IR 05000285/1993009
| ML20045D489 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/23/1993 |
| From: | Constable G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20045D484 | List: |
| References | |
| 50-285-93-09, 50-285-93-9, NUDOCS 9306290060 | |
| Download: ML20045D489 (8) | |
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APPENDIX
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U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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Inspection Report: 50-285/93-09 Operating License:
DPR-40 Licensee:
Omaha Public Power District 444 South 16th Street Hall Mail Stop 8E/EP4 Omaha, Nebraska 68102-2247 Facility Name:
Fort Calhoun Station (FCS)
Inspection At:
h Inspection Conducted:
June 7-11, 1993
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Inspector:
M. E. Murphy, Reactor Inspector, Plant Support Section Division of Reactor Safety
k bob Approved:
44, m
G.~ L. Constablf, Chief,' Pldnr Support Date Section,Di{isionofReactorSafety
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Inspection Summary Areas Inspected :
Routine, announced inspection of the licensee's implementation of the fire protection / prevention program.
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Results :
The licensee had established, was maintaining and implementing an
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effective fire protection / prevention program.
Maintenance of the material condition of the systems and equipment
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required to support the fire protection / prevention program was considered very good.
General housekeeping was considered to be excellent and a strength of
the program.
The training-improvements in the fire protection / prevention area
demonstrated the interest and support of licensee management and should prove to be a strength of the program.
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9306290060 930623 PDR ADOCK 050002B5'
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-2-t The licensee's QA program provides strong support to maintaining an
effective fire protection / prevention program and enhances the licensee's
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self assessment capability in this program area.
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Summary of Insoection Findinos:
There were no violations or deviations identified during this
inspection.
Attachments:
Attachment 1 - Persons Contacted and Exit Meeting
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Attachment 2 - Documents Reviewed
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-3-DETAILS 1 FIRE PROTECTION / PREVENTION PROGRAM (64704)
This inspection was corducted to determine that the licensee had established and was implementing a program for fire protection and prevention in conformance with regulatory requirements, Technical Specifications, and industry guides and standards. The inspection also assessed the licensee's system for conducting programmatic changes necessitated by quality assurance
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audit results, generic deficiencies, or licensee events.
1.1 PROGRAM REVIEW The licensee's program is presently contained in the FCS Technical Specifications; however, the licensee was in the process of obtaining a change that will remove the program from the Technical Specifications. The FCS fire protection program was administratively controlled by several station
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operating procedures. The central procedure was 50-G-28, " Station Fire Plan,"
and it contained a general plan overview, assigned responsibilities as they
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are outlined in the Updated Fire Hazards Analysis, defined the composition of the plant fire brigade, and promulgated the Prefire Plans.
Prefire plans were used by the plant fire brigade to develop fire fighting strategies. The inspector reviewed the licensee's Fire Hazards Analysis, Safe Shutdown Analysis, 50-G-28 and the other station operating procedures that comprise the program. These procedures are identified in Attachment 2.
This procedure review determined that there had been no significant changes to the licensee's program since the last inspection in August 1990. The review also verified that the licensee had technically acceptable procedures to implement the fire protection program.
Procedural guidance was provided to control combustible material and reduce fire hazards.
Administrative procedures provided for maintenance and surveillances on fire suppression, detection, and support equipment.
Personnel training, qualifications, and responsibilities were adequately provided. Maintenance evolutions that significantly increased fire risk were properly controlled.
During the review of the licensee's Abnormal Operating Procedure A0P-06,-
" Fire Emergency," the inspector noted that there were four equipment operating functions listed to be performed prior to exiting the control room. Generic Letter 86-10, " Implementation of Fire Protection Requirements," allows credit for only one action prior to control room evacuation and that-is usually the reactor trip.
In a discussion with the licensee, the inspector determined that the other actions listed in A0P-06 were considered as " perform if possible items" and could be accomplished outside the control room. The licensee had determined that these actions would not be negated by subsequent spurious actuation signals resulting from a fire in either the control room or cable spreading room. The licensee agreed to clarify the significance of the
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listed actions.
