IR 05000302/1986033

Insp Rept 50-302/86-33 on 861006-10.No Violation or Deviation Noted.Major Areas Inspected:Electrical & Instrumentation & Control Maint Activities

ML20214V864
Person / Time
Site:	Crystal River
Issue date:	11/25/1986
From:	Conlon T, Petrone C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214V838	List: IR 05000302/1986033 ML20214V835
References
50-302-86-33, NUDOCS 8612090882
Download: ML20214V864 (11)

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United States Nuclear Regulatory Commission Region II 101 Marietta Street, Atlanta, Georgia 30323 Report N /86-33 Licensee: Florida Power Corporation 3201.34th Street, South St. Petersburg, Florida 33733 Docket N License No. DPR-72 Facility Name: Crystal River 3 .!

Inspection D'ates: October 6-10, 1986 Inspector: C'.

[fb Petrone, Lead Reactor Engineer

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Operational Programs Section, Operations Branch, .

Division of Reactor Safety, Region 1 Approved by M / / 4 0 Td T. E. Conlon, Section Chief date Plant System Section Division of Reactor Safety, Region 2 Scope: This routine, unannounced inspection was conducted by a Region I based inspector in the areas of Electrical and Instrumentation and Control

. maintenance activitie Results: No violations or deviations were identifie PDR ADOCK 05000302 G PDR ,_

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DETAILS 1. Persons Contacted License Employees

• P. F. McKee Director Plant Operations

• R. Murgatroyed Maintenance Superintendent

• J. Alberdi Manager, Nuclear Site Support

• S. B. Sullens Electrical Shop, Senior Supervisor W. J. Nielson Senior I&C Supervisor

• P. Ezzell Nuclear Compliance Specialist W. K. Sandhauer Assistant Nuclear Plant Operations Manager

• Rossfeld Nuclear Compliance Manager Other licensee employees were contacted including engineers, technicians, electricians, and mechanic NRC Resident Inspectors T. Stetka Senior Resident Inspector J. E. Tedrow Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on October 10, 1986, with those persons indicated in paragraph 1 abov The- inspectors described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . License Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Electrical and Instrumentation Maintenance The inspector reviewed the licensee's Electrical and Instrumentation Maintenance activities by witnessing work activities, reviewing documentation, and interviewing licensee personne . ._ -

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. 2 5.1 Staffing Discussions were held with the Instrumentation and Controls (I&C)

senior supervisor and the Electrical Shop senior supervisor who explained the organization and staffing of their respective shop The I&C shop staff consists of three supervisors, five chief techni-cians, twenty journeyman technicians, two planners, and five assir-tant technician The I&C staff is assigned to cover three shifts, seven days a week. The Electrical Maintenance staff includes three supervisors, one planner, five chief electricians eleven electri-cians, and two trainees. They normally work three shifts, five days a week, and cover weekends on an on-call basi The inspector reviewed the licensee's status of backlogged corrective maintenance work requests and noted that for the period from March to August,1986 the I&C shop reduced .their backlog from I49 to 82, and the Electrical Shop reduced their backlog from 73 to 4 According to the senior supervisors, there is usually a large backlog of work requests following each outage which is reduced to near zero during the operating cycle. At the time of this inspection the plant had been operating for four months since the startup from the last outage. The inspector also reviewed the data for the preventative maintenance scheduled versus that actually performed, and noted that most of the maintenance was being performed as scheduled. Based on this review the inspector concluded that the staffing level of these shops appeared adequate. Maintenance management was maintaining good control over the status of maintenance activitie .2 Procedures Review The licensees procedures, listed in Attachment 1, were reviewed to ensure written procedures had been established for routine, corrective or emergency maintenance activities and that they included the following:

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Administrative approvals for removing the item from service and returning it to service;

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Provisions to require that the latest approved drawings are used;

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Hold points for inspection and sign-off by QC;

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Provisions for returning the affected system to the original configuration following maintenance;

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Provisions for operational readiness testing of the item - and affected system following maintenance;

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Requirements for special authorization for activities involving welding, open flame, or other ignition sources;

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Provisions to assure that materials, parts and components are correct and suitable, including environmental qualification;

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Provis1on for assuring that limiting conditions for operations requirements of the technical specifications are identified and satisfied;

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Provisions for the control of housekeeping;

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Provisions for obtaining approval from operations;

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Provisions to perform equipment failure analysis and trending;

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Provisions for removal of appropriate jumpers, restoration of lifted leads, reinstallation of tubing, and removal of test

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devices;

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Responsibility for reporting to licensee management details concerning design or construction related deficiencies identified during maintenance;

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Provisions for providing for control of special processes, special tools, and test equipment;

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Appropriate acceptance criteria;

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Provisions to assure personnel qualifications;

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Provisions to control the use of measurement and test equipment; and,

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Provisions to control work in radiation area No violations or deviations were identifie .3 Witnessing Maintenance Activities The inspector witnessed work activities performed by electricians and I&C technicians. These activities included corrective maintenance, preventive maintenance, and performance of routine surveillance activitie During these observations the inspector determined the following:

