ML20236M809

Insp Repts 50-348/87-24 & 50-364/87-24 on 870910-1009. Violations Noted.Major Areas Inspected:Previous Enforcement Matters,Surveillance Observation,Monthly Maint Observation & Operational Safety Verification

ML20236M809
Person / Time
Site:	Farley
Issue date:	10/28/1987
From:	Bradford W, Dance H, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20236M799	List: ML20236M797 ML20236M801 ML20236M809
References
50-348-87-24, 50-364-87-24, NUDOCS 8711130294
Download: ML20236M809 (7)

See also: IR 05000348/1987024

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sn prosj UNITED STATES

NUCLEAR REGULATORY COMMISSION

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j 101 MARIETTA STREET, N.W.

• ATLANTA, GEORGI A 30323

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I Report'Nos.:- 50-348/87-24 and 50-364/87-24-

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

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Inspection ~ Conducted: September 10~through October 9, 1987

- Inspection at Farley site near Dothan, Alabama

Inspectors: b W I 7

/Da e'Si ned

~Wl-H. Bra ord

~0 Ck<A ld y S' T 1

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, . H. Mille- /Dat Signed.

- Approved by: C /0 27 7 .

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H.'C. Dance, Section Chief Dhte Signed

' Division of Reactor Projects

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, SUMMARY

Scope: This routine, on-site' inspection involved a review of: previous

enforcement matters, surveillance ob.tervation, monthly maintenance observation,

operational safety. verification.

Results: Within the areas examined, one procedure violation was identified

.(Fire watch on roof of Auxiliary Building was not Attentive to duty.)

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8711130294 871029

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G ADOCK 05000348

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REPORT DETAILS

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1. Licensee Employees Contacted:

J. D. Woodard, General Plant Manager

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D. N. Morey, Assistant General Plant Manager

l 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

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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. 0sterholtz, Supervisor, Safety Audit Engineering Review

l Other licensee employees contacted included technicians, operations

l 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

interviews throughout the report period and on October 9,1987, with the

general plant manager and selected members of his staff. The inspection

findings were discussed in detail. The licensee acknowledged the inspec-

tion findings and did not identify as proprietary any material reviewed by

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the inspector during this inspection.

3. Licensee Action on Previous Enforcement Matters (92702)

a. (Closed) Violation (348/87-10-01), Failure to follow approved

L procedures by the Operator at the controls (0ATC) leaving Unit 1

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control board unattended for approximately 20 seconds. The licensed

Shift supervisor assumed the 0ATC without proper notification. The

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licensee's letter of response dated June 30, 1987 details the

l licensee's corrective action. The inspectors have reviewed this

corrective action and verified that licensed operators' duties in

the control room have been redefined and strengthened,

b. (Closed) Violation (348-364/87-13-01), Failure to restore unit 1B RHR

room cooler to service following maintenance activities in accordance

with approved procedures. The licensee's letter of response dated

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June 28, 1987, details the licensee's corrective action. The t

inspectors have' reviewed the corrective action and verified the

licensee has placed a high level of emphasis on following approved

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procedures.

4. Operational Safety Verification

a.. Plant Operations Review (71707)

The inspectors observed control room operations, reviewed applicable

logs and conducted discussions with control room operators during the

report period. The inspectors verified the operability of selected

emergency .syrtems, proper return to service of affected components

and reviewed tagout records. Tours of the auxiliary building, diesel

building, turbine building and service water structure were con-

ducted to _ observe plant equipment conditions, including fluid leaks

and excessive vibrations and general housekeeping efforts. 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 signi- I

ficant problems.

On September 17, 1987, at approximately 10:15 a.m. during a tour of

the auxiliary building the inspector observed repairs being performed i

by five contractor personnel on the roof of the auxiliary building.

