JPN-96-003, Forwards Application for Amend to License DPR-59,revising TS to Extend Instrumentation & Miscellaneous Surveillance Test Intervals to Support 24-month Operating Cycles,Per GL 91-04. Proprietary Repts Also Encl.Proprietary Repts Withheld

Forwards Application for Amend to License DPR-59,revising TS to Extend Instrumentation & Miscellaneous Surveillance Test Intervals to Support 24-month Operating Cycles,Per GL 91-04. Proprietary Repts Also Encl.Proprietary Repts Withheld

ML20097J661
Person / Time
Site:	FitzPatrick
Issue date:	01/25/1996
From:	William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19311B958	List: JPN-96-003, Forwards Application for Amend to License DPR-59,revising TS to Extend Instrumentation & Miscellaneous Surveillance Test Intervals to Support 24-month Operating Cycles,Per GL 91-04. Proprietary Repts Also Encl.Proprietary Repts Withheld ML20097J666 ML20097J669
References
GL-91-04, GL-91-4, JPN-96-003, JPN-96-3, NUDOCS 9602050091
Download: ML20097J661 (2)

Text

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123 Main Street 4 I White Plains, New York 10601

, 914 681 6840 914-287-3309 (FAX) i William J. Cahill, Jr.

80 % Chief Nuclear Officer January 25,1996 JPN-96-003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 l Washington, DC 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Changes to the Technical Specifications Regarding Extension of instrumentation and Miscellaneous Surveillance Test Intervals to Accommodate 24-Month Oneratina Cveles (JPTS-95-001G)  :

Reference:

1. NRC Generic Letter 91-04, " Changes in Technical Specification Surveillance intervals to Accommodate 24-Month Fuel Cycle," dated April 2,1991.

Dear Sir:

i This application for an amendment to the James A. FitzPatrick Nuclear Power Plant Technical Specifications proposes to extend instrumentation and miscellaneous surveillance test intervals to support 24-month operating cycles. The proposed changes follow the guidance of Generic Letter (GL) 91-04 (Reference 1). Approval of these changes will eliminate the need to execute mid-cycle outages to conduct these surveillance tests. The Authority requests approval of these proposed changes to support implementation upon startup from the Reload 12/ Cycle 13 refueling outage (Currently scheduled for Fall 1996).

Additionally, this application proposes: (1) revision of the Trip Level Settings for Emergency Bus Loss of Voltage and Degraded Voltage Instrumentation, (2) revision of the Reactor Protection System (RPS) Normal Supply Electrical Protection Assembly (EPA) Undervoltage l Trip Setpoint, and (3) editorial revisions, clarification and Bases changes. The instrumentation subject to this application involves the following: RPS, Primary Containment Isolation Systems, Core and Containment Cooling Systems, Control Rod Blocks, Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip, Accident Monitoring and Remote Shutdown, Radiological Effluent Technical Specification (RETS) monitoring, and safety-related plant ventilation systems. Non-instrumentation changes involve surveillance frequency notations, Residual Heat Removal (RHR) cross-tie valve position verification, and instrument line excess flow check valve testing.

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4 Extended surveillance intervals are identified in the proposed Technical Specifications as being performed "once per 24 months" or "R" for instrumentation located in tables.

Surveillance requirements that are to remain at an 18 month surveillance interval are identified as being performed "once per 18 months" or "18M" for instrumentation located in tables. This terminology is consistent with the guidance provided in GL 91-04 and BWR Standard Technical Specifications.

The signed original of the Application for Amendment to the Technical Specifications is enclosed for filing. Attachments I and lll to this application contain the proposed changes to the Technical Specifications and a mark-up of the current Technical Specifications pages, respectively. Attachment ll contains the associated Safety Evaluation. Attachment IV contains a copy of References that are not docketed for either the FitzPatrick or Indian Point Unit 3 plants. The methodology used in the Instrument Drift Evaluations was developed for the Authority by contract personnel from Raytheon Nuclear, Inc. (Raytheon), formerly Ebasco Services Inc. and is proprietary to Raytheon. For these references, a Proprietary and a Non-Proprietary copy of the Reference are included in Attachment IV, along with an Affidavit signed by Raytheon that addresses the considerations listed in 10 CFR 2.790(b)(4).

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

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

Very truly yours, m.' -

William J. Cahill, Jr.

Chief Nuclear Officer cc: Attachments I,11, lit only: All Attachments to:

Regional Administrator Mr. C. E. Carpenter, Project Manager U.S. Nuclear Regulatory Commission Project Directorate I-1 475 Allendale Road Division of Reactor Projects - l/II King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Office of the Resident inspector Washington, DC 20555 U.S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, NY 13093 Mr. F. William Valentio, President New York State Energy, Research and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253