ML18101B084
| ML18101B084 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/06/1995 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | Eliason L Public Service Enterprise Group |
| Shared Package | |
| ML18101B085 | List: |
| References | |
| TAC-M93405, TAC-M93406, NUDOCS 9511080394 | |
| Download: ML18101B084 (3) | |
Text
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Mr. Leon R. Eliason
- Chj~f Nuclear Officer. resident-
, Nuclear Business Unit
~:.:Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038 November 6, ~
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - ASME CODE SECTION III RELIEF REQUEST (TAC NOS. M93405 AND M93406)
Dear Mr. Eliason:
Your August 28, 1995, letter requested relief for Salem Nuclear Generating Station, Units 1 and 2; requirements of ASME Section III 1965 Edition Winter 1966 Addenda, Article 9, Subarticle N-910.8 for the Regenerative Heat Exchanger (RHE) and ASME Code Section III 1968 Edition, Article 9, Subarticle N-910.8 for the Volume Control Tank (VCT).
You requested this relief because the VCT and RHE relief valve discharge line manual isolation valves in both Unit 1 and 2 do not have positive controls and interlocks.
ASME Code Section N-910.8 requires positive controls and interlocks on stop valves in relief valve discharge lines.
We find that you have demonstrated that compliance with Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The proposed alternative would not result in unacceptable consequences or impair the ability to shut the plant down during normal operation or accident conditions.
Pursuant to 10 CFR 50.55a(a)(3)(ii), we have authorized the proposed alternative to the 1965 Edition, Winter 1966 Addenda and the 1968 Edition of ASME Section III, Article 9, Section N-910.8 control and interlock requirements for the RHE and VCT relief valve discharge line manual isolation valves identified in our enclosed safety evaluation. Accordingly, you may use the specified administrative controls on these block valves at Salem.
The enclosed safety evaluation contains our review results.
Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encl:
See next page DI STR IBUTI ON :
Docket File PUBLIC PDI-2 Reading W. Russell/F. Miraglia R. Zimmemran S. Varga J. Zwolinski M. O'Brien L. Olshan OGC Sincerely,
/SI John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation G. Hill (4)
R. Jones ACRS W. Dean W. Pasciak, RGN-I R. Wessman
- Previously Concurred OFFICE PD EMEB*
SRXB*
OGC*
NAME RWessman RJones MYoun DATE 10/16/95 OFFICIAL RECORD COPY DOCUMENT NAME:
SAM93405.REL 9511080394 951106 PDR ADOCK 05000272 P
. PDR
- ~
I
.I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Leon R. Eliason Chief Nuclea~*Officer & President-Nucl ear Business Unit Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038 November 6, 1995
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - ASME CODE SECTION III RELIEF REQUEST. (TAC NOS. M93405 AND M93406)
Dear Mr. Eliason:
Your August 28, 1995, letter requested relief for Salem Nuclear Generating Station, Units 1 and 2, requirements of ASME Section III 1965 Edition Winter 1966 Addenda, A'rticle 9, Subarticle N-910.8 for the Regenerative Heat Exchanger (RHE) and ASME Code Section III 1968 Edition, Article 9, Subarticle N-910.8 for the Volume Control Tank (VCT).
You requested this relief because the VCT and RHE relief valve discharge line manual isolation valves in b~th Unit 1 and 2 do not have positive controls and interlocks.
ASME Code Section N-910.8 requires positive controls and interlocks on stop valves in relief valve discharge lines.
We find that you have demonstrated that compliance with Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The proposed alternative would not result in unacceptable consequences or impair the ability to shut the pl ant down during normal operation or accident conditions. Pursuant to 10 CFR 50.55a(a)(3)(ii), we have authorized the proposed alternative to the 1965 Edition, Winter 1966 Addenda and the 1968 Edition of ASME Section III, Article 9, Section N-910.8 control and interlock requirements for the RHE and VCT relief valve discharge line manual isolation valves identified in our enclosed safety evaluation. Accordingly, you may use the specified administrative controls on these block valves at Salem.
The enclosed safety evaluation contains our review results.
Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encl:
See next page Sincerely, 7
o
- t. Stolz, Directo eject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr; Leon R. Eliason~
Public Service Electric & Gas Company cc:
Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street NW Washington, DC 20005-3502 Richard Fryling, Jr., Esquire Law Department - Tower SE 80 Park Place Newark, NJ 07101 Mr. John Summers General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. J. Hagan Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Mr. Charles S. Marschall, Senior Resident Inspector Salem 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, Maryland 21202 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne, PA 19087 Mr. S. LaBruna Vice President - Nuclear Engineering Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Nuclelaenerating 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 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 Ms. P. J. Curham MGR. Joint Generation Department Atlantic Electric Company P.O. Box 1500 6801 Black Horse Pike Pleasantville, NJ 08232 Carl D. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington, DE 19899 Public Service Commission of Maryl and Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806