ML20207E265

Insp Rept 50-482/86-28 on 861101-30.Violation Noted:Failure to Comply W/Surveillance Requirements

ML20207E265
Person / Time
Site:	Wolf Creek
Issue date:	12/19/1986
From:	Bruce Bartlett, Cummins J, Hunter D, Mullikin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20207E172	List: ML20207E169 ML20207E204 ML20207E265
References
50-482-86-28, IEB-86-003, IEB-86-004, IEB-86-3, IEB-86-4, NUDOCS 8701020125
Download: ML20207E265 (13)

See also: IR 05000482/1986028

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APPENDIX B

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.U.

S. NUCLEAR' REGULATORY COMMISSION

. REGION IV

'NRC: Inspection Report: 50-482/86-28

LP:

NPF-42'

50 482'.-

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Docket:

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~ Licensee: ; Kansas Gascand Electric Company (KG&E)

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Post Office Box 208

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Wichita,' Kansas 67201'

Facility l:Name: Wolf Creek Generating Station (WCGS)

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

Inspection Conducte'd: November 1 to 30,1986

Inspectors

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h)l.'E.Cummins,SeniorResidentInspector,

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(_ Operations, (pars. 4, 5, 6, 7, 8, 9, and 11)

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B. L. Bartlett, Resident Reactor Inspector,

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Operations, (pars. 2, 3, 4, 6, - 7, and 9)

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R. P. Mullikin,' Project Engineer

Date

(pars. 3, 8, and 10)

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Approved:

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D. R. Hunter, Chief, Project Section B

Date

Reaccor Project Branch

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- -Inspection Sununary

rInspection Conducted November 1-30, 1986 (Report 50-482/86-28)

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'AreasEInspected:. Routine, unannounced inspection including plant status;

fellowup of previously identified NRC items; operational safety verification;

monthly-surveillance observation; monthly maintenance observation; onsite

event followup; licensee event report review, IE Bulletin followup; fire

. brigade / fire watch ' training; and 10 CFR Part 21 followup.

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Results: Within the ten areas inspected, one violation was identified (failure

-to comply with surveillance requirements, paragraph 5).

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. DETAILS

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01..-PerhonsContacted

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Principal ~ Licensee Personnel

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f *B.:,D.-Withers,. President, Wolf Creek Nuclear Operating Company

'+*J..A. Bailey,. Interim Site Director

'+*F. TM Rhodes, Plant Manager

+*G.-D..Boyer, Deputy Piant Manager

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+*Rt M. Grant,~~ Director-Quality'-

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i+ C. .M.E Estes,~ Superintendent of Operations

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1*M. D.ERich, Superintendent of Maintenance

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+*M.:G. Williams,. Superintendent of Regulatory,-Quality, and

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. Administrative Services

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-*0. L.~Maynard,. Manager Licensing

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~+*K. Peterson;' Licensing

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i+*G.lPendergrassi Licensing

i+ W.

M.' Lindsay, Supervisor Quality Systems

+*C. J. Hoch, Quality = Assurance (QA) Technologist

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• W. J. Rudolph, QA Manager-WCGS

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.J. W., Johnson, Chief of' Security

H. Chernoff, Licensing Engineer

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J. Ives, Site Health Physicist

V.' MacTaggart, Results Engineering Supervisor

+ R. L. Logsdon, Site Chemist

- . + J. - L. ' Blat: kwell, Fire Protection Coordinator

• J. Stokes, Procurement & Materials Manager

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• T. M. Damashek, QA Systems

G..W.~ Reeves, QC Supervisor

• C. G.-Patrick, Superintendent of Quality Evaluations

+ J. A. Zell, Nuclear Training Manager

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.+ C. E. Parry, Quality Engineering Supervisor

+ W. Gaul, Radwaste Engineer

2+ C. L. Palmer, . Chemistry Supervisor

+ M. H. Megehee, Compliance Engineering

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+.R. C. Richardson, Radw nte Coardinator

