IR 05000285/1982016
| ML20023A738 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/17/1982 |
| From: | Hunnicutt D, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20023A731 | List: |
| References | |
| 50-285-82-16, NUDOCS 8210190539 | |
| Download: ML20023A738 (6) | |
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w APPENDIX l
U. S. NUCLEAR REGULATORY COMMISSION
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. REGION IV l
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NRC Inspection Report: 50-285/82-16 License:
' Docket: -50-285-Licensee: Omaha Public Power District
~1623 Harney Street Omaha, Nebraska.68102 racility Name: Fort Calhoun Station, Unit 1 inspection-ht: Fort Calhoun Station, Blair, Nebraska l Inspection Conducted: August 1-31, 1982
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Inspector: I du)j$
9/t NBA t. A. Yahdell, Senior Resident Reactor Inspector Date
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Approved:
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7//7/81 D.'M. Hunnicutt, Acting Chief, Reactor Project
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Section C s
a Inspection Summary
' Inspection conducted August 1-31, 1982 (Report 50-285/82-16)
Areas Inspected: Routine, announced inspection of operational safety verifica-l tion, surveillance testing, maintenance, preparation for refueling, and Licensee Event Reports followup. The inspection involved 71 inspector-hours onsite by l
one NRC, inspector.
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Results: Within the five areas inspected, no violations or deviations were identified.
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DETAILS
1.
Persons Contacted
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- W C. Jones, Division Manager, Production Operations
- R. L. Andrews, Section Manager, Operations
- K. J. Morris, Manager, Administrative Services
- F. A. Thurtell, Division Manager, Environmental and Regulatory Affairs
- M. C. Winter, Manager, Quality Assurance
- T. L. Patterson. Licensing Administrator
- W. G. Gates, Manager, Fort Calhoun Station J. J. Fluehr, Reactor Engineer J. J. Foley, Electrical Technician J. J. Fisicaro, Supervisor, Administrative Services and Security
- Denotes attendance at the exit interview.
.The NRC inspector also talked with, and interviewed, other licensee employees during.the inspection. These employees included licensed and unlicensed operators, craftsmen, engineers, and office personnel.
2.
Operational Safety Verification The NRC inspector perfonned activities as described below to ascertain that the facility is being maintained safely and in conformance with regulatory
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requirements, and that the licensee's management control systems are effective.
a.
The NRC inspecbr made several control room observations to verify licensee adherence to selected Technical Specifications, operator adherence to approved procedures, and proper control room and s':ift manning. The NRC inspector reviewed selected logs and records to verify compliance with regulatory requirements. The licensee's equipment control was reviewed for proper implementation by reviewing the maintenance order and tag-out logs, and verHication of " return to operable status of selected safety-related components and systems." The NRC inspector observed several shift turnovers and reviewed several shift turnover sheets, b.
The NRC inspector toured the plant at various times during the inspection period to determine and/or verify equipment conditions, plant conditions, security, safety, and general housekeeping. These observations included the following:
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' general plant and equipmentconditions
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fire hazards and control-of combustible material
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presence of fire watches when required
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physical security'
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-3-c.
The NRC inspector verified operability of the following safety-related systems by perfonning a walkdown or switch verification of the accessible portions of the system:
Auxiliary Feedwater System per Checklist ST-FW-1-CL-A
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Component Cooling Water System per Checklist CC-1-CL-A
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No violations or deviations were identified.
3.
Surveillance Testing The NRC inspector witnessed portions of the following surveillance test activities:
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Secondary CEA Position Indicating System PDIL, Deviation, Out-of-Sequence, and Overlap Monitoring System Test (Monthly) ST-CEA-1, F.6 b.
Spent Fuel Valves In-Service Testing (Quarterly) ST-ISI-SF-1, F.1 c.
SIRW Tank Level Channel Check (Monthly) ST-ESF-7, F.2 d.
Category A & B Nitrogen and Hydrogen Gas Valves In-Service Testing (Quarterly) ST-ISI-NG-1, F.1 In the above surveillance tests, the NRC inspector verified, where appli-cable, that:
testing was scheduled in accordance with Technical Specification
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requi rements procedures were being followed
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qualified personnel were performing the tests
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limiting conditions for operation were being met
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test data were being accurately recorded
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No violations or deviations were identified.
4.
Maintenance The NRC inspector witnessed some of the work performed on the following maintenance items:
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-4-a.
