IR 05000348/1987005
| ML20205Q314 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/19/1987 |
| From: | Brian Bonser, Bradford W, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205Q284 | List: |
| References | |
| 50-348-87-05, 50-348-87-5, 50-364-87-05, 50-364-87-5, NUDOCS 8704030492 | |
| Download: ML20205Q314 (5) | |
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UNITED ST ATES
/pm K80g##o, NUCLEAR REGULATORY COMMISSION
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Report Nos.:
50-348/87-05 and 50-364/87-05 Licensee: Alabama Power Company i
600 North 18th Street
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Birmingham, AL 35291-0400 r
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Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8 Facility Name:
Farley 1 and 2 j
Inspection Conducted:
February 11 - March 10, 1987 Inspection at Farley site near Dothan, Alabama
/k Inspectors:/
AMA J
l W. H. Bradfo Date 41gned
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Approved by: -
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/H. C. Dance, 'Section Chief Odte' Signed
Division of Reactor Projects
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SUMMARY Scope:
This routine, onsite inspection entailed, montly surveillance observation, monthly maintenance observation, operational safety verification, follow up of plant events, diesel generators, and 10 CFR Part 21 Report.
Results: No violations or deviations were identified.
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i 5704030492 B70320
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PDR ADOCK 05000348 O
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1EPORT DETAILS
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Lictnsee Employees Contacted:
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J. D. W3odard, General Plant Managnr
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O. H. Morey, Assistant Cene nl Plant Manager
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W. D. Shipman, Assistant Gen wal Plant Manager
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R. D. Hill, Operations Manaser C
0. Fesbitt, Technic 41 Manager R. G. Berryhill, Systems Performance and Pla nirs Manager
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L. A. Nard, Maintenarce Marager
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t. W. Enfinger, Administretwe Manager
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8. Pocre, Operations Superd sor J. E. Odom,. Operations Un*3 Supervicor B. W. Vinlandingham, Opehtions Unit Supervisor
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T. H. Estev4, Plannir.g St>perviser
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J. B. Hudspeth, Doevient Contml Supird sor
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L. K. Jor.es, Materia s Supervi or
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R. H. Marlow, Technical Superd sor
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L. M. Stir son, Plant Modificatirin Minager J. K. Osterholtz, Supervisar, Safety Audit 2t,gineerinq Review f<-
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Other l i cen.6.ee employees contated incluelej technicians, operations'
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personr:e 7 - :tair:ty nanct and I&C ptrsonnel,,decurity force terrbers, ird
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Exit Interview f
The insiectio1, scope ar.d findings were summarized dNring management interviews throughout the repn-t period and on February 9, 1937, wit!. the general plant managt r and wi6cted members' of bh staff. The 'aspection findings we*e ciscussed in jetail. The licensee did not i.ienti fy as proprietary any mi,tertti reviewed by(the inroect1r'Juring this inspection.
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Licensee Action on Prevfous Enfc. v m Mat +.ars (92702)
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Monthly S', ryeillance ObservatiQn (61726)
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The inspactors observed arni re)teAd Technical Spectficatter required
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surveil unce testing and varifie6 t5tt testing was perftsrmed in accordany.1
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with at.' equate procedir9s; f.5.nt test. Instrummtation was calibrated; that Ilmiting'conditiont. + ire m t; t.'a t test reMis met acceptance criteria and were riviewed by personnel other then the individual directing the
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test; that any deficiencies identified during the testing were properly
.t reviewed 3 and resolved by appropriate management personnel; and that personnel conducting the tests were qualified.
The inspector
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witnessed / reviewed portions of the following test activities:
Operations Daily and Shift Surveillance Requirements STP-1.0
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STP-71.0 - Main Control Room Remote Valve Verification Motor Operated Valve Power Isolation Verification
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STP-22.18 - Auxiliary Feed Automatic Valve Verification
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f, RCS Leakage STP-9.0
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STP-33.1A - Safeguards Test Cabinet Train "A" Functional. Test
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Diesel Generator 18 Operability Test i STP-80.1
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Diesel Generator 28 Operability Test STP-80.2
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STP-228.4 - Nuclear Instrumentation System Intermediate Range
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Channel N36 Calibration and Functional Test No violations or deviations were identified.
