ML18093A181
| ML18093A181 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/24/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Corbin McNeil Public Service Enterprise Group |
| References | |
| NUDOCS 8706300471 | |
| Download: ML18093A181 (4) | |
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UNITED STATES 1'
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Dock~t Nos.:
50-272 Mr. Corbin A. McNeill, Jr.
Senior Vice President - Nuclear Public Service Electric and Gas
-Company Post Office Box 236 June 24, 1987 Hancocks Bridge, New Jersey 08038
Dear Mr. McNei11:
SUBJECT:
SALEM NUCLEAR GENERP.TING STATION UNIT NO. 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES - SECOND 10 YEAR INTERVAL By letter dated Septem~er 24, 1986, you submitted a-proposed revision to your inservice testing*~rogtarn description for.pumps and valves and requests for relief from selected ASME Code requirements pursuant to 10 CFR 50.55a(g).
Based upon the results of a review by the staff and a subsequent site meeting held with your representatives on February 26, 1987, you submitted a revised second 10 year interval inservice testing program description for pumps and valves and requests for relief. This revision superseded the previous submittal and includes certain changes resulting from the February 26, 1987 meeting.
The IST program for pumps and valves is required by 10 CFR 50.55a(g) to comply with the ASME Boiler and Pressure Vessel Code,Section XI.
For Salem Unit No.
1, the applicable version of the ASME Section XI Code is the 1983 Edition through the Su1T1Tier 1983 Addenda.
This code version will supersede your currently referenced program version as is required under 50.55a for pumps and valves.
Pursuant to CFR 50.55a(g)(5), relief was requested from certain ASME Code testing requirements for specific pumps and valves where the Code requirements are impractical within the limits of design, geometry and system safety. The requests for relief include an explanation and justification for the relief requested and a proposal for alternative testing where practical.
Based on our preliminary review, we agree with the determination that it is impractical within the limitations of design, geometry and materials of construction of components, for you to meet certain of the specified ASME Code requirements and that imposition of those requirements would result in hardships or unusual difficulties without a compensating increase in the level of quality or safety. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), we hereby grant the interim relief until the staff has completed its detailed review or until December 31, 1987 whichever comes first, from those inservice testing requirements of the ASME Code that you have requested.
The granting of this relief is based only on the impraticality of selected ASME Code requirements.
The relief granted neither increases the probability or 71 970624.
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L consequences of accidents previously considered nor decreases safety margins; thus, the granting of this relief does not involve a significant hazards consideration. Therefore, you are authorized to, and should proceed to, implement your proposed program (except where your current Technical Specifi-cations are more restrictive).
During the period between now and the date we complete our detailed review of your submittal, you must comply with both your existing Technical Specifications and your proposed inservice testing program.
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements (e.g., shorter testing intervals, increased number of parameters measured).
In other words, the granting of this interim relief from ASME Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications, other than the superseding of the outdated version of the code with the above applicable version of the code.
When our detailed revjew of your submittal is complete we will:
(1) request a meeting with you to *discuss the results of our review; (2) issue final approval of your p-rogram which may contain modifications and/or additional imposed requirements resulting from the staff's review; and (3) grant relief from any ASME Code requirements that are determined to be impractical for your facility for the duration of the inspection interval.
cc: See next page Sincerely, J)alt:fl?~
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
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Mr. C. A. McNei11 Pub1ic Service Electric & Gas Company cc:
S. E. Mi1tenberger Vice President - Nuclear Operations Nuclear Department P. O. Box 236 Hancocks Bridge, NJ 08038 Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsy1vania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Law Department - Tower SE BO Park Place Newark; NJ 07101 Gene Fisher, Bureau Chief Bureau of Radiation Protection 380 Scotch Road Trenton, NJ 08628 Mr. John M. Zupko, Jr.
General Manager - Salem Operations Salem Generating Station Post Office Box E Hancocks BridgP, NJ 08038 Robert Traae, Mayor Lower Alloways Creek Township Municipal Ha 11 Hancocks Rridge, NJ 08038 Thomas Kenny, Resident Jnspector Salem Nuclear Generating Station U.S. Nuclear Regu1atory Commission Drawer I Hancocks Bridge, NJ 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, NJ 08625 Salem Nuclear Generating Station Frank Casolito, Action Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Richard B. McGlynn, Commission Department of Public Utilities State of New Jersey 101 Conmerce Street Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 631 Pa.rk Avenue 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. Bruce A. Preston, Manager Licensing and Regulation Nuclear Department P. O. Box 236 Hancocks Bridge, NY 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Morgan J. Morris, III General Manager - Operating License Atlantic Electric P. O. Box 1500 1199 Black Horse Pike Pleasantville, NJ 08232 Delmarva Power c/o Thomas S. Shaw, Jr.
Vice President - Production BOO King Street P. O. Box 231 Wilmington, DE 19899
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./. consequences of. acCi*dents previously considered nor decreases safety margins; thus, the grantfng of this relief does not involve a significant hazards consideration.. Therefore, you are authorized to, and should proceed to, implement your proposed program (except where your current Technical Specifi-cations are more restrictive).
During the period between now and the date we complete our detailed review of your submittal; you must comply with both your existing Technical Specifications and your proposed inservice testing program.
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements (e.g., shorter testing intervals, increased number of parameters measured).
In other words, the granting of this interim relief from ASME Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications, other than the superseding of the outdated version of the code with the above applicable version bf the code.
When our detailed review of your submittal is complete we will:
(1) request a meeting with you to discuss the results of our review; (i) issue final approval of your program which may contain modifications and/or additional imposed requirements resulting from the staff's review; and (3) grant relief from any ASME Code requirements that are determined to be impractical for your facility for the duration of the inspection interval.
cc: See next page DISTRIBUTION Docket File NRC PDR Local PDR PDI-2 Reading SVarga OGG-Bethesda p0.-r0rioC DF~;:ca 06/Vf/87 EJordan JPartlow DFischer/MThadani MO'Brien ACRS ( 10)
PDI-2/D J B WButler W 06/z.L\\,/87 Sincerely,
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II