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Insp Rept 50-482/87-16 on 870705-31.One Potential Violation Noted.Major Areas Inspected:Plant Status,Operational Safety Verification,Monthly Surveillance & Maint Observation,Review of LERs & Physical Security Verification
	ML20234B112
Person / Time
Site:	Wolf Creek
Issue date:	08/25/1987
From:	Bruce Bartlett, Cummins J, Hunter D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20234B082	List: ML20234B079; ML20234B112;
References
	50-482-87-16, NUDOCS 8709180265
	Download: ML20234B112 (11)
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APPENDIX i

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U. S. NUCLEAR REGULATORY C0FDtISSION .i

REGION IV !

NRC Inspection Report: 50-482/87-16 License: NPF-42 j

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Docket: 50-482 !

Licensee: Wolf Creek Nuclear Operating Corporation (WCNOC) ,

P. O. Box 411 ;

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Burlington, Kansas 66839 ,

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Facility Name: Wolf Creek Generating Station (WCGS) 4

Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas

Inspection Conducted: July 5-31, 1987

Inspect s: M,4/L64

Date' i

I[J.E.Cummins,5ElorResidentInspector,

Operations

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B. L. Bartlett, Resident Reactor Inspector,

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Operations

Approved: b1

D. R'."ITunter, Chief, Reactor Project Section B

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Reactor Projects Branch

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Inspection Summary c

Inspection Conducted July 5-31, 1987 (Report 50-482/87-16) /

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Areas Inspected: Routine, unannounced' inspection including plant ~ status, '

operational safety verification, monthly surveillance observation, monthly

maintenance observation, review of licensee event reports, 10 CFR Part 21 ,

report followup, onsite event followup, physical security ver.ification,

radiological protection, and new fuel receipt.

Results: Within the 10 areas inspected, one potential violaticn was identified

(failure to follow compensatory procedures, paragr ph 9).

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DETAILS

1. Persons Contacted

Principal Licensee Personnel

R. M. Grant, Vice President, Quality

J. A. Bailey, Vice President,' Engineering & Technical Services

G. Rathbun, Manager, Management Systems

F. T. Rhodes, Vice President, Nuclear Operations

G. D. Boyer, Plant Manager

0. L. Maynard, Manager, Licensing

C. M. Estes, Superintendent of Operations )

M. D. Rich, Superintendent of Maintenance '

M. G. Williams, Superintendent of Regulatory, Quality, and

Administrative Services

W. J. Rudolph, QA Manager, WCGS

A. A. Freitag, Manager, Nuclear Plant Engineering (NPE), WCGS

C. E. Parry, Superintendent of Quality Engineering

C. W. Russo, Superintendent of Academics Training

W. Mutz, Manager, NPE Systems

G. Pendergrass, Licensing

W. M. Lindsay, Supervisor, Quality Systems

C. J. Hoch, QA Technologist

T. M. Damashek, Quality Engineer, Systems

J. Goode, Licensing Engineer

B. L. Bergstrom, Technical Staff Specialist, NPE

D. L. Tokach, Configuration Manager & Supervisor

The NRC inspectors also contacted other members of the licensee's staff 1

during the inspection period to discuss identified issues.

Denotes those personnel in attendance at the exit meeting held on

August 7, 1987.

2. Plant Status l

The plant operated in Mode 1 during the inspection period except during '

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the time period described below:

On July 20, 1987, the reactor tripped from 100 percent power due to the

loss of a main feedwater pump. The plant was returned to power operations

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in Mode 1 on July 26, 1987.

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3. Operational Safety Verification

The NRC inspectors verified that the facility is being operated safely and

in conformance with regulatory requirements by direct observation of

licensee facilities, tours of the facility, interviews and discussions

with licensee personnel, independent verification of safety system status

. REMOVAL OF TH E PAGES MARKED " SAFEGUARDS INFORMATION'

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and .limitiiig conditice;s for operations, and reviewing. facility records.

The HRC -1,nspectors, by obsorvatior, of randomly selected activities and

interview of personnel verified that' 9agdcal< security radiation ,

protection, and fire' protection acti)itje6 waro controlled.

By observing accessible component 4 icr correct valve position and '

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electricai'breaisr position, r.nd/by observing control room indication, the J

NRC.ir:spectors confirmed the operability of selected portions of i

safety2rdlated systems. The NRC inspectors also visually inspected safety j

componen' for leakage, ' physical damage, and other impair >.lents that could i

prevent uhem from perfonning their designed functions. !

