IR 05000369/1985035

Insp Repts 50-369/85-35 & 50-370/85-36 on 850921-1028.No Violation or Deviation Noted.Major Areas Inspected: Operations Safety Verification,Surveillance Testing & Maint Activities

ML20198E186
Person / Time
Site:	McGuire, Mcguire
Issue date:	11/07/1985
From:	Dance H, William Orders, Pierson R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20198E144	List: IR 05000369/1985035 ML20198E139
References
50-369-85-35, 50-370-85-36, NUDOCS 8511130200
Download: ML20198E186 (11)

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' . Report Nos: 50-369/85-35 and 50-370/85-36 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station Docket Nos: 50-369 and 50-370 License Nos: NPF-9 and NPF-17 Inspection on September 21 - October 28, 198 Inspectors: 0, W. Orddrs, Yior JAf &

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V7I Mugh C# Dance, Sec\ ion Chief Date Signed Division of Reactor Projects SUMMARY Scope: ' This routine unannounced inspection involved 374 hours0.00433 days <br />0.104 hours <br />6.183862e-4 weeks <br />1.42307e-4 months <br /> on site in the areas of.' operations safety verification, surveillance testing and maintenance activitie Results: Of the areas inspected no violations or deviations were identifie PDR ADOCK 05000369 G PDR

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REPORT DETAILS Persons Contacte ~

Licensee Employees

• T. McConnell, Plant Manager

• B. Travis, Superintendent of Operations D.~ Rains, Superintendent of Maintenance B.-Hamilton, Superintendent of Technical Services  !

L. Weaver, Superintendent of Administration

• M. Sample, Superintendent of Integrated Scheduling

• E. McCraw, License and Compliance Engineer D. Mendezoff, License.and Compliance Engineer

D. Marquis, Performance Engineer R. White, IAE Engineer R.. Branch, Site QA Supervisor

• J. . Day, General Office Licensing

• J. .Torre, General Office Licensing Other licensee employees contacted included construction craftsmen, technicians, operators, mechanics, security force members, and office personne * Attended exit intervie . Exit-Interview The-inspection scope and. findings were summarized on November 1, 1985, with

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those persons indicated in paragraph 1 above. The licensee did not identify as proprietary l any of the - materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters (CLOSED) 369/84-11-03 Failure to follow procedure and inadequate procedure leading to inadvertent Train A blackou Adequate corrective steps have been taken which should preclude the type of personnel and adminisrative errors responsible for this violation. This item is close . Unresolved Items No unresolved ~ items were identified during this report perio . Plant Operations The inspection staff reviewed plant operations during the report period, to verify conformance with applicable regulatory requirements. Control room Llogs,- shift supervisors logs, shif t turnover records and equipment removal-and restoration records were routinely perused. Interviews were conducted

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with . plant operations, maintenance, chemistry, health physics, and perfor-mance personne Activities within the control room 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 taken during the reporting period included but were not limited to the turbine buildings, auxiliary building, Units 1 and 2 electrical equipment rooms, Units 1 and 2 cable spreading rooms, and the station yard zone inside the protected area. During the plant tours, ongoing activities, housekeeping, security, equipment status and radiation control practices were observe Unit 1 Operations McGuire Unit I began the reporting period in Mode 1 operating at 100% powe It was maintained in Mode 1 at or about 100% power for the duration of the reporting perio Unit 2 Operations McGuire Unit 2 began the reporting period operating at 100% power and was maintained at or about that power level until 8:45 a.m. on October 24, when the unit tripped.due to lo lo steam generator level in the C generato 'Immediately preceding the trip, at 8:42 A.M., inverter breaker 2EVIB feeding bus.2EKVB was inadvertently tripped. This, in turn, through associated circuitry and instrumentation led to diminished feed flow to the C . steam generator and the ' reactor tri Following necessary surveillance testing associated with the trip, the unit was taken critical at 3:25 a.m. on October 25 and was placed on line at 1:43 p.m. that afternoon. At 2:40 on October 26 the unit tripped from 90% power due to a malfunction of the main generator voltage regulator causing a turbine trip reactor tri Following troubleshooting and repairs to the main generator, the unit was taken critical at 2:10 that same day and was placed on line at 6:38 p.m. that evenin The unit completed the report period at 100% powe . Surveillance Testing The surveillance tests categorized below were analyzed and/or witnessed by the inspector to ascertain procedural and performance adequacy and con-formance with applicable Technical Specification The selected tests witnessed were examined to ascertain that current written approved proce-dures were available and in use, that test equipment in use was calibrated, that test prerequisites were met, system restoration completed and test results were adequat .

