ML20211J854

Forwards Insp Repts 50-282/97-17,50-306/97-17 & 72-0010/97-17 on 970825-29 & 970908-12.No Violations Noted. Inappropriate Decisions Re Scaling Factor Determinations for Radionuclides Demonstrated Sole Reliance on Past Experience

ML20211J854
Person / Time
Site:	Prairie Island
Issue date:	10/04/1997
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Wadley M NORTHERN STATES POWER CO.
Shared Package
ML20211J858	List: IR 05000282/1997017 ML20211J854
References
50-282-97-17, 50-306-97-17, 72-0010-97-17, 72-10-97-17, NUDOCS 9710080320
Download: ML20211J854 (2)

See also: IR 05000282/1997017

Text

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Mr. M. Wadley

Vice President, Nuclear Generation

Northern States Power Company

414 Nicollet Mall

Minneapolis, MN 55401

SUBJECT: NRC RADIATION PROTECTION INSPECTION REPORTS 50-282/97017(DRS);

50-306/97017(DRS); AND 7210/97017(DRS)

Dear Mr. Wadley:

On September 12,1997, the NRC completed an inspection at your Prairie Island Nuclear

Generating Plant. The enclosed report presents the results of that inspection.

Areas examined during the inspection are identified in the report. Within these areas, the

inspection consisted of a selective examination of procedures and representative records,

observations, and interviews with personnel. No violations of NRC requirements were

identified.

Overall, the station chemistry, environmental monitoring, and solid radwaste storage and

transportation prograrrs were effectively implemented. Chemistry quality assurance activities

ensured accurate analytical capabilities, although your staff experienced some problems with

quality assurance analyses in a primary system matrix. The environmental monitoring program

showed that station operations did not have a discernable radiological impact on the

environment.

. The solid radwaste management and transoortation program was implemented in accordance

with the new Department of Transportation regulations. However, recent inappropriate

cecisions regarding scaling factor determinations for two radionuclides and the unconditional

release of contaminated turbine building sump sludge demonstrated that your staff relied solely

on past experience and practices without sufficient consideration for recent plant developments.

in accordance with 10 CFR 2.700 of the NRC's " Rules and Practice," a copy of this letter and its

,

enclosure will be place in the NRC Public Document Room (PDR).

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We will gladly discuss any questions you have concerning this inspection.

I Sincerely,

Original Signed by John A. Grobe

John A. Grobe, Acting Director

Division of Reactor Safety

Docket Nos 50-282 50-306; 72-10

Licenses No. DPR-42; DPR-60; SNM 2506

Enclosure: Inspection Reports 50-282/97017(DRS); 50-306/97017(DRS); 7210/97017(DRS)

cc w/enet: Plant Manager, Prairie Island

State Liaison Officer, State

of Minnesota

State Liaison Officer, State

of Wisconsin

Tribal Council, Prairie Island

Dakota Community

Distribution:

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PUBLIC IE-01 w/enci SRis, Prairie Isiand, Enf. Coordinator, Rlli w/enci

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DRS w/enct A. B. Beach, Rill w/enci 00CDESK w/ encl

DOCUMENT NAME: G:\DRS\PRA97017.DRS

To receive a copy of this document, Indicate in the box 'C" = Copy w/o attach /enct 'E' = Copy w/ attach /enci"N" = No copy

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