IR 05000369/1988007

Insp Repts 50-369/88-07 & 50-370/88-07 on 880227-0318.No Violations or Deviations Noted.Major Areas Inspected: Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings

ML20150E419
Person / Time
Site:	Mcguire, McGuire
Issue date:	03/24/1988
From:	William Orders, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20150E416	List: IR 05000369/1988007 ML20150E414
References
50-369-88-07, 50-369-88-7, 50-370-88-07, 50-370-88-7, NUDOCS 8803310285
Download: ML20150E419 (6)

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Report Nos.: 50-369/88-07 and 50-370/88-07 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: ebruary 27 - March 18, 1988 n/,

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W. Drd6rs,' senior Re,sident Inspector r]YW Oate/ Signed Accompanying Personnel: D. Nelson R. Croteau

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'7't u' w 3/177PT T. A. Peebles, Section Chief Oate Signed Division of Reactor Projects SUMMARY Scope: This routine unannounced inspection involved the areas of operations safety verification, surveillance testing, maintenance activities, and follow-up on previous inspection finding Results: In the areas inspected, no violations or deviations were identified.

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REPORT DETAILS Persons Contacted Licensee Employees

• T. McConneil, Plant Manager B. Travi',, Superintendent of Operations

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

• N. McCraw, Compliance Engineer

• Sample, Superintendent of Integrated Scheduling L. Firebaugh, OPS /NPE/MNS S. LeRoy, Licensing, General Office

• D. Baxter, OPS /MNS/NPD S. Sopp, Planning Engineer

• R. Banner, Compliance J. Snyder, Performance Engineer N. Atherton, Compliance W. Reeside, Operations Engineer R. White, IAE Engineer

• J. Oldham, Design Engineer

• J. Reeside, Industrial Safety, Health and Fire Protection Coordinator

• R. Sharpe, Nuclear Engineer, General Office

• J. Day, Licensing Associate Engineer, General Office

• McIntyre, Fire Protection Specialists

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Other licensee employees contacted included construction craftsmen, technicians, operators, mechanics, security force members, and office personne * Attended exit interview Exit Interviev (30703)

The inspection findings identified below were summarized on March 18, i 1988, with those persons irdicated in paragraph 1 above. No violations or

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deviations were identifie The licensee representatives present of fered no dissenting comments, nor did they identify as proprietary any of the information reviewed by the inspectors during the course of their inspectio . Unresolved Items An unresolved item (UNR) is a matter about which more information is required to determine whether it is acceptable or may involve a violation or deviation. There were no unresolved items identified in this repor :

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, Flant Operations (71707, 71710)-

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 perused. Interviews were conducted with plant operations, maintenance, chemistry, health physics, and performance personne .

Activities within the control room were monitored during shif ts 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, the auxiliary building, Units 1 and 2 electrical equipment rooms, Units 1 and 2 cable spreading rooms, and tM station yard zone inside the protected are During the plant tours, ongoing activities, housekeeping, security, equip-ment status and radiation control practices were observe Inspections included a partial walkdown of the Unit 2 auxiliary feedwater (CA) system which revealed that the CA flow diagram had minor error These errors were reported to the licensee for correctio Unit 1 Operations Unit 1 operated at approximately 100 percent power during the report perio Unit 2 Operations Unit 2 operated at approximately 100 percent power during the report period.

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No violations or deviations were identified.

' Surveillance Testing (61726)

Selected surveillance tests were analyzed and/or witnessed by the inspector to ascertain procedural and performance adequacy and conformance with applicable Technical Specification Selected tests were witnessed to ascertain that current written approved procedures were available and in use, that test equipment in use was f calibrated, that test prerequisites were met, that system restoration was completed and test results were adequate.

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Detailed below are selected tests which were either reviewed or witnessed:

PROCEDURE EQUIPMENT / TEST PT/1/A/4450/012A OAPFT-1 / Air Flow Measurement PT/0/A/4601/07A Response Time Testing of Reactor Trip Breakers RTA and/or BYB No violations or deviations were identifie . Maintenance Observations (62703)

Routine maintenance activities were reviewed and/or witnessed by the resident inspection staff to ascertain procedural and performance adequacy and conformance with applicable Technical Specification The selected activities witnessed were examined to ascertain that, where applicable, current written approved procedures were available and in use, that prerequisites were met, that equipment restoration was completed and maintenance results were adequat No violations or deviations were identifie . Follow-up on Previous Inspection Findings (92702)

