ML17278A463

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Amend 17 to License NPF-21,revising Tech Specs to Change Surveillance Requirement 4.6.1.8.2 to Permit Greater Leakage Through Drywell & Suppression Chamber Purge Supply & Exhaust Isolation Valves
ML17278A463
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 11/01/1985
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17278A464 List:
References
TAC-59750, NUDOCS 8511070430
Download: ML17278A463 (8)


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1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.

2 AhENDliENT TO FACILITY OPERATING LICENSE License No. NPF-21 Amendment,No.

17 1.

The Nuclear Regulatory Commission (the Comilission or the NRC) has found that:

A.

The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee) dated Septeniber 26, 1985, complies with the standards and requi rements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's. regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application as

amended, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health arid safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulaticrs sct forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security oI the health and safety of the public; and E.

The i suance of this amendment is in accordance with 10 CFR Part 51 of the CommissioIi's regulations and all applicable requirements have been satisfied.

2.

Accordingly, Facility Operating License No.

NPF-21 is amended to revise the Technical Specifications as indicated in the attachment to this amendment and paragraph 2.C.(2) of Facility Operating License NPF-21 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

17, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the EnvironIIIental Protection Plan.

85ii070430 85ii0i PDR ADOCK 05000397-'

PDR

3.

This amendment is effective as of September 26, 1985.

FOR THE NUCLEAR REGULATORY CONIISSION Halter R. Butler, Chief Licensing Branch Ho.

2 Division of Licensing

Enclosure:

Changes to Technical Specifications Date of Issuance:

~0V

> 1985

3.

This amendment is effective as of September 26, 1985.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Chief Licensing Branch No.

2 Division of Licensing

Enclosure:

Changes to Technical Specifications Date of Issuance:

  • Previously concurred:

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ATTACHMENT TO LICENS AMENDtiEVT NO.

17 f~

DOCKET NO. 50-39 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.

The revised paoe is identified by Amendment nuiriher and contains a vertical line indicating the areas of change.

REYOYE 3/4 6-11 INSERT 3/4 6-11

CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6. 1.8 The drywell and suppression chamber purge system may be in operation with the drywell and/or suppression chamber purge supply and exhaust butterfly isolation valves open for inerting, deinerting, or pressure control, provided that each butterfly valve is blocked so as not to open more than 70 PURGING through the Standby Gas Treatment System shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

'a e With a drywell and/or suppression chamber purge supply and/or exhaust butterfly isolation valve open for other than inerting, deinerting, or pressure control, or not blocked to less than or equal to 70~

open, close the butterfly valve(s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With a drywell and suppression chamber purge supply and/or exhaust isolation valve(s) with resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.8.2, restore the inoperable valve(s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.6. 1.8. 1 When being opened, the drywell and suppression chamber purge supply and exhaust butterfly isolation valves shall be verified to be blocked so as to open to less than or equal to 70'pen, unless so verified within the previous 31 days.

4.6.1.8.2 At least once per 6 months, on a

STAGGERED TEST BASIS, each 24-and 30-inch drywell and suppression chamber purge supply and exhaust isolation valve with resilient material shall be demonstrated OPERABLE by verifying that the measured leakage is:

a.

Less than or equal to 0.05 L

per valve test or, Greater than 4.6. 1.8.2.a.

provided that:

1) the valves are secured closed and maintenance performed at the next plant cold shutdown to reduce the leakage to within 4.6. 1.8.2.a;
2) the leakage added to the previously determined total for all valves and penetrations subject to Type B and C tests per LCO 3/'4.6. 1.2 shall be less than 0.6 L

C.

In the event the valves are to be operated, and 4. 6. l. 8. 2. a.

has been

exceeded, a leakage test must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following operation, to ensure compliance with 0.6 L

WASHINGTON NUCLEAR - UNIT 2 3/4 6-11 Amendment No.

17

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