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TT/1/A/9100/99 Nuclear Service Water Train 1A Pump Special Test

. PT/1/A/4252/01A Motor Driven CA Pump A Performance Test PT/1/A/4252/01B Motor Driven CA Pump B Performance Test PT/1/A/4350/15B DG 1B Periodic Test '

PT/1/A/4601/02 Protective System Channel II Functional Test PT/1/A/4601/04 Protective System Channel 4 Functional Test PT/0/A/4450/01 In Place Test of HEPA and Carbon Adsorbe '

Filters PT/1/A/4208/01A Containment Spray 1A Performance Test

'PT/1/A/4208/01B Containment Spray IB Performance Test PT/1/A/4401/01A Component Cooling Train IA Performance Test PT/0/A/4350/08E 125VDC Vital Charger Performance Test PT/1/A/4403/01A Nuclear Service Water Train IA Performance Test PT/1/A/4403/05 RN System Baseline Performance Test PT/1/A/4403/04 RN Supplied Heat Exchanger Performance Monitoring PT/2/A/4601/01 Protective Systems Channel 1 Functional Test PT/2/A/4208/01A Containment Spray 2A Performance Test PT/2/A/4204/01B Residual Heat Removal 2B Performance Test

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PT/2/A/4209/01B Centrifugal Charging Pump 2B Performance Test PT/2/A/4206/01B Safety Injection Pump 2B Performance Test'

PT/2/A/4206/01A Safety Injection Pump 2A Performance Test PT/2/A/4252/01A M/D Aux. Feedwater Pump 2A Performance Test Maintenance Observations The maintenance activities categorized below were analyzed and/or witnessed by. the resident inspection staff to ascertain procedural and performance -

adequacy and conformance with applicable Technical Specifications. The selected activities witnessed were examined to ascertain that where applicable, current written approved procedures were available and in use, that prerequisites were me Equipment restoration completed and mainten-ance results were adequat Work Request Title 126021 Check Orifice on IRNFE-5040 (RN Pump Flow) Ventilation System Testing As detailed in. report 369/85-30 a review of the regulatory requirements associated with the preoperational and surveillance testing of the McGuire Auxiliary Building Filtered Exhaust System (VA), revealed that the pre-operational testing performed on both units VA systems was apparently not performed in accordance with documented commitment A deviation (369/85-30-02, 370/85-32-01) and Unresolved Item (369/85-30-03, 370/32-02)

were opened. The Unresolved Item was predicated upon the fact that the airflow distribution tests which were not performed, could affect the results- of other surveillance tests, i.e., the representativeness of the

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charcoal samples sent in for laboratory analysis. A special inspection was performed during the week of October 14 to evaluate the Unresolved Ite The details of that inspection are entailed on inspection report (50-369/85-39, 50-370/85-40). On October 25, testing which had not been performed . pursuant to FSAR commitment, specifically air flow distribution tests, were performed on the Auxiliary Building Ventilation Systems of both units. The ' results of that testing has been forwarded to Region II for evaluatio . Nuclear Service Water On October 4, 1985 during the performance of PT/1/A/4403/01A, Quarterly Surveillance on IA Nuclear _ Service Water (RN) Pump, it was determined that one data point on the pump head curve was less than 90% of the reference value. After additional evaluation and flow instrument verification the pump was declared inoperable at 10:30 p.m. that night. Over the weekend a new pump impeller was installed. The old impeller which had been installed in January of 1985, showed no visible signs of wea On October 7 additional pump head curves were performed which showed sub-stantially the same results as those performed Friday before the new impeller had been installed. As the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement was due to-expire Monday, the licensee chose to cross connect Nuclear Service Water Pump 1A and Nuclear Service Water Pumo.2A since the licensee judged that the combined flow was adequate, although 1A alone was no On October 9, during a runout test on IA RN, it was determined that one of the cross connect valves 1RN33 supposedly opened on October 7 was, in fact, closed due to an incorrect indicator which showed open when the valve was closed, and closed when the valve was open. Details of this incident and enforcement action taken are described in report 50-369/85-38 and 50-370/85-39. - This lineup was corrected and the loop was maintained in a unit cross connected lineup. On October 10, following an NRC Regional review of this incident, Regional-NRC management informed the licensee that operating the nuclear service water system with 1A RN and 2A RN pumps cross connected was not acceptable. The licensee subsequently shut the cross connects and. declared the 1A RN system inoperable. The licensee then performed a design evaluation and subsequently declared the 1A RN pump operable nn October 11, with restrictions on the loads it can supply with 1A and 2A operating on a common suction. This evaluation is currently under NRC review and will be discussed in detail in inspection report 50-369/85-38 and 50-370/85-3 ,. ,

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.35 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:

SUBJECT: REPORT N05. 50-369/85-35 AND 50-370/85-36 On September 21 - October 28, 1985, NRC inspected activities authorized by NRC Operating License Nos. NPF-9 and NPF-17 for your McGuire . facility. At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection repor Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progres Within the scope of the inspection, no violations or deviations were identifie Should you have any questions concerning this letter, please contact u

