IR 05000254/1981011

IE Insp Repts 50-254/81-11 & 50-265/81-11 on 810516-0630.No Noncompliance Noted.Major Areas Inspected:Operational Safety Verification,Monthly Maint Observation,Ler Followup & IE Bulletin Followup

ML20009D560
Person / Time
Site:	Quad Cities
Issue date:	07/07/1981
From:	Chrissotimos N, Dupont S, Reimann F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20009D558	List: IR 05000254/1981011 ML20009D557
References
50-254-81-11, 50-265-81-11, NUDOCS 8107240173
Download: ML20009D560 (9)

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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No.

50-254/81-11; 50-265/81-11 Docket No.

50-254; 50-265 License No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Quad-Cities Nuclear Power Station, Units 1 & 2 Inspection at: Quad-Cities Site, Cordova, IL Inspection Conducted: May 16, 1981, through June 30, 1981

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Inspectors:

N. J[Chrib inos b 3d'I!

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Approved by:

F. W. Reimann, Acting Chief O'9'N

Reactor Projects Section 1C Inspection Summary

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Inspection on May 16 through June 30, 1981 (Reports No. 50-254/81-11; 50-265/81-11)

Areas Inspected: Operational Safety Verification, Monthly Maintenance Observation, Monthly Surveillance Observation, Licensee Event Reports Followup, IE Bulletin Followup, IE Circular Followup, Surveillance, Meeting with Local Officials, Transportation of Irradiated Fuel and Review of Licensee's Monthly Performance Report.

The inspeck. ion involved a total of 377 inspector-hours by two NRC inspectors including 39 inspector-hours onsite during off-shifts.

Results: No items of noncompliance were identified.

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8107240173 810708 PDR ADOCK 05000254 G

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DETAILS 1.

Persons Contacted

• N.

Kalivianakis, Superintendent T. Tamlyn, Assistant Superintendent Operations D. Bax, Assistant Superintendent Maintenance L. Gerner, Assistant Superintendent for Administration

• J. Heilman, Quality Assurance, Operations

• R. Flessner, Technical Staff Supervisor The inspector also interviewed several other licensee employees, including shift engfeeers and foremen, reactor operators, technict1 staff personnel and quality control personnel.

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• Denotes those present at the exit interview on June 30, 1981.

2.

Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of June, 1981.

The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of Units 1 and 2 reactor buildings and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.

The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls.

During the month of June, 1981, the inspector walked down the accessible portions of Units 1 and 2 ECCS Systems to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.

These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and adminis-trative procedures.

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No items of noncompliance were identified.

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s 3.

Monthly Maintenance Observation

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Stat.on maintenance activities of safety related systems and

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i components listed below were observed / reviewed to ascertain that j

they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specifications.

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The following items were considered during this review:

the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved proceduces and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel;

parts and materials used were properly certified; radiological

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controls were implemented; and, fire prevention controls were implemented.

Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performance, i.

The following maintenance activities were observed / reviewed:

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Unit 1 Q11606 1A Recirculation Pump Discharge Valve Q12648 Backup Scram Solenoid Q12135 1001-16A RHR Valve Q11421 1001-19A RHR Valve Q12651 2001-16 D/W Equipment Drain Sump Valve

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Q11166 Reactor Building Vent Damper Unit 2.

Q12209 2A RHR Pump Seal Q12210 2B RHR Pump Seal Q12549 RHR 1001-7B Valve Q12546 Diesel Generator Voltage Regulator

' Unit 1/2 j

Q05883 Rebuild Spare CRD Q11633 MSIV Main Disc-Q12612

'l/2 Diesel Generator

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Following completion of maintenance on the Unit 2 Diesc1

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Generator; the inspector verified that these systems had been returned to service properly.

No items of noncompliance were identified.

4.

Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the Unit 1 Safety Relief Valve

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Operability and Unit 2 Core Spray and RRR Room Doors and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that liniting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identifed during the testing were properly reviewed and resolved by appropriate me:agement personnel.

The inspector also witnessed portions of the following test activities: Unit 2 RHR Containment Cooling Valve Operability.

