ML20154Q840
| ML20154Q840 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/27/1988 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20154Q843 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-2.K.3.13, TASK-2.K.3.27, TASK-TM GL-84-23, JPN-88-025, JPN-88-25, NUDOCS 8806070141 | |
| Download: ML20154Q840 (2) | |
Text
123 Main Street White Plains, New York 10601 914 C816240
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May 27,1988 JPN-88-025 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station PI-137 Washington, D.C. 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Regarding Reactor Vessel Water Letel Instrumentation (JPTS-83-014)
REFERENCE:
1.
NRC letter, P. J. Polk to L. W. Sinclair (PASNY), dated February 26, 1982, concerning the issuance of Amendment No. 67 to the FitzPatrick Technical Specificationr
Dear Sir:
This application for an amendment to the James A.
FitzPatrick Technical Specifica-tions proposes changes resulting from modifications to the reactor vessel water level instrumentation system. In accordance with the requirements of Regulatory Guide 1.97 and Generic Letter 84-23, change to the instrumentation system are made to reduce instrument errors resulting from post-accident containment heat-up and to increase the redundancy and reliability of Control Room indication.
Included with this application are additional changes to the Technical Specification which remove obsolete reactor vessel water level instrument setpoints. Currently, two sets of setpoints are contained in the Specifications. The first set, consisting of the original "indicated level" setpoints, is referenced to the boMara of the steam separator skirts (the original instrument zero). The second set is referenced to the tcp of active fuel (TAF).
The "indicated level" setpoints are to be deleted. TAF will remain the only reactor vessel water level reference point. Reference I amended the Technical Specifications to estab-lish new reactor vessel level setpoints as required by NUREG-0737 Item II.K.3.27. This was accomplished by referencing TAF as the new instrument zero. Amendment No. 67 added new setpoints (the second set as stated above) to several tables as parenthetical phrases located after the original setpoints.
Plant procedures, training programs, control room and local instrumentation have been or will be changed to reflect the new setpoints. The original setpoints were rendered obsolete following the complete implementation of the setpoints referenced to TAF.
A change is also being made to reflect a p ant modification performed to meet the requirements of NUREG-0737 Item II.K.3.13. The modification to the RCIC svstem replaced the turbine trip at high reactor water level with a recoverable steam line isola-tion. The Authority did not consider the change to the Technical Specifications necessary at that time, but is now making the change for clarification.
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These changes to the Technical Specifications are required for the startup following the 1988 refueling outage. Startup is currently scheduled for November 7,1988. The Authority requests that this application be approved by October 31,1988.
Enclosed for filing is the signed original of a document entitled "Application for Amendment to Operating License," with Attachments I and 11 thereto, comprising a state-ment of the proposed changes to the Technical Specifications and the associated Safety Evaluation.
In accordance with 10 CFR 170.12, a check in the amount of $150.00 is enclosed as payment of the application fee for the review of the proposed changes to the Technical Specifications.
In accordance with 10 CFR 50.91, a copy of this application and the associated attachmente are being provided to th. &signated New York State official.
Should you or your staff have any questions regarding the proposed changes, please contact hir. J. A. Gray, Jr. of my staff.
Very truly yours.
John C. Brons Executive Vice President Nuclear Generation m
cc:
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 hir. Harvey Abelson Project Directorate I-I Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission hiail Stop 14 B2 Washington, D.C. 20555 hir. J. D. Dunkelberger, Director Technology Development Programs New York State Energy Office Two Rockefeller Plaza Albany, New York 12223
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