ML15112A399

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Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves
ML15112A399
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 02/16/1999
From: Labarge D
NRC (Affiliation Not Assigned)
To: Mccollum W
DUKE POWER CO.
References
GL-96-05, GL-96-5, TAC-M97075, TAC-M97076, TAC-M97077, NUDOCS 9902190316
Download: ML15112A399 (5)


Text

February 16., 1999 Mr. W. R. McCollum, Jr.

Vice President, Oconee, Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (TAC NOS. M97075, M97076, AND M97077)

Dear Mr. McCollum:

On September 18, 1996, the NRC issued Generic Letter (GL) 96-05, "Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves," 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.

On March 31, 1998, Duke Energy Corporation responded to GL 96-05 and indicated its intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification at Oconee Nuclear Station, Units 1, 2, and 3. The staff has encouraged licensees to participate in the industry-wide JOG program to provide a benefit in reactor safety by sharing expertise and information on MOV performance and to increase the efficiency of GL 96-05 activities at nuclear plants. Participation in the JOG program also minimizes the amount of information necessary for the staff in its review of each licenseel 'esponse to GL 96-05. As a result, the staff requires only limited information to complete its GL 96-05 review for Oconee.

Enclosed is a request for additional information regarding the GL 96-05 program at Oconee. It is requested that your response be provided by June 1, 1999, as discussed with Mr. Ed Burchfield, of your office.

Sincerely, original signed by:

David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Licensing Project Management 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 DISTRIBUTION:

Docket File HBerkow ACRS PUBLIC LBerry COgle PDII-2 Reading DLaBarge TScarbrough JZwolinski OGC DTerao To receive a copy of this document, indicate in the box: "C" = Copy without attachmentlenclosure E" = Copy with chment/enclosure "N" = No copy OFFICE PM:PQ LA:PDII-A D:

NAME DlaB arge:mw LBerry IFJerW4,-- I DATE 2/10/99 A 6)/99

/ 699 DOCUMENT NAME: G:\\OCONEE\\97075RAl.WPD OFFICIAL RECORD COPY 9902190316 990216 PDR ADOCK 05000269' P

PDR

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 16, 1999 Mr. W. R. McCollum, Jr.

Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (TAC NOS. M97075, M97076, AND M97077)

Dear Mr. McCollum:

On September 18, 1996, the NRC issued Generic Letter (GL) 96-05, "Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves," 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.

On March 31, 1998, Duke Energy Corporation responded to GL 96-05 and indicated its intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification at Oconee Nuclear Station, Units 1, 2, and 3. The staff has encouraged licensees to participate in the industry-wide JOG program to provide a benefit in reactor safety by sharing expertise and information on MOV performance and to increase the efficiency of GL 96-05 activities at nuclear plants. Participation in the JOG program also minimizes the amount of information necessary for the staff in its review of each licensee's response to GL 96-05. As a result, the staff requires only limited information to complete its GL 96-05 review for Oconee.

Enclosed is a request for additional information regarding the GL 96-05 program at Oconee. It is requested that your response be provided by June 1, 1999, as discussed with Mr. Ed Burchfield, of your office.

Sincerel David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Licensing Project Management 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

Oconee Nuclear Station cc:

Ms. Lisa F. Vaughn Mr. J. E. Burchfield Legal Department (PBO5E)

Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28201-1006 P. 0. Box 1439 Seneca, South Carolina 29679 Anne Cottington, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.

Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Rick N. Edwards P. O. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28201-1006 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Virgil R. Autry, Director Division of Radioactive Waste Management Mr. Steven P. Shaver Bureau of Land and Waste Management Senior Sales Engineer Department of Health and Environmental Westinghouse Electric Company Control 5929 Carnegie Blvd.

2600 Bull Street Suite 500 Columbia, South Carolina 29201-1708 Charlotte, North Carolina 28209 County Supervisor of Oconee County Walhalla, South Carolina 29621

REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE OF OCONEE NUCLEAR STATION TO GENERIC LETTER 96-05 In NRC Inspection Report No. 50-269, 50-270, and 50-287/95-25, the staff closed its review of the motor-operated valve (MOV) program implemented at Oconee Nuclear Station, Units 1, 2, and 3 (Oconee) in response to Generic Letter (GL) 89-10, "Safety Related Motor-Operated Valve Testing and Surveillance." In the inspection report, the staff discussed certain aspects of the licensee's MOV program to be addressed over the long-term. For example, the inspectors noted that (1) Duke Energy Corporation (DEC) had committed to improve the margins for eleven Unit 2 and Unit 3 valves by the end of 1996; (2) DEC would be expected to review applicable information following completion of the staffs evaluation of the Electric Power Research Institute (EPRI) MOV Performance Prediction Methodology (PPM) and to take appropriate action, as necessary; and (3) the PPM model needed to be validated for Powell gate valves with inverted guides and Crane gate valves with nonstellite seating material. In addition, NRC Inspection Report No. 50-269, 50-270, and 50-287/97-05 (dated July 18, 1997), noted that DEC planned to (1) replace or dynamically test butterfly valve 1CC-7 and (2) conduct a prototype flow test to justify the assumed valve factor applied to Velan gate valve 2FDW-1 04. DEC is requested to provide a summary status of the actions taken to address the specific long-term aspects of the MOV program at Oconee noted in the two NRC inspection reports.

2.

In a letter dated May 13, 1998, DEC updated its commitment to implement the Joint Owners Group (JOG) Program on MOV Periodic Verification in response to GL 96-05.

The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee. In a previous letter dated March 18, 1997, DEC stated that the ranking of MOVs at Oconee would be based on the Westinghouse Owners Group (WOG)

Engineering Report V-EC-1658-A (Revision 0) and/or the Boiling Water Reactor Owners' Group (BWROG) methodology as described in BWROG Topical Report NEDC 32264, "Application of Probabilistic Safety Assessment of Generic Letter 89-10 Implementation."

Since the Oconee units are pressurized water reactors (PWRs) designed by Babcock &

Wilcox (B&W), DEC is requested to describe the application of the WOG or BWROG methodology to Oconee, including (1) the preparation of a sample list of high-risk MOVs from other B&W nuclear plants, and (2) consideration of the conditions and limitations discussed in the NRC's safety evaluation dated April 14, 1998, on the WOG methodology, or the NRC's safety evaluation dated February 27, 1996, on the BWROG methodology.

3.

DEC is requested to briefly 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.

Enclosure

-2

4.

The 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's safety evaluation dated October 30, 1997, on the JOG program, the staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. It is requested that DEC describe the plan at Oconee for ensuring adequate ac and dc MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.