Text

Amend 154 to License DPR-46,changing TS to Add Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer
	ML20106B086
Person / Time
Site:	Cooper
Issue date:	09/22/1992
From:	Larkins J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20106B089	List: ML20106B086; ML20106B091;
References
	NUDOCS 9209300300
	Download: ML20106B086 (6)
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(([@ASKA PUBLIC POWER DISTRICT DOCKET N0. 50-298 COOPER NUCLEAR STA110N AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. DPR-46 1.

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

A.

The application for amendment by Nebraska Public Power District (the licensee) dated October 7, 1991, 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:

(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; D.

The issuance of this license 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 LFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendnent snd Paragraph 2.C.(2) of facility Operating License No. DPR-46 is hereby amended to read as follows:

2.

Technical Specificationi The Technical Specifications contained in Appendix A, as revised through Amendment No.154, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION v-%

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John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects - !!!/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Vate of Issuance: September 22. 1992 l

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AllMHMENT TO Ll&[1(SL AMENDMENT NpJit, jfCJt ITY OPERAllNG LICENSE N04_0PR-45 DDIKET NO. S h218 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

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

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NOTES FOR TABLE 3.2.H Action:

A.

With the number of operable components less than required by the minimurn co;tponent operable requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1)

Either restore the inoperable component (s) to operable status within 7 days of the event, or r

2)

Prepare and submit a Special Report to the Comreission within 14 days following the eve r.t outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

B-The following actions will be taken if the minimum number of operable instrunent channels as required are not operable:

1)

With the number of operable channels one less than the minimum number of operstle channels shown, restore the inoperable channel to operable status within 30 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , 2)

With no operable channels available, restore at least one channel to operable status within 7 days or be in at least hot shutdown within the nes: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , Notes:

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These 2nstruents are required to be operable at all times except when the reactor is in cold shutdown or in the RETUEL mode during a refueling outage.

2.

With two channels operable, the normal condition is with one analyter in the s ancbv moce.

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rnOPER hTCTIAR STATTON T A T',1 E. :s. 2. t i rA1.1 BPATION 'TTQT'ENrY FOR POST-ACCIDENT T*JITORING TN"TRINENTATION+

I n s t r ' m'e n t Function Calibration ipytrument IDRmN r_

Test Fre<nte_ne v Freg y ncy Elevated Eclease Point (ERP)

Monitor (Iligh Range Noble EMP-FM-3R Once/ Month Once/ Cycle Gas)

Turbine Building Ventilation FMV-FM-70B Once/ Month Once/ Cycle Exhnost Monitor (Iligh Rnng. Noble Cas)

Radwaste/ Augmented Radwaste RMV-RM-30B Cnce/ Month Once/ Cycle Exhaue.t Monitor (Illgh Range Noble Cas) f Primary Cer.talnment Gross FMA-RM-40A Once/ Mon' h Once/ Cycle Radiation Monitors **

FitA-EM-40B l

Primary Containment flydrogen PC-AN-!! /0 1 Once/ Month Once/ Quarter 2

2 Concentration Analyter PC-AN-11,,/0 II 2

3=

S

Note:

Other Post-Accident Monitoring Instrumentation calibration requirements are in Table 4.2. F-Dr, eell Pressure, S

PC-PR-1A and IP, Suppression Chamber / Torus tJater !> vel PC-ilt-1 A and IB.

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- CliANNEL CALIBRATION shall consist of an electronic calibration of the charmel, not including the

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detector, for range decades above 10 R/hr and a one point callhration check of the detector below

'O R/hr with an installed or portable gamma source.

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ML20106B086

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