ML20212N439

Amend 95 to License NPF-3,modifying Surveillance Requirement 4.4.10.1.b to Permit one-time Extension of Surveillance Interval for Reactor Vessel Internals Vent Valves from 18 Months Until Removal of Reactor Vessel Head

ML20212N439
Person / Time
Site:	Davis Besse
Issue date:	08/20/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML20212N443	List: ML20212N439 ML20212N446
References
NPF-03-A-095 NUDOCS 8608280230
Download: ML20212N439 (5)

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a nJg UNITED STATES E"

h NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D. C. 20555 e

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TOLED0 EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUILEAR POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. NPF-3 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated June 6, 1986, as supplemented July 30, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and 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 rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health ana safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

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. Technical Specifications The Technical Specifications contained in Appendices A and B,.as revised through Amendment No. 95 are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULAT RY COMMISSION 2

l ohn F. Stolz, Director PWR roject Directorate ision of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: August 20, 1986 e

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ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICE' SE NO. NPF-3 N

DOCKET NO. 50-346 Replace the following page.of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.

Remove Insert 3/4 4-31 3/4 4-31 i

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (C'ontinued) b.

Each internals vent valve shall be demonstrated OPERABLE at least once per 18 months during shutdown,* by:

1.

Verifying through visual inspection that the valve body and valve disc exhibit no abnormal degradation, 2.

Verifying the valve is not stuck in an open position, and 9

3.

Verifying through manual actuation that the valve is fully open when a force of 3 400 lbs. is applied vertically upward.

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• For Cycle 5 Operation, performance of this Surveillance Requirement may be deferred to coincide with the next reactor vessel head removal but no later than the Cycle 5 refueling outage.

DAVIS-BESSE, UNIT.1 3/4 4-31 Amendment No. 23, 95

REACTOR COOLANT SYSTEM J

REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 The following reactor coolant system vent paths shall be oper-able:

a.

Reactor Coolant System Loop 1 with vent path through valves RC 4608A and RC 4608B.

b'.

Reactor Coolant System Loop 2 with vent path through valves RC 4610A and RC 4610B.

Pressurizer; with' vent path through EITHER valves RC11 and

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c.

RC2 (PORV) OR valves RC 239A and RC 200.

APPLICABILITY: Modes 1, 2 and 3 ACTION:

With one of the above vent paths inoperable, restore the a.

j inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY.within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With two of the above vent paths inoperable, restore at least one of the inoperable vent paths to 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With three of the above vent paths inoperable, restore at least two of the inoperable vent paths to 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in NOT SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d.

The provisions of specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1

a 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1.

Verifying all manual isolation valves in each vent path are locked in the open position, and 1

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2.

Cycling each valve in the_ vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING, and a

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3.

Verifying flow through the reactor coolant vent system vent paths during COLD SHUTDOWN or REFUELING.

I DAVIS-BESSE, UNIT 1 3/4 4-32 Amendment No. 85 i

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