IR 05000348/1981026
| ML20039B780 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/27/1981 |
| From: | Bradford W, Brownlee V, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039B773 | List: |
| References | |
| 50-348-81-26, 50-364-81-29, NUDOCS 8112230549 | |
| Download: ML20039B780 (6) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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REGION 11 f[
101 MARIETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303 o
Report Nos. 50-348/81-26 and 50-364/81-29 Licensee: Alabama Power Company 600 North 18th Street Birmingham, AL 35202 Facility Name:
Farley Nuclear Plant Docket Nos. 50-348 and 50-364 License Nos. NPF-2 and NPF-8 Inspection at farley site near Dothan, Alabama Inspectors:
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Wp dfg of P.e( den g pector e
ned T/A. Peebles, Resige'nt Isispepor Date Signed Approved by:
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V.'L. Brbwnlee, Section ghief, Division of Da'te ' Signed Resident and Reactor Project Inspection.
SUtt?1ARY Inspection on October 16 - November 13, 1981 Areas Inspected This inspection involved 196 inspector-hours on site by the resident inspectors in monthly surveillance observation, monthly maintenance observations, opera-tional safety verification, Unit 1 outage, independent inspection effort, and review of non routine events.
.Results Of the 6 areas inspected, no violations or deviations were identified.
Oh[o!dddh PDR
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p DETAILS 1.
Persons Contacted Licensee Baployees,
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W. G. Hairston, Plant fianager J.-. D.; Woodward, Assistant Plant ihnager
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D. Morey, Operations Supervisor R. S. Hill, Operations Supervisor
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W. D. Shipman, Maintenance Superintendent C. -Nesbitt, Technical Superintendent ~
'L.- Williams, Training Superintendent
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R. G. Berryhill, Systems Performance and Planning Superintendent L. A. Ward, Planning Supervisor W. C. Carr, Chemistry and Health Physics Supervisor M. W. Mitchell, Health Physics Supervisor R..D.. Rogers, Technical Supervisor.
J. Odom,' Operations Supervisor R. Bayne, Chemistry Supervisor i
0ther licensee employees contacted included technicians, operating.
personnel, maintenance and I&C personnel, security force. members, Westinghouse contract refueling -and maintenance. personnel, and office personnel.
2.
Exit Interview The. inspection scope and findings were. summarized during management'
interviews held. throughout the reporting. period with.the plant manager and.
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selected members 'of his. staff. The licensee acknowledged the inspection findings.
3.
Licensee Action on previous Inspection Findings c
(Closed) 348/81-01-02-Open Iten:.This open item concerned verification of the -
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status of official copies of plant procedures and standards. The inspector had no further questions.
. (Closed) 348/81-09-02 Open Item: This open. item concerned the completion of the modification of the service water. recirculation to the service water. wet-
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pit system..The inspectors have reviewed the completed modification and
- functional testing. This 'is documented by_ FNP-0-ETP-256 " Recirculation to the Service-Water Wet P' t System". The' test was completed and approved on October 19,1981. The inspectors had no further questions.
4.
Unresolved Items Unresolved items were not identified. during.this ' inspection'.
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f 5.
tionthly Surveillance.0bservation The inspector observed Technical Specification required surveillance testing and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that test results met acceptance criteria requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
The inspector witnessed / reviewed portions of the following test activities:
FNP-1-2-STP-14.0 - Containment Integrity Verification Test FNP-1-2-STP-1.0 - Operations Daily and Shift Surveillance FNP-1-2-STP-27.1 - A. C. Verification FNP-1-2-STP-70.0 - Containment Sump Surveillance FNP-1-2-STP-9.0 - RCS Leakage Test FNP-2-STP-002.4 - Boron Injection Flow Path Verification FNP-2-STP-004.7 - Charging Pump 2B Mnnthly Operability Check FNP-2-STP-47.0
- l11scellaneous valves Inservice Test FNP-2-STP-12.0
- Boron Injection Tank Operability Test FflP-2-STP-109
- Power Range Neutron Flux Channel Calibration FHP-2-STP-11.9
- RHR Pump 2A tionthly Operability check 6.
Monthly flaintenance Observation Station maintenance activities of safety-related systems and components were observed / reviewed to ascertain that they were conducted in accordance with approved precedures, regulatory guides and industry codes or standards and in conformance with Technical Specifications.
The following items were considered during this review: limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to 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 preventica controls were implemented.
