ML20005F470

Forwards marked-up Page to Tech Specs to Allow Performance of Loss Offsite Power Test Using Special Test Exception Spec 3.10.6,in Response to NRC 891228 Transmittal of Revs to Tech Specs

ML20005F470
Person / Time
Site:	Seabrook
Issue date:	01/04/1990
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90004, NUDOCS 9001160309
Download: ML20005F470 (4)

Text

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L New Hampshire v.d C.. # . =

Senior Vice President and

_ _ _ Chief Operating Officer p NYN-90004 January 4, 1990 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

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References:

(a) Facility Operating License NPF 67. Docket No. 50-443 (b) USNRC Letter dated May 26, 1989, ' Issuance of Facility operating License NPF Seabrook Station, Unit No. 1,*

S. A. Varga to E. A. Brown (c) New Hampshire Yankee Letter NYN-89123 dated October 17, 1989, ' Completion of Plant Modifications Associated with SSER 8 Confirmatory Issues # 56, 58, 60,' T. C. Feigenbaum to USNRC (d) USNRC Letter" dated December 28, 1989, ' Revisions to Seabrook Technical Specifications,' V. Nerses to E. A. Brown Subjects; certification of Seabrook Station Unit 1 Technical Specifications Gentlemen:

Reference (d) transmitted revisions to the Technical Specifications for Seabrook Station which were originally provided via Reference (b). New Hampshire Yankee has reviewed these proposed Technical Specifications as compared to the current Seabrook Station Technical Specifications (Reference (a)).

As a' result of this review, required corrections to the Technical Specifications have been identified. The Technical Specifications transmitted via Reference (b) contained a Technical Specification for the Control Building HVAC System in two configurations. The required modifications to this system have been completed as documented in Reference (c): therefore, only the Specification currently designated as 3/4.7.6B should be included in the Technical Specifications issued with a full power license. The Bases should also be modified to reflect the completion of this modification. An additional correction is provided in the form of a marked-up page as Enclosure 1. This correction is required to allow the performance of the Loss of Offsite Power Test (ST-39) using Special Test Exception Specification 3.10.6.

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9001160309 900104 PDR ADOCK 05000443 p PDC l

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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 1

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. 1 United States Nuclear Regulatory Commission January 4, 1990 l Attention: Document Control Desk Page 2 New Hampshire Yankee has performed a process to certify the Technical Specifications based on a review of the Seabrook Station FSAR through 1 Amendment 62, the NRC Staff's Safety Evaluation Report through Supplement 8, and the plant's as-built condition. To the best of my knowledge and belief,  ;

P and based on the foregoing. I certify that the proposed Technical Specifications as forwarded by Reference (d), with the inclusion of the enclosed corrections, accurately reflect the as-built plant configuration, the Seabrook Station FSAR through Amendment 62, the NRC Staff's Safety Evaluation  ;

Report through Supplement 8, and other docketed correspondence with the Nuclear Regulatory Commission.

Very truly yours, fg& C P' l Ted. C. Feigenbaum Enclosures cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20555 Mr. Antone C. Cerne NRC Senior Resident Inspector ,

P.O. Box 1149 Seabrook Station, NH 03874 l

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[ SPECIAL TEST EXCEPTIONS 3/4.10.6 REACTOR COOLANT LOOPS Y,3'l>

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S ecification 3.4.1.2 may be suspended during the  !

. perfonna nce of(--'"- ' **"ti"; for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in MODE 3 -

3 S- - $rovidea 4.1.2 are(1) at least two OPERABLE, (2)reactor coolant no operations areloops as listed permitted in Specification that would cause l dilution of the reactor coolant system boron concentration. (3) the reactor trip breakers are open, and (4) core outlet temperature is maintained at least 10'F below saturation temperature.

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APPLICABILITY: During perfonnance of reted,:e.hs.1,,.4a./e-e<%

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t J : ,;e d ,s v o d ar. /e.u 4 G m & 's With less t n the,above required reactor coolant loops OPERABLE during per-formance of _atere! criros!stie? *tetd"; comply with tie provisions of the >

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. SURVEILLANCE REQUIREMENTS 1

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L 4.10.6 At least the above required reactor coolant Io,op.&<dall s be detennine  :

'a OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to initiation of =ter:? chehtur, ;;;tir- ,d,,,)

f and at least once per 4 tours during aete^el circelet'= t'etin; r ying n rre t br = her eli; r zt: eMndicated power availability and by verifying f secondary side narrow range water level to be greater than or equal to 141 1 ,

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