IR 05000285/1985024
| ML20136D255 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/18/1985 |
| From: | Harrell P, Hunnicutt D, Murphy M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20136D251 | List: |
| References | |
| 50-285-85-24, NUDOCS 8601060103 | |
| Download: ML20136D255 (6) | |
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-APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
. REGION IV NRC Inspection Report: 50-285/85-24 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: October 1-November 30, 1985 12. - 4 - @h Inspectors:
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P. H. HaQlW or Resident Reactor Date Inspector W
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. Approved:
F1r8-D. M. Hunnicutt, Chief, Project Section 8, Date
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Reactor Project Branch
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Inspection Summary a
Inspection Conducted October 1 - November 30, 1985 (Report 50-285/85-24)
Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, and followup on previously identified
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The inspection involved 94 inspector-hours (including 10 backshift hours)
onsite by two NRC inspectors.
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t Results: Within the four areas inspected, no violations or deviations were j
identified.
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-3-DETAILS 1.
Persons Contacted J. J. Fisicaro, Nuclear Regulatory and Industry Affairs Supervisor
- W. G. Gates, Station fianager L. T. Kusek, Operations Supervisor T. J. ficIvor, Technical '>upervisor
- Denotes attendance at t'! exit interview.
The NRC inspectors also contacted other plant personnel, including operators, technicians, and administrative personnel.
2.
Followup on Previously Identified Items (Closed) Unresolved Item 285/8115-04:
Lack of control over unofficial markup of drawings.
This item has been closed based on issuance of a violation (285/8515-01) in NRC Inspection Report 50-285/65-15.
(Gosed) Unresolved Item 285/8304-02:
Affect of a nodification on the fire rating of a fire door.
Fire Door 1011-7 had been modified causing a hole to remain around the latching mechanism. The hole has been covered by a metal plate. An underwriters laboratory (UL) representative has completed a review of all plant fire doors and has inforned the licensee that specified conditions on a number of fire doors must be corrected.
Fire Door 1011-7 is one that will require additional repairs. The licensee is in the process of making the UL-recommended repairs.
(Closed) Unresolved Item 285/8315-02:
Performance of a biennial review of operating procedures.
The NRC inspector reviewed the procedure index and documentation of reviews that have been performed. The NRC inspector determined that reviews are being conducted and documented in accordance with the appropriate licensee requirements.
(Closed) Unresolved Item 285/8412-03: Apparent false statement in response to IE Bulletiun 82-02.
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s I-4-This item is closed based on the issuance of a notice of violation by NRC Region IV in a letter dated March 8, 1985.
3.
Operational Safety Verification The NRC inspector observed control room operations, reviewed applicable logs, and conducted discussions with control room operators. The NRC inspector verified the operability of selected emergency systems, reviewed tag-out records, verified proper return to service of affected components, and ensured that maintenance requests had been initiated for equipment in need of maintenance. The NRC inspector made spot checks to verify that the physical security plan was being implemented in accordance with the station security plan. The NRC inspector verified implementation of radiation protection controls during observation of plant activities.
The NRC inspector toured accessible areas of the unit to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibration. The NRC inspector also observed plant housekeeping and cleanliness conditions during the tour.
The NRC inspector walked down the accessible portions of the systems listed below. The systems were walked down using the drawings and procedures noted:
Auxiliary feedwater system (Drawings: M-253, Revision 43 and M-254,
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Revision 52; Procedures:
OI-FU-4, Revision 26 and 01-AFW-1, Revision 1)
Emergency diesel generators support systems (Drawings: M-262
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Revision 20 and B120F07001, Revision 12; Procedures: 01-DG-1, Revision 19 and OI-DG-2, Revision 19)
Main steam system (Drawing: M-252, Revision 33;
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Procedures: 01-MS-1, Revision 10 and OI-MS-2, Revision 13)
Main feedwater system (Drawing: M-253, Revision 43;
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Procedure: 01-FW-2, Revision 15)
During these walkdowns, the NRC inspector noted minor discrepancies between the drawings, procedures, and as-built plant configuration. The licensee and NRC inspector are still in process of resolving the noted discrepancies. This portion of this inspection will be continued during the next inspection period.
These reviews and observations were conducted to verify that_ facility operations were in conformance with the. requirements established under Technical Specifications,10 CFR, and administrative procedures.
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-5-No violations or deviations were identified.
4.
Monthly Maintenance Observation
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Station maintenance activities of safety-related systems and components t
listed below were observed to ascertain that they were conducted in accordance with approved procedures, Regulatory Guides, and industry codes or standards; and in conformance with Technical Specifications.
The following items were considered during this review:
the limiting
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conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the wo"k; I
activities were accomplished using approved procedures and were. inspected as applicable; functional testing and/or calibrations were performed prior
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to returning components or systems te service; quality control records were maintained; activities were accomplished by qualified personnel;
parts and materials.used were properly certified; radiological controls were implemented; and fire prevention controls were implemented.
Work requests were reviewed to determine the status of outstanding jobs
and to ensure that priority is assigned to safety-related equipment naintenance which may affect system performance.
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The' following maintenance activities were observed:
Preventive maintenance for the containment ventilation fan breaker
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(Procedure DP-VA-7D)
Preventive maintenance for the 480-volt, safety-related distribution
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breakers (Procedure MS-EE-4.0)
No violations or deviations were identified.
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Monthly Surveillance Observation
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The NRC inspector observed the Technical Specification required surveillance testing on the emergency diesel generator (Procedure ST-ESF-6-F.2) and verified that testing was performed in accordance with adequate procedures, test instrumentation was calibrated, limiting conditions fer operation were met, removal and restoration of the affected
components were accomplished, test results conformed with Technical Specifications and procedure requirements, test results were reviewed by
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personnel other than the individual directing the test, and any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
No violations or deviations were identified.
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Exit Interview The NRC inspector met with Mr. W. G. Gates (Station Manager) and other members of the OPPD staff at the end of this inspection. At this meeting, the NRC inspector summarized the scope of the inspection and the findings.
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