ML20095L184

Forwards License Amend Request 91-11 to License NPF-86 for Code Safety Valve Setpoint Tolerance Relaxation & Topical Rept YAEC-1847, Seabrook Station Code Safety Valve Setpoint Tolerance Relaxation

ML20095L184
Person / Time
Site:	Seabrook
Issue date:	05/05/1992
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20095L191	List: ML20095L184 ML20095L195 ML20095L197 ML20095L208
References
NYN-92059, NUDOCS 9205060269
Download: ML20095L184 (2)

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New Hampshire . -

Y Ted C. Feigenbaum  !

I President and Chief Esecutive Of ficer l

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NYN-92059 hiay 5,1992 United States Nuclear Regulatory Commission Washington, D.C. 20555

.\ t t e n tio n: Document Control Desk

Reference:

Facility Operating License No. NPF-86, Docket No. 50-443 S ubject : License Amendment Request 91 11: Code Safety Valve Setpolat Tolerance Relaxation Gentlemen:

Pursuant to 10CFR50.90 New Hampshire Yankee (NHY) hereby transmits License Amendment Request 91-11 as Enclosure 1. This License Amendment Request is distributed pursuant to 10CFR50.4.

The purpose of License Amendment Request 91-11 is to propose changes to the Seabrook Station Technical Specifications io allow a relaxation in the Pressurizer Safety Valve (PSV) and Niain Steam Safety Valve (h1SSV) setpoint tolerances to 3E New llampshire Yankee proposes to utilize the 3% tolerance for the 'as-found" acceptance criteria for additional valve testing required by AShlE Section XI, Article IWV-3513. The proposed Technical Specification changes require that the PSV and AISSV setpoints be

' restored to within 1% of their nominal setpoints following testing. New Hampshire Yankee is also proposing to revise the BASES for Technical Specification 3/4.7.1.1 to specify the correct Edition of the ASA1E Boiler and Pressure Vessel Code, Section til applicable to the htSSVs. The proposed relaxation of the PSV and htSSV setpoint tolerances complies with the 1989 Edition of the AshlE Code,Section XI. The proposed relaxation of the PSV and htSSV setpoint tolerances has been evaluated by Yankee Atomic Electric Company (YAEC) for NilY and is documented in topical report YAEC-1847 (enclosed in Section VIII).

License Ame dnent Request 91-11 has been reviewed and approved by the NHY Station Operation view Committee and the Nuclear Safety Audit Review Committee.

As discussed in the enclosed License Amendment Request 91-11,Section V, the proposed changes have been determined not to involve a significant hazards consideration pursuant to the standards of 10CFR50.92. A copy of this letter and the enclo<ed License Amendment Request 91-11 have been forwarded to the State of New llampshire State Liaison Officer pursuant to 10CFR50.91(b). Additionally, NHY has determined that License Amendment Request 9111 meets the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement (see Section Vil, enclosed).

9205060269 920505 PDR ADOCK 05000443 P PDR 1

" b ^ ' fhliw Hampshire Yankee Division of Public Service Company of New Hampshire 1 P.O. Box 300

• Seabrook, NH 03874

• Telephone (603) 474 9521 i

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) United States Nuclear Regulatory Commission. May 5,1992 Attention: Document Control Desk Page two New 11ampshire Yankee requests _NRC review of License Amendment Request 9111 l and issuance of a license amendment by August 31,1992 (see enclosed License Amendment Request 91-11, Section. VI). This schedule is proposed in support of code safety valve testing which is required to be performed pursuant to the NIIY .Inservio Test Program

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during the second refueling outage which is scheduled to begin in September 1992.

4 Should you have any questions regarding this letter, please contact Mr. Terry l-Ilarpster, Director of Licensing Services, at _(603) 474-9521, extension 2765, y

Very truly~ yours, Kh:t! < h, W Ted C. Feigeniih m 1

TCF: A LL/act  !

i j Enclosure f ec: Mr. Thomas T. Martin

Regional Administrator

United States Nuclear Regulatory Commission i Region I i 475 Allendale- Road

) King of Prussia, PA - 19406

{- Mr. Gordon E. Edison,- Sr. Project Manager 1

Project Directorate 1-3 d

_ Division of Reactor Projects i U.S. Nuclear Regulatory Commission

! Washington, 'DC 20555 -j i

!- Mr. Noel Dudley i l NRC Senior Resident- Inspector i P.O. Box 1149

Scabrook, Nil 03874-i Mr. George L. Iverson, Director

j. New llampshire Office of. Emergency Management 'l-i- 107- Pleasant Street Concord, NH 03301 .;

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