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, + K. M.-Thrall, Senior Engineering Specialist

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+lA. A. Freitag, Nuclear Plant Engineering Manager-WCGS

'+.M._Nichols, Plant Support Superintendent

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.+ J. Ives, Site Health Physicist

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- + B. ' McKinney,' Technical Support Superintendent

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.NRC Perscnnel

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+*J. E. Cummins, Senior Resident Inspector

+*B. L. Bartlett,-Resident Inspector

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+ R. P. Mullikin, Project . Inspector

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+*G.'A. Pick, Reactor. Engineer

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4 J. B. Nicholas,. Radiation Specialist

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

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during'thelinspection~ period to discuss identified issues.

+ Denotes.those personnel.in attendance at the exit meeting held on

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November 21, 1986.

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• Denotes those personnel-in attendance at the exit l meeting held on

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' December 5, 1986.

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21? Plant Status-

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lDuring this report period, the plant was in its'first refueling outage.

. Fuel assemblies were removed from the reactor to the spent fuel pool where

the fael shuffle occurred and.then the fuel for the next. cycle was placed

, in the reactor.

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3.-

' Followup On Previously Identified NRC Items

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-(Closed) Violation (482/8530-03): Flow Orifice Installed Backwards

The NRC inspectors verified-that Orifice Plates EG FE-64, 83, and 89 were

reversed and installed properly.

In addition, the NRC inspectors verified

that maintenance personnel have been trained on the proper orientation of

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orifice plates, that maintenance engineers have been trained to specify

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proper orientation and that quality engineers have been instructed to

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verify that work instructions provide for proper orientation.

This

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violation is' closed.

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(Closed) Open Item (482/8621-03):

Licensed Operator Requalification Exam

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Regrade

This item tracked the licensee's commitment to regrade all exams taken in

the 1986 requalification exam to insure correct grading.

The licensee has

performed this task. This open item is closed.

4.

Operational Safety-Verification

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

in conformance with regulatory requirements by direct observation of

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licensee facilities, tours of the facility, interviews and discussions with

licensee personnel, independent verification of safety system status and

limiting conditions for operations, and reviewing facility records.

The

NRC inspectors, by observation of randomly selected activities and interview

of personnel verified that physical security, radiation protection, and

fire protection activities were controlled.

By observing accessible components for correct valve position and

electrical breaker position, and by observing control room indication, the

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NRC inspectors confirmed the operability of the high pressure coolant

injection (charging) system. The NRC inspectors also visually inspected

safety components for leakage, physical damage, and other impairments that

could prevent them from performing their designed functions.

5.

Monthly Surveillance Observation

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The NRC inspectors observed selected portions of the performance of

surveillance testing and/or reviewed completed surveillance test procedures

to verify that surveillance activities were performed in accordance with TS

requirements and administrative procedures. The NRC inspectors considered

the following elements while inspecting surveillance activities:

Testing was being accomplished by qualified personnel in accordance

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with an approved procedure.

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The surveillance procedure conformed to TS requirements.

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Required test instrumentation was calibrated.

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Technical Specification limiting conditions f<

operation (LCO) were

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satisfied.

Test data was accurate and complete.

Where appropriate, the NRC

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inspectors performed independent calculations of selected test data to

verify their accuracy.

The performance of the surveillance procedure conformed to applicable

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administrative procedures.

The surveillance was performed within the required frequency and the

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test results rnet the required limits.