Sincerely,

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Virgiv L. Brownlee, Chief Reactor' Projects Branch 2 Division of Reactor Projects

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Enclosure:

Inspection Report Nos. 50-369/85-35 and 50-370/85-36 cc w/ encl:

T. L. McConnell, Station Manager

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r UNITE 3 STATES fp a atroq'o NUCLEAR REGULATORY COMMISSION

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• y , REGloN 18 g j 101 MARIETTA STREET, * 2 ATLANTA, GEORGI A 30323

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Report Nos: 50-369/85-35 and 50-370/85-36 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station Docket Nos: 50-369 and 50-370 License Nos: NPF-9 and NPF-17 Inspection on September 21 - October 28, 198 Inspectors: d, A,/ b -

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W. Orders, Yior sident"pspector Date S(gned , 'M sL/. Y Mi 9 3" R. P rson , le s tInsp%or Daye g d Approved by: k 5+ w = V7I Mugh C# Dance, Sec\ ion Chief Date $igned Division of Reactor Projects SUMMARY Scope: This routi~ne unannounced inspection involved 374 hours on site in the areas of operations safety verification, surveillance testing and maintenance activitie Results: Of the areas inspected no violations or deviations were identified.

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s ( * REPORT DETAILS . Persons Contacted Licensee Employees

*T. McConnell, Plant Manager
~* Travis, Superintendent of Operations D. Rains, Superintendent of Maintenance B. Hamilton, Superintendent of Technical- Services L. Weaver, Superintendent of Administration
*M. Sanple, Superintendent of Integrated Scheduling
*E. McCraw, License and Compliance Engineer D. Mendezoff, License and Compliance Engineer D. Marquis, Peeformance Engineer R. White, IAE Engineer R. Branch,_ Site QA Supervisor
*J.. Day, General Office Licensing
*J. Torre, General Office Licensing Other ' licensee employees contacted included construction craftsmen, technicians, operators, mechanics, security force members, and office personne * Attended exit intervie . Exit Interview The inspection scope ~and findings were summarized on November 1, 1985, with
 'those persons indicated in paragraph 1 above. 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 (CLOSED) 369/84-11-03 Failure to follow procedure and inadequate procedure loading to inadvertent Train A blackout. Adequate corrective steps have been taken which should preclude the type of personnel- and adminisrative
 - errors responsible for this violation. This item is close . Unresolved Items No unresolved items were identified during this report perio . Plant Operations The inspection staff reviewed plant operations during the report period, to verify conformance with applicable regulatory requirements. Control room logs, shift supervisors logs, shift turnover records and equipment removal and restoration records were routinely peruse Interviews were conducted
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with plant. operaticns, maintenance, chemistry, health physics, and perfor-mance personne Activities within the control room were monitored during shifts and at shift changes. Actions and/or activities observed were conducted as prescribed in ! applicable station administrative directives. The complement of licensed ' personnel on each shift met or exceeded the minimum required by technical , specification j Plant tours taken during the reporting period included but were not limited to the turbine. buildings, auxiliary building, Units 1 and 2 electrical equipment rooms, Units 1 and 2 cable spreading rooms, and the station yard zone.inside the protected area. During the plant tours, ongoing activities, housekeeping, security, equipment status and radiation control practices were observe Unit 1 Operations McGuire Unit 1 began the reporting period in Mode 1 operating at 100% powe .It .was maintained in Mode 1 at or about 100% power for the duration of the reporting perio Unit 2 Operations-McGuire Unit 2- began the reporting period operating at 100% power and was maintained at or about that power level until 8:45 a.m. on October 24, when the unit tripped due to lo lo steam generator level in the C generato Immediately preceding the trip, at 8:42 A.M., inverter breaker 2EVIB feeding bus 2EKVB was inadvertently tripped. This, . in turn, through- associated circuitry and instrumentation led to diminished feed flow to the C steam generator and the reactor trip. Following necessary surveillance testing associated with the trip, the unit was taken critical at 3:25 a.m. on October 25 and was placed on line at 1:43 p.m. that afternoon. At 2:40 on -October 26 the unit tripped from 90% power due to a malfunction of the main generator voltage regulator causing a turbine trip reactor tri Following troubleshooting and repairs to the main generator, the unit was taken critical at 2:10 that same day and was placed on line at 6:38 p.m. that evening. The unit completed the report period at 100% powe . Surveillance Testing-The surveillance tests categorized below were analyzed and/or witnessed by the inspector to ascertain procedural and performance adequacy and con-formance with applicable Technical Specifications. The selected tests witnessed were examined to ascertain that current written approved proce-dures were available and.in use, that test equipment in use was calibrated, tnat test prerequisites were met, system restoration completed and test results were adequat '

