ML20137U647
| ML20137U647 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/12/1986 |
| From: | Bruce Bartlett, Cummins J, Hunnicutt D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137U613 | List: |
| References | |
| 50-482-86-01, 50-482-86-1, NUDOCS 8602190275 | |
| Download: ML20137U647 (8) | |
See also: IR 05000482/1986001
Text
--
-.
'
'
/
?-
'
, ,
.,
Y
Y,
.
_
h
5
%
APPENDIX B
'~i'
US NUCLEAR REGULATORY COMMISSION
t
NRC Inspection Report: 50 Ie82/86-01
LP: NPF-42
,
Docket': 50-482 '
,
Licensee: = Kansas Gas and Electric Company (KG&E)
Post Office Box 203
'
,
Wichita, Kansas 67201
l '.
~
Facility Name: Wolf Creek Generating Station (WCGS)
.
l
Inspection At: . Wolf Creek Site, Coffey County, Burlington, Kansas
,
'
Inspection / Conducted: January 5 to 31, 1986
,
_
' Inspectors-
k
y2,//4/8/
,
J. E. Cuaunins, Senior Resident Inspector,
/ Da t'e
,
Operations
<
.
%
'
%La
2b.u'n
'
B. L. Bar'tlett,' Resident Reactor Inspector,
-' Date
.
~_
'
Operations-
.,
Approved:
h/
10- 8
,!/4/RI.
D. M. Hunnicutt, Acting Chief, Project
Dat6.
d
Section B, Reactdr Projects Branch
.
s
Inspection Sununary
,
n
Inspection Conducted January 5 to 31, 1986 (Report 50-482/86-01)
~
Areas Inspected: Routine, unannounced inspection including plant status;-
ifollowup on previously identified NRC items; operr*ional safety verification;
'
i.
engineered' safety features system walkdown; onsite followup of events; licensee
!
event report (LER) review; monthly maintenance observation; monthly surveillance
-
observation; and plant tours. The inspection involved 148 inspector-hours onsite
>
by two NRC inspectors including 12 inspector-hours onsite during offshifts.
Results: Within the nine areas inspected, one violation was identified (failure
.. , 7 to comply with licensee's temporary modification procedure, paragraph 10).
I
Na
[D
J2
L
e
i
L
a
-
,-
.
,
.
=s;
-n
1
L
.
,
-2-
DETAILS
1.
Persons Contacted
Principal Licensee Personnel
'
G. L. Koester, Vice President-Nuclear
- J. A. Bailey, Interim Site-Director
- F. T. Rhodes, Plant Manager
.,
R. M. Grant, Director-Quality
- G. D. Boyer, Superintendent of Technical Support
- J.
A. Zell, Superintendent of Operations-
- M. D. Rich, Superintendent of Maintenance
- M. G. Williams, Supt.. of Regulatory, Quality, and Administrative
Services
H. K. Chernoff~, Licensing
K. Peterson, Licensing
G. Pendergrass, Licensing
- W. M. Lindsay, Supervisor Quality Systems
- C. J. Hoch, QA Technologist
- A. A. Freitag, Manager of Nuclear Plant Engineering, WCGS
- C, M. Herbst, Project Engineer, Bechtel
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
Janua ry 31, 1986.
2.
Plant Status
.
,The plant operated in Mode 1 during this inspection period.
.
3.
Followup on Previously Identified NRC Items
'
(Closed) Open Items (50-482/8508-07 and 8508-09):
Issuance of
Surveillance Procedures.
These open items tracked the issuance of surveillance procedures that had
not been issued at the time of the inspection. The NRC inspector verified
the following surveillance procedures had been issued:
STS IC-214, Rev. 1, Trip Actuating Device Operational Test Phase A
-
Containment Isolation Manual Initiation
STS IC-225, Surveillances in this STS were incorporated into STS
-
GT-003, Rev. O, CPIS Manual Test, therefore STS IC-225 was
cancelled.
,
_ _ . _ _ _ _ -
i.
. ,
.e
-3-
i,
f
STS IC-229A, Rev. 0- Actuation Logic Test Load Shedder and
-
Emergency Load Sequencer Group I (Red).
STS IC-229B, Rev. 0- Actuation Logic Test Load Shedder and
-
Emergency Load Sequencer Group IV (Yellow).
STS NT-054, Rev. 1 - Feedwater Venturi Inspection.
-
.T ese items are closed.
h
(Closed) Open Item (50-482/8459-09): System Restoration Instructions in
Preoperational Test Procedures.
The following startup test procedures were reviewed to verify that they
contained comprehensive instructions for system restoration upon
completion of testing:
SU7-0009.1, Rev. 1, Thirty Percent Power Load Swing Test Section
-
8.0 System Restoration.
SU7-SF06.3, Rev. 1, Operational Alignment of Process Temperature
-
Instrumentation Section 8.0 System Restoration.
