IR 05000320/2004020

Insp Repts 50-369/85-14 & 50-370/85-15 on 850320-0420.No Violations or Deviations Noted.Major Areas Inspected: Operations,Safety Verification,Surveillance Testing,Maint & Refueling Activities

ML20127N992
Person / Time
Site:	Three Mile Island, McGuire, Mcguire
Issue date:	05/08/1985
From:	Dance H, William Orders, Pierson R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127N986	List: IR 05000320/2004020 ML20127N981
References
50-369-85-14, 50-370-85-15, NUDOCS 8507020280
Download: ML20127N992 (5)

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Report Nos.: 50-369/85-14 and 50-370/35-15 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17 i Facility Name: McGuire 1 and 2 Insbection Conducted: March 20 - April 20, 1985 Inspectors: C_ [ G w W.' Order's, ' Senior Resident Inspector

1. Datd r!#:r Signed , erson,' Resident Inspector Yif Date' Signed Approved by: , C $ A2 _ (N &

Hugh T. Dancs, Tection Chief Date Signed Division of Reactor Projects SUMMARY Scope: This routine, special, unannounced inspection involved 246 inspection hours on site in the areas of operations, safety verification, surveillance testing, maintenance activities and refueling activitie Results: Of 'the.j five areas inspected, no violations or - deviations were identified. One bnresolved Item was identifie .

B 8507020200 850500 PDR ADOCK 05000369 O PDR

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REPORT DETAILS Licensee Employees Contacted

• T. McConnell, Plant Manager

• G. Cage, Superintendent of Operations D. Rains, Superintendent of Maintenance B. Hamilton, Superintendent of Technical Services

• L. Weaver, Superintendent of Administration

• B. Travis, Superintendent of Integrated Scheduling E. McCraw, License and Compliance Engineer

• R. White, IAE Engineer

< *G. Terrell, Station Health Physicist

• Rider, Maintenance Engineer

• Sipe, McGuire Safety Review Group

• Pierce, IAE Engineer

• Mendezoff, License and Compliance Engineer Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personne * Attended exit interview Exit Interview The inspection scope and findings were summarized on April 26, 1965, with those persons indicated in paragraph I above. The licensee acknowledged understanding of the issues discussed and offered no substantive related discussio The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items *

Unresolved items are discussed in paragraph . Plant Operations The inspection staff reviewed plant operations during the report period, March 20 - April 20, 1985, to verify conformance with applicable regulatory

• An Unresolved Item is a matter about which more information is required to determine whether it is acceptable or may involve a violation or deviatio I

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requirement Control room logs, shift supervisors logs, shift turnover records and equipment removal and restoration records were routinely perused. Interviews were conducted with plant operations, maintenance, chemistry, health physics, and performance personne Activities within the control rooms were monitored during shifts and at shift changes. Actions and/or activities observed were conducted as prescribed in applicable station administrative directive The complement of licensed personnel on each shift met or exceeded the minimum required by technical specification Plant tours were taken during the reporting period on a systematic basi The areas toured included but were not limited to the following:

Turbine Buildings Auxiliary Building Units 1 and 2, Electrical Equipment Rooms Units 1 and 2, Cable Spreading Rooms Station Yard Zone Within the Protected Area Unit 2 Reactor Building

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During the plant tours, ongoing activities, housekeeping, security, equip-ment status and radiation control practices were observe Unit 1 Operations McGuire Unit I began the reporting period in Mode 1 operating at 65%

power to facilitate optimum outage scheduling. The unit continued operating at or about 65% power until April 6, when power was reduced to 31% again to optimize coordination of outage scheduling with Unit On April 8 the unit was shut down when an out of specification boron sample was received from the "A" cold leg accumulator. Following correction of the boron concentration the unit was restarted and entered Mode 1 and was subsequently paralleled to the grid on the morning of April 10th. The unit was then maintained at approximately 34% through April 19, 1985, when the unit was shutdown for a refueling outage. This is the second refueling outage for Unit Unit 2 Operations McGuire Unit 2 began the reporting period in Mode 6 in the midst of the first refueling outage with fuel load in progress. Following comple-tion of fuel load and core alterations the unit entered Mode 5 on April 9. The unit remained in Mode 5 throughout the duration of the reporting perio . Missing Valve Operator Shorting Bars On April 3,1985, at 3:05 p.m., while performing Performance Test PT-2-A-4200-09A ESF Train A, the licensee found that shorting bars which were to have been installed on the breaker of the operator of valve 2NI-9A had not _ - _ _ _ _ _ _ . _ _ _ .

