ML20128F056
| ML20128F056 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/02/1993 |
| From: | Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19303F273 | List: |
| References | |
| NYN-93020, TAC-M85493, NUDOCS 9302110223 | |
| Download: ML20128F056 (5) | |
Text
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eab k NH O3874 Telephone (603)474 9521 j
Facsimile (603)474 2987
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Energy Service Corporation Ted C. Feigenbaum Senior Vice President and Chief NuclearOfficer N YN-93020 February 2,1993 I
United States Nuc! car Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
References:
(a)
Facility Operating License No. NPF-86, Docket No. 50-43 (b)
TAC No, M85493 (c)
North Atlantic Letter, NYN-92162, dated November 25,1992 ' License Amendment Request 92-14; incore Detector System", (T A C No.
M85020), T.C. Feigenbaum to USNRC
Subject:
Request for NRC Review and Approval of Analysis Methodologies to be Applied to Seabrook Station Gentlemen:
North Atlantic Energy Service Corporation (North Atlantic) requests NRC review and approval of the enclosed topical reports which describe core reload analysis methodologies that North Atlantic proposes to use in support of future operation of Seabrook Station.
Enclosed are copics of three proprietary topical reports that have been prepared by Yankee Atomic Electric Company (YAEC) acting as agent for North Atlantic. Since the topical reports contain information which is considered proprietary to YAEC, an affidavit pursuant to 10CFR2.790 is also enclosed (Enclosure A).
YAEC 1849P, (Enclosure B), describes tfic extension of YAEC's NRC approved thermal. hydraulic subchannel analysis methodology for Pressurized Water Reactors (PWRs) to the VIPRE-01 computer code for application at Seabrook Station. YAEC has performed analyses to support core reloads for the Yankee Nuclear Power Station (YNPS) and the Maine Yankee Atomic Power Station (MYAPS) with approved applications of this methodology using the COBRA-IIIC computer code since the early 1970's.
YAEC-1854P, (Enclosure C), describes the extension of YAEC's NRC approved methodology for determining core thermallimit protection function setpoints for application at Seabrook Station. YAEC has utilized its current methodelogy to determine core thermal design limit protection function setpoints for MYAPS since the late 1970's.
YAEC-1856P,(Enclosure D), describes YAEC's extension of NRC approved RETRAN computer code applications for analysis of Seabrook Station systems to include the full range of non-LOCA events considered in Chapter 15 of the UFSAR. YAEC has performed safety
. analyses in support of both PWRs and Boiling Water Reactors (BWRs) using.either the RETRAN or GEMINI II computer codes since the ectly 1970's. These analyses have been Ig&
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s United States Nuclear Regulatory Commission February 2,1993 Attention:
. Document Control Desk Page two 4
reviewed and approved by the NRC and used'in support of YNPS, MYAPS, Seabrook Station and Vermont Yankee. North Atlantic intends to have YAEC extend the range of. Its application of RETR AN for PWRs to additional non LOCA transients, i.e., to the full range of transients for which the RETRAN computer code has received NRC approval, c
The three topical reports provide comprehensive documentation of the methodologies-previously employed by YAEC and Westinghouse for core reload analysis of PWRs. The
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methodologies also complement the advanced in-core power distribution measurement system at Seabrook Station [ Reference (c)].
3 These methodologies will be applied by YAEC to its continuing support of PWRs, including Seabrook Station to improve operational flexibility, capacity factor, and cycle economics while maintaining or-even increasing the current level of plant safety. These operational improvements will be achieved by applying these methodologies in tw; separate but linked phases.
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In the first phase, the Wide Band Delta-! Program, the methodologies will be applied to permit optimum use of the core power distribution;information continuously 'available from the fixed in core detectors at Seabrook Station. A benefit in operational flexibility will be realized by using the continuous core power. distribution information to relax the l
constraints currently imposed on axial flux difference (or Delta 1) in the Seabrook Station Technical Specifications. North Atlantic's goal is to begin wide band Delta-1 operation in Cycle 4.
The Cycle 4 startup is currently scheduled for May 1994. The enclosed topical reports are submitted at this time to permit a timely NRC review and approval of the methodologies consistent with application in Cycle 4.
