ML20198A400
| ML20198A400 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/23/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20198A404 | List: |
| References | |
| 50-282-97-19, 50-306-97-19, NUDOCS 9801050364 | |
| Download: ML20198A400 (2) | |
See also: IR 05000282/1997019
Text
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December 23, 1997
Mr. M. Wadley
Vice President, Nuclear Generation
Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
NRC INSPECTION REPORTS 50-282/97019(DRS); 50-306/97019(DRS);
LICENSED OPERATOR REQUALIFICAT!ON TRAINING PROGRAM
EVALUATION AND NOTICE OF VIOLATION
Dear Mr. Wadley:
On October 3,1997, the NRC completed an on site inspection at your Prairio Island Nuclear
Generating Plant. The purpose of this inspection was to review the licensed operator
requalification program. This initial inspection identified some issues which resulted in
additionalinspection. The inspection findings were discussed with your staff on October 3,
1997, and during a teleconference on October 23,1997. The inspection findings were also
discussed during a management meeting on November 25,1997. The final disposition of the
remaWng unresolved issues was discussed during the regularly scheduled resident inspector
meeting on December 2,1997. The enclosed report presents the results of the inspection.
The inspectors concluded the licensed reactor operator and senior reactor operator
requalification programs were generally implemented in accordance with 10 CFR Part 55
require <nents. Examination material prepared by your training staff, and operator evaluations
perfomied by your training staff, were satisfactory.
However, based on the results of this inspection, the NRC has determined that two violations of
NRC requirements occurred. The first violation involved a procedure inadequacy that
circumvented proper performance of the Reactor Trip and Anticipated Transisnt Without Scram
emergency operating procedures. This violation is of concem because your r taff failed to
understand the proper entry conditions for a fundamental plant operating pre :edure. It is clear
that your staff still did not understand these entry conditions until after the .. sember 25,1997
management meeting. The second violation involved a nroblem with your procedure change
management program and is of concem because appropriate management oversight of such
changes is an important element of the process.
These violations are cited in the enclosed Notice of Violation (Notice). The r*cumstances
pertaining to the violations are described in detail in the enclosed report. Please note that you
are required to respond to these violations and should follow the instructions specified in the
enclosed Notice when preparing your response. The NRC will use your response, in part, to
determine whether further enforcement action is necessary to ensure compliance with
regulatory requirements,
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosures, and your response will be placed in the NRC Public Document Room (PDR).
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December 23, 1997
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
original signed by J. M. Jacobson g
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John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-282; 50-306
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Enclosures:
2. Inspection Reports 50 282/97019(DRS); 50-306/97019(DRS)
A w/encis:
Plant Manager, Prairie Island
State Liaison Officer, State
of Minnesota
State Liaison Officer, State
of Wisconsin
Tribal Council, Prairie 1 stand
Dakota Community
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SRI, Prairie Island w/encls
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DOCDESK w/ enc!s
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