ML20235K759
| ML20235K759 | |
| Person / Time | |
|---|---|
| Issue date: | 02/07/1989 |
| From: | Novak T NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Newton R WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| Shared Package | |
| ML20235K761 | List: |
| References | |
| NUDOCS 8902270235 | |
| Download: ML20235K759 (3) | |
Text
_ _ _ _ _ _ _ _ _
FES 7 1988
\\
M.r. Ro'.er Newton, Chairman AE0D/T902 g
Westinghouse Owners Group Wisconsin Electric Power Company P.O. Box 2046 Milwaukee, Wisconsin 53201
Dear Mr. Newton:
Subject:
AE0D Technical Review Report, " Inadvertent Reactor Trips due to RCS Flow Instrumentation Maintenance Activities" l
We have recently performed a review of recent operating events at Westinghouse i
supplied nuclear power facilities. The review focused on inadvertent reactor trips resulting from maintenance activities performed on reactor coolant I
system (RCS) flow instrumentation. Since January 1988, there are four licensee event reports of inadvertent trips from RCS flow instrumentation maintenance.
These trips were found to result from personnel errors and flow instrumentation design configuration. The design configuration utilized transmitters sharing a common "high side" sensing line. During maintenance activities on a single a
transmitter, perturbations were propagated into the common sensing line and I
caused sensed low RCS flow conditions and resultant inadvertent reactor trips.
We are aware that both the Westinghouse Owners Group and NUMARC have ongoing programs to address reactor trip reductions, hence reducing unnecessary challenges to plant safety systems. We believe that the results of our technical review may be relevant to your program. A copy of our report is enclosed for your consideratica in your Trip Reduction and Assessment Program or other similar effort.
If you have any questions, please feel free to contact me or Mr. Mark Padovan of my staff at (301) 492 4445.
Sincerely, Original nicned by:
ThNaYiht[oYa'k', Director Division of Safety Programs Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated r
cc w/ enclosure:
Walt Smith, HUMARC o
r P
flark Beaumont, W E. Rossi, NRR
~
c J. Roe, NRR 0
rh Distribution:
Central File WLanning JRosenthal c3 PDP MTaylor VBenaroya Dhy ST ROAB R/F EJordan MWilliams L
f1Padovan CHeltemes KBlack
'\\
gd Plam TNovak DSP R/F
- See previous concurrences M
- R0AB:DSP:AE00
- ROAB:DSP:AE0D B:DSP:AE0D DSP:AE0D D
ilPadovan:mp Plam Rosenthal VBenaroya Ti k
1/ /89 1/ /89 1//ff69 1/W/89 f/[/89
Mr. Roger Newton, Chairman
~
Westinghouse _ Owners Group Wisconsin Electric Power Company P.O. Box 2046 Milwaukee, Wisconsin 53201
Dear Mr. Newton:
Subject:
AE0D Technical Review Report, " Inadvertent Reactor Trips due to RCS Flow Instrumentation Maintenance Activities" We have recently performed a review of recent operating events at Westinghouse.
supplied nuclear power facilities. The review focused on inadvertent reactor trips resulting from maintenance activities performed on reactor coolant system (RCS) flow instrumentation. Since January 1988, there are four licensee event reports of inadvertent trips from RCS flow instrumentation maintenance.
These trips were found to result from personnel errors and flow instrumentation design configuration. The design configuration utilized transmitters sharing
.a common "high side" sensing line. During maintenance activities on a single transmitter, perturbations were propagated into the common sensing line and caused sensed low RCS flow conditions and resultant inadvertent reactor trips.
We are aware that both the Westinghouse Owners Group and NUMARC have ongoing programs to address reactor trip reductions, hence reducing unnecessary challenges to plant safety systems. We believe that the results of our engineering evaluation may be relevant to your program. A copy of our report is enclosed for your consideration in your Trip Reduction and Assessment Program or other similar effort.
of my staff at (questions, please feel free to contact me or Mr. Mark Padovan If you have any 301)492-4445.
Sincerely, Thomas M. Novak, Director Division of Safety Programs Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated cc w/ enclosure:
Walt Smith, NUMARC Mark Beaumont, W E. Rossi, NRR Distribution:
Central File WLanning PDR MTaylor l
R0AB R/F EJordan MPadovan CHeltemes Plam TNovak
{
JRosenthal MWilliams VBenarcya KBlack
- See previous concurrences
- R0AB:DSP:AEOD ROAB:DSP;AE0D ROAB:DSP:AE00 DSP:AEOD D:DSP:AEOD MPadovan:mp PLam gm JRosenthal VBenarcya TNovak 1/ /89 1/tg/89 1/ /89 1/ /89 1/ /89
Mr. Roper Newton, Chairman Westinghouse Owners Group-Wisconsin Electric Power Company P.O. Box 2046 Milwaukee, Wisconsin 53201
Dear Mr. Newton:
Subject:
AE0D Engineering Evaluation Report, " Inadvertent Reactor Trips due to RCS Flow Instrumentation Maintenance Activities" We have recently performed a review of recent operating events at Westinghouse supplied nuclear power facilities. The review focused on inadvertent reactor trips resulting from maintenance activities performed on reactor coolant system (RCS) flow instrumentation. Since January 1988, there are four licensee event reports of inadvertent trips from RCS flow instrumentation maintenance.
These trips were found to result from personnel errors and flow instrumentation design configuration. The design configuration utilized transmitters sharing a common "high side" sensing line. During maintenance activities on a single transmitter, perturbations were propagated into the common sensing line and caused sensed low RCS flow conditions and resuitant inadvertent reactor trips.
We are aware that both the Westinghouse Owners Group eod NUMARC have ongoing programs to address reactor trip reductions, hence recucing unnecessary challenges' to plant safety systems. We feel that the results of our engineer-ing evaluation may be relevant to your program. A copy of our report is enclosed for your consideration in your Trip Reduction and Assessment Program or other similar effort.
If you have ary questions, please feel free to contact me or Mr. Mark Padovan of my staff at (301) 492-4445.
Sincerely, Thomas M. Novak, Director Division of Safety Programs Office for Analysis and Evaluation of Operational Data cc: Walt Smith, NUMARC MarkBeaumont,}l
Enclosure:
As stated Distribution:
Central File WLar u.49 PDR MTay;or ROAB R/F Edordan MPadovan CHeltemes Plam TNovak JRosenthal MWilliams i
VBenaroya KBlack PA
- AEOD ROAB:DSP: OD ROAB:DSP:AEOD DSP:AE0D D:DSP:AEOD MPa va :mp Plam JRosenthal VBenaroya TNovak 1 / 17 / 8 9 1/(7/89 1/ /89 1/ /89 1/ /89
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