ML17278A532

Forwards Rev 3a to Pump & Valve Inservice Test Program Plan, for Approval.Changes Correct Clerical Errors.Fee Paid

ML17278A532
Person / Time
Site:	Columbia
Issue date:	12/26/1985
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML17278A533	List: ML17278A532 ML17278A534
References
NUDOCS 8512310286
Download: ML17278A532 (4)

Text

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I REGULA Y, INFORNATION DISTRIBUTIO BYSTEN (RIDS)

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~, ACCESSION -blBR: 851231028b DOC. DATE: 85/12/2b NOTARIZED: NO DOCKET q<

'*CIL:50-397 WPPSS Nuclear Progecti Unit 2i Washington Public. Pore 05000397 AUTH. NANE 'UTHOR AFFILIATION SORENSON> Q. C. Washington Public Power Supplg System RECIP. NANE RECIPIENT AFFILIATION ADENBANE E. Q. BMR ProJect Directorate 3

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SUBJECT:

Forwards Rev 3 to "Pump h Valve Inservice Test Program. Plan"

~ for approval. Changes correct clerical errors. Fee paid.

DISTRIBUTION CODE: AO47D TITLE: OR COPIEB RECEIVED: LTR Submittal: Inservice L ENCL/

Inspection/Testing BIZE:

NOTES:

OL:12/20/83 ~/~ /$4. <<

05000397 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NANE LTTR ENCL BWR PD3 PD 01 5 5 BRADFUTEE J 1 1 INTERNAL: ACRS 10 10 ADN/LFNB 1 0 ELD/HDB2 1 0 NRR BWR ADTB 1 1 NRR BWR EB 1 NRR PWR-A ADTS 1 NRR PWR-A EB 1 NRR PWR-B ADTB 1 EB 1 1 NRR/TANB 1 REQ FIL 04 1 1 RQN5 1 1 EXTERNAL: 24X 1 1 LPDR 03 1 1 NRC PDR 02 1 NSIC 05 1 TOTAL NUNBER OF COPIES REQUIRED: LTTR 31 ENCL 29

Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 December 26, 1985 8512310286 851226 PDR ADOCN, 05000397 P PDR Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Ms. E. G. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 REQUEST FOR INTERIM APPROVAL OF REVISION 3 TO THE WNP-2 PUMP AND VALVE INSERVICE TEST PROGRAM PLAN WITH CHANGES DESCRIBED HEREIN

References:

1) Letter, W. R. Butler (NRC) to G. C. Sorensen (SS)

"Pump and Valve Inservice Testing Program Review-Meeting Minutes", dated June 10, 1985

2) Letter, G02-85-319, G. C. Sorensen (SS) to W. R.

Butler (NRC), "Submittal of Revision 3 to WNP-2 Pump and Valve Inservice Test Program Plan",

dated June 17, 1985 The version of the subject Plan currently approved (on an interim basis) by the NRC is Revision 2, dated November 3, 1983. Since Revision 2 of that Plan was submitted prior to WNP-2 entering into commercial operation, it has been found to require. numerous changes due to lessons learned re-garding actual system operating and testing configurations as well as design changes occurring in the late construction completion phase of the plant.

Reference 1 documents a meeting on April 16 and 17, 1985 in Bethesda to review the WNP-2 Pump and Valve Inservice Testing Program. The meeting was a working session attended by personnel from the Supply System, EGKG (the NRC contractor), and the NRC. The version of the Plan discussed at the meeting was an upgraded version of Revision 2 (i.e. Revision 3) reflecting knowledge gained by operating experience through the first quarter of commercial operation.

E. G. Adensam Page Two REQUEST FOR INTERIM APPROVAL OF REV. 3 TO THE WNP-2 PUMP 5 VALVE INSERVICE TEST PROGRAM PLAN WITH CHANGES DESCRIBED HEREIN Revision 3 of the Plan, dated June 10, 1985, was subsequently submitted to the NRC per Reference 2. Revision 3 of the Plan reflects the incorporation of the various comments from the meeting and as such is considered far superior to Revision 2 of the Plan. Since Revision 2 of the Plan is obviously outdated, we are basing our current revisions to the implementing surveillance test procedures on the criteria contained in Revision 3, as further modified by additional changes described in Attachment A. The Supply System is therefore requesting your interim approval of Revision 3 of the Plan and the specific changes described in Attachment A pending completion of a formal comprehensive review such that we will continue to have a legitimate basis for our implementing procedures.

Enclosed is an application fee of One hundred fifty dollars ($ 150.00) in accordance with 10 CFR 170. 12(f). Should you have any questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, G. C. Sorensen, Manager Regulatory Programs RPW/t@h Attachments cc: RC Barr - BPA JO Bradfute - NRC JB Martin NRC RV E Revell - BPA NS Reynolds - BLCP&R AD Toth - NRC Site

ATTACHMENT A Description of Specific Changes to Revision 3 Several clerical errors have been identified and corrected.

Valves, SW-V-214, 215, 216, and 217 have no manual control switch and no remote position indicators. Attempts to measure valve stroke times have yielded inconsistent and misleading results. This requires relief from IWV-3413, measure the stroke time of power operated valves. These valves will be verified to stroke in a timely manner and continue to be exercised quarterly. This is similar to Relief Request RV-10 and RV-12. See Relief Request RV-21.

Temperature Control Valves, SW-TCV-15A and 15B will be added to the Plan. These valves have a required fail position (open) in order for the system to operate and perform its safety function. This is the same reason SW-TCV-llA and 11B were added in Revision 3.

Temperature Control Yalves, SW-TCV-llA, llB, 15A, and 15B have no manual control switch or valve position indication. Measure-ment of valve stroke time per IWY-3413 is not practical. These valves will be verified to operate in a timely manner and continue to be exercised quarterly. This is similar to Relief Request RV-10 and RV-12. See Relief Request RV-22.

Pumps, DO-P-lA, 1B, and 2 are submersible pumps. The, requirement to observe proper lubrication level and/or pressure per'WP-3100 is not applicable.

The diesel oil transfer pumps (DO-P-1A, 1B and 2) do not have a rate or quantity meter installed in the test circuit per IWP-4600.

However, WNP-2 employs a flowrate measurement test methodology which yields equivalent results by measuring the change in tank volume. Relief from IWP-4600 is requested in RP-5.

A single keylock control switch is used to operate the nine inboard Post Accident Sampling valves performing a containment isolation safety function. It is not practical to measure the stroke times of all nine valves per IWY-3413. These valves will be tested quarterly and the stroke time of the slowest of the nine valves will be recorded. This is similar to Relief Request RV-19.

See Relief Request RY-23.

Valves, RWCU-V-l, 4, and 40 can not be tested during normal power operations without jeopardizing the RWCU pumps. Testing interrupts flow through the pumps causing them to overheat, significantly increasing the potential for equipment damage. These valves will be tested during cold shutdowns per IWV-3412.