box 305 Lapwai, Idaho R. Jim, Manager Environmental R e s t o r a t i o n / Waste Management Program Confederated T r i b e s and Bands o f t h e Yakama N a t i o n P. 0. Box 1 Toppenish, Washington 848 ONSITE U.S. Department o f Energy, Richland Ooerations O f f i c e C. M. B e l l R. M. C a r o s i n o J. E. Mecca R. S. O l l e r o H. M. Rodriguez D. W. Templeton OSTI ( ) Reading Room ( ) Distr-1 MSIN A5-5 A4-5 R3-7 R3-7 A5- R3-7 E6-44 H-53
22 ONSITE DISTRIBUTION (cont) Pacific Northwest National Laboratory Hanford Technical Library Westinqhouse Hanford Comoany P. K. Aardal T. E. Frazier R. E. Johnson (5) D. J. McBride () P. J. Sullivan Air Operating Permit File DPC EDMC () Central Files MSIN K1- A3-01 H6-5 H6-5 T5-54 T5-54 H6-5 A3-4 H6-08 ~3-8a Distr-
WASTE CHARACTERIZATION FOR RADIOACTIVE LIQUID WASTE EVAPORATORS AT ARGONNE NATIONAL LABORATORY - WEST
WASTE CHARACTERIZATION FOR RADIOACTIVE LIQUID WASTE EVAPORATORS AT ARGONNE NATIONAL LABORATORY - WEST Low Level, Intermediate Level, and Mixed Waste By Boyd D. Christensen Operations Division and Michael
More informationUNIVERSITY OF HOUSTON ENVIRONMENTAL HEALTH AND & LIFE SAFETY POLICIES AND PROCEDURES I. PURPOSE
UNIVERSITY OF HOUSTON ENVIRONMENTAL HEALTH AND SAFETY POLICIES AND PROCEDURES SECTION: SUBJECT: ENVIRONMENTAL HEALTH AND & LIFE SAFETY HAZARD COMMUNICATION I. PURPOSE This procedure establishes the requirements
More informationMETHOD 7B - DETERMINATION OF NITROGEN OXIDE EMISSIONS FROM STATIONARY SOURCES (ULTRAVIOLET SPECTROPHOTOMETRIC METHOD)
683 METHOD 7B - DETERMINATION OF NITROGEN OXIDE EMISSIONS FROM STATIONARY SOURCES (ULTRAVIOLET SPECTROPHOTOMETRIC METHOD) NOTE: This method does not include all of the specifications (e.g., equipment and
More informationRadcalc: A Computer Program to Calculate the Radiolytic Production of Hydrogen Gas From Radioactive Wastes in Packages
Radcalc: A Computer Program to Calculate the Radiolytic Production of Hydrogen Gas From Radioactive Wastes in Packages Prepared for the U.S. Department of Energy Office of Environmental Restoration and
More informationTransuranic Wastes at Hanford. Robert Alvarez
Transuranic Wastes at Hanford Robert Alvarez May 2009 Transuranic (TRU) wastes are contaminated with radioactive elements heavier than uranium on the periodic chart ( i.e. plutonium, americium, curium
More informationFlammable/Combustible Liquid Storage
8.12.1 RESPONSIBILITY University personnel are responsible for using approved and safe methods for storing flammable/combustible liquids. Personnel must store flammable and combustible liquids in accordance
More informationTritium Fuel Cycle Safety
Tritium Fuel Cycle Safety W Kirk Hollis 1, Craig MV Taylor 1, Scott Willms 2 1 Los Alamos National Laboratory, 2 ITER IAEA Workshop on Fusion Energy June 14 th, 2018 Slide 1 Overview What is a Tritium
More informationStoring, using and disposing of unsealed radioactive substances in a Type C Laboratory: Extract of regulatory requirements
Storing, using disposing of unsealed radioactive substances in a Type C Laboratory: Extract of regulatory requirements Radiation Protection Control (Ionising Radiation) Regulations 2000 Requirements for
More informationHach Method Total Organic Carbon in Finished Drinking Water by Catalyzed Ozone Hydroxyl Radical Oxidation Infrared Analysis
Hach Method 1061 Total Organic Carbon in Finished Drinking Water by Catalyzed Ozone Hydroxyl Radical Oxidation Infrared Analysis Hach Company Method 1061 Revision 1. December 015 Organic Carbon in Finished
More informationAP1000 European 15. Accident Analyses Design Control Document
15.7 Radioactive Release from a Subsystem or Component This group of events includes the following: Gas waste management system leak or failure Liquid waste management system leak or failure (atmospheric
More informationFacilities Management
Policy Number: 700.20 Title: Chemical Fume Hood Policy Implementation Date: 2002 Last Audited: August, 2017 Last Revised: October 23rd, 2017 Facilities Management Introduction The laboratory chemical fume
More informationThe outermost container into which vitrified high level waste or spent fuel rods are to be placed. Made of stainless steel or inert alloy.
