ML021650437

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Use of EPRI Report TR-113594 for Evaluating Generic Letter 96-006 Waterhammer Issues at R. E. Ginna Nuclear Power Plant
ML021650437
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/07/2002
From: Mecredy R
Rochester Gas & Electric Corp
To: Clark R
Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-96-006, TAC M96814, TR-113594
Download: ML021650437 (2)


Text

I A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORATION

  • 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001
  • 585 546-2700 www.rge.com ROBERT C. MECREDY Vice President June 7 2002 Nuclear Operations Mr. Robert L. Clark Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Use of EPRI Report TR-113594 for Evaluating Generic Letter 96-06 Waterhammer Issues R. E. Ginna Nuclear Power Plant Docket No. 50-244

References:

(1)

Letter from R.L. Clark, NRC, to R.C. Mecredy, RG&E,

Subject:

Electric Power Research Institute (EPRI) Report TR-1 13594, "Resolution of Generic Letter 96-06 Waterhammer Issues, " Volumes 1 and 2 - R.E.

Ginna Nuclear Power Plant (TAC No. M96814), dated April 26, 2002.

(2)

Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,

Subject:

Response to Request for Additional Information (RAI) Related to Generic Letter 96-06 (TAC No. M96814), dated July 21, 1998.

(3)

Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,

Subject:

Response to Generic Letter 96-06, "Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions,"

dated September 30, 1996.

Dear Mr. Clark:

In Reference (1), the Nuclear Regulatory Commission (NRC) notified Rochester Gas and Electric Corporation (RG&E) that they had determined that EPRI Report TR-13594 was acceptable for use in evaluating Generic Letter (GL) 96-06 waterhammer issues within the limits of the report and the NRC safety evaluation (SE). RG&E had previously stated that it intended to use this EPRI guidance in Reference (2) as part of the resolution to GL 96-06. As such, the NRC stated in Reference (1):

We request that you complete actions to address GL 96-06 and submit the information referred to in Section 3.3 of the NRC SE by July 30, 2002. Please contact us to make alternate arrangements if you are unable to meet this schedule.

10004851

Use of EPRI Report TR-113594 for GL 96-06 Page 2 of 2 The purpose of this letter is to provide the NRC with the schedule for completing the remaining required actions of GL 96-06 for Ginna Station.

RG&E plans to complete and submit the analyses necessary to fully implement EPRI Report TR-113594 by November 30, 2002. The primary reason for this extending the analysis completion date beyond what was requested by the NRC is that RG&E also plans to complete preparation of an application to extend the operating license of Ginna Station later this summer.

The resources that are helping to prepare the license extension submittal are the same as those necessary to do the analyses in support of implementing the EPRI methodology. However, as described in References (2) and (3), RG&E does not believe that waterhammer is a concern for the containment recirculating fan coolers (CRFCs) and the associated service water piping and supports at Ginna Station and does not anticipate that any modifications will be required as a result of these analyses.

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.

Any questions concerning this issue should be directed to Mr. Peter Bamford, Manager, Primary!

Reactor Systems at (585) 771-3832.

Very truly yours, Executed on June 7, 2002 Robert C. Mecredy MDF_254 xc:

Mr. Robert L. Clark (Mail Stop O-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 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector 1000485