ML20126A993

Forwards Results of Pump & Valve Operability Review Team/Sqrt 850507-10 Equipment Qualification Audits.Results Identify Open & Confirmatory Items.Brief Description Provided as Well as Actions Necessary to Resolve Item

ML20126A993
Person / Time
Site:	Hope Creek
Issue date:	05/30/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:	Mittl R Public Service Enterprise Group
References
NUDOCS 8506130535
Download: ML20126A993 (8)

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Docket lio. 50-354 MAY 3 0 1984 j Mr. R. L. Mittl, General Manager Nuclear Assurance and Regulation Public Service Electric & Gas Cornpany P. 0. Box 570, T22A Newark, New Jersey 07101

SUBJECT:

MAY 1985 EQUIPMENT QUALIFICATICW AUDITS On May 7-10, 1985, nenbers of the NRC staff and our consultants performed the g Pump and Valve Operability Review Team (PVORT) and the Seismic Qualification Review Team (SQRT) audits at Hope Creek. The enclosures to this letter identify open and confirmatory itens resulting frcu the audits. Specifically, the PVORT and SORT audit action items are identitied in Eticlosures 1 and 2 respectively.

For each item, a brief description is provided as well ac.the actions necessary for Public Service to resolve the item.

Please advise us should any of the action iten response dates change.

Sincerely, Isl Italter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosures:

As stated cc:- See next page Distribution: {05ck'EITEile; NRC PDR Local PDR PRC Systen NSIC LB#2 Reading EHylton Dilagner Dewey,0 ELD ACRS (16) JPartlow BGrimes Edordan Alee JJackson

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• MAY 3 0 -1985 Docket Uc. EC-24 Mr. R. L. liitti, General Manager Nuclear Assurance and Regulation Public Service Electric & Gas Conpany P. O. Box 570,~T22A liewar k', I;o Jersey 07101

SUBJECT:

lVY 1085 ECUIPMENT QUALIFICATI0ll AUDITS On t,ay 7-10, 1985, nenbers of the NRC staff erd our consultants perfornico the Punp and Valve Operability Prview Team (PV0RT) and the Seismic Qualification Review Team (SQFO) accits at Hope Creek. The enclosures te this letter identify oper, and cerfirratory items resulting from the audits. . Specifically, the PV0FT ard SCET.t.Ldit action items are ioentified in Enclosures 1 and 2 respectively.

For each iten, a brief descriptier: is provided as well as the. actions recessary for Public Service to resolve the iten.

Please advise 05 itevid any of the action iten respenst dates change.

Sincerely, i

if. ,[(H.Lt n.% /i Walter R. Butler, hief Licensing Branch No. 2 Division of Licensing

Enclosures:

As stated cc: See next page l

lic, l'. L. hitti hope Creek Generating Statier FoLiic-Service Electric & Gas Co.

• i cc: bregory Hinor - Susan C. Renis

-Richaro hubbarc Lisision of Public Interest Adyccr.cy Dale BridenLLLst f'ry Jersey State Departnent of l'FF T(cht.icci Associates the Public fcsoccte 1723 Hamilton Avenue, Sbitt L Licharc U. hughes Justice Cocpics Scn Jose, California 95125 CN-E50 Trenter., hcw Jersey 08625 Troy C. Ccnner, Jr. Esquire Office cf Legtl Counsel Conner & Wetterhahn Departocr.t of flatural Resources 1747 Pennsylvania Avenue li.W. and Environroental Control Washington, D.C. 20000 89 Kings highway P.O. Box 1401 Dover, Oclaware 19903 Richard Frylir.9, Jr. , Esquire Mr. K. K. bur rowes, Project Engineer Associate General Soliciter Lechtel Power Corporation Public Service Flectric & Gas Co. 50 Bealc Strcot

-P. G. Box 570 TSE P. O. Box 390E llework,fiew Jersey 0/1C1 Scr. Freccisco, California 9411C I;r. C. B1coch Mr. J. M. Ashley Resident Inspector Senior Licensing Engineer U.S.L.E.C. c/o Public Service Electric L Cus Co.

P. O. Box 241 Eethesda Office Center, Suit 550 Hancocks Bridge, ikw CLrse) 06036 4520 East-West highway Bethesda, Marylard 20P1/

hicharc F. Engel Ceputy Attorney General Pr. A. E. Giardino Divisicn of Law kanager - Quulity Assurance E&C Envirc rr.rrtal Protection Section Public Service Electric h Gas Co.

Eichard J. Fughes Justice CCFple). P. O. Cox A tr-4lif hancocks Bridge, liew Jortcy Of0 8 Trerton, New Jersey 08625 1:r. Lotert J. Touhey, Mr. Anthony J. Pietrofitta Acting Director General Manager bhkEC - Division of Power Producticn Engineering Environmental Control Atl6ntic Electric 00 Kings Highway 1199 Black Horse Pike F. O. box 1401 Pleasantville, NJ 0023:

Ccycr, Delaware 19903 Mr. Thonas E.1:urley Mr. E. S. Salvesen U. S. i4RC, Region 1 -

General Manager-Ilope Creet Opercticn 631 Park Avenue Public Service Electric & Ocs Co. King of Prussia, Perrtylve.nia 19406 P.O. Box A Mcrcccks Bridge, New Jersey 08038 hr. b. i. Frester.

Project Licensing titr.tctr

ILLlic -Service Electric & Gas Cc.