-No items of noncompliance were identified.

5.

Licensee Event Reports Followup

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r Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accom-plished in accordance with technical specifications.

Unit 1 R0 81-09, dated April 7, 1981, during operability test, lA RHR Service Water Pump did not meet technical specifications flow requirements.

R0 81-10, dated April 14, 1981, during normal operation, RCIC Steam Line Drain Valve closed in excess of limits.

Unit 2 R0 81-09, dated May 5, 1981, during RHR Containment Cooling

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Valve Operability Test, a Valve Breaker tripped from high starting current.

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R0 81-10, dated May 15, 1981, during normal operation, Control

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Room received Unit 2 Diesel Generator alarm.

In regards to R0 81-10, the cause of this occurrence has been designated as equipment failure. The 4 KV breaker in tus 24-1 which connects the Unit Two Diesel Generator with the emergency bus spuriously closed in, causing the bus to energize the the generator stator and motor the generator.

The cause of the breaker closing in was postulated to be a ground fault in the 125 volt DC control power circuit which operates that breaker.

Four wires inside the breaker cubicle were found to have the insulation worn off. One of these wires probably shorted to ground or another wire causing the breaker closing mechanism to energize, thus closing the breaker.

Damage to the generator was limited to the three power current transformers which go to a neutral ground detector. These transformers are directly wired into the 4 KV circuit coming off the generator.

The transformers had overheated renulting in internal damage to the transformers, also, a lead to the primary winding of one of the transformers was burned off.

The emergency Diesel Generator is manufactured by the Electro-Motive Division of General Motors Corporation, model A-20-Cl; rated at 4160 volts, 452 amps, 3250 KVA.

The 4 KV circuit breaker is manufactured by General Electric Company, model MC-4.76.

There have been no previous failures of this type at Quad-Cities Station.

The licensee's immediate corrective action taken was to verify operability of the 1/2 Diesel Generator and its associated emergency bus.

Extensive inspections and tests were performed on the generator and equipment connected to it.

The rotor and stator were meggered and revealed no indications of faults or degraded insulation.

A visual inspection of generator internals showed signs of localized heating on the rotor pole faces and slight flaking of the insulation. The loose insulation was removed and new insulation material was applied. New power current transformers were installed in the neutral ground detector circuit.

The four wires with worn insulation in the

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4 KV breaker cubicle were replaced. No other problems were found in the breaker cubicle. At 0957 on May 17, 1981, the Diesel Generator was successfully started and loaded to 2500 kilowatts on bus 24-1.

Vibration readings were taken with the Diesel Generator loaded and unloaded to verify no damage was incurred in the shaft or coupling. Approximately 15 minutes after loading the generator, all generator electrical indication was lost in the Control Room. The output breaker was immedi-

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ately opened and the Diesel was shutdown.

Operability of the 1/2 Diesel Generator and the associated low pressure core and containment cooling systems were readily verified.

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off-site lines capable of supplying 345 KV power were available.

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The problem was found to be a failed diode in the voltage regu-lator circuit. The diode had probably ove:neated when the generator was motored, but had not completely failed.

The failed diode was replaced, and on May 19, 1981, at 9052, the Diesel Generator was successfully started and loaded to the bus to verify operability.

To prevent recurrence, modification M-4-2-77-21 will be installed during the next Unit Two Refueling Outage in the fall of 1981.

This modification will trip the Diesel Generator to bus 24-1 breaker from loss of excitation, generator neutral voltage, generator reverse power, and overcurrent relays.

This modifi-cation will also be installed on the 1/2 Diesel Generator during the Unit Two fall Refueling Outage.

These protective tripping devices were installed on the Unit One Diesel Generator in the fall of 1980.

No items of noncompliance were identified.

6.

IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation-in the bulletin and the licensee's response, that licensee. management forwarded copies of the written response to the appropriate onsite management representatives, that-information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as omscribed in the written response.

IE Bulletin 81-02, dated April 9, 1981, Failure of gate type valves to close against differential pressure.

No items of noncompliance were identified.

7.

IE Circular Followup For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applicable to the facility, appropriate corrective actions were taken or were scheduled to be taken.

