ML20136F558
| ML20136F558 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1985 |
| From: | Bruce Bartlett, Cummins J, Hunnicutt D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20136F533 | List: |
| References | |
| 50-482-85-37, NUDOCS 8601070428 | |
| Download: ML20136F558 (10) | |
See also: IR 05000482/1985037
Text
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APPENDIX B
US NUCLEAR REGULATORY C0FDilSSION
REGION IV
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NRC Inspection Report: 50-482/85-37 LP: NPF-42
Docket: 50-482
Licensee: Kansas Gas and Electric Company (KG&E)
Post Office Box 208
Wichita, Kansas 67201
Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas
Inspection Conducted: _0ctober 5 to November 30, 1965
I pectors: M +
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~ . E. Cummins, Senior Resident Inspector, Date
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B. L. Bartlett, Resident Reactor Inspector, Date
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Operations
Approved: [ mEd / 3/ b
D. M. Hunn'icutt, Acting Chief, Project Da(e #
Section B, Reactor Projects Branch
8601070428 860102
PDR ADOCK 05000482
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C.W#5 '? Inspection Condiicted October 51t o'NovembeW30,1985 (Report 50-482/85-37) . .
Wei . Areas Inspected: ~Routin, e, unannounced inspection including plant status,
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W Qvfollowup
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on previously1 identified items, operational safety verification,. ','
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engineered safety features system'walkdown, onsite followup of events,
t;;/ monthly surveillance observation,0 security," emergency drill, enforcement~
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.k.._.. . ( conference,, cold weather preparations.. and' plant tours.
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LThe~ inspection; involved 271. inspector-hours onsite by.two NRC inspectors ~
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including'41Linspector-hours onsite during~offshifts.
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(Results:: .Within the 11 areas.? inspected, one violation was identifie'd
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.E,. Inonseismic sight: glass.leve.l gage not isolated, paragraph 5). . - -
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DETAILS-
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/Persoris Contacted
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l Principal- Licensee Personnel - -
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(M_,4 Ja ig G; L/Koeiter,$1ce' President-Nuclear -
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J.; Bailey, Interim Site Director m , ,
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M *F. T.ERhode_s, Plant Superintendent'
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, *J. AF Zell., Operations. Superintendent- ',
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. ,H. K. Chernoff,, Licensing-
- G.CJ. Pendergrass, Licensing
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4. . *K.Peterson, Licensing , . . _ .
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' *M. G.1 Williams, Superintendent of Regulatory, Quality, and
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(*R.fii.: Grant, Director-Quality ,
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J__ , -*W. J..Rudolph,' Site QA Manager-
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- " . - J.; J. Johnson.. Chief of. Security
, . - . *C.fJ.- Hoch,.QA Technologist '
~ W. M. Lindsay, Quality Systems Supervisor.
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- R. .. Hoyt, Emergency' Plan . Supervisor
d *R.1D.- Flannigan," Kansas City Power & Light' Site Representative
t*C.KM. Herbst, Assistant Pro, ject Manager, Bechtel
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1*A. A .Freitag, Manager NPE
V The NRC irispectors also contacted other members of the licensee's staff
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, ;during the Linspection period to discuss identified issues.
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f ;,.. } . *Denoteslthose personnel:in attendance at the exit meeting held on
- December. 5,1985.
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a2. Plant Status
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iT O plant' operated in Mode 1 during this inspection period except for -
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oneishutdown and one reactorJtrip, when the. reactor was shut down due to
%J~ Jmoss in the~ circulating water at the circulating ~ water intake str:.cture.
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x'; :The. plant was shut down on October 7,~1985, due. to moss clogging the
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' circulating water intake' traveling screens. Then-during the subsequent ~
if :-startup on October 10, 1985, a reactor trip ~ occurred due. to a 10-10
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ist,eam generator level. The total shutdown time from these two events
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. was approximately 3.5' days.
