ML20085B457

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Forwards 1991 Annual Rept of ECCS Evaluation Model Revs,Per 10CFR50.46
ML20085B457
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 07/26/1991
From: Feigenbaum T
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-91120, NUDOCS 9108010251
Download: ML20085B457 (5)


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6 New Hampshire Y

hh Ted C. Feigenbaum Presdent and Chief Execunve Officer NYN 91120 July 26,1991 United States Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Document Control Desk

References:

(a)

Facility Operating License No. NPF-86, Docket No. 50 443 (b) 10CFR50.46, Acceptance Criteria for Emergency Core Cooling System for Light Water Nuclear Power Reactors

Subject:

10CFR50.46 ECCS Evaluation Model Revisions Annual Report Gentlemen:

New Hampshire Yankee (NilY) has enclosed herein, pursuant to 10C FR 50.46 (a)(3)(ii), the 1991 Annual Report of Emergency Core Cooling System (ECCS) Evaluation blodel Revisions (Enclosure 1). includes a tabulation of the limiting 1.arge Break LOCA and limiting Small Break LOCA Peak Cladding Temperature (PCT) margin allocations applicable to Seabrook Station.

The PCT margin allocations reported in E. :losure I represent permanent PCT margin allocations attributable to ECCS evaluation model revisions and plant specific input assumption revisions through the period of June 1991 as reported to NilY 'ay Westinghouse on June 28, 1991.

New Hampshire Yankee notes that the PCT margin allocations for this period exceed 50 F and thus are reportable pursuant to 10CFR50.46(a)(3)(ii). This letter satisfies the 30 day reporting requirement of 10CFR50.46(a)(3)(ii) for ECCS evaluation model revisions or errors. Enclosure 1 demonstrates NHY's continuing compliance with the requirements of 10CFR50.45 and thus no additional analysis or other actions ar required.

If you have any questions regarding this letter please contact Mr. James M. Peschel, Regulatory Compliance Manager, at (603) 474 9521 extension 3772.

Very truly yours, gg h

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Ted C. Fe', nbaum Enclosure TCF:ALL/ssi/act 9109010251 910726 DR ADOCK 05000443 I

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New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

  • Seabrook, NH 03874
  • Telephone (603) 474-9521 i

f United States Nuclear Regulatory Commission July 26,1991-Attention; Document Control Desk Page two ec:

Mr. Thomas T. Martin Regional. Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. ' Edison, St. Project Manager Project Directorate 13 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington,- DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149

. Seabrook, tTH 03874 i

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New Hampshire Yankee July 26,1991 ENCI.OSURE 1 TO NYN 01120 ECCS Evaluation Model Revisions 10CFR50.46 Annual Report 1991 t

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ECCS Evaluation Model Revisions 10CFR50.46 Annual Report 1991 Peak ' Clad Temperature- (PCT) Margin Allocation Large Break LOCA A.

Analysis of Record- (Updated PCT = 1965.2 'F Final Safety Analysis - Report,

Rev. 0,'May.1991, Sec. 15.6*)

B.

ECCS Evaluation Model Revisions (thru 6/91 as reported in NAH 91-3753, dated 6/20/91) a.

Fuel Rod Initial A PCT = +25.0 'F i

Condition Inconsistency b.

Steam.

Generator A PCT = +40.0 'F 4

Seismic /LOCA Assumption C.

Plant Specific Input Assumption Revisions a.

Chamfered Pellet-A PCT = +10.0 'F l

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Tube = Plugging A PCT = +1.0 *F i.

Licensing Basis PCT + PCT Margin Allocation = 2041.2 F

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l-The Large Break LOCA analysis was performed util'izing the February 1978 1.

-version of the Westinghouse Large Break Evaluation Model.

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ECCS Evaluation Model Revisions 10CFR50.46 Annual Report 1991 Peak Clad Temperature (PCT) Margin Allocation Small Break LOCA l

A.

Analysis lof Record (Updated-PCT = 1790.0 'F Final Safety Analysis Report, Rev. O. May 1991 Sec. 15.6*,3 B.

ECCS Evaluation Model Revisions (thru 6/91 as reported in NAH 91-3753. dated 6/20/91) a.

Fuel

-Rod Init'ial A PCT = 37.0F Condition Inconsistency C.

-Plant Specific Input Assump' tion Revisions a.

Chamfered Pellet A PCT = +10.0 'F b.

Emergency-Feedwater A PCT = +136.2 'F-Enthalpy Switchover Licensing Basis PCT + PCT Margin Allocation = 1973.2 *F-The -Small-Break LOCA analysis was performed utilizing 'ne October 1975

--version of the Westinghouse ECCSl$ mall Break Evaluation Model, d

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