ML17261A820

Provides Addl Info Re Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switching. Thirty Valves Tested Have Average Closure Time of 18.29

ML17261A820
Person / Time
Site:	Ginna
Issue date:	01/06/1989
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Stahle C NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
IEB-85-003, IEB-85-3, NUDOCS 8901190346
Download: ML17261A820 (2)

Text

Ac CELE RATED Dl BUTI ON DEMONSTRATION SYSTEM REGULATOR. NFORMATION DISTRIBUTION SVEM (RIDE)

ACCESSION NBR:8901190346 DOC.DATE: 89/01/06 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION STAHLEFC. Document Control Branch (Document Control Desk)

SUBJECT:

Provides addi info re IEB 85-003, "Motor-Operated Valve Common Mode Failures During Plant Transients Due to DISTRIBUTION CODE: IEllD COPIES RECEIVED:LTR I ENCL 0 SIZE: I TITLE: Bulletin Response (50 DKT)

D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 8

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA PD1-3 PD STAHLE,C INTERNAL: AEOD/DOA AEOD/DSP/TPAB 1 NRR ALEXION,T NRR/DEST/ADE 8H 1 NRR/DEST/ADS 7E NRR/DEST/MEB 9H 1 NRR/DOEA/EAB 11 NRR/DOEA/GCB 11 1 NRR/DREP/EPB 10 NR S/ILRB12 1 NUDOCS-ABSTRACT 02 1 RES/DS1R/EIB RGN1 FILE 01 1 EXTERNAL: LPDR NRC PDR NSIC R

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL

ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 January 6, 1989 Tf a.L>~O'Nt i>ca coDt ice 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No. 1 Washington, D.C. 20555

Subject:

Additional Information Request Concerning Response to IEB 85-03, "Motor-Operated Valve Common Mode Failures Dur'ing Plant Transients Due to Improper Switching" R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Stahle:

Your letter dated December 8, 1988 requested that the response to Question 2 of our October 9, 1987 lettei be revised. As mentioned in our October 9, 1987 response, the effect of water hammer due to valve closure was considered to be negligible due to the slow closure times of the valves involved. Since the effect was considered negligible, it was not added to the static pressure drop calculated for valve closure ~

The thirty valves tested in the IEB 85-03 program have an average closure stroke time of 18. 29 seconds. The fastest valves stroke in 5.81 seconds. The slowest stroke is 31.68 seconds. These times are judged to be slow enough to preclude any water hammer effects. Also, plant experience during valve closure has not indicated any problems attributable to water hammer.

Very truly yours, 890ii90346 890i06 Robert C. ecre PDR ADOCK 05000244 P PNU General Manager Nuclear Production RWE~012 xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector I 0