IR 05000313/1986009
| ML20205N494 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/22/1986 |
| From: | Hunter D, Murphy M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20205N471 | List: |
| References | |
| 50-313-86-09, 50-313-86-9, 50-368-86-09, 50-368-86-9, NUDOCS 8605020154 | |
| Download: ML20205N494 (6) | |
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8pPENDIX U.S. NUCLEAR REGULATORY COMISSION
REGION IV
NRC Inspection Report:
50-313/86-09 Licenses:
DPR-51 50-368/86-09 NPF-6 Dockets:
50-313 50-368 Licensee: Arkansas Power & Light Company (AP&L)
P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2
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Inspection At: ANO Site, Russellville, Arkansas Inspection Conducted:
March 17-21, 1986
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Inspector:
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M. E. Murphy, Project inspec~ tor, Projects Date Section B, Rinctor Projects Branch Approved:
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D. R. Hunter, Chief, Projects Section B, Date Reactor Projects Branch
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Inspection Summary Inspection Conducted March 17-21, 1986 (Report 50-313/86-09)
Areas Inspected:
Routine, unannounced inspection of calibration of plant instrumentation and Fire Protection / Prevention Program.
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Results: Within the two areas inspected, no violations or deviations were identified.
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i Inspection Sunnary Inspection Conducted March 17-21, 1986 (Report 50-368/86-09)
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Areas Inspected:
Routine, unannounced inspection of calibration of plant
instrumentation and fire protection / prevention program.
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Results: Within the two areas inspected, no violations or deviations were
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i DETAILS
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1.
Persons Contacted
- M. Bolanis, Health Physics Superintendent a
- P. Campbell, Plant Licensing Engineer
- E. Ewing, General Manager, Plant Support
- L. Humphrey, General Manager, Nuclear Quality P. Jones, Maintenance I&C Superintendent J. Lamb, Safety and Fire Prevention Coordinator
- J. Levine, Director, Site Nuclear Operations
- D. Lomax, Plant Licensing Supervisor
- G. Provencher, Q.A. Supervisor.
- R. Rispoli, Fire Protection Specialist
- E. Sanders, Maintenance Manager
- L. Schempp, Q.C. Superintendent
- C. Shively, Plant Engineering Superintendent
- G. Storey, Safety and Fire Prevention Coordinator
- Denotes those present at exit interview.
The NRC inspector also contacted other plant personnel, including operators, craft and administrative personnel.
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Followup On Previously Identified Items i
(Closed) Violation 368/8516-01:
Failure to maintain procedures. The NRC inspector reviewed Procedure 2203.09, " Fire Protection System Annunciator Corrective Action," and determined that the procedure was revised May 23, 1985, to address the actions necessary to. assure flow to the
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corridor by the emergency control room chillers.
Previous fire protection program related exemptions were reviewed and documented by the licensees
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engineering group.
No further procedure changes were required. This item is considered closed.
(Closed) Deviation 313/8215-03,50-368/8212-02:
Failure to maintain fire
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barrier rating as committed. The NRC inspector reviewed the LL report on
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the review of fire doors and frames in ANO, Units 1 and 2.
This report identified the types of modifications that were acceptable and those that could have adversely affected the door assembly rating. This item is considered closed.
(0 pen) Open Item 313/8215-05:
Cable penetration fire stop design.
The licensee has completed additional fire stop material testing and will submit the results to NRR.
This item remains open pending NRR action and review during a subsequent inspection.
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3.
Licensee Event Report (LER) Followup (Unit 2)
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Through direct observation, discussions with licensee personnel, and review of records, the following fire protection / fire prevention related LERs were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished.
LER 83-035 identified the potential for flooding in certain areas protected by deluge systems because of inadequate drain capacity.
The licensee's engineering organization had not yet resolved the long term corrective action.
LER 83-037 identified the penetration of fire door lintels by conduit.
The licensee requested an inspection by UL to determine what modifications to fire door assemblies had affected the assembly rating.
This inspection was completed and UL has issued a report detailing the findings. The licensee has taken corrective action where required.