The following previously identified items were reviewed to ascertain that the licensee's responses, where applicable, and licensee actions were in compliance with regulatory requirements and corrective actions have been complete Selective verification included record review, observations, and discussions with licensee personne (CLOSED) Licensee Identified Violation 369, 370/86-35-0 Inadequate Control of Operations Management Procedure (OMP) Changes Contrary to 10 CFR 50, Appendix B, Criterion VI. Licensee personnel have evaluated the method of processing changes to OMPs, Station Directives, etc. and issued Revision 2 to OMP 1-1, Administration of Operations Management Procedures, on February 29, 1988. One of the items included in this revision was the assignment of the Shift Support Technician as the responsible person for updating the control room OMP Manual and other affected logs and files. This item is close (CLOSED) Violation 369, 370/86-28-10, Surveillances Not Perfcrmed. This violation involved missed surveillance on Source Range Nuclear Instruments (SRNI) and Diesel Generators. Corrective actions included reviewing the events with appropriate personnel, revising the associated surveillance procedures to incorporate steps to prevent recurrence, and establishing a check off sheet to be used in Mode 6 to keep track of the seven day SRNI surveillance. A review of licensee event reports issued subsequent to these events revealed no recurrence of missing these surveillance . -

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(CLOSED) Inspector. Followup Item 369, 370/86-28-08, Hydrogen Ignition Problem This item is being tracked as followup to LER 369/86-17. This item is close (CLOSED) Unresolved Item 369/87-19-01, Review PIR 1-M87-0116 Regarding Operation Above the Rated Thermal Power. This item was reported via Licensee Event Report 369/87-35 and identified as a Licensee Identified Violation in Inspection Report 50-369, 370/87-42. This item is close , Licensee Event Report (LER) Followup (90712, 92700)

The following LERs were reviewed to determine whether reporting require-ments have been met, the cause appears accurate, the corrective actions appear appropriate, generic applicability has been considered, and whether

. the event is related to previous events. Selected LERs were chosen for more detailed followup in verifying the nature, impact, and cause of the event as well as corrective actions take (CLOSED) Licensee Event Report 369/86-12, Both Trains of Chilled Water and Control Room Ventilation System Inoperable Due to Design and Management Deficiency. The system was restored to operation within the allowable TS time limit and corrective actions are complete. This item was identified as a Licensee Identified Violation in Inspection Report 50-369, 370/86-3 This item is close (CLOSED) Licensee Event Report 370/86-9, Engineering Safeguard Features Train A Feedwater Isolation Signal Generated Oue to Defective Procedur The procedures for response time testing of reactor trip and bypass breakers have been revised to prevent recurrence of this event. This item is close (CLOSED) Licensee Event Report 369/86-15, Missed Surveillance on Source Range Neutron Flux Monitors; Test Not Performed to Satisfy the Seven Day Requirement of T.S. 4.9.2.C. This item was identified as a violation in Inspection Report 50-369, 370/86-28. Corrective actions have been taken and this item is close (CLOSED) Licensee Event Report 370/86-14, Diesel Generator Operability Not Verified as Required Due to Personnel Error. This item was identified as a violation in Inspection Report 50-369, 370/86-2 Correct;ve actions have been taken and this item is close (CLOSED) Licensee Event Report 370/86-13, Unit 2 Entered Technical

Specification 3.0.3 Due to Unidentified Wiring in Containment Air Return

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and Hydrogen Skimmer Valve. This event resulted from an inspection documented in Inspection Report 50-369, 370/86-20 pursuant to 10 CFR 50.49 Environmental Qualification of electrical equipment. This generic issue was subsequently addressed i n an NRC Region II letter to Duke dated October 5, 1987 and is considered close .

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(CLOSED) Licensee Event Report 369/86-19, Missed Quarterly Surveillance on Nuclear Service Water Valve Due to Management Deficiency. Corrective actions included revising Station Directive 3.2.1, Identifying and Scheduling Plant Surveillance Testing, to better control scheduling of surveillance testing. This item is close . Corbicula sp. (Asiatic Clams) Inspection

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On March 9, 1988, Catawba Unit 2 experienced a reactor trip followed by an auxiliary feedwater (CA) actuation. A low suction pressure signal caused CA to realign suction to nuclear service water (RN) supplying river water to the steam generator The CA flow control valves contain cages to prevent cavitation and these cages became partially blocked with Corbicula sp. (Asiatic clams) believed to have accumulated in the stagnant section

. of piping between the RN line and the CA line. This caused degraded flow to the steam generator McGuire has a similar piping arrangement and similar CA flow control valve In response to the Catawba event, McGuire disassembled check valves on both RN to CA lines in each unit to visually inspect the areas for any indication of Corbicula sp. No evidence of Corbicula sp. was found. The licensee is evaluating what actions are needed.to ensure that these lines do not encounter Corbicula sp. growth in the futur No violations or deviations were identified.

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