ML17277B034

Forwards Procedure to Ensure Operability of ESF Sys Following Removal from Svc Per NUREG-0737,Items II.K.1.10 & II.K.1.5.Confirmatory Issue 22 Considered Closed

ML17277B034
Person / Time
Site:	Columbia
Issue date:	11/11/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17277B035	List: ML17277B034 ML17277B036 ML17277B037 ML17277B038 ML17277B039 ML17277B040 ML17277B041 ML17277B042
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.1, TASK-TM GO-83-1044, NUDOCS 8311210258
Download: ML17277B034 (5)

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REGULATORY I MATION DISTRIBUTION SYST (RIDS) c ACCESSION NOR;8311210258 DOC ~ DATE! 83/11/11 NOTARIZED: NO DOCKET ¹ FACIL:50 397 BYNAME ISPPSS Nuclear Pr ojectp Uni t 2i Washington Public Powe 05000397 AUTH AUTHOR AFFILIATION SORENSEN~G<C, Nashington Public Power Supply System

'EC IP ~ NAME RECIPIENT AFFILIATION SCHNENCERpA ~ Licensing Br anch 2

SUBJECT:

Forwards proce u t censure operability of ESF sys" fol lowing removal from svc per NUREG 0737iltems 'll+K,1-,10 It II ~ K~ 1+5 ~ Confirmatory Issue 22 considered closed.

DISTRIBUTION CODE ~ 800 1S COPIES RECEIVED $ LTR << 'NCL <<<<SIZE r.8 e<<

T?TLE: Licensing 'Submittal: PSAR/FSAR Amdts L Related<< Correspondence NOTES; RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL 1 0 NRR LB2 BC 1 0 NRR L82 L'A 0 AULUCKpR, Oi 1 1 INTERNALS ELD/HOS2 1 0 IE F ILK 1 1 IE/DEPER/EPB 36 3 3 IE/DEPER/IRB 35 1 1 IE/DEQA/QAB 21 1 1 NRR/DE/AEAB 1 0 NRR/DK/CEB 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13 2 NRR/OE/GB 28 2 2.

NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRA/DK/SAB 24 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFE840 1 1 NRR/DHFS/LQB 32 1 NRA/DHFS/PSRB 1 1 NRR/OL/SSPB 1 0 NRR/DS I/AEB 26 1 1 NRR/DS I/ASB 1 1 NRR/DSI/CPB 10 1 NRR/DS I/CSB 09 1 1 NRR/DSI/I CSB 16 1 1 NRR/DSI/METB 12 NRR/DSI/PSB 19 1 1 N RAB 22 1 1 NRR/DSI/RSB 23 1 1 KG F ILK 04 1 1 RGN5 3 3 AMI/MIB 1 0 EXTERNAL: ACRS 41 6 BNL(AMDTS ONI Y) 1 1 DMB/DSS (AMDTS) 1 1 FKMA<<RKP DIV 39 1 1 LPDR 03 1 1 NRC PDR 02 1 NSIC 05 1 1 NTIS 1 TOTAL NUMBER OF COPIES REQUIRED! LTTR 53 ENCL 46

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 November G02-83-1044 ll, 1983 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:

NUCLEAR PROJECT NO. 2 NUREG-0737, TMI-2 ACTION PLAN, ITEMS II.K.1.10 AND II.K.1.5, CONFIRMATORY ISSUE 22 II.K.1.10 TMI-2 Action*Plan Item II.K.1.10 is concerned with ensuring operability of an Engineered Safety Feature (ESF) system following its removal from service.

At WNP-2, there exists four procedures (attached) which may affect the oper-ability of ESF systems. They are:

1) PPM 1.3.7 - Work Request

2) PPM 1.3.8 - Equipment Clearance and Tagging

3) PPM 1.3.9 - Control of Jumpers, Lifted Leads and Mechanical Jumpers

4) PPM 1.5. 1 - Technical Specification Surveillance Testing Program All four of these procedures require the Shift Manager's review and approval prior to the execution of the work on an ESF system or component and also prior to returning the component or system to operable status. In executing this review, the Shift Manager is assuring that all program and technical require-ments for the removal of and the return to operable status are met. Procedures 1.3.8, 1.3.9, and 1.5.1 provide for the additional controls of independent verification.

8311210258 PDR ADOCK 83iiii 05000397 A PDR

A. Schwencer Page Two There are three additional administrative procedures which address the issue of system operability. They deal primarily with keeping the operating shift informed of system operability. These procedures are also attached and include:

1) PPM 1.3. 1 - Standing Orders/Night Orders 2 PPM 1.3.4 - Operating Data and Logs 3 PPM 1.3.6 - Shift Turnover A WNP-2 design feature includes an inoperative status panel which will automatically display the inoperative status of primary ESF components.

These procedures and programs provide adequate controls of safety related equipment at WNP-2.

II.K.1.5 The full procedure and program controls outlined for item II.K.1. 10 also apply to TMI-2 Item II.K.1.5. Additional clarification concerning this i tem is that all ESF systems are aligned and are operated as outlined in their respective Volume 2 Plant Procedures Manual. These system alignments are initially independently verified. Our program also requires independent verification following each major outage. In addition, the principle ESF components have direct control board status indication to alert the operator and ensure their proper alignment. Critical manual valves are locked in their required position. These valves require Shift Manager approval prior to deviating from their required position. In addition, independent verifi-cation is required when they are returned to their normal position.

These procedures and programs provide adequate controls of ESF equipment at WNP-2. We feel that concerns to these items are resolved and the issue is closed.

Should you have any further questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, 44~~ e6 G. C. Sorensen, Manager Regulatory Programs JWB/tmh Attachment cc: R Auluck - NRC WS Chin - BPA AD Toth NRC Site

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