ML021780594
| ML021780594 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 05/08/2002 |
| From: | Simpson J Westinghouse |
| To: | Lowenstein R US Atomic Energy Commission (AEC) |
| References | |
| FOIA/PA-2002-0248 | |
| Download: ML021780594 (17) | |
Text
DMlE Of: DOCUMENT-IDATE NO..7 FROM- E RECEIVE 5-11-62 W"nu PittbwA , N Lii. CITHERt tTR. MAW (J30 P6- Wlpa so WTR-lT 1
ORG.. Ccl mn TO. --
lAM (iavnswn ln) 3 12 ACTION NECESSARY Q CONCURRENCE Q DATE ANSWEREIN NO ACTION NECESSARY E3 COMMENT_ 0 BY._
CLASSI.. POST OFF ICE FILECODl.
I m*. Not 50-V2__________
TO DATE RECEIVED BY DATE REFERE DESCRiPTION. (Must Be Undaulfied)
Ltr. tratia. the f*onevfg d req.
Lmins~ with$ -l aaendwt to TR-2 to permit posession 04Y atd statiug that all pr 'u E - n apple. for meniaeat to TR,-2 awe w/tdI' ENCLOSURES,
- U-zta Repor" Wh¶RA 17O-Sh~iutdowRepr for j4*gtiflghDm Testing Roacterw, dt.d. 5-3-62--at covers kAu I ______________ I t F dowsribias the AmcsM7aryti@35 being taken to bring facility to retirmalet stage. 5tarizee 5-P-62)
(3,5 eys each of ltr & report ree'd-- i I -- F-REMARK$s manl Roim -Ists OW-0c 1 orAl'U011 (tbrz K. #6010e)
- U.. &ATOMIC 84ERG COMMISSION NW4AL CONTROL FORMFR AEC-32S
- U. S. GOVERNMENT PRINIMNG OF~FIlr 1963 - 613988
WES T I N GH OU S.,9 ý_
Testing Reactor P. 0. Box 1075 Pittsburgh 30, Pa.
May 8, 1962 Mr. Robert Lowenstein Division of Licensing and Regulation U. S. Atomic Energy Commission Washington 25, D. C.
Application for Amendment of License TR-2 (Docket 50-22)
Dear Mr. Lowenstein:
The Westinghouse Electric Corporation has shut down and permanently retired the Westinghouse Testing Reactor. This action is being implemented as a two-phase operation described below:
Phase I During a period extending until approximately the end of 1962, the necessary actions are being and will be taken to bring the facility to the condition described in the attached Shutdown Report, WfR-170.
Phase II This phase will begin approximately at the end of 1962 and extend indefinitely. By the end of 1962, any necessary amendments to the Shutdown Report will be submitted with a request for further license modifications, if necessary, to permit what remains of the facility to be held in the condition described.
At this time, amendment of the TR-2 license is requested to permit possession but not operation of the facility, as described in Phase I above, The WTR Safeguards committee has reviewed and approved WTR-170. Please note that this discussion and request refers to the TR-2 license only. Other source, By-Product and Special Nuclear Materials licenses associated with the facility will be handled on an individual basis, and terminated as the need for them disappears. A license to operate the Hot Laboratory as a separate facility is being requested by separate correspondence. In the interim only work on materials irradiated in WTR will be continued in the Hot Laboratory under the TR-2 license.
""u I r5.
Mr. Robert Lowenstein may 8, 1962 Also attached is an Appendix A (one page) showing estimated schedule of transfers of Special Nuclear Material and indicating the diminution of our allocation needs. Allocations for non-delivered Special Nuclear Materials will be terminated forthwith. All previous applications for amendment of TR-2 are hereby withdrawn. All further communications regarding TR-2 should be directed to J. M. Yadon, Manager, Nuclear Power Service, P. 0. Box 355, Pittsburgh 30, Pennsylvania.
Yours very truly, iWe.impsi iePresident Subscribed and sworn before me this 9th day May, 1962.
