ML18095A971
| ML18095A971 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/05/1991 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | Tosch K NEW JERSEY, STATE OF |
| Shared Package | |
| ML18095A972 | List: |
| References | |
| TAC-67948, NUDOCS 9106190390 | |
| Download: ML18095A971 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 June 5, 1991 Docket No. 50-272 Mr. Kent Tosch, Chief Bureau of Nuclear Engineering Division of Environmental Quality New Jersey Department of Environmental Protection CN 415 Trenton, New Jersey 08625-0415
Dear Mr. Tosch:
SUBJECT:
FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL, SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 (TAC NO. 67948)
By letter dated April 8, 1988, the Bureau of Nuclear Engineering, State of New Jersey, forwarded to the NRC, comments on the First Ten-Year Inspection Interval, Inservice Inspection Program (!SI) relief requests that were proposed by Public Service Electric and Gas Co. (PSE&G) for Salem Unit 1. The staff has completed their review of PSE&G 1 s relief requests and has approved them.
This approval was sent to PSE&G by letter dated March 11, 1991.
A copy of the staff 1 s evaluation of PSE&G 1 s request is enclosed.
The comments received from your office pertain to the following requests:
A.
Examination 1 Ca tegor,y_~.:1.:~-t-l.!~!!1-~~? ~~J_.P.!'~;; suri ~~!__~- St~E!!!
Ge~~!2~~!_f_2£Ejng Inspection.
The staff 1 s evaluation of this request is as follows:
The Code requirements to visually examine, during each inspection interval, 100% of the patch areas for Pressurizer, Heat Exchanger and St~am Generator Cladding is impractical because of the radiation exposure of 4 man-rem for the removal of one steam generator manway.
In addition, the 1974 Edition through Summer 1975 Addenda, Item No.
B2.9, Category B-I-2 and Item No. B3.8, Category B-I-2 requirements have been deleted from later editions of the Code.
Furthermore, the later editions of the Code have been approved by NRC and incorporated into 10 CFR 50.55a. Therefore, the staff has determined, pursuant to 10 CFR 50.55a(g)(4){iv) (the license for full power was issued on December 1, 1976) the licensee may use the later Code editions approved in 10 CFR 50.55a(b). Visual inspection of the cladding for the Pressurizer, Heat Exchangers and Steam Generators is no longer required by later editions of the Code.
Compliance with specific ASME requirement would result in hardship due to the high radiation exposure and the visual inspection would not contribute to quality and safe operation of the plant.
(See section 2.A. of the enclosed safety evaluation for a complete discussion.)
Mr. :.Kent lo sch June 5, 1991 B.
Examination Category B-L-2, ASME Section XI 1974 through Summer-75 Addenda The staff 1s evaluation of this request is as follows:
The requirement to visually inspect the internal pressure boundary surfaces of the Reactor Coolant Pumps (RCP) is impractical because of the relatively high radiation exposure from insulation removal, disassembly, examination, and reassembly of the pumps.
In addition, to disassemble the pumps for the sole purpose to inspect the internal pressure boundary surfaces may be counterproductive due to the possibility of causing damage to the pump internals during the disassembly and/or reassembly of the pumps.
The staff has determined that the alternative inspection proposed by the licensee will provide adequate assurance of the structural integrity of the Reactor Coolant Pump's casings with the exception that the licensee perform the required Code inspections when a RCP is completely disassembled for a scheduled maintenance activity. Pursuant to 10 CFR 50.55a(g)(6)(i),
we conclude that relief from the ASME Boiler and Pressure Code requirement may be granted as requested by the licensee provided the licensee performs the required Code inspections when a RCP is completely disassembled for a scheduled maintenance activity.
(See section 2.B of the enclosed safety evaluation for a complete discussion.)
C.
Examination Category B-M, Item B 6.7, ASME Section XI 1974 through Summer-75 Addenda The staff's evaluation of this request is as follows:
The Code requirements to visually examine the internal pressure boundary surfaces, on valves exceeding 4 inches nominal pipe size is impractical because of the radiation exposure associated with the disassembly, examination, and reassembly of the valves.
In addition, the disassembly and reassembly of the valves could be counter-productive due to the possibility of causing damage to the internals of the valve.
The staff has determined that the alternative inspections will provide adequate assurance of the structural integrity of the valve's internal pressure boundary surfaces.
Pursuant to 10 CFR 50.55a(g)(6)(i), we conclude that relief from the ASME Boiler and Pressure Code requirement may be granted as requested by the licensee. (See section 2.C of the enclosed safety evaluation for a complete discussion.)
Mr. kent Tosch June 5, 1991 The staff has the authority, as stated in 10 CFR 50.55a(g)(6)(i), to grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
In each instance, the appropriate findings have been made.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page DISTRIBUTION:
Docket File NRC & Local PDRs PDI-2 Reading SVarga JCalvo MO'Brien(2)
JS tone OGC EJordan, 3701 CY Cheng ACRS(lO)
RBlough JWhite Sincerely,
/SI James C. Stone, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr *. Kent Tosch June 5, 1991 The staff has the authority, as stated in 10 CFR 50.55a{g){6)(i), to grant such relief and may impose such ~lternative requirements as it determines is authorized by law and wi 11 not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
In each instance, the appropriate findings have been made.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Sincerely,
~C,~
James C. Stone, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
cc:
Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street NW Washington, DC 20005-3502 Richard Fryling, Jr., Esquire Law Department - Tower 5E 80 Park Place Newark, NJ 07101 Mr. Calvin A. Vondra General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. S. LaBruna Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Mr. Thomas P. Johnson, Senior Resident Inspector Salem Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection CN 415 Trenton, NJ 08625-0415 Maryland People's Counsel American Building, 9th Floor 231 East Baltimore Street Baltimore, Maryland 21202 Mr. J. T. Robb, Director Joint Owners Affairs Philadelphia Electric Company 955 Chesterbrook Blvd., 51A-13 Wayne, PA 19087 Salem Nuclear Generating Station Richard B. McGlynn, Commission Department of PubliC Utilities State of New Jersey 101 Commerce Street 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 Mr. Frank X. Thomson, Jr., Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Mr. Scott B. Ungerer MGR. - Joint Generation Projects Atlantic Electric Company P.O. Box 1500 1199 Black Horse Pike Pleasantville, NJ 08232 Mr. Jack Urban General Manager, Fuels Department Delmarva Power & Light Company 800 King Street Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division ATTN:
Chief Engineer 231 E. Baltimore Street Baltimore, MD 21202-3486
1*
Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038 Salem Nuclear Generating Station