IR 05000348/1982010
| ML20053B288 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/27/1982 |
| From: | Bradford W, Brownlee V, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053B280 | List: |
| References | |
| 50-348-82-10, 50-364-82-09, 50-364-82-9, IEB-80-04, IEB-80-05, IEB-80-12, IEB-80-18, IEB-80-4, IEB-80-5, NUDOCS 8205280252 | |
| Download: ML20053B288 (8) | |
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Luty UNITED STATES o,,
NUCLEAR REGULATORY COMMISSION c.
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REGION 11 101 MARIETTA ST., N.W., SUITE 3100 c,%
s ATLANTA, GEORGIA 30303 s
Report Nos. 50-348/82-10 and 50-364/82-09 Licensee: Alabama Power Company 600 North 18th Stret'.
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 C/!2_7!P2 hyra$t Inspectors:
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W. H. $radford, Senior Residdnt Inspector D' ate Signed UGIf&uA (~
Y/27/et
_T. A. Pdebles, Resident Inspei tor Dat'e Signed t
Approved by: [
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V. L. Brjiwnlee,' Section Chief, Division of D4t'e Sidned Project and Resident Programs SUMMARY Inspection on March 16 - April 15,1982 Areas Inspected This routine inspection involved 160 inspector-hours on site in the areas of monthly surveillance observation, monthly maintenance observation, operational
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safety verification, independent inspection effort, review of routine events, followup of plant incidents and IE Bulletin followup.
Results No violations o. Jeviations were identified.
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i DETAILS 1.
Persons Contacted i
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Licensee Employees
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W. G. Hairston, Plant Manager J. D. Woodard, Assistant Plant Manager O. Morey, Operations Superintendent
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R. S. Hill, Operations Supervisor W. D. Shipman, Maintenance Superintendent C. Nesbitt, Technical Superintendent L. Williams, Training Superintendent 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 i
R. D. Rogers, Technical Supervisor J. Odom, Operations Section Supervisor T. Esteve, Operations Section Supervisor R. Bayne, Chemistry Supervisor
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J. Thomas, I&C Supervisor
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J. Hudspeth, Document Control Supervisor K. Jones, Material Supervisor R. H. Graham, Security Supervisor L. W. Enfinger, Administrative Superintendent W. G. Ware, Superviosr, Safety Audit Engineering Review Other licensee employees contacted included technicians, operating personnel, maintenance and I&C personnel, security force members, and office personnel.
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2.
Exit Interview The inspection scope and findings were summarized during management inter-views held throughout the reporting period with the plant manager and selected members of his staff. The licensee acknowledged the inspection findings.
j 3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation 348/81-17-01 - Reactor mode change made without required equipment operable.
The inspectors have reviewed the licensee's response dated August 31, 1982 and verified that corrective action has been initiated and is appropriate. The inspectors had no further questions.
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b.
(Closed) Violation 348/81-29-01 - Failure to follow procedures. The inspectors have reviewed the licensee's corrective action and response to the violation.
The corrective action has been verifed to be appropriate. The inspectors had no further questions.
c.
(Closed) Violation 348/82-03-01 - Containment spray nozzles not installed in accordance with design drawings.
The inspectors have reviewed the licensee's response and corrective action. The corrective action is considered to be appropriate. The inspectors had no further questions.
d.
(Closed) Violation 364/81-20-01 - Reactor mode change made without required equipment operable.
The inspectors have reviewed the
, licensee's response and have verified that corrective action has been initiated and is appropriate. The inspectors had no further questions.
e.
(Closed) Violation 364/81-32-01 - Violation of Technical Specification,
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Diesel Generator inoperable.
The inspectors have reviewed the i
licensee's response and verified the corrective action to be appro-priate. The inspectors had no further questions.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Monthly Surveillance Observation The inspectors 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-2-STP-23.11
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Component Cooling Water Pump 2C monthly operational check.
FNP-1-STP-109.0
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Power Range Neutron Flux Chnnel Calibration.
FNP-2-STP-27.1
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A. C. source verification.
l FNP-2-STP-70.0
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Containment Sump Surveillance.
l FNP-2-STP-9.0
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RCS Leakage Test.
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FNP-2-STP-27.3 Auxiliary and Service Water Building D.C.
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Distribution.
FNP-2-STP-27.2
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Onsite A.C. Distribution.
l FNP-1-2-STP-1.0
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Operation Daily and Shift Surveillance Requirements - Modes 1, 2, 3, and 4.
FNP-0-STP-26.3 Control Room Ventilation Isolation Test.
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FNP-1-STP-16.5
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Containment Spray System Flow Path Verification.
FNP-1-STP-5.0
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Full Length Rod Operability Test.
FNP-1-STP-610.1
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Hydraulic Snubber Functional Test.
FNP-1-STP-607.0 Containment Airlock Interlock Test.
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Within the areas inspected there were no violations or deviations identi-fied.
6.
Monthly Maintenance Observation Station maintenance activities of safety-related systems and components were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, 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
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service; approvals were obtained prior to initiating the work; activities were accomplished during approved procedures and were inspected as appli-
l cable; functional testing and/or calibrations were performed prior to l
returning components or systems to service; quality control records were l
maintained; activities were accomplished by qualified personnel; parts and materials were properly certified; radiological controls were implemented; and fire prevention 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.
i The following maintenance activities were observed / reviewed:
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a.
