ML20196K728

Application for Amend to License DPR-3,modifying Tech Spec Table 3.6.1, Containment Barriers to Delete Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, to Add Requirements for Level Switch.Fee Paid

ML20196K728
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
ML20196K730	List: ML20196K728 ML20196K736
References
FYR-88-89, PD-217, NUDOCS 8807070091
Download: ML20196K728 (3)

Text

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• Telephone (r? ti) 872-8100

? TWX 710480-7619 YANKEE ATOMIC ELECTRIC COMPANY 1671 Worcester Road, Framingham, Massachusetts 01701 Yg N I June 27, 1988 PC 217 FYR 88-89 Unfted States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

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

Subject:

Technical Specifications Governing Containment Isolation Barriers and Main Coolant Leakage Detection Systems

Dear Sir:

Pursuant to Section 50.90 of the Commissions Rules and Regulations, the Yankee Atomic Electric Company (YAEC) hereby requests the authorization to make the following changes:

Proposed Change Referhnce is made to the Technical Specifications of License No. DPR-3 of the Yankee Nuclear Power Station. We propose to modify the license as follows:

1. Modify Technical Specification Table 3.6.1, Containment Barriers, to delete valve VD-V-752.

2. Modify Specification 3.4.5.1, Main Coolant Leakage Detection Systems, to: (l) add operability, action, and surveillance requirements for the neutron shield tank telltale level switch, and (2) revise the operability, and action statements pertaining to the Containment Atmosphere Particulate Monitoring System to provide consistency in system name with the applicable surveillance section of the referenced specification.

Reason and Basis for Change Proposed modifications in the nonsafety class portion of the neutron shield tank cavity leakage collection piping will prevent such leakage from being collected and monitored in the installed Containment Drain Collection System.

The neutron shield tank telltale leakage monitoring connections are currently monitored periodically for evidence of leakage. Should excessive

( leakage occur, the existing configuration allows the excess fluid to be directed to the Containment Drain Collection System located in the Primary Auxiliary Building. This overflow feature is being eliminated and replaced l

with a level switch and the necessary piping and valves to manually align the drains to the Containment Drain Collection System if required.

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United States Nuclear Regulatory Commission June 27, 1988 Page 2 FYR 88-89 To Facilitate detection of leakage in both the inner and outer telltale lines, the piping will be modified to connect the drain lines together upstream of the level switch. This will result in the elimination of one neutron shield tank telltale containment isolation valve (VD-V-752).

Description of Change

1. The revised Specification Table 3.6.1, Section B.1, reflects the deletion of Containment Isolation Valve VD-V-752 for the reasons described above.

2. The revised Specification 3.4.5.1 requires that the new level switch be operable as a subsystem of the Main Coolant Leakage Detection System.

Should the level switch be inoperable, the system will be lined up to allow any leakage to be directed to the Containment Drain Collection System. No further actions will be required once the system is realigned.

The surveillance requirements are specified to be consistent with those for the existing Main Coolant Leakage Detection Systems.

3. The revised Specification 3.4.5.1 also includes changes in the operability and action statments for the Containment Atmosphere Particulate Monitoring System to provide consistency in system name with the applicable surveillance section.

Safety Consideration This change is requested to reflect the elimination of a containment isolation valve and to reflect installation of alternate and equivalent Main Coolant Leakage Detection System necessitated by piping modification in the nonsafety class portion of the neutron shield tank telltale drain piping.

This change also includes revisions in the operability and action statements in Specification 3.4.5.1 for the Containment Atmosphere Particulate Monitoring System to provide consistency in system name with the applicable surveillance section. As such, this proposed change would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. This change does not alter the function or design basis of any safety-related system, structure, or component. The changes made to the containment boundary will eliminate a potential leakage path by removal of a containment barrier valve. The design of the proposed neutron shield tank telitale drain line level switch is equivalent to the existing detection systems and has the advantage of distinguishing leakage that originates from within the reactor cavity region from other containment drains.

2. Create the possibility of a new or different kind of accident from any previously analyzed. The proposed changes do not alter the performance or operating design bases of any plant syste.is, components, or structures.

j

, United States Nuclear Regulatory Commission June 27, 1988

. Page 3 FYR 88-89

3. Involve a significant reduction in the margin of safety. This proposed change eliminates a potential leakage path by consolidation of two containment piping penetrations to a single isolation barrier, and does not alter the allowable containment leakage during testing. The proposed change will enhance the Leakage Detection System capabilities by distinguishing leakage originating within the reactor cavity region from other containment drains.

Based on the considerations contained herein, 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, fee An application fee of $150.00 is enclosed in accordance with 10CFR170.21.

Schedule of Change These changes to the Yankee Technical Specifications are needed to support plant modifications scheduled for Cycles 19 and 20 refueling outage.

A timely review and approval of this submittal would be appreciated.

We trust that you will find this submittal satisfactory; however, should you have any questions, please contact us.

Very truly_yours,

/

YANKEE ATOMJC ELECTRIC COMPANY k Mo.b' 0 B. L. Drawbridg Vice President / Manager of Operations BLD/25.530 Enclosure 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.

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Robert H. Groce Notary Public My Commission Expires August 29, 1991 L.