ML18102A691

Submits Supplemental Info Re 960531 Request for Change to TS Channel Calibr Definition

ML18102A691
Person / Time
Site:	Salem
Issue date:	12/23/1996
From:	Storz L Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18102A692	List: ML18102A691 ML18102A693
References
LR-N96423, NUDOCS 9612310072
Download: ML18102A691 (4)

Text

Public Service Electric and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations DEC 2 31996 LR-N96423 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENT TO REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CHANNEL CALIBRATION DEFINITION SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:

By letter LR-N96069, dated May 31, 1996, Public Service Electric

& Gas Company (PSE&G) submitted a request to amend the Salem Generating Station Units 1 and 2 Technical Specifications (TSs) definition 1.4 for Channel Calibration to address calibration of instrument channels with resistance temperature detectors (RTDs) or thermocouple sensors. This letter provides a supplement to that request.

The previously submitted request proposed a revision to the definition that was consistent with that provided in NUREG-1433, Revision 1, "Standard Technical Specifications General Electric Plants, BWR/4." As detailed in the previously submitted revision request, this NUREG was used rather than NUREG-1431, Revision 1, "Standard Technical Specifications Westinghouse Plants" since it was more inclusive by addressing Channel Functional testing and was consistent with PSE&G's present application.

Upon review of the initial submittal by the Staff, it was noted that NUREG-1431 contains additional wording requiring that a cross calibration be performed whenever a sensing element is replaced. This test would compare the replaced element to the other sensing elements.

PSE&G currently performs a cross calibration of the Reactor Coolant RTDs on a refueling frequency to satisfy, in part, the requirements of Specification 4.3.1.1.1 pertaining to Reactor Trip System Instrumentation and 4.3.2.1.1 pertaining to 9612310072 961223 PDR ADOCK 05000272 P PDR Printed on Recycled Paper

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1 DEC231996 Document Control Desk 2 LR-N96423 Engineered Safety Feature Actuation System Instrumentation. This test would also be performed, as required by these surveillance requirements, to verify the operability and accuracy of any replaced RTD.

To provide clarification of this requirement in the definition section of the TSs, PSE&G is proposing to add the applicable portion of NUREG-1431 to the previously submitted request.

Clarification was added to specify RTD or thermocouple sensing elements since cross calibration is not applicable to other type sensors. Marked up TS pages for Salem Units 1 and 2 affected by the proposed changes of this supplement are attached.

The revision to the Channel Calibration definition proposed by this supplement are considered an enhancement to the change request submitted previously. PSE&G has reviewed the previously submitted evaluation in accordance with the three standards set forth in 10CFR50.92 and has concluded that no change is necessary as a result of the revised pages and the conclusion of no significant hazards consideration remains valid.

Should you have any questions regarding this supplement, we will be pleased to discuss them with you.

Attachment C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933

DEC 2 31996 Document Control Desk 3 LR-N96423 SRM/mrh BC Senior Vice President - Nuclear Engineering (N19)

General Manager - Salem Operations (SOS)

Director - QA/NSR (XOl)

Manager - Nuclear Business Relations (N28)

Manager - Salem Operations (SOl)

Manager - System Engineering - Salem (S02)

Manager - Nuclear Safety Review (N38)

Salem Mechanical Engineering Manager (N51)

Onsite Safety Review Engineer - Salem (X15)

J. Giessner J. O'Conner G. Nagy T. Wescott General Solicitor, E. Selover (Newark, 5G)

Mark J. Wetterhahn, Esq.

Records Management (N21)

Microfilm Copy Files Nos. 1.2.1 (Salem) 2.3 (LCR S96-03)

REF: LR-N96423 STATE OF NEW JERSEY SS.

COUNTY OF SALEM L. F. Storz, being duly sworn according to law deposes and says:

I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief.

Subsc~ib~d and Sworn~ before me this c93.A.....J.. day of 'Qf((1Ylli,_. *1996 4/Vl1W4~~\

Not~ry Public~New Jersey KIMBERl YJO BROWN NOTARY. P!JBUC OF NEW JERSEY My Commission expires on My Comm1ss1on Expires April 2!, 1998