ML20206Q652
| ML20206Q652 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/15/1987 |
| From: | Bruce Bartlett, Boardman J, Cummins J, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20206Q630 | List: |
| References | |
| 50-482-87-06, 50-482-87-6, NUDOCS 8704220012 | |
| Download: ML20206Q652 (9) | |
See also: IR 05000482/1987006
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APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-482/87-06
LP:
Docket:
50-482
Licensee: Wolf Creek Nuclear Operating Corporation (WCNOC)
P. O. Box 411
Burlington, Kansas 66839
Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas
Inspection Conducted: March 1-31, 1987
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Inspectors:
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,. E. Cdmmins, Senior Resident Inspector,
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Operations
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B. L. Bartlect, Resident Reactor Inspector,
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R. Boirdman, Reactor Inspector,
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peration Section, Reactor Safety Branch
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Approved:
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D.7 . Hunter, Chief, Reactor Project
Date
Section B, Reactor Projects Branch
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Inspection Summary
Inspection Conducted March 1-31, 1987 (Report 50-482/87-06)
Areas Inspected: Routine, unannounced inspection including _ plant status,
operational. safety verification, monthly surveillance observation, monthly
maintenance observation, onsite event followup, corrective action, and
licensee event reports.
Results: Within the seven areas inspected, one violation was identified
(fire door blocked open, paragraph 4). One unresolved item is identified
in paragraph 4.
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DETAILS
1.
Persons Contacted
Principal Licensee Personnel
- G. D. Boyer, Plant Manager
0. L. Maynard, Manager of Licensing
- C. M. Estes, Superintendent of Operations
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M. D. Rich, Superintendent of Maintenance
- M. G. Williams, Superintendent of Regulatory, Quality, and
Administrative Services
W. J. Rudolph, QA Manager-WCGS
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- A. A. Freitag, Manager, Nuclear Plant Engineering-WCGS
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M. Nichols, Plant Support Superintendent
- K. Peterson, Licensing
- G. Pendergrass, Licensing
- W. M. Lindsay, Supervisor Quality Systems
C. J. Hoch, QA Technologist
The NRC inspectors also contacted other members of the licensee's staff
during the inspection period to discuss identified issues.
- Denotes those personnel in attendance at the exit meeting held on
April 1, 1987.
2.
Plant Status
The plant operated in Mode 1 during this inspection period.
3.
Followup of Previously NRC Identified Items
(Closed) Violation (482/8608-03):
Failure to Adequately Perform TS
Surveillance Requirement.
This violation identified a situation where the stroke distance on two
valves was adjusted improperly to meet the stroke time requirements. The
NRC inspector reviewed the following documents to verify that the valve
stroke distance was corrected and that no other valves had been modified
in the same manner: WCGS. Internal Operations Program Deficiency 86-02,
Plant Modification Request 01669, Work Request (WR) 01694-86, and
Engineering Evaluation Request 86-AL-01. This violation is closed.
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(Closed) Open Item (482/8605-02):
Essential Service Water Inside
Auxiliary Feedwater System.
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This open item was being.used to track the licensee's actions following
the inadvertent introduction of ' essential service water into portions of
the auxiliary feedwater system (AFW). The licensee flushed the AFW system
and during the first refueling outage all steam generat]rs were sludge
lanced. This open item is closed.
(Closed) Violation (482/8613-02):
Data Not Recorded On a Work Request
(WR) As Required.
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This violation concerned a completed WR which did not have all the data
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recorded that was required. The NRC inspector verified that the violation '
had been placed in the electrical and mechanical maintenance required
reading program. Mechanical maintenance had completed the required
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reading, while electrical maintenance was nearly finished with the
required reading. This violation 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
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
NRC inspectors confirmed the operability of the safety injection system.
The NRC inspectors also visually inspected safety components for leakage,
physical damage, and otner 1mpairments that could prevent them from
performing their designed functions.
Selected NRC inspector observations are discussed below:
On March 25, 1987, during a routine tour of the control room, the NRC
inspector reviewed three Wolf Creek Work Request (WR) that had been
written on containment isolation valves.
The WRs were on Valves
BG HV-8105, GT HZ-6 and LF FV-96 and were written to inspect and
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repair, as necessary, valve internals during the next refueling
outage. Retest instructions were written to perform local leak rate
tests (LLRT). Upon questioning Results Engineering personnel, the
NRC inspector determined that the valves had exhibited some leakage
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during the last LLRT, but that the leakage was within acceptance
criteria and that the maintenance was to be performed as a
precaution.
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The licensee stated that an 'as-found' LLRT would not be performed
prior to maintenance. The 10 CFR Part 50,_ Appendix J, section III.c.
requirements state. in part, "Each valve to be tested shall be closed
by normal operation and without any preliminary exercising or
adjustments '. . . ." The NRC inspector informed the licensee that in
his opinion Section III.c required that the valves be tested in the
'as-found' condition and that a LLRT should be performed prior to
valve internal maintenance.
Pending further review, this item will
remain unresolved (482/8706-02).
On March 4, 1987, during a routine tour of the 2016 ft. elevation of
the control building, the NRC inspector observed that TS Fire Door
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34031~had an air' hose running through it, blocking it open and
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thereby preventing it from performing its design function. After
checking the surrounding area and not finding any workers, the NRC
inspector called the control room supervisor operator (S0). The SO
stated that'no fire impairment permit had been issued for Door 34031.
