ML20097J666

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Application for Amend to License DPR-59,revising TS to Extend Instrumentation & Miscellaneous Surveillance Test Intervals to Support 24-month Operating Cycle
ML20097J666
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 01/25/1996
From: William Cahill
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19311B958 List:
References
NUDOCS 9602050093
Download: ML20097J666 (1)
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Text

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION in the matter of )

NEW YORK POWER AUTHORITY ) Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE The New York Power Authority requests an amendment to the Technical Specifications contained in Appendix A to Facility Operating License No. DPR-59 for the James A.

FitzPatrick Nuclear Power Plant. This application is filed in accordance with Section 10 CFR 50.90 of the Nuclear Regulatory Commission's regulations.

This application proposes the following changes to the Technical Specifications: (1) extend instrumentation and miscellaneous surveillance test intervals to support a 24-month operating cycle, (2) revise the Trip Level Settings for the Emergency Bus Loss of Voltage and Degraded Voltage Instrumentation, (3) revise the Reactor Protection System (RPS) Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint, and (4) incorporate miscellaneous editorial, clarification and Bases changes. The proposed changes eliminate the need to execute mid-cycle outages to conduct surveillance tests and follow the guidance of Generic Letter 91-04.

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 j 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 Specification pages, respectively. Attachment il 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.

New Yerk Power Authority

. I William J. Cahill, Jr.

Chief Nuclear Officer STATE OF NEW YORK COUNTY OF WESTCHESTER Subscribed and sworn to before me thisM day of fg 1996.

bu& AG~L N'otary Public GERALDINE STRAND Notory Putdic, State of New Wet No.4991272 9602050093 960125 Quellflodin Wessesseer PDR ADOCK 05000333 Commission Emperse Jan. 27,1 P PDR f

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, 91 M816,840 414 -287- 3304 . FA N William J. Cahill. Jr.

4# Authority c- ~ ~ c-January 25,1996 JPN-96-003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 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:

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 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.

OM D/ 1 ff

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 ill to this application contain the proposed changes to the Technical Specifications and a mark-up of the current Technical Specifications pages, respectively. Attachment 11 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 contra 1. personnel from Raytheon Nuclear, Inc. (Raytheon), formerly Ebasco Services Inc. and is proprietary to Raythson. 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, j n.: .

William J. Cahill, Jr.

Chief Nuclear~ Officer cc: Attachments I, ll, 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 - 1/ll 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

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e BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of )

NEW YORK POWER AUTHORITY ) Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE The New York Power Authority requests an amendment to the Technical Specifications contained in Appendix A to Facility Operating License No. DPR-59 for the James A.

FitzPatrick Nuclear Power Plant. This application is filed in accordance with Section 10 CFR 50.90 of the Nuclear Regulatory Commission's regulations.

This application proposes the following changes to the Technical Specifications: (1) extend instrumentation and miscellaneous surveillance test intervals to support a 24-month operating  ;

cycle, (2) revise the Trip Level Settings for the Emergency Bus Loss of Voltage and I Degraded Voltage instrumentation, (3) revise the Reactor Protection System (RPS) Normal Supply Electrical Protecticn Assembly Undervoltage Trip Setpoint, and (4) incorporate miscellaneous editorial, clarification and Bases changes. The proposed changes eliminate the need to execute mid-cycle outages to conduct surveillance tests and follow the guidance of Generic Letter 91-04.

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 111 to this application contain the proposed changes to  ;

the TechnicaLSpecifications and a mark-up of the current Technical Specification pages, l respectively. Attachment Il 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. i l

New York Power Authority

. /

William J. C ill, Jr.

Chief Nuclear Officer STATE OF NEW YORK COUNTY OF WESTCHESTER Subscribed and sworn to before me this.1( day of [nwg 1996.

Rahk f(otary Public '

GERALDINE STRAND Notary Putdic. State of New Wrk No.4991272 Quellfled in Wesecheseer

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