ML20195F777
| ML20195F777 | |
| Person / Time | |
|---|---|
| Issue date: | 11/17/1998 |
| From: | Lainas G NRC (Affiliation Not Assigned) |
| To: | Terry C NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML20195F782 | List: |
| References | |
| TAC-M98266, NUDOCS 9811200082 | |
| Download: ML20195F777 (3) | |
Text
90 ntn g g\ UNITED STATES 3
- Q NUCLEAR REGULATORY COMMISSION II [, t WASHINGTON, D.C. 20066 4 001 C
- R* /
November 17,1998 Carl Terry, BWRVIP Chairman Niagara Mohawk i eer Company Post Office Box 63 Lycoming, NY 13093 .
SUBJECT:
SAFETY EVALUATION OF THE "BWRVIP VESSEL AND INTERNALS PROJECT, INTERNAL CORE SPRAY PIPING AND SPARGER REPLACEMENT DESIGN CRITERIA (BWRVIP-16)" EPRI REPORT TR 106708, MARCH 1997; AND, OF THE *BWRVIP VESSEL AND INTERNALS PROJECT, INTERNAL CORE SPRAY PIPING AND SPARGER REPAIR DESIGN CRITERIA (BWRVIP-19)" EPRI REPORT TR 106893, SEPTEMBER 1996 (TAC NOS. M98266 AND M96539)
Dear Mr. Terry,
The NRC staff has completed its review of the Electric Power Research Institute (EPRI) proprietary Reports TR-106708, 'BWR Vessel and Internals Project, Internal Core Spray Piping and Sparger Replacement Design Criteria (BWRVIP-16)," dated March 18,1997, and TR-106893, "BWR Vessel and Intemals Project, Internal Core Spray Piping and Sparger Repair Design Criteria (BWRVIP-19)," dated September 16,1996, as supplemented by letter dated February 24,1997.
The BWRVIP-16 report provides general design acceptance criteria for full and/or partial replacement of 300 series stainless steel internal core spray piping, spargers and supports and is intended to assist licensees in designing replacements which will maintain the structural integrity of the core spray system under normal operation as well as under postulated transient and design basis accident conditions. The BWRVIP-19 report provides general design acceptance criteria for temporary and permanent repair of 300 series stainless steel internal core spray piping and spargers.
The NRC staff has reviewed the BWRVIP-16 and -19 reports and finds, in the enclosed Safety Evaluation (SE), that the guidance of the BWRVIP-16 and -19 reports are acceptable for replacement and/or repair, as applicabte, of the subject safety related RPV internal components, k(l) j except where the staff's conclusions differ from the BWRVIP's, as discussed in the enclosed SE. '
The staff has concluded that licensee implementation of the guidelines in the BWRVIP-16 and -
19 reports will provide an acceptable level of quality for replacement and/or repair, as applicable, w!th modifications to address the staff's conclusions in the enclosed SE, of the safety-related components addressed in the BWRVIP-16 and -19 reports. The staff requests to be informed by each BWR licensee of plans to replace and/or repair, as applicable, internal core spray piping and spargers in accordance with the guidance of the BWRVIP-16 or -19 reports prior to the fh replacement and/or repair, as applicable.
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Carl Terry i
, The staff requests that the BWRVIP review and resolve the issues raised in the enclosed SE, and incorporate the staff's conclusions into revised BWRVIP-16 and -19 reports. Please inform the staff within 90 days of the date of this letter as to your proposed actions and schedule for such revisions.
Please contact C. E. (Gene) Carpenter, Jr., of my staff at (301) 415-2169 if you have any further questions regarding this subject.
l Sincerely, l r ORIGIN.AL SWrw i
GUS C.LAINAS Gus C. Lainas, Acting Director
- Division of Engineering Office of Nuclear Reactor Regulation l
Enclosure:
As stated I 1
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CarlTerry The staff requests that the BWRVIP review and resolve the issues raised in the enclosed SE, and incorporate the staff's conclusions into revised BWRVIP-16 and -19 reports. Please inform the staff within 90 days of the date of this letter as to your proposed actions and schedule for such revisions.
Please contact C. E. (Gene) Carpenter, Jr., of my staff at (301) 415-2169 if you have any further questions regarding this subject.
Sincerely, b
Gus C. Lainas, Acting Director Division of Engineering Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page i
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cc:
l George Jones, Executive Chairman Dana Covill, Technical Chairman BWRVIP Assessment Task BWRVIP AssessmentTask
!. Pennsylvania Power & Light GPU Nuclear A6-1 1 Upper Pond Road Two North Ninth Street Parsippany, NJ 07054 Allentown, PA 18101 Joe Hagan, Executive Chairman Carl Larsen, Technical Chairman BWRVIP inspection Task BWRVIP inspection Task Entergy Yankee Atomic P. O. Box 756 580 Main Street Waterloo Road Bolton, MA 0)?40 Port Gioson, MS 39150 Paul Bemis,' Executive Chairman Vaughn Wagoner, Technical Chairman BWRVIP Integration Task BWRVIP Integratien Task Washington Public Power Supply System Carolina Power & Light Company P. O. Box 968 One Hannover Square 9C1 North Power Plant Loop P.O. Box 1551 Richland, WA 99352-0968 Raleigh, NC 27612 ;
Lewis Sumner, Executive Chairman John Wilson, Technical Cha!rman BWRVIP Mitigation Task BWRVIP Mitigation Task J Southem Nuclear Operating Co. Clinton Power Station, M/C T-31C 40 Invemess Center Parkway P.O. Box 678 Birmingham, AL 35201 Clinton,IL 61727 John Blomgren, Executive Chairman Bruce McLeod, Technical Chairman BWRVIP Repair Task BWRVIP Repair Task l Commonwealth Edison Co. Southem Nuclear Operating Co. I 1400 Opus Place, Suite 600 Post Office Box 1295 l Downers Grove, IL 60515 5701 40 invemess Center Parkway i Birmingham, AL 35201 i Bill Campbell, BWRVIP Vice Chairman Warren Bilanin, EPRI BWRVIP Carolina Power & Light Integration Manager P. O. Box 1551 Joe Gilman, EPRI BWRVIP Raleigh, NC 27612 Mitigation Manager Ken Wolfe, EPRI CWRVIP Robert Carter, EPRI BWRVIP Repair Manager Assessment Manager Electric Power Research Institute Greg Selby, EPRI BWRVIP P. O. Box 10412 Inspection Manager 3412 Hillview Ave.
l EPRI NDE Cen:er Palo Alto, CA 94303 l P. O. Box 217097 L 1300 W. T. Harris Blvd.
Charlotte, NC 28221 i
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