ML20100J813

Forwards Applications for Amend to License NPF-29,modifying Safety Setpoint Tolerence Requirements for Safety/Relief Valves.Attachment 4 Provides Details of Analyses Requested by NEDC-31753-P-A SER

ML20100J813
Person / Time
Site:	Grand Gulf
Issue date:	02/22/1996
From:	Meisner M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20100J816	List: ML20100J813 ML20100J831 ML20100J839 ML20100J862
References
GNRO-96-00008, GNRO-96-8, NUDOCS 9602290263
Download: ML20100J813 (3)

Text

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S-Ent:rty Oper:tiin2,Inc.

• . = ENTERGY eo so 7so Pcrt G bson. MS 39150 le) 601437 6470 M. J. Meisner

( Dran rurars w a % w m February 22,1996 U.S. Nuclear Regulatory Commission Mail Station P1-37 Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Grand Gulf Nuclear Station Docket No. 50-416 i

License No. NPF-29

! Modification of the Safety Setpoint Tolerance Requirements for i the Safety / Relief Valves, Proposed Amendment to the Operating License. (PCOL-96/01)

GNRO 96/00008 Gentlemen:

Entergy Operations, Inc. is submitting by this letter a proposed amendment to the Grand Gulf Nuclear Station (GGNS) Operating License to increase the present11% tolerance on the safety function lift setpoint for the safety relief valves (S/RVs) to 13% This proposed change affects Technical Specification Surveillance Requirement 3.4.4.1.

l' The Boiling Water Reactor Owners Group, with the assistance of the General Electric  ;

Company, submitted Licensing Topical Report NEDC-31753P, "BWROG In-Service 1 Pressure Relief Technical Specification Revision Licensing Topical Report", for NRC review.

o The resulting Safety Evaluation Report (NEDC 31753-P-A SER) approves the increase of the S/RV safety function lift setpoint to 13%, and requires licensees that choose to implement these technical specification modifications to provide certain plant specific analyses. A summary of the required analyses is provided in Attachment 2.

The GGNS Inservice Testing (IST) program controls the frequency of S/RV testing as

! required by the GGNS Operating License; therefore, this proposal will also incorporate i

changes to applicable IST procedures. GGNS willincorporate the recommendations of the NEDC 31753-P-A SER, by resetting the safety function lift setpoints for all tested valves to I within 11% of the design lift setpoint and increasing the test sample size by two valves for each valve found outside of the 13% safety function lift setpoint. GGNS will determine the number of S/RVs to be tested each outage using the currently licensed ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition, with Addenda through Winter 1980 (Subsections IWA and IWV), rather than the prescribed 50% of allinstalled valves as recommended by the NEDC 31753-P-A SER and the GGNS Updated Final Safety Analysis l Report. This method of sample selection has been granted to a similar BWR facility l requesting the 13% increase in safety function lift setpoint.

l 9602290263 960222 PDR ADOCK 05000416 p PDR O

GNRO 96/00008 Page 2 of 2 Attachment 2 also provides a detailed description of the proposed change, justification, and the no significant hazards considerations. Attachment 3 is a copy of the marked-up GGNS Operating License. Attachment 4 provides details of the analyses requested by the NEDC 31753-P-A SER.

This action will save Entergy Operations, Inc. approximately $5.4M for the remaining life of the GGNS plant. It is Entergy Operations, Inc. desire that this be treated as a cost beneficiallicensing action and given appropriate priority. We request NRC Staff complete its review and approval by July 1,1996 in order to support planning for the October,1996 refueling outage.

In accordance with the provisions of 10 CFR 50.4, the signed original of the requested amendment is enclosed. The amendment has been reviewed and accepted by the plant safety review committee and the safety review committee. Based on the guidelines presented in 10CFR50.92, Entergy Operations has concluded that this proposed amendment involves no significant hazards considerations.

You s truly, f '

BJB/bjb I

Attachment 1: Affirmation per 10CFR50.30 Attachment 2: Detailed Description of the Proposed Change, Justification, and the No Significant Hazards Considerations i Attachment 3: Copy of the Marked-up Operating License Attachment 4: Grand Gulf Nuclear Station Engineering Report," Safety / Relief Valves Safety Function Lift Setpoint Tolerance Relaxation Summary Report" cc: (See Next Page)

GNRO 96/00008 cc: Mr. C. R. Hutchinson Mr. J. E. Tedrow (w/a)

Mr. J. W. Yelverton (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. L. J. Callan (w/a) -

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400

. Arlington, TX 76011 Mr. J. N. Donohew, Project Manager (w/2)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 l

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