ML030690514
| ML030690514 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/03/2003 |
| From: | Mecredy R Rochester Gas & Electric Corp |
| To: | NRC/SECY/RAS |
| References | |
| Download: ML030690514 (4) | |
Text
RZ An Energy East Company ROCHESTER GAS AND ELECTRIC CORPORATION ° 89 EAST AVENUE, ROCHESTER, NY 14649-0001 ° 585 546-2700 www rge corn ROBERT C MECREDY VICE PRESIDENT NUCLEAR OPERATIONS March 3, 2003 Secretary Office of the Secretary of the Commission U.S. Nuclear Regulatory Commission ATI'N: Rulemakings and Adjudications Staff Washington, DC 20555
Subject:
Response to Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors R. E. Ginna Nuclear Power Plant Docket No. 50-244
References:
(1)
Letter from Samuel J. Collins, NRC, to Robert C. Mecredy, RG&E,
Subject:
Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors, dated February 11, 2003
Dear Sir:
In Reference (1), the Nuclear Regulatory Commission (NRC) issued an Order, effective immediately, which modified the license for the R.E. Ginna Nuclear Power Plant under the criteria of 10 CFR 2.202. In accordance with the Order, Rochester Gas and Electric Corporation (RG&E) must respond to the Order within 20 days with a written answer under oath and affirmation addressing the following:
- 1.
Answer the Order as either consenting or requesting a hearing as described in Section V.
- 2.
Identify if the licensee is unable to comply with any of the requirements of Section IV or if compliance with any requirements of Section IV is unnecessary.
RG&E has evaluated the requirements contained within Section IV of the Order and has determinated that it will comply as specified. Consequently, RG&E consents to entry of the Order. Attachment A lists those regulatory commitments which result from consenting to this Order. It should be noted that since RG&E plans to replace the reactor vessel head during the upcoming fall 2003 refueling outage, the calculated susceptibility category for the subsequent operating cycle will be "low."
1000683
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. Brian Flynn, Manager, Primary I Reactor Systems at (585) 771-3734.
Executed on March 3, 2003 Very truly yours, Robert C. Mecredy MDF_283
xc:
Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Assistant General Counsel for Materials Litigation and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 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
Attachment A List of Regulatory Commitments The following table identifies those actions committed to by Rochester Gas & Electric (RG&E) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Mr. Brian Flynn, Manager, Primary/ Reactor Systems at (585) 771-3734.
DUE DATE Calculate the susceptibility category of the Ginna Station Prior to shutdown for each reactor pressure vessel head per Section IV.A and IV.B of refueling outage (RFO).
the Order dated February 11, 2003.
Perform inspections of the reactor vessel pressure head per As required.
Section IV.C of the Order dated February 11, 2003.
Submit report to NRC detailing the inspection results.
Within 60 days after returning plant to operation.
Perform visual inspections during each RFO to identify Each RFO.
potential boric acid leaks from pressure-retaining components above the reactor pressure vessel head.
Submit report to NRC detailing the inspection results if Within 60 days after returning leaks are found.
plant to operation.
If boron deposits are discovered on the surface of the reactor Prior to returning plant to pressure vessel head or related insulation, perform operation.
inspections of the affected head surface and penetrations appropriate to the conditions found to verify the integrity of the affected area and penetrations.
Submit report to NRC detailing the inspection results.
Within 60 days after returning plant to operation.