IR 05000285/1982028
| ML20028E267 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/23/1982 |
| From: | Johnson W, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028E263 | List: |
| References | |
| 50-285-82-28, NUDOCS 8301210161 | |
| Download: ML20028E267 (5) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-285/82-28 License:
DPR-40 Docket: 50-285 Licensee: Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name:
Fort Calhoun Station Inspection At: Fort Calhoun Station, Blair, Nebraska Inspection Conducted: November 1-30, 1982
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Inspector:
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L. A. Yandell, Senior Resident Reactor Inspector Date ~
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Approved:
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/2 I,3 8 1 W. D. Johnson, Chief, Reactor Project Section C Date
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Inspection Summary Inspection conducted November 1-30, 1982 (Report 50-285/82-28)
Areas Inspected:
Routine, announced inspection of operational safety verifica-tion, surveillance testing, and maintenance. The inspection involved 92 inspector-hours onsite by one NRC inspector.
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Results: Within the three areas inspected, no violations or deviations were identi-fied.
i 8301210161 821229 gDRADOCK 05000285 PDR
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DETAILS 1.
Persons Contacted F. K. Smith, Plant Chemist G. R. Peterson, Supervisor, Maintenance L. T. Kusek, Supervisor, Operations
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R. J. Mueller, I&C Engineer
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B. J. Hickle, Supervisor, Chemistry and Radiation Protection
- W. G. Gates, Manager, Fort Calhoun Station
- 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
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operators, craftsmen, engineers, and office personnel.
2.
Operational Safety Verification The NRC inspector performed activities as described below to ascertain that the facility is being operated safely and in conformance with regulatory requirements, and that the licensee's management control systems are effec-tive.
a.
The NRC inspector made several control room observations to verify proper shift manning, operator adherence to approved procedures, adherance to selected Technical Specifications, and operability of the reactor protec-tive system. The NRC inspector reviewed selected logs, records, recorder traces, annunciators, and panel indications 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 by verifying selected safety related tag-outs. Several shift turnovers were observed and shift turnover sheets were reviewed during this inspection period.
b.
The NRC inspector verified operability of the following safety-related systems by performing a walkdown or switch verification of the accessi-ble portions of the system:
Auxiliary Feedwater System per Checklist ST-FW-1-CL-A
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Engineered Safeguards Controls per Checklist ES-1-CL-A
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Safety Injection Tanks and Leakage System per Checklist SI-1-CL-C
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The NRC inspector toured the plant at various times to assess plant and equipment conditions. The following items were observed during the tours:
vital area barriers are not degraded
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adherance to requirements of radiation work permits
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proper use c' protective clothing and respirators
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proper personnel monitoring practices
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status of selected personnel monitors, area radiation monitors, and
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air monitors general plant and equipment conditions
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plant housekeeping and cleanliness practices including fire hazards
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and the control of combustible material the presence of fire watches when required
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physical security
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d.
The NRC inspector observed operator actions and recording of data during Containment Purge CP 82047. Proper samples were taken, initial conditions were met, the correct ventilation lineup was established, the appropriate
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meteorological data was recorded, and the atmospheric dispersion factors were calculated and compared with the limiting condition. At the comple-tion of the purge, the NRC inspector observed health physics personnel review and process the document for final calculations and signoff.
No violations or deviations were identified.
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3.
Surveillance Testing The NRC inspector witnessed portions of the following surveillance test activ-ities:
a.
Diesel Generator Inspection (Annual) ST-ESF-6, F.5.
In conjunction with this annual inspection, the I&C technicians performed seven annual cali-brations on various diesel generator instrument channels, and the electri-cians performed their annual PMs on the diesel generator panels.
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Chemical and Volume Control Pump Inservice Testing (Monthly) ST-ISI-CVCS-3, F.1 Safety Injection Valves In-Service Testing (Quarterly) ST-ISI-SI-1, F.1 c.
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d.
Power Range Safety Channels (Monthly) ST-RPS-1, F.3 j
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Fire Pump Strainer Inspection (Annual) ST-FP-8, F.1 and F.2 f.
Fire Protection System Diesel Fire Pump Battery Check (Monthly)
ST-FP-2, F.2 g.
Control Element Assembly Check (Bi-weekly) ST-CEA-1, F.4 h.
Incore/Excore Calibration; Cecor/Excore Offset Check (Monthly)
ST-RPS-13, 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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requirements procedures were being followed
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calibrated test equipment was being used
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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 portions of the work performed on the following maintenance items:
a.
Safety Related Design Change Order (SRDCO) 82-14, " Main Steamline Radia-tion Monitor." The NRC inspector observed portions of the initial calibration of RM-064, " Main Steamline Monitor," by an I&C technician.
Calibrated test equipment was being used, and the work was being done in accordance with new Calibration Procedure ECP-RM-064, " Calibration of Main Steamline Monitor."
b.
DC0 80-27, " Remote Annunciation of TSC Deluge Actuation Alarm, Power Connection to TSC Charcoal Filter Panel, and Power Connections of TSC Emergency Alarm Horns." The NRC inspector observed portions of the wiring and cable pulling work, and reviewed the job package documentation,
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-5-and Setpoint/ Procedure Change 8636. Maintenance Order (M0) 17045, " Core Drill Fire Penetration No.1088 and 1089 for DC0 80-27," was reviewed
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for completion, and the NRC inspector verified that the fire watch was posted as required until QC inspected and approved the " temporary stuff" for the fire barrier.
c.
A sub-contractor was brought onsite with a portable solidification unit to process drums of contaminated oil. The NRC inspector observed the work being performed and verified that licensee personnel were properly monitoring the activity. Approximately 90 barrels were to be completed for shipment offsite.
d.
MO 16760, " Cleaning of AC-1A, Component Cooling Water Heat Exchanger."
The licensee has initiated work to flush all four CCW heat exchangers, and the NRC inspector observed the flushing operation in progress, the reinstallation of the end bells and torquing of the nuts. The work was performed by qualified personnel using an approved procedure.
e.
As part of the surveillance test on the diesel fire pump strainer, the NRC inspector noted that strainer elements were inspected and cleaned, QC inspection points were observed, reassembly of the strainer was done in accordance with the procedure, and the fire pump was test run for operabili ty.
In conjunction with this work, I&C performed Calibration Procedure CP 2201, " Diesel Fire Pump Strainer D/P Switch Calibration Procedure." The work was performed by qualified personnel, using cali-brated test equipment and an approved, current procedure. A similar inspection was performed on the electric driven fire pump strainer after the first pump was verified operational,
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No violations or deviations were identified.
5.
Exit Interview The NRC inspector met with the Fort Calhoun Station Manager on December 1, 1982, to summarize the scope and findings of the inspection.
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