ML20214D247
| ML20214D247 | |
| Person / Time | |
|---|---|
| Issue date: | 10/16/1986 |
| From: | Thomasson W NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Rubin S NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR AEOD-E611, IEIN-80-21, NUDOCS 8611210433 | |
| Download: ML20214D247 (2) | |
Text
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POR October 16, 1986 MEMORANDUM FOR: Stuart D. Rubin, Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation AE0D/E611 of Operational Data FROM:
W. Neill Thomasson, Senior Reactor Systems Engineer Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data l
SUBJECT:
SEISMIC ANCHORS FOR ELECTRICAL AND CONTROL PANELS
?.nclosed is an engineering evaluation report concerning several recent events -
involving inadequate anchorage of electrical and control panels. As a consequence of initial reviews under the Systematic Evaluation Program (SEP) in 1979 - 1980, significant regulatory concern was identified regarding the adequacy of as-built seismic design of operating reactors. Consequently, an Information Notice (IN 80-21) was issued on the subject and the issue was designated Unresolved Safety Issue (USI) A-46.
Based on a number of recent events, there is evidence that deficiencies continue to exist in the seismic mounts or anchorage of critical safety-related equipment.
USI A-46 is nearing a resolution which is proposed to result in a Generic Letter (GL) requiring older operating plants (those not reviewed under current seismic equipment qualification criteria) to conduct plant walk-through inspections using generic checklists, procedures and criteria to verify the adequacy of anchorage of equipment necessary to bring a nuclear power plant to safe, hot shutdown and to maintain it for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Based on the enclosed study we suggest that IE issue an updated Information Notice, coincident with the GL, in order to highlight and characterize the continuing deficiencies regarding seismic anchorage of critical equipment.
In addition, we also suggest that NRR modify the GL to require preliminary walk-through inspections to verify the absence of gross deficiencies in the equipment anchorage.
W. Neill Thomasson, Senior Reactor Systems Engineer Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated DISTRIBUTION:
/PDR Wlanning ROAB CF KBlack ROAB SR (conc.)
MWilliams NThomasson FHebdon Plam CHeltemes SRubin AE0D SF
- SEE PREVIOUS CONCURRENCE OFC
- ROAB *
- BC:ROAB *
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8611210433 861016 NAME : WThomasson : SRubin PDR ORG NEXD PDR DATE : 10/ /86
- 10/ /86 0FFICIAL RECORD COPY
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MEMORANDUM FOR: Stuart D. Rubin, Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data FROM:
W. Neill Thomasson, tenior Reactor S stems Engineer Reactor Systems Section 1 Reactor Operations Analysis Branc Office for Analysis and Evaluati_on of Operational Data
SUBJECT:
SEISMIC ANCHORS FOR ELECTRICAL AND CONTROL PANELS
/
Enclosed is an engineering evaluation report concerning several recent events involving inadequate anchorage of electrical and control panels. The study determined that, as a consequence of init'ial reviews under the Systematic 1979 - 1989', built seismic design of operating Evaluation Program (SEP) in significant regulatory concern was identified regarding the adequacy of as-reactors. Consequently, an Information Notice (IN 80 21) was issued on the subject and the issue was designated Unresolved Safety Issue (USI) A-46.
Based on a number of recent events, thers is evidence that deficiencies continue to exist in the seismic mounts or anchorage of critical safety-related equipment.
The study found that USI A-46 is nearing a resolution which is proposed to result in a Generic Letter (GL)~ requiring older operating plants (those not reviewed under current seismi_c equipment qualification criteria) to conduct plant walk-through inspections using generic checklists, procedures and criteria to verify the adequacy of anchorage of equipment necessary to bring a nuclear power plant to safe, hot shutdown and to maintain it for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The study suggests issuance of an updated information notice, coincident with the GL, in order to highlight and characterize the continuing deficiencies regarding seismic anchorage of critical equipment.
It also suggests modifica-tion of the GL to require preliminary walk-through inspections to verify the absence of gross deficiencies in the equipment anchorage.
W. Neill Thomasson, Senior Reactor
/
Systems Engineer
/
Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated DISTRIBUTION:
TTR WLanning R0AR CF KBlack R0AB SR (conc.)
MWilliams NThomasson FHebdon Plam CHeltemes SRubin AE0D SF TYChang, NRR NAnderson, NRR G. Bagchi, NRR DFC
- ROAB
- BC:R0AB NAME : WThomasson : SRubin
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