ML17265A528
| ML17265A528 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/03/1999 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| GL-96-05, GL-96-5, TAC-M97050, NUDOCS 9902080181 | |
| Download: ML17265A528 (8) | |
Text
Dr. Robert C. Mecredy ~
Vice President, Nuclear rations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 February 3, 1999
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONREGARDING GENERIC LETTER 96-05 PROGRAM ATTHE R. E. GINNA NUCLEAR POWER PLANT (TAC NO.
M97050)
Dear Dr. Mecredy:
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 3, 1998, you submitted an updated response to GL 96-05 indicating your intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification. The NRC 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.
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 Ginna.
Enclosed is a request for additional information regarding the GL 96-05 program at Ginna.
Please provide a response within 60 days of the date of this letter.
9902080i8i 990203 PDR ADOCK 05000244 P
PDR Docket No. 50-244
'incerely, Original signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
'tD~n'cket
'leh PUBLIC PDI-1 R/F J. Zwolinski S. Bajwa DOCUMENT NAME: G:\\
S. Little G. Vissing T. Scarbrough OGC ACRS C. Cowgill, RGN I PI t Q~'g~jgiIL03 P~PV To receive a copy of this docunent, indicate in the box:
"C" = Copy without attachment/enclosure "E" = Copy uith attachment/enclosure "H" ~ Ho co OFFICE PH:PDI-1 HAHE Gvissing: Icc DATE 02/
/99 LA:PDI-1 SLittl 02/
/99 D:PDI-1 SBa ua 02/
/99 02/
/99 OFFICIALRECORD COPY
February 3, 1999 Dr. Robert C. Mecredy ~
Vice President, Nuclear~erations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONREGARDING GENERIC LETTER 96-05 PROGRAM AT THE R. E. GINNA NUCLEAR POWER PLANT (TAC NO.
M97050)
Dear Dr. Mecredy:
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 3, 1998, you submitted an updated response to GL 96-05 indicating your intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification. The NRC 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.
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 Ginna.
Enclosed is a request for additional information regarding the GL 96-05 program at Ginna.
Please provide a response within 60 days of the date of this letter.
Sincerely, Original signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F J. Zwolinski S. Bajwa S. Little G. Vissing T. Scarbrough OGC ACRS C. Cowgill, RGN I DOCUMENTNAME'A To receive a copy of this document, indicate in the box:
"C¹ ¹ Copy without attachment/enclosure
¹E¹ "-Copy with attachment/enclosure
¹ii¹ = Mo co OFFICE PH:PDI-I LA:PDI-1 D:PDI-1 IIAHE Gvissing: lcc SLIttia SBa Ma DATE 02/
/99 02/
/99 02/
/99 02/
/99 OFFICIALRECORD COPY
<qua R500
~o Cy 4u O
IA O
C gO
++*++
- Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 February 3, 1999
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONREGARDING GENERIC LETTER 96-05 PROGRAM ATTHE R. E. GINNA NUCLEAR POWER PLANT (TAC NO.
M97050)
Dear Dr. Mecredy:
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.
P On March 3, 1998, you submitted an updated response to GL 96-05 indicating your intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification. The NRC 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.
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 Ginna.
Enclosed is a request for additional information regarding the GL 96-05 program at Ginna.
Please provide a response within 60 days of the date of this letter.
Sincerely, Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page
C r
~ f
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Sr. 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 Mr. F. WilliamValentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Falls Road, Room 11 Rochester, hlY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
RE UEST FOR ADDITIONALINFORMATIONON RESPONSE OF R.E. GINNA NUCLEAR POWER PLANTTO GENERIC LETTER 96-05 In NRC Inspection Report No. 50-244/98-06, the NRC staff closed its review of the motor-operated valve "(MOV)program implemented at R.E. Ginna Nuclear Power Plant (Ginna) in response to Generic Letter (GL) 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance."
In the inspection report, the NRC staff discussed certain aspects of the I licensee's MOVprogram to be addressed over the long term. For example, the inspectors noted that the licensee had established plans to perform additional dynamic tests or use the Electric Power Research Institute (EPRI) Performance Prediction Model (PPM) to provide a long-term basis for the predicted thrust and torque requirements applied to selected valves in Groups B, D, and E. The licensee should provide a summary status of the actions taken to address this specific long-term aspect of the MOVprogram at Ginna noted in the NRC inspection report.
In a letter dated November 18, 1996, the licensee stated 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.
As Ginna is a pressurized-water reactor (PWR) nuclear plant designed by Westinghouse, is the licensee applying the Westinghouse Owners'roup (WOG) methodology for ranking MOVs based on their safety significance as described in WOG Engineering Report V-EC-1658-A (Revision 2, dated August 13, 1998), "Risk Ranking Approach for Motor-Operated Valves in
Response
to Generic Letter 96-05," and the NRC safety evaluation dated April 14, 1998'?
If not, the licensee should describe the methodology used for risk ranking MOVs at Ginna in more detail, including a description of (1) the process used to develop sample lists of high-risk MOVs from other Westinghouse plants; and (2) how expert panels were used to evaluate MOV risk significance.
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 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 MOVmotor actuator and its potential degradation.
The licensee should describe the plan. at Ginna 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.
Enclosure
'