ML19224B939

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Comments on Constructive Changes to Regulatory Requirements for Nuclear Power Plants:Knowledge of Reactor Vessel Water Level & Gas Bubble Dispersion Need Addressing
ML19224B939
Person / Time
Site: Crane 
Issue date: 06/18/1979
From: Wenzinger E
NRC OFFICE OF STANDARDS DEVELOPMENT
To: Mattson R
Office of Nuclear Reactor Regulation
References
NUDOCS 7906280045
Download: ML19224B939 (1)


Text

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Dsta ROUTING AND TRANSMITTAL SLIP M 18 S79 TO: Name, omes symbol, room number, Initials Date utiding, Agency / Post)

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L NRC PDR Assessions Unit (P-50) V 2

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Action Fila Note and Retum Approval For Clearance Per Conversation i

As Requested For Correction Prepare Reply Circufate For Your Informat!on See Me bmment Investigate Signature l Coordination Justify REMARK 3 TO BE PLACED IN NRC PDR I&.

DO NoT use this form as a RECORD of approvals, concurrences, disposa!s, clearances, and similar actions l

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Robert L. Tedesco, L Task Force, Fnone No.

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JUN 18 1979

'T 7' N MEMORANDUM FOR:

R. J. Mattson, Director Division of Systems Safety Office of Nuclear Reactor Regulation FROM:

E. C. Wenzinger, Chief Reactor Systems Standards Branch Division of Engineering Standards Office of Standards Development

SUBJECT:

LESSONS LEARNED FROM THE TMI-2 ACCIDENT In your memo to the NRR Staff dated May 31, 1979 you asked for suggestions and comments concerning constructive changes for regulatory requirements for nuclear power plants.

I would like to submit the following suggestion.

Two problems which I am aware of appear to be amenable to a common solution.

First, TMI-2 has identified a need for knowledge of reactor vessel water level. Another problem which came up in the course of the accident was how to get rid of a gas bubble which developed in the reactor vessel.

The common solution which I suggest be considered is a small vent line (pipe) from the vessel head to some lower pressure point in the primary system or to a higher pressure point with a pump in the vent line. The vent line could allow removal of the gas bubble from the vessel.

Measure-ment of flow in the vent line would provide an indication that the vessel is full.

Please let me know if this idea has m3rit.

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l-Q il. '.f.,,N E. C. Wenzinger, Chi f Reactor Systems St'a ards Branch Office of Standards Development 257 135