IR 05000369/1986017

Insp Repts 50-369/86-17 & 50-370/86-17 on 860521-0620.No Violations or Deviations Noted.Major Areas Inspected: Operations,Surveillance Testing & Maint Activities

ML20210F850
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/28/1986
From:	William Orders, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20210F783	List: IR 05000369/1986017 ML20210F777
References
50-369-86-17, 50-370-86-17, NUDOCS 8609250289
Download: ML20210F850 (5)

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%..... JUL 2 81986 Report Nos.: 50-369/86-17 and 50-370/86-17 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 Facility Name: McGuire 1 and 2 Inspection Conducted: M 21 through June 20, 1986 Inspector: . , wst ha f jf Yd nt lodgiiftor

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W. 'ITrde rs , 'Seni oTRe s Aate Si@ned Appmved by: J /1 f4 T. 'A. Peebles, Section Chief Date Sisned Division of Reactor Projects .

ta SUMMARY *

Scope: This routine, unannounced inspection was conducted on site in the areas of operations, surveillance testing and maintenance activitie Results: Of the areas inspected, no violations or deviations were identifie l

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REPORT DETAILS Persons Contacted 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

• N. Atherton, License and Compliance 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 July 11, 1986, 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 . Previously. Identified Inspection Findings On May 7, 1986, during a design engineering review conducted at McGuire Nuclear Station pursuant to NRC IE Bulletin No. 85-03, Motor-0perated Valve

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Common Mode Failures During Plant Transients Due to Improper Switch Settings, valvas 1NI 9, 1NI 10, and 2NV 7 were determined to be inoperabl The NI valves are Centrifugal Charging Pump discharge valves to the Reactor Coolant System and the NV valve is a Letdown Isolation valve outside the reactor building. At the conclusion of the report period ending May 20, 1986, - this was carried as an Unresolved Item pending completion of an ongoing inspection (369/86-12-01). The area remains under investigation with a tentative completion date of July 11, 198 . Unresolved Items No new unresolved items were identified.

4 Plant Operations The inspector reviewed plant operations during the report period, to verify conformance with applicable regulatory requirements. Control room logs, shift supervisor's logs, shift turnover records and equipment removal and

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restoration records were routinely perused. Interviews were conducted with plant operations, maintenance, chemistry, health physics, and performance personnel. 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 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 are During the plant tours, ongoing activities, housekeeping, security, equipment status and radiation control practices were observe Unit 1 Operations Unit 1 began the report period in Mode 5, on the leading edge of a refueling outage. The unit completed the report period with the core off-loade Unit 2 Operations Unit 2 began the report period in Mode 6, ~ nearing the completion of a refueling outage. The unit was made critica1 at 3:03 a.m. on June 18 and ended the report period in. low power physics testin No violations or deviations were identifie . Surveillance Testing The surveillance tests categorized below were analyzed and/or witnessed by the inspector to verify procedural and performance adequacy and conformance with applicable Technical Specifications. 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 adequat Procedure Number Title PT 1 A 4350 15A D/G 1A Periodic Test PT 1 A 4350 ISB D/G 1B Periodic Test PT 1 A 4204 02 ND Valve Stroke Timing Test PT 1 A 4206 03 NI Valve Stroke Timing Test PT 1 A 4200 22 FW Auto Switchover PT 1 A 4401 02 KC Valve Stroke Timing PT 1 A 4209 018 NV Pump 2B Perf. Test PT 2 A 4601 03 Protective System Channel III PT 2 A 4200 29 2NI9, 10 Pressure Verification PT 2 A 4403 02 RN Valve Stroke Timing

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3 Maintenance Observations Routine maintenance activities were reviewed or witnessed by the resident inspector 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 met, equipment restoration completed and maintenance results were adequat No violations or deviations were identifie . Refueling Activities Selected refueling activities on Units 1 and 2 were reviewed and/or witnessed to verify that:

Periodic testing and verification of the operability of refueling-related equipment and systems were performed as required by TS and licensee administrative procedure Fuel handling ' operations were performed in accordance with TS and approved procedure Plant conditions were maintained as required by T .The licensee's staffing was in accordance with TS and approved procedure The inspector reviewed and/or witnessed selected of the following activities to ascertain that they were being controlled and conducted as required by TS and approved procedures:

Core monitoring during refueling operation Fuel accountability method Vessel and spent fuel storage pool water level Boron concentrations and appropriate dilution path valve checks are performe Checks of containment penetration Checks of decay heat removal system flowrat Operability of the containment purge and exhaust isolation system .

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On June 26, subsequent to the completion of this report period during the performance of a core reload visual verification, the licensee detected some loose fuel pellets in the core area. An investigation revealed that baffle jet impingement damage had occurred on at least one-fuel assembly. Details of the fuel damage. and corrective actions are entailed in report (50-369/86-19,50-370/86-19).

No violations or deviations were identifie . Inoperable Containment Purge Isolation On June 4,1986, at 12:30 p.m., McGuire Unit I was in Mode 6, refueling when during periodic testing of radiation monitor ~ 1 EMF-39L, the licensee discovered the trip 2 logic (high-high activity) would not isolate the Containment Purge (VP) system as required. The inability of IEMF-39L to isolate the VP system violated Technical Specification (TS) 3.3.3.9, which requires 1 EMF-39L to be operable at all time During the subsequent investigation, the licensee discovered that 1 EMF-39L sends a signal to the Solid State Protection System (SSPS) to energize a relay which, in turn, isolates the VP system. The investigation revealed that on the morning of June 3, both trains of SSPS were taken out of service. With both trains of SSPS out of service, there was no automatic isolation capability of the VP system. This condition existed from the time both trains of SSPS were taken out of service until the VP system was secured at 9:55 p.m. that evening. At 2:20 a.m. the following morning, both trains-of SSPS were returned to service and the VP system was returned to

service shortly thereafte The VP system provides the capability for purging the containment atmosphere to the environment through the unit vent. 1 EMF-38 is a radiation monitor used to monitor gaseous activity and 1 EMF-40 monitors iodine activity in the VP system. On high activity, IEMF-38, IEMF-39L, or 1 EMF-40 are designed to terminate on release from the VP syste TS 3.3.3.9 requires, in part, that EMF-39, be operable at all time Further, with EMF-39 inoperable, purging or venting of the containment be suspended immediately. On the date in question, EMF-39 was inoperable yet

, purging continued for approximately 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> In consideration of the safety significance of a postulated event which in Mode 6 and the length of time the situation existed, this event would quality as a Severity Level IV violatio Therefore in accordance with the enforcement policy of 10 CFR Part 2 APP.C and since this event was identified and corrected by the licensee, is a Severity Level IV violation, was reported, and was not a violation that could reasonably be expected to have been prevented by the licensee's corrective actions for a previous violation, a Notice of Violation will not be issued (50-369/ LIV 86-17-01).

No violations or deviations were identifie _ - _ .

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