ML20205P749

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Forwards 870326 Memo & Discharge of Primary Coolant Outside Containment at PWRs While on RHR Cooling, Engineering Evaluation Rept.Suggests Issuance of Info Notice to Alert Licensees to Potential Problems W/Subj Events
ML20205P749
Person / Time
Issue date: 03/26/1987
From: Israel S
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Rubin S
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20205P752 List:
References
NUDOCS 8704030362
Download: ML20205P749 (2)


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MEMORANDUM FOR: Stuart D. Rubin, Chief Reactor Operations Analysis Branch Office.for Analysis and Evaluation

'of Operational Data THRU:

Peter Lam, Chief..

Reactor Systems Section 2 Reactor Operations Analysis Branch Office for Analysis and Evaluation of. Operational Data FROM:.

Sanford L. Israel, Senior Reactor Systems Engineer Reactor Systems Section 2 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data

SUBJECT:

DISCHARGE OF PRIMARY COOLANT OUTSIDE 0F CONTAINMENT AT PWRS WHILE ON RHR COOLING Enclosed.for your consideration 'is an engineering evaluation report on operational events involving the discharge of primary coolant outside.of,(RHR).

containment.at pressurized water reactors while on residual ~ heat removal cooling. Seven operating events which occurred at different PWRs in the last-nine years were identified and evaluated in the study. These events were primarily caused by human errors and insufficient procedures associated with the operation of the RHR system in the shutdown cooling mode. The personnel errors were primarily caused by inattention or lack of training; while'the-procedural deficiencies were related to omissions or lack of specificity in sequential valve operations when conducting tests on the RHR sy' stem.-

If the loss of primary ecolant is not terminated in a timely manner these.

types of events could eventually progress into loss'of RHR cooling situations--

with a containment bypass. The potential for a severe accident with containment bypass makes the consequences of these loss-of-coolant events potentially more significant than those associated with the loss of RHR. cooling events reported-in AE0D case study report AE00/C503; however, the likelihood of these~ operating events leading to a severe accident is. smaller than the loss of RHR cooling events.

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Stuart.D. Rubin The study concludes that these operating events have a moderate safety signifi-

-cance and consequently warrant further consideration.

It is suggested that an i

information notice be issued to alert the licensees to the potential problems associated with these operational events.

Sanford L. Israel, Senior Reactor Systems Engineer Reactor Systems Section 2 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data Enclosure-As Stated cc w/ enclosure:

K. Black, AE0D M. Williams, AE0D A. Marchese, NRR H. Ornstein, AE0D DISTRIBUTION:

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'DATE :3/0 /87

3/M/87 OFFICIAL RECORD CO'Y

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