ML20072U177

Submits Hazards Analysis of Licensee 620111 Request for Change to TS to Authorize Decrease in Required Sensitivity of Source Range Startup Instrumentation.Proposed Change Acceptable

ML20072U177
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	02/15/1962
From:	Bryan R US ATOMIC ENERGY COMMISSION (AEC)
To:	US ATOMIC ENERGY COMMISSION (AEC)
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References
FOIA-91-17 NUDOCS 9104190043
Download: ML20072U177 (1)

Text

RAZARDS AMA JIS BY THE RESPARCH AND POWER h.CTOR SAFETY BRANCH DIVISION OF LICD(SING AND REGULATION IN THE MATTER OF SAXTON __NUCLFAR EIPERDENTAL CGOMATICal D00KET NO. 50-lh6_

Introduction Pursuant to paragraph 3.B. of License No. DPR-h, Saxton Nuclear Experimental Corporation by Change Request No. 1 dated January 11, 1962, requested authori-sation to change paragraph 7.(j) of the Technical Specifications to authorise a decrease in the required sensitivity of the source range startup instrumenta-tion and to correspondingly change the Final Safeguards Report to include the decreased sensitivity.

Discussion The sensitivities and ranges of the startup source range instrumentation are as follows:

Sensitivity Range (SeeTable203.3,FinalSafeguardsReport)

Original hocounts/sec/nv 2.5 x 10-2 to 2.5 x 103 av Proposed 13.3 counts /sec/nv 5 decades startjng no higher than 7.5 x 10 nv.

We have noted that the censitivity of the startup channel detectors would be decreased by a factor of 3.

However, under the proposed revised Technical Specification, if a minimm rate of 5 counts per second is not achieved during startup, the instrumantation will be changed to cover the range originally specified. With the proposed sensitivity ar# range the min 4='=

detactable count rate would be 1 count per second.

V miniemim Count proposed ' '

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mrmm > neutron multir" -

mccury ern: 1 ar"'

tro posed chwe win. "ot dernely affect the safety of the Sanon fact.

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Conclusion We have concluded that the nroposed change in the Technical Specifications requested by_ Change Request No.1 does not present significant hasards con-siderations not described or implicit in the Final Safeguards Report, and that there is reasonable assurance that the health and safety of the public will not be endangervd by operation of the reactor under the proposed Technical Specifications change.

Robert H. Bryan, Chief Datet FEB i 5 N Divielen of Licensing and Regulation 9104190043 910314 PDR FOIA DEKOK91-17 PDR