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e 3  ! TT/1/A/9100/99- Nuclear Service Water Train IA Pump Special Test PT/1/A/4252/01A Motor Driven CA Pump A Performance Test PT/1/A/4252/018 Motor Driven CA Pump B Performance Test PT/1/A/4350/15B DG 1B Periodic Test PT/1/A/4601/02 Protective Syst'em Channel II Functional Test PT/1/A/4601/04 Protective System Channel 4 Functional Test PT/0/A/4450/01 In Place Test of HEPA and Carbon Adsorber Filters PT/1/A/4208/01A Containment Spray 1A Performance Test PT/1/A/4208/01B Containment Spray 1B Performance Test PT/1/A/4401/01A Component Cooling Train 1A Performance Test PT/0/A/4350/0BE 125VDC Vital Charger Performance Test PT/1/A/4403/01A Nuclear Service Water Train IA Performance Test PT/1/A/4403/05 RN System Baseline Performance Test PT/1/A/4403/04 RN Supplied Heat Exchanger Performance Monitoring PT/2/A/4601/01 Protective Systems Channel 1 Functional Test PT/2/A/4208/01A Containment Spray 2A Performance Test PT/2/A/4204/018 Residual Heat Removal 2B Performance Test PT/2/A/4209/01B Centrifugal Charging Pump 2B Performance Test PT/2/A/4206/01B Safety Injection Pump 28 Performance Test PT/2/A/4206/01A Safety Injection Pump 2A Performance Test PT/2/A/4262/01A M/D Aux. Feedwater Pump 2A Performance Test Maintenance Observations The maintenance activities categorized below were analyzed and/or witnessed by the resident inspection staff to ascertain procedural and performance adequacy and conformance with applicable Technical Specifications. The.' selected activities witnessed were examined to ascertain that where applicable, current written approved procedures were available and in use, that prerequisites were me Equipment restoration completed and mainten-ance results were adequat Work Request Title 126021 Check Orifice on IRNFE-5040 (RN Pump Flow) Ventilation System Testing As detailed in report 369/85-30 a review of the regulatory requirements associated with the preoperational and surveillance testing of the McGuire Auxiliary Building Filtered Exhaust System (VA), revealed that the pre-operational testing performed on both units VA systems was apparently not performed in accordance with documented commitments. A deviation (369/85-30-02, 370/85-32-01) and Unresolved Item (369/85-30-03, 370/32-02) were opene The Unresolved Item was predicated upon the fact that the airflow distribution tests which were not performed, could affect the results of other surveillance tests, i.e., the representativeness of the

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charcoal samples sent in for laboratory analysis. A special inspection was performed during the week of October 14 to evaluate the Unresolved Ite The details of that inspection are entailed on inspection report (50-369/85-39, 50-370/85-40). On October 25, testing which had not been performed pursuant to FSAR commitment, specifically air flow distribution tests, were performed on the Auxiliary Building Ventilation Systems of both units. The results of that testing has been forwarded to Region II for evaluatio . Nuclear Service Water On October 4, 1985 during the performance of PT/1/A/4403/01A, Quarterly - Surveillance on 1A Nuclear Service Water (RN) Pump, it was determined that one data point on the pump head curve was less than 90% of the reference value. After additional evaluation and flow instrument verification the pump was declared inoperable at 10:30 p.m. that night. Over the weekend a new pump' impeller was installed. The old impeller which had been installed in January of 1985, showed no visible signs of wea On October 7 additional pump head curves were performed which showed sub-stantially the same results as those performed Friday before the new impeller had been installed. As .the 72 hour action statement was due to expire Monday, the licensee chose to cross connect Nuclear Service Water Pump 1A and Nuclear Service Water Pump 2A since the licensee judged that the combined flow was adequate, although 1A alone was no On October 9, during a runout test on IA RN, it was determined that one of the cross connect valves IRN33 s.upposedly opened on October 7 was, in fact, closed:due to an incorrect indicator which showed open when the valve was closed, and closed when the valve was open. Details of this incident and enforcement action taken are described in report 50-369/85-38 and 50-370/85-39. This lineup was corrected and the loop was maintained in a unit cross connected lineup. On October 10, following an NRC Regional review of this incident, Regional NRC management informed the licensee that operating the nuclear service water system with 1A RN and 2A RN pumps cross connected was not acceptable. The licensee subsequently shut the cross connects and declared the 1A RN system inoperabl The licensee then performed 'a design evaluation and subsequently declared the 1A RN pump operable on October 11, with restrictions on the loads it can supply with 1A and 2A operating on a common suction. This evaluation is currently under NRC review and will be discussed in detail in inspection report 50-369/85-38 and 50-370/85-39.

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