Work requests were reviewed to determine the status of outstanding jobs to assure that priority is assigned to safety-related equipment maintenance which may affect system performance.
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7 The following maintenance activities were observed / reviewed:
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Unit 1 RHR pumps inspection and maintenance.
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Unit 1 Reactor vessel stud cleaning and ultrasonic inspection.
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1 A charging pump, d.
Unit 1 lube schedule inside containment.
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Diesel Generator 1-2A fuel oil day tank level transmitter, f.
Diesel Generator 2C jacket water recirculation pump.
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No. 5 River water pump.
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Within the areas inspected, no violations or deviations were identified.
w s 7.
Operational Safety Verification The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the renort period. The inspectors verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the auxiliary, diesel, and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations. The inspectors by observation and direct interviews verified that the physical security plan was being implemented in accordance with the station security plan.
The inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection control. The inspectors walked down accessible portions of the following safety-related systems on Units 1 and 2 to verify operability and proper valve alignment:
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Component cooling water c.
Residual heat removal Portions of environmental monitoring and a training lecture for security personnel was observed.
The inspector observed that some of the indicating lights on the hot shutdown panels were burned out. The licensee stated that these panels will be reviewed periodically to verify that the indicating lights are functioning correctly.
Within the areas inspected, no violations or deviations were observed.
8.
Unit 1 Outage The inspectors toured the containment and witnessed maintenance testing, and defueling activities which included the following:
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Instrument Calibration c.
Instrument and instrument loop response time testing d.
Defueling of the reactor-e.
Gauging and peening of the core baffles per IEC-80-17 f.
Ultrasonic testing of the primary loop flow splitters g.
fiovement of primary loop pressure transmitters from the lower level of containment per design changes.
All activities were covered by appropriate procedures and with proper health physics surveys and controls.
The inspectors observed the inservice inspection of high energy line welds on the main steam lines and the hydrostatic testing of the RHR system for leak reduction program.
The containment purge seals on the 14,18, and 48 inch purge valves were changed per NRC commitment and local leak rate testing was perfomed satisfactorily.
Security activities during the shutdown were monitored for adherance to the security plan.
Within the areas inspected, no violations or deviations were identified.
10.
Independent Inspection Effort The inspectors routinely attended meetings with certain licensee management and various shift turnovers between shift supervisors, shift foreman and licensed operators during the reporting period. These meetings and discussions provided a daily status of plant operating and testing activities in progress as well as discussion of significant problems or incidents.
11.
Review of Nonroutine Events Reported by the Licensee The following licensee events reports were reviewed for potential generic problems, to determine trends, to determine whether the information included in the report meets the NRC reporting requirements, and to consider whether the corrective action discussed in the report appears appropriate. Licensee action with respect to selected reports was reviewed to verify that the events were reviewed and evaluated by the licensee as required by the Technical Specification, that corrective action was taken by the licensee, and that safety limits, limiting safety settings, and limiting conditions of operation were not exceeded.
The inspector examined selected plant operations review committee minutes, incident reports, logs anci records, and interviewed selected personnel.
Unit 1 LER's 81-44 Diesel Generator 1C inoperable 81-48 Diesel Generator 2C_ inoperable 81-51 Diesel Generator 1B inoperable
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81-53 Diesel Generator 1C inoperable 81-54 Instrument channel N43 inoperable 81-55 Fuel Storage Pool Rad Monitor Surveillance not performed.
81-56 Supply breaker for 1A charging pump racked out 81-57 Containment air temperature exceeds specifications 81-58 Containment atmospheric radioactivity monitoring systems de-energized 31-59 Diesel Generator 1-2A inoperable 81-60 Protection channel 412D inoperable 81-62 Train A penetration room filtration system inoperable 61-63 Supply breaker for Vacuum pump supply containment radioactivity monitors racked out 81-64 Instrumentation loop associated with refueling water storage tank level indication inoperable 81-65 Pressurized instrumentation channel to hot shutdown panel inoperable 81-67 Diesel generator tripped under load while testing therefore declared inoperable 81-68 Containment Hydrogen analyzer B inoperable Unit 2 LER's 81-32 Containment atmosphere radioactivity monitoring system inoperable 81-33 Refueling water storage tank level transmitter inoperable 81-34 Train A heat trace inoperable on boron injection tank 81-35 Refueling water storage tank level transmitter inoperable 81-37
"A" Train Boron Injection tank heat tracing inoperable 81-43 Diesel generator 1C inoperable 81-45 Diesel generator 1-2A inoperable