ML19319A840

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Notifies That Revised ECCS Evaluation Model Consisting of Mods to post-CHF Heat Transfer Calculations Applicable & Tech Specs Meet App K Criteria.Forwards Safety Evaluation. W/O Encl
ML19319A840
Person / Time
Site: Oconee  
Issue date: 05/11/1977
From: Baer R
Office of Nuclear Reactor Regulation
To: Goller K
Office of Nuclear Reactor Regulation
References
NUDOCS 7912190890
Download: ML19319A840 (1)


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' DOCKET !40: 50-269/270/237 J

'ME!10RA!i30'i FOR:

.K.-R. Goller, Assistant Director for Operating EReactors,JDOR:

LTROMi R. L ' Baer, Chisf, Reactor Safety Branch, D0R

SUBJECT:

~ OCONEE 'FLAliT, ECCS EVALUATIO t PODEL CHMGE -

-PLANT iME: Oconee Muclear' Station bnits 1, 2 and 3 DOCKET: !40. :. 50-269/270/287

? RESP 0tiSIBLE BRANCH AtiD PROJECT MANAGER: ORB #1, J. D. fleighbors 10PERATIOllAL TECHf40 LOGY BRAMCH st(VOLVED: Reactor Safety REVIEW STATUS: 2 Complete lThe Reactor = Safety' Branch has' reviewed ~the applicability of the revised

, :ECCS evaluation model and the resultant change. in peak cladding tex.perature

-in~theE0conee Plant. The ' revision of the model consisted of the nodifications introdaced to the post-CHF heat transfer calculations.

Our review Lhas -Indicated that the revised model is applicable and the presentL0conce. Plant's Technical Specifications Acat the 10 CTR 50 Appendix K: criteria.

L'c have recently discussed with B&W another nodification. of the ECCS.

dodel due -to the change in the hydraulic resistance of the inlet

' nozzle" baffles. -- This SER does not cover this subject.

Original signed by

-[I Robert Eaer Robert L. Baer, Chief Reactor Safety Branch Division of 0;>erating Reactors -

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Enclosure:

cSafety Evaluation lcc::cVi Stello.

F. Coffman.

?D. Eisenhut S.' Weiss-.

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