Surveillances witnessed and/or reviewed by the NRC inspectors are listed

below:

STS BG-100A, Revision 1, " Centrifugal Charging System 'A' Train

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Inservice Pump Test," conducted on November 11, 1986

STS EF-100A, Revision 0, "ESW System Inservice Pump 'A' Test,"

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conducted on November 15, 1986

STS EJ-100A, Revision 0, "RHR System Inservice Pump 'A' Test,"

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conducted on November 14, 1986

STS KE-002, Revision 5, "CTMT Aux Hoist Retueling Test," (Section 5.3

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only) conducted on October 27, 1986

STS KE-001, Revision 5, " Refueling Machine Op Test," conducted on

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November 1, 1986

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STS EM-202,: Revision 1~, !' Safety Injection System Inservice Valve -

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ETest";(EM HV-8835), conducted on November 18, 1986

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STS EJ-1008,' Revision _0,'"RHR System Inservice Pump B_ Test,"-

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conducted on' November 24, 1986

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-STS MT-016, Revision 3, " Standby Diesel-Generator Inspection"

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(KKJ01B), conducted starting November 1, 1986

' Selected NRCLinspector observations are discussed'below:

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During'a review of randomly selected surveillance procedures that had been

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completed and transmitted to the records vault; the NRC inspector observed

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that Steps 6.3, 6.4,'and 6.5 of Surveillance Procedure STS MT-016,

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Revision 3, " Standby Diesel Generator Inspection," had not been signed, as

required.

In_ addition Section 5.6.2 of Administrative procedure ADM

02-300, " Surveillance Testing," states that, "Each reviewer of test

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results shall ensure that each test package is complete including all test

data / signatures required by the subject test." This failure of designated

-pe.rsonnel (test performer, supervisor, and QC supervisor / lead) to sign the

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required procedure steps and of the reviewers to identify and ccrrect the

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oversight, as required by the above procedures is an apparent violation

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(482/8628-01).

The NRC inspector did not identify any other

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discrepancies during this review.

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Monthly Maintenance Observation

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The-NRC inspector observed maintenance activities performed on

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

conducted in accordance with approved procedures, Technical Specifications,

and applicable industry codes and standards.

The following elements were

considered by the NRC inspector during the observation and/or review of

the maintenance activities:

LCOs were met and, where applicable, redundant components were

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' operable.

Activities complied with adequate administrative controls.

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

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used.

Craftsmen were qualified to accomplish the designated task and

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

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was made available when appropriate.

Replacement parts and materials being used were properly certified.

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Required radiological controls were implemented.

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Fire prevention controls were implemented where appropriate.

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Required alignments and surveillances to verify post maintenance

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. 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.

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Selected portions of the maintenance activities accomplished on the work

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requests (WR) listed below were observed and related documentation

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reviewed by the NRC inspector:

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Title

WR 07178-85, "Limitorque Operator for EM HV-8814B, Rework Limitorque

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Operator and Perform S:heduled Maintenance."

WR 01161-86, " Implemented PMR 1382 for Snubbers on Pressure

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Switches-Replacement of Pressure Switch"

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WR 030;/-86, " Cutler Hammer Switches, Implement PMR 1316, Revision 1,

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Pushrod Replacement for Switches EN HIS-1"

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WR 03951-86, " Implement PMR 1722 Wiring Change on Limitorque

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Operator, EM VH 8814B"

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WR 04272-86, "BG-017-GCB-3, Due to Modifications IAW PMR 00991 a

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Hydrostatic Test Is Required"

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WR 04516-86, "AB01-R520-145Q, Remove and Replace the Above to Allow

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for ISI Injection"

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WR 04761-86, " Check Valve /EP V88180, Install Freeze Seal Downstream

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of Valve EP V88180 on Line 32-BCA-6"

WR 04863-86, "BG V201-Seal Injection Throttle Valve, Remove Piping

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Downstream of BG V201 to Investigate Foreign Objects"

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WR 52520-86, " Semi-Annual Maintenance on D/G Starting Air Compressor,

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No violations or deviations were identified.

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7.

Onsite Event Followup

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The NRC inspector performed onsite followup of nonemergency events that

occurred during this report period.

The NRC inspector (when available)

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observed control room personnel response, observed instrumentation

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indicators of reactor plant parameters, reviewed logs and computer

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printouts, and discussed the event with cogr.izant personnel.

