UNITED STATES'

o,,8 NUCLEAR REGULATORY COMMISSIONo

[ E REGION 118 101 MARIETTA ST., N.W., SUITE 3100Q

ATLANTA, GEORGIA 30303% s

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Report Nos. 50-348/82-06 and 50-364/82-05

Licensee: ' Alabama Power Company600 North 18th StreetBirmingham, AL 35202

Facility Name: Farley Nuclear Plant

Docket Nos. 50-348 and 50-364

License Nos. NPF-2 and NPF-8

Inspection at Fa ley si e n ar Dothan, Alabama

Inspectors: / lf or, EW b C T'LH Bfad esident Intpector _Ddte/ Signed

W.b ' ord, Seniors 0> m, F Rk/ru/ -aTTA.feebles,Resdent.Insp t6r Ifate' Signed

Approved by: MIf// 'M // NC[fLC L.~ qpbwnlee, Section Chief, Division of ITate' Signed

Project and Resident Programs

SUMMARY

| Inspection on January 16 - February 15, 1982

Areas Inspected

| This routine inspection involved 130 inspector-hours on ' site in the areas of| monthly surveillance observation, monthly maintenance observation, operational'

safety verification, Unit 2 outage, independent inspection effort, review ofroutine events and THI Action Items.

| Resul ts

No violations or deviations were identified.|t

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8204010465 820308PDR ADOCK 05000348G PDR

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DETAILS

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1. Persons Contacted

| Licensee Employees

W. G. Hairston, Plant ManagerJ. D. Woodard, Assistant Plant' ManagerD. tiorey, Operations SuperintendentR. S. Hill, Operations SupervisorW. D. Shipman, Maintenance SuperintendentC. Nesbitt, Technical Superintendent i

L. Williams, Training SuperintendentR. G. Berryhill, Systems Performance and Planning SuperintendentL. A. Ward, Planning SupervisorW. C. -Carr, Chemistry and Health Physics SupervisorM. W. Mitchell, Health Physics SupervisorR. D. Rogers, Technical SupervisorJ. Odom, Operations Section SupervisorT. Esteve, Operations Section SupervisorR. Bayne, Chemistry SupervisorJ. Thomas, I&C SupervisorJ. Hudspeth, Document Control SupervisorK. Jones, Material SupervisorR. H. Graham, Security SupervisorL. W. Enfinger, Administrative Superintendent

Other licensee employees contacted included technicians, operatingpersonnel, maintenance and I&C personnel, security force members, and officepersonnel .'

2. Exit Interview

The inspection scope and findings were summarized during management.interviews held throughout the reporting period with the plant manager andselected members of his staff. The licensee acknowledged the inspectionfindings.

3. Licensee Action on Previous Inspection Findings

Not inspccted.

4. Unresolved Items

Unresolved items were not identified during this inspection.

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5. Monthly Surveillance Observation

The inspectors observed Technical Specification required surveillancetesting and verified that testing was perfonned in accordance with adequateprocedures, that test instrumentation was calibrated, that limitingconditions for operation were met, that test results met acceptance criteriarequirements and were reviewed by personnel other than the individualdirecting the test, and that any deficiencies identified during the testingwere properly reviewed and resolved by appropriate management personnel.

The inspector witnessed / reviewed portions of the following test activities:

FNP-1-STP-51.0 - Fire Protection Water Storage

FNP-1-STP-29.2 - Shutdown Margin Calculation

FNP-1-STP-11.6 - Residual Heat Removal Valves Inservice Test

FHP-1-STP-45.0 Refueling Valve Inservice Test-

FNP-1-SOP-1.3 RCS Filling and Venting-

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FNP-1-S0P-24/0A - System Check List - Service Water System

FNP-1-S0P-56.0A - Control Room HVAC System

FNP-1-S0P-364A - 120 volt AC Instrumentation and Control DistributionSystem

FNP-2-50P-1.3 RCS Filling and Venting-

FNP-2-STP-45.1 Cold Shutdown Valves Inservice Test-

FNP-2-S0P-50.0A Reactor Coolant Drain Collection and Discharge-

System

FNP-2-SOP-21.0A Condensate and Feed Water System - Main Steam-

valve room

FNP-2-SOP-17.0A Main Steam-

Unit No. 2 Local Reak Rate Testing

Within the areas inspected there were no violations or deviations identi-fled.

6. Monthly Maintenance Observation

Station maintenance activities of safety-related systems and components wereobserved / reviewed to ascertain that they were conducted in accordance with

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approved procedures, regulatory guides and industry codes or standards andin conformance with Technical Specifications.

The following items were considered during this review: limiting conditions

for operation were met while components or systems were re,noved fromservice; approvals were obtained prior to initiating the work; activitieswere accomplished during approved procedures and were inspected as eppli-cable; functional testing and/or calibrations were performed prior toreturning components or systems to service; quality control records weremaintained; activities were accomplished by qualified personnel; parts andmaterials were properly certified; radiological controls were implemented;and fire prevention controls were implemented.

Work requests were reviewed to determine the status of outstanding jobs toassure that priority is assigned to safety-related equipment maintenancewhich may affect system performance.

