ML20216B623

Amend 121 to License NPF-30,revising SRs of TS 3/4.7.4, Essential Svc Water Sys, by Removing Requirement to Perform 3/4 7.4.b,4.7.4.b.2 & 4.7.4.c During Shutdown

ML20216B623
Person / Time
Site:	Callaway
Issue date:	02/24/1998
From:	Westreich B NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216B625	List: ML20216B623 ML20216B628
References
NUDOCS 9803130132
Download: ML20216B623 (4)

Text

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j NUCLEAR REGULATORY COMMISSION 2

WAsMINGToN, D.C. 3008641001 UNION FI FCTRIC COMPANY CAI I AWAY PLANT UNIT 1 4

DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATiiWiUG3yQ Amendment No.121 License No. NPF-30 i

1.

The Nuclear Regulatory Commission (the Commission) has fou,d that:

A.

The application for amendment to the Callaway Plant Unit 1(the facility) Facility Operating License No. NPF-30 filed by the Union Electric Company (the Company), dated August 8,1997, 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, as amended, the provisior.s of the Act, and the rules and 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; l

D.

The issuance of this license amendment will not be inimical to the common

?ense and security or to the health and safety of the public; and

)

E.

i m issuance of this amendrrrat is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfim$.

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-30 is hereby amended to read as follows:

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9903130132 900224 PDR ADOCK 05000483 i~

P PDR l

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ATTACHMENT TO LICENSE AMENDMENT NO.121 FACILITY OPERATING LICENSE NO. NPF-30 1

DOCKET NO. 50-483 i

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Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3/4 7-12 3/4 7-12 l

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., (2) Technical Soecifications and Environmentaf Protection Plan i

The Technical Specifications contained in Appendix A, as revised through Amendment No.121 and the Environmental Protection Plan contained in Appendix 1

B, are hereby incorporated in the license. The licensee shall operate the facility in l

accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance to be implemented within 30 days from the date ofissuance.

FOR THE NUCLEAR REGULATORY COMMISSION M/ \\ \\

D i

AV~

Barry. Westreich, Project Manager Project Directorate IV-2 Division of Reactor Projects fil/IV Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of Issuance: February 24,1998 i

PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent essential service water (ESW) loops shall be OPERABLE.

3 APPLICABILITY: MODES 1. 2. 3. and 4.

ACTION:

With or.ly one ESW loop OPERABLE. restore at least two ESW loo)s 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 at least HOT STANDBY within tie next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l SURVEILLANCE REQUIREMENTS 4.7.4 At least two ESW loops shall be demonstrated OPERABLE:

i a.

At least once per 31 days by verifying that each valve (manual.

power-operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

In addition, at least once per 31 days, an ANALOG CHANNEL OPERATIONAL TEST of the differential pressure instrumentation for automatic isolation of the ESW to the air compressors shall be performed; b.

At least once per 18 months by verifying that:

l 1)

Each automatic valve servicing safety-related equipment or

)

isolating the non-nuclear safety-related portion of the system actuates to its correct position on a loss-of-Power or Safety Injection test signal and on a simulated High Differential Pressure test signal; and 2)# Each ESW System pump starts automatically on a Safety Injection.

Loss-of-Power test signal, and during shutdown on a Low Suction Pressure (AFW pumps).

c.

At least once per 18 months by performing a CHANNEL CALIBRATION of l

the differential pressure instrumentation for automatic isolation of the ESW to the air compressors.

1. The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1. 1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

CALLAWAY - UNIT 1 3/4 7-12 Amendment No. 8.121