IR 05000348/1986017
| ML20210L529 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/19/1986 |
| From: | Brian Bonser, Bradford W, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210L525 | List: |
| References | |
| 50-348-86-17, 50-368-86-17, NUDOCS 8610020077 | |
| Download: ML20210L529 (6) | |
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l pm400 UNITED STATES
9'o NUCLEAR REGULATORY COMMISSION
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j 101 MARIETTA STREET, N.W.
ATLANTA, GEORGI A 30323
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Report Nos.: 50-348/86-17 and 50-364/86-17 Licensee: Alabama Power Company 600 North 18th Street Birmingham, AL 35291
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Docket Nos.:
50-348 and 50-364 License Nos.:
NPF-2 and NPF-8 Facility Name: Farley 1 and 2 Inspection Conducted: August 11 - September 10, 1986 Inspection at Farley site near Dothan, Alabama Inspectors:
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W. H. Bradford Date 51gned
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B'. R Bonser
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5 Approved by:_. C. Dance,'Section Chief Dafte Signed
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Division of Reactor Projects SUMMARY Scope:
This routine, onsite inspection entailed, monthly surveillance observation, monthly maintenance observation, operational safety verification, licensee event reports, and engineered safety feature system, Results: No violations or deviations were identified.
I 8610020077 860919 PDR ADOCK 05000348
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REPORT DETAILS 1.
Licensee Employees Contacted:
J. D. Woodard, General Plant Manager D. N. Morey, Assistant General Plant Manager W. D. Shipman, Assistant General Plant Manager R. D. Hill, Operations Manager C. D. Nesbitt, Technical Manager R. G. Berryhill, Systems Performance and Planning Manager L. A. Ward, Maintenance Manager L. W. Enfinger, Administrative Manager B. Moore, Operations Supervisor J. E. Odom, Operations Unit Supervisor B. W. Vanlandingham, Operations Unit Supervisor T. H. Esteve, Planning Supervisor J. B. Hudspeth, Document Control Supervisor L. K. Jones, Material Supervisor W. H. Marlow, Technical Supervisor L. M. Stinson, Plant Modification Manager J. K. Osterholtz, Supervisor, Safety Audit Engineering Review Other licensee employees contacted included technicians, operations personnel, maintenance and I&C personnel, security force members, and office personnel.
2.
Exit Interview The inspection scope and findings were summarized during management interviews throughout the report period and on September 10, 1986, with the general plant manager and selected members of his staff.
The inspection findings were discussed in detail.
The licensee did not identify as proprietary any material reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters (92702)
(Closed) Violation (348/86-10-01), Inoperable ECCS subsystem - RHR suction valve closed.
Based on the licensee's corrective action described in a letter of response to the violation, dated August 14, 1986, and an inspection of the corrective action, this item is closed.
(Closed) Violation (364/86-10-01), Failure to follow procedures, flammable material stored in hot machine shop.
Based on the licensee's corrective action described in a letter of response to the violation dated August 14, 1986 and an inspection of the corrective action, this item is close _.
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I (Closed) Violation (364/86-11-02), Fire damper could not fulfill its intended functicn.
Based on the licensee's corrective action described in a letter of response to the violation dated August 5,1986 and an inspection of the corrective action, this item is closed.
4.
Monthly Surveillance Observation (61726)
The inspectors observed and reviewed Technical Specifications required surveillance testing and verified that testing was performed in accordance with adequate procedures; that test instrumentation was calibrated; that
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limiting conditions were met; that test results met acceptance criteria and i
were reviewed by personnel other than the individual directing the test; that any deficiencies identified during the' testing were properly reviewed and resolved by appropriate management personnel; and that personnel
i conducting the tests were qualified.
The inspector witnessed / reviewed
portions of the following test activities:
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STP 20.0 Penetration Room Filtration Operability.
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STP 22.1 - Auxiliary Feedwater Pump 1A Inservice Test.
STP 26.0 - B Train Control Room Ventilation Operability Test.
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STP 7.0
- Quadrant Power Tilt Ratio Calculation.
