ML18102B676
| ML18102B676 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 11/12/1997 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | Eliason L Public Service Enterprise Group |
| References | |
| GL-96-06, GL-96-6, TAC-M96821, TAC-M96860, TAC-M96861, NUDOCS 9711210278 | |
| Download: ML18102B676 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 12, 1997 Mr. Leon R. Eliason Chief Nuclear Officer & President-Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
INFORMATION PERTAINING TO HOPE CREEK GENERATING STATION AND SALEM NUCLEAR STATION, UNITS 1 AND 2, IMPLEMENTATION OF MODIFICATIONS ASSOCIATED WITH GENERIC LETTER 96-06, "ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" (TAC NOS. M96821, M96860, AND M96861)
Dear Mr. Eliason:
The staff issued Generic Letter (GL) 96-06 oi September 30, 1996.
The generic letter requested licensees to determine (1) if containment air cooler cooling water systems are susceptible to either waterhammer or two-phase flow conditions during postulated accident conditions, and (2) if piping systems that penetrate the containment are susceptible to thermal expansion of fluid so that overpressurization of piping could occur.
By letter dated January 27, 1997, you submitted your 120-day response to GL 96-06 for Hope Creek Generating Station.
In addition, by letter dated January 28, 1997, as supplemented October 20, 1997, you submitted your 120-day response to GL 96-06 for Salem Nuclear Generating Station Units 1 and 2.
The staff is currently performing a detailed review of your responses.
Implementing corrective actions to resolve the GL 96-06 issues can have a significant impact on outage schedules and resources.
Some licensees have indicated that it would be prudent to take more time to better understand the specific concerns that have been identified in order to optimize whatever actions are needed and to assure that they do not ultimately result in a detriment to safety. Current issues and ongoing efforts that could influence a licensee's decision in planning corrective actions include (1) risk implications of installing relief valves to deal with the thermal overpressurization issue, (2) feasibility of using the acceptance criteria contained in Appendix F to Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the permanent resolution of the GL 96-06 issues, (3) ongoing tests by the Electric Power Research Institute to support a generic resolution of the overpressuri zat i)on of piping issue, and (4) questions regarding the staff's closure of Generic Safety Issue 150, "Overpressurization of Containment Penetrations." Risk insights and industry initiatives that are being considered or that may be proposed could also influence the course of action that licensees take to 11 resolve the GL 96-06 issues..
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Licensees are responsible for assessing equipment operability, determining actions, and establishing schedules that are appropriate for resolving the specific conditions that have been identified.
In determining the appropriate actions and schedules for resolving GL 96-06 issues, licensees should consider, for example, the continued validity of existing operability determinations, compensatory actions required to maintain operability, the safety significance associated with the specific nonconformances or degraded conditions that have been identified, risk insights, and the time required to complete any generic initiatives and/or plant-specific actions (e.g., engineering evaluations, design change packages, material procurement, and equipment modification and installation). Also, analytical solutions employing the permanent use of the acceptance criteria contained in the ASME Code,Section III, Appendix F (or other acceptance criteria) may present viable alternatives to plant modifications and can be used where appropriate, justified, and evaluated in accordance with NRC requirements such as 10 CFR 50.59, as applicable. Licensees may find the revised guidance contained in GL 91-18, "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability,". Revision 1, dated October 8, 1997, helpful in determining appropriate actions and schedules. Although adjustments in schedules may be warranted on the basis of these (and other) considerations, specific actions that have been defined and are clearly needed should not be delayed without suitable justification.
It is the staff's current position that licensees can use the ASME Code, Section Ill, Appendix F, criteria for interim operability determinations for degraded and nonconforming piping and pipe supports until permanent actions have been identified and approved by the NRC (as applicable) for resolving the GL 96-06 issues. This guidance supplements the guidance provided by GL 91-18 for resolution of the GL 96-06 issues.
In order to further facilitate resolution of the GL 96-06 issues, the NRC will participate in a public workshop on this topic later this fall. The workshop proceedings will be summarized by the NRC staff and made publicly available.
The need for additional NRC guidance and generic communication will be considered upon completion of the workshop.
Lr Eli a son If you choose to revise your commitments for resolving the GL 96-06 issues, you should submit a revised response to the generic letter. Your revised response should include appropriate discussion of the considerations discussed above, the current resolution status, and actions remaining to be completed, and plans being considered for final resolution of the GL 96-06 issues.
If you have any questions, please contact me at (301) 415-1430.
Docket No. 50-272, 50-311, and 50-354 cc:
See next page Sincerely, rT
. Stolz, Director ro ect Directorate I
- ision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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L Eliason November 12,, 1997*
- If you choose to revise your commitments for resolving the GL 96-06 issues, you shoµld submit a revised response to the generic letter. Your revisedc
- response should include appropriate discussion of the considerations discussed abov.e, the current re so 1 ut ion status, and actions remaining to be comp 1 eted,
- and plans being considered for final resolution of the GL 96-06 issues.
If~jou have a~y questions, please contact me at (301) 415-1430.
Docket No. 50-272, 50-311, and 50-354 cc:
See next page DISTRIBUTION:-..
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SA96860. OUT Sincerely, Isl John F. Stolz, Director Project Directorate I-2
. Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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- Mt. Leon R. El i a son
- 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. Box 236 Hancocks Bridge, NJ 08038 Mr. Louis Storz Sr. Vice President - Nuclear Operations Nuclear Department P.O. Box 236 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., fi3C-5 Wayne, PA 19087 Mr. Elbert Simpson Senior Vice President-Nucl ear Engineering Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Hope Creek Resident Inspector U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Salem Nuc"'ar Generating Station, Units 1 and 2, and Hope Creek Generating Station Richard Hartung Electric Service Evaluation Board of Regulatory Conunissioners 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 Manager-Licensing and Regulation Nuclear Busienss Unit - N21 P.O. Box 236 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 General Manager - Hope Creek Operations Hope Creek Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038