JPN-96-005, Forwards Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode

Forwards Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode

ML20097A183
Person / Time
Site:	FitzPatrick
Issue date:	02/01/1996
From:	William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097A185	List: JPN-96-005, Forwards Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20097A192 ML20097A227
References
JPN-96-005, JPN-96-5, NUDOCS 9602050199
Download: ML20097A183 (2)

Text

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123 Main Street i White Plains. New York 10601 914 681-6840

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4# Authority c"*'" * "'o" - i February 1,1996 .

JPN-96-005 1 U. S. Nuclear Regulatory Commission J ATTN: Document Control Desk  ;

Mail Station P1-137 Washington, DC 20555 t i

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Regarding Inservice Leak and Hydrostatic Testina Oneration (JPTS-95-004)

REFERENCE:

LER-95-007, Enforcement Discretion Required for Control Room Ventilation Operability Requirements, dated April 20,1995, (JAFP 0190) to NRC Document Control Desk from Harry P. Salmon, Jr.

Dear Sir:

This application for an amendment to the James A. FitzPatrick Technical Specifications (TS) proposes to allow reactor coolant system pressure tests to be performed while remaining in the Cold Shutdown Mode. Primary containment integrity is not required in the Cold Shutdown Mode thus allowing unrestricted access to the primary containment for the performance of inspections. The changes will also allow outage activities on other systems to continue. The changes, with minor exceptions, adopt Special Operations Section 3.10.1,

" Inservice Leak and Hydrostatic Testing Operation," from Standard Technical Specifications (STS), NUREG 1433. Minor exceptions are required to ensure consistency within FitzPatrick TS, reflect differences between FitzPatrick TS and STS, and ensure the same level of ECCS redundancy afforded by STS during pressure testing. These exceptions will be eliminated when the FitzPatrick TS are converted to STS.

Editorial changes to improve the table of contents, relocate text, use consistent terminology, and reflect the addition of new TS pages are also proposed.

The Authority committed to submit this amendment application in LER-95-007 (Reference) to eliminate the need for future requests for enforcement discretion during reactor coolant system pressure tests. Approval of this amendment application will eliminate the need for future requests because TS requirements which do not provide any safety benefit will not be applicable during pressure tests. In addition, approval of this amendment application will significantly lower cost by reducing critical path time during outages.

9602050199 960201 i PDR ADOCK 05000333 j P PDR 050045 g

• t GE Nuclear Energy (GE) reviewed this amendment application for conformance with 10 CFR 50.92, and for technical adequacy and consistency with FitzPatrick TS and STS.

GE's review did not result in any technical concerns, and GE concluded that this amendment application does not involve a significant hazards consideration.

The signed original of the Application for Amendment to the Operating License is enclosed for filing. Attachment I contains the proposed new Technical Specification pages, and Attachment 11is the Safety Evaluation for the proposed changes. A markup of the affected Technical Specification pages is included as Attachment lli.

There are no commitments contained in this submittal.

A copy of this application and the associated attachments are being provided to the designated New York State official in accordance with 10 CFR 50.91.

The Authority requests approval of this amendment application by July 1996, in order to support preparations for the next refueling outage.

If you have any questions, please contact Ms. C. D. Faison.

Very truly yours, f

. J. Cahill, Jr.

Chief Nuclear Officer cc: Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U. S. Nuclear Regulatory Commission P.O. Box 136

' Lycoming, NY 13093 Mr. C. E. Carpenter, Jr., Project Manager Project Directorate I-1 Division of Reactor Projects-l/II U. S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253