2-C Charging Pump 011 Cooler Cleaning and Inspection.
b.
2-C Diesel Generator Starting Air Compressor.
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c.
Unit 1 Reactor Coolant System Filter Change Out.
d.
2-B Diesel Generator "A" Air Compressor.
e.
Service Water "B" Train Strainer Auto Blow Down Valve.
f.
2-C Diesel Generator Day Tank Level Indication.
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lA BIT Recirculation Pump.
h.
lA RHR Pump Seal Water Heat Exchanger Component Cooling Water PRV Body / Bonnet Leak.
1.
125V. D. C. Grounds in Auxiliary and Turbine Building.
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Various Instrument Calibration and Repair Throughout the Plant.
Within the areas inspected there were no violations or deviations identi-fied.
i 7.
Operational Safety Verification The inspectors observed control room operations, reviewed applicable logs i
and conducted discussions with control room operators during the report 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, turbine building and
containment were conducted to observe plant equipment conditions, including
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potential fire hazards, fluid leaks, and excessive vibrations. The inspec-tors verified, by observation and direct interviews 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:
a.
Unit 2 Condensate and Feedwater System.
b.
Units 1 and 2 Auxiliary Feed Water Systems.
c.
Service Water Systems - Units 1 and 2.
d.
Units 1 and 2 Charging / Safety Injection Suction.
e.
Diesel Generators Starting Air and Jacket Cooling Water.
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f.
Station Electrical Boards in the Control Room and various parts of the plant for proper electrical line up.
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Portions of various other systems (safety-related and non-safety-related) were observed for proper line up and proper operation during various plant tours during the report period.
Within the areas inspected, there were no violations or deviations
identified.
8.
Independent Inspection Effort
The inspectors routinely attended meetings with certain licensee management
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and observed 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.
During the reporting period the inspectors expressed concern.to the licensee about licensee vehicle traffic in and around the station transformers. The possibility of damage by vehicles which could cause loss of offsite power to the station was discussed. The licensee performed a review of the trans-
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former yard and has initiated corrective action by constructing a fence at
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the end of the transformer yard.
The inspectors had no further questions.
9.
Followup of Plant Incidents During the reporting period the inspectors conducted followup inspections of the following incidents at the facility:
a.
Unit 2 reactor tripped on March 30, 1982 at 0207 hours0.0024 days <br />0.0575 hours <br />3.422619e-4 weeks <br />7.87635e-5 months <br /> due to a steam generator feed pump turbine trip.
The reactor tripped on low steam generator level. The trip occurred in conjunction with testing of the
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emergency 125V 0.
C. oil pump.
Reactor safety systems were not actuated.
The licensee has not determined the cause of the steam generator feed pump turbine trip.
i b.
On May 13,1982 at 10:17 a.m. Units 1 and 2 were tripped simultaneously i
from 100*4 power when Alabama Power Company System Protection personnel were functionally testing the trip circuit for a newly installed breaker (#830) located in the high voltage distribution switch yard.
i Testing was being performed under Production Change Notice (PCN)80-662. A personnel error occurred when jumpers were placed in the trip circuit to existing feeder breakers to 18 and 28 start-up trans-
formers. Unit 1 trip was due to denergizing startup transformer IB and
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the loss of reactor coolant pumps 18 and IC.
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Unit 2 trip was due to denergizing startup transformer 2B and the loss of reactor coolant pump 2A.
The required diesel generators started and all systems functioned as as designed. Safety injection systems were not initiated.
The inspector reviewed the circumstances involved in each incident and, where appropriate, the actions taken by licensee management in response to the incident. The licensee's management action appeared to be timely and adequate in each case.
10.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on informa-tion presented in the bulletin and the licensee's response, that licensee management forwarded copies of the written rosponse to the app opriate onsite management representatives, that information discussed in the licensee's written response was accurate, and the corrective action taken by the licensee was as described in the written response.
80-80-04 Analysis of a PWR Main Steam Line Break with Continuous Feedwater Addition 80-8U-05 Vacuum Condition in Chemical and Volume Control Systems 80-BU-12 Decay Heat Removal System Operability 80-BU-18 Maintenance of Adequate Minimum Flow thru Centrifugal Charging Pumps 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 were reviewed to verify that the event had been 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 setting, and limiting conditions of operation were not exceeded. The inspector examined selected Plant Opera-tions Review Committee minutes, incidents reports, log 3 - and records, and interviewed selected personnel.
Unit 1 LER's 81-29 Fire Main ruptured in low voltage switchyard.
82-02 Containment Gas Activity Monitor inoperable due to flow fault.
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82-03 Containment Personnel Airlock interlock inoperable.
82-04 Seven unsealed fire barrier penetrations inoperable.
82-05 Control Room Ventilation inoperable.
82-06 Fire Protection Tanks below allowable level.
Unit 2 LER's 82-06 Component Cooling Water system trains cross-connected.
82-07
'2C' Accumulatory below minimum boron concentration.
82-08
'28' Steam Generator Level Indication inoperable.
82-09
'2A' Main Feedwater Flow Indication inoperable.
82-10
'2A' Steam Generator Level inoperable.