IR 05000348/1986019

Insp Repts 50-348/86-19 & 50-364/86-19 on 860911-1010.No Violation or Deviation Noted.Major Areas Inspected:Monthly Surveillance Observation,Monthly Maint Observation, Operational Safety Verification,Lers & IE Bulletin

ML20197A903
Person / Time
Site:	Farley
Issue date:	10/21/1986
From:	Brian Bonser, Bradford W, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20197A895	List: IR 05000348/1986019 ML20197A889
References
50-348-86-19, 50-364-86-19, IEB-86-002, IEB-86-2, NUDOCS 8610270419
Download: ML20197A903 (6)

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- NUCLEAR REGULATORY COMMISSION REGION 11 g' j 101 MARIETTA STREET. * = ATLANTA. GEORGI A 30323

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Report Nos.: 50-348/86-19 and 50-364/86-19 Licensee: Alabama Power Company 600 North 18th Street Birmingham, AL 35291 Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8 Facility name: Farley 1 and 2 Inspection Conducted: September 11 - October 10, 1986 Inspection at Farley site near Dothan, Alabama Inspec ors: M /0 / /

Dats Signed W. H. Bradford

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lufzt EA Date Sfgned m_ B. R. Bonser Approved by: -/ N H. C. Danc'e,' Section Ch nf '

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Date Signed Division of Reactor Projects SUMMARY Scope: This routine, on-site inspection entailed monthly surveillance observation, monthly maintenance observation, operational safety verification, licensee event reports, and IE Bulleti Results: There were no viola'tions or deviations identifie .

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REPORT DETAILS 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 Manage 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, Operatfuns 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 R. 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 personne . Exit Interview The inspection scope and findings were summarized during management interviews throughout the report period and on October 10, 1986, with the general plant manager and selected members of his staff. The inspection findings were discussed in detai The licensee did not identify as proprietary any material reviewed by the inspector during this inspectio ; 364/86-19-01, Unresolved Item. Environmental Qualification of Limitorque Motor Operators. (Paragraph 10) Licensee Action on Previous Enforcement Matters (92702)

Not inspecte . Unresolved Items Unresolved items are matters about which more information is -required to determine whether they are acceptable or may involve violations or deviations. One unresolved item is identified in paragraph 1 '

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2 Monthly Surveillance Observation (61726)

The inspectors observed and reviewed Technical Specification required surveillance testing and verified that testing was performed in accordance with adequate procedures; that test instrumentation was calibrated; that limiting conditions were met; that test results met acceptance criteria and 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 conducting the tests were qualifie The inspector witnessed / reviewed portions of the following test activities:

ETP-1013 - Steam Generator cooldown using Auxiliary Feed Water Flow through Main Steam Lin STP-32.1 - Accumulator Check Valve Leak Tes STP-27.3 - Auxiliary Building D.C. Distributio STP-11.10 - RHR Pump Monthly Operability Tes STP-154.2 - IC Diesel Generator Air Dryer Operability Tes STP- RCS Leakag STP-11.7 - Verifying RHR Relief Valve Isolations are ope STP-29.2 - Shutdown Margin Calculation (Tavg 9 547).

STP-80.1 - Diesel Generator 18 Operability Tes STP- Full Length Control Rod Operability Tes STP-22.18 - Auxiliary Feed Water Automatic Valve Position Verificatio STP-7 Main Control Room Remote Valve Verificatio STP- Daily Shift Surveillance Requirement No violations or deviations were identifie . Monthly Maintenance Observation (62703)

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 were in conformance with Technical specification . . _ . .. _ _ _ _ _ . _

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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

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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 performed prior to

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returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and t

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:

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Replacement of Unit 1 control rod drive containment electrical penetration Radiation Monitor R-24A maintenance and calibration (Unit 2).

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Inspection of environment Qualification of certain Unit 1 motor

operated valves.

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Installation of Unit I remote disconnect switches for charging pump i

suction and discharge header cross connect valve No violations or deviations were identifie . Operational Safety Verification (71707)

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The inspectors observed control room operations, reviewed applicable logs j 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 j equipment conditions, including fluid leaks and excessive vibrations. The

inspector verified compliance with selected Limiting Conditions for

! Operations (LCO) and results of selected surveillance test 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

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occurred.

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l The inspectors routinely attended meetings with certain licensee management and observed various shift turnovers between shift supervisor, shift foremen and licensed operator These meetings and discussions provided a daily status of plant operations, maintenance, and testing activities in progress,

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The inspector verified by observation and interviews with security force members that measures taken to assure the physical protection of the facility met current requirement 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 followe No violations or deviations were identifie . Licensee Event Reports (92700)

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 appropriat 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 LCOs were no exceeded. The inspector examined selected incidents reports, logs and records and interviewed selected personnel . The following reports are considered closed:

Unit 1 LER-86-12 -

Actuation of one train of RPs while in tes LER-86-13 -

Fire watch not establishe LER-86-14 -

Inoperability of both trains of charging due to clogged oil cooler LER-86-16 -

Inoperable fire detector LER-86-17 -

Inoperable smoke detector Unit 2 LER-86-10 -

Reactor trip when both trains of SSPS received indica-tions of general warning due to a faulty secondary disconnecting contac LER-85-01 -

Upgrade affected walls to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire wall statu . IE Bulletin No. 86-02, Static "0" Ring Differential Pressure Switches (92703)

The licensee has investigated the use of static "0" ring (SOR) differential pressure switches model 102 and 103 in Farley 1 and .

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The investigation has concluded that none of these pressure switches has been installed at Farley Nuclear Plan This is documented by licensee letter dated August 8, 198 This item is close . Environmental Qualification (10 CFR 50.49) of Limitorque Motor-Operated Valves (92703)

On August 20, 1986, Region II's Atlanta based personnel contacted Alabama Power Company and the site concerning their 10 CFR 50.49 Limitorque motor-operated valves (MOVs) with regard to IEN 86-03, Potential Deficiencies in Environmental Qualification of Limitorque Motor Valve Operator Wiring. The licensee was requested to advise the Region of the action they had taken with regard to IEN 83-72, Environmental Qualification Notice No. 24, and the above IEN (86-03) and, if required, to provide a justification for continued operation (JCO). The subsequent telephone calls and their letter of August 26, 1]86, provided the JCO. The correspondence indicated that nine MOVs were evaluated by physical inspection. The unidentifiable wire, as a i result of this inspection, was replaced with known qualified wir Since there is some question involving 10 CFR 50.49 interpretation and its 1985 deadline, there is an unresolved item identified as 50-348, 364/86-19-01, Environmental Qualification of Limitorque Motor Operators.