IR 05000348/1981018
| ML20010H386 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/31/1981 |
| From: | Bradford W, Brownlee V, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010H378 | List: |
| References | |
| 50-348-81-18, 50-364-81-18, NUDOCS 8109240410 | |
| Download: ML20010H386 (6) | |
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UNITED STATES
NUCLEAF. REGULATORY COMMISSION o
HEGION 11 t
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101 MARIETTA ST., N.W., SUITE 3100 g% *****p ATLANTA, GEORGIA 30303 Report Nos. 50-348/81-21 and 50-364/81-21 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 F0rley site near Dothan, Alabama Inspector:
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W. W.Jradford, Sen)or/ Resident Inspector
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- T." A.'Peelles, Resident Anspector
'Oh te ' Signed'
07'"'" UkWAJ em /ri V. L. drownlee, Acting Section Chief
' (Date Sign 6d Division of Resident and Reactor Project Inspection SUtiMARY Inspection on July 16 - August 14, 1981 Areas Inspected This routine inspection involved 200 inspector-hours on site by the resident inspectors in operational safety verification, monthly surveillance observation, monthly maintenance observation, Unit 2 startup testing, independent inspection effort, diesel generator 1-C failure, and IE Bulletins.
Resul ts Of the 7 areas inspected, no violations or deviations were identified.
8109240410 010831 gDRADOCK 05000348 i PDR
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DETAILS 1.
Persons Contacted Licensee Employees W. G.'Hairston, Plant Manager J. D. Woodward, Assistant Plant Manager D. Morey, Operations Supervisor R. S. Hill, Operations Supervisor W. D. Shipman, Maintenance Superintendent K. McCraken, Technical Superintendent D. E. Mansfield, Unit 2 Startup Superintendent C. Nesbitt, C&HP Supervisor L. Williams, Training Superintendent W. C. Carr, Supervisor of SAER K. W. Kale, SAER Engineer R. D. Rogers, Technical Supervisor R. H. Marlow, Engineering Supervisor L. A. Ward, Planning Supervisor R. G. Berryhill, Systems Performance and Planning Superintendent H. McClelland, Plant Engineer Other licensee employees contacted included technicians, operating personnel, maintenance and I&C personnel, security force members and office personnel.
2.
Exit Interview The inspection scope and findings were summarized during management inter-views on July 31, 1981 and August 14, 1981, with the plant manager and selected members of his staff.
The licensee acknowledged the inspection findings.
3.
Licensee Action on Previous Inspection Findings (Closed) 348/81-11-01 and 364/81-14-01 violation:
Failure to follow shift turnover procedures. The inspector reviewed the licensee's corrective actions and the licensee's response dated August 6, 1.981. The inspector had no further questions.
(Closed) 348/80-42-02 Violation: Inoperable service water trains due to cross tie of trains A and B lube and cooling supply header. The inspector reviewed the licensee's corrective actions and the licensee's response dated March 27, 1981. The inspector had no further questions.
4.
Unresolved Items Unresolved items were not identified during this inspection.
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5.
Operational Safety Verification The inspectors observed control room operations, reviewed applicable logs and conducted discussion; with control room operators during the report period. The inspectors verified the operability of selected emergency systems, reviewed ?.agout 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 plar.t 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 rarify operability and proper valve alignment:
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High head safety injection.
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Portions of the boric acid system.
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The inspectors observed the loading and shipping of a low level radwaste shipment on July 28, 1981.
These reviews and observations were ccnducted to ascertain that facility operations vore in conformance with regulatory requirements, Technical Specifica'. ions and Administrative Procedure No.16, " Conduct of Operation -
Operations Group".
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Within the areas inspected, no violations or deviations were identified.
6.
Monthly Maintenance Observation Station maintenance act1 ities of safety-related systems and components were observed / reviewed to asce ain that they were conducted in accordance with approved procedures, regu,_ tory 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 o~ tained prior to initiating the work; activities o
were accomplished using approved procedures and were inspected as appli-cable; 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 materiaI used were properly certified; radiological controls were imple-mented; and, fire prevention controls were implemented.
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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.
The following maintenance activities were observed / reviewed:
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Overhaul of 1-C diesel and the run-in testing of the diesel.