-
SU7-SF09.1, Rev. 1, RCCA or Banks Worth Measurement at Power (30%
Power Pseudo Rod Ejection).
SU7-S0ll, Rev. 1, Initial Criticality and Low Power Test Sequence.
-
, .
SU7-SR03, Rev. 1, Incore Movable Detector Test
-
SU7-S010, Rev. 2, Post Core Loading Precritical Test Sequence.
-
This item is closed.
(Closed) Open Item (50-482/8504-01):
Incorporation of Certain Evacuation
,
'
Activities into Procedures.
This open item tracked the incorporation in appropriate procedures of
instructions for the evacuation of nonessential personnel from the plant
evacuation initial assembly point for those personnel who do not have
-
transportation immediately available to them.
Instructions to cover this
situation have been incorporated in Wolf Creek Radiological Emergency
,
Respsnse Plan Implementing Procedure EPP 01-2.2, " Activation of Emergency
Plan / Organization. This procedure, in Attachment 2.0, " Initial
Announcement," and Attachment 3.0, " Reclassification Announcement," states:
"If you do not have a vehicle try to ride with someone else who has a
I
vehicle or notify security."
[
This item is-closed,
i
i
(Closed) Open Itam (50-482/8459-08):
Discrepancy in Starttp Procedure.
This open item was initiated to track a discrepancy in Power Ascension
Test Procedure SU7-SF09.2, Revision 0, "RCCA or Bank Worth Measure at Power
(50% Pseudo Rod Drop)."
!
1
I
.
L
-
.
.
-4-
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, interview of personnel, and review of
documents, verified the physical security plan was being implemented in
accordance with the security plan and that radiation protection activities
were controlled.
By observing valve position,-electrical breaker position, and control room
indication, the NRC inspectors confirmed the operability of the safety
injection system, residual heat removal system, and the containment spray
system. 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 operability 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 could
degrade system performance.
The ESF systems listed below were walked down during this inspection
report period:
Class IE 4160 Volt AC Electrical Systems
-
Auxiliary Feedwater System
-
-
Class IE 120 Volt DC Electrical Systems
No violations or deviations were identified.
6.
Onsite Followup of dvents
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 computer
printouts, and discussed the event with cognizant personnel.
The NRC
inspectors verified the licensee had responded to the event in accordance
with procedures and had notified the.NRC and other agencies as required in
a timely fashion.
-
_
,
.
, .
-
-,
9_
,
-
.
-
- -
<
. . ,
-5-
ESF actuations that occurred during the report period are listed in the
table.below. The NRC inspector will review the license event report (LER)
for each of these events and will report any findings in subsequent NRC
inspection reports.
Date
Event
Plant Status
Cause
1/04/86
CRVIS*
Mode 1
Broken paper sensing
tape in chlorine monitor
>
1/04/86
CRVIS*
Mode 1
Blown fuse on chlorine
monitor
- CRVIS - control room ventilation isolation signal
No violations or deviations were identified.
7.
Review of Licensee Event Reports (LERs)
'
.
During this inspection period, the NRC inspectors performed followup on
selected Wolf Creek LERs. The LERs were reviewed to ensure:
The corrective action stated in the report has been properly
-
completed.
'
Responses to the events were adequate.
-
Responses to the events met license conditions, commitments, or other
-
applicable regulatory requirements.
-The information contained in the report satisfied applicable'
-
reporting requirements.
That any generic issues were identified.
-
The report conformed to the guidelines contained in NUREG-1022 and
4
-
Supplements 1 and 2.
The following LERs were reviewed and closed.
'
'50-482/85-024-00, "ESF Actuation-Feedwater Isolation, Auxiliary
-
Feedwater Actuation"
50-482/85-025-00, " Condition Prohibited.by Technical
-
Specifications"
50-482/85-026-00, "ESF Actuation-Containment Purge, Fuel Building,
-
and Control Room Ventilation Isolation"
50-482/85-027-00, "ESF Actuation-Safety Injection and Main
-
Steamline Isolation"
50-482/85-028-00, "ESF Actuation-Auxiliary Feedwater Actuation"
-
- .
50-482/85-029-00, "ESF Actuation-Containment Purge Isolation, Fuel-
-
Building and Control Room Ventilation Isolation"
53-482/85-030-00, "ESF Actuation-Feedwater Isolation"
-
50-482/85-031-00, "ESF Actuation-Feedwater Isolation, Auxiliary
-
Feedwater Actuation, Steam Generator Blowdown and Sample
Isolation"
l
-
-
.
. . .