F. O. Ecx 570 T22A Fev.7,rk, t,a Jersey 07101

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Enclosure 1 PVORT AUDIT ACTION ITEMS Generic Confirmatory Item:

It is an NRC requirement that all equipment important to safety be qualified and approved by the applicant prior to fuel load.

In order to satisfy this requirement the following subtasks must be completed prior to fuel load:

1. Provide written confirmation that all pumps and valves important to safety are properly qualified and installed

. prior to fuel load.

2. Provide written confirmation that the original loads used in the tests or analyses to qualify pumps and valves important to safety are not exceeded by any new loads, such as those imposed by a LOCA (hydrodynamic loads) or as-built conditions.

Action: PSE&G will provide the required statements prior to Hope Creek Generating Station fuel load.

Confirmatory Item: ,

1. HPCI Turbine - The nameplate data is separated from the HPCI turbine. Confirm that the nameplate data is restored to its proper location.

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Action: PSE&G will provide documentation to NRC of the restoration of the HPCI turbine nameplate to a proper i

location by July 1985.

Open Item

1. Service Water Pump (AD-502) -

This pump was operated with a blocked cyclone separator.

The second (remaining) separator clogged and caused the pump packing to fail from the loss of cooling water. It is not clear as to the extent the blocked separator

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contributed to this event. In addition, it is not clear as to the adequacy of the present instrumentation to detect such failures.

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a) Analyze this event to determine the precise cause of the failure.

b) Demonstrate that the service water pumps can perform their safety related function given the present cyclone separator system design.

. c) Provide assurance that the present service water instrumentation is adequate to detect impending f ailures of the service water pumps.

Action: PSE&G will provide the information requested above by July 1985.

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Enclosure 2 SORT AUDIT ACTION ITEMS A) Confirmatory Issues

1) NSSS-2; HCU; 0S-213-0643 Question: Inspection of lines attached to HCU units revealed several spans of piping which appeared to be too flexible.

Action: PSEEG has dynamically analyzed the lines in question. In all cases the nozzle loads and piping stresses are below code allowable.

Additional evaluation of these lines are

. being performed to confirm acceptability of their recent design. NRC will be informed of the results by July 31, 1985.

2) NSSS-2; HCU; OS-213-0643 (small SST lines to HCU units) .

Question: Inspection of lines attached to the HCU units revealed a gang support at vertical member F567220 which appeared to be complete except that one line was not attached, leaving an unsupported span approximately 14' long. Please either demonstrate that the support is still under construction or,

- that a deficiency has been recorded against the support (no tag was observed), or that the line in question needs no support at that point.

Action: PSEEG indicated that the design is adequate. The installation will be verified by QC, NRC will be informed of the results by July 31, 1985.

3) BOP-2; Control Damper - IHD-9603BI Question: The ITT actuator qualification report is a summary report prepaired by MCC Powers. It is based on test data performed at Wyle Laboratory. The raw test data by Wyle Laboratory is not available {or review. Can it be obtained?

Action: PSE&G will obtain Wyle Laboratory raw test data and submit to NRC for review by May 1, 1985.

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4) BOP-2 Control Damper - IHD-9603BJ Question: The ITT actuator requires additional support as described in DCP 299 (Design Change Package). What is the expected completion date of this additional support?

Action: PSEEG will provide confirmation of completion of DCP-299 by July 15, 1985.

5) Draf t Safety Evaluation Report (SER) O Open Item 2 " Equipment Qualification" pen Item 103 SER Questions Further clarification is required for Open Jtem 103, furnished by PSE&G to NRC via letter dated August 20, 1984. .

I Action: NRC indicated that the draft response presented during the audit is acceptable, .

the formal response shall be included in the Amendment 11 submittal to Hope Creek FSAR presently scheduled for July 1985.

6) NSSS-9 RPV Level and Pressure Rack; 106-026/H21-PO26 Question: There is a run of SST tubing attached to the panel (water level B21-NO95D) which appears to be flexibly mounted. Revo all the

- supports on the tubing been installed /was the tubing shown to be adequate for seismic loads?

Action: PSE&G indicated that work is in process, adequate support will be provided for the tubing in question in accordance with established acceptance criteria (re: BPC Spec 10855-J-S-1303). NRC will be informed of the results by May 31, 1985.

B) Equipment Specific Open Item

1) Question: RRS for switches mounted in the panel

-(145C3040P003 were obtained with calculations involving the floor response

, spectra and the dynamics characteristics of the panel. Since this methodology was new i

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to the reviewer, a description of this methodology has been requested for a post-audit review to allow thorough evaluation. This has been classified as an equipment specific item, note that a) a summary description of the methodology indicates it is reasonable, and b) only two plant items were qualified using it.

. Action: General Electric will provide a formal written description of the methodology in question directly to M. Russell of EG&G. A copy will also be sent to Arnold Lee of NRC. The information will be provided by June 1,1985.

C) Generic Open Issue .

1) NSSS-1; Reactor Core Spray Pump and Motor; 1AP-206/ -

E21-C001 Ouestion: The determination of relative displacements using the response spectra method should be done on a modal level. Subtracting unsigned peak (SRSS) displacements is unacceptable.

Conservatively adding peak values is an acceptable alternative. Two pump analyses performed by GE determined relative displacements by subtracting peak SRSS '.

displacements. This appears to be a generic Concern.

Action: GE will review methods used to, determine relative displacements' for essential NSSS pumps, and will revise calculations where necessary to demonstrate operabilty by July 31, 1985.

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