Glossary of Nuclear Waste Terms Atom The basic component of all matter; it is the smallest part of an element having all the chemical properties of that element. Atoms are made up of protons and neutrons
More informationTrihalomethane Formation Potential (THMFP)
Trihalomethane Formation Potential (THMFP) DOC316.53.01147 THM Plus Method 1 Method 10224 Scope and application: To determine the potential of potable source waters that form trihalomethanes and other
More informationRadioactive Waste Policies
Radioactive Waste Policies APRIL 8, 2012 By Maury Riner Approved: April 8, 2010 Radiation Safety Committee TABLE OF CONTENTS 1. Purpose 5 2. Scope 5 3. Radioactive Waste Classification 5 3.1 Waste Definitions
More informationSTATE OF COLORADO DESIGN CRITERIA FOR POTABLE WATER SYSTEMS WATER QUALITY CONTROL DIVISION. Price: $5.00. Revised March 31, 1997
STATE OF COLORADO DESIGN CRITERIA FOR POTABLE WATER SYSTEMS WATER QUALITY CONTROL DIVISION Revised March 31, 1997 Price: $5.00 a. an arrangement where the water pipe to be injected with chlorine enters
More information1. What would be the dose rate of two curies of 60Co with combined energies of 2500 kev given off 100% of the time?
1.11 WORKSHEET #1 1. What would be the dose rate of two curies of 60Co with combined energies of 500 kev given off 100% of the time?. What would be the dose rate of 450 mci of 137Cs (gamma yield is 90%)?
More informationRPR 29 CYCLOTRON RADIOCHEMISTRY LABORATORY
RPR 29 CYCLOTRON RADIOCHEMISTRY LABORATORY PURPOSE This procedure provides instructions for developing, maintaining, and documenting, radiation safety procedures conducted at the Cyclotron Radiochemistry
More informationEvaluation and Measurements of Radioactive Air Emission and Off-Site Doses at SLAC
SLAC-PUB-15365 Evaluation and Measurements of Radioactive Air Emission and Off-Site Doses at SLAC I.Chan, J.Liu, H.Tran SLAC National Accelerator Laboratory, M.S. 48, 2575 Sand Hill Road, Menlo Park, CA,
More informationGlossary of Common Laboratory Terms
Accuracy A measure of how close a measured value is to the true value. Assessed by means of percent recovery of spikes and standards. Aerobic Atmospheric or dissolved oxygen is available. Aliquot A measured
More informationThe Radiological Hazard of Plutonium Isotopes and Specific Plutonium Mixtures
LA-13011 The Radiological Hazard of Plutonium Isotopes and Specific Plutonium Mixtures Los Alamos NATIONAL LABORATORY Los Alamos National Laboratory is operated by the University of California for the
More informationDevelopment of an Improved Sodium Titanate for the Pretreatment of Nuclear Waste at the Savannah River Site
Development of an Improved Sodium Titanate for the Pretreatment of Nuclear Waste at the Savannah River Site D.T. Hobbs, M.R. Poirier, M.J. Barnes, M.E. Stallings, S.D. Fink Savannah River National Laboratory
More informationRadioactive Waste Characterization and Management Post-Assessment Answer Key Page 1 of 7
Key Page 1 of 7 1. Uranium tailings from mining operations are typically left in piles to. a. decay b. dry c. be re-absorbed d. be shipped to a disposal site 2. is the most important radioactive component
More informationHealth, Safety, Security and Environment
Document owner and change code Document Owner Aaron Perronne Title HSSE Manager Mark X Change Code Description X N/A First Issue A Typographical/Grammatical correction; formatting change; text clarification-no
More informationCHARACTERIZATION AND PROCESSING OF PYROCHEMICAL SALTS
CHARACTERIZATION AND PROCESSING OF PYROCHEMICAL SALTS Susan J. Eberlein, Safe Sites of Colorado, L.L.C. Micheline L. Johnson, Safe Sites of Colorado, L.L.C. ABSTRACT The Rocky Flats Environmental Technology
More informationSuccessful Development of a New Catalyst for Efficiently Collecting Tritium in Nuclear Fusion Reactors
January 15, 2015 Japan Atomic Energy Agency Tanaka Precious Metals Tanaka Holdings Co., Ltd. Successful Development of a New Catalyst for Efficiently Collecting Tritium in Nuclear Fusion Reactors World
More informationUniversity of Tennessee Safety Procedure
