ML16141B023
| ML16141B023 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/13/1996 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | Hampton J DUKE POWER CO. |
| References | |
| GL-95-07, GL-95-7, TAC-M93492, TAC-M93493, TAC-M93494, NUDOCS 9606190067 | |
| Download: ML16141B023 (4) | |
Text
clune 13, 1996
'Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION -
GENERIC LETTER 95-07, "PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" - OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 (TAC NOS. M93492, M93493, AND M93494)
Dear Mr. Hampton:
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 responses to GL 95-07. Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review. We request that you submit your response within 30 days.
Sincerely, original signed by David E. LaBarge, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear'Reactor Regulation Docket Nos. 50-269, 50-270 DISTRIBUTION:
and 50-287 (Docket Fill' OGC, 0-15BI8 PUBLIC ACRS, TWF
Enclosure:
Request for Additional PD22 r/f EMerschoff, RH Information SVarga JZwolinski H. Rathbun R. Eaton cc w/encl:
See next page R. Crlenjak, RII To receive a copy of this document, Indicate In the box:
"C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N"= Nocopy OFFICE PDH-2/LAN () 1 PDII 2 1
PDII NAME Lerry D
D~aB cdw HBe/k DATE
//96 1
/13 /96 t/V96
/ /96 DOCUMENT NAME:
G:\\OCONEE\\0C093492.RAI OFFICIAL RECORD COPY 9606190067 960613.
PDR ADOCK 05000269 FIR BE CENT-E CO11PY
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 13, 1996 Mr. J. W. Hampton Vice President, Oconee Site.
Duke Power Company P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION -
GENERIC LETTER 95-07, "PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" - OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 (TAC NOS. M93492, M93493, AND M93494)
Dear Mr. Hampton:
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 responses to GL 95-07. Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review. We request that you submit your response within 30 days.
Sine rely, David E. LaBarge, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287
Enclosure:
Request for Additional Information cc w/encl:
See next page
Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:
Mr. Paul R. Newton Mr. Ed Burchfield Legal Department (PB05E)
Compliance Duke Power Company Duke Power Company 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28242-0001 P. 0. Box 1439 Seneca, South Carolina 29679 J. Michael McGarry, III, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Robert B. Borsum P. 0. Box 629 B&W Nuclear Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike Mr. G. A. Copp Rockville, Maryland 20852-1631 Licensing -
ECO50 Duke Power Company Manager, LIS 526 South Church Street NUS Corporation Charlotte, North Carolina 28242-0001 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Dayne H. Brown, Director Division of Radiation Protection Senior Resident Inspector North Carolina Department of U. S. Nuclear Regulatory Commission Environment, Health and Route 2, Box 610 Natural Resources Seneca, South Carolina 29678 P. 0. Box 27687 Raleigh, North Carolina 27611-7687 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County Walhalla, South Carolina 29621
REQUEST FOR ADDITIONAL INFORMATION OCONEE NUCLEAR STATION, UNITS 1. 2 AND 3 RESPONSE TO GENERIC LETTER 95-07, "PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES"
- 1.
Regarding valves 1, 2, 3 LP-17, -18, Low Pressure Injection RB Isolation Valves, the licensee's submittal states that administrative controls exist to limit maximum pressure in this line to 225 psig. The NRC staff believes that reliance on check valves to limit the pressure can be uncertain. Please provide detailed information regarding the administrative controls existing to limit pressure in this line.
In addition, the licensee's submittal states that calculations have been performed that demonstrate the capability of these valves to open under potential pressure locked conditions. Please provide these calculations for our review. Also, please include any associated actuator capability and thrust requirement calculations.
- 2.
Regarding valves 1, 2, 3 RC-4, PORV Block Valve, the licensee's submittal.states that calculations have been performed to quantify the effects of pressure locking. Please provide these calculations for our review. Also, please include any associated actuator capability and thrust requirement calculations.
In addition, the licensee's submittal states that the actuator thrust requirement for valve 3RC-4 is 14,569 lbs. and the actuator available thrust is 14,052 lbs.
Please provide your basis for the capability of this valve to perform its safety function.
- 3.
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 that 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.
ENCLOSURE