ML19329D698

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Forwards Util & RO 77-52 Re Unresolved Safety Question Involving Moderator Dilution.Transfer of Lead Responsibility Should Be Transferred to Ofc of Nuclear Reactor Regulation
ML19329D698
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/29/1977
From: Long F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML19329D697 List:
References
NUDOCS 8003160316
Download: ML19329D698 (1)


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DN 50-302 FEMOPJCIDUM FOR:

K. V. Seyfrit,. Chief, Reactor Technical Assistance Branch, Office of Inspection and Enforce =ent, Headquarters FROM:

F. J. Long, Chief, Reactor Operations and Iiuelear Support Branch, Office of Inspection and Enforce =ent, Region II SUEJECT:

POTE'iTIAL MODERATOR DILUTION ACCIDENT (F21616E2)

The attached Reportable Occurrence provides additional information on the injection of NaOH into the RPV at Crystal River 3 on February 7, 1977 Analysis by B&W indicates that a single failure of the NaOH tank, effluent valve, while operating in the decay heat removal mode, is potentially an unreviewed safety question.

The postulated accident appears less censervative than that analyzed in FSAR lh.l.2.h.

If you conce, we "a-and that the lead recpensibility in this matter be transferred to HF.R.

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,N'31%n c F. J. Lchg, Chief Reacter Operations and Nuclear Support 3 ranch

Attachment:

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Lewis rance

. R. Martin T. Epps COUTACT:

T. N. EPPS 2!.2-5557 i

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