ML20216B545
| ML20216B545 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/04/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20216B533 | List: |
| References | |
| 50-341-97-11-01, 50-341-97-11-1, NUDOCS 9803130114 | |
| Download: ML20216B545 (17) | |
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NOTICE OF VIOLATION Detroit Edison Company
. Docket Number 50-341 Enrico Fermi 2 Nuclear Power Plant License Number NPF-43 EA 97-479 i
During an NRC inspection conducted on August 4 - October 10,1997, a violation of NRC requirements was idenbried. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violation is listed below:
I 10 CFR 50.59 permits the licensee, in part, to make changes to the facility, and procedures, as described in the safety analysis report, without prior Commission approvs!, provided the changes do not involve an unreviewed safety question. Records of these changes must include
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a written safety evaluation which provides the bases for the determination that the changes do not involve an unreviewed safety question.
10 CFR 50.59(a)(2) states, in part, that a proposed change shall be deemed to involve an.
unreviewed safety question if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created.
The Fermi Updated Final Safety Analysis Report, Revision 7, Section 9.2.2.2, " System Description," stated, in part, that during normal plant operation, both emergency equipment cooling water divisions were isolated from the reactor building closed cooling water system. It further noted that the emergency equipment cooling water system would automatically activate upon failure of the reactor building closed cooling water system.
Contrary to the above, Safety Evaluation 95-0036, Revision 0, approved by the licensee on July 14,1995, which evaluated a change to the facility as described in the updated final safety analysis report to permit operation of the emergency equipment cooling water system during normal plant operation to supply non-safety-related loads, was inadequate in that an incomplete analysis was performed. Specifically, the analysis did not consider all scenarios in providing the bases for the determination that an unreviewed safety question did not exist. For a high energy line break outside containment without a concurrent loss of offsite power, the change resulted in bypassing an automatic actuation of the system due to loss of the reactor building closed cooling water system. This resulted in operator actions being specified to resolve an apparent i
lack of cooling to safety-related equipment, a scenario not previously evaluated. (01014) l This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, the Detroit Edison Company is hereby required to submit a written statement or explanation to the U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, Region lil, and a copy to the NRC Resident inspector at the Fermi 2 site, within
. 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include (1) the reason for the violation, or if contested, the basis for disputing the violation; (2) corrective action taken and the results achieved; (3) the corrective action to be taken to avoid further violations; and (4) the date when 9803130114 990304 PDR ADOCK 05000341 G
full compliance will be achieved. Your response may reference or include previous docketed correspondence,if the correspondence adequately addresses the required response. If an r
adequate response is not received within the time specifim$ in this Notice, an order or a demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is -
shown, consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response to the
- Director, Office of Enforcement, U. S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
i l-Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include way personal privacy, proprietary, or safeguards information so j
that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your i
response that deletes such information. If you request withholding of such material, you mutt specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by l
10 CFR 2.790(b) to support a request for withholding confidential commercial or financial l
Information).
Dated at Lisle, Illinois, this 4 th day of February,1998 i
l L
List of Attendees at Public Pre-Decisional Enforcement Conference Detroit Edison Comoany P. Fessler, Plant Manager D. Gipson, Senior Vice President, Nuclear Generation K. Howard, Plant Support Engineering, Director L. Layton, Nuclear Information Supyvisor P. Marquardt, Practice Group Head W. O'Connor, Manager, Nuclear Assessment N. Peterson, Director, Licensing J. Plona, Technical Director Nuclear Reaulatorv Commission B. Beach, Regional Administrator, Region 111 (Rlll)
B. Berson, Regional Counsel, Rill J. Bongarra, Human Factors Specialist, Office of Nuclear Reactor Regulation (NRR)
R. Burrows, Enforcement Staff, Rill M. Dapas, Acting Deputy Director, Division of Reactor Projects (DRP), Rlli S. DuPont, Project Engineer, DRP, Rlli J. Grobe, Director, Division of Reactor Safety (DRS), Rill G. Harris, Senior Resident inspector A. Kugler, Project Manager, NRR P. Lougheed, Acting Branch Chief, Lead Engineers Branch, DRS, Rlli C. Weil, Enforcement Specialist, Rlli
- Public Attendee M. Durning, NUS Information Services l
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