IR 05000254/1980011
| ML19330C631 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/27/1980 |
| From: | Chrissotimos N, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19330C627 | List: |
| References | |
| 50-254-80-11, 50-265-80-14, NUDOCS 8008110090 | |
| Download: ML19330C631 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-254/80-11; 50-265/80-14
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Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Faci.lity Name: Quad Cities 1, 2 Inspection At:
Cordova, Illinois Inspection Conducted: May 8-June 5, 1980 f b unL Inspector:
N. J. Chr otimos f f.-
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6!T.1f 70 Approved By:
R. L. Spe sard, Chief Reactor Projects Section 1-1 Inspection Summary Inspection on May 8-June 5, 1980 (Report No. 50-254/80-11; 50-265/80-14)
Areas Inspected: Routine, unannounced inspection consisting of opera-tional safety verification, maintenance observation, surveillance obser-vation, licensee event report followup, IE Circular followup, IE Infor-mation Notice followup, observation of Emergency Medical Drill, news media contacts, information meeting with local organizations, and inde-pendent inspection. The inspection involved 158 inspector-hours onsite by one NRC inspector.
Results: No apparent items of noncompliance were identified.
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DETAILS 1.
Persons Contacted
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Kalivianakis, Superintendent T. Tamlyn, Assistant Superintendent Operations
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K. Graesser, Assistant Superintendent Administrative D. Bax, Assistant Superintendent Maintenance
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Gerner, Technical Staff Supervisor G. Conschack, Senior Operating Engineer
- J. Hei.1 man, Quality Assurance, Operations The inspector also interviewed several other licensee employees in-cluding shift engineers and foremen, reactor operators, technical staff personnel and quality control personnel.
- Denotes those present at the exit interview on June 5,1980.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance Item (265/80-01-02): Valve position verifica-tion was not accomplished. The inspector verified that corrective actions described in the licensee's response dated May 12, 1980 were accomplished. No further concerns were identified.
3.
Operational Safety Verification TL' inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of May, 1980. The inspector verified the operabil: ty of selected emergency systems, reviewed tagout records and veriF.ed proper return to service of affected components. Tours of UL ts 1 and 2 reactor buildings and turbine buildings were conducted to ob-l serve 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 May, 1980, the inspector walked down the accessible portions of the Unit I containment spray and Unit 2 core spray systems to verify l
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 j
technical specifications, 10 CFR, and administrative procedures.
i No apparent items of noncompliance were identified.
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Monthly Maintenance Observation Station maintenance activities of safety related systems and com-ponents listed below were observed / reviewed to ascertain that 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 procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality
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control records were maintained; activities were accomplished by quali-fied personnel; parts and materials used were properly certified; radic-logical 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.
The following maintenance activities were observed / reviewed:
Unit 2 - Group I PCI Logic, 4KV Breaker Bus 21, CRD-stroke adjust-ment, core spray inlet valve, recirculation pump suction valves, and
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reroute of cable from MCC 28 to MCC 28-2.
i Unit 1 - IRM Channel and recirculation M-G set repairs.
Following completion of maintenance en the recirculation pump M-G sets and 4KV Bus 21, the inspector verified that these systems had been re-turned to service properly.
No apparent items of noncompliance were identified.
5.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the shared Diesel Generator and Unit 1 ADS, Scram Timing and MSIV Closure Timing and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and pro-cedure requirements and were reviewed by personnel other than the individual directing the test, and - aat any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
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The inspector also witnessed portions of the following test activities on Unit 2:
flow control line determination, APRM.4ownscale tests, off-gas high radiation monitoring testing.
No apparent items of noncompliance were identified.
6.
Licensee Event Reports Followup
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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 pre-vent recurrence had been accomplished i.s accordance with technical specifications.
LER'S Unit 1 R0 80-13/03L dated April 15, 1980, reactor low water level switch was found to trip below technical specifications.
R0 80-14/03L dated April 15, 1980, high drywell pressure switch found to trip higher than technical specifications.
R0 80-10/03L dated April 23, 1980, instrument setpoint drift of an EHC pressure switch.
R0 80-12/03L dated April 29, 1980, recirculation pump trip.
RO 79-15/03L dated February 25, 1979, MSIV limit switch trip positions greater than 10% closure.
Unit 2 R0 80-11/03L dated April 20, 1980, relief valve failed to open during su rveillance.
R0 80-12/03L dated April 28, 1980, conductivity found to be high during unit startup.
No apparent items of noncompliance were identified.
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7.
IE Circular Followup For the IE Circulars listed below, the inspector verified that the circular was received by the licensee manaatment, that a review for applicability was performed, and that if r.he circular were applic-able to the facility, appropriate corrective actions were taken or were scheduled to be taken.
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IEC 80-05 dated April 1,1980, Emergency Diesel-Generator Lubricating
Oil Addition and Onsite Supply IEC 80-07 dated April 3, 1980, Problems with HPCI Turbfae Oil System.
The licensee does not have this type turbine.