University of Tennessee Safety Procedure Program Subject: Chemicals Requiring Review Prior to Use Procedure Review/Revised: 12/15/08 Affected Area/Department: Laboratories at the University Date Effective:
More informationFact Sheet United States Nuclear Regulatory Commission Office of Public Affairs Washington, D.C Telephone: 301/
Fact Sheet United States Nuclear Regulatory Commission Office of Public Affairs Washington, D.C. 20555 Telephone: 301/415-8200 E-mail: opa@nrc.gov IRRADIATED GEMSTONES The Nuclear Regulatory Commission
More informationStandard Practice for Calculating Formulation Physical Constants of Paints and Coatings 1
Designation: D 5201 05 Standard Practice for Calculating Formulation Physical Constants of Paints and Coatings 1 This standard is issued under the fixed designation D 5201; the number immediately following
More informationSampling. Information is helpful in implementing control measures for reducing pollutant concentration to acceptable levels
Types of pollutant sampling and measurement: Air quality monitoring: Sampling and measurement of air pollutants generally known, as air quality monitoring. It is an integral component of any air pollution
More informationDimethylglyoxime Method Method to 6.0 mg/l Ni TNTplus 856
Nickel DOC316.53.01065 Dimethylglyoxime Method Method 10220 0.1 to 6.0 mg/l Ni TNTplus 856 Scope and application: For water and wastewater. Test preparation Instrument-specific information Table 1 shows
More informationChlorine, Free and Total, High Range
Chlorine, Free and Total, High Range DOC316.53.01490 USEPA DPD Method 1 Method 10069 (free) 10070 (total) 0.1 to 10.0 mg/l Cl 2 (HR) Powder Pillows Scope and application: For testing higher levels of free
More informationPROPOSED POLICY LETTER: CARRIAGE OF CONDITIONALLY PERMITTED SHALE GAS EXTRACTION WASTE WATER IN BULK
Commandant United States Coast Guard 2703 Martin Luther King Jr. Ave. SE Stop 7509 Washington, DC 20593-7509 Staff Symbol: CG-ENG 16710 From: To: Subj: J. W. MAUGER, CAPT COMDT (CG-ENG) Distribution PROPOSED
More informationCadmium Reduction Method Method to 30.0 mg/l NO 3 N (HR) Powder Pillows or AccuVac Ampuls
Nitrate DOC316.53.01066 Cadmium Reduction Method Method 8039 0.3 to 30.0 mg/l NO 3 N (HR) Powder Pillows or AccuVac Ampuls Scope and application: For water, wastewater and seawater. Test preparation Instrument-specific
More informationEXPERIMENT #4 Separation of a Three-Component Mixture
OBJECTIVES: EXPERIMENT #4 Separation of a Three-Component Mixture Define chemical and physical properties, mixture, solubility, filtration, sublimation, and percent Separate a mixture of sodium chloride
More informationU.S. Nuclear Regulatory Commission and Agreement States. Transportation of Radioactive Materials NRC Course H-308
UNIT 3 HAZARDOUS MATERIAL CLASSIFICATION and DETERMINATION U.S. Nuclear Regulatory Commission and Agreement States Transportation of Radioactive Materials NRC Course H-308 OBJECTIVES Define hazardous material,
More informationCadmium Reduction Method Method to 0.50 mg/l NO 3 N (LR) Powder Pillows
Nitrate DOC316.53.01067 Cadmium Reduction Method Method 8192 0.01 to 0.50 mg/l NO 3 N (LR) Powder Pillows Scope and application: For water, wastewater and seawater. Test preparation Instrument-specific
More informationSOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 NRC DOCKET NOS AND
SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR
More informationHach Method Spectrophotometric Measurement of Free Chlorine (Cl 2 ) in Finished Drinking Water
Hach Method 1041 Spectrophotometric Measurement of Free Chlorine (Cl ) in Finished Drinking Water Hach Company Method 1041 Revision 1. November 015 Spectrophotometric Measurement of Free Cl in Finished
More informationHAZARD COMMUNICATION PROGRAM
HAZARD COMMUNICATION PROGRAM A. General Information 1. The Texas Hazard Communication Act (THCA), codified as Chapter 502 of the Texas Health and Safety Code (HSC), requires all public employees in Texas
More informationChemical Hygiene Plan for Laboratories
SAFETY POLICIES AND PROCEDURES MANUAL LABORATORY SAFETY 4.12.1 OVERVIEW Washington State University has developed the chemical hygiene plan to aid units in promoting a high standard of health and safety.