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Proper operational personnel had been notified and clearances issued;

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Appropriate maintenance work orders had been issued and approved;

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The latest approved procedures, drawings and instructions were being used;

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Properly specified parts and materials were used;

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QC inspection signoffs were made where specified in the procedure;

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Qualified test equipment and tools were in use;

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Adequate identification of jumpers and lifted leads was maintained;

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Proper restoration of barriers and covers was accomplished;

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Required system lineups had been accomplished and verified prior to functional testing;

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Adequate post maintenance functional testing was performed;

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Fire Protection precautions were observed;

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Limiting conditions for operation were met; and,

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Housekeeping was satisfactor The inspector witnessed portions of the following maintenance and surveillance activities:

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PrevenEative Maintenance Procedure PM-126, Electrical Checks of CRD Power Trai This maintenance was performed by a chief electrician and a journeyman electricia It is performed monthly to ensure each Control Rod Drive (CRD) power supply is operating properly and to provide a basis for SP-110 Reactor Protective System (RPS) Functional Testing and SP-333, Control Rod Exercis During the performance of this test the Electricians identified that one of the six symmetrical voltage pulses, described in step 7.2.7, was missing indicating that the output from the "B" train, Group 5, Silicon Controlled Rectifiers (SCR's) was zer The electricians stopped work and initiated Work Request Form 83490 to permit troubleshooting in accordance with Mainte-nance Procedure MP 531, Troubleshooting Plant Equipment. Using voltage and resistance measurements they located an open 150 Amp, 250 VDC fuse. They replaced this fuse which corrected the problem and submitted the work request results to Nuclear Quality Engineering for evaluation.

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Surveillance Procedure SP-140, In-Core Neutron Detector System Calibratio This is performed on an 18 month interval and is used to verify the operability of the in-core neutron detector system by performing a channel calibration and a detector resistance check. The inspector witnessed the performance of paragraph 6.3, Computer Input Calibration, and paragraph 6.4.,

Detector Resistance Measurements, for three in-core detector Troubleshooting and repair of a 480 VAC feeder breaker for the Control Complex Chilled Water Syste This system provided chilled water for the Control Room Air Conditioning system. The breaker, an ITT Type M-600, 480 VAC, tripped during normal operation causing loss of the "A" train. Work Request 83701 was issued to perform PM-107, which provided instructions for inspecting, calibrating, cleaning, and testing of 480 VAC breakers. During the performance of this PM, the electricians tested-the breaker and discovered that one phase would trip at a current lower than the required trip set point. They performed troubleshooting in accordance with MP-531, Troubleshooting Plant Equipment, and the Vendor Manual, and determined that the 0D-4, Overcurrent Trip Device was defective. They replaced the OD-4 part and, following adjustment, the breaker passed the required PM-107 tests and was returned to servic Sp-110, Reactor Protection System Functional Testing, Paragraph 7.15, Intermediate Range Neutron Flux and Rate Functional Test for channels "C" and "D". This test is performed monthly during modes 1 and 2 to verify operability of the Reactor Protection Syste Microwave Intrusion Alarm Syste The inspector witnessed the alignment and checkout of one of the microwave transmitters in accordance with Work Request For 81290 and functional test procedure for MAR 80-12-08-0 Troubleshooting of the Borated Water Storage Tank heater control DH-9-TE. The heater unit turned on but stayed on as the temperature increased past the cut off temperatur The I&C Technician narrowed the problem down to a faulty transmitting alarm unit using a fluke digital multimeter and a thermocouple calibration standard to simulate the signal from the thermo-couple on the borated storage water tank. He replaced the faulty unit with one from the supply system which they calibrated before us No violations or deviations were identifie .

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5.4 Measurement and Test Equipment During the witnessing of these work activities the inspector selected a sample of ten pieces of measurement and test equipment and verified they were within their specified calibration due dat These instruments are listed in attachment The inspector also reviewed the calibration records for these instruments maintained by the licensees calibration lab. These records were readily accessible and properly maintaine The record of instrument usage was being accurately maintaine No violations or deviations were identifie .5 Records Review The inspector reviewed a sample of twenty-five completed Electrical and I&C work requests, listed in attachment 1, to ensure Nuclear Quality Engineering had reviewed all safety related work requests, po.st maintenance testing had been -specified where appropriate, snift Supervisor. approval had been obtained where necessary, work was signed off as completed, and final reviewers had signed off as required. All work requests appeared to be satisfactor No violations or deviations were identifie .6 Temporary Procedure Changes The inspector reviewed the Immediate Temporary Changes Accountability Log for the period August 30, 1986 to the present and noted that all temporary changes had been reviewed in less than the maximum 14 days required by AI-401. A sample of ten temporary changes were reviewed to ensure the procedure review record was complete and that a 10 CFR 50.59 safety evaluation checklist had been complete No violations or deviations were identifie .7 Quality Control The NRC inspector examined the role of the licensee's quality control department during the performance of maintenance activitie The Nuclear Quality Control supervisor explained the Nuclear Quality Engineering department reviews safety related procedures and work requests to establish hold points and other inspection requirement The mechanic performing the work notifies QC whenever work beings, and again whenever a hold point is reache The NRC inspector exanined the QC file of active Quality Control Inspection Reports. These reports document the inspection activities performed and any nonconformance identified. These records are in

