ML20217P884
| ML20217P884 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/21/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20217P887 | List: |
| References | |
| 50-282-97-14, 50-306-97-14, NUDOCS 9708290038 | |
| Download: ML20217P884 (2) | |
See also: IR 05000282/1997014
Text
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August 21, 1997
Mr. M. Wadley .
Vice President, Nuclear Generation
Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
NRC RADIATION PROTECTION INSPECTION REPORTS 50 282/97014(DRS)-
AND 50 306/97014(DRS)
Dear Mr. Wadley:
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On July 18,1997, 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.
Overall, the implementation of the station effluents program was effective in maintaining
site releases As Low As is Reasonably Achievable. The performance and material
condition of the various ventilation system filters, station radiation monitors, and
liquid / gaseous radwaste components were acceptable. However, there were several
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problems identliied during our review which indicated a weakness in the calibration of the
area and process radiation monitors. Additionally, we identified several minor errors in the
1996 Annual Radioactive Effluent and Waste Disposal report, and with some radiation
monitor calibration records. These items together with your self assessment findings
regarding the failure to prepare composite samples in accordance with the Offsite Dose-
Calculation Manual were considered problems with attention to detail by plant personnel.
As a result of your identification and thorough corrective actions, the failure to prepare the
composite samples in accordance with the procedural requirements of the Offsite Dose
Calculation Manual was considered a Non-Cited Violation.
in accordance with 10 CFR 2.790 of. the NRC's " Rules and Practice," a copy of this tetter
and its enclosures will be place in the NRC Public Document Room.
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9708290038 970821
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M. Wadley
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August 21 ,1997
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..We will gladly discuss any questions you have concerning this inspection.
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Sincerely,
Original Signed by John M. Jacobson (for).
John A. Grobe, Acting Director -
Division of Reactor Safety
Docket Nos. 50 282, 50 306
Enclosure: Inspection Report 50 282/97014(DRS),.50-306/97014(DRS)
cc w/ encl:
Plant Manager, Prairie Island
John W. Ferman, Ph.D.
Nuclear Engineer, MPCA
State Liaison Officer, State
of Minnesota
State Liaison Officer, State
of Wisconsin
Tribal Council, Prairie Island
Dakota Community
Distribution:
Docket File w/enci
Rlli PRR w/ encl
W. L. Axelson, Ritl w/enci
PUBLIC IE 01 w/ encl
SRis, Prairie Island,
Enf. Coordinator, Rlll w/enci
OC/LFDCB w/enci
Monticello w/enct
TSS w/enci
. DRP w/ encl
LPM, NRR w/enci-
CAA1 w/ encl
DRS w/enci
A. B. Beach, Rlli w/enci
DOCDESK w/enci
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DOCUMENT NAME: G:\\DRS\\PRA97014.DRS
To receive a copy of this document. Indicate in the box 'c' = Copy w/o attach / enc! T = Copy w/ attach / encl T = Nopapy
OFFICE
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DATE-
08/7 /97
08/g /97
08/7 /97
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OFFICIAL RECORD COPY
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