More informationRADIOACTIVE MATERIAL LICENSE
RC Form 12-1 Page 1 of 7 Texas Department of State Health Services Pursuant to the Texas Radiation Control Act and Texas Department of State Health Services (Agency) regulations on radiation, and in reliance
More informationModule 20: Corrosion Control and Sequestering Answer Key (edited April 2017)
Module 20: Corrosion Control and Sequestering Answer Key (edited April 2017) Bureau of Safe Drinking Water, Department of Environmental Protection 1 UNIT 1 EXERCISE Exercise for Unit 1 Background and Properties
More informationO R D E R OF THE HEAD OF THE STATE NUCLEAR POWER SAFETY INSPECTORATE
O R D E R OF THE HEAD OF THE STATE NUCLEAR POWER SAFETY INSPECTORATE ON THE APPROVAL OF NUCLEAR SAFETY REQUIREMENTS BSR-1.9.1-2011 STANDARDS OF RELEASE OF RADIONUCLIDES FROM NUCLEAR INSTALLATIONS AND REQUIREMENTS
More informationSAFETY NOTE: Before beginning this procedure, read all of the Material Safety Data Sheets for the chemicals listed in Section 5 of this procedure.
USTUR 300: ANION EXCHANGE ISOLATION OF AMERICIUM FROM PREPARED TISSUE SOLUTIONS Purpose Anion exchange for 241 Am Method Number USTUR 300 Original Date 10/10/95 Author Radiochemistry Staff Revision Number
More information3. Chemical Hygiene Plan: Laboratory Standard Operating Procedures. A. Laboratory Specific Information and Signatures
3. Chemical Hygiene Plan: Laboratory Standard Operating Procedures A. Laboratory Specific Information and Signatures The Chemical Hygiene Plan: Laboratory Standard Operating Procedures (section 3 only),
More informationOxygen Demand, Chemical
Oxygen Demand, Chemical DOC316.53.01103 USEPA Reactor Digestion Method Method 10211 1 to 60 mg/l COD (ULR) TNTplus 820 Scope and application: For wastewater, process water, surface water, and cooling water.
More information7/8/2013. What is GHS?
What is GHS? 0 Globally Harmonized System of Classification and Labeling of Chemicals 0 A standardized approach to classifying and labeling chemicals based on hazards 0 A United Nations program meant to
More informationColorimetric Method Method to 0.70 mg/l Ag Powder Pillows
Silver DOC316.53.01134 Colorimetric Method Method 8120 0.02 to 0.70 mg/l Ag Powder Pillows Scope and application: For water and wastewater. Test preparation Instrument-specific information Table 1 shows
More informationCadmium Reduction Method Method to 10.0 mg/l NO 3 N (MR, spectrophotometers) 0.2 to 5.0 mg/l NO 3 N (MR, colorimeters)
Nitrate, MR DOC316.53.01069 Cadmium Reduction Method Method 8171 0.1 to 10.0 mg/l NO 3 N (MR, spectrophotometers) 0.2 to 5.0 mg/l NO 3 N (MR, colorimeters) Scope and application: For water, wastewater
More informationResponsibilities: Effective Date: November Revision Date: February 8, VP, Facilities and Construction Management. Issuing Authority:
Title: Chemical Hygiene Written Program Effective Date: November 2005 Revision Date: February 8, 2017 Issuing Authority: Responsible Officer: VP, Facilities and Construction Management Director Environmental
More informationJason T. Harris, Ph.D. Department of Nuclear Engineering and Health Physics
Jason T. Harris, Ph.D. Department of Nuclear Engineering and Health Physics Idaho State University North American Technical Center July 24, 2012 1 2 Commercial Nuclear Power Plants (NPPs) produce gaseous,
More informationChapter 1 Introduction: Matter and Measurement
Lecture Presentation Chapter 1 Introduction: and Based on Power Point Presentation by James F. Kirby Quinnipiac University Hamden, CT What is Chemistry? the study of the properties and behavior of matter.
