ML20205F877

Forwards SE Authorizing Licensee 971222 Relief Requests Re Second 10-year Interval for Pumps & Valves IST Program for Hope Creek Generating Station

ML20205F877
Person / Time
Site:	Hope Creek
Issue date:	03/18/1999
From:	Adensam E NRC (Affiliation Not Assigned)
To:	Keiser H Public Service Enterprise Group
Shared Package
ML20205F881	List: ML20205F877 ML20205F891
References
TAC-MA0425, TAC-MA1430, TAC-MA425, NUDOCS 9904070048
Download: ML20205F877 (4)

Text

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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20056 4001

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March 18, 1999 L

l Mr. Haiold W. Keiser Chief Nuclear Officer & President Nuclear Business Unit Public Service Electric & Gas l

Company

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Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

SAFETY EVALUATION OF RELIEF REQUESTS FOR SECOND 10-YEAR INTERVAL FOR PUMPS AND VALVES INSERVICE TESTING PROGRAM -

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HOPE CREEK GENERATING STATION (TAC NOS. MA0425 AND MA1430)

Dear Mr. Keiser:

By .Second Interval Is Being Reduced to Nine Years W/End Date of Dec 20,2006 & Requirements Will Be Phased in by 960331 IAW NUREG-1482|letter dated December 22,1997]], Public Service Electric and Gas Company (PSE&G) submitted the Hope Creek Generating Station Inservice Testing (IST) Program for the second 10-year interval. The first 10-year interval was extended by one year from December 20,1996, to December 20,1997. Accordingly, the second interval will be reduced to 9 years with an end date of December 20,2006. In the submittal dated December 22,1997, PSE&G included requests for relief from the American Society of Mechanical Engineers Boiler and Pressure vessel Code (ASME Code),Section XI requirements. An additional relief request was provided in your letter dated April 7,1998. Additional information was provided in your letter dated September 21,1998.

The NRC staff, with tQ Aal assion.nce from Brookhaven National Laboratory (BNL), has reviewed the relief requests. The staff adopts the evaluations and recommendations for granting relief or authorizing attematives contained in the Technical Evaluation Report (TER) prepared by BNL, as reflected or modified in the attached safety evaluation (SE). Our SE concludes the following:

1)

With respect to Relief Requests Nos. P-01 and P-02, compliance with the Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, the proposed attematives are authorized pursuant to

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10 CFR 50.55a(a)(3)(ii).

2)

With respect to Relief Request Nos. P-03, V-01, and V-02, the proposed attematives

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provide an acceptable level of quality and safety. Therefore, the proposed attematives are authorized pursuant to 10 CFR 50.55ata)(3)(i).

3)

With respect to Relief Requests Nos. V-03 and RJ-8, the requirements of the Code are impractical. Therefore, reliof is granted pursuant to 10 CFR 50.55a(f)(6)(i). The relief

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granted is authorized by law and will not endanger life or property, or the common I

defense and security, and is otherwise in the public interest. In making this determination, the staff has considered the burden on the licensee if the requirements were imposed on the facility.

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H. Kriser 1 PSE&G based the Hope Creek IST Program on the requirements of the 1989 Edition of ASME Section XI, Subsections IWP and IWV, which is incorporated by reference in 10 CFR 50.55a.

ASME Operations and Maintenance (OM) Standard Part 6, for IST of pumps is referenced by Subsection IWP and OM Standard, Part 10, for IST of valves is referenced by Subsection IWV.

The relief requests were reviewed against the requirements of the 1969 Edition of ASME Section XI for pumps and valves. A summary of the Nuclear Regulatory Commission's (NRC) action on each relief request is provided in Attachment 1 to the enclosed SE. The test deferrals for valves Oich are in accordance with Part 10 have been reviewed and are summarized in l

Section 4 of ths TER which is included as Attachment 2 to the SE.

The IST program relief requests that are granted or authorized herein are acceptable for implementation. The staff notes that in Section 6 of the TER, certain program action items have been identified. These items should be addressed within one year of the date of the SE or by the end of the next refueling outage, whichever is later, unless another period is specified. The granting of relief is based upon the fulfillment of any commitments made by PSE&G in the basis for each relief request and the alternatives proposed. Where interim relief has been granted, PSE&G should resolve the issues before expiration of the interim period. PSE&G is requested to respond to the NRC within one year of the date of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.

Program changes involving new or revised relief requests should be submitted to the NRC.

New or revised relief requests that meet the positions in NRC Generic Letter (GL) 89-04,, should be submitted to the NRC but may be implemented prior to staff approval 1

provided the guidance in GL 89-04, Section D, is followed.

If you have any questions regarding this matter, please contact the Hope Creek Project Manager, Richard B. Ennis, at (301) 415-1420.

Sincerely,

/s/

Elinor G. Adensam, Director Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

Safety Evaluation cc w/ encl: See next page DISTRIBUTION Docket File EAdensam OGC GMeyer, RGN-l PUBLIC REnnis ACRS RNorsworthy (E-Mail SE)

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H. Keiser PSE&G based the Hope Creek IST Program on the requiremants of the 1989 Edition of ASME Section XI, Subsections IWP and IWV, which is incorporated by reference in 10 CFR 50.55a.

A6ME Operations and Maintenance (OM) Standard Part 6, for IST of pumps is referenced by Subsection (WP and OM Standard, Part 10, for IST of valves is referenced by Subsection IWV.

The relief requests were reviewed against the requirements of the 1989 Edition of ASME Section XI for pumps and valves. A summary of the Nuclear Regulatory Commission's (NRC) action on each relief request is provided in Attachment 1 to the enclosed SE. The test deferrals for valves which are in accordance with Part 10 have been reviewed and are summarized in Section 4 of the TER which is included as Attachment 2 to the SE.

The IST program relief requests that are granted or authorized herein are acceptable for implementation. The staff notes that in Section 6 of the TER, certain program action items have been identified. These items should be addressed within one year of the date of the SE or by the end of the next refueling outage, whichever is later, unless another period is specified. The granting of reliefis based upon the fulfillment of any commitments made by PSE&G in the basis for each relief request and the altematives proposed. Where interim relief has been granted, PSE&G should resolve the issues before expiration of the interim period. PSE&G is requested to respond to the NRC within one year of the date of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.

Program changes involving new or revised relief requests should be submitted to the NRC.

New or revised relief requests that meet the positions in NRC Generic Letter (GL) 89-04,, should be submitted to the NRC but may be implemented prior to staff approval provided the guidance in GL 89-04, Section D, is followed.

If you have any questione regarding this matter, please contact the Hope Creek Project Manager, Richard B. Ennis, at (301) 415-1420.

Sincerely, Elinor G. Adensam, Director Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354 l

Enclosure:

Safety Evaluation cc w/ encl: See next page

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Mr. Harold W. Keiser Hope Creek Generating Station Public Service Electric & Gas Company cc:

Jeffrie J. Keenan, Esquire Manager - Joint Generation Nuclear Business Unit - N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg Harbor Twp., NJ 08234-4130 Hope Creek Resident inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 0509 Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township i

Nuclear Department c/o Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 General Manager - Hope Creek Operations Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Director-Licensing Regulatiors & Fuels Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region l U.S. Nuclear Regulatory Commission 1

475 Allendale Road l

King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 l