ML17264A739
| ML17264A739 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/21/1996 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M96529, NUDOCS 9611250198 | |
| Download: ML17264A739 (6) | |
Text
Dr. Robert C. Hecredy~
Vice President, Nucle~Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 November 1996
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATING TO ROCHESTER GAS AND ELECTRIC COMPANY (RGKE)
LETTER DATED SEPTEMBER 13, 1996 (TAC NO. H96529)
Dear Dr. Hecredy:
By letter dated September 13,
- 1996, RGEE submitted an application to amend the Ginna Technical Specifications which pertain to reactor coolant system pressure and temperature limits and low temperature overpressure protection limits.
In order for the NRC staff to complete its review, we telefaxed the enclosed Request for Additional Information on November 14, 1996.
You responded to this request via a telefax.
Please transmit the response formally and for the record.
Sincerely, ORigiMlL SigN60 l3)':
Guy S. Vissing, Senior 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:
Docket. Fi1 e.
PUBLIC PDI-1 R/F S.
Varga J. Zwolinski S.
Bajwa S. Little G. Vissing OGC ACRS L. Doerflein, Region I DOCUMENT NAME:
G:iGINNAiH96529.RAI me,e mX esII' To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclosure "E" = Co
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LA:PDI-1 D:PDI-1 NAHE DATE GVissing/rsl SLIttla SBajwa 11/ 'jA/96 11/Q /96 11/
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 21, 1996 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATING TO ROCHESTER GAS AND ELECTRIC COMPANY (RGSLE)
LETTER DATED SEPTEMBER 13, 1996 (TAC NO. M96529)
Dear Dr. Mecredy:
By letter dated September 13,
- 1996, RGSE submitted an application to amend the Ginna Technical Specifications which pertain to reactor coolant system pressure and temperature limits and low temperature overpressure protection limits.
In order for the NRC staff to complete its review, we telefaxed the enclosed Request for Additional Information on November 14, 1996.
You responded to this request via a telefax.
Please transmit the response formally and for the record.
Sincerely, Docket No. 50-244
Enclosure:
Request for Additional.
Information cc w/encl:
See next page y S. Vissing, Senior Project Manager
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Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
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 Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston
& 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 Mr. Paul Eddy New York State Department of Public Service 3 Empire State
- Plaza, Tenth Floor
- Albany, NY 12223
c,
RE VEST FOR ADDITIONAL INFORMATION RELATING TO PRESSURE TEMPERATURE AND LOW TEMPERATURE OVERPROTECTION ISSUE Describe the basis for the copper and nickel values used (i.e., 0.25 and 0.56, respectively) for the reactor vessel circumferential weld seam SA-847.
In addition, describe how the coil-to-coil variability in the amount of copper in the filler wire is accounted for.
It appears from Table 5-4A of WCAP-14684 that the copper and nickel values used for the Ginna surveillance program weld metal are 0.236 and 0.517 respectively.
In the staff's pressurized thermal shock evaluation forwarded by letter dated March 22, 2996, the staff concluded that the best estimate of the copper and nickel content in the surveillance weld was 0.225X and 0.53X, respectively.
In addition, it was reported that the licensee's best estimate for copper and nickel in the surveillance weld were 0.214X and 0.50X.
Discuss the basis for the values of copper and nickel in the surveillance weld reported in Table 5-4A.
Furthermore, discuss how the chemistry factor for the surveillance weld reported on page 56 of WCAP-14684 was determined (i.e., provide the interpolation).
Clarify the thickness of the reactor vessel.
On page 22 of WCAP-14684, it indicates that the vessel thickness is 16.83 cm (6.6 inches).
On page 52,
- however, the thickness reported as 6.5 inches.
Discuss the reason for the apparent discrepancy.
Enclosure