ML20138P357

Forwards Wyle Labs Test Procedure & Certification Test Rept Re Air Vs Water Correlation for Leak Testing of Reactor Coolant Boundary Valves,In Response to Question 210.56 & SER Confirmatory Item 3

ML20138P357
Person / Time
Site:	Hope Creek
Issue date:	12/23/1985
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML20138P358	List: ML20138P357 ML20138P359 ML20138P364
References
NUDOCS 8512260072
Download: ML20138P357 (3)

Text

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Public Service Electric and Gas Company Corbir A. McNet!!, Jr.

Pub!ic Service E:ectnc and Gas Company P.O. Box 236, Hancocks Bndge.NJ 08038 600030-4800 Vice President -

Nuclear December 23, 1985 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:

Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing i

Dear Ms. Adensam:

PRESSURE ISOLATION VALVE TEST PROGRAM HOPE CREEK GENERATING STATION l

DOCKET NO. 50-354 Enclosed is the Public Service Electric and Gas Company (PSE&G) submittal which details the test procedure, Attach-ment 2, and certification test report, Attachment 3, regard-ing the air versus water correlation for leak testing of reactor coolant boundary valves at the Hope Creek Generating Station (HCGS).

This information is being provided as the final response to Question 210.56, Attachment 1, and Safety Evaluation Report (SER) Confirmatory Item #3.

PSE&G has developed the attached test procedure for indicating reactor coolant system pressure isolation valve (PIV) leakage and has investigated the accuracy and conservatism as sociated with this procedure.

The test procedure is based on the fact that all identified PIV's are also required to be' tested in accordance with 10CFR50 Appendix J Type C requirements and.that the Appendix J events and time schedule that will initiate testing is the same as those identified in the SER Section 3.9.6.

Therefore, it is PSE&G's position that fhGo [

satisfactory completion of Appendix J, Type C testing of the identified PIV's also satisfies the requirements for PIV leakage.

/r To demonstrate the accuracy and conservatism associated with this test procedure, PSE&G contracted with an independent test facility, Wyle Laboratories, to investigate the correlation N-m22;ggggnag3y E

e Director of Nuclear 2

12-23-85 Reactor Regulation of air / nitrogen leakage at the Type C test pressure, 48.1 psig, with the leakage of water at reactor pressure, 1020 psig.

In addition, Wyle Laboratories also reviewed the methodology and results of PSE&G's field testing of the identified PIV's under the same conditions and has prepared a test report documenting their findings.

In summary, both the laboratory and field test results support the position, that as long as the Type C leakage is less than 30,000 sccm for any PIV, the results for water leakage were equal to or less than 1 gpm.

Field test results for water leakage were equal to or less than that which would be predicted by the laboratory correlation.

It is not the intent of this test procedure to quantify the water leakage based on air leakage but rather qualify the leakage as being equal to or less than the acceptance criteria identified in the SER and in the Technical Specifi-cations.

The Technical Specification acceptance criteria is higher than that identified in the SER which increases the conservatism of this test method.

While Technical Specification 3.4.3.2 identifies the requirements to demonstrate PIV operability along with the acceptance criteria and limiting conditions, revisions will be made to address the Type C air leakage as an alternative acceptance criteria.

The revisions to the Final Safety Analysis Report (FSAR) contained in Attachment 1 will be included in the next amendment pending NRC staff review and approval.

Should you have any questions of the subject filing, do not hesitate to contact us.

Sincerely,

Director of Nuclear 3

12-23-85 Reactor Regulation Attachments (3)

C D.H. Wagner USNRC Licensing Project Manager R.W.

Borchardt USNRC Senior Resident Inspector

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