NRC-91-0013, Provides Summary Rept of First Individual Plant Exam Milestone,Per 891025 Response to Generic Ltr 88-20, Individual Plant Exams for Severe Accident Vulnerabilities
| ML20067D580 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/29/1991 |
| From: | Orser W DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-91-0013, CON-NRC-91-13 GL-88-20, TAC-74410, NUDOCS 9102130140 | |
| Download: ML20067D580 (2) | |
Text
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Senior Vice President -
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i January 29.?1991 URC-91-0013 J
q< p JU. S. Nuclear Regulatory Commission-Attnt. Document Control Desk.
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i "1g Referencesi:
- 1) --Fermi'2 j
~NRC Docket No. 50-341 4
=NRC_ License No.~ NPF-43 1
- 2) L NRC : Generic. Letter 88-20. " Individual Plant j
4 Examinations'fer-Severe Accident Vulnerabilities",
dated November :23,1988, Land Supplement 1. dated August 29,:1989 S,, 9
- 53) Detroit; Edison Letter to NRC, "Femi-2 Individual j i
- Plant 1 Examination Program for. Severe Accident W
' Vulnerabilities" NRC-89-0213, dated.
C:tob~eri25, 1989.
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- 4) NRC ' Letter to-. Detroit Edison, " Review. of 60-Day
, Response: to Generic? Letter 88-20. Individual. Plant-i Examinationsi (IPE).<(TACLNo. - 74410) " dated -
j January.18. -_1990 '
iSubject;;
4 Summary Progress Report' of First IPE Milestone -
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. By Reference 3. Detroit Edison provided its Lresponse-to NRC Generic
' Letter'88-20M(Reference 2).- Thisfresponsefwas found' acceptable by the
' NRC in Reference L 4.,
In-that response _ Detroit Edison committed to -.
c provide-brief summary progress reports on completion ofleach of three:
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- IPE milestones; This letterJis submitted t'o-provide the summary y
'. report Lof.the first IPE milestone.
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-;Thel activities required for the first milestone regarding enhancements i l lto.the? Level 1-analysis have been completed. -Specifically, the following has ;been accomplished:
lo- -Six containment systems have been modeled.-
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' Applicab'le findings f rom the' multiplo control' system failure study and f rom a detailed' a.c. load list have been analyzed and dispositioned.
9102130140 910129 ON PDR ADOCK 05000341 7
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USNRC January 29, 1991 NRC-91 4013 Page 2 o
All der'ign chnegts "ade since completion of the original Level 1 PRA model through the fir st refueling out ege have been reviewed and incorporated into the Leve' 1 model as determined to be appropriate.
o The Level 1 model hun been ec>mpletely transf erred to new PC sof tware developed by Packard, Lo ? and Garrick (ItG), the primary Level 1 PRA consu' tent.
Appropriat e enhancement e resulting f rom third party review as o
well as additional internal and PLG review have been incorporated into the Level 1 model.
To date, there have been no significent findings to report.
- However, the Level 1 model will continue to be exercised and scrutinized thrcughout the remainder of the IPE program.
Consultanto to support internal ficoding and containment performance analysen were relected in 19i% and the related technical activity has recently been initiated. The corresponding completion milectones are being see back by two months and one month, respectively i.e., June 1991 inotead of Aprdi 1991 for internal flooding and November 1991 innterd of October 1991 f or containment perf ormance.
- However, submitt el of the final IPE report is still scheduled for April 1992.
If you have any questions, please contret Mr. Girija S. Shukla at (313) 506-4270.
Sincerely, cc A. B. Davis R. W. DeFayette W. G Rogers J. F. Stang
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