The NRC

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inspcetor verified the licensee had responded to the event in accordance

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

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Engineered ' afety: feature'actuations(that occurred

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during the report period are' listed in the table below. Where applicable,

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> the NRC inspector willz review the-LER for each of these ' events and will

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report'any findings,in. subsequent NRC inspection reports.

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Date_

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Plant Status

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11/14/86i'CRVIS

Mode 6

Chlorine Monitor Failed-Root

.Cause' Unknown

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CRVIS-l Control'RoomVentilationIsolationSignal

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iSelected.NRC' inspector observations are discussed below:

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- The CRVIS that occurred on November 14, 1986, was caused by the-

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> failure.of Chlorine Monitor GK AITS-2.

The instrument technicians

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could not identify a root cause for the failure.

The chlorine

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monitor has been~placed back in service and as of November 30, 1986,

-thelfailurehas_notreoccurred.

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'No violations.~or deviations were identified.

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Licensee Event Report.(LER) Review

-During'this inspection' period,:the NRC inspectors performed followup on

' selected Wolf Creek LERs. The LERs.were reviewed to ensure:

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. Corrective action stated in the report has been properly completed or

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work is in progress.

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' Responses.to the events were adequate.

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Resp'onses to the' events met license conditions, commitments, or other

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.applicableiregulatory requirements.

The information contained in the report satisfied applicable

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reporting requirements.

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That any generic issues were identified.

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The report conformed to the guidelines contained in NUREG-1022 and

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Supp,lements 1 and 2.

(Closed) LER 86-028:

" Technical Specification Violation-Failure to Test

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Sealed Sources"

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This LER reported two instances where the requirements of TS 3.7.9 were

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not complied with. On May 22, 1986, during an internal audit, it was

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determined that a sealed source had not been tested as required every six

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months.

This event was caused when licensee personnel, who incorrectly

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categorized this source as being "i.fstorage" and removed it from the list

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of sources requiring a leak test every six months.

Licensee personnel put

.the source back on the list when the error was identified and verified

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through records that all other sources had been tested, as required, and

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also made it a requirement that.the site health physicist had to approve

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removal of any test sources from the list.

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The second event occurred on April 22, 1986, when an incore neutron

detector was installed prior to being tested as required by the TS. The

licensee placed tags on the storage cabinet for the fission detector

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instructing warehouse personnel to contact reactor engineering and health

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physics prior to. issuing the detectors.

This LER and the related Defect

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Deficiency Report (DDR)86-043 were provided as required reading for

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cognizant personnel.

The NRC inspector reviewed the required reading

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signoff sheets for these items.

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(Closed) LER 86-051:

" Technical Specification Violation-Use of Improperly

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Adjusted Spent Fuel Pool Crane"

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On September 23, 1986, licensee personnel determined durir.g performance of

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a routine surveillance that the spent fuel crane overload limit was set

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200 pounds greater than the TS (3.9.7) specified 2250 pounds.

Contrary to

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the TS, new fuel was moved between September 23 and 25, 1986, with the

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crane overload limit set wrong.

Discussion with the licensee determined

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that the overload limit apparently had not been challenged.

The NRC

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inspector verified by review that Procedure STS KE-003, Revision 4, " Spent

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Fuel Pool Cranes Surveillance Test," had been revised to. clarify the

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proper method for measuring and setting the overload limit stop.

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(Closed) LER 86-013:

" Technical Specification Violation-Due to Personnel

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Error"

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On March 14, 1986, a containment depressurization was performed with one

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of the two required containment atmosphere radiation monitors inoperable

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due to it having been left in bypass.

The redundant radiation monitor was

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operable at all times during this event and no release limits were

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exceeded.

This LER was assigned as required reading for licensed

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personnel. The NRC inspector verified by reviewing the required reading

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signature sheets that cognizant personnel had been made aware of this

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event.