This work consisted of removing portions of the old tar and gravel

roof surface and installation of a fiberglass mat material (0 wens

Corning "Bidium") to the roof surface. This material was being

adhered to the roof by heat from an open flame supplied from portable ,

LP gas cylinders. The contractor's personnel were not provided with

plant access badges. Therefore, an escort was assigned to meet the

licensee's security program requirements. To meet the licensee's

fire protection program requirements a continuous fire watch was

assigned to observe the operations and to be alert to any fire or

fire prevention hazards. However, the fire watch was stationed

approximately 75 feet from the operations and could not observe the

work area due to piping and equipment located between the work area

and the fire watch. This arrangement did not conform to the

requirement of plant procedures FNP-0-AP-38, Use of Open Flame and

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FNP-0-AP-39, Fire Patrols and Watches, which require a contentious

fire watch to be assigned to observe the fire hazardous operations

and areas, and to be able to continuously detect a fire in any part

of the affected area. The failure to maintain an fire watch for

this open flame operation is identified as

Violation 348,364/87-24-01,

b. Radiological Protection Program (71709)

Selected activities of the licensee's Radiological Protection

Program were reviewed by the inspectors to verify conformance

with plant procedures and NRC regulatory requirements. The

areas reviewed included the organization and management of the

plant's health physics staff; "ALARA" implementation; Radiation

Work Permits (RWP's) for complience to plant procedures;

personnel exposure records; observation of work and personnel in

radiation areas to verify compliance to radiation protection

procedures; and'centrol of radioactive materials,

c. Physical Security Program (71881)

The licensee's compliance to the approved security plan was

reviewed by the inspectors. The inspectors verified by obser-

vation and interviews with security force members that measures

taken to assure the physical protection of the facility met

current requirements. Areas inspected included: organization

of the security force; establishment and maintenance of gates,

doors, and isolation zones; access control; and, badging

procedures.

One violatica was identified as described in 4.a.

5. Surveillance Observation (61726)

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. Portions of the following surveillance inspections and tests required by

the Technical Specifications (TS) were witnessed, observed or reviewed by

the inspectors:

- STP-1.0 - Operations Daily Shift Surveillance Requirements.

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STP-71.0 - Main Control Room Remote Valve Verification.  ;

- STP-4.1 - Charging Pump 2A Quarterly Inservice Test

- STP-22.4 - Auxiliary Feedwater Pump 2B Annual In Service Test

- STP-33.2A - Reactor Trip Train A Operability Test

- STP-80.16 - Degrading Grid Voltage and Loss of Protection Relays

Operability Test

- STP-121A - Power Range Axial Off Set Calibration

- STP-605.3 - Auxiliary Building Battery Weekly Verification

- 1 S0P-2,1B - Align IB Charging Pump to A Train.

. The inspectors verified that the surveillance were performed in

I. accordance with adequate procedures; instrumentation was calibrated;

limiting conditions were met; test results met acceptance criteria and

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Lwere reviewed-by' personnel other than the individual directing the testi

deficiencies identified' during the testing were properly reviewed and

resolved by appropriate management. personnel; and personnel conducting the-

test were' qualified.

NoLviolations or. deviations were identified, except surveillance STP-22.4

on auxiliary feedwater pump 2A;was unsatisfactory and pump was declared '  ;

inoperative 'due to excessive pump vibration. The licensee promptly

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initiated the limiting condition for operation conditions of the Technical

Specifications and took appropriate corrective action to restore-this: pump

to service..

6. Monthly Maintenance Observation (62703)

The : inspectors observed /reviend 'the following maintenance. activities .s

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of ' safety-related systems and ' components to ascertain that they were

conducted ~in -accordance with approved procedures, regulatory guides,

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industry codes and standards, and were.in conformance with TS:

- Control room area radiation monitor adjustment and calibration

(MRW149386).

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- Retenninate motor leads on charging pump'2A 4160V motor (MRW 139166).

