IR 05000285/1986030

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Insp Rept 50-285/86-30 on 861101-30.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Plant tours,safety-related Sys Walkdown & Security Observations
ML20212E706
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/19/1986
From: Harrell P, Hunter D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20212E680 List:
References
50-285-86-30, NUDOCS 8701050413
Download: ML20212E706 (6)


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APPENDIX U.S. NUCLEAR REGULATORY COMISSION

REGION IV

NRC Inspection Report: 50-285/86-30 License: DPR-40 Docket: 50-285 Licensee: .0maha 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, 1986

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Inspector: / 7-- 1 P4 p. H. HarrelV, S#nig Resident Reactor

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Inspector Approved: M D. R. Hunter, Chief, Project Section B iMIifk Date Reactor Projects Branch Inspection Summary Inspection Conducted November 1-30, 1986 (Report 50-285/86-30)

Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, plant tours, safety-related system walkdown, and security observation Results: Within the six areas inspected, no violations or deviations were identifie PDR 0 ADOCK 05000285 PDR

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DETAILS Persons Contacted

  • Gates, Plant Manager C. Brunnert, Supervisor, Operations Quality Assurance M. Core, Supervisor, Maintenance J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs J. Foley, Supervisor, I&C and Electrical Field Maintenance M. Kallman, Supervisor, Security L. Kusek, Supervisor, Operations
  • D. Munderloh, Licensing Engineer T. McIvor, Supervisor, Technical R. Mueller, Plant Engineer G. Roach, Supervisor, Chemical and Radiation Protection J. Tesarek, Reactor Engineer S. Willrett, Supervisor, Administration Services and Security
  • Denotes attendance at the monthly exit intervie The inspector also contacted other plant personnel, including operators, technicians, and administrative personne . Operational Safety Verification The NRC inspector conducted reviews and observations of selected activities to verify that facility operations were performed in conformance with the requirements established under 10 CFR, administrative procedures, and the TS. The NRC inspector made several control room observations to verify:

. Proper shift staffing

. Operator adherence to approved procedures and TS requirements

. Operability of reactor protective system and engineered safeguards equipment

. Logs, records, recorder traces, annunciators, panel indications, and switch positions complied with the appropriate requirements

. Proper return to service of components

. Maintenance orders (M0) initiated for equipment in need of maintenance

. Appropriate conduct of control room and other licensed operators

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During an emergency planning (EP) inspection performed by Region IV personnel, the NRC EP inspector noted that the individual designated on the watchbill as the shift supervisor and emergency site director had impaired vision. This individual had eye surgery for cataracts in the recent past and his vision had not fully recovered to a point where he could pass an eye examination. The licensee had elected to provide an additional individual licensed as a senior reactor operator onshift with the designated shift supervisor. The licensee stated that the purpose of adding the individual to the shift was to provide the shift supervisor with assistance, should the need arise, due to the shift supervisor's vision problem Following discussions between the licensee management and the NRC SRI on November 21, 1986, the licensee designated the additional senior reactor operator on shif t as the acting shift superviso On November 26, 1986, the licensee filed a report with the NRC in accordance with 10 CFR Part 55.41. This report provided the NRC with a netification of disability related to the vision impairment of the shift supervisor. This item remains unresolved pending review during a subsequent inspection. (285/8630-01)

No violations or deviations were note . Plant Tours The NRC inspector conducted plant tours at various times to assess plant and equipment conditions. The following items were observed during the tours:

. General plant conditions

. Equipment conditions, including fluid leaks and excessive vibration

. Plant housekeeping and cleanliness practices including fire hazards and control of combustible material

. Adherence to the requirements of radiation work permits

. Work activities performance in accordance with approved procedures During tours of the plant, the NRC inspector noted the following:

. On two different occasions, compressed gas cylinders were observed to be stored in the plant that were not properly secured. Upon notification by the inspector, the licensee immediately secured the cylinder . During replacement of fire doors, the individuals performing the replacement failed to reinstall the appropriate personnel warning sign This included signs such as no smoking, no two-way radio

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transmission allowed, and evacuation when halon fire system alarm j ',

sounds. The licensee stated that the signs would be reinstalled in .

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s the appropriate location ,

No violations or deviations were identifie , Security Observations ,

The NRC inspector verified the physical security plan was being < implemented by selected observation of the following items: '

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. The security organization is properly manne . Personnel within the protected area (PA) display their identification badge .

. Vehicles are properly authorized, searched, and escorted or controlled within the P . Persons and packages are properly cleared and checked before entry into the PA is permitted. An observation, made by the SRI on November 20, 1986, regarding the apparent failure to search a package, was referred to the NRC physical security inspector, onsite at the tim .

The effectiveness of the security program is maintained when security equipment failure or impairment requires compensatory measures to be employe No violations or deviations were identifie . Safety-Related System Walkdowns The NRC inspector walked down accessible portions of the following safety-related system to verify system operability. Operability was determined by verification of selected valve and switch positions. The system was walked down using the following drawing and procedure:

. Raw water system (Drawing 11405-M-100, Revision 27, and Procedure 01-RW-1-CL-A, Revision 14).

During the walkdown, the NRC inspector noted minor discrepancies of an editorial nature between the drawing, procedure, and plant as-built conditions for the selected areas checked. None of the conditions noted affected the operability or safe operation of the system. Licensee personnel stated that the noted minor discrepancies would be correcte No violations or deviations were identified, s

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I\\ Monthly Maintenance Observation

)' The NRC inspector reviewed and/or observed selected station maintenance activities on safety-related systems and components to verify the

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maintenance was conducted in accordance with approved procedures, regulatgy requirements, and the TS. The following items were considered during the reviews and/or observations:

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The TS limiting conditions for operation were met while systems or components were removed from servic .s Approvals were obtained prior to initiating the wor Activities were accomplished using approved M0s and were inspected, as applicabl . Functional testing and/or calibrations were performed prior to returning components or systems to servic y, . Quality control records were maintaine fI .N Activities were accomplished by qualified personne .

j Parts and materials used were properly certifie . Radiological and fire prevention controls were implemente The NRC inspector reviewed and/or observed the following maintenance activities:

( . Intake structure cell valve stem repair (M0 864194)

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. Repair of various plant fire doors (M0 863229)

Repair of the chemical and volume control system totalizer

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t (M0 860346)

. Repair of the steam generator pressure alarm circuit (M0 857709)

No violations or deviations were note . Monthly Surveillance Observation The NRC inspector observed selected portions of the performance of and/or reviewed completed documentation for the TS required surveillance testing on safety-related systems and components. The NRC inspector verified the following items during the testing:

. Testing was performed by qualified personnel using approved procedure (

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. Test instrumentation was calibrate . The TS limiting conditions for operation were me . Removal and restoration of the affected system and/or component were accomplishe . Test results conformed with TS and procedure requirement . Test results were reviewed by personnel other than the individual directing the tes . Deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne Thc NRC inspector observed and/or reviewed the documentation forsthe

following surveillance test activities. The procedures usea for the test-activities are noted in parenthesi ,

. Acoustic monitor circuit check (ST-AC00STIC-1-F.1)

. Containment narrow-range water level check (ST-CWL-1-F.1)

. Containment wide-range water level checA (ST-CWL-2-F.1)

. Containment wide-range pressure indication check (ST-CWP-1-F.1)

No violations or deviations were identifie . Exit Interview The NRC' inspector met with Mr. W. G. Gates (Plant Managsr) and anot'er h member of the licensee 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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