ML20216F455: Difference between revisions
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| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | ||
| page count = 3 | | page count = 3 | ||
| project = TAC:M99638 | |||
| stage = Approval | |||
}} | }} | ||
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==Dear Mr. Terry,== | ==Dear Mr. Terry,== | ||
f The NRC staff has completed its review of the Electric Power Research Institute (EPRI) proprietary report TR-108823, "BWR Vessel and Internals Project, BWR Shroud Support inspection and Flaw Evaluation Guidelines (BWRVIP-38)." This report was submitted by letter dated September 15,1997, and supplemented by letter dated November 24,1998, which was in response to the staff's request for additional inforiaation, dated April 8,1998. | f The NRC staff has completed its review of the Electric Power Research Institute (EPRI) proprietary report TR-108823, "BWR Vessel and Internals Project, BWR Shroud Support inspection and Flaw Evaluation Guidelines (BWRVIP-38)." This report was submitted by {{letter dated|date=September 15, 1997|text=letter dated September 15,1997}}, and supplemented by {{letter dated|date=November 24, 1998|text=letter dated November 24,1998}}, which was in response to the staff's request for additional inforiaation, dated April 8,1998. | ||
The BWRVio-38 report provides generic guidelines intended to present the appropriate inspection and flaw evaluation recommendations to assure safety function integrity of the j subject safety-related reactor pressure vessel (RPV) internal components. These guidelines considered degradation susceptibility, degradation mechanisms, loads, and inspection strategies for shroud supports. The report also allows for plant-specific analysis to be performed for a given weld location. These plant-specific analysis are not addressed in the scope of this report, and NRC approval must be obtained on a case-by-case basis, until such time as they are approved for general usage by the staff. | The BWRVio-38 report provides generic guidelines intended to present the appropriate inspection and flaw evaluation recommendations to assure safety function integrity of the j subject safety-related reactor pressure vessel (RPV) internal components. These guidelines considered degradation susceptibility, degradation mechanisms, loads, and inspection strategies for shroud supports. The report also allows for plant-specific analysis to be performed for a given weld location. These plant-specific analysis are not addressed in the scope of this report, and NRC approval must be obtained on a case-by-case basis, until such time as they are approved for general usage by the staff. | ||
The staff has reviewed the BWRVIP-38 report and finds, in the enclosed safety evaluation (SE), | The staff has reviewed the BWRVIP-38 report and finds, in the enclosed safety evaluation (SE), |
Latest revision as of 06:10, 21 March 2021
ML20216F455 | |
Person / Time | |
---|---|
Issue date: | 09/16/1999 |
From: | Strosnider J NRC (Affiliation Not Assigned) |
To: | Terry C NIAGARA MOHAWK POWER CORP. |
Shared Package | |
ML20216F457 | List: |
References | |
TAC-M99638, NUDOCS 9909220050 | |
Download: ML20216F455 (3) | |
Text
gp CE2 g M1 UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566-0001
- ,o September 16, 1999 Carl Terry, BWRVIP Chairman Niagara Mohawk Power Company Post Office Box 63 Lycoming, NY 13093
SUBJECT:
SAFETY EVALUATION OF THE "BWR VESSEL AND INTERNALS PROJECT, BWR SHROUD SUPPORT INSPECTION AND FLAW EVALUATION GUIDELINES (BWRVIP-38)," EPRI REPORT TR-108823 (TAC NO. M99638)
Dear Mr. Terry,
f The NRC staff has completed its review of the Electric Power Research Institute (EPRI) proprietary report TR-108823, "BWR Vessel and Internals Project, BWR Shroud Support inspection and Flaw Evaluation Guidelines (BWRVIP-38)." This report was submitted by letter dated September 15,1997, and supplemented by letter dated November 24,1998, which was in response to the staff's request for additional inforiaation, dated April 8,1998.
The BWRVio-38 report provides generic guidelines intended to present the appropriate inspection and flaw evaluation recommendations to assure safety function integrity of the j subject safety-related reactor pressure vessel (RPV) internal components. These guidelines considered degradation susceptibility, degradation mechanisms, loads, and inspection strategies for shroud supports. The report also allows for plant-specific analysis to be performed for a given weld location. These plant-specific analysis are not addressed in the scope of this report, and NRC approval must be obtained on a case-by-case basis, until such time as they are approved for general usage by the staff.
