ML17264A293
| ML17264A293 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/11/1995 |
| From: | Andrea Johnson NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M93827, NUDOCS 9512180055 | |
| Download: ML17264A293 (5) | |
Text
December 11, 1995 Mr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 f,
SUBJECT:
R.
E.
GINNA NUCLEAR POWER STATION REQUEST FOR ADDITIONAL INFORMATION PRESSURIZED THERMAL SHOCK (PTS)
ASSESSHENT FOR GINNA REACTOR VESSEL (TAC NO. M93827) u
Dear Mr. Mecredy:
8)
On May 16, 1995, the NRC staff met,with you to discuss the staff's PTS assessment of the Ginna reactor vessel,,that was documented in Attachment 2 to SECY-95-119.
At the conclusion of, this meeting you agreed to submit a revised PTS assessment, which we receivedon,October,';ll,
- 1995, and is currently under our review.
Your revised PTS assessment was to consider (1) the use of best-estimate chemistries less than the gene'ric value and (2) the use of smaller margin terms, than the values determined from generic data.
We request that a further, revised assessment that contains the requested information',(Enclosure) be, provided within 60 days of receipt of this letter.
The requirement affects nine or fewer respondents and, therefore, is not subject of Office of Management and Budget review under P.L.96-511.
Sincerely, I
ORIGINAL SIGNED BY:
Allen R. Johnson, Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
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UNITED STATES NUCLEAR REGULATORY COMMlSSlON WASHINGTON, D.C. 2055&4001 December 11, 1995 Mr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
R.
E.
GINNA NUCLEAR POWER STATION REQUEST FOR ADDITIONAL INFORMATION PRESSURIZED THERMAL SHOCK (PTS)
ASSESSMENT FOR GINNA REACTOR VESSEL (TAC NO. M93827)
Dear Mr. Mecredy:
On May 16,
- 1995, the NRC staff met with you to discuss the staff's PTS assessment of the Ginna reactor vessel that was documented in Attachment 2 to SECY-95-119.
At the conclusion of this meeting you agreed to submit a revised PTS assessment, which we received on October ll, 1995, and is currently under our review.
Your revised PTS assessment was to consider (1) the use of best-estimate chemistries less than the generic value and (2) the use of smaller margin terms than the values determined from generic data.
We request that a further revised assessment that contains the requested information (Enclosure) be provided within 60 days of receipt of this letter.
The requirement affects nine or fewer respondents and, therefore, is not subject of Office of Management and Budget review under P.L.96-511.
Sincerely, Docket No. 50-244 Allen
. Johnso
, Project Manager Proje t Dire orate I-1 Division o Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page
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. William 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 8 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 ill West Fall Road, Room ll Rochester, NY 14620
~
~
RE UEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PRESSURIZED THERMAL SHOCK ASSESSMENT FOR GINNA REACTOR VESSEL The licensee should revise their submittal in response to the following request for addi tional in for mat ion:
1)
Since the initial reference temperature data for heat 61782 shows large variability (two values at -1'F and -38'F), provide the technical basis for not utilizing the generic mean value and generic standard deviation for the initial reference temperature for B8W fabricated Linde 80 welds.
Note:
The square of the standard deviation for these values should have been determined by dividing the sum of the squares of the differences between the value and the mean value by n-1 to give an appro'ximate unbiased estimate.
2)
Provide the unirradiated drop weight test data and charpy test data for welds material fabricated from heat number 61782 weld wire.
'3)
Provide the actual chemistry data utilized in determining the best-estimate chemistry for heat number 61782 welds and the chemistry for the surveillance welds.
Identify the source of the data and the reference document.
How was the best-estimate chemistry and the chemistry for the surveillance weld determined from this data')
Identify whether the surveillance data meets the credibility criteria in Regulatory Guide 1.99, Revision 2.
Demonstrate the criteria 3.
(scatter about the best-fit line should normally be less than 28'F for welds) has been met by determining the scatter of the MT>> from surveillance data about the best-fit line described in Regulatory Position 2. 1.
Does the correlation monitor material in the capsules fall within the scatter band of the data base for the materia17 Enclosure