/
Notary Public GENEVIEVE LEDDON, NOTARY PUBUC FOREST HILLS BOROUGH. ALLEGuEY COUNTY MYCOMMISSION EXP'IRES JULY 22, 1964
- a.
O.
Appendix A to Westinghouse Electric Corporation License No. TR-2 Estimated Schedule of Transfers of Special Nuclear Material from the Commission to Westinghouse and to the Commission from Westinghouse:
Returns by Westinghouse Date of Transfers from AEC Electric Corp. to AEC to Westinghouse Kjs. U-235 Net Yearly Cumulative Transfer Dist. Dist.
(Fiscal Electric Corp. Recoverable Spent Scrap Fuel Kgs. U-235 Kas. U-235 Year) Kgs. U-235 1958 1959 1960 45o65 .... 45.65 45o65 194, 40.28 --. 40.28 85.93 37.10 14.56 -- 22.54 108.47 1962 1963 -- 9.58 71.47 (81.05)* 27.42*x 19 64 6
19 5 1966 19bb 1967 1967
- Inventory to be returned.
- Conversion, fabrication and burnup losses.
May 8, 1962
e96T OLT-Elm
,do--j7ýaftu asploll'A .UMA idocisu taocilflHs tý6/, OL
iNTRODUCTION and it is The Westinghouse Testing Reactor has been shut down proposed to possess but not operate this facility. The retirement in two phases; of the Westinghouse Testing Reactor will take place 1962 the first phase covering a period from Shutdown to the end of An and the second phase will be the final shutdown condition.
anticipated schedule is shown in Figure 1. This report describes placed during this the conditions into which the facility is being or first phase. In addition, any hazards to Westinghouse employes analysed.
the general public which may remain at the site are Plant, reference is For more detailed information concerning the WTR made to the WTR Final Safety Report WCAP-369 (Rev.).
TABLE OF CONTENTS I. Description of Retired Condition of Facility A. SNM and By-Product materials under License TR-2.
- 1. WTR Fuel Elements
- a. irradiated Fuel Elements
- b. Non-irradiated Fuel Elements
- 2. Experiments
- a. Irradiated Non-fueled
- b. Irradiated Fueled
- c. Non-irradiated
- 3. Cobalt 60 and Radioactive Isotopes B. Reactor Vessel and associated areas and systems.
- 1. Reactor Vessel
- 2. Subpile Room
- 3. Primary Coolant Piping and Tanks C. Miscellaneous Areas, Systems and Components
- 1. Canal
- 2. Hot Cells
- 3. Evaporator and Contaminated Water Inventory II. Hazards A. Contamination and Direct Radiation B. Fire C. Natural Forces D. Unlawful Entry III. Administration A. License Administration B. Security C. Inspection Table I -- Radiation Levels and Contamination Figure 1 -Anticipated Schedule Figure 2 - Estimated Fuel Element Activity Remaining At WTR
x' t
Ii.*Desclript -ion of Retired Condition of the Facility A. SNM And By-Product materials -he'ld ~under 14ien se MIR-12
- 1. WTR Fuel Elements
- a. Irradiated Fuel Elements All of these elements will be transferred to the WMR Decontamination Building Water Pit for temporary storage from which they will be returned to the AEO for reprocessing. (WTR-153; SNM-576) See Figure 2 for estimate of decrease in fuel element activity as a result of decay and shipment.
- b. Non-irradiated fuel Elements Arrangement will be made for cold processing these fuel elements.
- 2. Lxperiments
- a. Irradiated Non-fueled These will be returned in suitable casks to the original experimenter, or in some cases, disposal will be made through WTR Waste Disposal.
b Irradiated Fueled These will be returned in suitable shielded casks to the original experimenter.
- c. Non-irradiated These will be returned to the original experimenter in suitable shipping containers.
- 3. Cobalt 60 and Radioactive Isotopes Arrangements have been made to transfer the Cobalt 60 to various customers. All low activity cobalt and radioactive isotopes not so disposed of will be handled by normal waste disposal procedures.
