ML17278B064

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Amend 30 to License NPF-21,revising Tech Spec Section 3/4.6.4 to Permit Plant Operation W/Two of Nine Sets of Suppression chamber-to-drywell Vacuum Breakers Inoperable
ML17278B064
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/31/1986
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17278B065 List:
References
TAC-59793, NUDOCS 8611100341
Download: ML17278B064 (9)


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

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. NPF-21 1.

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

A.

The applications for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),

dated May 30,

1985, and September 30,
1985, comply with the standards and require-ments 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, 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 and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph 2.C.(2) of the Facility Operating License No. 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. 30, 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 Environmental Protection Plan.

861l100341 861031 PDR rDaCtt; 0S000397 P

PDR!

2 3.

This amendment is effective as of the date of issuance FOR THE NUCLEAR REGULATORY COYKISSION 8d'linor G ~ Adensam, Director BWR Proiect Directorate No.

3 Division of BWR Licensing

Enclosure:

Changes to the Technical Specifications Date of Issuance:

October 3l,

) 986

0 i

l I

ENCLOSURE TO LICENSE AMENDMENT NO. 30 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REYOVE.

3/4 6-34 3/4 6-35 8 3/4 6-4 INSERT 3/4 6-34 3/4 6-35 8 3/4 6-4

1

CONTAINMENT SYSTEMS 3/4.6.4 VACUUM RELIEF SUPPRESSION CHAMBER - DRYWELL VACUUM BREAKERS, LIMITING CONDITION.FOR OPERATION 3.6.4. 1 Seven of the nine pairs of suppression chamber - drywell vacuum breakers shall be OPERABLE and all nine pairs shall be closed.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

b.

With one or more vacuum breakers in up to two pairs of suppression chamber - drywell vacuum breakers inoperable for opening, verify both vacuum breakers of each pair to be closed within two {2) hours.

With one or more vacuum breakers in three or more pairs of suppression chamber - drywell vacuum breakers inoperable for opening but known to be

closed, restore the inoperable pairs of vacuum breakers such that a

minimum of seven pairs are in an OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />.

With one suppression chamber - drywell vacuum breaker open, verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; restore the open vacuum breaker to the closed position within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />.

With one closed position indicator of any suppression chamber-drywe11 vacuum breaker inoperable:

l.

Verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per 15 days thereafter, or 2.

Verify the vacuum breaker{s) with the inoperable position indicator to be closed by conducting a test which demonstrates that the hP is maintained at greater than or equal to 0.5 psi for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> without makeup within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 15 days thereafter.

3.

Otherwise, 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 />.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-34 Amendment No.

30

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS 4.6.4. 1 Each suppression chamber - drywell vacuum breaker shall be:

a.

- Verified closed at least once per 7 days (regardless of operability).

b.

Demonstrated OPERABLE:

1.

At least once per 31 days and within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after any discharge of steam to the suppression chamber from the safety/relief

valves, by cycling each vacuum breaker through at least, one com-plete cycle of full travel.

2.

At least once per 31 days by verifying both position indicators OPERABLE by observing expected valve movement during the cycling test.

3.

At least once per IS months by; a)

Verifying the opening setpoint, from the closed position, to be less than or equal to 0.5 psid, and b)

Verifying both position indicators OPERABLE by performance of CHANNEL CALIBRATION.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-35 Amendment No.

3O

t

CONTAINMENT SYSTEMS BASES OEPRESSURIZATION SYSTEMS (Continued)

Because of the large volume and thermal capacity of the.suppression

pool, the volume and temperature normally changes very slowly and monitoring these parameters daily is sufficient to establish any temperature trends.

By requiring the suppression pool temperature to be frequently recorded during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken.

The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.

In addition to the limits on temperature of the suppression chamber pool water, operating procedures define the action to be taken. in the event a

safet::/relief valve inadvertently opens or sticks open.

As a minimum this aetio:: shall include:

(1) use of all available means to close the valve, (2) initiate suppression pool water cooling, (3) initiate reactor

shutdown, and (4) if other safety/relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open safety/relief valve to assure mixing and uniformity of energy insertion to the pool.

3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES The OPERABILITY of the primary containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation within the time limits specified ensures for those isolation valves designed to close auto-matically that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

3/4. 6. 4 VACUUM RELIEF Vacuum relief breakers are provided to equalize the pressure between the suppression chamber and drywell and between the reactor building and suppres-sion chamber.

This system will maintain the structural integrity of the primary containment under conditions of large differential pressures.

The vacuum breakers between the suppression chamber and the drywell must not be inoperable in tne open position since this would allow bypassing of the suppression pool in case of an accident.

There are nine pairs of valves to provide redundancy and capacity so that operation may,continue indefinitely with no more than two pairs of vacuum breakers ihoperable in the closed position.

MASHINGTON NUCLEAR - UNIT 2 B 3/4 6"4 Amendment No.

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