IR 05000282/1980014
| ML19339B483 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/19/1980 |
| From: | Burgess B, Feierabend C, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19339B480 | List: |
| References | |
| 50-282-80-14, 50-306-80-15, NUDOCS 8011070040 | |
| Download: ML19339B483 (5) | |
Text
es a % gf U.S. NUCLEAR REGUI). TORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No: 50-282/80-14; 50-306/80-15 Docket No: 50-282; 50-306 License No: DPR-42; DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN.
55401 Facility Name: Prairie Island Nucle se Generating Plant
Inspection At: Prairie Island Site, Red Wing, MN.
55066 Inspection Conducted: August 1-31, 1980 Inspectors: g
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C.D.Feierabend
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Jo B.L. Burgess
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Appro ed By:
'W.S.Little, Chief
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Reactor Projects Section 2 Inspection Summarv Inspection on August 1-31, 1980 (Report No. 50-282/80-14; 50-306/80-15)
i Areas Inspected: Routine resident inspection of plant operation, maintenance, surveillance, security, radiation protection, organization, training and followup on I.E. Bulletins. The inspection involved 89 inspection hours onsite by two NRC inspectors. This included 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> of offshift inspection.
Results: No items of noncompliance were identified.
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i DETAILS 1.
Personnel Contacted F. Tierney, Plant Manager J. Brokaw,' Plant Superintendent, Operations and Maintenance E. Wat:1, Plant Superintendent, Plant Engineering and Radiation Protection A. Hunstad, Staff Engineer R. Lindsey, Superintendent, Operations J. Nelson, Superintendent, Maintenance J. Hof fman, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, Radiat!on Protection
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A. Smith, Senior Scheduling Engineer M. Klee, Nuclear Engineer R. Pearson, Engineer D. Brown, Engineer K. Albrecht, Superintendent, Quality Assurance Engineering D. Cragoe, Shif t Supervisor G. Edon, Shift Supervisor M. Balk, Shift Supervisor D. Walker, Shif t Supervisor P. Valtakis, Shift Supervisor 2.
Operational Safetv Verification a. General Unit 2 operated routinely throughout the month. Unit I was shut down on August 31 to begin an extended refueling and maintenance outage.
Plant visitors during the month included members of tne Atomic Safety and Licensing Board Panel on August 5, and the NRR Project Manager for Prairie Island on August 7.
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.
c.
Tours Tours of the auxiliary, turbine and shield 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 haplementec in accordance with the plant security plan.
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The inspectors observed plant housekeeping / cleanliness conditions, and verified implementation of radiation protection controls. This included observing decontamination. of the irradiated specimen cask prior to release for shipment..
d.
Independent Verification The inspectors performed walkdowns of the accessible portions of the cooling water and auxiliary feedwater systems. This included confirmation of selected portions of tne licensee's procedures, check-lists, and plant drawings, inspection of condition of components and piping supports, inspectio,' of 0;2akers and cabinets, verification of selected instruments for proper valving, equipment contr'1 locks or tags and comparison of remote and local indication.
The' inspector also performed independent verification of the D1 diesel generator and of the No.ll auxiliary feedwater pump.after return to service following completion of maintenance and surveillance tests.
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e.
Verification of Plant Conditions The inspectors independently verified the status of plant and equip-ment conditions to confirm fulfillment of Technical Specifications (TS)
limiting condition for operation (LCO) requirements, the following LCO's were verified:
TS 3.3.C Component Cooling Water Sys tem TS 3.3.D Cooling Water System TS 3.4 Steam and Power Conversion System TS 3.7 Auxiliary Electrical System TS 3.10.32 Power Distribution Limits TS 3.10.D Rod Insertion Limits 3.
Organization and Administration The licensee has transferred responsibility for all training from the plants to the General Office under direction of Nuclear Safety Technical i
Services. This will require minor change to the Technical Specifications which will be included in the next routine Technical Specification change request.
Maintenance a.
Review of Work Request (RR's) and Work Request Authorizations (WRA' s)
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The inspector selected.and reviewed several WR's and WRA's to determine 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 for operation ( LCO'd, 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.
The inspectors witnessed maintenance activities during replacement of the oil cooler on D2 diesel generator and during annual preventive maintenance of D1 diesel generator.
5.
Surveillance The inspectors witnessed portions of surveillance testing of safety related systems and components. Witnessing included verifying that the tests were scheduled and performed within Technical Specification requirements, observing that procedures were being followed, that LCO's were not violated and that system restoration was completed.
Tests witnessed included portions of tests conducted on the D1 and D2 diesel generators, the No.12 auxiliary feedwater pump 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> endurance test and the main steam safety valves.
6.
Training The inspectors monitored a retraining lecture / discussion conducted for Technical staff senior license holders. Subject of the training was the control rod drive system.
7.
I.E. Bulletins The irspector reviewed the licensee's written response to the following bulletins, verified that the response incluled the recadred information and confirmed that the information in the response we securate.
a.
I.E.Bulletin 30-04 Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition Licensee analysis indicates that.no corrective action is required.
Additional plant specific analysis is expected to be completed later this. year.
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b.
I.'E.Bulletin 80-08 Examination of Containment Liner Penetration Welds Licensee response was not complete. -The licensee has supplemented the response, which is being reviewed by I.E. construction specialists.
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c.
I.E.Bulletin 80-09 Hydramotor Actuator Deficiencies
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There are no actuators of this type installed in safety related systems.
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d.
I.E.Bulletin 80-18 Minimum Flow Through Centrifugal Charging Pumps Not applicable.
(Closed)
8. Exit Interviews The inspectors conducted interim interviews wit' Messrs. Watzl a.ed Tierney and met with Mr. Tierney at the conclut. ion of the inspection.
The inspector discussed the scope and results of the inspection.. No items -of noncompliance or deviations were identified.
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