IR 05000282/1980020
| ML20008E829 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/20/1981 |
| From: | Burgess B, Feierabend C, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20008E828 | List: |
| References | |
| 50-282-80-20, 50-306-80-20, NUDOCS 8103090799 | |
| Download: ML20008E829 (1) | |
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U.S. NUCLEAR REGUIATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEFENT
REGION III
Report No:
50-282/80-20; 50-306/80-20 Docket No:
50-282; 50-306 License No: DPR-42; DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, EN.
55401 Facility Name:
Prairie Island Nuclear Generating Plant Inspection At:
Prairie Island Site, Red Wing, MN.
Inspection Conducted: December 1-31, 1980 Inspectors:
C. D. Feierabend B. L. Burgess
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Approved By:
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S. Lit'tle, Chief
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Reactor Projects Section 2 Inspection Summary Inspection on December 1-31, 1980 (Report No. 50-282/80-20; "0-306/80-20)
Areas Inspected: Routine Resident inspectice of plant operation, mainten-ance, surveillance, security, radiation pro cection, preparation for reftel-ing, followup on IE Bulletins and followup of licensee actions on previous inspection findings. - The inspection involved 98 inspection hours onsite by two NRC inspectors including 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> onsite during offshif ts.
Results: No items of noncompliance or deviations were identified.
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e DETAILS
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1.
Personnel Contacted F. Tierney, Plant Manager J. Brokaw. Plant Superintendent, Operations and Maintenance E. Watzl, Plant Superintendent, Plant Engineering and Radiat 'on Protection A. Hunstad, Staff Engineer R. Lindsey, Superintendent, Operations J. Nelson, Superintendent, Maintenance J. Hoffman, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, Radiation Protection R. Stenroos, Assistant Radiation Protection Superintendent A. Smith, Senior Scheduling Engineer M. Klee, Superintendent, Nuclear Engineering K. Albrecht, Superintendent, Ouality Assurance D. Haugland, Engineer K. Beadell, Engineer D. Cragoe, Shift Supervisor P. Ryan, Shift Supervisor M. Balk, Shift Supervisor 2.
Licensee Actions on Previous Inspection Findings The inspector confirmed licensee corrective actions, a.
(Closed) Noncompliance (306/78-23) Review and approval of relay test procedure.
b.
(Closed) Deviation (282/80-06; 306/80-07) Special inspection of motor starters on safety related systems.
3.
Operational Safety verification a.
General Units 1 and 2 operated routinely throughout the month.
C. L. Miller, NRR, was a site visitor on December 10, 1980. Visit was related to NRR contract research program.
b.
Control Room Observations The inspector observed control room operations, reviewed applicable logs, conducted discussions with control room operators and observed shift turnovers. The inspector verified the operability of selected emergency systems, reviewed equipment control records, and verified proper return to service of affected components.
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c.
Tours Tours of the auxiliary, turbine and containment buildings, and external areas were conducted to observe plant equipment conditions, including potential fire hazards, and to verify that maintenance requests had been initiated for equipment in need of maintenance. By observation and direct interview, the inspector verified that security procedures were being implemented in accordance with the plant security plan.
The inspectors observed plant housekeeping / cleanliness conditions, and verified implementation of radiation protection controls, d.
Independent Verification The inspector performed a walkdown of the accessible portions of the fire protection (FP) system. This included confirmation of selected portions of the licensee's procedures, checklists, and plant drawings, inspection of condition of components and piping supports, inspection of breakers and cabinets, verification of selected instruments for proper valving, equipment control locks or tags and comparison of remote and local indication.
e.
Spent Resin Cask The inspector observed the transfer of spent resin from the spent resin tank to the spent resin cask. The ins pection included review of the applicable plant procedures and technical specifications, observation of the preparation and radiological controls prior ec resin transfer, the transfer.of the resin, independent meastlement and verification of radiation surveys made during and after resin
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transfer, insuring compliance with NRC and DOT transportation re-quirements, and interviews with plant personnel.
4.' Maintenance
.a.. Review of Work Requests (WR's) and Work Request Authorizations (WRA's)
The inspector selected and reviewed several WR's and WRA's to deter-mine. the ' status of safety related systems, to verify that proper priorities were given and to verify that design changes were initiated where appropriate.
b..
Observations
.The inspector observed portions of safety related maintenance activities to determine that the' activities did not violate limiting conditions
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for operation (LCO's), that administrative approvals and equipment control' tags were completed prior to initiating.the work, that approved
' procedures were used (or activity was within the " skills of the trade"),
and that the procedures used were adequate to control the activity.
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i The inspector observed maintenance performed on Unit 2 chemical
injec'cion line to the auxiliary feedwater system, maintenance on No. 121 motor driven fire pump, and replacement of the Unit I reactor coolant filter.
5.
Surveillance The inspector observed SP-1093 - 4.16 KV Rejection-Restoration Scheme Surveillance and verified that testing was performed in accordance with adequate procedures, that limiting conditions for operation were met, that removal and restoration of the af fected components were accomplished, and that test results conformed with Technical Specifications and pro-cedure requirements.
6.
I. E. Bulletins The inspector completed review of the licensee's actions in response to the following Bulletins and verified that the required actions are complete.
a.
IEB 78-05 Circuit Breaker Auxiliary Contact Mechanism b.
IEB 80-21 Valve Yokes Supplied by Malcom Foundary Co., Inc.
7.
Preparation for Refueling The inspector verified that approved procedures were available covering the receipt, inspection, and storage of new fuel, reviewed the qualifica-tion of fuel receipt and QA inspectors, observed the receipt inspection and storage of new fuel elements and verified these activities in adher-ance with the licensee's procedures.
No items of concern were identified.
8.
Exit Inte rviews The inspector conducted interim interviews during the inspection period and met with Mr. Tierney at the conclusion of the inspection. The in-spector discussed the scope and results of the inspection.
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