- Replace batteries to turbine driven auxiliary feedwater uninterrup-  !

table power supply (MWR 142709 and 149048'

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- . Replace seals for Unit 1 spent fuel pool cooling pump 1B (MWR 139259). -

- Determinate motor leads'on charging pump room cooler 2B (MWR 159938).

- Reterminatemote#1eadsonchargingpumproomcaoler1A(MWR154798).

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- Rework of electrical splices on various solenoid valves, motor  !

~ operated valves and motors on Unit 2 and certain instruments inside 1

Unit I containment building. i

- Disassembly, inspection and reassembly of certain motor operated

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valve operators.

Items considered during the review included: verification that limiting

conditions for operations were met while components or systems were

removed from service; approvals were obtained prior to initiating the

work; approved procedures were used; completed work was ' inspected as

applicable; functional testing and/or calibrations were performed 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; and., i radiological and fire prevention

. controls were implemented. Work requests were also reviewed to determine i

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the status .of outstanding jobs to assure. that priority was assigned to.

safety-related equipment maintenance which may affect system performance.

The inspectors reviewed the Motor 0perated Valve (MOV) 0perator Inspection

. Program. There are 37.MOV's on unit 2 designated for. ins) ction during

the - Unit 2. refueling .~ outage. The _ inspection is conducteo by M0 VATS,

under contract to - Alabama Power Company. The inspectors ~ observed the . i

disassembly,of-a M0V operator, inspection and' documentation of as-found

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condition, documentation of work done and replacement of any part.s, and

reassembly; The inspectors verified the qualifications of the workmen by

observation and-interviews; verified that the appropriate procedures were

utilized and .that procedural steps were properly signed off and dated.  ;

The inspectors reviewed the following procedures:

FNP-0-MP-45.0 ' - Limitorque Operator Removal and Installatic. - Mod' els

SMB-000-SMB-4.

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FNP-0-MP-45.2 - Limitorque Operator Overhaul - Models SMB-000-SMB-00.

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'FNP-0-MP-45.3 .- Limitorque Operator Overhaul - Model SMB-0-SMB-4.

FNP-0-MP-28.212 - Limitorque - Type SMB MOV Inspection and Adjust' ment. .

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The inspectors will- continue to conduct periodic inspections and review

of procedures and documentation until the completion of this program.

No violations or deviations were identified.

7. Licensee Event Reports ]

'The. 911owing Licensee Event Reports (LERs): were reviewed for potential

genenc problems to determine trends, to determine whether information '

included in the report meets the NRC reporting requirements and to con-

sider 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 TS; that corrective action was taken by the

licensee; and that safety limits, limiting safety setting and LCOs were

not exceeded. The -inspector examined selected incident reports, logs and

records, and interviewed selected personnel. The following reports are .I

considered closed:

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LER-87-08 -

Personnel error results in missed fire watch.

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LER-87-18 - RHR pump 1B room cooler service water valve found isolated, j

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LER-87-10 - Reactor trip caused by inadvertent de-energize action of

4160V Bus 1H.

LER-87-11 - Inoperable control room fire dampers.

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D 1B. Eng'ineered Safety Systems Inspections (71710)

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The inspectors performed various system inspections during the inspection

period., Overall plant. conditions were assessed with particular attention R

to1 equipment condition,, radiological' controls, security, safety, adherence

-to! technicali specification requirements, systems valve alignment, and

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locked valve ' verification. Jiajor components lwere checked for leakage and  !

any' general conditions that would' degrade performance or prevent fulfill - i

ment of Afunctional . requirements. The-inspectors verified that approved

procedures and:up-to-date drawings.were used. 1

1P ortions of Jthe followingf systems were- observed for proper operation, ,

valve alignment and valve. verification:  !

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Auxiliary Feedwater Systems

Chemical Volume Control Systems

Service Water' Systems ..

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' Boric Acid Transfer Systems .

. Containment Spray ' System l Including Chemical . Additive ~ System. i

Residual Heat Removal System

No-violations or. deviations were: identified.

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