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addition to the signoffs contained in the maintenance procedures and Work Requests. : The NRC inspector reviewed a sample of . forty recently performed -inspection reports and noted there appeared to be active, ongoing QC inspection of maintenance activitie No violations or deviations were identifie ATTACHMENT:

Document Reviewed

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2 Attachment Work Requests Reviewed-Work Request Number Description System WR-62237 Repair Asco Solenoid Core Flood WR-62238 Repair Asco Solenoid Core Flood WR-65970 CFV Valve Failed Response Time Core Flood WR-70227 Wiring Problems CF-1, 3 LT Core Flood WR-71926 CF-1-PI4 Pressure Indicator Inop Core Flood WR-64002 BWST Storage Tank Alarm Decay Heat Removal WR-64258 DHV-3 Valve Inop Decay Heat Removal WR-65352 DH-18-MS Install Bypass Jumper Decay Heat Removal WR-68402 Functional Test Foxboro Control System Decay Heat Removal WR-68407 Test Decay Heat Valve DHV-111 Decay Heat Removal WR-68865 Flow Indicator DH-38-FI2 Drop Decay Heat Removal WR-68883 DHV-111 Failed to Control Flow Decay Heat Removal WR-69693 BWST Level Indication Inop Decay Heat Removal WR-40359 Perform MAR 80-10-66-13 Emergency Feedwater WR-60118 Calibrate Instrumentation Emergency Feedwater WR-60133 Calibrate Transmitters Emergency Feedwater WR-62936 Calibrate Bailey TI20 Emergency Feedwater WR-64331 Panel Functional Test Emergency Feedwater WR-68170 PSA/FFIC Panel Calibration Emergency Feedwater WR-71473 Vector Logic FCN-73A Emergency Feedwater WR-81278 Replace Anodes in DCHE-1A Decay Heat Closed Cycle Cooling WR-83486 CRDM UV TRIP Device Trip Coil Control Rod Drive WR-83482 Checkout of CRD AC Breakers Control Rod Drive WR-83490 "B" Power Supply Drop Control Rod Drive WR-83416 DCHE-1A Ground Strap Broken Decay Heat Closed Cycle Cooling

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Attachment Documents Reviewed

~ AI-600, Conduct of Maintenance, Rev 32, 07/09/86

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PM-100, Preventative Maintenance Program, Rev 11, 09/05/86 MP-531, Troubleshooting Plant Equipment, Rev 0, 02/08/85 PM-107, 480 V Breakers, Rev 11, 05/15/86 PM-126, Electrical Checks of CRD Power Train, Rev 14, 02/07/86 PM-200, Master Instrument Calibration Program, Rev 3, 04/17/86 SP-110, Reactor Protection System Functional Testing, Rev 6, 7, 07/18/86 MAR 80-12-08-02, Perimeter Intrusion Detection System Functional Test, TP SP-169, Plant Safety Related Equipment Calibration, Rev 16, 05/05/86 Measurement and Test Equipment Instruments Instrument N Date Due Calibration Tektronics Ocilloscope TI-1203 11/13/86 Fluke Digital Multimeter TI-1048 09/25/87 Volt Source TI-534 07/02/87 Kiethley Electrometer TI-394 12/23/86 Kiethley Picoammeter Source TI-167 03/04/87 Kiethley Digital Voltmeter TI-1364 11/20/86 Powerstat Variable Transformer TI-725 09/18/87 Micro Ohmmeter TI-689 01/18/87 American Research DC HIP 0T TI-80 02/12/87 Multi-A TI-794 01/04/87

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Proposed SALP Input Crystal River 3 Area: Electrical and I&C Maintenance Rating: Category I Inspection 86-33, 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> onsite Inspection of Electrical and I&C maintenance activities by a Region I based inspector revealed that all activities were being performed in a safe and professional manne The inspection consisted primarily of witnessing main-tenance activities. The licensee has established good control over tagout of

. electrical and I&C equipment. Maintenance activities are well coordinated with plant operations personne The electricians and I&C technicians were very knowledgeable of the equipment and trouble shooting _ techniques. They under-stood and followed administrative requirements and procedures. The maintenance manager maintained a timely and accurate status of corrective and periodic maintenance, and was successfully reducing the number of backlogged maintenance work request Measuring and Test Equipment was being maintained in calibratio Staffing of the electrical and I&C shops appears adequate to handle the workload. The Nuclear Quality Control staff is actively involved in coverage of maintenance activitie However, the size of the staff (one supervisor, six licensee inspectors, and three contractor inspectors) appears to be small.