ML20195C636
| ML20195C636 | |
| Person / Time | |
|---|---|
| Issue date: | 11/10/1998 |
| From: | Essig T NRC (Affiliation Not Assigned) |
| To: | Liberatori L WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| Shared Package | |
| ML20195C640 | List: |
| References | |
| PROJECT-694 TAC-MA1152, NUDOCS 9811170186 | |
| Download: ML20195C636 (3) | |
Text
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', Itog W k UNITED STATES l . ,f j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066H001 r
p $
Y*****/ November 10, 1998 l
l Mr. Lou Liberatori, Chairman Westinghouse Owners Group Steering Committee Indian Point Unit 2 I
Broadway & Bleakley Ave.
Buchanan, NY 10511
SUBJECT:
SAFETY EVALUATION OF TOPICAL REPORT WCAP-15029
" WESTINGHOUSE METHODOLOGY FOR EVALUATING THE ACCEPTABILITY OF BAFFLE-FORMER-BARREL BOLTING DISTRIBUTIONS UNDER FAULTED LOAD CONDITIONS"(TAC NO. MA1152)
The staff has completed its review of the subject report requested by Westinghouse Owners Group (WOG) by letter of June 19,1998. The staff has found that this report is acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the report and in the associated NRC safety evaluation, which is enclosed. The safety evaluation defines the basis for acceptance of the report.
In response to reported foreign experience with baffle bolt failures and concems of potential degradation of baffle barrel bolts in domestic plants the WOG proposed that licensees perform corrective action inspections and replacement of baffle bolts under the provisions of 10 CFR 50.59 for two lead plants (2 & 3 loop). In determining the applicability of the 10 CFR 50.59 licensing approach, WOG requested NRC review and approval of WCAP-15029,
" Westinghouse Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bolting Distributions Under Faulted Load Conditions," and WCAP-14748/9, " Justification of increasing Postulated Break Opening Time." The latter WCAP report invokes the leak-before-break (LBB) concept and provides a justification for break-opening times greater than one millisecond. The LBB concept and break-opening times greater than one millisecond are applied, by reference, in the methodology guidance provided in WCAP-15029. WCAP-14748/9 was reviewed separately and the staff's safety evaluation was transmitted to WOG on October 1,1998.
Consequently, it is not included in this safety evaluation of WCAP-15029. Further, WOG requested that WCAP-9735 Rev.2,"Multiflex 3.0, A Fortran IV Computer Program for Analyzing Thermal Hydraulic Structural System Dynamics-Advanced Beam Model," which was previously submitted for staff review and approval, be withdrawn from review under the NRC licensing topical report program for referencing in licensing actions. Multiflex 3.0 is also applied in WCAP-15029 methodology guidance, by reference, but is not evaluated in this safety evaluation.
The staff will not repeat its review of the matters described in the WOG Topical Report WCAP-15029, when the report appears as a reference in license applications, except to ensure '[ ,
that the material presented applies to the specific plant involved. In accordance with procedures established in NUREG-0390, the NRC requests that WOG publish accepted .m I
versions of the submittal, proprietary and non-proprietary, within 3 months of receipt of this letter. The accepted versions shallincorporate this letter and the enclosed safety evaluation X[O 4"S '
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L. Liberatori -2 November 10, 1998 between the title page and the abstract and an -A (designating accepted) following the report identification symbol.
If the NRC's criteria or regulations change so that its conclusion that the submittalis acceptable are invalidated, WOG and/or the applicant referencing the topical report will be expected to revise and resubmit its respective documentation, or submit justification for the continued ,
applicability of the topical report without revision of the respective documentation. I Sincerely,
[jw,K. '
Thomas H. Essig, Acting Chief Generic issues and Environmental Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 694
Enclosure:
Safety Evaluation cc w/ enc: See next page I
f I
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l
O L. Liberatori -2 November 10,1998 between the title page and the abstract and an -A (designating accepted) following the report identification symbol.
If the NRC's criteria or regulations change so that its conclusion that the submittal is acceptable are invalidated, WOG and/or the applicant referencing the topical report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability of the topical report without revision of the respective documentation.
Sincerely, Original Signed By:
Thomas H. Essig, Acting Chief
~ Generic Issues and Environmental Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 694
Enclosure:
Safety Evaluation cc w/ enc: See next page DISTRIBUTION:
Project File JRoe/DMatthews RCaruso PUBLIC TEssig LLois PGEB r/f FAkstulewicz AEl-Bassioni OGC PWen ACRS FGrubelich DOCUMENT NAME: G:\pxw\wog15029.ser To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy withattachment/ enclosure N = No copy M ///f/f/
OFFICE PM:PGEB 6 BC:EMEB 4 SC:PGEB J4 (A) BC:PGEB NAME PWen:sw 'Pcv/ RWessh FAkstulewicz TEssig h DATE 11/ Cl/98 11/ @ /98 11/ f J/98 gg/ gg /93 ;
OFFICIAL RECORD COPY
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