ML20196K104

Application for Amend to License DPR-3,adding Tech Spec Section C.2 Re Check Valves to Table 3.6-1,containing Check Valve WC-V-622 & Manual Isolation Valves WC-V-621,VD-V-1170 & VD-V-1171 to Section B.1 of Table 3.6-1.Fee Paid

ML20196K104
Person / Time
Site:	Yankee Rowe
Issue date:	06/27/1988
From:	Drawbridge B YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20196K108	List: ML20196K104 ML20196K139
References
FYR-88-90, NUDOCS 8807060514
Download: ML20196K104 (4)

Text

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' TGIsphons (017) 872 8100 TWX 710-380 7619

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YANKEE -

ATOMIC ELECTRIC COMPANY y

w 1671 Worcester Road, Framingham, Massachusetts 01701

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June 27, 1988 PC-219 FYR 88-90 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

(a) License No. DPR-3 (Docket No. 50-29)

Attachments: A. Proposed Technical Specification Changes B. Piping Modifications

Subject:

Request for Changes to Technical Specification Table 3.6-1

Dear Sir:

Pursuant to Section 50.90 of the Commission's Rules and Regulations, the Yankee Atomic Electric Company (YAEC) hereby requests the authorization to make the following change.

Proposed Change Reference is made to the Technical Specifications of License No. DPR-3.

The specific change is shown in Attachment A. We propose to modify the Technical Specifications as described below:

1. Add a new Section C.2, check valves (subject to Type C testing), to Table 3.6-1, containing Check Valve WC-V-622.

2. Add Manual Isolation Valves WC-V-621, VD-V-1170, and VD-V-1171 to Section B.1 of Table 3.6-1.

Reason for Change This proposed change covers the installation of two spare penetrations into containment. Presently, all contninment penetrations are beirg used.

These spare penetrations would be available for use as a backup to existing penetrations if one had to be taken out of service for repair during an outage where the specific service was still needed. These penetrations could also be dedicated for a specific use to meet futcre plant needs.

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' Unit'ed States Nuclear Regulatory Commission ' June 27.-1988 Page 2 FYR 88-90 Basis for Change Attachment B'is a simplified. sketch of'the new containment penetrations.

One containment penetration.will be isolated by a locked closed manual isolation valve'outside containment, and a check valve inside containment.

.The other will be isolated by a locked closed manual isolation valve inside and'outside containment.

The addition of these containment isolation provisions will be subject to surveillance and test requirements based upon current Technical Specifications and 10CFR50, Appendix J testing requirements.

Saf0ty' Considerations This. proposed addition of new containment isolation boundary valves which conform to 10CFR50, Appendix A, Criterion 56, does not expose'the plant to an r increased chance of failure of containment integrity. [

.The inside containment check valve, WC-V-622, and the outside containment, locked closed, manual gate valve, WC-V-621, will serve as containment isolation valves for one penetration into the Vapor Container.

-The inside containment, locked closed, manual gate valve, VD-V-1170, and the ,

outside containment. locked closed, manual gate valve, VD-V-1171, will serve as containment isolation valves.for the other penetration into the Vapor Container. The addition of these valves to Section 3/4 6-12 Sections B and-C, involves a change that constitutes a. limitation and control which -i presently exists in the Technical Specifications. The containment leakage limiting conditions for operation set forth in Section 3.6.1.2 are applicable to all containment barriers listed in Table 3.6-1. The addition of four valves to be Type C tested in Table 3.6-1 are pieces of equipment which shall be subject to existing requirements and limitatiens set forth in the current Technical Specifications.

As such, this proposed change would not: i

1. Involve a significant increase in the probability or consequences of an accident'previously evaluated. The new containment penetration designs conform to 10CFR50, Appendix A, Criterion 56. These '

penetrations will be Type C tested in accordance with 10CFR50, Appendix J requirements. The containment leakage limiting condition ,

for operation in Technical Specification 3.6.1.2 remains unchanged.

Any leakage attributed to these penetrations must still fit within '

Technical Specification 3.6.1.2 limits.

2. Create the possibility of a new or different ! .c f accident from '

any previously analyzed. The new containment y ao* ations are identical to existing installed equipment. The..

• allure would be identical to those previously analyzed, and would not create any new or different kind of accident. r Y

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United. States Nuclear Regulatory Commission June 27,' 1988

Page 3 ,

FYR 88-90

3. Involve'a significant reduction in a margin of safety. The new containment penetrations do not reduce the margin of safety of any Technical Specification. The limiting condition for operation of Technical Specification 3.6.1.2 remains. unchanged, ensuring the

-present margin of safety is maintained.

p Based on the consideration contained dierein, it is concluded that there is reasonable assurance that operation of the Yankee plant consistent with the proposed Technical Specifications will not endanger the health and safety of the public. This proposed change has been reviewed by the Nuclear Safety Audit.and Review Committee.

F. e e An application fee of $150.00 is enclosed in accordance with 10CFR170.21.

Schedule of Change This change to the Yankee Technical Specifications is needed to support work scheduled for the Cycle 20 refueling outage.

We trust that you will find the submittal satisfactory; however, should you desire additional information, please contact us.

Very.tr61y your ,

Y 'KEE ATOMIC LECTRIC COMPANY

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B' L. Drawbr dge Vice Presiden Manager of Operations BLD/25.612

- Attachment-COMMONWEALTH OF MASSACHUSETTS)

)ss MIDDLESEX COUNTY )

Then personally appeared before me, B. L. Drawbridge, who, being duly sworn, did state that he is Vice President and Manager of Operations of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Yankee Atomic Electric Company and that the statements therein are true to the best of his knowledge and~ belief.

~Nb Robert H. Groce

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Notary Public My Commission Expires August 29, 199l cc: USNRC Region I USNRC Resident Inspector. YNPS

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ATTACHMENT A l Proposed Technical Specification Changes I

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