The following maintenance activities were observed / reviewed:

a. Unit 1 main electrical generator repair.

b. Various instrument calibration and repair throughout the plants.

c. 2A Reactor Coolant pump seal replacement.

d. Unit 1 accessible and inaccessible snubber inspection.

e. Unit 1-C Reactor Coolant pump seal maintenance.

f. Unit 2-D containment cooler fan motor replacement.

g. 2-B Diesel Generator preventative maintenance.

h. Unit 2 pressurizer power operated relief valve 444B maintenance.

i. Unit 1 RTD cold leg maintenance.

J. PCN-80-755 Environmental Qualifications of NAMC0 limit switches onvalves in main steam room.

Within the areas inspected there were no violations or deviationsidentified.

7. Operational Safety Verification

The inspectors observed control room operations, reviewed applicable logsand conducted _ discussions with control room operators during the report'

period. The inspectors verified the operability of selected emergencysystems, reviewed tagout records and verified proper return to service ofaffected components. Tours of the auxiliary, diesel, turbine building andcontainment were conducted to observe plant equipment conditions, including

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potential fire hazards, fluid leaks, and excessive vibrations. Theinspectcrs by observation and direct interviews verified that the physicalsecurity plan was being implemented in accordance with the station securityplan.

The inspectors observed plant housekeeping / cleanliness conditions andverified implementation of radiation protection control. The inspectorswalked down accessible portions of the following safety-related systems onUnits 1 and 2 to verify operability and proper valve alignment:

a. Units 1 and 2 service water system.

b. Unit 2 auxiliary feedwater system.

c. Unit 1 and 2 component cooling.

d. Unit 2 Hi head safety injection.

e. Unit 2 RHR/Lo head safety injection.

f. Unit 2 charging / safety injection suction.

Within the areas inspected, there were no violations or deviationsidentified.

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8. Unit No. 2 Outage

On January 30, at 7:40 a.m. the number one seal leakoff on reactor coolantpump 2A increased to 4.1 gpm. The licensee reduced unit load from 100% to50% in anticipation of removing the unit from service. On January 31, 1982at 8:45 a.m. No. I seal leakoff increased to 5 gpm. The number 2 seal wasplaced in service and the unit was removed from service. Reactor coolantpump 2A was secured at 9:00 a.m. The licensee and Westinghouse Corporationare investigating the cause of the seal failure.

9. Independent Inspection Effort

The inspectors routinely attended meetings with certain licensee managementand observed various shift turnovers between shift supervisors, shiftforeman and licensed operators during the reporting period. These meetingsand discussions provided a daily status of plant operating and testingactivities in progress as well as discussion of significant problems orincidents.

10. Review of Nonroutine Events Reported by the Licensee

The following licensee events reports were reviewed for potential genericproblems, to determine trends, to determine whether the information includedin the report meets the' NRC reporting requirements, and to con:ider whetherthe corrective action discussed in the report appears appropriate. Licenseeaction with respect to selected reports were reviewed to verify that the

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event had been reviewed and evaluated by the licensee as required by theTechnical Specification, that corrective action was taken by the licensee,and that safety limits, limiting safety setting, and limiting conditions ofoperation were not exceeded. The inspector examined selected PlantOperations Review Committee minutes, incidents reports, logs and records,and interviewed selected personnel.

Unit 1 LER's

81-37 Volume Control Tank Control System Inadequate

81-70 Fire Protection Tank Level Low

81-71 Fire Barrier Inoperable

81-73 Shutdown 11argin Calculation Late

81-74 Containment Purge Radiation lionitor not Isolated

81-75 Fuel Storage Pool Radiation Monitor Operable

| Unit 2 LER's

81-38 Diesel Generator 2B Inoperable

81-46 Control Room Ventilation Test flot Performed

81-47 2B Steam Generator Pressure Loop Inoperable,

81-48 Plant Stack Effluent lionitor inoperable

81-49 Diesel Generator 2B Sequencers Inoperable

81-50 Penetration Room "A" Filtration Inoperable

81-51 Overtemperature - T Instrument Loop Inoperable

81-52 Control Room "A" Chlorine Detector Inoperable

81-54 River Water Pump Train Without Emergency Power

81-55 28 Recombiner Oxygen Inlet Analyzer Inoperable

81-57 "A" Train BIT Heat Tracing Inoperable

81-58 Snubber Inoperable

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82-01 "A" Chlorine Detector Inoperable

82-02 Main Feedwater Flow Sensing Lines Frozen Inoperable

82-03 Refueling Water Storage Tank Level Frozen Inoperable !

82-04 Main Steam Line Pressure Sensing Lines FrozenInoperable

11. TMI Action Items

The following TMI Action Items have been reviewed and verified to becompleted: ,

Unit 1 Unit 2

I.A.1.3 2.A 80-41C Minimum Shift Crew

II.B.1 2 2 Install Reactor Coolant System Vents

II.F.1 1.B.2 2.A Noble Gas Monitor ;

2.B.2 2.B. Iodine / Particulate Sampling

3 2.C. Containment High Range RadiationMonitors

4 80-41C Containment Pressure Montior

5 2.E. Containment Water Level Monitor

6 2.F. Containment Hydrogen Montf or

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