ML032200361
| ML032200361 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/01/2003 |
| From: | Mecredy R Rochester Gas & Electric Corp |
| To: | Arrighi R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML032200361 (3) | |
Text
'3/4VW R
Sri Always At Your Service Robert C. Mecredy Vice President Nuclear Operations August 1, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Russell Arrighi (Mail Stop 0-1 lFl)
Office of Nuclear Reactor Regulation Washington, D.C. 20555-0001
Subject:
Supplemental Information Regarding July 30, 2003 Correspondence R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Arrighi:
By letter dated July 30, 2003, RG&E provided the annual Supplement to the Ginna Station License Renewal Application, per 10CFR54.21(b).
Additional information is being provided in the enclosure to clarify this submittal.
I declare under penalty of perjury under the laws of the United States of America that I am authorized by RG&E to make this submittal and that the foregoing is true and correct.
Very truly yours, Executed on August 1, 2003 Robert C. Mecredy Enclosure An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com iI da%----
3e An gy Eam t Company
'L - e-cc:
Mr. Russ Arrighi, Project Manager (Mail Stop 0-1 IFI)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Robert L. Clark (Mail Stop 0-8-C2)
Project Directorate I Division of Licensing Project Management Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. NRC Ginna Senior Resident Inspector Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
ENCLOSURE - LRA SUPPLEMENT CLARIFICATIONS Item 1 of the enclosure to the LRA supplement stated hat an SI accumulator fill system had been installed. It should be noted that all piping, fittings, and valves associated with that modification are covered by Table 2.3.2-1, component groups "pipe" and "valve body".
The following information should be added to 2.3.2.1 of the LRA (end of the third paragraph of the system description): "A low flow fill system is also provided between the RWST and the SI accumulators."
Item 2 of the enclosure stated that a cross-connect had been installed in the spent fuel pool cooling system. It should be noted that all piping, fittings, and valves associated with this modification are Table 2.3.3-3, component groups "pipe" and "valve body". The following information should be added to 2.3.3.3 of the LRA (end of the third paragraph of the system description): "A cross-tie was also installed to allow operation of the "A" spent fuel pool pump with the "B" spent fuel heat exchanger."
Item 5 of the enclosure provided an UFSAR Supplement regarding the TLAA described in Section 4.3.5, "Reactor Vessel Nozzle-to-Vessel Weld Defect." The following two paragraphs should be added to the end of that supplement description:
"It has been determined that the design basis transient set for Ginna Station remains bounding for the period of extended operation. The number of design cycles for heatups and cooldowns, and therefore vessel pressurizations, is 200. Since irradiation effects at the flaw location are negligible and fatigue crack growth is insignificant even for 1200 cycles of pressurization, the flaw will remain stable and of no structural significance for the period of extended operation.
Since the number of pressurizations during the period of extended operation are less than that analyzed in the fatigue crack growth analysis, the amount of flaw growth for the period of extended operation is bounded by the fracture mechanics analysis performed in 1989."