More informationPOLYPHOSPHORIC ACID ASSAY
POLYPHOSPHORIC ACID ASSAY Introduction This Technical Information Report describes the sampling technique and method of analysis recommended to perform rapid and reliable polyphosphoric acid assays for
More informationTitle: Assessment of activity inventories in Swedish LWRs at time of decommissioning
Paper presented at the seminar Decommissioning of nuclear facilities, Studsvik, Nyköping, Sweden, 14-16 September 2010. Title: Assessment of activity inventories in Swedish LWRs at time of decommissioning
More informationPowerPoint Presentation by: Associated Technical Authors. Publisher The Goodheart-Willcox Company, Inc. Tinley Park, Illinois
Althouse Turnquist Bracciano PowerPoint Presentation by: Associated Technical Authors Publisher The Goodheart-Willcox Company, Inc. Tinley Park, Illinois Chapter 1 History and Fundamentals of Refrigeration
More informationAppendix A. Physics and Technology of Nuclear-Explosive Materials
Appendix A Physics and Technology of Nuclear-Explosive Materials NEM and Fissile Materials Nuclear weapons exploit the explosive release of nuclear energy from an exponentially growing chain reaction sustained
More informationHIGH EFFECIENCY PARTICULATE AIR (HEPA) FILTER GENERATION, CHARACTERIZATION, AND DISPOSAL EXPERIENCES AT THE OAK RIDGE NATIONAL LABORATORY
HIGH EFFECIENCY PARTICULATE AIR (HEPA) FILTER GENERATION, CHARACTERIZATION, AND DISPOSAL EXPERIENCES AT THE OAK RIDGE NATIONAL LABORATORY D. E. Coffey Oak Ridge National Laboratory, UT Battelle, LLC P.
More informationDR/4000 PROCEDURE NITRATE. Using Powder Pillows
DR/4000 PROCEDURE Method 8171 Powder Pillows or AccuVac Ampuls Cadmium Reduction Method MR (0 to 5.0 mg/l NO 3 N) Scope and Application: For water, wastewater and seawater. The estimated detection limit
More informationRADIOPHARMACY PURPOSE
RADIOPHARMACY PURPOSE This procedure provides general instructions for developing, maintaining, and documenting, radiation safety procedures for Intermountain Radiopharmacy, Radiology Department, University
More informationSECTION 3 PRODUCT COMPOSITION The test kit is composed of QuSTICK Strep A Reagent Stick, Reagent A, Reagent B, Positive Control, and Negative Control.
SECTION 1 PRODUCT AND COMPANY IDENTIFICATION Product Identification: Ref No. 6000, 6000-025, etc. Test kit contains QuSTICK Strep A Reagent Stick, Reagent A, Reagent B, Positive Control, and Negative Control.
More informationImplementation of the NPT Safeguards Agreement in the Republic of Korea
International Atomic Energy Agency Board of Governors GOV/2004/84 Date: 11 November 2004 Restricted Distribution Original: English For official use only Item 4(c) of the provisional agenda (GOV/2004/82)
More informationNOTE: This method does not include all of the. specifications (e.g., equipment and supplies) and procedures
1923 METHOD 111 ) DETERMINATION OF POLONIUM-210 EMISSIONS FROM STATIONARY SOURCES NOTE: This method does not include all of the specifications (e.g., equipment and supplies) and procedures (e.g., sampling
More informationNITROGEN AND ITS COMPOUNDS Q30 (i) Explain how the following would affect the yield of ammonia. An increase in (i). Pressure.
