JAFP-07-0130, License Renewal Application, Amendment 15
| ML073320168 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/16/2007 |
| From: | Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-07-0130 | |
| Download: ML073320168 (4) | |
Text
Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 Pete Dietrich Site Vice President - JAF November 16, 2007 JAFP-07-0130 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
REFERENCE:
SUBJECT:
1.
Letter, Entergy to USNRC, "James A. FitzPatrick Nuclear Power Plant, Docket No. 50-333, License No. DPR-59, License Renewal Application," JAFP-06-0109, dated July 31, 2006 Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333, License No. DPR-59 License Renewal Application, Amendment 15
Dear Sir or Madam:
On July 31, 2006, Entergy Nuclear Operations, Inc. submitted the License Renewal Application (LRA) for the James A. FitzPatrick Nuclear Power Plant (JAFNPP) as-indicated by Reference 1.
During the NRC review of an LRA, 10 CFR54.21 (b) specifies that an applicant report changes to the current licensing basis (CLB) that materially affect the content of the LRA, includina the Updated Final Safety Analysis Report (UFSAR) supplement. In accordance with 10 CFR54.21 (b), Entergy has completed a review and determined that:
the changes identified in Attachment 1 materially affect the content of the JAFNPP LRA. deletes reference to the RHR steam condensing mode. As a result of a series of plant design changes and procedure revisions performed in accordance with 10 CFR 50.59, the steam condensing mode for the RHR system is no longer available' under any operating condition. This change affected only the system descriptions in Section 2.3.2 of the LRA as shown in Attachment 1. The change has no effect on the scoping and screening or aging management review results provided in the LRA and subsequent amendments.
Should you have any questions concerning this submittal, please contact Mr. Jim Costedio at 315-349-6358 f0g~2\\
I declare under penalty of perjury that the foregoing is true and correct. Executed on the
/4t'& day of November, 2007.
Sincerely,
-L
%_y-Y,~ sC-
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PETE DIETRICH SITE VICE PRESIDENT PD/cf Attachment cc:
Mr. N.B. (Tommy) Le, Senior Project Manager License Renewal Branch B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-11-F1 Washington, DC 20555 Mr. Samuel J. Collins, Administrator Region" I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia,-PA 19406 NRC Resident Inspector U. S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. John P. Boska, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10 th Floor Albany, NY 12223 Mr. Paul Tonko, President NYSERDA 17 Columbia Circle Albany, NY 12203-6399
JAFP-07-0130 2007 LRA Annual Update Review Results James A. FitzPatrick Nuclear Power Plant
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2007 LRA Annual Update Review Results James A. FitzPatrick Nuclear Power Plant Page 2.3-21 Revise the fourth paragraph of Section 2.3.2.1 to read:
The RHR system is a two-loop system containing two heat exchangers with-steam condenOing capability and four main system pumps. The loops are physically separated from each other. A single header cross connects the two loops, making it possible to supply either loop from the pumps in the other loop. The system discharge piping is kept in a filled condition by its keep-full pumps to minimize time delay in LPCI actuation and to avoid water hammer on pump starts.
Page 2.3-22 Delete the entire second subsection, Steam Condensing, of Section 2.3.2.1:
Steam CandenRing The RHR sytemn the steam condening mode may be opearated oi conn2junc5tion With the RCIC cosre isolations cooing (RiIC) system in case of a loso 9f the main condense as dirented by emefgency elorating me-prcedures. Duri reactor iseol.ation, reaorl Stea may be relieved to the sesine hamber, via-the relieef valve, where it is.ond-uene and subco.led. Dc ay heat6is transferred to the RHR sersie water uSing the RHR heat exChargers as direct steam condensest.
Page 2.3-31 Revise the second paragraph of Section 2.3.2.5 to read:
The ROIC system consists of a steam-driven turbine-pump unit and associated valves and piping capable of delivering make-up water to the reactor vessel. ROIC normally takes suction from the demnineralized water in the condensate storage tanks. A back-up supply is available from the suppression pool. RCIC alsoe conecptsrA to the RHR system, enablin~g RCIC alignFment to the RHR system when the RHR system operates in the steam condensing moede. RCIC injection to the vessel occurs through the feedwater line.
RCIC shares suction points and full flow test lines with H PCI.
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