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(Closed) LERs85-052, 85-061,85-081, 85-085, and 86-002:

" Engineered

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Safety Features Actuation-Control Room Ventilation Isolation"

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On July 12, 1985; September 14, 1985; five times between November 26

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through December 13, 1985; December 18, 1985; and January 18, 1986; a

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control room ventilation isolation occurred due to a chlorine monitor

signaling high chlorine level in the outside air makeup to the control

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bull' ding ~ ventilation system.- The isolation' occurred (except for LER ^

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85-085) due to breakage of the chemically sensitive' paper tape used to

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. detect chlorine in the monitor ~ analysis unit. lLER 85-085 was caused by

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ithe. paper. tape bunching up resulting in a blown fuse. The NRC inspector

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. reviewed:the LERs'and the licensee's defect / deficiency reports for_ each

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. occurrence. sThe licensee ~could not determine a specific cause:for the

tape problem but~did replace two monitors with s' pares and cleaned the~ tape

drive mechanisms. ;Although the root cause could not be determined the

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-occurrences of this problem have ceased.

The NRC; inspector will pursue

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Lthis issue-further if this problem reoccurs.:

-(Closed):LER 86-046: - " Error During Surveillance Testing Causes Control

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Room-Ventilation Isolation"

On September 4,1986,-during surveillance testing of a control room air

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intake radiation monitor, GK RE-04, an unexpected " process radiation

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smonitor failure" alarm annunciated in the control room. The source of the

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f alarm was determined to be a check source test failure on GK RE-04 due to

the monitor's signal cable being disconnected for testing. When restoring

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-the system to test configuration, a typographical error was made in a

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keyboard command.- This error. indicated that testing was to be performed

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on redundant control room air intake radiation monitor GK RE-05 which was

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not in the required bypass position.

The licen:ce provided this LER as

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required reading for I&C personnel.

The NRC inspecMr reviewed the DDR as

well. as documentation of the required reading'being earformed.

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LNo violations or deviations were identified.

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9.

IE Bulletin (IEB) Followup

The NRC inspector by review of doc.uments and discussions with licensee

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. personnel, verified that the IEBs discussed below had been reviewed and

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appropriately acted upon by the licensee.

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(Closed) IE Compliance Bulletin 86-03, " Potential Failure of Multiple ECCS

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-Pumps Due to Single Failure of Air-0perated Valve in Minimum Flow

Recirculation Line"

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The purpose of this IEB was to inform the licensee of a design deficiency

-involving the minimum flow recirculation paths for emergency core cooling

system (ECCS) pumps which could allow a single failure to result in a

common-cause failure of all ECCS pumps in a system and to request certain

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. licensee actions.

The licensee's response to this IEB (KMLNRC 86-209 dated November 7, 1986)

' stated, in part, ". . . the WCGS design configuration of the ECCS pumps

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and their recirculation paths is not vulnerable to a single failure in the

minimum flow recirculation line . . . that could cause a failure of more

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than one train."

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The NRC inspector verified through review of the licensee's response,

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review of piping and instrumentation diagrams, review of surveillance

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procedures and field inspections that the design configuration for the

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ECCS pumps appears to meet the single failure criterion in General Design

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Criterion (GDC) 35 (10 CFR Part 50, Appendix A).

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In addition, the NRC inspector verified that the following systems

appeared to comply with the intent of this IEB:

Auxiliary feedwater

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Essential service water

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Containment spray

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Main feedwater

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This IEB is closed.

(Closed) IEB 86-04, " Defective Teletherapy Timer That May Not Terminate

Treatment Dose"

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This IEB was reviewed and determined not to be applicable to WCGS.

This

IEB is closed.

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Fire Brigade / Fire Watch Training

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The NRC inspect'or reviewed the current control room list of qualified fire

brigade and fire watch members.

Six individuals from each list were

selected to assure that their required training was current.

