ML18106B096
| ML18106B096 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/12/1999 |
| From: | Adensam E NRC (Affiliation Not Assigned) |
| To: | Keiser H Public Service Enterprise Group |
| Shared Package | |
| ML18106B097 | List: |
| References | |
| TAC-M98259, TAC-M98260, NUDOCS 9903190004 | |
| Download: ML18106B096 (4) | |
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- 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 12, 1999.
SUBJECT:
RELIEF REQUESTS V-24 AND V-25 REGARDING TESTING OF ACCUMULATOR CHECK VALVES, SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 (TAC NO. M98259 AND M98260)
Dear Mr. Keiser:
In a letter dated December 26, 1996, Public Service Electric and Gas Company (PSE&G, the licensee) submitted a proposed revision.to the lnservice Testing (IST) Program for the Salem Nuclear Generating Station, Unit Nos. 1 and 2. The proposed revision to the IST Program contained Relief Requests V-24 and V-25. In these relief requests, PSE&G requested approval from the U.S. Nuclear Regulatory Commission (NRC) to use an alternative to the requirements in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, "lnservice Inspection," for the safety injection accumulator check valves. Specifically, PSE&G proposed (1) an alternative to the Code test frequency requirements of IWV-3521 and IWV-3522 to allow testing each check valve during refueling outages and (2) relief from the exercise procedure requirements of IWV-3522(b) to allow the use of a partial accumulator dump test to verify that each check valve is exercised to its safety position. In a [[letter::05000311/LER-1997-001-01, :on 970115,inadequate Surveillance for PORV Accumulator Discharge Check Valves Was Noted.Caused by Reviewers Not Identifying That Test Method Did Not Meet Requirements of ASME Code.Revised Procedure|letter dated February 13, 1997]], the NRC had granted interim relief until the next refueling outage to allow the NRC staff additional time to perform a more detailed evaluation.
The NRC staff has reviewed the proposed relief requests and completed its evaluation. The licensee's proposed ~lternative to the Code test frequency requirements of IWV-3521 and IWV-3522 to test each check valve every refueling outage is approved pursuant to 1 O CFR 50.55a(f){4)(iv) because the proposed alternative frequency meets the test frequency requirement in -the 1989 edition of ASME Code,Section XI which is the latest edition of the Code inc~rporated by reference in the regulations. The licensee's proposed relief from the exercise procedure requirements of IWV-3522(b) to use a partial accumulator dump test to verify that the check valve is exercised to its safety position is granted pursuant to 10 CFR 50.55a(f)(6)(i) based on the impracticality of performing testing in accordance with the Code requirements, an~ in consideration of the burden on the licensee if the Code requirements were imposed on tl:le facility. This. relief is granted provided the licensee adjusts its acceptance criterion to 27.0 seconds and stipulates in the relief request that if the acceptance criterion is exceeded,* Qoth the SJ55 and. SJ56 check valves of the associated accumulator be subject to corrective action. Prior to invoking the granted relief, the licensee must inform the NRG upon completion of the appropriate changes to its IST Program.
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March 12, 1999 The NRC staff concludes that the relief requests, as evaluated in the enclosed safety evaluation with stated conditions, will provide reasonable assurance of operational readiness of the subject check valves on an interim basis. The NRC staff has determined that granting relief requests and approving later editions and addenda of the Code pursuant to 1 O CFR 50.55a(f)(6)(i) and (f)(4)(iv), respectively are authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest. In making a determination of impracticality, the staff has considered the burden on the licensee if the requirements were imposed.
Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encls: See next page DISTRIBUTION
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March 12, 1999 The NRC staff concludes that the relief requests, as evaluated in the enclosed safety evaluation with stated conditions, will provide reasonable assurance of operational readiness of the subject check valves on an interim basis. The NRC staff has determined that granting relief requests and approving later editions and addenda of the Code pursuant to 10 CFR 50.55a(f)(6)(i) and {f)(4)(iv), respectively are authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest. In making a determination of impracticality, the staff has considered the burden on the licensee if the requirements were imposed.
Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encls: See next page Sincerely, Elinor G. Adensam, Director 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. Box 236 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. Box236 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 CN 415 Trenton, NJ 08625-0415 Maryland Office of People's 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 Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station, Units 1 and 2 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 Black Horse Pike Egg Harbor Twp., NJ 08234-4130 Carl D. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806
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