Associated Technical Specification-E.
changes are scheduled to be submitted in October 1993.
In the second phase, the Fuel Procurement Program, the methodologies will be applied to achieve improved fuel cycle economics. This benefit wi.ll be realized through a relaxation in the constraints currently imposed on core power distribution peaking factors and moderator tempereture coefficient in the Seabrook Station Technical Specifications.
These relaxations will permit greater flexibility in future core designs using a fewer number of fresh fuct assemblies. The methodologies, combined with improved fuel design featuces permit this benefit while maintaining or even increasing the current icvel of plant safety.
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- North Atlantic's goal is to obtain this benefit starting'with Cycle 5, currently scheduled to begin in November 1995. Associated Technical Specification changcs are scheduled to be submitted in October 1993 in order to support the Cycle 5 fuel procuremint schedule of September 1,1994 The two phases are linked through the use of the analyris methodologies documented in the enclosed topical reports and through required changes to common sections of the Seabrook Station Technical Specificatio_ns. North Atlantic believes that significauttbenefit
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can be gained in a meeting uuring which North' Atlantic can provide explanations of the
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topical reports, the Wide Band Delta I Program, the Fuel Prt>curement Program, theic 4
. combined schedules and the proposed implementation strategy. Necth Atlantic requests such p
a meeting with the appropriate NRC technical staff in early 1993.
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United States Nuclear Regulatory Commission February 2,1993 Attention:
Document Control Desk Page three Should you have any questions regarding this request, please contact Mr. Terry L.
Harpster, Director of Licensing Services, at (603) 474-9521 extension 2765.
Very truly yours, h
Ted C. Feigenbaum TCF:MDO/act Enclosures
. cc:
Mr. Thomas T. Martin (1 copy)
. Regional Administrator U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Senior Project Manager (6 copies)
Project Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley (1 copy)
NRC Senior Resident Inspector P.O. Ilox 1149 Seabrook NH 03874
North Atlantic February 2,1993 i
9 ENCLOSURE A TO TJYN-93020 Affidavit Pursuant To 10CFR2.790 4
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q-AFFIDAVIT PURSUANT TO 10CFR2.790 YANKEE ATOMIC ELECTRIC COMPANY)
NUCLEAR SERVICES DIVISION
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COMMONWEALTH OF MASSACHUSETTS )
WORCESTER COUNTY
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ss I,
Stephen P.
Schultz, depose and say that I an a Vice President of Yankee A?.omic Electric Company, duly authorized to make this affidavit, and have reviewed-or cause to have reviewed the information which is identified as proprietary.- I am submitting this affidavit in conformance with the provisions of 10CFR2.790 of the Commission's regulations for withholding this information from public disclosure.
The information for which proprietary treatment is sought is contained in topical reports YAEC-1849P, YAEC-1854P, and YAEC-1856P dated November, 1992.
q Pursuant to the provisions of Paragraph (b) (4) of Section 2.790 of the Commission'a regulations, the following-is furnished for consideration by the Commission in determining whether the information in the above reports should be withheld from public disclosure:
1.
The material contained in the topical reports was obtained at considerable expense to Yankee Atomic Electric Company and our sponsor companies, and the release.of it would seriously affect our competitive position as a supplier of nuclear design analysis software and services.
2.
The information contained in the topical reports is of the type customarily held in confidence and not customarily disclosed to the publ:.c.
3.
This information is being transmitted to the Commission in confidence under the provisions of 10CFR2.790 with the understanding that it is to be received in confidence by the Commission.
4.
This information is for Commission internal use only and-should not be released to persons or organizations outside L
the Directorate of Regulation and the ACRS without-prior approval of Yankee Atomic Electric Company.
Should it
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become necessary to release this information to such persons as part of the review process, please contact Yankee Atomic Electric Company.
l Further deponent sayeth not.
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S.Jf. Schultz Vice President i
_ Sworn to before me this l
c#(,,
th day of November, 1992 i
M Kathryn Gites,/ Notary Public
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My Commission Expires 01/24/97
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