The computer

printouts of training received showed that training commitments for these

individuals were met,

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No violations or deviations were identified.

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10 CFR Part 21 Report Followup

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The NRC inspector by review of documents and discussions with licensee

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personnel, verif'ed that the 10 CFR Part 21 reports discussed below had

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been reviewed and appropriately acted on by the licensee.

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(Closed) Cracked Welds in Generator Coil Guards, dated March 6, 1985.

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This 10 CFR Part 21 report identified a potential problem with cracked

welds on the conical baffle section of the coil guards for the emergency

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diesel generators.

The licensee issued WRs to inspect and repair, if

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necessary, the wcids reported by this 10 CFR Part 21 Report.

The NRC

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inspector verified by review of the completed documents listed below that

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the licensee performed the recommended inspections and had taken

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appropriate corrective action.

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WR 06001-85, inspection of welds in the conical baffle section of the

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coil guards on Standby Diesel Generator KKJ01A.

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,

-12-

WR 06704-85, repair cracked welds identified on WR 06001-85.

No

.

cracked welds needing repairs were identified.

WR 06002-85, inspection of welds in the conical baffle section of the

.

coil guards on Standby Diesel Generator KKJ01B.

WR 06706-85, repair cracked welds identified during the inspection

.

performed on WR 06002-85. One cracked weld was identified and

repaired.

a

The four 10 CFR Part 21 reports discussed below have previously been

reported, reviewed, and closed as 10 CFR Part 50.55(e) reports by the

licensee.

These items have previously been reviewed and closed by NRC

inspectors.

The documents that documented these reviews and closures are

identified in the discussion for each of the four 10 CFR Part 21 reports.

(Closed) Limitorque Operator Motor Pinion / Worm Shaft, dated

.

November 11,-1986.

This 10 CFR Part 21 report was reported as 10 CFR Part 50.55(e) Report No. 53564-K146 by the licensee.

This item was

discussed and made an open item (482/8455-09) in NRC Inspection

L

Report 50-482/84-55, which was closed in NRC Inspection

Report 50-482/85-04.

(Closed) Design Deficiency in Field-Run Cables to Valcor Solenoid

.

Valves, dated March 19, 1984.

This 10 CFR Part 21 report was

reported as 10 CFR Part 50.55(e) Report No. 53564-K127 by the

licensee.

This item was discussed and closed in NRC Inspection

Report 50-482/84-49.

(Closed) Material May Be Defective in Workmanship, dated

-

.

May 15, 1984.

This 10 CFR Part 21 Report was reported as 10 CFR

l'

Part 50.55(e) Report No. 53564-K114 by the licensee.

This item was

discussed and closed in NRC Inspection Report 50-482/84-49.

(Closed) Valve Stem Bushing Too Loose on Steam Valve Preventing

.

Closing, dated April 9, 1984.

This 10 CFR Part 21 Report was

reported as 10 CFR Part 50.55(e) Report No. 53564-K156 by the

licensee.

This item was discussed and closed in NRC Inspection

Report 50-482/84-49.

No violations or deviations were identified.

12.

Exit Meeting

.

The HRC inspectors met with licensee personnel to discuss the scope and

findings of this inspection on December 5, 1986.

The NRC inspectors also

attended entrance / exit meetings of the NRC region based inspectors

identified below:

-

• $

_ _ _ _ _ - - _ _ _ __. . _ _ _ _ _

. . . .

.

13-

-

Inspection

Lead

Area

Inspection

Period

Inspector

Inspected

Report No.

__

-

11/17-21/86

G. Pick

Surveillance

86-26

Procedure Review

11/03-07/86

L. Gilbert

Inservice

86-27

Inspection

11/17-21/86

R. Baer

Radiological

86-30

Control

11/17-21/86

B. Nicholas

Liquid Radwaste

86 '/3

11/17-21/86

R. Mullikin

Fire Protection

86-28

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