No violbtions or deviations were identified. I

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4. MonthlySurvet,llanceObservation

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The NRC'idspectors observed selec',ed portions of the performance of i

surveillance testing and/or reviewed. completed surveillance test )

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procedures to'varify that surveillance activities were performed in '

accordance w{th Technical Specifications (TS) requirements and

administrative procedures. The NRC inspectors considered the following i

elements while, inspecting surveillance activities: '

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resting was being accomplished by qualified personnel in accordance '

with an approved procedure.

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The surveillance procedure conformed to TS requirements.

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,ReNuiredtestinstrumentationwascalibrated.

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TS limiting con'itions d for operation (LCO) weYe utisfied.

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Iestdatawasaccurateandcomplete. WhereapMopriate,theNRC l

inspectors performed independent. calculations z of selected test data

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to verify their accuracy.

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.The performance of the surveilidnce procedure conformed ti" applicable l

administrative procedures. ,

The, surveillance was perfobmed within the required frequency and the

. test results met tie 3 vaquired limits. ,

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survelllances witnessed anc/or' reviewed by the NR'C inspectors are listed

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STS MT-001, ' Revision 3, " Pressurizer Heater Verification," performed

Januarp 5,and March 28, 1987.

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STS RE-402, Revision 5, "Ceterminction of Estimated Critic:? Position," ,

performed on July 24,1987, at 11:12 a.m. (CDT)'for a criticality of

9.p.m., July 26, 1997, and at 3 a.m. for a criticality of S:45 a.m. i

plEMOVAL OF THE PAG 7 Vy"GD "0 WEG'iAprm WFCnM ATIOW :

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.STS RE-004, Revision 6, " Shutdown Margin Determination," performed on

. July 25,.1987, at 12 midnight.

H _STS EJ-001, Revision 4, " Containment Inspection," performed on July 26,

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STS IC-260, Revision 6, " Analog Channel Operational Test. Auxiliary

'Feedwater Pump Suction Pressure Low Transfer to ESF," performed on July'6,

1987.

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STS EN-100A, Revision 1, " Containment Spray Pump A Inservice Pump Test," l

performed on July.1, 1987.

Selected NRC inspector observations are discussed below:

On July 24, 1987, the NRC inspector performed a manual estimated critical

position calculat' . using the licensee's procedure and compared his

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L The licensee's result was Control Bank "C" at 185 steps and Control

Bank "0" at 70 steps, while the NRC inspector's result was Control

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Bank "C'!'at 172 steps and Control Bank "0" at 57 steps. The actual

critical position was: Control Bank "0" ~at 60 steps. The, difference

between the two results was caused by the NRC inspector using a reference

all rods out (ARO), beginning of life (BOL), hot zero power (HZP), and

axial offset (AO) constant of 59 percent (from' licensee tables), and the

computer using an ARO, BOL, and HZP A0 of 54 percent. Reactor engineering

agreed to change the computer value to agree with the manual calculation.

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No violations or deviations were identified, l

5. Monthly Maintenance Observation .

The NRC inspector observed maintenance activities performed on

safety-related systems and components to verify that these activities were q

conducted in accordance with approved procedures, Technical j

Specifications, and applicable industry codes and standards. The i

following elements were considered by the NRC inspector during the ]

observation and/or review of the maintenance activities: j

, LCOs were met and, where applicable, redundant components were

operable.

Activities complied with adequate administrative controls.

Where required, adequate, approved, and up-to-date procedures were

used.

Craftsmen were qualified to accomplish the designated task and

technical expertise (i.e., engineering, health physics, operations)

was made available when appropriate.

O40 VAL OF THE PAGEG M ARKED S AFFGU ARDS INFORM ATION"_

DECON1T10LS THG REMAINDE9 OF THIS DOCUMENT.

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Replacement parts and materials being u' sed were properly certified.

Required radiological controls ~were implemented.

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Fire prevention controls were' implemented where appropriate.

Required alignments and surveillance to verify post-maintenance

operability were performed.

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Quality control hold points and/or checklists were used when

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appropriate and quality control personnel observed designated. work

activities.. !

Selected portions of'the maintenance activities accomplished on the work

requests.(WR) listed below were observed and related documentation

reviewed by the NRC inspector:

No. Activity.

WR 02478-87 "CCW to RHR HX B,'EG HV-102, won't open from

Control room"

WR 02153-87 "EJ-01 piping system, perform NDE for the ISI h

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program . . . . "

WR 02522-87 "Ctmt. Personnel Hatch-Excessive Leakage on Outer l

Door Upper Shaft Seal" -

No violatio'ns or deviations were identified.