This LER is considered closed.
LER 84-016 identified the discovery of an inoperable fire damper.
The licensee's investigation disclosed that the installation of the fire damper was causing binding in the tracks.
This damper has been removed, the opening modified and the damper reinstalled.
This LER is considered closed.
4.
Fire Protection / Prevention Program Implementation This inspection was conducted to determine that the licensee was implementing a program for fire protection and prevention in conformance with regulatory requirements and industry guides and standards.
The NRC inspector toured accessible areas of the plant site, noting general area condition, work activities in progress, and visual condition of fire protection systems and equipment.
It was found that combustible materials, flammable and combustible liquid and gas usage was restricted or properly controlled in areas containing safety-related equipment and components.
There were no welding, cutting, or use of open flame ignition sources found inside in the areas toured.
General housekeeping conditions were found to be very good.
There were no construction activities in progress inside the plant buildings, however, there was considerable construction activities on the
plant grounds.
The NRC inspector noted that access to hose houses and fire hydrants were maintained clear in these construction areas.
Fire protection systems and equipment installed for protection of cafety-related areas were found to be functional, ano tested in accordance with the requirements spccified in the technical specifications.
Fire brigada
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equipment including emergency breathing apparatus was found to be properly stored and maintained.
The NRC inspector also reviewed fire brigade training and drill records s
and reviewed the current roster of qualified brigade members.
The records were in order and confirmed that training and drills were being conducted at the specified intervals.
The NRC inspector also witnessed the conduct of training fire drills for each of the three shifts.
Response was prompt, personnel were properly equipped and questioning by the drill coordinator resulted in the proper strategy response by the brigade leader.
No violations or deviations were identified.
5.
Calibration This inspection was conducted to determine that the licensee had developed and implemented a program for the calibration of plant instrumentation in
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conformance with technical specifications and industry guides and standards.
The NRC inspector reviewed the following completed calibration procedures:
Revision and Procedure No.
Procedure Title Date I
i 1302.004 Power Imbalance Detector Correlation Test RS, 12-28-84 and Calibration
1302.005 Peri.ic Calibration Of Incore Detectors RS, 12-28-84 I
1304.016 Circulating Water Temperature Instrument R4, 07-03-84 Calibration 1304.025 Fire System Instrumentation Calibration R1, 06-30-83 1304.041 Reactor Protection System Channel A R9, 09-19-85 Calibration
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1304.044 Reactor Protection System Channel D R8, 12-07-84
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Calibration 1304.052 ESAS Analog Channel 1 Calibration RS, 09-24-84 j
1304.053 ESAS Analog Channel 2 Calibration R4, 09-24-84
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1304.064 Decay Heat Isolation Valve CV-1410 Auto R2, 03-08-84 Closing Calibration
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Revision and Procedure No.
Procedure Title Date I
1304.102 High Range Containment Pressure Instrument R1, 01-09-85 Calibration 1304.134 Emergency Diesel K4A Instrument Calibration R1, 08-24-85 2304.004 Boronometer Calibration R6, 03-18-85 2304.041 Plant Protection System Channel A R8, 02-20-85 Calibration 2304.042 Plant Protection System Channel 8 R8, 04-18-85 Calibration 2304.072 Safety Injection Tank Pressure and Level R4, 03-14-85 Calibraticn A Tank 2304.096 Core Protection Calculator Channe' A R10,-03-26-85 Calibration The review determined that the test documentation was coa.plete; accept.Ance criteria had been met; the proper, approved test procedure was used, :Ind; technical content was acceptable.
The licensee used a computerized program for scheduling the conduct of calibrations. The notification of a due calibration was promulgated to the proper supervisor and feedback on completion was inputed. The NRC inspector found no overdue calibrations in
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the areas reviewed.
No violations or deviations were identified.
6.
Exit Meeting An exit interview was conducted March 21, 1986, with those personnel denoted in paragraph 1 of this report. The resident in',pector also attended this exit meeting.
At this exit interview, the NRC inspector summarized the scope and findings of the inspection, i
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