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Instrument maintenance in progress throughout the plant.
Within the areas inspected, no violations or deviations were identified.
7.
Monthly Surveillance Observation The inspector observed Technical Specification required surveillance testing and verified that testing was perfonned in accordance with adequate pro-cedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that test results met acceptance criteria require-ments 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-4.5 -
Charging Pump 1-B Annual Inservice Test.
FNP-1-2-STP-27.1 -
A. C. Source Verification FNP-1-2-STP-70.0 - Containment Sump Surveillance.
FNP-1-2-STP-9.0 -
RCS Leakage Test.
FNP-1-2-STP-33.1 - Safeguards Test Cabinet Train B Functiona'i Test.
FNP-1-2-STP-33.0 - Solid State Protection System Train B Operability Test.
FNP-1-2-3TP-63.0 - Area Temperature monitoring.
FNP-1-2-STP-7.0 -
Quadrant Power Tilt Ratio Calculation.
FNP-1-2-STP-37.0 - Power Distribution Surveillance (Plant Computer Inoperable).
FNP-1-2-STP-1-19.0 - Electric Hydrogen Recombiner 1A(B) Operability Check.
FNP-2-SOP-2.6E -
System check list - Boric Acid System.
FNP-2-S0P-50.1 -
Unit 2, Appendix 1 - Waste Monitor Tank No.1 Release to the Environment year batch. Liquid Waste Release Permit No. 2-81.203.
Within the areas inspected, no violations or deviations were identified.
8.
Unit 2 Startup Testing The inspectors witnessed portions of the following power escalation testing on all shifts and reviewed the test results and evaluations of all testing
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to date. The performance of each test was evaluated against the require-me" s of ANSI N18.7-1972 Section 6.0, " Test and Inspection Procedures,"
ANS! N45.2-1971, Section 12, " Test Control", FSAR Chapter 14, " Initial Tests and Operations", and Regulatory Guide 1.6,1.9 and 1.41.
Testing was sat'ifactory.
500-7-301 - Statepoint Data at 90% and 100% Power.
500-7-201 - RCS Flow Measurement at 100% Power.
500-7-534 - 10% - Load Swing from 100% Power.
500-7-535 - 50% Load Swing from 100% power.
500-7-536 - Turbine Trip - Reactor Trip at 100% Power.
500-7-105 - Steam Generator Moisture Carryover Test.
500-7-542 - Radio-Chemistry Survey.
500-7-050 - Radiation Survey at 100% Power.
500-7-537 - Main Generator Trip at 100% Power. The reactor trip resulted from 10-10 level in "B" steam generator.
Within the areas inspected, no violations or deviations were identified.
9.
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 di-scussions provided a daily status of plant operating and testing activities in progress as well as discussion of significant problems or incidents.
10.
Diesel Generator 1C Failure.
The inspectors observed the maintenance work performed on 1C Diesel to correct internal damage to the engine.
The damage appears to have been caused by overload tests which caused the upper wrist-pin bushing failure.
Consequently, the piston appeared to have overheated the engine sleeve resulting in 0-ring failure. This allowed the engine jacket cooling water to enter the cylinders.
Repairs were made under the supervision of the engine manufacturer representative.
Repairs included replacement of twelve cylinder liners, the vertical drive assembly, piston and new rings, and a new lower crank shaft thrust bearing. The engine was run in by an approved maintenance procedure.
The inspectors observed portions of the run-in tests. The licensee considers diesel generator 1C to be in a completely overhauled condition.
This is the second failure on this diesel generator. The failures resulted
in issuance of emergency license amendments on May 8,1981 and on July 31, 1981. The first amendment authorized a 10 day extension.
Within the areas inspected, no violations or deviations were identified.
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11.
IE Bulletin 8C-10, Contamination of Nonradioactive Systems.
The inspectors have received the licensees response and evaluation on the above subject. The inspectors reviewed each normally radioactive systems / components as to the associated potential transfer mechanisms and the potential system (s) which could be contaminated. The sampling and monitoring programs were reviewed for adequacy to assure that potential paths for contaminating nonradiot 'tive systems were monitored and sampled on a scheduled basis.
The inspector had no further questions.
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