1
B. Reactor viebsel-;and associated areas",nd systems
~~~~1
"'2 Reactor Vessel bsbe~ ~ed nteie~ b~e The head assemblyhabend sela4otd down as per approved WT" procedures, making the interior of the vessel inaccessible except to a skilled crew of riggers.
Any openings in the vessel will be secured. Certain miscellaneous hardware in the vessel, such as core support structure, will be allowed to remain. When the head has been replaced the vessel will be drained, and comprehensive radiation surveys made to ensure compliance with 10 CFR Part 20 Sections 20.105, 20.201, 20.202, 20.203, 20,401, and other sections and appendices as applicable.
- 2. Subpile room The subpile room will remain a ,,Contamination Zone" but steps will be taken to reduce direct radiation levels to the point where it can be classified as a "Radiation Area" rather than a "High Radiation Area". In addition the subpile room doors will be locked and access restricted to properly trained and equipped personnel.
- 3. Primary Coolant Piping and Tanks This system will be completely drained and all openings secured to prevent escape of any airborne activity which may develop as residual drops of PC water evaporate. The system will be allowed to "breathe" through an existing absolute filter.
- 4. Contanminated Pipe Tunnels These will remain in their present condition but access to them slabs.
will be prevented by locked gates, doors, and concrete C. Miscellaneous-areas, systems and componentb
- 1. Canal The first steps being taken with respect to the canal is the removal and disposal of irradiated material. Subsequent possibilities are now being evaluated but it may be several months before a decision is reached. The final state will be such to insure compliance with 10 CFR Part 20 Sections 20.105, appendices 20.201, 20.202, 20.203, 20.401 and other sections and as applicable.
2
£ ~V
-..-- 2. Hot ,ls Operation of the Hot Cells is to be continued for an indef ini~te period. it is intended, khat the Ilot Call area of' the plant and- required-utilities -will b-o-psie'a**y isolated from the Reactor complex.
3.. Evaporator plant and contaminated water inventory.
The operation of the evaporator plant will be continued until the contaminated water inventory ha.. teen prcce.*sed..
At this point, the evaporator plant itself will be retired of in the same manner as the reactor systems, by seeuring all contaminated tanks and piping. Access to the liquid waste disposal area is prevented by a fence.
- 4. Activated and contaminated hardware and tools.
of as solid ..*a3te
- n general, this equipment will be disposedi in the areas.*
although certain selected items may be stored to vwhich access is prevented.
- . ~Hazards hazard.s. associatea ;.ith With the reactor in a shutdown condition, the and contaminated surfaces the facility are primarily direct radiation with the associated contamination. The hazards associated with Bailding Water Pit temporary storage of fuel in the Decontamination 1961 and it isý. not have been analysed in WTR-153 dated October, In so far a.:
considered necessary to repeat in this report.
contamination is concerned the basic principle of "confine and Areas" will contain" will be used and the principle of "Restricted The following be applied to contaminated or to radiation areas.
the hazards analysis indicates the feasibility of controlling associated with the retired facility.
3
-A. . ontaminated Areas and Direct Radiation
- n the pre viu section. the retired c4Aitin C'f ,-petfic arei3 of interest vas described, it in a reao-nable exqectattonr + hat as- t imges o.te radiat ionand pni otevley _zqf tifesýe areas sill decrease. However, all Radiation Areas (as defined by i0 OFR Part 20, Section 20.202)will be included in those to which access is completely restricted. Contaminated area.:-: wil. be handled as follows:
- 1. Access to those areas where there are surfaces where the degree a.s of contamination iY such that they would be designated
".,ontamination Areas" by present safety procedures ana the if not nature of the surfaces make decontamination difficult impossible will be completely restricted. An example of such an areas is the primary coolant pipe tunnel. The secureG entrances to such areas will be clearly posted with ;ign. to indicate the hazards inside.
- 2. Surfaces in areas where it is impractical to restrict acce7..
