1 3 4 5 6 7 8 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 41 4 43 44 45 46 47 48 4 50 CONTENTS TERMS................. v METRIC CONVERSION CHART........... vi 1.0 INTRODUCTION............... 1.0 FACILITY LOCATION............... 1 3.0 RESPONSIBLE MANAGER (Requirement )........ 4 4.0 TYPE OF PROPOSED ACTION (Requirement 3).... 4 5.0 STATE ENVIRONMENTAL POLICY ACT (Requirement 4).. 4 6.0 PROCESS DESCRIPTION (Requirements 5 end 7)....... 4 7.0 ANNUAL POSSESSION QUANTITY AND PHYSICAL FORM (Requirents 8,,, end 1)............. 8 8.0 CONTROL SYSTEM (Requirement 6).......... 8.0 MONITORING SYSTEM (Requirement )......0 RELEASE RATES (Requirement ).......0 OFFSITE IMPACT (Requirements and )..... 1.0 FACILITY LIFETIME (Requirement ).. 1.O TECHNOLOGY STANDARDS (Requirement )................0 DISCUSSION OF BEST AVAILABLE RADIONUCLIDE CONTROL TECHNOLOGY....0 REFERENCES.......................... 1.. 3. 4. FIGURES Hanford Site............................ Plutonium Finishing Plant Complex.................. 3 Process Flow Diagram of the Vertical Calciner............ 5 Appl icable Control Technology Components.............. 607.0853 iii
1 TABLES 3 4 1. Isotopic Distribution for Weapons Grade Production Plutonium.... 8 5. Potential Annual Unabated Emissions................. 6 3. Potential Annual Abated Emissions.............,.... 7 4. Radionuclide Air Emissions Data for the 1--1 Stack (PFP).. 8 5. Potential Annual Unabated Offsite Dose............... 1 6. Potential Annual Abated Offsite Dose................ 1 607. iv
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 7 607. 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
1 3 4 5 6 7 8 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 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 0.76456 cubic meters cubic meters 1.308 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. 607. Vi
1 3 4 5 6 7 8 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 41 4 43 44 45 46 47 48 4 50 51 5 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) 46-47-060. 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.
Figure 1. Hanford Site. T6070 607.
DOE/RL-6-6, Rev, 0 Figure. Plutonium Finishing Plant Complex. 6O7.77 7
DOE/RL-6-6, The geodetic coordinates for the main stack, 1--1 are as follows: 1 3 4 5 6 7 8 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 41 4 43 44 45 46 47 48 4 50 51 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) 376-7471. 4.0 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 1--1. 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 1 6 0 ' 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. 607. 4
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
1 3 4 5 6 7 a 1 1 0 1 3 4 5 6 7 za 30 3 33 34 35 36 37 38 3 40 41 4 43 44 45 46 47 48 4 50 51 5 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
DOE/RL-6-6, 1 3 4 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 41 4 43 44 45 46 47 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.
DOE/RL-6-6, 1 3 4 5 6 7 8 1 7.0 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-38 0.01 1 Pu-3 3.75 Pu-40 5.5 Pu-41 0.7 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 41 4 43 44 I Am-41 0.0 8.0 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). 607. 8
r- Figure 4 Applicable Control Technology Components 607.
.0 MONITORING SYSTEM (Requirement ) 1 1 0 1 3 4 5 6 1 8 30 3 33 34 35 36 38 3 40 41 4 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 Et01 1.71 Et01 1 E-03 5.73 E-01 3. Et05 6.0 E-0 1 E-03 1.5 Et01 1. Et04.30 E-01 1 E-03 4.58 EtOO.05 Et0 1. Et0 1 E-03.5 Et01 6.70 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.
1 3 4 5 6 7 8 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 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-04 1.5 Et01.0 Et03.74 E-03 4.58 Et01.0 Et03. E-0.5 Et01.0 Et03 4.7 E-0. Et00.0 Et03 1.07 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-05 3.0 E-04.0 E-03 5.5 E-05 1.6 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 0.0348 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.
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. 3 4 6 7 8 1 Table 6. Potential Annual Abated Offsite Dose. Radioisotope 1 0 1 3 4 5 Pu-38 Pu-3 Pu-40 Pu-41 Am-41 Total dose 6 7 8 30 3 33 34 Abated emissions (curie per year).86 E-04.74 E-03. E-03 4.7 E-0 1.07 E-03 WA Unit dose factor (millirem per curie)..4.41 0.0486.4 N/A 1.0 FACILITY LIFETIME Abated dose (millirem per year) 6.1 E-04.36 E-0 5.5 E-03.4 E-03.67 E-03 3.48 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. 35 36 607. 1
.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. 1 1 0 1 3 4 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.
DOE/RL-6-6,.0 6 7 8 1 1 0 1 3 4 5 6 7 8 30 3 33 34 35 36 37 38 3 40 Rev. 0 REFERENCES DOE,, Criteria for Safe Storage o f Plutonium Metal and O x i d e s, DOE-STD-30-4.0. 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 873--1, 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.
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 8504-005 ' 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 80540 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 ( ) 607.41 Distr-1 MSIN A5-5 A4-5 R3-7 R3-7 A5- R3-7 E6-44 H-53
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