6. Review of Licensee Event Reports (LER) 1

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During this inspection period, the NRC inspectors performed followup on

Wolf Creek LERs. The LERs were reviewed to ensure:

Corrective action stated in the report has been properly completed or

work is in progress.

Response to the event was adequate.

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Response to the event met license conditions, commitments, or other

applicable regulatory requirements.

The information contained in the report satisfied applicable

reporting requirements.

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Generic issues were identified.

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The LERs discussed below were reviewed and closed: 1

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LER 87-016: Personnel Error Causes Failure to Maintain Fire Watch As i

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Required by Technical Specification

This LER reported that on April 9, 1987, a continuous fire watch had not !

been maintained as required by TS. The deficiency was identified by the i

licensee and reported in a timely manner. The continuous fire watch was 1

stationed to provide coverage in the two adjacent engineered safety

features (ESF) switchgear rooms. The fire watch at the time of this event

did not understand that he was suppose to check the adjacent ESF

switchgear room every 20 minutes. The missed fire watches were confined

-to one individual on one shift and this appeared to be an isolated ;

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occurrence. The event had minimum safety significance. The licensee had

taken reasonable measures to prevent recurrence of the event, in that the

fire watches were reinstructed at to their duties and the problem appears

to have been corrected. This LER is closed. l

The three LERs listed below reported actuations of the control room ,

ventilation isolation system (CRVIS) which were caused by malfunctions of '

the chlorine monitors. The licensee is pursuing a design change to

correct this problem. These three LERs are closed.

LER 87-015-01: ESF Actuation CRVIS Caused by Paper Tape Bunching Up on

Chlorine Monitor

LER 87-002: ESF Actuation CRVIS Caused by Paper Tape Breaking on Chlorine

Monitor

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LER 87-024: ESF Actuation CRVIS Caused by Loss of Power to Chlorine

Monitor Because of Faulty Sample Pump

No violations or deviations were identified.

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7, 10 CFR Part 21 Report Followup

a. The NRC inspector, by review of documents and discussions with

licensee personnel, verified that the 10 CFR Part 21 reports

discussed below had been reviewed and appropriately acted on by the

licensee.

P21-1987-87-27: Possible Failure of Worm Shaft Gear in Operators

With Certain Speed / Gear Ratio

This 10 CFR Part 21 was reported by the licensee as 10 CFR

Part 50.55(e) Report No. 53564-K146. This item has been closed. See

, NRC Inspection Report 50-482/86-28.

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P21-1987-87-31: Houghto No. 620 Lubricant Attacks and Degrades

Aluminum in Valves

The licensee determined that Houghto No. 620 lubricant is not l

currently used at the WCGS. The licensee provided a copy of this l

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report to appropriate personnel to make them aware of the problem.

This information'is documented in WCGS Industry Technical Information

Review and Evaluation (ITIP) No. 00367. This item is closed.

P21-1987-87-42: Cracking of 0-Rings on the Latch Mechanism of

Contactors on Fairbanks Morse Diesel Generator Exciters

This 10 CFR Part 21 report states that Hope Creek and Shoreham are

the only affected facilities. This item does not apply to WCGS and

is closed.

P21-1987-87-44: Diesel Generator Engine Fire in Injection Tube

(Nuts Supplied with Tube Not per SAE J5216 Specification)

The licensee has determined that this 10 CFR Part 21 report is not '

applicable to WCGS. The emergency diesel generator engines at WCGS

are Colt-Pielstik. This information is documented in ITIP No. 00392.

This item is closed.

P21-1987-87-41: Internal Failure of Diesel Generator Engine

This 10 CFR Part 21 report reported a problem with Cooper-Bessemer

emergency diesel generators. Since WCGS uses Colt-Pielstik emergency

diesel generators, the licensee has determined that this 10 CFR

Part 21 report is not applicable to WCGS. This information is

documented in WCGS ITIP No. 00393. This item is closed.

b. The NRC resident inspector provided copies of the 10 CFR Part 21

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report listed below to the licensee for review and action, if

required.

P21-1987-87-51: Gas Bubble Formation Between Diaphragm Layers

Within Sensing Element of Pressure Switches May Cause Set Point

to Shift Outside Technical Specifications

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No violations or deviations were identified.