NAME SCHOOL INDEX NUMBER DATE NITROGEN AND ITS COMPOUNDS 1. 1990 Q30 (i) Explain how the following would affect the yield of ammonia. An increase in (i). Pressure. (2 marks) marks)... (ii) Temperature
More informationTHE CATHOLIC UNIVERSITY OF EASTERN AFRICA A. M. E. C. E. A
THE CATHOLIC UNIVERSITY OF EASTERN AFRICA A. M. E. C. E. A MAIN EXAMINATION P.O. Box 62157 00200 Nairobi - KENYA Telephone: 891601-6 Fax: 254-20-891084 E-mail:academics@cuea.edu JANUARY APRIL 2014 TRIMESTER
More informationChapter X: Radiation Safety Audit Program
Chapter X: Radiation Safety Audit Program Policy All laboratories using radioactive material shall be reviewed as required by the Illinois Emergency Management Agency (IEMA), Division of Nuclear Safety
More informationDepartment of Energy OffIce of Worker Protection Programs and Hazards Management Radiological Control Technical Position RCTP
OffIce of Worker Protection Programs and Hazards Management Issue: The occupational radiation protection regulations established by the (DOE) and Nuclear Regulatory Commission (NRC) are similar in many
More informationHach Company TNTplus 835/836 Nitrate Method Spectrophotometric Measurement of Nitrate in Water and Wastewater
Hach Company TNTplus 835/836 Nitrate Method 10206 Spectrophotometric Measurement of Nitrate in Water and Wastewater Hach Company TNTplus 835/836 Method 10206 Revision 2.2 January 15, 2013 Spectrophotometric
More informationCOLUMBIA UNIVERSITY PERMIT APPLICATION FOR NON-HUMAN USE OF RADIOACTIVE MATERIALS
COLUMBIA UNIVERSITY PERMIT APPLICATION FOR NON-HUMAN USE OF RADIOACTIVE MATERIALS This is an application for non-human (research) use of ionizing radiation and is required in order to receive a permit
More informationPhosphorus, Total. USEPA 1 PhosVer 3 with Acid Persulfate Digestion Method Method to 3.50 mg/l PO. Test preparation
Phosphorus, Total DOC316.53.01121 USEPA 1 PhosVer 3 with Acid Persulfate Digestion Method Method 8190 0.06 to 3.50 mg/l PO 3 4 (0.02 to 1.10 mg/l P) Test N Tube Vials Scope and application: For water,
More informationChapter 1 Introduction: Matter and Measurement Honors Chemistry Lecture Notes. 1.1 The Study of Chemistry: The study of and the it undergoes.
Chapter 1 Introduction: Matter and Measurement Honors Chemistry Lecture Notes 1.1 The Study of Chemistry: The study of and the it undergoes. Matter: Anything that has and takes up The Atomic and Molecular
More informationEXPERIENCE OF TEST OPERATION FOR REMOVAL OF FISSION PRODUCT NUCLIDES IN TRU-LIQUID WASTE AND CONCENTRATED NITRIC ACID USING INORGANIC ION EXCHANGERS
EXPERIENCE OF TEST OPERATION FOR REMOVAL OF FISSION PRODUCT NUCLIDES IN TRU-LIQUID WASTE AND CONCENTRATED NITRIC ACID USING INORGANIC ION EXCHANGERS ABSTRACT H. Tajiri, T. Mimori, K. Miyajima, T. Uchikoshi
More informationCh 1: Introduction: Matter and Measurement
AP Chemistry: Introduction: Matter and Measurement Lecture Outline 1.1 The Study of Chemistry Chemistry study of properties of materials and changes that they undergo. Can be applied to all aspects of
More informationChemistry and Measurement
Chemistry and Measurement What Is Chemistry? Chemistry is the study of the composition, structure, and properties of matter and energy and changes that matter undergoes. Matter is anything that occupies
More informationClassification of Mystery Substances
Classification of Mystery Substances This document supports the safety activity Mystery Substance Identification: The Identification of Unlabeled Chemicals Found on School Premises from Flinn Scientific.
