ML17264A217
| ML17264A217 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/03/1995 |
| From: | Andrea Johnson NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| GL-95-07, GL-95-7, TAC-M93466, NUDOCS 9511130022 | |
| Download: ML17264A217 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION VIASHlNGTON> D.C. 20555-0001 November 3, 1995 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
RESPONSE
TO ROCHESTER GAS AND ELECTRIC CORPORATION 60-DAY RESPONSE TO GL 95-07 (TAC NO. H93466)
Dear Dr. Hecredy:
On August 17, 1995, the NRC issued Generic Letter (GL) 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves."
This GL requested certain actions on a 90-day and 180-day schedule and a
response within 60 days indicating the licensee's intended actions regarding the requested actions.
By letter dated October 17,
- 1995, Rochester Gas and Electric (RG&E) submitted its 60-day response to GL 95-07 for R.
E. Ginna Nuclear Power Plant.
In its response, RGSE proposed an exception to the 90-day requested actions.
- Rather, RG&E proposes to comply with all GL 95-07 actions and responses within 180 days.
RG&E stated that it believes that as a
result of the Mestinghouse Owner's Group (HOG) efforts in resolving the concerns associated with GL 95-07, "ther e are no safety implications in delaying completion of the 90-day requested actions to 180 days."
The staff established the recommended actions for the 90-day screening evaluation in GL 95-07 to provide confidence that no short-term safety concerns exist regarding particular valves as a result of pressure locking and thermal binding.
The purpose of this action is for licensees to ensure that no critical deficiencies exist in past evaluations, and take action if appropriate.
The essence of the 90-day screening evaluation is to conduct an initial assessment, using current knowledge, of all safety-related power-operated gate valves to assure they are operable should they be potentially susceptible to pressure locking or thermal binding.
The staff considers a prompt screening evaluation to be reasonable considering the length of time the industry has been aware of and had opportunity to take action for situations involving pressure locking and thermal binding.
As described in GL 95-07, the staff has provided several notifications of this issue in the past 2 years.
Additionally, notifications from the Institute for Nuclear Power Operations (INPO) include Significant Operating Experience Report 84-7, "Pressure Locking and Thermal Binding of Gate Valves," dated December 14,
- 1984, and INPO Significant Event Report 8-88, "Pressure Locking of Residual Heat Removal Gate Valves," dated Harch 25, 1988.
Based on our review, we do not find RG&E's submittal to be fully responsive in that the existence of ongoing MOG efforts does not constitute an acceptable safety basis for deferring the 90-day requested actions of GL 95-07.
In light of recent industry events involving pressure locking and thermal binding of 95iii30022 95ii03 PDR ADOCK 05000244 P
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Robert C. Mecredy safety-related power-operated gate valves, we conclude that the decision to defer the 90-day requested actions of GL 95-07 does not allow RGKE to assure itself of the current operability of these valves.
Therefore, RG8E is requested to commit to the 90-day requested actions of GL 95-07 or provide the safety basis for determining the acceptability of the planned alternative course of action by November 15, 1995.
Should you have any questions on this matter, please contact me at (301) 415-1497.
The information requested by this letter is within the scope of the overall burden estimated in GL 95-07, which was a maximum of 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> per response.
This request is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires July 31, 1997.
Sincerely, Docket No. 50-244 cc:
See next page l en R. Johnson, Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Dr. Robert C. Hecredy R.E. Ginna Nuclear Power Plant CC:
Thomas A. Hoslak, 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 Hr. 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 Hs. Thelma Wideman
- Director, Wayne County Emergency Hanagement Office Wayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Hs. Hary Louise Heisenzahl Administrator, Honroe County Office of Emergency Preparedness 111 West Fall
- Road, Room ll Rochester, NY 14620
Robert C. Hecredy November 3,
1995 safety-related power-operated gate valves, we conclude that the decision to defer the 90-day requested actions of GL 95-07 does not allow RG&E to assure itself of the current operability of these valves.
Therefore, RG&E is requested to commit to the 90-day requested actions of GL 95-07 or provide the safety basis for determining the acceptability of the planned alternative course of action by November 15, 1995.
Should you have any questions on this
- matter, please contact me at (301) 415-1497.
The information requested by this letter is within the scope of the overall burden estimated in GL 95-07, which was a maximum of 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> per response.
This request is covered by the Office of Hanagement and Budget Clearance Number 3150-0011, which expires July 31, 1997.
Sincerely, Docket No. 50-244 cc:
See next page Original signed by:R. Eaton for:
Allen R. Johnson, Project Hanager Project Director ate I-1 Division of Reactor Projects I/II Office'f Nuclear Reactor Regulation DISTRIBUTION:
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