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-4-1.2 PLANT / SYSTEM TOVE
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A tour of accessible areas of the plant was conducted to assess general area condition, work activities in progress, and the visual conditions of fire protection systems and equipment. Combustible materials and flammable and combustible liquid and gas usage were restricted or properly controlled in areas containing safety-related equipment and components.
Items checked included positions of selected valves, fire barrier conditions, hose stations, hose houses, Halon system lineups, fire lockers, and fire extinguishers for type, location, and condition. There were no construction activities in process in the toured areas.
There was no maintenance work and only limited surveillance testing noted. General housekeeping conditions were found to be excellent.
Fire protection systems and equipment installed for protection of safety-
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related areas were found to be functional and tested in accordance with.
requirements specified in the Technical Specifications.
Fire brigade equipment, including emergency breathing apparatus, was easily accessible and found to be properly stored and maintained. The inspector conducted a walkdown of the fire suppression water supply system and verified that it was l
operable as required by the Technical Specifications. During this walkdown, the inspector noted a full, free standing acetylene gas bottle in an outside gas storage area. The licensee took prompt and effective action to have the bottle properly secured.
Hose houses, hydrants, and post indicator valves were found to be clear and unobstructed.
Hose stations, fire extinguishers, and deluge manifolds were also clear and unobstructed.
Fire suppression sprinkler heads and halon nozzles were unobstructed and clean.
1.3 FIRE BRIGADE The inspector reviewed fire brigade training and drill records.
The records were in order and confirmed that training and drills were being conducted at the specified intervals. A review of selected lesson plans confirmed that the licensee was meeting the requirements of the commitments to fire brigade-training. Training was conducted under a full time fire professional and was a blend of classroom lecture, video presentations and practical exercises.
The inspector toured the licensee's burn pad where practical lessons were presented.
This was a relatively new addition and provided excellent hands on experience and effective fire environment exercises.
This training program was supplemented with hands on practical training at the Omaha Fire Tower.
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Interviews were conducted with personnel qualified as fire brigade members and
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fire watches. The first individual was a nuclear equipment operator, with the licensee for three and a half years, who qualified as a fire brigade member during his initial training.
This individual assessed the training as fair but with recent improvement and was satisfied with the level of training and the quality of equipment. The individual appeared competent and was knowledgeable of his duties as a fire brigade member. The second person was a
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-5-licensed reactor operator, with the licensee for six years, and qualified as a fire brigade leader for two years. This individual appeared very competent, was fully satisfied with the training, and felt confident in his ability as a brigade leader. The fire watches were members of maintenance and security, with varying years of experience, felt that the training was satisfactory and appeared knowledgeable of the duties and responsibilities of the various fire watch assignments and the actions that could be required of them.
1.4 00ALITY ASSURANCE AUDITS The inspector reviewed three QA surveillance reports and the last two annual audit reports, the second of which was also the triennial audit required by.
the Technical Specifications. The surveillances, F1-92-1, F-92-1, and F1-93-1 were observations conducted in accordance with a check list of the fire protection attributes, augmented with surveillance tests in progress and modifications being performed that affect fire protection systems or equipment. The audits, SARC Audit Report 25A and QA Audit Report 25, and SARC Audit 25 A/B, were the formal reviews of the program required by the Technical Specifications on an annual basis, with the one conducted every third year to include an independent fire protection consultant.
The surveillances covered such attributes as portable fire extinguisher monthly checks, hose cabinets, emergency lighting, housekeeping, Halon system modification, fire hose hydrostatic testing, fire door labeling, flammable material storage, fire protection system freeze protection, and fire watches.
No corrective action reports were issued as a result of these surveillances and only one concern was identified. This concern was the fact that the licensee's Transient Combustibles Procedure S.0. G-91 had not been issued.
