ML20128F243
| ML20128F243 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/29/1993 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N93016, NUDOCS 9302110314 | |
| Download: ML20128F243 (2) | |
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bhi{ hlVl(O Doctric and Gat Compny Stanley LaBruna Nt+c Seiere (k t tne and Gas Company I' O Don 2.30. Hancc>ths Dodge, NJ 08330 009-339 1200 w._ww~,
JAN 2 01991 HLR-H930lb United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Contlement ASSESSMENT OF INCIDENTS DOCUMENTED DURING FOURTil REFUELING OUTAGE PER REQUEST OF INSPECTION REPORT 354/92-13 IlOPE CREEK GENERATING STATION FACILITY OPf7 TING LICENSE NO. NPF-57 DOCKET NO. Su-354 Public Service Electric and Gas Company (PSE&G) has completed its assessment of incidents documented during the fourth refueling outage of Hope Creek Generating Station (llCGS).
The review was performed by a five man team comprised of personnel from the On-Site Safoty Review Group and Station Quality Assurance Department.
The assessment team utilized a modified Management Oversight Risk Tree (MORT) analysis.
All incidents documented during the Hope Crook fourth refueling outage (a total of 47) wore reviewed to datormine whether common cause(s) for the incidents could be ascertained and corrective actions developed.
The entire report, including recommendations for performance improvement, has boon provided to the NRC Senior Resident Inspector for his review.
All incidents assessed were documented in accordance.ith Nuclear Department procedure NC.NA-AP.ZZ-0006, entitled, " Incident Report /
Reportable Event Program and Quality / Safety Concerns Reporting System".
The purpose of this procedure is to ensure that lessons learned from operating experience are translated'into corrective actions for improved plant safety and reliability, and.that off-normal events are promptly reported to PSE&G management, to regulatory and government agencios, and to other organizations as required.
In summary, the MORT analysis determined that there' wore five
" clusters" of similar causal factors.
Specific analysis of circumstances which led to each incident indicatos that, other than the fundamental " attention to detail" causal factor to which virtually all human failures can be inevitably traced, incidents were exclusive of each other - without a specific cause or " common hoh hg9 I
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WAN 2 01993 NLR-N93016 thread".
kccommendations to management includo emphasizing to personnel the nood to be aware of changing plant conditions as the outage progresses, and to remain vigilant regarding common work on redundant equipment under varying circumstancos.
In addition to the MORT analysis, a comparison was performed for the incident report issue rate of the third refueling outage versus the fourth refueling outago (i.e.,
incident reports por thousand completed work activitics).
Thoro was no discernible differenco in issue rato; this is in spito of a lowering of the threshold for dotormining what constitutes a documentablo incident since the third refueling outago.
Our overall conclusion is, as discussed previously, that there was no identifiablo common thread and that the incidence rate of personnel error did not show an increasing trend.
However, as always, there is room for improvement.
Lossons learned from this outage will bo integrated into planning for futuro outages.
If you have any questions regarding this submittal, please do not hesitate to call us.
Sincorolyg l hs-:
C Mr. T.
T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendalo Road King of Prussia, PA 19406 Mr.
S. Dombok, Licensing Project Manager U.
S.
Nuclear Regulatory Commission 1 Whito Flint North 11555 Rockvillo.Piko (MS 14 E-21)
Rockvillo, MD 20852 Mr. T. P. Johncon (SOS)
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection & Energy Division of Environmental Quality Bureau of Nuclear Engineering 4
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