JPN-95-053, Forwards Application for Amend to License DPR-59,revising TSs to Incorporate IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code
| ML20095F692 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/14/1995 |
| From: | William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20095F694 | List: |
| References | |
| JPN-95-053, JPN-95-53, NUDOCS 9512190184 | |
| Download: ML20095F692 (2) | |
Text
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123 Main Street White Plains, New York 106t)1 j y
~ 914-6816840 914 287-3309 (FAX) 4 N
William J. Cahill, Jr.
Chief Nuclear Officer g
December 14,1995 JPN-95-053 l
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C. 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant a
Docket No. 50-333 Proposed Change to the Technical Specifications ASME Section XI Surveillance Testina (JPTS-93-003)
Dear Sir:
This application for an amendment to the James A. FitzPatrick Technical Specifications (TS) proposes to incorporate the inservice testing requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code. The proposed change adds a new surveillance requirement,4.0 E, which refers to the requirements of Section XI of the ASME B&PV E
Code and Addenda established by 10 CFR 50.55a(f). Ancillary changes are also required since the proposed Specification 4.0.E replaces the surveillance testing requirements of safety related pump and motor operated valves and extends the surveillance testing frequency of other components from once every month, to coincide with the ASME Section XI requirements.
Quarterly pump and valve testing is required by the 1980 Edition of the ASME Code and the applicable sections of 10 CFR SC,55a. These changes will result in an appropriate test interval for assuring compoxnt operability, will not significantly impact system reliability, and will make the FitzPatnck Plant Technical Specifications more
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consistent with Standard Technical Specifications.
Editorial changes have been made on the pages being revised by the incorporation of ASME Section XI. These changes include correction of typographical / punctuation errors and editorial clarifications.
The signed original of the Application for Amendment to Operating License is enclosed for filing. The proposed change to the Technical Specifications is Attachment I to this Application for Amendment to the Operating License. The Safety Evaluation for the proposed char.ge is included as Attachment 11. A markup of the affected Technical Specification pages is included as Attachment 111.
- A copy of this a lication and the associated attachments are being provided to the designated; fgr8 S} ate official in accordance with 10 CFR 50.91.
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I 9512190184 951214 p
PDR ADOCK 05000333
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If you have any questions, please contact C. D. Faison.
Very truly yours l_
William J. CaYl, Jr.
Chief Nuclear Officer att: 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. C. E. Carpenter, Project Manager 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
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