"ill be cecontaminated.
Vii it is possible that within specif~c areas contaminated level, change. :n any event, action will be taken to ensure that the compliance development of airborne activity will be controlled in with 10 CFR ?Art 20, Section 20.202. Surveys will be made during the remainder of 1942 on a periodic baifs, the frequency of such n no nle.
inspection being determined by the statun of an arear.
-wil the period be treater than one month. nformat ion on w:inif >at.
change.- 1-;ill be supplied monthly to the ARE During May 19-2. a
.urvey of area. as .-hown in Table Y is being made and the revvY ilI be supplied to the AFW to serve as a referenze for the s-hut dowrn conditions. From this data and the results of the perzcu:'
f-,re 3urveyE made during 19<2 it will be pc:-.tible to deterrrzne survey requirement) .- ich -"ill be specifie :n an amenurent lo this repcrt to be submittec at the en. Wf 192.
4
B. Fire The plant itself being of steel and concrete construction is highly resistant to fire, but to further reduce this hazard, the following s3tep~s ~will be taken:.
- 1. As far as practicable, all combustible materials will be removed.
- 2. Fire extinguishers will be located at strategic points so that security personnel can extinguish small fires.
- 3. Unnecessary electrical circuits will be de-energized.
personnel
- 4. Officials of local fire companies along with security will be briefed on the condition of the plant.
Natural Forceo exposed The natural forces to which the facility structure: are are described in WrAP-369 (Rev), Section -- The analyrsis contained therein is still applicable. -n addition., the plant. i-tructures are otand for conservatively designed and relatively new. and they can many year' without attention. however, it is expected t.hat any personnel deterioration will be detected and reported by -ecurity appropriate or thoje making periodic inspection of the plant and action will1 be taken.
D. Unlawful Entry to the person or Thil io considered from the point of vLew of hazard persons who might enter the plant. All plant buildings -will be locked.
type chain link fence..
The entire area is surrounded by an AEC security and the plant is under guard. To obtain access to any radiation or contamination area another strong barrier must be breached.
-- Administration A. Licen3e Admini t rat ion To preserve continuity in regulations concerning licensing of the WTPR 3pec ifc responSibility will be maintained within the shutdown, Westinghouse organization.
5
" '. t.eet*rlty T're:4'ent i].an are tc mrnaintain
- 2. hour uarc on ;he W.ltz f+ i i, premise'n. Guardsv ill make pe~riodic tour-; of plant buiiJ+/-~'.
Security personnel will not have rout'ie a-cce:a'z to areas. wich have been isolated az contamination and radiation areas.
. :nspect ion t is planned that a definite inspection schedule will be established for the WrR facility by personnel experienced in the detection of hazards. both nuclear and non-nuclear. The periodicity of these in.ipections will. be determ.ned by experence gained in shutting down the plant. The final revisions, of thi3; report will specify the timing of the.,e inspections9 and include a checklist of items to be covered in the inspection. The results of the periodic inspections previously described will be reported to the AEC.
6
TABLE i Radi ationi and Contamination' Areas UOnta2Iu1r1dLJoI1 (Yn T-.f-%t, n Radiation
+ i r)-i Levels * ,- Contamination Leve s u
rnr/hr~ -2rI'C 13- ,an Inn - Lie,1 j cliQi JI.JJJ. q M.'.' '-'- 4 Reactor Complex Fenced Areas external to buildings
- 1. Waste storage Area NA NA North of Cooling Tower NA
- 2. Pad at rear of Process Building
- 3. Other external areas Retention Basin Area
- 1. Waste storage pad NA
- 2. Pool Areas a , b,; c', d.
