ML20236N990

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Forwards Insp Repts 50-282/98-10 & 50-306/98-10 on 980605-12 & Nov.One Violation Identified.Violation Involved Inadequate Procedural Guidance for Dumping SG Power Operated Relief Valves While Maintaining Plant in Prolonged Shutdown Mode
ML20236N990
Person / Time
Site: Prairie Island  Xcel Energy icon.png
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

l

Mr. M. Wadley, President

Nuclear Generation

Northem States Power Company

l 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

PDR ADOCK 05000202

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M. Wadley -2-

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

License Nos.: DPR-42; DPR-60

Enclosures: 1. Notice of Violation

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:

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C. Paperiello, Rlli w/enci

J. Caldwell, Rill w/enci

B. Clayton, Rlli w/enct

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DATE 07/10/98 l07/m/98 07/c/98 9/1$ 07/s*/98

OFFICIAL RECORO COPY

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