Maintenance Order (MO) 13946, " Inverter A Trouble." During a routine tour, the auxiliary operator noted that the "L2 to ground" light on the A Inverter was lit and, upon contacting the control room, deter-mined that the remote annunciator at CB-20 had not actuated. The licensee traced the problem to a design change implemented during the 1977 outane to provide additional alarms for each inverter. This required changing the annunciator contact arrangement from a "nonnally open" to "normally closed" scheme and removing sevcral jumpers. The licensee determined that the design change package failed to inc1'ude a step to remove a jumper from the "L2 to ground" circuit and the remote annunciation feature for that specific item has not been avail-able since that time.
In addition, the acceptance test performed for this modification verified annunciator operation locally at the panel but failed to check for remote annunciation of this specific item in the control room. At no time during this period did the inverters fail to perform their required functions as a result of this failure in the remote annunciator circuit.
A review of the design package showed that this modification was imple-mentad on only the A and B Inverters, due to spurious alarm problems with the new circuit. The licensee elected not to perform the change on C and D Inverters until the problem was addressed, and a Modifi-cation Completion Report was not issued. However, it was assumed by Generation Station Engineering that the work was completed and draw-ings were updated showing the change on all four devices. This is an example of a weakness in the licensee's design control / completion review system as previously identified in IE Inspection Report 50-285/
79-08. The licensee has since revised Procedure G-21, " Station Modifi-cation Control," to establish better tracking and accountability of design changes and to have more plant staff involvement in the comple-tion signoff process.
The NRC inspector observed the wiring checks performed by the licensee and reviewed the design change package information.
It was verified that the applicable drawings have been annotated to reflect actual conditions. The licensee has corrected the spurious alarm problems and intends to complete the design change on the C and D Inverters during the next refueling outage. This will remain an open item until the design change has been completed on all four inverters.
(8216-01)
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Safety Related Design Change Order (SRDCO) 82-14/FC-79-190C, Main Steam Line Radiation Monitor RM-064 (NUREC 0737, Item II.F.1). Over a period of several days the NRC inspector observed the installation of electrical conduit, setting of the sample cask in place, cable pulling, and internal wiring installation at AI-33.
It was verified by the NRC inspector that approved procedures (with proper signoffs) were present at the job loca-tions, that approved and current drawings were being used, that qualified personnel were performing the work, and that QC hold points were being observed. The NRC inspector noted that the licensee followed approved procedures for posting a fire watch when any fire barrier was compro-mised during conduit installation.
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M0's 16381 and 16385, " Diesel Fire Pump." Restricted cooling water flow l
was ' causing the pump to run hot and the licensee was' investigating the
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possibility of either blockage in the heat exchanger or a malfunctioning control valve. The NRC inspector verified that applicable Technical Specification conditions were met and that qualified personnel performed the repair work, d.
MO 16503, "HCV 820B and 821B Malfunction." During testing of the new Hydrogen Sampling System, electrical problems caused the fuses on HCV 8208 and HCV 821B to blow. The valves are inside containment and when indica-
' tion was lost it was assumed that the valves had gone to their failed (open) position. By the Technical Specification definition, this is con-sidered a loss of containment integrity and placed the licensee under a six-hour action statement limit even though the' redundant valve in each line was verified closed. To correct the situation,' the licensee per-formed a containment entry and capped the lines leading to the valves.
The lines were successfully pressure tested to 60 PSIG and containment integrity was declared restored within four hours. The NRC inspector discussed the situation with Regional and NRR representatives, and veri-fied that Technical Specification limits were observed and proper main-
'tenance procedures were followed in correcting the problem. The licensee will be issuing a 30-day Licensee Event Report (LER) to cover this incident.
No violations or deviations were identified.
5.
Preparation for Refueling New fuel for the 1983 refueling arrived onsite during this reporting period.
The licensee received a total of 32 bundles which were inspected and stored
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in the new fuel storage racks. The NRC inspector verified that shock detec-tors on the shipping containers were not tripped and that the containers were secure with no evidence of shifting. During the next few days the NRC inspec-tor observed the unloading, inspection,and storage of Fuel Assemblies JA01, JA02, JAIS, and JA16, and verified that the assemblies were handled properly, that required data were taken and recorded, and that HP coverage was present as required.
No violations or deviations were identified.
6.
Followup on Licensee Event Reports The -following LER's were reviewed to verify that:
Correct reporting requirements were met.
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Proper corrective action was identified and taken.
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Licensee administrative procedures were followed in the evaluation and
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review of the event.
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s-6-LER's reviewed included:
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LER 82-009 - component cooling water valves failed to open
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LER 82-010 - RPS channel (RC flow) out-of-specification during operation
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LER 82-014 - component cooling water valves failed to open
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LER 82-015 - containment isolation valve failed to close during
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i surveillance test LER 82-013 has been cancelled by the licensee and will not be issued.
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Exit Interview The NRC inspector met with licensee representatives on September 3,1982, to sumarize-the scope and findings of the inspection.
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