8. Onsite Event Followup

The NRC inspectors performed onsite followup of nonemergency events that

occurred during this report period. The NRC inspectors reviewed control

room logs and discussed the events with cognizant personnel. The NRC

inspectors verified the licensee had responded to the events in accordance

with procedures and had notified the NRC and other agencies as required in

a timely fashion. The events that occurred during this report period are

listed in the table below. The NRC inspectors will review the LER for

each of these events and will report any findings in a subsequent NRC

inspection report.

REMOVAL OF THE PAGES M AMKED " SAFEGUARDS INFORM ATION"

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Date Event Plant' Status Cause _

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7/20/87' Reactor Trip Mode 1 Loss.of Main

(100 percent) Feedwater Pump

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'7/21/87 Shutdown Load ' Mode 3 Personnel Error d

. Sequence Actuation

Selected NRC inspector's observations are discussed below:

The reactor trip on July 20, 1987, occurred when a potential.

transformer in the switchyard shorted and caused an electrical i

perturbation in the electrical circuitry. feeding one of the main j

' feedwater pumps. This caused.the main feedwater pump to trip and

subsequently the reactor tripped, as designed, on the loss of a main 3

feedwater pump above 50 percent power. 1

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The shutdown load sequence actuation occurred when the operator

failed to secure power to the sequencer while transferring the "A"

4160 volt AC ESF bus from offsite power to the emergency diesel I

operator. j

No violations or deviations were identified.

9. Physical Security Verification j

The NRC inspectors verified that the facility physical security plan (PSP)

was being: complied with by direct observation of licensee facilities and

security personnel.

-The NRC inspectors by observation of randomly selected activities verified

that search equipment was operable, that the protected area barriers and

vital area barriers were well maintained,_that access control procedures

were followed, and that appropriate compensatory measures were followed

when equipment was inoperable.

During this inspection, the NRC inspectors observed an instance where ,

required compensatory measures were compromised by licensee personnel. '

The discussion of this apparent violation contains safeguards information,

as defined in 10 CFR Part 73.21; therefore, the details of this apparent

violation are provided in the Safeguards Attachment to this inspection

report.

10. Radiological Protection

By performing the following activities, the NRC inspectors verified that

radiologically-related activities were controlled in accordance with the

licensee's procedures and regulatory requirements: I

Reviewed documents such as active radiation work permits and the

health physics shift turnover log. ,

R8w3 VAL OF THE PAGES MARKED " SAFEGUARDS INFORM ATION"

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Observed personnel activities in the radiologically controlled

area (RCA) such as:

. Use of the required dosimetry equipment.

. " Frisking out" of the RCA.

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. Wearing of appropriate anticontamination clothing where ;

required. '

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Inspected postings of radiation and contaminated areas. j

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Discussed activities with radiation workers and health physics l

supervisors.

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No violations or deviations were identified.

11. New Fuel Receipt

The NRC inspectors observed randomly selected portions of the handling,

receipt inspection, and storage of the 52 new fuel assemblies received by

the licensee. The handling, receipt inspection, and storage of these

assemblies were performed in accordance with licensee procedure FHP 01-001, i

Revision 9, "New Fuel Receipt." The NRC inspectors reviewed this '

procedure for technical adequacy and required approvals. The NRC

inspectors periodically reviewed the following procedures which are used

by the licensee to verify operability of fuel handling equipment prior to

use: j

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FHP 03-007, Revision 6, " Spent Fuel Pool Bridge Crane Operating l

Instructions" 1

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FHP 03-008, Revision 5, " Cask Loading Crane Operating Instructions"

FHP 03-009, Revision 2, "New Fuel Elevator Operating Instructions"

During the removal of Fuel Assembly E18 from its shipping container, the

operator accidentally put excessive stress on the assembly while it was

still clamped to the shipping container by the top and bottom clamps. The

operator was attempting to take the slack out of the lifting strap and

should have had the crane in the jog mode; however, it was in the normal

mode. The spring scale used to monitor the fuel assembly weight indicated

approximately 2100 pounds. L;censee and Westinghouse personnel inspected l

l the assembly, reviewed the event, and determined that the assembly was

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No violations or deviations were identified.

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12. Exit Meeting

The NRC inspecturs met with licensee personnel to discuss the scope and

findings of this inspection on August 7, 1987. The NRC inspectors also

attended entrance / exit meetings of the NRC inspectors identified below:

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Inspection Lead Area Inspection

Period Inspector Inspected Report No.

l 07/13-17/87 R. Stewart TI Followup 87-18

07/27-31/87 P. Harrell Training 87-19

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ML20234B112

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