ML20090B493

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Agrees That Steam Generator Tube Rupture Constitutes AO as Major Degradation of Primary Coolant Pressure Boundary. Editorial Changes Recommended to Evaluation Per Encl.W/O Encl
ML20090B493
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/06/1982
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Michelson C
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML082380335 List:
References
FOIA-91-106, RTR-NUREG-0909, RTR-NUREG-909 NUDOCS 8205240157
Download: ML20090B493 (1)


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DESIGNATED ORIGINAL-Cer*.ified By ALL O kfI d

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e co MEMORANDUM FOR:.Carlyle Michelsen, Director Office for Analysis and Evaluation RECEIVED %

of Operational Data g}

MAY1gj FROM:

Harold-R. Denton, Director T

8 mun Office of Nuclear. Reactor Regulation

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SUBJECT:

PROPOSED ABNORMAL OCCURRENCE - GINNA STENi 4

GENERATOR TUBE RUPTURE 7'u c)

In response to your stquest of April = 23,1982 we have reviewed your evaluation of the Ginna Steam Generator Tube Rupture (SGTR) event as an abnonnal occurrence and have reviewed and prepared comnants on the pmposed Comission paper on this subject. We agree with your evaluation that the Ginna SGTR constitutes an abnonnal occurrence since it meets the criterior of being a major degradation of the primary coolant pressurt boundary.

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Your draft Commission paper on this subject presents aa uccurate and thorot.qh discussion of the event and is consistent with the Task Force report, NUREG-

.0909. We therefore concur with your draft Commission paper, although we do

- recor:nend some editorial changes as shown on the attached copy.

u;::.u 1. :wa Id R. Denton, Director ice of Nuclear Reactor Regulation L

Attachment:

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