ML19319B535
| ML19319B535 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/22/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001230664 | |
| Download: ML19319B535 (3) | |
Text
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. REGULATORY INFORMATION DISTRIBUTION' SYSTEM RIDS)
DISTRIBUTION FOR INCOMING MATERIAL -
50-546 REC: STOLZ J F ORG: ROE L E NRC DOCDATE: 06/29/79 TOLEDO EDISON DATE RCVD: 06/29/79 DOCTYPE: LETTER NOTARIZED: NO SUDJECT:
COPIES RECEIVED FURNISHING INFO TO QUESTIONS 1 & 4 OF NRC REQUEST FOR ADDL INFO C LTR 1 ENCL O CONTAMINATION OF EXIGTING SPENT FUEL RACKS, IN SUPPORT OF APPLICAt1T"S SFENT FUEL STORAGE APPL.
PLANT NAME: DAVIS EESSE - UNIT 1 4
REVIEWER INITIAL:
XJM DISTRIEUTOR INITIAL:
- "**** DISTRIEUTION OF THIS MATERIAL IS AS FOLLOWS
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NOTES:
1.
SEND ALL AMENDMENTS TO J.
ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTICN CODE COO 1)
FOR ACTION:
ASST DIR YAS? ALLO **LTR ONLY(1)
BR CHIEF LWR #1 FC++LTR ONLY(l' F
I WR ENOLE+-+LTR ONLY ( 1 )
LIC AGST LWR #1 LA4*LTR ONL'/ (1 )
INTERNAL:
REG F TR ONLY(1)
NRC PI'R4*LTR ONLY ( 1 )
LTR ONLY(2)
OELDe LTR ONLY(1)
OPERATOR LIC ER**LTR ONLY(1)
QAB**LTR ONLY(1)
EMERGENCY PLAN ER*4LTR ONLY(1)
MIPC+4LTR ONLY(1)
DIRECTOR NRR**LTR ONLY(1)
MECH ENG CR**LTR ONLY(1)
AD FOR ENO44LTR ONLY(1)
STRUCTURAL ENG ER*4LTR ONLY(1)
MATERIAL ENG ER4*LTR ONLY(2)
AD FOR REAC SFTY44LTR ONLY(1)
REACTOR SYSTEMS ER**LTR ONLY(1) ANALYSIS ER**LTR ONLY(1)
CORE PERFORMANCE ER+*LTR ONL'r (1 AD FOR PLANT SYSTEMS AUXILIARY SYS ER**LTR ONLY(1)
CCNTAINMENT SYSTEM $oLTR ONLY(1 I
- C SYSTEMS ER44LTR ONLY(1)
POWER SYS ER4*LTR ONLY(1)
AD FOR SITE TECH +*LTR ONLY(4)
AD FOR SITE ANLYS++LTR ONLVf1)
ACCIDENT ANALYSIS 4+L TR ONLY( 1 )
EFFLUENT TREAT SYS++LTR ONLYti RAD ASSESSMENT BR MLTR ONLY(1)
KIRKWOOD wLTR ONLY(1)
CEOSCIENCES ER**LTR ONLY(1)
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CLINTON, OH**LTR CNLYs1)
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SIZE: 1P CONTROL NER:
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%mm EDISON June 22, 1978 LOWELL E. ROE
+c. Pres 4ent s.ea...:. e n-.m 14191 259-S242 Docket No. 50-346 License No. NPF-3 Serial No. 451 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Light Water Reactors Branch #1 Division of Project Managescnt United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
In our submittal Serial No. 425 dated April 4, 1973, we responded to your Request for Additional Information (RAI) pertaining to the proposed Davis-Besse Nuclear Power Station Unit 1 spent fuel storage capacity modification. Questions 1 and 4 of the RiI dealt with contamination of the existing spent fuel racks to which Toledo Edison had responded that the existing fuel racks had not been contaminated. Subsequent to our responses, Davis-Besse Unit 1 became involved with the burnable poison rod assembly (BPRA)/ orifice rod assembly (ORA) problem addressed in our letters, Serial No. 435 dated May 18, 1978 and Serial No. 439 dated
>by 26, 1978. Activities associated with this problem were envisioned to cause a then undefined contamination of the existing spent fuel racks. We were thus informed that your staff would stop further review on the spent fuel storage application until the rasponses to RAI Ques-tions 1 and 4 were revised.
In an effort to have the review of the spent fuel storage application proceed without undue delay, we wish to provide the following information.
The BPRA/ ORA events included the activity of passing the removed BPRA's and ORA's through the spent fuel pool and into the adjacent cask pit where they will be stored under an adequate shield of water until their ultimate disposal. This transfer operat!on has been completed. During the transfer, the brief period of mixing of contaminated, borated refuel-ing water present in the transfer pit, with the demineralized water contained (for shielding purposes only) in the spent fuel pool, and any deposits " washed" off the assemblies in the transfer process, have O
caused only a very small amount of contamination of the spent fuel pool pe A ?/,
water. Activity levels in the spent fuel pool water are currently on y
the order of 1.5 X 10, uC1/cc with the primary constituent being
.kt" F5 Cobalt-58. The existing racks were not subjected to any irradiation by 1*J"4'
\\
kE spent fuel assemblies.
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THE TCLEDO EDISCN COMPANY ECISCN PLAZA 3CO MACISCN AVENUE TCLECO. CHO 43E52 a
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.. Draining of the spent fuel pool will be done at a convenient time follow-ing the May-June outage when proper processing of the slightly borated water can be performed. With proper wash down during the draining of the spent fuel pool, contamination of the existing racks and pool walls will be minimal. Subsequent to draining of the spent fuel pool, the existing racks and area will be properly surveyed for contamination and further decontaminated as necessary, consistent with health physics requirements, to allow as much as practicable uncontrolled handling and disposal of the existing racks. There is the possibility that small areas of the racks will not be able to be reasonably deccataminated below controlled levels. In such cases it may become desirable to remove sections of the racks for disposal as low level waste.
This is not envisioned to be a significant amount of material.
We trust that the above information will suffice to al.3w continuance of your review and timely approval of our application for che spent fuel storage capacity modification.
Yours very truly, Q
bj d/5-6