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3 .J Licensee Actions on Previously Identified Items-
(Closed): Violation.(50-482/8519-01): Failure to Properly Update
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. Procedure Manuals.'
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iThis Yiolation concerned outdated procedures which were found in-
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procedure manuals located.in the Technical Support Center,(TSC) and~
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Emergency Operations Facility (E0F). The NRC inspector reviewed the
- licensee's written response to this violation and verified that a
full-time document control clerk has been assigned to the TSC/E0F. In
addition, on October 22, 1985, the NRC inspector audited the procedure
- manuals and drawings located in the TSC and E0F using the KG&E master
. drawing file index and the master procedure index. This item is closed.
>
(Closed) Open Item (50-482/8455-07) Fan Mechanical Interlocks
,TE53564-K128.
This open item documented periodic failures of the contact assembly
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-' .which causes the shift of containment cooling fans from high to low
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- speed on~ the receiptiof a safety injection signal. Yhe failures were
caused by excessive length of the extender arm on the interlock
assembly. The~ extender arms, with vendor approval, have been shortened
by 4811nches to . resolve this problem. This item is closed.
4. Operatiional Safety Verification
The NRC inspectors verified that the facility is being operated safely
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and'in conformance with regulatory requirements by direct observation of
licensee facilities, tours of the facility, interviews and discussions
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with licensee personnel, independent verification of safety system
status and 1imiting conditions for operations, and reviewing facility
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records. The NRC inspectors, by observation and direct interview,
verified the physical security plan was being implemented in accordance
with the security plan.
The NRC inspectors confirmed the operability of the emergency diesel
generators, Class 1E in volt AC systems, the safety injection system,
the residual heat removal system, and the coolant charging system by
observing valve positions, electrical breaker positions, and control
room indications. The NRC inspectors also visually inspected safety
components for leakage, physical damage, and any other impairment that
could prevent them from performing their designed function.
No violations or deviations were identified.
5. Engineered Safety Features (ESF) System Walkdown
The NRC inspectors verified the cperability of ESF systems by walking
down selected accessible portions of the systems. The NRC inspectors
verified valves and electrical circuit breakers were in the required
position, power was available, and valves were locked where required.
The NRC inspectors also inspected system components for damage or other
conditions that might degrade system performance. The ESF systems
listed below were walked down during this inspection report period:
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- Containment Spray System
- . Component Cooling Water System
- Auxiliary Feedwater System
. The NRC inspector findings are discussed below:
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During the walkdown of the component cooling water (CCW) system, the NRC
inspectors noted that Piping and Instrumentation Diagram M-12EG01,
Revision 1,'showed Valves EG-V 100, 161, 171, and 172 to CCW Surge Tanks 3
TEG01A and TEG01B to be closed while Checklist EG-120, Revision 5,
called for the valves to be opened. Further review of the drawing
showed that the level gage between the valves is nonseismic and the
valves should have been closed in order to isolate the seismic portion
of the system from the nonseismic portion. This failure to have
appropriate procedures is an apparent violation (50-482/85L7-01).
6. Onsite Followup of Events
The NRC-inspectors performed onsite followup of nonemergency events
that occurred during this report period. The NRC inspectors (when
available) observed control room personnel response, observed
instrumentation indicators of reactor plant parameters, reviewed logs
and compute; prit.%uts, and discussed the event with cognizant
personnel. The NRC inspectors verified the licensee had responded to
the event in accordance with procedures and had made required
netifications to the NRC and other agencies in a timely fashion.
ESF actuations that occurred during the report period are listed in the
table below. The'NRC inspector will review the licensee eveat report (LER)
for each of these events and will report any findings in NRC inspection
. reports.
