ML20245B619
| ML20245B619 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Nine Mile Point, Oyster Creek, Columbia, LaSalle, 05000000 |
| Issue date: | 04/15/1989 |
| From: | Kauffman J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Rosenthal J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| Shared Package | |
| ML20245B622 | List: |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR AEOD-E801, NUDOCS 8904260191 | |
| Download: ML20245B619 (1) | |
Text
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UNITED STATES
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%,.....,o APR 151988 MEMORANDUM FOR: Jack E. Rosenthal, Chief AE0D/E801 Reactor Operations Analysis Branch Division of Safety Programs, AE0D THRU:
George F. Lanik, Chief Reactor Systems Section GE & CE h Reactor Operations Analysis Brarfch Division of Safety Programs, AE0D FROM:
John V. Kauffman, Peactor Systems Engineer Reactor Systems Section GE & CE Reactor Operations Analysis Branch Division of Safety Programs, AEOD
SUBJECT:
BWR OVERFILL EVENTS RESULTING IN STEAM LINE FLOODING Forwarded is a copy of the subject AE0D Engineering Evaluation report. The investigation of BWR overfill events resulting in steam line flooding found:
1)
All of the inadvertent overfill events included a reactor depressurization followed by an uncontrolled condensate or condensate booster pumps injection or both.
2)
Operating experience indicates that these events are infrecuent and have had little actual safety significance.
3)
NRC should ensure licensee actions address all safety concerns.
Licensees should perform engineering evaluations and system walkdowns to identify and correct any damage from these events, prior to plant restart.
4)
Relatively minor design changes and continued training and procedural enhancements can minimize these events.
It is suggested that a copy of this report be forwarded to RES for consideration in USI A-47, " Safety Implications of Control Systems," as well as to the NRR Generic Consunications Branch.
V John V. Kauffman, Peactor Systems Engineer l
Reactor Systems Section GE & CE Reactor Operations Analysis Branch l
Division of Safety Programs, AE0D
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Enclosure:
As stated 8904260191 890415
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