NRC-91-0153, Submits Summary Progress Rept Re Third Individual Plant Exam Milestone.Activity Required for Third Milestone Re Containment Evaluation Completed.Final Quantification Awaits Completion of Final Model Enhancements
| ML20086F882 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/27/1991 |
| From: | Orser W DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-91-0153, CON-NRC-91-153 GL-88-20, TAC-M74410, NUDOCS 9112040025 | |
| Download: ML20086F882 (2) | |
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Novembe r 27, 1991 NRC-91 -0153 U. S. Nuclear Regulatory Cmanission Attn Document Control Deck Washington, D.C. 20555
References:
- 1) Fenni 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) NRC Generic Letter 88-20, " Individual Plant Examinations for Severe Accident Vulnerabilities,"
dated Novecber 23, 1988, and Supplement 1 dated August 29, 1989.
- 3) Detroit Edison Letter to NRC, " Fermi 2 Individual Plant Examination Program for Severe Accident Vulnerabilitse. " NRC-89-0213, dated October 25, 1989.
- 4) NRC Letter to Detroit Edicon, " Review of 60-Day Response to Generic Letter 58-20, Individual Plant Examinations (IPE) (TAC No.f74410)," dated Janua ry 18, 1990.
- 5) Detroit Edison letter to NRC, " Summary Progress Report of First IPE Milestone," NRC-91-0013, da ted Janua ry 29, 1991.
- 6) Detroit Edison letter to NRC, " Summa ry Progres s Report of Second IPE Milestone," NRC-91-0083, dat(d July 9, 1991
Subject:
Summary Progress Report of Third IPE Milestone By Reference 3. Detroit Edison provided its response to NRC Ceneric Letter 88-20 (Ref e rence 2). This response was found acceptable by the NRC in Reference 4 In that response Detroit Ed is on c ocimit t ed t o provide brief summary progress reports on completion of each of three IPE milestones. The first progress report was submitted on Janua ry 29, 1991 (Reference 5) and the second progress report was submitted on July 9, 1991 (Reference 6).
This letter is submitt ed to provide the summary report of the third IPE milestone.
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November 27, 1991 NRC-91-0153 Page 2 The activity required for the third milestone regarding containreent evaluation has been complet ed..
This activity developed containment event trees that were directly coupled to those developed in the Level 1 effort and utilized the MAAP code to develop plant specific information on the timing and progression of accident sequences and to aid in the determination of source terma.
To date, there have been no significant findings to report.
Howeve r, final quantification awaits completion of final model enhancements that result f rom a continuing process of review. Moreove r, a focused ef fort to obtain insighto from the overall IFE ef fort is about to begin. The additional remaining ef fort mainly consists of compiling the final report and supporting documentation.
If you have any questions, please contact Mr. Girija S. Shukla at (313) 586-4270.
Sincerely, cc C. E. Ca rpe n t e r, J r.
A. B. Davis R. W. DeFayette S. Stasek
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