ML20236H597

Application for Amend to License DPR-61,adding New Tech Spec Section Re Main Feedwater Isolation Valves.Fee Paid

ML20236H597
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/29/1987
From:	Mroczka E, Sears C CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236H599	List: B12560, Proposed Tech Specs,Adding New Section Re Main Feedwater Isolation Valves ML20236H597
References
B12560, NUDOCS 8708050259
Download: ML20236H597 (4)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N, CONNECTICUT P O. box 270

• HARTFORD, CONNECTICUT 061410270 TELEPHONE 3Uly 29,1987 203-665-5000 Docket No. 50-213 B12560 Re: 10CFR50.90 U.S. Ncclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Haddam Neck Plant Proposed Revision to Technical Specifications Feedwater Isolation Valves Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPCO) hereby proposes to amend Operating License DPR-61 for the Haddam Neck Plant by incorporating the attached proposed change into the Plant Technical Specifications.

The proposed change would add a new Technical Specification section, Main Feedwater Isolation Valves (FW-MOV-II, 12, 13, 14). This addition will subject these valves to periodic testing to ensure closure time, per the Haddam Neck inservice testing program. The accident analysis for a main steam line break in containment assumes the Main Feedwater Isolation Valves close within 70 seconds. Addition of this Technical Specification, Section 3.25, will ensure surveillance testing is performed to verify the 70 second closure time is observed. It should be noted that the valves are designed to close within 65 seconds and, therefore, the 70 secer.d closure time assumed within the accident analysis has margin built in to ensure the valve can meet this design basis assumption.

Discussion Haddam Neck feedwater penetrations (P-46, 47, 48 and 49) have valves inside and outside of containment. The outside valves are motor operated gate valves (FW-MOV-11,12,13, and 14). Since the steam generator secondary sides are considered closed loops within containment, only the outside gate valves need to be considered containment isolation vsives (per 10CFR50 Appendix A General Design Criterion (GDC) 57).

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. U.S. Nuclear Regulatory Commission

. B12560/Page 2 July 29,1987 Haddam Neck systems and procedures maintain water level and pressure on the secondary side of the steam generators in a design basis accident. The pressure differential between the secondary side of the steam generators and the depressurized primary sides (post-LOCA) will prevent reactor coolant leakage out of the generators (even with tube failures). An exemption from Appendix 3 testing of containment valves in penetrations P-46 through P-49 has been granted by the NRC on this basis (Reference Amendment #49 to License DPR-61).

Valves FW-MOV-II,12,13 and 14 will still close on receipt of a containment isolation signal. Therefore, these valves will still act as containment barriers.

This is consistent with the exemption from Appendix 3 testing of these valves granted in Amendment #49. The feedwater isolation valves act as a back-up to the feedwater regulation valves in the event a feedwater regulation valve fails open during a main steam line break accident. Classification of these valves as containment isolation valves is consistent with 10CFR50 Appendix A GDC-57 (on closed loop systems).

1 Safety Evaluation CYAPCO has reviewed the attached proposed change pursuant to 10CFR50.59 and has determined it does not constitute an unreviewed safety question. The probability of occurrence or the consequences of a previously analyzed accident have not been increased and the possibility for a new type of accident has not been created. The proposed change is consistent with 10CFR50 Appandix A, G DC-57.

Effect on Design Basis Accident Analysis Since this amendment request only documents the existing plant configuration,it does not affect the design basis accident analysis of the Haddam Neck Plant. In addition, the inclusion of the valves FW-MOV-II,12,13, and 14 in the inservice testing program will ensure that they will perform their back-up furiction to the feedwater regulating valves.

Potential for Creauon of Unanalyzed Accident Tnis amendment request only adds a surveillance requirement to existing valves.

It does not create the possibility of an accident or malfunction of a different type than evaluated previously in the safety analysis report.

Effect on the Margin of Safety Since this amendment request adds a surveillance requirement for added reliability, it does not reduce the margin of safety as specified in the basis of any Technical Specification. In fact, it ensures more adequately the margin of safety.

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. U.S. Nuclear Regulatory Commission

. B12560/Page 3 July 29,1987 Summary and Conclusions Based on the foregoing assessment, the change proposed herein is considered safe and does not constitute an unreviewed safety question as defined in 10CFR50.59, since it does not:

1. Increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report,

2. create the possibility for an accident or malfunction of a different.

type than any previously analyzed in the safety analysis report, or

3. reduce the margin of safety as defined in the basis of any technical specification.

Significant Hazards Consideration In acc.ordance with 10CFR50.92, CYAPCO has reviewed the attached proposuJ change, and has concluded it does not involve a significant hazards consideration.

The basis for this conclusion is that the three criteria of 10CFR50.92(c) are not compromised; a conclusion which is supported by our determinations made pursuant to 10CFR50.59. The proposed change does not involve a significant hazards consideration because the change would not:

1. Involve a significant increase in the probability or consequences of an accident previously analyzed. The proposed change does not degrade Haddam . Neck's containment capabilities, and has no impact on the probability of occurrence or consequences of an accident or malfunction of equipment important to safety.

2. Create the possibility of a new or different kind of accident from any previously analyzed. This change is consistent with 10CFR50 Appendix A GDC 57 and Amendment.#49 resolutions on 10CFR50 1 Appendix 3 as applied to containment penetrations P-46 through P-49.

3. Involve a significant reduction in a margin of safety. Adding a new Technical Specification, Main Feedwater Isolation Valves, will not l reduce any margins of safety defined in the bases for the Haddam Neck Tecianical Specifications.

1 The Commission has provided guidance concerning the application of standards in i 10CFR50.92 by providing certain examples (51FR7750, March 6,1986). The {

change proposed herein is enveloped by example (ii), in that the propsed ]

addition of Section 3.25, "Feedwater Isolation Valves", will subject the valves to  !

periodic closure timing tests per the Haddam Neck in-service testing program, constituting a more stringent surveillance requirement.

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

1 In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment.

1 J.

. U.S. Nuclear Regulatory Commission

. B12%0/Page 4

.iuly 29,1987 Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.00.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY Y.b- ACU E. J. Mroczka N Senior Vice President By: C. F. Sears Vice President cc: Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 W. T. Russell, Regic . I Administrator J. T. Shediosky, Resident inspector, Haddam Neck Plant F. M. Akstulewicz, NRC Project Manager, Haddam Neck Plant 1

I I 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.

ma%A%e JNotary PublK/

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My Commission Expires March 31,1988

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