The staff has reviewed the BWRVIP-38 report and finds, in the enclosed safety evaluation (SE),
that the guidance of the BWRVIP-38 report is acceptable for inspection and flaw evaluation of the subject safety-related RPV internal components, except where the staff's conclusions differ from the BWRVlP's, as discussed in the enclosed SE. The staff has concluded that licensee implementation of the guidelines in the BWRVIP-38 report will provide an acceptable level of quality for inspection ancl flaw evaluation, with modifications to address the staff's conclusions in the enclosed SE, of the safety-related components addressed.
The staff requests that the BWRVIP review and resolve the issues raised in the enclosed SE and incorporate the staff's conclusions into the revised BWRVIP-38 report. Please inform the staff within 90 days of the date of this letter of your proposed actions and schedule for revisions. -
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. . .- :d B g[$M T 9909220050 990916 PDR TOPRP EXIEPRI e\ a cmLk>b F l O_l i
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9 Carl Terry ,
Please contact C. E. (Gene) Carpenter, Jr., of my staff at (301) 415-2169 if you have any further questions regarding this subject.
Sincerely,
'L /4M 5%
Jack R. Strosnider, Director Division of Engineering Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page l
cc:
Karl W. Singer, Executive Chair Steve Lewis, Technical Chairman BWRVIP Assessmca Task BWRVIP Assessment Task Tennessee Valley Authority Entergy PO Box 2000 P. O. Box 756 Decaltur, AL 35602-2000 Waterloo Road Port Gibson, MS 39150 Bill Eaton, Executive Chair Inspection Committee Carl Larsen, Technical Chairman Entergy Operations, Inc. BWRVIP Inspection Task PO Box 756, Waterloo Rd P.O. Box 157 Port Gibson, MS 39150-0756 Vernon, VT 05354 H. Lewis Sumner, Executive Chairman John Wilson, Technical Chairman BWRVIP Mitigation Task BWRVIP Mitigation Task Southern Nuclear Operating Co. Clinton Power Station, M/C T-31C M/S BIN B051, PO Box 1295 P.O. Box 678 40 inverness Center Parkway Clinton,IL 61727 Birrningham, AL 35201 Vaughn Wagoner, Technical Chairman Harry P. Salmon, Executive Chairman BWRVIP Integration Task BWRVIP Integration Task Carolina Power & Light Company New York Power Authority One Hannover Square 9C1 123 Main St., M/S 11 D P.O. Box 1551 White Plains, NY 10601-3104 Raleigh, NC 27612 George T. Jones, Executive Chair Bruce McLeod, Technical Chairman BWRVIP Repair Task BWRVIP Repair Task Pennsylvania Power & Light, Inc. Southem Nuclear Operating Co.
M/S GEN A 61 Post Office Box 1295 2 N 9* Street 40 invemess Center Parkway Allentown, PA 18101-1139 Birmingham, AL 35201 Robert Carter, EPRI BWRVIP Tom Mulford, EPRI BWRVIP Assessment Man;ger Integration Manager EPRI NDE Center Raj Pathania, EPRI BWRVIP P. O. Box 217097 Mitigation Manager 1300 W. T. Harris Blvd. Ken Wolfe, EPRI BWRVIP Charlotte, NC 28221 Repair Manager I Electric Power Research Institute Greg Selby, EPRI BWRVIP P. O. Box 10412 Inspection Manager 3412 Hillview Ave.
l EPRI NDE Center Palo Alto, CA 94303 P. O. Box 217097 1300 W. T. Harris Blvd. James P. Pelletier, BWRVIP Liaison Charlotte, NC 28221 to EPRI Nuclear Power Council Nebraska Public Power District Joe Hagan, BWRVIP Vice Chairman 1200 Prospect Avenue PEPCO Energy Co. PO Box 98 MC 62C-3 Brownville, NE 68321-0098 965 Chesterbrook Blvd Wayne, PA 19807-5691