ML18102B324
| ML18102B324 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/16/1997 |
| From: | Olshan L NRC (Affiliation Not Assigned) |
| To: | Eliason L Public Service Enterprise Group |
| References | |
| GL-95-03, GL-95-3, TAC-M92269, TAC-M92270, NUDOCS 9705290170 | |
| Download: ML18102B324 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-@01 May 16, 1997 Mr. Leon R. Eliason Chief Nuclear Officer & President-Nuclear Business Unit Public Service* Electric & Gas Company Post Office Box 236 Hancocks. NJ 08038
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03.
"CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES." DATED.APRIL 28.
1995. FOR SALEM NUCLEAR GENERATING STATION. UNITS 1 AND 2 (TAC NOS. M92269 AND M92270)
Dear Mr. Eliason:
On.April 28. 1995. the U.S. Nuclear Regulatory-commission CNRC) issued Generic Letter (GU 95-03. "Circumferential Cracking of Steam Generator Tubes." to all holders of operating licenses or construction permits for pressurized-water reactors. The NRC issued GL 95-03 for three principal reasons:
(1)
Notify addressees about the safety significance of the recent steam generator tube inspection findings at Maine Yankee Atomic Power Station.
(2)
Request that all addressees implement the actions described within the generic letter.
(3)
Require that all addressees submit to the NRC a written response regarding implementation of the requested actions.
In addition. GL 95-03 alerted addressees to the importance of performing comprehensive examinations of steam generator tubes using techniques and equipment capable of reliably detecting the types of degradation to which the steam generator tubes may be susceptible. The staff.also noted that the
_performance of steam generator tube examinations *is controlled. in part. by Appendix B to Title 10. Part 50. of the Code of Federal Regulations (10 CFR Part 50).
In GL 95-03, the NRC staff also requested that licensees take the following actions:
(1)
Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to deter.mine the applicability to their plants.
(2)
On the basis of the evaluation in Item (1) above. as well as past inspection scope and results. susceptibility to circumferential cracking, threshold of detection. expected or inferred crack growth rates. and other relevant factors. develop a safety assessment justifying continued operation until the next scheduled steam generator tube~ inspections.
1 9705290170 970516 PDR ADOCK 05000272 P
PDR NBC FILE CENTER C
-"-*, L.' Eliason *
- May 16, 1997 (3)
Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking.
The inspection plans should address. but not be limited to. scope (including sample expansion criteria. if applicable). methods. equipment. and criteria (including personnel training and qualification).
To document the outcome of these actions. the NRC staff req~ested that addressees prepare and submit the following:
(1)
A safety assessment justifying continued operation. predicated on the evaluation performed in accordance with requested actions 1 and 2 (above).
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for the next planned inspection.
In response to GL 95-03, you provided letters dated July 17, 1995. and October 17. 1995 for Salem Nuclear Generating Station. Units 1 and 2.
These submittal(s) provided the information requested by GL 95-03; therefore TAC Nos. M92269 and M92270 are closed.
For your information. the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
If you have any questions regarding this matter. please contact L. Olshan at (301)-415-1419 Docket Nos: 50-272 and 50-311 cc:
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Leonard N. Olshan. Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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r May 16, 1997 (3)
Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking. The inspection plans should address. but not be limited to. scope (jncluding sample expansion criteria~ if applicable). methods. equipment. and criteria (including personn~l training and qualification>.:
To document the -Outcome of these actions. the NRC staff requested that addressees prepare and submit the following:
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- A safety assessment justifying continued operation. predicated on the evaluation performed in accordance with requested actions 1 and 2 (above).
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for the next planned inspection.
In response to GL 95-03. you provided letters dated July 17. 1995. and October 17. 1995 for Salem Nuclear Generating Station. Units 1 and 2. These submitta1(s) provided the information requested by GL 95-03; therefore TAC Nos. M92269 and M92270 are closed.
For your information. the staff's findings regarding this issue are contained in NUREG-1604. "Circumferential Cracking of Steam Generator Tubes."
If you have any questions regarding this matter. please contact L. Olshan at (301)-415-1419.
Docket Nos: 50-272 and 50-311
- cc: See next page Sincerely,
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Leonard N. Olshan. Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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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. D. F. Garchow General.Manager - Salem Operations Salem Generating.Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Louis Storz Sr. *vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge. New Jersey 08038 Mr. Char1es S. Marschall. Senior
. Resident Inspector Salem Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill. Li poti. Asst. Di rector 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
- 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 Admini'strator. 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 Muni ci pa 1 Building. P. 0. Box J57 Hancocks Bridge, NJ 08038
- Mr. David R. Powell. Manager Licensing and Regulation Nuclear Business Unit P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg. PA* 17120 P. M. Goetz MGR. 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 Maryl and Engineering Division Chief Engineer 6 St. Paul Centre Baltimore. MD 21202~6806 Mr. Elbert Simpson Senior Vice President - Nuclear* Engineering Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038