ML20236N990
| ML20236N990 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/10/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20236N992 | List: |
| References | |
| 50-282-98-10, 50-306-98-10, NUDOCS 9807160106 | |
| Download: ML20236N990 (2) | |
See also: IR 05000282/1998010
Text
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July 10, 1998
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Mr. M. Wadley, President
Nuclear Generation
Northem States Power Company
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414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
NRC SPECIAL INSPECTION REPORT NO. 50-282/98010(DRS);
50-306/98010(DRS) AND NOTICE OF VIOLATION
1
Dear Mr. Wadley:
On June 12,1998, the NRC completed a special inspection et your Prairie Island Nuclear
Generating Plant. The enclosed report presents the results of that inspection.
On June 5,1998, the plant experienced a reactor trip as the result of a dropped control rod.
This special inspection consisted of a review of selected equipment abnormalities, procedure
adequacy, and operatkins staff performance associated with the plant response and
subsequent placement of the plant in a safe shutdown condition. Areas inspected are ider'jfied
in the enclosed report.
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The inspection revealed that your operators initially did a good job responding to the
unexpected reactor trip, and took appropriate action based on plant indications. However, their
training and practical experience had not prepared them to maintain the plant in a hot shutdown
condition with the main steam isolation valves closed and using the steam generator power
operated relief valves to dissipate decay heat. Additional weaknesses that contributed to the
inability to maintain adequate decay heat removal included: an inadequate procedure for
dumping steam; one instance of a lack of three part communications; lack of maintaining a
consistent oversight of plant status; and apparent lack of fidelity between the simulator and
plant power operated relief valve response.
Based on the results of this inspection one violation of NRC requirements was identified and is
cited in the enclosed Notice of Violation (Notice). The violation involved inadequate procedural
guidance for dumping steam using the steam generator power operated relief valves while
maintaining the plant in a prolonged hot shutdown mode with the main steam isolation valves
closed. Please note that you are required to respond to this lette: 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.
9807160106 990710
ADOCK 05000202
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M. Wadley
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In accordance with 10 CFR Pstt 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosures, and your resoonse will be placed in the NRC Public Document Room.
Sincerely,
Original /s/ R. N. Gardner for
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-282; 50-306
Enclosures:
2. Inspection Report 50-282/98010(DRS);
50-306/98010(DRS)
cc w! encl:
Plant Manager, Prairie laiand
State Liaison Officer, State
of Minnesota
State Liaison Officer, State
of Wisconsin
Tribal Council
Prairie Island Dakota Community
Distnbution:
CAC (E-Mail)
Project Mgr., NRR w/enci
C. Paperiello, Rlli w/enci
J. Caldwell, Rill w/enci
B. Clayton, Rlli w/enct
SRI Prairie Island w/enci
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Rlli PRR w/enct
PUBLIC IE-01 w/enci
Docket File w/enci
GREENS
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DOCDESK (E-Mail)
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DATE
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OFFICIAL RECORO COPY
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