ML20125A444

Forwards Safety Evaluation of Plant Conformance to Requirements of App K to 10CFR50 & Acceptability of Proposed GETAB-based TS

ML20125A444
Person / Time
Site:	Monticello
Issue date:	09/30/1975
From:	Stello V Office of Nuclear Reactor Regulation
To:	Goller K Office of Nuclear Reactor Regulation
Shared Package
ML20125A447	List: ML20125A444 ML20125A452
References
NUDOCS 9212080349
Download: ML20125A444 (1)

Text

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utp 3 0 G1 Karl Goller, Assistant Director for Operating Reactors, RL REVIEW OF M)NTICELLO APPENDIX K CALCULATIONS AND GETAB TECH SPECS (T Plant Name: Monticello Docket No.: 50-263 Responsible Branch and Project Leader: ORB-2, B. Buckley Technical: Review Branch Involved: Reactor Systems Branch Review Status: Complete l

Enclosed 1s the Reactor Systems Branch evaluation of the confomance of I

Monticello's ECCS.perfomance to the requirements of Appendix X to i

10 CFR Part 50, and of the proposed Technical Specification changes

' incorporating the GETAB/GEXL analysis.- Both were found acceptable with the restrictions noted below.

The submittal did not address operation with one~ loop and the license-should be amended by a change to the Technical Specifications to reflect -

i this. - The valves in the equalizer piping between the meirculation loops shall be closed at all times;during reactor operation, and the reactor shall not be continuously operated with one recirculation loop out of service. We recommend that operation with one loop _be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Also, the Technical Specifications should be modified so as not to allow j

[ continuous operation with any ADS valve out of service. Since the 11cer.see -

did not provide a--LOCA analyses by assuming the operation of the ADS with i- i one valve out of service for small line breaks:and an HPCI failure, we reconnend a limit of seven days for an ADS valve to be out of service which j is compatible to the outage. time of the HPCI-system.

i i- Finally, the additional changes, included in Mr. L._0. Mayer's July 10, =1975

! letter to D. L. Ziemann, requesting changes in the slope of the APRM scram and rod block settings are not acceptable as discussed in the enclosed SERi Orfclnal SIipid!

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i " for SteDe Victor Stello,'Jr. Assistant Director-l-

.[ for Reactor Safety

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