ML17264A304
| ML17264A304 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/19/1995 |
| From: | Andrea Johnson NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M93827, NUDOCS 9512220191 | |
| Download: ML17264A304 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 December 19, 1995 5o -Zgg Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
TELECONFERENCE BETWEEN NRC AND ROCHESTER GAS AND ELECTRIC CORPORATION AND MESTINGHOUSE ON DECEMBER 12, 1995 (TAC NO.
M93827)
Dear Dr. Mecredy:
The NRC staff held discussions with Rochester Gas and Electric Corporation (RG&E) and Mestinghouse representatives by teleconference on December 12, 1995, with regard to RG&E's submittal of October 11, 1995, which provided a
revised pressurized thermal shock (PTS) assessment of the R.
E. Ginna Nuclear Power Plant (Ginna) reactor vessel for the staff to review.
The staff previously met with RG&E on May 16, 1995, to discuss the staff's generic PTS assessment which included the Ginna reactor vessel.
The staff's analysis used a generic mean value for the chemistry and large margin terms to account for potential variability of chemistry (copper and nickle) determined from generic data.
The staff's assessment indicated that the Ginna reactor vessel would be projected to reach the PTS screening criteria in 7 effective full-power years (about 2003).
The revised October ll, 1995, PTS submittal was a result of the licensee's commitment to include the test results from their surveillance program that
'could demonstrate that the PTS screening criteria would not be exceeded at the expiration of its license (EOL) in 2009.
The staff initiated the subject teleconference to inform the licensee of the status of the staff's review.
The licensee's current assessment uses plant-specific material data which indicates that the Ginna reactor vessel will be below the PTS screening criteria in 10 CFR 50.61 at the EOL.
The staff indicated that its review of the RG&E assessment could not be completed until the information requested in a Request for Additional Information dated December 11, 1995, is received.
However, the staff discussed with the licensee its preliminary evaluation of the surveillance data that was provided in the October ll, 1995, submittal.
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R. Mecredy The staff's preliminary evaluation used:
(a) generic values of copper and initial reference temperature, (b) the margin value recommended in Regulatory Guide (RG) 1.99, Revision 2, and (c) the ratio procedure recommended in RG 1.99, Revision 2 for surveillance data.
This preliminary evaluation indicates that the Ginna reactor vessel would be below the PTS screening criteria in 10 CFR 50.61 at the expiration of its license.
Using generic values results in a more conservative assessment than the licensee's assessment.
Sincerely, Docket No. 50-244 cc:
See next page F46
, Project Manager QTlen R. Johnso P oject Direct ate I-1 i 'sion of actor Pr ffic uclear Reac D
ojects - I/II 0
tor Regulation
December 19, 1995 R. Hecredy The staff's preliminary evaluation used:
(a) generic values of copper and initial reference temperature, (b) the margin value recommended in Regulatory Guide (RG) 1.99, Revision 2, and (c) the ratio procedure recommended in RG 1.99, Revision 2 for surveillance data.
This preliminary evaluation indicates that the Ginna reactor vessel would be below the PTS screening criteria in 10 CFR 50.61 at the expiration of its license.
Using generic values results in a more conservative assessment than the licensee's assessment.
Sincerely, ORIGINAL SIGNED BY'ocket No. '50-244 Allen R. Johnson, Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of.Nuclear Reactor Regulation cc:
See next page DISTRIBUTION, c-Docket-Fi1 e PUBLIC PDI-1 Reading SVarga LHarsh
- See previous concurrence DOCUMENT NAME:
G: iGINNAI,G193827. LTR To receive e copy of this document, indicate in the box: "C" Copy without enciosures "E" ~ Copy with enclosures "N" ~ No copy OFFICE LA:PDI-NAME SLitt DATE 12/l /95
- BC:EMCB JStrosnider PM:PDI-1 AJohnso
- sm 12/18/95 12/
/9 OFFICIAL RECORD COPY D: PDI-1 LMarsh 12/t
/95 12/
/95
Dr. Robert C. Mecredy R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior Resident Inspector R.E.
Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. Williams Valentino, President New York State
- Energy, Research, and Development Authority 2 Rockefeller Plaza
- Albany, NY 12223-1253 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston 5 Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator.,
Monroe County Office of Emergency Preparedness 111 West Fal-1
- Road, Room ll Rochester,.
NY
" 14620