IR 05000285/1980012
| ML19337A966 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/18/1980 |
| From: | Gagliardo J, Jaudon J, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19337A955 | List: |
| References | |
| 50-285-80-12, NUDOCS 8010010092 | |
| Download: ML19337A966 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/80-12 Docket No. 50-285 License No. DPR-40 Licensee: Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name:
Fort Calhoun Station Unit 1 Inspection at:
Fort Calhoun Station, Blair, Nebraska and Omaha Public
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Power District Offices, Omaha, Nebraska Inspection Conducted:
July 28-31, 1980 Inspet.cors :
J.t V Oh 9//9/ $
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L.'A. Yandell, Reac'to'i Inst ctor
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a don, Reactod Inspector Date
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Reviewed by: j
- {.E.Ga liardo, Chief, Nuclear Support Branch Date Approved by:
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vm Em8 9 /8 $M D. M. Hunnicutt, Chief, Reactor Projects Section
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Accompanying Personnel:
- G. L. Madsen, Chief, Reactor Operations and Nuclear Support Branch
- P. C. Wagner, Project Manager, NRR j
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- D. L. Kelley, Senior Resident Inspector
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- Present at Management Meeting July 31, 1980.
Inspection Summary Inspection on July 28-31, 1980 (Report No. 50-285/80-12)
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Areas Inspected:
Routine, unannounced inspection of the licensee's: (1)
organizational structure and the qualifications / experience of personael assigned to key management positions; and (2) the calibration program for safety-related instrument systems. The inspection consisted of forty (40)
hours on-site and one (1) hour at the district office by two (2) inspectors.
This visit also included an appraisal of the licensee's performance and an announced management meeting on July 31, 1980, to discuss with licensee representatives the region's annual evaluation of licensee performance.
Specific areas of the annual evaluation were:
management control, plant operations, refueling operations and activities, maintenance, surveillance testing, t; lining, radiation protection, environmental protection, emergency planning, fire protection, security and safeguards, design changes and modifications, reporting, committee activities, quality control, and procurement. The annual evalu..cion and the management meeting consisted of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on-site and 16 houri in the licensee's district offices by six (6) NRC personnel.
Results: Of the two (2) areas inspected, no items of noncompliance or deviations were noted.
No new enforcement actions were identified by the licensee performance evaluation.
A number of areas where improvements appear warranted were identified and discussed with the licensee.
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DETAILS 1.
Persons Contacted a.
Omaha Public Power District
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- R. Andrews, Section Manager, Operations
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M. Core, I&C Coordinator D. Dale, Quality Control Inspector J. Fisicaro, Supervisor Administrative Services
- B. Hickle, Licensing Administrator
- R. Jaworski, Section Manager, Technical Services
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- W. C. Jones, Division Manager, Production Operations
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G. Peterson, Maintenance Supervisor
- S. Stevens, Manager, Ft. Calhoun Station
- D. Wittke, Section Manager, Generating Station Engineering
- Indicates presence at exit interview.
- Indicates presence at management meeting.
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The inspectors also contacted other plant personnel including operators, technicians, and administrative personnel.
2.
Organization The inspector reviewed plant and off-site organizations and the quali-fications and experience of personnel assigned to key management
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positions.
No items of noncompliance or deviations were identified at a result of this inspection. The inspector noted, however, that the titles of two off-site positions delineated in the Technical Specifications (TS) as members of the Safety Audit and Review (i.e.,
off-s?te) Committee had changed. The inspector found that the changes in position title had not changed the functional responsibilities for thesc positions from that which was specified in the TS.
Licensee representatives stated that the changed titles were included in a TS change which the licensee had submitted in 1978 but which was still pending.
3.
Calibration The inspectors selected a sample of safety-related instruments to verify that the frequency calibration requirements of the license had been met, Limiting Conditiocs for Operation were met during calibration, the calibration procedures were adequate, and that qualified personnel performed the calibration. The inspectors selected three devices used L
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as calibration standards and verified that their calibration requirements
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had been met, their accuracy was verified and traceable to the National Bureau of Standards, and their control wie adequate.
The calibration procedures reviewed are listed below.
Title Procedure Number Reactor Coolant Flow Rate CP-A/114W, X, Y, Z ST-RPS-3
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Containment Pressure CP-744-1
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Station Relaying - Emerg. B/S, CP-SVR-1-1 Low Voltage
SIRW Tank Level CP-381-1 Boric Acid Tank Level CP-254-1 Monitor Tank Discharge Monitor ECP-RM-055-1 Environmental Monitor CP-RM-030-1 Area Radiation Monitor CP-RM-081-1 Linear Power Channel Rod Drop CP-RPS/ Rod Drop-A-1 Pressurizer Pressure CP 105/123-1 No items of noncompliance or deviations were identified.
