JPN-94-050, Forwards Application for Amends to License DPR-59,proposing Changes to TS by Extending Functional Test Intervals & Allowable out-of-service Times,Removing APRM Downscale & Response Time Values & Incorporating Miscellaneous Changes
| ML20073L061 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/03/1994 |
| From: | William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20073L065 | List: |
| References | |
| JPN-94-050, JPN-94-50, JPTS-90-010-22, JPTS-90-10-22, NUDOCS 9410120300 | |
| Download: ML20073L061 (2) | |
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- 123 Man Street 1
White Plains. New York 10601
- 914 681 6200
- b NewYorkPower 4# Authority October 3,1994 JPN-94-050 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant i
Docket No. 50-333 Proposed Changes to the Technical Specifications Regarding Instrumentation Surveillance Test Intervals, Allowable Rut-of-Servira Times. and Other Changes _(JPTS-9D-010)
Dear Sir:
This application for an amendment to the James A. Fitzpatrick Technical Specifications proposes an extension in the functional test intervals and allowable out-of-service times for most of the instrumentation subject to the requirements of the Technical Specifications.
These changes are based on NRC approved Licensing Topical Reports prepared under the i
direction of the BWR Owners Group. The changes will enhance plant safety by reducing the potential for test related reactor scrams, excessive test cycles on equipment, and operator errors.
Additionally, the application proposes the following changes to the instrumentation sections: (1) remove the APRM downscale scram function, (2) remove the instrument response time values in accordance with Generic Letter 93-08, and (3) incorpcrate miscellaneous changes involving editorial revisions, clarification improvements, and revisions 3
to conform the Technical Specifications to the actual plant design. The instrumentation subject to this application involves the following safety functions: Reactor Protection System, Primary Containment isolation Systems, Emergency Core Cooling Systems, Control Rod Blocks, and ATWS Recirculation Pump Trips.
The signed original of the Application for Amendment to Operating License is enclosed for filing. Attachments I, ll, and lll to this application contain the proposed revisions to the Technical Specifications, the associated safety evaluation, and the marked-up Technical Specification pages, respectively. A copy of this application and the associated attachments is being provided to the designated New York State official in accordance with 10 CFR 50.91.
Considering the safety benefits associated with the proposed changes, an expedited review will be appreciated. The Authority is prepared to brief the NRC reviewers on the contents of the application at a meeting scheduled at your convenience.
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9410120300 9410o3 ppf PDR ADOCK 05000333 PDR 3
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if you have any questions, please contact Mr. J. A. Gray, Jr.
Very truly yours, Y
/
i William J. Cahill, Jr.
Executive Vice President and Chief Nuclear Officer
Attachment:
as stated 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. John E. Menning Project Directorate I-1 Division of Reactor Projects-l/II U. S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Ms. Donna Ross New York State Energy Office 2 Empire State Plaza 16"' Floor Albany, NY 12223