ML18106B109
| ML18106B109 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/23/1999 |
| From: | Milano P NRC (Affiliation Not Assigned) |
| To: | Keiser H Public Service Enterprise Group |
| References | |
| GL-96-05, GL-96-5, TAC-M97095, TAC-M97096, NUDOCS 9903310267 | |
| Download: ML18106B109 (7) | |
Text
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, I UNITED STATES NUCLEAR REGULATORY COMMISSION Mr. Harold W. Keiser Chief Nuclear Officer & President -
Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038 WASHINGTON, D.C. 20555--0001 March 23, 1999
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO GENERIC LETTER 96-05, SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 & 2 (TAC NOS. M97095 AND M97096)
Dear Mr. Keiser.
In a letter dated June 4, 1998, the Public Service Electric and Gas Company (PSE&G, the licensee) submitted an updated response to the U.S. Nuclear Regulatory Commission (NRC) for the Salem Nuclear Generating Station, Unit Nos. 1 and 2, regarding NRC Generic Letter (GL)'96-05,... Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." In GL 96-05, the NRC had requested that licensees establish a program, or ensure
- the effectiveness of their 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.
In its June 4, 1998, letter, PSE&G indicated its intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification at Salem. The NRC staff has encouraged licensees to participate in the industry-wide JOG program to provide a benefit in reactor safety by sharing e)cpertise and information on MOV performance and to increase the efficiency of GL 96-05 activities at nuclear plants.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the 9903310-267990323. ----- --- -----
PDR ADOCK 05000272 p
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enclosure. In a telephone conversation with representatives of your staff, the NRC staff discussed this information and obtained agreement that PSE&G would provide the additional information requested within 60 days of receipt of this letter.
If you have any questions regarding this matter, please contact me at (301) 415-1457.
Docket Nos. 50-272 and 50-311
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PD 1-2 R/F JZwolinski EAdensam
~
1>\\e-v-q,o Sincerely, original signed by:
Patrick D. Milano, Senior Project Manager Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation PMilano TScarbrough A Hansen OGC RBlough, RI ACRS OFFICE PDl-3/LA NAME TClarkjiv DATE J /7_,
/99 31J'!J199 OFFICIAL RECORD COPY DOCUMENT NAME: RAl97095.wpd
enclosure. In a telephone conversation with representatives of your staff, the NRC staff discussed this infomiation and obtained agreement that PSE&G would provide the additional information requested within 60 days of receipt of this letter.
If you have any questions regarding this matter, please contact me at (301) 415-1457.
Docket Nos. 50-272 and 50-311
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File JZwolinski PUBLIC EAdensam PD 1-2 R/F KMa"oly 1>1e('C{..O Sincerely, original signed by:
Patrick D. Milano, Senior Project Manager Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation PMilano TScarbrough A Hansen OGC RBlough, RI ACRS OFFICE PDl-3/LA NAME TClark)iG DATE J /t, /99
.J 1J.?J /99 OFFICIAL RECORD COPY DOCUMENT NAME: RAl97095.wpd
- > / '2-?::> /99
/99
enclosure. In a telephone conversation with representatives of your staff, the NRC staff discussed this information and obtained agreement that PSE&G would provide the additional information requested within 60 days of receipt of this letter.
If you have any questions regarding this matter, please contact nie at (301) 415-1457.
Docket Nos. 50-272 and 50-311
Enclosure:
Request for Additional Information cc w/encl: See next page Sincerely, Patrick D. Milano, Senior Project Manager Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
"'" Mr. Harold W. Keiser Public Service Electric & Gas Company cc:
Jeffrie J. Keenan, Esquire Nuclear Business Unit - N21 P.O. Box236 Hancocks Bridge, NJ 08038 General Manager - Salem Operations Salem Nuclear Generating Station P.O. Box236 Hancocks Bridge, NJ 08038 Mr. Louis Storz Sr. Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector
- Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN415 Trenton, NJ 08625-0415
- Maryland Office of People'~ Counsel 6 St. Paul Street, 21st Floor -
Suite 2102 Baltimore, MD* 21202 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne, PA 19087 Mr. Elbert Simpson
- Senior Vice President-.
Nuclear Engineering Nuclear Department P.O. Box236 Haricocks Bridge, NJ 08038 Salem Nuclear Generating Station, Units 1and2 Richard Hartung.
Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Director - Licensing Regulation & Fuels Nuclear Busienss Unit - N21 P.O. Box236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Manager - Joint Generation Atlantic Energy 6801 Bl~ck Horse Pike Egg Harbor Twp., NJ 08234-4130 Carl D_. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box231 Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806
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REQUEST FOR ADDITIONAL INFORMATION RESPONSE TO NRC GENERIC LETTER 96-05 SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1AND2
- 1.
Through NRC Inspection Report (IR) 50-272 & 311/97-03 (Unit2), IR 50-272198-01 (Unit 1), and IR 50-272 & 311/98-08 (Unit 1), the NRC staff closed its review of the*
motor-operated valve (MOV) program implemented at Salem in response to Generic
- Letter (GL) 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance.* In the inspection reports, the NRC staff discussed certain aspects of the licensee's MOV program that were to be addressed over the long term. These issues have been separated by unit and are discussed below.
Unit 1 In IR 50-272/98-01 and IR 50-272 & 311/98-08, the NRC noted that PSE&G agreed to (1) increase the available margins for the reactor coolant pump thermal barrier heat exchanger isolation valves, 1CC130 and 1CC190; (2) verify correct wedge shoe orientation and dynamically test Anchor/Darling double disc gate valves, 1CC117 and 1CC118; and (3) include valves 1CC118, 1CC30, 1PR7, and 1SJ4 in its margin improvement plans.
In IR 50-272 & 311/97-03 and in Section EB, "Miscellaneous Engineering Issues," of IR 50-272 & 311/98-08, the NRC noted that PSE&G agreed to (1) perform modifications on residual heat removal valves 2RH1 and 2RH2; (2) confirm the unsupported guide lengths of the pressurizer power operated relief valve block valves; (3) increase the motor actuator capability, verify the unsupported guide length, and verify the disc and guide edge treatments on the reactor coolant pump thermal barrier heat exchanger isolation valves, 2CC130 and 2CC190; (4) dynamically test and perform additional evaluations on valves 2CC136, 22CC16, 2SJ4, and 2SJ5; and (5) increase the output capability for four 24" Pratt butterfly valves included in Family 16.
Provide an update of the actions taken to address the specific long-term aspects of the MOV program at Salem noted in the NRC inspection reports.
- 2.
In a letter dated March 13, 1997, PSE&G 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 significanee are the responsibility of each participating licensee. In its March 13, 1997, letter, PSE&G stated that the frequency of static diagnostic testing would be based, in part, on Salem's Probabilistic Safety Assessment and an expert review. Since Salem uses a pressurized water reactor designed by.
Enclosure
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( Westinghouse, discuss whether PSE&G is applying the Westinghouse Owners' Group (WOG) methodology for ranking MOVs based on \\heir 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 th~ NRC's safety evaluation dated April 14, 1998. If not, describe the methodology used for risk ranking MOVs at Salem 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.
- 3.
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 NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. Describe the plan at Salem for ensuring adequate a.c. and d.c. MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.