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As the NRC inspector was leaving the area, a worker was seen
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adjusting the air hose. . Upon questioning, the worker stated he had
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blocked the door open with his air hose in order to reach the only
air connection on that floor and that he had not initiated an
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impairment permit. This failure to get a fire impairment permit as
required by plant procedures is an apparent violation (482/8706-01).
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5.
Monthly Surveillance Observation
The NRC inspectors observed selected portions of the performance of
surveillance testing and/or reviewed completed surveillance test
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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
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activities:
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Testing 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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Required test instrumentation was calibrated
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Technical Speciffcation limiting conditions for operation (LCO) were
satisfied
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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
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The performance of the surveillance procedure conformed to applicable
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administrative procedures
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lhe surveillance was performed within the required frequency 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 BG-001, Revision 3, " Boron Injection Flow Path Verification,"
performed on December 27, 1986
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STS BG-003, Revision 3, '"Boration System Flow Rate Verification,"
performed on October 17, 1986
No violations or deviations were identified.
6.
Monthly Maintenance Observation
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:
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LCOs were met and, where applicable, redundant components were
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Activities complied with adequate administrative controls
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Where required, adequate, approved, and up-to-date procedures were
used
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Craftsmen were qualified to accomplish the designated task and
technical expertise (i.e., engineering, health physics, operations)
was made available when appropriate
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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
operability were performed
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Quality control hold points and/or checklists were used when
appropriate and quality control personnel observed designated work
activities
Selected portions of the maintenance activities accomplished on the work
requests listed below were observed and related documentation reviewed by
the NRC inspector:
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WR 52341-86,." Annual Maintenance Of Para Blade Isolation Dampers"
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"WR 00727-87, " Para Blade Isolation Damper GGD-019"
No violations or deviations were identified.
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7.
Onsite Event Followup
The NRC inspector performed onsite followup of a nonemergency event that
occurred during this report period. The NRC inspector reviewed control
room logs and discussed the event with cognizant personnel.
The NRC
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' inspector verified the licensee had responded to the event in accordance
with procedures and had notified the NRC and other agencies as required in
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a timely fashion. An engineered safety feature actuation that occurred
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during the. report period is listed in the table below. The NRC inspector
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will review the LER for this event and will report any findings in a
subsequent NRC inspection report.
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Date
Event
Plant Status
Cause
3/09/87
CRVIS*
Mode 1
Spurious spike
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- Control Room Ventilation Isolation System
No violations or deviations were identified.
8.
Corrective ~ Action
The NRC inspector discussed with licensee personnel the corrective action
aspects of licensee management systems and procedures.
No violations or deviations were identified.
9.
Review of Licensee Event Report (LER)
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During this inspection period, the NRC inspectors performed followup on
Wolf Creek LERs. The LERs were reviewed to ensure:
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Corrective action stated in the report has been properly completed or
work is in progress.
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Response to the event was adequate.
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Response to the event met license conditions, commitments, or other
applicable regulatory requirements.
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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:
LER 482/86-057: Unplanned Engineered Safety Features Actuation During
Surveillance Testing,
ihisLERreportedaneventwherean.unplannedTrainAandB-fuelbuilding
ventilation isolation signal (FBVIS) and Train A control room ~ ventilation
isolation signal (CRVIS).were initiated because of.the presence of a trip.
-signal from Radiation Monitor GG RE-27. The trip signal was generated by-
the simultaneous. performance of two surveillance tests and a personnel-
error in removing GG RE-27 from the bypass condition. The LER was made
required reading for operating personnel.
LER-482/86-053: Delay In Establishing Required Fire Watch For Fire
Protection Impairment.
This LER reported an event where the shift supervisor (SS) issued an
impairment control permit to establish an hourly fire watch patrol of an
auxiliary feedwater alternate supply valve to compensate for the removal
of the fire barrier enclosure around the valve, but failed to notify the
fire watch patrol to add the area to their watch. The LER was made
required reading for operating personnel.
LER 482/86-050: TS Violation Caused By Incomplete' Closure Of Fire Door.
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This LER reported an event where an NRC inspector on a routine plant tour
discovered a fire door had been blocked open and unattended. . It was later
determined that contractor personnel had been holding the door open for
ventilation while cleaning up a charcoal spill, but on leaving the area
for shift turnover had left the door open. Discussions were held with the
involved personnel and their foreman emphasized the importance of TS fire
barriers.
In addition, TS fire doors have been posted.
10. Unresolved Item
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Unresolved items are ir.atters about which more information is required in
order to ascertain whether they are acceptable items, items of
noncompliance, or deviations. An unresolved item disclosed during the
inspection is discussed in paragraph 4.
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11. Exit Meeting
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The NRC inspectors met with licensee personnel to discuss the scope and
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findings of this inspection on April 1,1987. The NRC inspectors also
attended entrance / exit meetings of the NRC region-based inspectors
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identified below:
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Inspection
Lead.
Area
Inspection
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Period
Inspector
Inspected.
Report No.
03/02-06/87
B. Nicholas
Transportation
87-08
and Solid Rad-
waste Activities
03/02-06/87
J. Kelly
Security
87-07
03/16-17/87'
J. Boardman
Corrective Action 87-06
Program
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