ML20248A046

Application for Amend to License DPR-61,modifying Proposed Tech Spec 3.12, Electrical Power Sys, Provided in .Tech Spec Incorporated Degraded Grid Voltage Protection Requirements in Westinghouse STS Format

ML20248A046
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/01/1989
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20248A051	List: B13327, Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests ML20248A046
References
B13327, TAC-66797, NUDOCS 8908080192
Download: ML20248A046 (3)

Text

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7 NOttTHEAST UTILITIES c,.nor.i Omc . s.io.n stro,i, s.riin. Conn.ciicui l s' 'd >=

P.O. BOX 270 HARTFORD, CONNECTICUT 06141-0270 i k L J 7.70Z"w".,,, (203) 665-5000 i

August 1, 1989 i Docket No. 50-213 B13327 Re: 10CFR50.90  !

U.S. Nuclear Regulatory Commission  ;

Attention: Document Control Desk i Washington, DC 20555

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Gentlemen: I I

Haddam Neck Plant i Proposed Revision.to Technical Specifications  !

Electrical Power Systems (TAC No. 66797)  !

Additional Information  !

On August 29, 1988,(I) Connecticut Yankee Atomic Power Company (CYAPCO) submitted a proposed amendment to Facility Operating License DPR-61 by incor-  ;

porating the changes identified in Attachment I of the August 29, 1988 letter into the Technical Specifications of the Haddam Neck Plant. A new Technical Specification 3.12 entitled " Electrical Power System" was proposed .which  !

incorporated the degraded grid voltage protection requirements in the Westing- 1 house (H) Standard Technical Specification (STS) format, j The purpose of this submittal is to modify the pr, posed Technical Specifica-  !

tions provided in the August 29, 1988 letter by incorporating: (1) proposid changes agreed to during a March 30, 1989 NRC + Ming and' subsequent conf l ence calls and documented in draft form in a 'Ter dated June 9,1989,g +

(2) proposed changes necessitated by the new switchgear building modifica-tions, (3) proposed changes-to the numbering and format to be consistent with  ;

the H STS including a clarifying action statement emphasizing that entry into Mode 5 from Mode 6 is not permitted while in a limiting condition of opera-tion, and (4) a clarification of the Level 1 undervoltage surveillance test which was submitted as a proposed technical specification by letter dated (1) E. J. Mrotzka letter to U.S. NRC Document Control Desk, "Haddam Neck  :

Plant Proposed Revision to Technical Specifications - Electrical Power '

Systems (TAC No. 66797)," dated August 29, 1988.

(2) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission Document Control Desk, "Haddam Neck Plant - Additional Information Regarding Proposed Prif sion to Technical Specifications - Electrical Power Systems (TAC No. 66/97)," dated June 9, 1989.

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U.'S. Nuclear Regulatory Commi.sion B13327/Page 2 August 1, 1989 June 23, 1989.(3) The proposed Techni' 41 Specifications are included in Attachment 1 (Revised Technical Specifications). These changes are further described in Attachment 2. ,

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This reformatted proposed Technical Specification is or.e in a series of the improved the set of Technical first supplement Specifications was submitted on October for the Hadd26,1988.gNeck Plant of whi CYAPC0 has reviewed the proposed changes in accordance with 10CFR50.92 and has determined that they involve no significant hazards considerations. The i l

switchgear additions do not represent any degradation to the design basis l safety analysis. The addition of the 480 volt bus No.11 and 120 volt AC l vital bus Nos. C1 and D1 into the Technical Specifications does not introduce  !

failure modes different from those previously analyzed for 480 volt bus Nos. ,

4, 5, 6, and 7 and 120 volt AC vital bus Nos. C and D. In actuality, they improve the design basis safety analysis by adding 10CFR50, Appendix R l shutdown capability, and improved electrical train separation. It should be '

noted that the significant hazards consideration discussion prey!ously includ-ed in the August 29, 1988 letter is still applicable for the above changes.

l Moreover, the Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain examples (March 6, 1986, 51 FR 7751) of amendments that are considered not likely to involve a significant hazards consideration. The changes proposed herein are enveloped by example (ii), a change that constitutes an additional limitation, restriction or control not previously included in the Technical Specifications. These proposed changes would add LCOs and surveillance requirements for the electrical power systems. This will help ensure the operability and reliability of the A.C. and D.C. power sources and associated distribution systems during operation, and ensure that sufficient power will be available to supply the safety-related equipment required for: (1) the safe shutdown of the facility and (2) the mitigation and control of accident conditions within the facility.

The Haddam Neck Plant Nuclear Review Board has reviewed and approved the proposed changes and has concurred with the above determinations.

We believe the information contained in this letter, along with the informa-tion provided in the August 29, 1988 letter, provides a complete basis - for (3) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission Document Control Desk, " Proposed Revision to Technical Specification Section 2.0, 3/4.3 of the Rcvised Technical Specifications," dated June 23, 1989.

(4) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission Document Control Desk, " Amendment Request for Sections 1.0, 3/4.2, 3/4.9, 3/4.10, 3/4.11, 5.0 ed 5.0 of the Revised Technical Specifications," dated October 26, 1988.

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'U.S. Nuclear Regulatory Commission j B13327/Page 3 i August 1, 1989  ;

a)prrval of the requested amendment. CYAPC0 requests review and issuance of t11s proposed licensed amendment by October 6,1989 to support startup from the 1989 refueling outage. Should the NRC Staff have any additional questions, please contact our licensing representative directly. l

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Very truly yours, '

CONNECTICUT YANKEE ATOMIC POWER COMPANY ,

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E. K)ffoczka /

Seniof Vice President i l

cc: W. T. Russell, Region I Administrator i A. B. Wang, NRC Project Manager, Haddam Neck Plant i J. T. Shedlosky, Senicr Resident Inspector, Haddam Neck Plant I Mr. Kevin McCarthy, Director i Radiation Control Unit '

Department of Environmental Protection Hartford, CT 06116 1

l STATE OF CONNECTICUT i ss. Berlin I COUNTY OF HARTFORD Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Connecticut Yankee Atomic Power Company, a Licensee herein, that he is authorized to execute and file the  !

foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information are tree and correct to the best of his knowledge and belief.

bw%.

No",ary Public

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