ML17251A868
| ML17251A868 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/17/1986 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17251A869 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR TAC-59956, NUDOCS 8611260126 | |
| Download: ML17251A868 (2) | |
Text
Docket No. 50-244 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas 8 Electric Corp.
89 East Avenue
.Rochester, New York 14649
Dear Mr. Kober:
SUBJECT:
PROJECTED VALUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS RE(UIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS R.
E.
GINNA NUCLEAR POWER PLANT We have reviewed your letter dated January 13, 1986 which was submitted in response to the Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61 for the R.
E. Ginna Nuclear Power Plant.
We have found the material properties of reactor vessel shell circumferential materials, the projected fluence at the inner surface o'f the reactor vessel at the expiration date of the license and the calculated RTPT at the expiration date of the license, April 25, 2006, to be acceptable.
fhe calculated RT is below the screening criterion of 300'F for circumferential weld materGf at the expiration date of the license.
This meets the requirements of the PTS rule.
The PTS Rule requires that the projected assessment of the RT must be updated whenever changes in core loadings, surveillance measuQIents, or other <
information (including changes in capacity factor) indicate a significant change in the project values.
This ensures that the licensees will track the fluence at the limiting shell circumferential materials throughout the life of the plant to verify their assumptions.
In this regard, we request you to submit a reevaluation of the RT and comparison of the predicted value with future Pressure-Temperature subNftals which are required by 10 CFR Part 50, Appendix G ~
This completes our review of the PTS issue for your plant.
Our associated Safety Evaluation is enclosed.
We consider this licensing action under TAC No.
59956 complete.
Enclosure:
As Stated cc's:
See Next Page George E. Lear, Director PWR Project Directorate 81 Division of PWR Licensing-A 8611260126 861117 PDR ADOCK 05000244:
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'DRg Office:
LA/PAD81 Surname:
PShuttl¹wmor Date:
11//r///86 PM/PAD¹1QQS PD/PAD¹1 Q$8 DDiIanni/tg GLear ll//+86 ll/j7/86
Mr. Roger W.
Kober Rochester Gas and Electric Corporation R.
E.
Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D. C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2
Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S.
Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Jay Dunkleberger Division of Policy Analysis 8 Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223