3 Retention Basin
- 4. Fvaporator Area NA 5 Tank Area Process Building NA NA
- 1. Standby Pump Room General Bkgd NA NA NA
- 2. Standby Pump Contact NA NA
- 3. Pump Room No. 1 NA 47 Pump Room No. 1, Contact with pum NA NA
- 5. Pump Room No. 2, General bkgd
- 6. Pump Room No. 2, Contact with pumI NA NA
- 7. Pump Room No. 3, general bkgd 1 3, Contact with pump NA
- 8. Pump Room No. NA NA
- 9. Head Tank Powncomer, contact NA NA NA
- 10. Heat Exchanger Room at entrance NA NA ii. Heat Exchanger Room, general Bkgd NA NA
- 12. Heat Exchanger Room, under exchangers NA NA NA NA
- 13. Surge Tank Room, General Bkgd Top Landing
- 14. Surge Tank Room, around tank
- 15. ."on Exchanger Cubicle, entrance
- 16. -on Exchanger Cubicle 17 on Exchanger, contact 18 Waste Disposal Basement, ",eneral Bkgd NA 19 Waste Disposal Basement, tan" 325-1 Cnntact with bottom i LEGEND: NA -- Not Applicable I
.. ... ; ..... ' -r
- '=: . . . -- Page 2 TABLEo Radiat ion and.0ontaminationrrAreas Th..L--.
A I niH jnotio 2 Qeonc cc S "
0204b mr/I .r c/rn/i 00crm c/cc P.c/g
_____________ I I Tank 325-2
- 20. Waste Disposal Basement, NA Contact with bottom Tank 322-1 NA
- 21. Waste Disposal Basement, Contact with bottom Tank 322-2
- 22. Waste Disposal Basement, NA Contact with bottom
- 23. Pit PC Tunnel at 16i level (4' water at 0' level)
NA
- 24. Waste Disposal Room NA NA
- 25. Fan Room Filter Boxes
- 26. Fan Room Head Tank Monitor Cubicle B. Reactor Building NA NA
- 1. 16' Elevation Reactor Building NA NA
- 2. Subpile Room Background NA NA
- 3. APP Loop Cubicle over open top NA NA
- 4. APD Loop Cubicle NA NA
- 5. Loop No. 1 North Side Contact NA NA
- 6. Loop No. I South Side Contact NA NA
- 7. Reactor Top, .n Trench Reactor Top, over open vessel NA NA 8.
(Vessel with water) w only NA Reactor Top, over open vessel NA NA
- 9. NA (Vessel with water) 0-7 NA NA
- 10. Pressure Vessel, inside wall NA NA
- 11. Reactor Top, General Background
- 12. Canal Wall Top
- 13. Rabbit Pump Room NA NA 4ý. Canal Water C. Reactor Building Annes
- 1. 16' elevation in annex
- 2. Canal Wall Top NA NA 3I Canal water D. Decontamination Building 1- General Area
- 2. Pit Wall Top Survey values for References will b- supplied with
- Peak Values for Arcas Tabulated. the May Report.
JI 4 94 JiEDVE SGPAED I
!Aar3h AprilI MaY une 111JV '-epterbe October Novemnber rec'nimber
'4 F~EA,"'-7 irlperen' ",-..tdo,.-n -A
-ýrepare D p )oval ry-ýAmendrer."ýs "r.
- '-..;.do~wn of T'ýhil A.o~vn 'ýhl-tdoim. Eeport' Report, Report
&ýaf egt.Aards ReviewT Present I
4..
Shutdown Report. to AE C Fuel Shipment FI17~1'
.44 p
Ci96-L ýý96T' U-6 f' oac AON q-100 PnV RAnf ý)ufl2 ll.cidV 14CJ-Vw oozý A 009 008 OOOT I -7 1-77 77 I... a . -- - . _ -.
009t 7.
I1-7
- 0008 L.>tv
~-- - .7 J- . --
e ~~~~~.7, - -- ...
-F76
" 17:
37 T
F 17 4 1ý7- 7 1 4 L
.... 41tiU'OLUU VOGT VILFI +
... 2Lz~~~~ ~.-~- ----------
F .4.~ ~t l."..-~..... i::t:. ~ -t~tffI-+/-~-Vi't~i~ 71 SI . A,
~~~-V~.. w r . ... 7~-414