ML19319D386

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Forwards Info Re Potential Moderator Dilution Incident Due to Unterminated Injection of Sodium Hydroxide Into Primary Coolant Sys.Evaluation of Situation & Recommendations Re Licensing Action Requested
ML19319D386
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/11/1977
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Baer R
Office of Nuclear Reactor Regulation
References
TAC-08377, TAC-8377, NUDOCS 8003160219
Download: ML19319D386 (11)


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D. Eisenhut

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R. Baer, Chief. Reacter Safety Granch, DDR FROM:

D. G. Eisenhut, Assistant Director,for,0perational Technology, DOR

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_m Attached is infomation related to a' postulated moderator"dflution incident at Crystal River Unit No. 3.(CR-3) due ~to inadvertent and

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unteminated injection of NaOH into the pririary/ coolant system.

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limited dilution event actually oc6rred at C63 in March,1977 due to the misposition of a single. valve while the unit was in decay heat removal :: ode of operation; h0xever, the HaOH injection was,tenninated.

before an uncontrolied mctor criticality occurred.

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As discussed in the bune 9, IW letter frca 0:bcock & Ulicox (BAW)

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, to the Florida Po%r Ccrporatic, tha emptying of the entire contents of an Mn tank into the reacc. vessel is not bounded by the rodera-

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ter dilution events analyzed in Chapter 14 of the CR-3 FSAR. :Conse-quently, Bi!Lhas roccmer.ded saveral corrective actions totthe licensee.

Altheu';h I3E appears to ca pursuing the resolution of thJs concern with the licensee, there is no indication that NRR has been or is c'urrently involved in this evaluation effort. Consequently, since CR-3 will be transferred to DOR ~in the 'neaFfdture, please evaluate.

this situation and provide reed 65endaftons foFaypropriatellicensing

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actions, if any. Your review should'idcTudd iri assessmnt of the-generic i@lications of"this concie:Wa'nd the yreparation of an

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