Date Event * Plant Status Cause
10-07-85 Rx Trip Mode 1 Blocked CWSH Intake
Screens
10-03-85 CRVIS Mode 1 Broken Tape
l 10-10-85 Rx Trip Mode 1 Lo-Lo S/G Level
10-31-85 TDAFP Start flode 1 18C Surveillance
11-26-85 CRVIS flode 1 Broken Tape
- Evant
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CRVIS - Control Room Ventilation Isolation Signal
Rx Trip - Reactor Trip
CWSH - Circulating Water Screen House
TDAFP - Turbine Driven Auxiliary Feedwater Pump
S/G - Steam Gei.erator
I&C - Instrumentation and Control
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. -"85-125 - Unplanned Mar.ual' Reactor Trip
85-126 - CRVIS-Lightning Strike
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.,85-127. - Reactor Trip Lo-Lo $/G Level
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1 ,85-128 -l5 Disabled Transmitters / Receivers on Panel KC008
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>85-129 - Venting RHUT "B" with 2H and 02 Monitors Out-of-Service .,
w .- 85-130 - Potential, Backflow Thru Intake Plenum While Venting
! / Containment
rf ,- 85-131 - MSIV/MFIV 4-Way Valves Pctential Cracking '
q ,. '85-132. .TDAFP Start
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The-fdllowing Wolf Creek. event reports were reviewed:
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'85-122 - Valve Diaphragm and Support Sheet Stacked In Wrong' Order
- 85-126 ' Replacement of Temporary Non-1E Voltmeter and Ammeter '- 85-127 - Hourly Fire Watch Late
- - 85-128 - Actuation of Control Room Halon System
. . .- 85-129 - Load Reject 100% to 20%
- 85-130 - Failure To Recognize Technical Specifications Action ,
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, : Statement
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qNo.v'olations'ofaeiiationswereidentified. .
' 7.4 -Monthly Surveillance Observation
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The-NRC inspectors observed selected portions of the performance of ,
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surve'.llance testing and/or reviewed completed surveillance test
procedures to verify that surveillance activities were performed in
y. .accordance with Technical Specifications (TS) requirements and
p- . administrative procedures. The NRC inspectors cor,sidered the following
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items while inspectir.g surveillance activities:
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- .Testingwasb51ngaccomplishedbyqualifiedpersonnelinaccordance
e with an approved procedure.
., - The surveillance procedure conforms ta TS requirements.
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Required test instrumentation was calibrateo.
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Technical Specification limiting conditions for operation were
p satisfied.
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- - Test data was accurate and complete. The NRC inspectors performed
kt independent calculations of' selected test data to verify thef r
accuracy.
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The performance of the' surveillance procedure conformed to
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applicable administrative procedures.
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The surveillance was performed within'the required 'requency ~and '
the test results met the required limits.
Surveillances witnessed and/or reviewed by the NRC inspectors are listed
below:
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- STS NB-005, Reyision 3 - Breaker Alignment Verification
- STS BG-002, Revision 3 - Emergency Core Cooling System Valve Check
and System Vent
- STS KJ-005B, Revision 4 - Manual / Auto Start, Synchronization, and
Loading of Emergency Diesel Generator NE02
- STS EF-100, Revision 3 - Essential Service Water Inservice Pump
Test (ESWP-A')
- STS RE-013, Revision 1 - Incore-Excore Detector Calibration
No violations or deviations were identified.
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8. Security
The ilRC inspectors verified the physical security plan was being
implemented by selected observation of the following items:
. The security organization is properly manned and the security
personnel are capable of performing their assigned functions.
. Persons within the protected area (PA) display their identification
badges, when in vital areas are properly authorized and when
1 required are properly escorted.
. Vehicles are properly authorized, searched, and escorted or
controlled within the PA.
. Persons and packages are properly cleared and checked before entry
'into the PA is permitted.
.. . The effectiveness of the security program is maintained when
security equipment failure or impairment requires compensatory
measures to be employed.
. Response to threats or alarms, or discovery of a condition that
appears to require additional precautions is consistent with
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procedures and the physical security plan.