4.
Management Meeting The regional managers listed on the summary page held a meeting with the licensee managers indicated in paragraph 1 on July 31, 1980 at the
licensee's district offices. The primary purpose of this meeting was to discuss the region's annual evaluation of the licensee's performance.
The licensee's performance evaluation is provided as enclosure 2 to I
this letter.
l In e.dditon to presenting the evaluation, the regional managers also discussed the licensee's enforcement history and significant reportable
events from the appraisal period.
These issues provided a partial basis
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for the licen.see's evaluation.
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The regional managers also discussed the following:
The positive attitude toward safe operation which has been demonstrated
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by the licensee; The status of significant issues discussed during the last management
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meetf ug (January 1979);
i Recent reorganization in Region IV;
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The resident inspection program implementation at Fort Calhoun;
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Forthcoming HP Appraisal;
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Observations of the emergency drill of July 29; and
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Significant outstanding items from previous inspections.
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The NRR Project Manager, who was a member of the evaluation board, also discussed his perception of the licensee's performance.
The licensee expressed no significant concerns regarding the appraisal.
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Emergency Drill
1 Ft. Calhoun F*.ation's annual emergency drill was conducted July 29, 1980.
The two inspe. tors assisted other regional inspectors in observing this emergency drill. One inspector acted as observer in the licensee's Technical Support Center, and the other inspector observed licensee activities in the Emergency Control Center and at the controlled area exit point.
Details of the emergency drill are reported in inspection report 50-285/80-13.
6.
Exit Interview A meeting was held July 31, 1980.
At this meeting the inspectors
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summarized their findings to the Manager, Ft. Calhoun Station.
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ENCLOSURE 2 PERFORMANCE EVALUATION
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FORT CALHOUN STATION
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JULY 1980 REG 10N SV
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LICENSEE PERFORMANCE EVALUATION (OPERATIONS)
Facility:
Fort Calhoun Station
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Licensee:
Omaha Public Power District Unit Identification: Unit 1 Docket No.
License No./Date of Issuance Unit No.
50-285 DPR 40 May 24, 1973
Reactor Information:
Unit 1
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Appraisal Period:
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January 1, 1979 - June 30, 1980 Appraisal Completien Date:
July 29, 1980 Review Board Members:-
G. L. Madsen, Chief, Reactor Operations and Nuclear Support Branch (R0&NSB)
J. E. Gagliardo, Chief, Nuclear Support Section, RO&NSB D. M. Hunnicutt, Chief, Reactor Projects Section No. 2, RO&NSB P. Wagner, Project Manager, NRR D. Kelley, Senior Resident Inspector, Region IV
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l A.
Number and Nature of Noncomoliance Items Noncompliance category:
Unit I l
Violations
Infractions
Deficiencies
Areas of Noncompliance:
Unit 1
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Management Control
Maintenance
Surveillance Testing
Training
Radiation Protection
Security
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Total Points
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N_ umber and Nature of Licensee Event Recorts Type of Events:
Unit 1 l
Personnel errors
Defective procedures
Casually-linked events
Licensee Event Reoorts Reviewed (Recort Nos.)
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79-01 - 79-22 80-01 - 80-11 80-16
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Escalated Enforcement Actions Civil Penalties None.
Orders None.
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Immediate Action Letters None.
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Manacement Conferences Held Ouring Past Twelve Months
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None in Past twelve months Last Meeting - January 1979 E.
Justification of Evaluations of Functional Areas Catecorized as Recuirino an increase in insoection Frecuency/Scoce (See evaluation sheets )
None.
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Inspsetion Frecuency and/or Scoce FUNCTIONAL AREA Increase No. Change Decrease 1.
Management Control
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Plant Operations X
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Refueling Operations & Activities X
Maintenance X*
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Surveillance & Preoperational Testing X*
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Training X
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Radiation Protection X
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Environmental Protection X
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Emergency Planning X
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Fire Protection X
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Security & Safeguards X
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Design Changes & Modifications X*
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Reporting X
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QA Audits X
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Committee Activities X*
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Quality Control X
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Procurement X
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- Inspections in these areas are currently on a.3 reduced frequency as authorized by MC 2515 and based on the licensees performance inythat area over the,...t two years.
// J s' of,rm.J
'(Designatea Regional Manager)
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