The procedure was subsequently issued.
The scope of the audits included modifications to systems and structures, procedure changes, Technical Specification surveillance tests, fire protection equipment, fire protection systems, fire barriers, fire loading in safety related areas, and fire protection training including fire brigade, fire watch
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and general employee training. The audits resulted in the identification of several deficiencies; however, they were of such a minor nature the conclusion of the auditors was that the licensee's program was effective and continued to show improvements The deficiencies identified were formally presented to the affected organizations.
Responses were tracked to closecut, and actions taken were reviewed for adequacy.
1.5 CONCLUSIONS
The licensee had established and was maintaining an effective fire protection / prevention program. The program had been very effectively implemented, with very good maintenance of the material condition of the systems and equipment required to support the program. General housekeeping, with the resultant control of combustible materials, was found to be excellent. There was a significant improvement in the fire protection i
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training area, especially in the quality of the classroom presentations and capability in providing hands on practical experience. The training improvements demonstrated the interest and support of licensee management.
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The QA audits and surveillances conducted in the area of fire
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protection / prevention were thorough and met the Technical Specification i
requirements.
Responses to the audit findings were prompt and corrective actions appropriate. Self assessment capability in the fire protection / prevention program area appears to be both comprehensive and ef fective.
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ATTACHMENT 1 1.aERSONS CONTACTED-1.1 Licensee Personnel R. Acker, Senior QA Auditor
- J. Chase, Manager, Fort Calhoun Station
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S. Chomos, Fire Protection System Engineer
- G. Cook, Supervisor, Station Licensing S. Danon, Senior Instructional. Technologist, Fire Protection
- S. Gambhir, Division Manager, Engineering
- J. Gasper, Manager, Training
- D. Gorence, Supervisor, System Engineering (Acting)
- D. Gross, Training Specialist, Nuclear Security Services R. Huber, Licensed Reactor Operator
- R. Jaworski, Manager, Station Engineering R. Johansen, Supervisor, Maintenance Support
- W. Jones, Senior Vice President L. Kusek, Division Manager, Nuclear Services Division (Acting)
D. Lippy, Station Licensing Engineer
- W. Orr, Manager, QA/AC
- T. Patterson, Division Manager, Nuclear Operations
- R. Phelps, Manager, Design Engineering H. Sefick, Manager, Security Services
- C. Simmons, Station Licensing Engineer M. Stanley, Equipment Operator Nuclear C. Sterba, Fire Detectioon System Engineer
- M. Sweigart, Nuclear Safety Review Specialist J. Uhland, Supervisor, Radiation Orientation and Emergency Preparedness Training B. Van Sant, Supervisor, Mechanical Design Engineering 1.2 NRC Personnel
- R. Azua, Resident Inspector D. Kelley, Reactor Inspector C. Johnson, Reactor Inspector In addition to the personnel listed above, the inspector contacted other personnel during this inspection period.
- Denotes personnel that attended the exit meeting.
2 EXIT MEETING An exit meeting was conducted on June 11, 1993. During this meeting, the i
inspector reviewed the scope and findings of the report. The licensee did not
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identify as proprietary any information provided to, or reviewed by, the inspector.
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ATTACHMENT 2 DOCUMENTS S0-G-6 Housekeeping, Rev. 45, 12/17/92 S0-G-28 Station Fire Plan, Rev. 28,6/3/93
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S0-G-58 Control of Fire Protection System Impairments, Rev. 19a, 3/25/93
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S0-G-91 Control and Transportation of Combustible Materials, Rev. O, 3/10/93 S0-H-9 Fire Prevention Uu ing Flame Cutting, Grinding and Welding Operations, Rev. 18,3/28/92 S0-0-38 Fire Watch Duties-and Turnover Procedures, Rev. 9, 6/21/91 A0P-06 Fire Emergency, Rev. 0.2,3/29/93 Updated Fire Hazards Analysis Updated Safe Shutdown Analysis