STP 23.10 - B Component Cooling Water Pump Monthly Operability Check.
STP 22.0A
. Reactor Trip Breaker Train A Operability Test.
STP 80.1 Diesel Generator 2B Operability Test.
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STP 1.0 Daily Shift Surveillance. Requirements.
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STP 71.0 Main Control Room Remote Valve Verification.
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No violations or deviations were identified.
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5.
Monthly Maintenance Observation (62703)
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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, industry codes and standards, and
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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 i
service; approvals were obtained prior to initiating the work; activities i
were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to
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returning components or systems to service; quality control records were s
maintained; activities were accomplished by qualified personnel; parts and
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materials were properly certified; radiological controls were implemented;
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and fire prevention controls were implemented. Work requests were reviewed to determine the status of outstanding jobs to assure that priority was
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assigned to safety-related equipment maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
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28 Diesel Generator outage maintenance Charging pump gear oil heat exchanger cleaning and flushing Parts replacement and flow monitoring of motor driven fire pump Replacement of 1A Service Water Pump Preventative Maintenance of 1C Diesel Generator No violations or deviat*ons were identified.
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6.
Operational Safety Verification (71707)
The inspectors observed control room operations, reviewed applicable logs
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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 Mere conducted to obrerve plant equipment conditions, including fluid leaks and excessive vibratio.7s.
The inspector verified compliance with selected Limiting Conditions for Operations (LC0) and results of selected surveillance tests.
The verifications were accomplished by direct observation of monitoring instrumentation, valve positions, switch positions, accessible 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 gates, doors, and isolation zones; that access control and badging were proper; and procedures were followed.
No violations or deviations were identified.
7.
Licensee Event Reports The following Licensee Event Reports (LERs) were reviewed for potential generic problems to determine trends, to determine whether 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 events had been reviewed and evaluated by the licensee as required by the Technical Specifications (TS); that corrective action was taken by
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the licensee; and that safety-limits, limiting safety setting and LCOs were not exceeded.
The inspector examined selected incidents reports, logs and records and interviewed selected personnel.
The following reports are considered closed:
Unit 1 LER 86-03 - Inadequate design calculation for Cycle 7 reload LER 86-04 Short in containment penetration module causes reactor trip
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LER 86-05 - Fuel rod uranium weights exceeded TS limit LER 86-06 Residual heat removal system inoperable due to personnel error
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LER 86-07 - Reactor trip caused by deteriorated diaphragm on the main turbine interface valve LER 86-08 Short in containment penetration module causes reactor trip
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Failure to follow procedure results in actuation of-LER 86-09
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penetration room filtration system Unit 2 LER 86-01 Reactor trip due to loss of both steam generator feed pumps
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LER 86-03 2A containment spray pump inoperable due to defective
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microswitch in breaker.
LER 86-04 - Steam generator tube degradation.
LER 86-05 - Reactor trip while performing trip testing on the main turbine.
LER 86-07 Unit shutdown due to losing one train of charging.
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8.
Engineered Safety Feature System Walkdown (71710)
The inspectors performed various system inspections during the inspection period.
Overall plant conditions.were assessed with particular attention to equipment condition, radiological controls, security, safety, adherence to technical specification requirements, systems valve alignment, and locked j
valve verification.
Major components were checked for leakage and any i
general conditions that would degrade performance or prevent fulfillment of functional requirements.
The inspectors verified that approved procedures and up-to-date drawings were used.
Portions of.the following systems were observed for proper operation, valve alignment and valve verification:
Auxiliary feedwater systems.
l Chemical volume control systems.
Service water systems.
Boric acid transfer system.
Containment spray system including chemical addit;ve system.
Residual heat removal system.
The inspector verified the operability of the Control Room Ventilation (CRV)
System by performing a complete inspection of the accessible portions of the system.
The inspector verified the positions of dampers, operability of
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local and remote instrumentation where possible, the condition of equipment and compared the licensee's system checklist with system drawings and actual position of dampers.
The inspector also examined the CRV system for conformance with~ the FSAR, Technical Specifications, and system design requirements.
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No violations or deviations were identified.
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