ML20202C177
| ML20202C177 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/27/1999 |
| From: | Hernan R NRC (Affiliation Not Assigned) |
| To: | Scalice J TENNESSEE VALLEY AUTHORITY |
| References | |
| GL-96-05, GL-96-5, TAC-M97100, TAC-M97101, NUDOCS 9901290319 | |
| Download: ML20202C177 (3) | |
Text
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N January 27, 1999 Mr. J. A. Scalice Chief Nuclerr Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE TO GENERIC LETTER 96-05 FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TAC NOS. M97100 AND M97101)
Dear Mr. Scalice:
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal by Tennessee Valley Authority (TVA) dated April 28,1998, regarding Generic Letter (GL) 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." The purpose of the GL was to request that nuclear power plant licensees establish a program, or ensure the effectiveness of the current program, to verify, on a periodic basis, that safety-related motor-operated valves (MOVs) continue to be capable of performing their safety functions within the current licensing basis of the facility.
TVA's response submitted an updated response to GL 96-05 indicating its intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV periodic verification at Sequoyah. The NRC staff has encouraged licensees to participate in the industry-wide JOG program by sharing expertise and information on MOV performance. Licensee participation in the JOG program also minimizes the amount of information necessary for the NRC staff to review each licensee's response to GL 96-05. As a result, the NRC staff requires only limited information to complete its GL 96-05 review for Sequoyah.
Enclosed is a request for additional information regarding the GL 96-05 program. As discussed with Jim Smith of your staff on January 25,1999, TVA has agreed to provide a response to this request by April 26,1999.
Sincerely, Original signed by Ronald W. Hernan, Senior Project Manager Project DirectorateII-3 9901290319 990127 Division of Reactor Projects - t/11 DR ADOCK 0500 7
Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Request for Additional Information I
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Mr. J. A. Scalice SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Senior Vice President Mr. Pedro Salas, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority Sequoyah Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Soddy Daisy, TN 37379 Mr. Jack A. Bailey Mr. D. L. Koehl, Plant Manager Vice President Sequoyah Nuclear Plant Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Soddy Daisy, TN 37379 1101 Market Street Chattanooga, TN 37402-2801 Regional Administrator U.S. Nuclear Regulatory Commission Mr. Masoud Bajestani Region ll Site Vice President 61 Forsyth Street, SW., Suite 23T85 Sequoyah Nuclear Plant Atlanta, GA 30303-3415 Tennessee Valley Authority P.O. Box 2000 Mr. Melvin C. Shannon Soddy Daisy, TN 37379 Senior Resident inspector Sequoyah Nuclear Plant General Counsel U.S. Nuclear Regulatory Commiesion Tennessee Valley Authority 2600 Igou Ferry Road ET 10H Soddy Daisy, TN 37379 400 West Summit Hill Drive Knoxville, TN 37902 Mr. Michael H. Mobley, Director TN Dept. of Environment & Conservation Mr. Raul R. Baron, General Manager Division of Radiological Health Nuclear Assurance 3rd Floor, L and C Annex Tennessee Valley Authority 401 Church Street SM Lookout Place Nashville, TN 37243-1532 1101 Market Street Chattanooga, TN 37402-2801 County Executive Hamilton County Courthouse Mr. Mark J. Burzynski, Manager Chattanooga, TN 37402-2801 Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
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REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE OF SEQUOYAH NUCLEAR PLANT TO GENERIC LETTER 96-05 1.
In NRC inspection Report No. 50-327 & 328/97-18, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at Sequoyah Nuclear Plant (Sequoyah) in response to Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance," based on the results of the inspection and the licensee's plan to resolve several outstanding MOV issues as described in a letter dated February 12,1998. In the inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term. For example, the inspectors noted that (1) additional industry valve factor information would be gathered for Walworth, Anchor / Darling, and Copes Vulcan gate valves; and (2) margin improvements were scheduled for valves 1/2FCV-72-002 and 1/2FCV-72-039 during the next outage for each unit. In addition to the NRC inspection report items, the licensee committed in its February 12,1998, letter to take specific actions, including (1) use of the Electric Power Research Institute MOV Performance Prediction MeSodology to establish thrust requirements for gate valve Groups 1,2, and 8; (2) application of additional industry information and revision of necessary calculations for Sequoyah's Pratt butterfly valves; and (3) implementation of maintenance improvements for the Unit 1 pressurizer power operated relief valve (PORV) block valves during the Fall 1998 outage. The Tennessee Valley Authority (TVA) should describe the actions taken to address the specific long-term aspects of the MOV program at Sequoyah noted in the NRC inspection report and its letter dated February 12,1998.
2.
TVA indicates that its MOV static diagnostic periodic verification program will include test methods at the valve and the motor control center. Will diagnostic data be obtained for all GL 96-05 MOVs, including gate, globe and butterfly valves? If not, TVA should describe its plans to monitor degradation in capability for those MOVs not diagnostically tested.
3.
TVA should briefiv describe its plans for the use of test data from the motor control center (MCC) including (1) correlation of new MCC test data to existing direct force measurements; (2) interpretation of changes in MCC test data to changes in MOV thrust and torque performance; (3) consideration of system accuracies and sensitivities to MOV degradation for both output and operating performance requirements; and (4) validation of MOV operability using MCC testing.
4.
The Joint Owners Group (JOG) program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30,1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. In a letter dated April 28,1998, the licensee stated that potential actuator degradation would be identified through review and trending of actuator performance parameters. The licensee should describe the actions taken at Sequoyah for ensuring adequate ac and de MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1 in more detail.
ENCLOSURE