GO2-83-834, Forwards 830812 Interim Deficiency Rept for Condition 216 Re RHR Relief Valve Vents & Condition 270 Concerning Intermediate Grade Matl on ECCS Pumps.Deactivation of RHR Sys in Steam Condensing Mode to Remove Valves Initiated

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Forwards 830812 Interim Deficiency Rept for Condition 216 Re RHR Relief Valve Vents & Condition 270 Concerning Intermediate Grade Matl on ECCS Pumps.Deactivation of RHR Sys in Steam Condensing Mode to Remove Valves Initiated
ML17333A009
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 09/15/1983
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML17277A817 List:
References
GO2-83-834, NUDOCS 8309290201
Download: ML17333A009 (4)


Text

.p REGULATORY iFORMATION DISTRIBUTION S EM (RIDS) c" re ACCESSION NOR:8309290201 DOC ~ DATE: 83/09/15 NOTARIZED: NO, DOCKET FACIL:50-397 HPPSS Nuclear Projects Unit 2i Nashington Public Powe 05000397 AUTH,NAME AUTHOR AFFILIATION SORENSEN<G.C.

Nashington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION SCHAENCERiA ~

Licensing Branch 2

SUBJECT; Forwards 830812 interim deficiency rept for Condition 216 re RHR relief valve vents 5 Condition 270 concerning intermediate grade matl on ECCS

'pumps, Deactivation of RHR sys in steam condensing mode to remove valves initiated, DISTRIBUTION CODE:

8001S COPIES RECEIVED:LTR ENCL g SI E: ~

TITLE: Licensing Submi t tal:

PSAR/FSAR Amdts ff Related Correspondence NOTES:

RECIPIENT ID CODE/NAME NRR/DL/ADL NRR L82 LA INTERNAL: ELD/HDS2 IE/DEPER/EPB 36 IE/DEQA/QAU 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2u NRR/DHFS/HFEBu0 NRR/DHFS/PSRB NRR/DSI/AE8 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RS8 23 RGN5 EXTERNAL: ACRS DMB/DSS (Al'aDTS)

LPDR 03 NSIC 05 COPIES LTTR ENCL 1

0 0

1 0

3 3

1 1

1 2

1 1

1 1

1 1

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1

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3 6

6 1

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1 RECIPIENT ID CODE/NAME NRR L82 BC AULUCKgR~

01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DSI/ASB NRR/DS I/CSB 09 NRR/DSI/METB 12 N

RAB 22 C'ILt ou RM A

/MI8 BNL(AMDTS ONLY)

FEMA-f<EP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1

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'TOTAL NUMBER OF COPIES REQUIRED:

LTTR 53 ENCL u6

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 September 15, 1983 G02-83-834 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:

Mr; A.'Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Schwencer:

Subject:

Reference:

NUCLEAR PROJECT NO.

2 RESIDUAL HEAT REMOVAL STEAN CONDENSING MODE, DELETION OF

Letter, C. S. Carlisle (SS) to J.

B. Martin (NRC)

"10CFR50.55(e)

Reportable Conditions:

0'216, RHR Relief Valve Vents; 8270, Indeterminate Grade Material on ECCS Pumps",

dated August 12, 1983 (Attachment 1)

Attachment 1 to the referenced letter describes a potential leakage path from primary containment to secondary containment caused by a deficiency in the design of four.RHR relief valves.

As corrective action, the Supply System has decided to deactivate operation of the RHR system in the steam condensing mode and remove the subject valves.

This mode of operation is infrequently used and credit is not taken for its operation in the WNP-2 FSAR Chapter 15 accident analysis.

Deactivation of this mode of operation represents no obstacle in the safe operation of WNP-2.

830929020i 8309i5 PDR ADOCK 05000397 S

PDR

A. Schwencer Page Two September 15, 1983 RESIDUAL HEAT REMOVAL STEAf1 CONDENSING NODE, DELETION OF Attachment 2 is the FSAR change reflecting deletion of the RHR steam condensing mode.

This change will be incorporated in Amendment 33 to the FSAR.

Should you have any questions, please contact Nr. P. L. Powell, Acting

Hanager, WNP-2 Licensing.

Yery truly yours, G.

C. Sorensen, Acting Nanager Nuclear Safety and Regulatory Programs PLP/tmh Enclosures cc:

R Auluck -

NRC WS Chin

- BPA A

Toth NRC Site