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been installed. The shorting bars were to have been installed to bypass the thermal overload protection of the breaker to assure valve operation during an accident situatio This issue is currently under review and will be maintained as an Unresolved Item pending completion of that analysis (50-370/85-15-01).

7. Surveillance Testing

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The surveillance tests categorized below were analyzed and/or witnessed by the inspector to ascertain procedural and performance adequacy. The completed test procedures examined were analyzed for embodiment of the necessary test prerequisites, preparations, instructions, acceptance criteria, and sufficiency of technical content. The selected tests witnessed were examined to ascertain that current written approved procedures were available and in use, that test equipment in use was calibrated, that test prerequisites were met, system restoration completed and test results were adequate. The selected procedures perused attested conformance with applicable Technical Specifica-tions and procedural requirements, they appeared to have received the required administrative review and they apparently were performed within the surveillance frequency specifie Procedure Number Procedure Title PT/2/A/4200/09A Engineering Safety Features Actuation Periodic Test PT/2/A/4600/08 Precriticality Survey Items PT/1/A/4250/04C Turbine Generator Overspeed Test PT/2/A/4252/04 CA Valve Movement Test / Shutdown PT/2/A/4355/01A Diesel Generator 2A Room Sump Pump Performance Test PT/1/A/4150/14 PORV Function PT/2/A/4252/02 CA Valve Stroke Timing-Quarterly PT/2/A/4206/03 NI Valve Stroke Timing-Quarterly PT/2/A/4360/11C Performance Test on 125 VDC Battery PT/1/A/4251/02 BB Valve Stroke Timing-Quarterly PT/1/A/4601/02 Protective System Channel II Function Test PT/0/A/4457/01A Control Room Chilled Water Pump 1 Performance Test PT/1/A/4403/018 RN Pump 1B Performance Test PT/1/A/4209/01A NV Pump 1A Performance Test PT/0/A/4350/11 RCP UV/UF Functional Test PT/1/A/4401/018 KC Train B Performance Test PT/1/A/4206/01A NI Pump 1A Performance Test PT/1/A/4601/03 Protective System Channel III Functional Test PT/1/A/4601/04 Protective System Channel IV Functional Test PT/1/A/4251/02 BB Valve Stroke Test PT/1/A/4208/01A NS Pump 1A Performance Test PT/1/A/4252/01A CA Pump 1A Performance Test PT/1/A/4252/01B CA Pump 1B Performance Test PT/1/A/4150/14 PORV Channel Function Test

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PT/2/A/4208/01A NS Pump 2A Performance Test PT/2/A/4206/03 NI Valve Stroke Test PT/2/A/4209/01B NV Pump 2B Performance Test PT/2/A/4601/03 Protective System Channel III Performance Test PT/2/A/4209/01C Standby Makeup Pump Performance Test 8. Unit 2 Refueling Outage During this report period, Unit 2 was involved with a refueling outag During this outage, the following major maintenance activities and plant modifications were completed: Following the destruction of several main journal bearings on the 2A diesel generator (DG), the crankshaft was replace The Reactor Vessel Level Indication System (R VLIS) was installed, Three containment spray pressure transmitters were replace Steam generator blowdown valves BB-140, 141, 142, and 143 were remove The main feedwater pump pedestals were replaced due to cracking in the old concrete pedestals. They were replaced with steel pedestal Changeout of the Unit 2 moisture separator reheater tube bundle . Maintenance Observations The maintenance activities categorized below were analyzed and/or witnessed by the resident inspection staff to ascertain procedural and performance adequacy. The completed procedures examined were analyzed for embodiment of the necessary prerequisites, preparations, instruction, acceptance criteria and sufficiency of technical detail. The selected activities witnessed were examined to ascertain that were applicable, current written approved procedures were available and in use, that prerequisites were met, equipment restoration completed and maintenance results were adequate. The selected work requests /

maintenance packages perused attested conformance with applicable Technical Specifications and procedural requirements and appeared to have received the required administrative revie Work Request Equipment 120067 Repair NC-133 040575 SR Detector NI-31 040576 SR Detector NI-32 55779 2B NV Pump 92430 Perform Checkout of Electrical Portion of RVLIS Installation Unit 2