IEC 80-08 dated April 18, 1980, BWR Technical Specification Incon-sistency - RPS Response Time IEC 80-09 dated April 28, 1980, Problems with Plant Internal Communi-cations Systems IEC 80-10 dated April 29, 1980, Failure to Maintain Environmental Qualification of Equipment IEC 80-11 dated May 13, 1980, Emergency Diesel Generator Lube Oil Cooler Failures IEC 80-12 dated May 14, 1980, Valve-Shaft-To-Actuator Key May Fall Out of Place When Mounted Below Horizontal Axis
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No apparent items of noncompliance were identified.
8.
IE Information Notice Followup For the IE Information Notices listed below, the inspector verified that the information notice was received by the licensee management, that a review for applicability was performed, and that if the in-formation notice were applicable to the facility, appropriate actions were taken or were scheduled to be taken.
IE IN 80-01 dated January 4, 1980, Fuel Handling Events IE IN 80-02 dated January 25, 1980, 8 x 8R Water Rod Lower End Plug Wear IE IN 80-03 datad January 31, 1980, Main Turbine EHC System IE~IN_80-04 dated February 4, 1980, BWR Fuel Exposure in Excess of Limits IE IN 80-05 dated February 8,1980, Chloride Contamination of Safety Related Piping IE IN 80-06 dated February 27, 1980, Notification of Significant Events IE IN 80-07 dated February 29, 1980, Pump Shaft Fatigue Cracking IE IN 80-08 dated March 7, 1980, The States Company Sliding Link Electrical Terminal Block IE IN 80-09 dated March 7, 1980, Possible Occupational Health Hazard Associated with Closed Cooling System-5-
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d IE IN 80-10 dated March 7, 1980, Partial Loss of Non-Nuclear Instru-ment System Power Supply During Operation IE IN 80-11 dated March 14, 1980, General Problems with ASCO Valves in Nuclear Application Including Fire Protection Systems IE IN 80-12 dated March 31, 1980, Instrument Failure Causes Opening of PORV and Block Falve IE IN 80-13 dated April 2, 1980, G.E. Type SBM Control Switches -
Defective Cam Followers IE IN 80-14 dated April 2, 1980, Safety Suggestions From Employees IE IN 80-15 dated April 21, 1980, Axial (Longitudinal) Oriented Cracking in Piping IE IN 80-16 dated April 29, 1980, Shaft Seal Packing Causes Binding in Main Steam Swing Disc Check and Isolation Valves No apparent items of noncompliance were identified.
9.
Emergency - Drill (Medical)
The inspector observed the response by the licensee organization and selected offsite support agencies during a scheduled drill conducted by the licensee's emergency medical contractor on June 4, 1980.
Site personnel sad an ambulance crew responded to the simulated accident
.and hospital personnel responded to the decontamination and medical treatment. Radiation Management Corporation (RMC) personnel prepared the victim and directed the hospital segment of the drill.
Communications with the scene of the accident were established and were noted as being acceptable. Control room personnel, in reporting the injury to the hospital, contacted the emergency room instead of the house supervisor as prescribed. Some confusion was also noted
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as to how to classify the accident. This classification is now dis-tinguishable in the latest GSEP procedures.
The inspector also observed the drill conducted at Jane Lamb Hospital and noted the following:
(1) decontamination and medical sample col-lecting procedures were acceptable, and (2) contamination control dealing with step-off pads and cleanliness have improved since the previous drill; however, some improvement is still needed.
The medical contractor held a critique with the hospital personnel and station personnel involved in the drill.
No apparent items of noncompliance were identified.
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10.
Media Contacts On May 20, 1980 the Senior Resident Inspector met with Mr. John Richard of WQUAD (ABC) News of Moline. The interview concerned the recent un-planned release of noble gases from the station. The release was 1.8%
of technical specification limits. The cause was attributed to an equipment attendant receiving poor communications as what was to be done plus the mechanical failure of the equipment. This led to tSe opening of a valve which momentarily bypassed the off gas filtration system. This event had no effect on the environment and did not exceed any regulatory limits.
11.
Local Meeting On May 21, 1980 the Senior Resident Inspector met with a church or-ganization from the Bettendorf community. The topics of discussion included the recent release of gases from the station, nuclear pcwer and the accident at Three Mile Island.
12.
Independent Inspection The inspector took part in discussions with contractor personnel on site to answer questions related to construction activities and the NRC's role of inspection and regulations.
13.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection June 5, 1980 and summarized the scope and findings of the inspection activities. The licensee acknowledged the inspector's comments.
The licensee announced that K. Graesser, Assistant Superintendent Opera-tions, will be promoted to Plant Superintendent at Zion; L. Genner, cur-
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rently Technical Staff Supervisor, will replace him.
R. Flessner, cur-l rently Rad Chem Supervisor, will become Technical Staff Supervisor and T. Kovac, Lead Health Physicist, will become Rad Chem Supervisor. All l
personnel except Mr. Graesser will retain their respective prime respon-sibilities until the completion of the upcoming refueling outage. Also Mr. Jack Baker, Technical Staff Supervisor of Braidwood will become a Staff Assistant at Quad-Cities.
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