GO2-86-859, Advises That GE Performed Independent Verification of Util Analysis Results of App R Calculation for Alternate Shutdown from Remote Control Room Utilizing Six Main Steam Safety Relief Valves.Rev 0 to Calculation NE-02-86-10 Encl
| ML17278B001 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/09/1986 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17278B002 | List: |
| References | |
| GO2-86-859, NUDOCS 8609150208 | |
| Download: ML17278B001 (6) | |
Text
REQULA RY INFORMATION DISTRIBUTION'-SYSTEl'l
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ACCESS IQN NBR: 8609150208 DOC. DATE: 86/09/09 NOTARIZED:
NO DOCKET I FACIL:50-397 WPPSS Nuclear Prospect, Unit 2i Washington Public Powe 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSENi Q. C.
Washington Public Power Supply System RECIP. NANE RECIPIENT AFFILIATION ADENSAN> E. Q.
BWR Prospect Directorate 3
SUBJECT:
Responds to 860630 request for addi info re fire protection programs App Ri calculation for alternate shutdown from remote control room utilizing six main steam safety relief valves.
DIETR IBUTION CODE:
A0060 COPIEE RECEIVED: LTR g ENCL g, SIZE:
TITLE: QR/Licensing Submittal: Fire Protection NOTES:
REC IPIENT ID CODE/NAI'lE BWR PD3 LA BRADFUTE. J INTERNAL: AGRS 11 RLD/HDS2 S
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Washington Public Pd'war.Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 860915p208 86p9p
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- Docg PgPPP~97, F'DR
~I September 9,
1986 G02-86-859 Docket No.
50-397 Director of Nuclear Reactor Regulation Attn:
E.
G.
- Adensam, Project Director BWR Project Directorate No.
3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 H
Dear Hs.
Adensam:
Subject:
NUCLEAR PLANT NO.
2 OPERATING LICENSE NPF-21, WNP-2 FIRE PROTECTION
- PROGRAM, APPENDIX R CALCULATION FOR ALTERNATE SHUTDOWN FROM REMOTE CONTROL ROOM UTILIZING SIX HAIN STEAM SAFETY RELIEF VALVES
Reference:
- Letter, G02-86-613, G.
C. Sorensen (SS)'to E.
G.
Adensam (NRC),
"WNP-2 Fire Protection Program - Request for Additional Information", dated June 30, 1986 In the reference letter (NRC guestion 2 of the Attachment),
the Supply System committed to having the General Electric Company perform an independent verification of our analysis results that we had performed to provide reactor parameter responses following depressurization utilizing six (6) main steam line safety relief valves.
That analysis has been performed and is included as Appendix 5 to the attached Supply System Report (NE-02-86-10, Rev. 0).
The final results of the GE analysis, and the Supply System's subsequent plant specific re-analysis, demonstrate that with credit taken for only those systems which are operable from the remote shutdown room(s), there is minimal core uncovery as a result of the worst case IIesign basis fire, and that the peak cladding temperature remains over 900 F below the value that gould reasonably be expected to cause any serious cladding damage (1700 F}.
i
~
E.
G.
Adensam Page Two September 9,
1986 WNP-2 FIRE PROTECTION
- PROGRAM, APPENDIX R CALCULATION FOR ALTERNATE SHUTDOWN FROM REMOTE CONTROL ROOM UTILIZING SIX MAIN STEAM SAFETY RELIEF VALVES Should you have any questions regarding this matter,- please contact Mr.
P.
L. Powell, Manager, WNP-2 Licensing.'ery truly yours, Qc.
G.
C. Sorensen, Manager Regulatory Programs HLA/tmh Attachment cc:
JO Bradfute -
NRC JB Martin -
NRC RV E
Revell -
BPA NS Reynolds - BLCP8R NRC Site Inspector