-6-
50-482/85-032-00, "ESF Actuation-Containment Purge and Control
-
Room Ventilation Actuation"
-
50-482/85-033-00, "ESF Actuation-Control Room Ventilation Isolation"
-
50-482/85-034-00, " Technical Specification Violation"
50-482/85-036-00, "ESF Actuation-Feedwater Isolation, Auxiliary
-
Feedwater Actuation, Steam Generator Blowdown and Sample Isolation"
50-482/85-037-00, "ESF Actuation-Control Room Ventilation Isolation"
-
50-482/85-038-00, "Auxilia ry Feedwater Actuation"
-
50-482/85-039-00, "ESF Actuation and Reactor Trip on Low Steam
-
Generator Level"
50-482/85-040-00, "ESF Actuation-Control Room Ventilation Isolation"
-
No violations or deviations were identified.
8.
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:
-
Limiting conditions for operation (LCO) 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 qual',fi'ed to accomplish the designated task and
technical expertise (i.e., engineering, health physics, operations)
were made available when appropriate.
Replacement parts and materials being used were properly certified.
-
Required radiological controls were implemented.
-
Fire prevention controls were implemented where appropriate.
-
Required alignments and surveillances to verify post maintenance
-
operability were performed.
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 (WR) listed below were observed and related documentation
reviewed by the NRC inspector:
WR 00310-86, Containment 11 Analyzer, GS 0658-II Analyzer 8 Pan
-
2
2
is extremely low.
WR 50146-86, Three month inspection and lubrication of the
-
personnel air lock during operation.
No violations or deviations were identified.
1
- -
-
,
-
- --
,
.
-
_.
_
. - - -
- - -
-
4 .
. .: s
,
-7-
9.
Monthly Surveillance Observation
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
Technical Specifications (TS) requirements and administrative procedures.
The NRC inspectors considered the following items while inspecting
surveillance activities:
Testing was being accomplished by qualified personnel in accordance
-
with an approved procedure.
The surveillance procedure conforms to TS requirements.
-
Required test instrumentation was calibrated.
-
TS limiting conditions for operation were satisfied.
-
Test data was accurate and complete. The NRC inspectors performed
-
independent calculations of selected test data to verify their
accuracy.
The performance of the surveillance procedure conformed to applicable
-
administrative procedures.
The 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:
STS NB-005, Rev. 3, " Breaker Alignment Verification"
-
STS KJ-005A, Rev. 5, " Manual / Auto S art, Synchronization, and Loading
-
of Emergency Diesel Generator NE01"
-
STS IC-915, Rev. 2, " Analog Channel Operational Test Component
-
Cooling Water Non-nuclear Safety-Related"
STS KJ-005B, Rev. 4, " Manual / Auto Start, Synchronization, and
-
Loading Of Emergency Diesel Generator NE02"
STS IC-913, Rev. 3, " Containment Hydrogen Analyzer GS 065B
-
Calibration Test"
STS PE-013, Rev. 4, " Personnel Airlock Seal Test"
-
-
No violations or deviations were identified.
10.
Plant Tours
At various times during the course of the inspection period the NRC
inspectors conducted general tours of the reactor building, auxiliary
building, radwaste building, fuel handling building, control building,
turbine building, essential service water building, and the secured area
surrounding the buildings.
During the tours, the NRC inspectors observed
housekeeping practices, fire protection barriers and equipment, and
maintenance on equipment. The NRC inspectors also discussed various
subjects with licensee personnel.
t
l
_
.. . .
.
.
-8-
Selected NRC inspector observations are discussed below:
On January 23,1986, on the 2026' level (northeast corner) of the
auxiliary building, the NRC inspector observed that a temporary modifica-
tion had been made in that safety-related flexible Electrical
Conduit IJ1E1D was tied cff with wire to Essential Service Water Pipe
Support 1-EF02-R009/134Q. The licensee has established and implemented
Administrative Procedure (ADM)02-101, Revision 13, " Temporary Modifica-
tion," to control temporary modifications; however, the actions required by
Procedure ADM 02-101 had not been performed to install the temporary
modification described above.
This failure to control this temporary modification in accordance with an
established procedure is an apparent violation.
(50-482/8601-01) When
this condition was identified to licensee personnel, they took immediate
action and removed the wire attaching the flexible conduit to the pipe
support, returning the installation to design configurations.
10.
Exit Meeting
The NRC inspectors met with licensee personnel to discuss the scope and
findings of this inspection on January 31, 1986. The NRC inspectors also
attended entrance / exit meetings of other NRC region based inspectors
identified below:
Inspection
Area
-Inspection
Period
Inspector
Inspected
Report No.
1-27/31-86
J. Kelly
Security
86-03