ML20235V085

Application for Amend to License DPR-61,revising Tech Specs Re Core Exit Thremocouples,Main Stack wide-range Noble Gas Monitor,Reactor Vessel Water Level & RCS Subcooling Margin Monitor,Per Generic Ltr 83-37

ML20235V085
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/01/1989
From:	Mroczka E, Sears C CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20235V087	List: B13127, Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37 ML20235V085
References
RTR-NUREG-0737, RTR-NUREG-737 B13127, GL-83-37, TAC-54538, NUDOCS 8903100032
Download: ML20235V085 (3)

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N UTILETIES conor.i Ome.. . seio n street. seriin. Connecticut ARTFORD. CONNECTICUT 06141-0270 L t Ta l "Z ;"'

• C ," ", (203) 665-5000 March 1, 1989 i

Docket No. 50-213

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B13127 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

References:

(1) E. J. Mroczka letter to U.S. Nuclear Regulatory Commis-sion, Proposed Changes to Technical Specifications, Generic Letter 83-37, dated July 1, 1988.

(2) F. M. Akstulewicz letter to J. F. Opeka, Outstanding Technical Specification Issues, dated November 13, 1986.

(3) A. B. Wang letter to E. J. Mroczka, Request for Additional Information, dated October 21, 1988.

' (4) E. J. Mroczka letter to U.S. Nuclear Regulatory Commis-sion, Responses to Request for Additional Information, Regarding Technical Specification Changes for GL 83-37, dated December 2, 1988.

Gentlemen:

Haddam Neck Plant Technical Specification Changes for Generic letter 83-37 (TAC No. 54538)

On July 1,1088, Connecticut Yankee Atomic Power Company (CYAPCO) submitted a proposed amendment to facility Operating License DPR-61 for the Haddam Neck Plant (Reference (1)). That amendment would revise certain Technical Specifi-cations in response to Generic Letter (GL) 83-37 as applicable to the Haddam Neck Plant (Reference (2)).

In Reference (4), CYAPC0 provided additional information to respond to the Staff's questions (Reference (3)) regarding Technical Specification Table 3.23-1 and corresponding ACTION statements. The purpose of this letter is to submit the revised Technical Specification Table 3.23-1 and correspond-ing ACTION statements. The proposed revision as indicated in Attachment I to Reference (4) are described below:

I 1. Table 3.23-1. Item 6 - Core Exit Thermocouple The proposed change specifies that the number of core exit thermocouple (CET) will be at least 4/ quadrant except Quadrant IV which may have only 3/ quadrant and that the tc,tal number of channels will be 16/ core. In 8903100032 890301 PDR P

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d.S. Nuclear Regulatory Commission B13127/Page 2 March 1, 1989 addition, Technical Specification Table 3.23-1 has been revised to include ACTION Statement 6 for less than the minimum channels operable for the CETs. )

2. Table 3.23-1. Item 7 - Main Stack Wide Ranae Noble Gas Monitor ACTION Statement 3 has been revised to include the words "a Preplanned."

3. JJble 3.23-1. Item 9 - Reactor Vessel Water Level Technical Specification Table 3.23-1 has been revised to include ACTION Statement 4 for less than the minimum channels operable for reactor vessel water level.

4. Table 3.23-1. Item 10 - Reactor Coolant System (RCS) Subcoolina Marain Monitor Technical Specification Table 3.23-1 has been revised to include ACTION Statement 4 for less than the minimum channels operable for the RCS subcooling margin monitors. In addition, ACTION Statement 8 has been revised to include the Staff's recommended words to limit the time the RCS subcooling margin monitors can be inoperable.

CYAPC0 has reviewed the proposed changes in accordance with 10CFR50.92 and has determined that they involve no significant hazards consideration. It is noted that the significant hazards consideration discussion included in Reference (1) is also applicable for the above changes. The lladdam Neck Plant Nuclear Review Board has reviewed and approved the proposed changes and has concurred with the above determinations.

The enclosed additional information (Attachment 2) is provided in response to the Staff's verbal request regarding (1) use of the power-operated relief valves (PORVs) in lieu of the reactor coolant system vent valves, (2) the containment high-range radiation monitor alarm / trip set points, and (3) con-tainment water level (narrow range) instrumentation. As indicated in Attach-ment 2, CYAPC0 expects to submit the revised Technical Specification Table 3.23-1 to the NRC by April 30, 1989. Of course, should the Staff have any additional questions, CYAPC0 will be available to discuss the Staff's concerns.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY t

E.. h b reh E. J. Mroczka 4 Senior Vice President ALOA/L By: C. F. Sears Vice President

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d.S.NuclearRegulatcryCommission B13127/Page 3 March 1, 1989 cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 STATE OF CONNECTICUT)

) ss. Berlin COUNTY OF HARTFORD )

Then personally appeared before me, C. F. Sears, who being duly sworn, did state that he is 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 Licensees herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief.

bNothy*m.

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