ML20038C437

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Safety Evaluation Supporting Amend 44 to License DPR-72
ML20038C437
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/24/1981
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20038C434 List:
References
TAC-46970, NUDOCS 8112110032
Download: ML20038C437 (2)


Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULTTION SUPPORTIflG A!1ENDf1ENT NO. 44 TO FACILITY OPERATING LICEtlSE fl0. DPR-72 1

FLORIDA POWER CORPORATION, ET AL CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT c

DOCKET NO. 50-302 Introduction By letter dated February 15, 1980, Florida Power Corporation (FPC) submitted Technical Specification (TS) Change Request No. 58 to revise requirements for

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testing of Radiation tionitor RM-A5 to be consistent with Standard Technical Specifications (STS). The change would also reduce the potential for un-necessary reactor shutdown.

Evaluation TS 4.7.7.1.e.2 presently requires the use of a high radiation test signal for the control room ventilation system tests, whereas the operability and surveillance requirements for other radiation monitoring instruments are speci-fied in Tables 3.3-6 and 4.3-3 of the TSs. With the surveillance requirements for Radiation Monitor Rft-A5 specified as part of the control room ventilation TSs, the ventilation system may be declared inoperable if RM-A5 is found to be defective during the ventilation test.

The function of the RM-A5 monitor is to cause control room ventilation to switch to the recirculation mode if the radiation setpoint is reached. An adequate compensation for having R!i-A5 temporarily out of service is to manually place the control room ventilation system in a recirculation mode.

This corrective action is not clearly permitted by the present TSs, however.

The proposed change would (1) put surveillance requirements for Rft-A5 in the proper section of the TSs, (2) allow the corrective action discussed above if RM-A5 is determined to be out of service, (3) require more frequent testing of the RM-A5 monitor, and (4) make the operability and surveillance requirements for RM-A5 consistent with STS.

Environmental Consideration We have determined that the amendment does not authorize a change in effluent types'or total amounts nor an increase in power level and will not result in any significant environmental impact. Having i

made this determination, we have further concluded that the atendment i

involves an action which is insicnificant from the standpoint of environmental impact and, pursuaitt to 10 CFR 151.5(d)(4), that an environmental impact statement, or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.

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i Conclusion We have concluded, based on the considerations discussed above, that:

(1) because the amendment does not involve a significant increase in

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the probability or consequiences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Cor=tission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety "of the public.

Dated: November 24, 1981 l

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