More informationDimethylphenol Method Method to mg/l NO 3 N or 1.00 to mg/l NO
Nitrate DOC316.53.01070 Dimethylphenol Method Method 10206 0.23 to 13. NO 3 N or 1.00 to 60.00 mg/l NO 3 (LR) TNTplus 835 Scope and application: For wastewater, drinking water, surface water and process
More informationDraft PS 18 APPENDIX A Dynamic Spiking Procedure ( ) 1.1 This appendix to Performance Specification 18
Draft PS 18 APPENDIX A Dynamic Spiking Procedure (4-4-2013) A1. Scope and Application 1.1 This appendix to Performance Specification 18 describes the procedure and performance requirements for dynamic
More informationStandard Operating Procedure for the Analysis of Dissolved Inorganic Carbon CCAL 21A.1
Standard Operating Procedure for the Analysis of Dissolved Inorganic Carbon CCAL 21A.1 Cooperative Chemical Analytical Laboratory College of Forestry Oregon State University 321 Richardson Hall Corvallis,
More informationSeaborg s Plutonium?
Seaborg s Plutonium? Eric B. Norman, Keenan J. Thomas, Kristina E. Telhami* Department of Nuclear Engineering University of California Berkeley, CA 94720 Abstract Passive x-ray and gamma ray analysis was
More informationSOME ASPECTS OF COOLANT CHEMISTRY SAFETY REGULATIONS AT RUSSIA S NPP WITH FAST REACTORS
Federal Environmental, Industrial and Nuclear Supervision Service Scientific and Engineering Centre for Nuclear and Radiation Safety Scientific and Engineering Centre for Nuclear and Radiation Safety Member
More informationJúlio Takehiro Marumo. Nuclear and Energy Research Institute, IPEN CNEN/SP, Brazil
Júlio Takehiro Marumo Nuclear and Energy Research Institute, IPEN CNEN/SP, Brazil Introduction Brazil State of São Paulo City of São Paulo Reactor IEA-R1 Source: http://www.relevobr.cnpm.embrapa.br Source:
More informationPREP Course 13: Radiation Safety for Laboratory Research. William Robeson Radiology Service Line Physicist
PREP Course 13: Radiation Safety for Laboratory Research William Robeson Radiology Service Line Physicist CME Disclosure Statement The North Shore LIJ Health System adheres to the ACCME s new Standards
More informationSafety Issues Related to Liquid Metals
Safety Issues Related to Liquid Metals Kathryn A. McCarthy Fusion Safety Program APEX Meeting July 27-31, 1998 Albuquerque, NM Idaho National Engineering and Environmental Laboratory Lockheed Martin Idaho
More informationLOS ANGELES UNIFIED SCHOOL DISTRICT REFERENCE GUIDE
REFERENCE GUIDE TITLE: NUMBER: ISSUER: Chemical Safety Coordinators REF-1563.3 Yi Hwa Kim, Interim Director Enrique G. Boull t Chief Operating Officer ROUTING All Secondary Schools All Middle Schools All
More informationList of Legislative Regulations Dealing with Nuclear Energy and Ionizing Radiation and Related Documents
List of Legislative Regulations Dealing with Nuclear Energy and Ionizing Radiation and Related Documents as on 18 June 2001 I. Atomic Act and Related Implementing Regulations a) Atomic Act 1. Act No. 18/1997
More informationWM 07 Conference, February 25 March 01, 2007, Tucson, AZ
Design and Construction of a High Energy X-Ray R&D Facility, and the Development and Optimization of Real Time Radioisotopic Characterization of Remote Handled Waste at MeV Energies. S. Halliwell, V.J.Technologies
More informationAPPLICATION FOR AUTHORIZATION
INSTRUCTIONS: This form is intended to be a template for completion by the applicant, followed by subsequent review by the Radiation Safety Officer, and then the Radiation Safety Committee. Please fill
More informationASTER CONF-~W OSTI MAY DISTRIBUTION OF THIS
PLUTONIUM STABILIZATION AND STORAGE RESEARCH IN THE DNFSB 94-1 CORE TECHNOLOGY PROGRAM P. Gary Elle9, Larry R. Avensa and Gary D. Robersonb a) Advanced Technology Group Nuclear Materials Technology Division
More informationChromazurol S Method Method to 0.50 mg/l Al TNTplus 848
Aluminum DOC316.53.01004 Chromazurol S Method Method 10215 0.02 to 0.50 mg/l Al TNTplus 848 Scope and application: For drinking water, surface water, swimming pool water, wastewater and process analysis.
