ML17158B647
| ML17158B647 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/10/1996 |
| From: | Poslusny C NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| GL-95-07, GL-95-7, TAC-M93528, TAC-M93529, NUDOCS 9606120183 | |
| Download: ML17158B647 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 June 10, 1996 Hr. Robert G. Bryam Senior Vice President-Nuclear Pennsylvania Power and Light Company
. 2 North Ninth Street Allentown, PA 18101
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 95-07, "PRESSURE LOCKING AND THERNL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," SUSQUEHANNA STEAN ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
M93528 AND N93529)
Dear Nr. Bryam:
On August 17, 1995, the NRC issued Generic Letter (GL) 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.
The NRC staff is reviewing and evaluating your response to GL 95-07 dated February 13, 1996.
Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review.
We request that you respond within 30 days.
Sincerely, Docket Nos. 50-387/388 Chester
- Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/encl:
See next page
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Enclosure:
Request for Additional Information QP'Q 1
~M KE CP/TEIR ~V
Mr. Robert G.
Byram Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mrs. Maitri Banerjee Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-.0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Vice President-Nuclear Operations Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Engineering Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Chairman Board of Supervisors 738 East Third Street
- Berwick, PA
. 18603
RE VEST FOR A DITIONAL'NFORMATION SUS UEHANNA S EAM LECTRIC STATION UNITS AND 2
RESPONSE
TO GENERIC LETTER 95-07 "PRESSURE LOCK NG AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" I;
The licensee's submittal does not discuss the potential susceptibility of HV-l(2)49-F013, reactor core isolation cooling (RCIC) Injection, and HV-l(2)49-F031, RCIC Suppression Pool Suction, to pressure locking. It is noted
- that, although the reactor core isolation cooling sys'em is considered safety-related at some facilities, it is considered non-safety-related at 'others and similarly may not be within the scope of GL 95-07 for Susquehanna Steam Electric Station.
Please discuss whether these valves were considered in your GL 95-07 review. If not, please discuss how the potential for pressure locking and thermal binding was addressed for these valves within your licensing commitments regarding the RCIC system, such as GL 89-10 or Bulletin 85-03.
2.
The licensee's submittal states that HV-l(2)55-FOOI, high-pressure coolant injection (HPCI) Turbine Steam Admission Valve, was determined not to be susceptible to thermal binding, based on valve heatup/cooldown scenarios and valve materials of construction.
The NRC staff believes that, while different disk/body materials can increase the likelihood of thermal binding, similar disk/body materials does not preclude, the occurrence of thermal binding.
Has the licensee performed any analysis or testing (including pa'st diagnostic testing performed under similar heatup/cooldown scenarios as would be present during a design basis event) to verify the assertion that these valves are not susceptible to thermal binding?
3.
Regarding HV-1(2)55-F042, HPCI Suppression Pool Suction Valve, the licensee's submittal states that a detailed heat transfer analysis determined that the water within the valve cavity will experience an insignificant temperature rise during accident conditions.
Please provide this analysis for our review.
4.
In Attachment I to GL 95-07, the NRC staff requested that licensees include consideration of the potential for gate valves to undergo pressure locking or thermal binding during surveillance testing.
During workshops on GL 95-07 in each Region, the NRC staff stated that, if closing a safety-related power-operated gate valve for test or surveillance defeats the capability of the safety system or train, the licensee should perform one of the following within the scope of GL 95-07:
l.
Verify that the valve is not susceptible to pressure locking or thermal binding while closed, 2.
Follow plant technical specifications for the train/system while the valve is closed, 3.
Demonstrate that the actuator has sufficient capacity to overcome these phenomena, or 4.'ake'ppropriate hardware and/or procedural modifications to prevent pressure locking and thermal binding.
The staff stated that normally open, safety-related power-operated gate valves which are closed for test or surveillance but must return to the open position should be evaluated within the scope of GL 95-07.
Please discuss if valves which meet this criterion were included in your review, and how potential pressure locking or thermal binding concerns were addressed.
5.
Through review of operational experience
- feedback, the staff is aware of instances where licensees have completed design or procedural modifications to preclude pressure locking or thermal binding which may have had an adverse impact on plant safety due to incomplete or incorrect evaluation of the potential effects of these modifications.
Please describe evaluations and training for plant personnel that have been conducted for each design or procedural modification completed to address potential pressure locking or thermal binding concerns.
Hr. Robert G.
Bryam Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101 e
June 10, 1996 r
SUBJECT:
RE(UEST FOR ADDITIONAL INFORMATION 'GENERIC LETTER 95-07, "PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," SUSQUEHANNA STEAN ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
H93528 AND H93529)
Dear Hr. Bryam:
On August 17, 1995, the NRC issued Generic Letter (GL) 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.
The NRC staff is reviewing and evaluating your response to GL 95-07 dated February 13, 1996.
Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review.
We request that you respond within 30 days.
Sincerely, Original signed by:
Chester
- Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation F
Docket Nos. 50-387/388
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
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