ML17299B322
| ML17299B322 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/06/1985 |
| From: | Heltemes C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Harold Denton, Minogue R, Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML17299B323 | List: |
| References | |
| REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR TAC-59183, TAC-61289, NUDOCS 8511190401 | |
| Download: ML17299B322 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 NOV 06 lg8g MEMORANDUM FOR:
5 Harold R. Denton, Director Office of Nuclear Reactor Regulation James H. Taylor, Director Office of Inspection and Enforcement Robert B. Hinogue, Director Office of Nuclear Regulatory Research Thomas E. Murley, Regional Administrator, Region I J.
Nelson Grace, Regional Administrator, Region II James G. Keppler, Regional Administrator, Region III Robert D. Hartin, Regional Administrator, Region. IV John B. Hartin, Regional Administrator, Region V
FROM:
SUBJECT:
C. J.
Heltemes, Jr., Director Office for Analysis and Evaluation of Operational Data PRELIMINARY CASE STUDY REPORT -- EFFECTS OF AMBIENT TEMPERATURE ON ELECTRONIC EQUIPMENT IN SAFETY RELATED INSTRUMENTATION AND CONTROL SYSTEMS The Office for Analysis and Evaluation of Operational Data has conducted a
study of operational events involving failures of solid state electronic components in safety related instrumentation and control (IEC) systems due to high ambient temperature.
The study was initiated by an event that occurred at the McGuire Station on June 4, 1984, which involved the total loss of the control area ventilation system while Unit 1 and Unit 2 were operating at full power.
The enclosed preliminary report documents the review and evaluation of the event at McGuire and of other events involving similar failures at operating Westinghouse pressurized water reactor (PWR) units.
Based on the review of these events and on the similarity of electronic components used in other types of operating reactor units, the study concludes that the problem of high ambient temperatures affecting electronic components in safety related I&C systems is potentially generic to all operating nuclear units that use heat sensitive electronic components.
The study a)so finds that, in general, plant technical specifications regarding control room/instrument room ventilation
4 H
systems and instrument system operability are inadequate.
The study also finds that certain assumptions in the staff's evaluation of USI-A44, Station Blackout, regarding environmental effects on IBC system equipment could be incorrect..
Our preliminary report contains several specific recommendations aimed at addressing the concerns raised by the study's findings and conclusions.
In accordance with AEOD's "peer review" process, prior to the finalization and distribution of our case study reports, we are providing NSAC, INPO and Duke Power Company with a copy of a preliminary report for review and comment, particularly regarding accuracy and completeness of the technical details.
Changes to the findings, conclusions, and recommendations will be considered only if the underlying information concerning the details of plant design, systems operation or sequence of events is in error.
Therefore, comments are being solicited on the technical accuracy of the report.
The findings, conclusions and recommendations are provided for your information in order that you may understand the significance which AEOD places on this issue and therefore obtain a more complete picture of the total report.
We would welcome comments either informally by phone or formally by memorandum.
Since we wish to finalize and issue the report shortly, we ask that any comments be received by us within 30 days from receipt of the preliminary report.
Should your office require some additional time beyond that point, please let us know, otherwise it will be assumed that there are no comments.
We are also placing ~ copy of the preliminary report in the Public Document Room.
If you or your staff have any questions regarding this matter, please contact Matthew Chiramal of my staff.
Mr. Chiramal can be reached at 301/492"4441.
C. J:: Ae1temes, Jr., Oirector Office for AnaTysis and Evaluation of Operational Data
Enclosure:
As stated CC w/enclosure:
R. Walker, R II D.
- Hood, NRR P.
- Bemis, R. II W. Orders, RI, McGuire Station H. Dance, R II V. Brownlee, R II G. Lainas, NRR J. Stewart, IE
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHtKGTOK,O. C. 20555 NOV 06 885 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
'7 James H. Taylor, Director Office of Inspection and Enforcement Robert B. Hinogue, Director Office of Nuclear Regulatory Research Thomas E. Hurley, Regional Administrator, Region I J.
Nelson Grace, Regional Administrator, Region II James G. Keppler, Regional Administrator, Region III Robert D. Hartin, Regional Administrator, Region IV John B. Hartin, Regional Administrator, Region Y
FROM:
SUBJECT:
C. J.
Heltemes, Jr., Director Office for Analysis and Evaluation of Operational Data PRELIMINARY CASE STUDY REPORT EFFECTS OF AMBIENT TEMPERATURE ON ELECTRONIC E(UIPMENT IN SAFETY RELATED INSTRUMENTATION AND CONTROL SYSTEMS The Office for Analysis and Evaluation of Operational Data has conducted a
study of operational events involving failures of solid state electronic components in safety related instrumentation and control (I&C) systems due to'igh ambient temperature.
The study was initiated by an event that occurred at the McGuire Station on June 4, l984, which involved the total loss of the control area ventilation system while Unit l and Unit 2 were operating at full power.
The enclosed preliminary report documents the review and evaluation of the event at McGuire and of other events involving similar failures at operating Westinghouse pressurized water reactor (PWR) units.
Based on the review of these events and on the similarity of electronic components used in other types of operating reactor units, the study concludes that the problem of high ambient temperatures affecting electronic components in safety related I&C systems is potentially generic to all operating nuclear units that use heat sensitive electronic components.
The study also finds that, in general, plant technical specifications regarding control room/instrument room ventilation
I I
I
systems and instrument system operability are inadequate.
The study also finds that certain assumptions in the staff's evaluation of USI-A44, Station Blackout, regarding environmental effects on I&C system equipment could be incorrect.
Our preliminary report contains several specific recommendations aimed at addressing the concerns raised by the study's findings and conclusions.
In accordance with AEOD's "peer review" process, prior to the finalization and distribution of our case study reports, we are providing NSAC, INPO and Duke Power Company with a copy of a preliminary report for review and comment, particularly regarding accuracy and completeness of the technical details.
Changes to the findings, conclusions, and recommendations will be considered only if the underlying information concerning the details of plant design, systems operation or sequence of events is in error.
Therefore, comments are
~
being solicited on the technical accuracy of the report.
The findings, conclusions and recommendations are provided for your information in order that you may understand the significance which AEOD places on this issue and therefore obtain a more complete picture of the total report.
We would welcome comments either informally by phone or formally by memorandum.
Since we wish to finalize and issue the report shortly, we ask that any comments be received by us within 30 days from receipt of the preliminary report.
Should your office require some additional time beyond that point, please let us know, otherwise it will be assumed that there are no comments.
We are also placing a copy of the preliminary report in the Public Document Room.
If you or your staff have any questions regarding this matter, please contact Matthew Chiramal of my staff.
Mr. Chiramal can be reached at 301/492"4441.
l C.
e emes r., Director Of c
for Ana is and Evaluation of Operational Data
Enclosure:
As stated CC w/enclosure:
R. Walker, R II D.
- Hood, NRR P.