Monthly Maintenance Observation (62703)
Station maintenance activities of safety-related systems and components were observed / reviewed to ascertain that they were conducted in accordance
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with approved procedures, regulatory guides, industry codes and standards, and were in conformance with Technical specifications.
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The following items were considered during the review:
limiting conditions for operations 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 porformed prior to returning components or systems to service; quality control records were 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 was assigned to safety-related equipment maintenance which may affect system performance. The following maintenance activities were observed / reviewed:
Diesel generator keep warm lube oil pumps Diesel generator 1B and 2B lube oil filters system
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IC diesel generator day tank level indicator 4160V to 600V: Breaker PM's
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Unit 2 boric acid tank level indicator TDAFP steam admission and steam warm up valves
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Motor operated auxiliary feed water pump check valves
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s Unit 2 steam generator blowdown system s
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The auxiliary feedwater system check valves on Unit 2, suppling auxiliary feedwater to 2A and 2C steam generators, are not seating properly and allow leak back of high temperature water into the discharge piping of the auxiliary feed water pumps. This necessitates the operation of the motor driven and turbine driven auxiliary feed pumps to pump cool water from the condensate storage tank into the steam generators to cool the discharge piping. This operation is required about every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
The licensee has disassembled these check valves on several occasions with the Anchor-Darlin valves manufacture's representative present in order to determine the cause of the leakage. The check valves in Unit 1 and Unit 2 have undergone modifications in an attempt to improve the valve operation.
The licensee is considering changing the check valves from the swing disc type to plug type check valves.
The inspectors will continue to follow this work (IFI 348/364/87-05-1).
The inspectors continued to review maintenance activities of equipment that lead to a plant shutdown or a reduced capability of a safety related system.
No violations or deviations were identified.
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Operational Safety Verification (71707)
The inspectors observed control room operators, reviewed applicable logs and conducted discussions with control room operations 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 building, diesel building, turbine building and service water structure were conducted to observe plant equipment conditions, including fluid leaks and excessive vibrations. The inspector verified compliance with selected Limiting Conditions for Operations (LCO) and results of selected surveillance tests.
The verifications were accomplished by direct observation of monitoring instrumentation, valve positions, switch positions, Jaccessible hydraulic snubbers, and review of completed logs, records, and chemistry results.
The licensee's compliance with LC0 action statements were reviewed as events occurred.
The inspectors routinely attended meetings with certain licensee management and observed various shift turnovers between shift supervisor, shift foremen and licensed operators.
These meetings and discussions provided a daily status of plant operations, maintenance, and testing activities in progress, as well as discussions of significant problems.
The inspector verified by observation and interviews with security force members that measures taken to assure the physical protection of the facility met current requirements.
Areas inspected included the organization of the security force; the establishment and maintenance of
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gates, doors, and isolation zones; that access control and badging were proper; and procedures were followe.
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No violations or deviations were identified.
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Follow up of Plant Events (92702)
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28,1987 at 3:26 p.m. Unit 2 tripped from 100% power on an On February overtemperature (OT) delta T trip signal.
The reactor trip occurred during calibration of loop 3 overpressure and OT delta T.
Channel 3 of overtemperature delta T was already tripped for the surveillance test when an electrical transient tripped channel 1 OT delta T.
The cause of the electrical transient was an apparent failure in a lead-lag card.
Reactor Trip System Interlock P-6 did not re energize the source range instruments following the trip; the source range instruments were manually energized. The engineered safeguards systems were not challenged. The channel 3 OT delta T was returned to service, the channel one Tavg was verified to be operating properly and the unit returned to' power operations on March 1, 1987.
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Colt Industries 10 CFR Part 21 Report The 10 CFR Part 21 states that a possible malfunction of the thermostatic valves on diesel generators 1-2A,1-B, and 2-8 could cause the valve to fail to the full cooling position.
These valves are supplied by Robertshaw valves. The inspectors verified that these valves have been replaced with overrun assemblies which utilize cotter pins to positively lock the nut to the stem. The units are now free of the defect. The work is documented on Maintenance Work Request (MWR's No 51772, 51773, 66412, 66413, 66414 and 66415. The inspectors had no further questions.
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