More informationCHEMICAL MANAGEMENT PLAN
POLICY EDB CHEMICAL MANAGEMENT PLAN Section I: Annual Review The Chemical Management Plan shall be reviewed at least annually by the Chemical Management Officer and the Chemical Management Committee. Section
More informationChlorine, Free and Total, High Range
Chlorine, Free and Total, High Range DOC316.53.01449 USEPA DPD Method 1 Method DPD 0.1 to 8.0 mg/l Cl 2 Powder Pillows Scope and application: For testing residual chlorine and chloramines in water, wastewater,
More informationChromotropic Acid Method Method to 30.0 mg/l NO 3 N (HR) Test N Tube Vials
Nitrate, HR DOC316.53.01068 Chromotropic Acid Method Method 10020 0.2 to 30.0 mg/l NO 3 N (HR) Test N Tube Vials Scope and application: For water and wastewater. Test preparation Instrument-specific information
More informationWM2016 Conference, March 6 10, 2016, Phoenix, Arizona, USA. Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604
Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604 Ioana Witkowski, Anthony Nettleton, Alex Feldman Los Alamos National Laboratory INTRODUCTION TO OSRP ACTIVITIES
More informationELECTRODEPOSITION OF ACTINIDES
Analytical Procedure ELECTRODEPOSITION OF ACTINIDES (SOURCE PREPARATION) 1. SCOPE 1.1. This is a procedure for preparing sources for the measurement of actinides by alpha spectrometry using electrodeposition
More informationAP1000 European 11. Radioactive Waste Management Design Control Document
CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated
More informationION EXCHANGE SEPARATION OF PLUTONIUM AND GALLIUM (1) Resource and Inventory Requirements, (2) Waste, Emissions, and Effluent, and (3) Facility Size
LA-UR-97-3902 -f$t I Revision 1 Los Alarnos National Laboratory is operated by the University of California for the United States Department of Energy under contract W-7405-ENG-36. TITLE: AUMOR(S): SUBMlrrED
More informationOxygen Demand, Chemical
Oxygen Demand, Chemical DOC316.53.01104 USEPA Reactor Digestion Method Method 10212 250 to 15,000 mg/l COD (UHR) TNTplus 823 Scope and application: For wastewater and process waters; digestion is required.
More informationVALIDATION STUDY OF FTIR-BASED EMISSIONS MEASUREMENTS AT A MUNICIPAL WASTE COMBUSTOR
AP-157 VALIDATION STUDY OF FTIR-BASED EMISSIONS MEASUREMENTS AT A MUNICIPAL WASTE COMBUSTOR Grant M. Plummer, Ph.D. Peter Zemek, Ph.D. Special Projects Manager Applications Manager Enthalpy Analytical,
More informationSEQUENTIAL DETERMINATION OF AMERICIUM, PLUTONIUM AND URANIUM IN LIQUID EFFLUENTS FROM NUCLEAR POWER PLANTS
U.P.B. Sci. Bull., Series C, Vol. 75, Iss. 3, 2013 ISSN 2286-3540 SEQUENTIAL DETERMINATION OF AMERICIUM, PLUTONIUM AND URANIUM IN LIQUID EFFLUENTS FROM NUCLEAR POWER PLANTS Ruxandra TOMA 1, Cristian DULAMA
More informationNew Report on Hanford Contamination Finds Potential for Off-Site Radiation Doses
PRESS RELEASE Immediate Release Contact: Tom Carpenter, 206-419-5829 September 4, 2018 Marco Kaltofen, 508-314-9334 New Report on Hanford Contamination Finds Potential for Off-Site Radiation Doses Seattle,
More informationPA DEP SOUTHWEST REGIONAL OFFICE
PA DEP SOUTHWEST REGIONAL OFFICE MEMO TO FROM Air Quality Permit File: OP-04-00043 / Thomas J. Joseph, P.E. Facilities Engineering Manager Air Quality Program THROUGH Mark R. Gorog, P.E. Environmental
More information