JAFP-10-0019, Submittal of Corrected Proposed Technical Specifications Mark-Up Page and Final Typed Format with Change Bars

Submittal of Corrected Proposed Technical Specifications Mark-Up Page and Final Typed Format with Change Bars

ML100480039
Person / Time
Site:	FitzPatrick
Issue date:	02/05/2010
From:	Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-10-0019
Download: ML100480039 (6)

Text

f Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Pete Dietrich Site Vice President

-JAF JAFP-10-0019 February 5, 2010 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

REFERENCE:

Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record (TAC No. ME2809), Corrected Technical Specification Pages James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Entergy Letter, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record, JAFP-09-0131, dated November 23, 2009

Dear Sir or Madam:

On November 23, 2009, Entergy Nuclear Operations, Inc. (Entergy) requested an amendment to the Technical Specifications (TS) for the James A. FitzPatrick Nuclear Power Plant (JAF), revising the American Society of Mechanical Engineers (ASME) Code of Record for the Fourth Inservice Testing (IST) Interval [Reference].

Subsequent to that submittal, it was identified that both the mark-up and final revised Technical Specification pages had a typographical error in the section heading. This letter resubmits the pages with the error corrected.

Since the error was contained only in the transmitted pages and not in the current Technical Specification page, the change is not marked.with a revision bar.Attachment 1 provides the corrected, proposed TS change mark-up page.Attachment 2 provides the corrected, proposed TS change final typed format with change bars.There are no new commitments made in this letter.Questions concerning this request may be addressed to Mr. Joseph Pechacek, Licensing

\Manager, at (315) 349-6766.Vol JAFP-10-0019 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.Executed on the 5h da f February, 2010.Sincerel / .)Pete Dietrich PD/JP/ed Attachments:

1. Proposed Technical Specification Change (Mark-up, Corrected)

2. Proposed Technical Specification Change (Final Typed, Corrected) cc: Mr. Samuel Collins Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 101h Floor Albany, NY 12223 Mr. Francis Murray, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 JAFP-1 0-0019 Attachment 1 Proposed Technical Specification Change (Mark-up, Corrected)

Page 5.5-6 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued)

d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following:

a. Testing Frequencies specified in Seetion X!-of the ASME Beiler anid Pressure Vessel OM Code and applicable Addenda are as follows: 5.5.7 ASME Boiler and Pressure Vessel OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly Quarterly or every 3 months ever; 6 months Every 9 months Yearly or annually Biennially or every 2 years At least ence per 31 days At least once per 92 days A* laSt. once per 184 days At l n's one. per 276 days At least once per 366 days At least once per 731 days b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; C. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued)

JAFNPP 5.5-6 Amendment 2-74 JAFP-1 0-0019 Attachment 2 Proposed Technical Specification Change (Final Typed, Corrected)

Page 5.5-6 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued)

d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.Inservice Testing Program 5.5.7 This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following:

a. Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows: ASME OM Code and applicable Addenda terminology for inservice testing activities Quarterly or every 3 months Biennially or every 2 years Required Frequencies for performing inservice testing activities At least once per 92 days At least once per 731 days b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued)

JAFNPP 5.5-6 Amendment