ML20012E773
| ML20012E773 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/23/1990 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Sylvia B DETROIT EDISON CO. |
| Shared Package | |
| ML20012E774 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 9004060277 | |
| Download: ML20012E773 (2) | |
See also: IR 05000341/1990002
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MAR 2 31990'
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The Detroit Edison Cempany
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ATTN:
B. Ralph Sylvia
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Senior Vice President -
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Nuclear Operations
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6400 North Dixie Highway
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Newport, MI 48166
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' Gentlemen:
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This refers.to the routine safety inspection conducted by Messrs. W. G. Rogers,
S. Stasek, P. R. Polke, and M. J. Farber of this office on January 1 through
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February 20, 1990,'of activities at Fermi 2 authorized by Facility Operating
License No, NPF-43 and to the discussion of our findings with Mr. W. S. Orser
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at the conclusion of the inspection.
The enclosed copy of our inspection report identifies areas examined during
the inspection. . Within the:,e areas, the inspection consisted of a selective
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' examination of procedures and representative records, observations, and
interviews with personnel..
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An Enforcement Conference was held on February 7,1990, to address the issues
involved in the loss of auto-start capability of the Emergency Equipment
Cooling Water and Emergency Equipment Service Water pumps as discussed in
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Inspection Report No. 50-341/89033(DRP). We have completed our review of
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the apparent v?olations discussed in Paragraphs 7.a (341/89033-01) and 7,b
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-(341/89033-02) and have determined that they do not warrant escalated
enforcement action. However, we have categorized the issue discussed in
Paragraph 7.a as a Severity Level IV problem as described in the enclosed
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Notice of Violation. A written response is required.
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The issue'of 10 CFR 50.72 reportability discussed in Paragraph 7.b was carefully
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reviewed by regional management and determined not to be a violation.
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decision is based on accepting your assessment of the systems' ability to meet
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their intended functions and recognizing the engineering judgement inherent in
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that assessment.
Notwithstanding, we are concerned that matters of far less
significance have been reported under 10 CFR 50.72, while loss of technical
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specification operability of the pumps associated with your ultimate heat sink
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is unreported. We encourage you, when presented with similar circumstances in
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.the future where the reportability of an occurrence is in question, to make
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.the report via the Emergency Notification System.
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Attachment I to the enclosed inspection report documents the results of a
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followup inspection of Emergency Operating Procedures issues conducted by
Ms. P. L. Eng of the Office of Nuclear Reactor Regulation on July 31 through
August 2, September 25-29, and November 3, 1989. The majority of previously
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. identified items were adequately resolved; hcwever, some corrective actions had
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not been fully implemented by the conclusion of the inspection. These will be
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reviewed in the future by the resident inspector staff.
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In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
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this letter and the enclosed inspection report and attachment will be placed
in the NRC Public Document Room.
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
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Origina,1 signed by E. G. Cretnman
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Edward G. Greenman, Director
Division of Reactor Projects
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Enclosures:
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2.
Inspection Report
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No. 50-341/90002(DRP)
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3.
Attachment 1
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cc w/ enclosures *
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D. R. Gipson Plant Manager
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Patricia Anthony, Licensing
P. A. Marquardt, Corporate
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Legal Department
DCD/DCB (RIDS)
Licensing Fee Management Branch
Resident Inspector, RIII
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James R. Padgett, Michigan Public
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Service Commission
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Harry H. Voight, Esq.
Michigan Department of
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