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IE Circular 81-04, dated April 30, 1981, The role of Shift Technical Advisors and importance of reporting operational events.

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IE Circular 81-06, dated April 14, 1981, Potential deficiency affecting certain Foxboro 10 to 50 mil 11 ampere transmitters.

- IE Circular '1-07, dated ?tay 14, 1981, Control of radioactively contaminated material.

No items of noncompliance were identified.

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Surveillance The inspector observed technical specifications required sur-veillance testing (other than calibrations and checks) on the Unit 1 Safety Relief Valve operability and Unit 2 Core Spray and RHR Room Doors'and verified that testing was performed in l

accordance with technically adequate procedures, that results were in conformance with technical specifications and procedure requirements and were reviewed'by personnel other than the individual directing the test, and that any deficiencies identified during testing were properly reviewed and resolved by appropriate management personnel.

The following surveillance performed between December, 1980, and June, 1981, were reviewed:

Unit 1 QFD-100-3 QoS-1600-14 QTS-300 QoS-20-1 QoS-1600-15 QIS-2

- QoS-300-1 QoS-1600-18 QIS-5 QoS-1600-2 QoS-1600-19 QIS-8

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QoS-1600-4 QOS,1600-20 QIS-11 QoS-1600-5 QoS-1600-23 QIS-14 Qos-1600-7 QTS-1300 QIS-17 QOS-1600-9 QTS-1311 QIS-20 QoS-1600-10 QTS-100 QIS-23 QoS-1600-11 QTS-130 QIS-26

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QOS-1600-12 QTS-160 QIS-29 QoS-1600-13 QTS-260 QIS-32 QIS-35 QIS-46 QIS-55 QIS-38 QIS-49 QIS-58 QIS-41 QIS-52 QIS-68 l

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Unit 2 QTS-1300 QOS-1600-2 QOS-1600-14 QTS-1512 QOS-1600-4 QOS-1600-15

. QTS-100 QOS-1600-5 QOS-1600-18 QTS-130 QOS-1600-7 QoS-1600-19 QTS-160 QOS-1600-9 QOS-1600-20 QTS-260 QoS-1600-10 QOS-1600-23 QTS-300 QOS-1600-11 QIS-32 QTS-1104 QOS-1600-12 QIS-35 QOS-5670-1 QOS-1600-13 QIS-38 QIS-2 QIS-17 QIS-41 QIS-5 QIS-20 QIS-46

QIS-8 QIS-23 QIS-49 QIS-11-QIS-26 QIS-52 QIS-14 QIS-29 QIS-55 No items of noncompliance were identified.

9.

Meeting with Local Officials On June 17, 1981, the resident inspector attended meetings with local officials of the cities of Caman'che, Iowa, and Cordova, Illinois, State Representatives from the Iowa i

Office of Disaster Services, Illinois Emergency Service and Federal Officials of Regions V and VII FEHA.

Topics discussed were the emergency drill conducted at the Quad-Cities Nuclear Power Station and he evacuation plans for the respective states.

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No items of noncompliance were identified.

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Transportation of Irradiated Fuel on June 17, 1981, the inspector observed a shipment of-segmented fuel rods being loaded and transported from the

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site.

The inspector verified that in addition to the driver,

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fone escort was available, the required communication equip-ment was available and that the transport vehicle was equipped with an immobilization device.

The inspector also witnessed restricted mode operation of

'the crane and radiation surveys of the cask.

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No items of noncompliance were identified.

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11.

Review of Licensee's Monthly Performance Report The inspector reviewed the licensee's monthly. performance report of Units 1 and 2 for the month of May, 1981.

Areas covered by the report were a-dments to Technical Specifications, summary of correc e maintenance performed d

on Safety Related Equipment, Licensee Event Reports, Operating.

Data Tabulations, and refueling information.

The report was reviewed for compliance with 7 chnical Specifications 6.6.A.3.

No items of noncompliance were identified.

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12.

Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection on June 30, 1981, and summarized the scope and findings of the inspection activities. The licensee acknowl-edged the inspectors comments.

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