JPN-93-028, Forwards Application for Amend to License DPR-59,changing TS Table 4.7-2, Exception to Type C Tests, to Add Sys Numbers to Valve Identification Numbers for Seven CRD Containment Isolation Valves
| ML20035F427 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/15/1993 |
| From: | Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20035F428 | List: |
| References | |
| JPN-93-028, JPN-93-28, NUDOCS 9304210277 | |
| Download: ML20035F427 (2) | |
Text
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& Authority Executwe vice Presicent Nuclear Generation April 15,1993 JPN-93-028 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C. 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Revision of Table 4.7-2 (JPTS-89-038 and JPTS-92-0091
REFERENCE:
- 1. NRC letter, D. LaBarge to J. C. Brons, dated November 14,1989, ([[::JAF-89-379|JAF-89-379]]) transmits Amendment 143.
Dear Sir:
This application for an amendment to the James A. FitzPatrick Technical Specifications makes four changes to Table 4.7-2, " Exception to Type C Tests." The first adds system numbers to the valve identification numbers for seven control rod drive containment isolation valves to be consistent with valve identifiers in the Technical Specifications, and clarifies the penetration arrangements. There is no change to the valves themselves or to the penetrations. The second change removes valves 10MOV-57 and 10MOV-67 from the table because they are not containment isolation valves as defined by the current FitzPatrick licensing basis. The third change adds valves 10RHR-729A and 10RHR-729B to the table to exempt them from Type C testing based on the current FitzPatrick licensing basis. Fourthly, three errors introduced in Amendment 143 (Reference 1) are corrected.
The signed original of the Application for Amendment to Operating License is enclosed for filing. Attachments I and ll to this application contain the proposed changes to the Technical Specifications and the associated Safety Evaluation.
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A copy of this application and the associated attachments are being provided to the designated New York State officialin accordance with 10 CFR 50.91.
1 If you have any questions, please contact Mr. J. A. Gray, Jr.
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Very truly_yours, S
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Ralph E. Beedle 1
l att: as stated I
cc: Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector l
U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Brian C. McCabe l
Project Directorate 1-1 Division of Reactor Projects - 1/II e
U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 6
l Ms. Donna Ross l
New York State Energy Office 2 Empire State Plaza l
16'" Flw Albany, NY 12223 1
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