No violatioils or deviations were identified.
9. Emergency Drills
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During this reporting period, the NRC inspectors participated in three
emergency preparedness field exercises conducted at WCGS. The WCGS
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, training simulator was used to simulate reactor plant conditions during
the' accident scenarios. Players in the drills performed the tasks they
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would perform durir.g an actual event.
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( - a. Drills held on October 23 and November 6,1985:
The pu'rpose of these drills was to train appropriate personnel to
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) respond to a~ radiological emergency at WCGS. These drills were
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_ also used to test emergency equipment, emergency facilities,
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- emergency procedures, and emergency communications.
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b. DhillheldonNovember 20, 1985:
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- The purpose of:this drill was to perform the annual NRC and Federal
Emergency Management Agency (FEMA) evaluation of the capability of
the licensee, the county, and the state to respond during a
radiological emergency at WCGS. Onsite activities were evaluated
by the NRC and offsite (county and state) activities were evaluated
by FEMA.
NRC observations and findings of the licensee's activities will be
,
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reported in NRC~ Inspection Report 50-482/85-40. The drill was also
used to perform the annual evaluation of the NRC Region IV staff's
capability to respond to a radiological emergency at one of the
commercial reactor plants that is regulated by Region IV.
Some of the related activities that took place during the drill
were:
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Emergency response facilities were activated at Ramson
Memorial Hospital, Ottawa, Kansas, to treat a simulated
contaminated worker.
- Coffey County Response Center was activated.
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State emergency response faci 3ities were activated.
- The NRC Headquarters Operations Center (Bethesda, MD) was
activated and all emergency response team functions were
staffed. The Operations Center staff provided support to the
. licensee and the regional response team during the drill.
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The Region IV Incident Response Center was activated and a
Region IV site emergency response team reported to the sit,
and participated in the drill.
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Evacuation of affected areas around WCGS was si"Jlated
v including the evacuation of the public schools in Burlington,
- Xansas.
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-10.s Enforcement Conference
On November 25, 1985, en enforcement conferencc with KG&E managenent was
held in the NRC Regio. .IV offices to discuss NRC concerns in the area of
security at WCGS. The event that generated the NRC concerns had been
identified by;the licensee and reported to the NRC. Details of the NRC
e concern will-be~ reported in NRC Inspection Report 50-482/85-44.
Licensee representatives at the enforcement conference described
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corrective actions'that were being taken in the area of concern.
11. Cold Weather-Preptrations
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.The NRC inspector verified by reviewing a completed copy of the
licensee's Procedure STN GP-001, Revision 0, " Plant Winterization," that
the licensee had taken action to protect vital areas and equipment that'
could be subject to freezing conditions. The procedure verified valve
lineup for steam heat to these areas and also verif_ied electrical
-breaker lineups to ensure equipment in these areas such as space heaters
and_ heat tracing was energized. The NRC, inspector walked down areas
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adjacent to the Vefueling water storage tank and the condensate storage
z tank and verified that lines = (heating and instrument) were insulated
Ewhere they could be subjected to freezing conditions, and that steam was
being supplied to the area:for heat..
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No violations er deviations.were identified. ,
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.12. Plant Tours
At various times during' the course of,the inspection period the NRC
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- -inspectors conducted general tours of the reactor bui saing, auxiliary
building, radwaste building, fuel handling building, control building,
turbine ~ building, essential service water b 1L1 4ng .and the secured area
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surrounding tl'e buildings. During the tcurs, the NRC inspectors
observed housekeeping practices, fire protecticn barriers and equipment,.
end maintenance on equipment. The NRC irspcctors also discussed various
subjects with licensee personnel.
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Selected NRC inspector findings are discussed in appropriate paragraphs
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of this' inspection report.
13. Exit Meeting
The NRC inspectors met with licensee personnel to discuss the scope and
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findings of this inspection on December 5,1985. The NRC inspectors
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