ML11119A230
| ML11119A230 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/25/2011 |
| From: | John Carlin Ginna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11119A230 (4) | |
Text
John Carlin Site Vice President CENG a joint venture of Constelbao
"'eDF Energy 10%
R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.5200 585.771.3943 Fax iohn.carlin(.acenqllc.com April 25, 2011 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk R.E. Ginna Nuclear Power Plant Docket No. 50-244 Commitment Change Associated with the Pressure at which to Perform Two Structural Integrity Tests During Period of Extended Operation
References:
(1)
U.S. NRC, Safety Evaluation Report, "Related to the License Renewal of R.E.
Ginna Nuclear Power Plant," NUREG-1786, May 2004. (ML041400502)
(2)
Letter from R. C. Mecredy, RG&E, to NRC Document Control Desk,
Subject:
RAI Response Clarifications and Commitment Schedule Update, dated July 30, 2003.
(3)
U.S. NRC, Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995. (ML003740058)
(4)
ANS, "American National Standard for Containment System Leakage Testing Requirements," ANSI/ANS-56.8-1994, August 4, 1994.
In May 2004, the NRC issued the Safety Evaluation Report NUREG-1786 regarding the License Renewal of the R.E. Ginna Nuclear Power Plant (Reference 1). On p. 3-250 of the aforementioned report, the NRC found that the applicant's commitment to perform two Structural Integrity Tests (SITs) in conjunction with Integrated Leakage Rate Tests (ILRTs) during the extended period ofoperation as described in letter dated July 30, 2003, from RG&E to the NRC (Reference 2), to be acceptable.
NUREG-1786, p. A-4, and the letter dated July 30, 2003, p. 8, described the commitment as performing the two SITs at the design pressure of the containment.
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Document Control Desk April 25, 2011 Page 2 of 2 The R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) Technical Specifications, Section 5.5.15, "Containment Leakage Rate Testing Program," references NRC Regulatory Guide (R.G.) 1.163 (Reference 3). In turn, R.G. 1.163 references ANS Standard ANSI/ANS-56.8-1994 (Reference 4). This latter standard specifies that a Type A ILRT be performed at a pressure that shall be no less than 0.96 Pac nor exceed Pd. Ginna LLC is revising the commitment to perform the two SITs in conjunction with two Type A ILRTs as set forth in R.G. 1.163 and ANSI/ANS-56.8-1994. Attachment 1 provides the revised regulatory commitment made in this letter.
If you should you have any questions regarding this submittal, please contact Mr. Thomas Harding at (585) 771-5219 or Thomas.Harding Jr@Constellation.corn.
S y
ours, : Regulatory Commitment Revision cc:
W.M. Dean, NRC D. V. Pickett, NRC Resident Inspector, NRC
ATTACHMENT 1 Regulatory Commitment Revision
ATTACHMENT 1 Regulatory Commitment Revision The following table identifies those actions committed to by Ginna LLC in this document. Any other statements made in this licensing submittal are provided for informational purposes only and are not to be considered regulatory commitments. Please direct any questions you have in this matter to Mr. Thomas Harding at (585)771-5219.
COMMITMENT COMPLETION DATE Perform two structural integrity 2011 tests during period of extended and operations at a pressure that is 2021 consistent with the ILRT Type A (2026 if 15 year frequency is methodology set forth in R.G.
requested/approved) 1.163.