ML20197A669
| ML20197A669 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/21/1986 |
| From: | Bruce Bartlett, Jamarl Cummings, Cummins J, Hunicutt D, Hunter D, Lummins J, Mullikin R, Greg Pick, Sharkey J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20197A608 | List: |
| References | |
| 50-482-86-17, NUDOCS 8610270366 | |
| Download: ML20197A669 (14) | |
See also: IR 05000482/1986017
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APPENDIX B
US NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-482/86-17
License Permit: NPF-42
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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: July 6 to August 2, 1986
Inspectors:
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J. E. Cumins, Senior Resident Inspector,
Date
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Operations
(pars. 3, 5, 7, 8, and 13)
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B. L. Bartlett, Resident Reactor Inspector,
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Operations
(pars. 3, 4, 5, 6, 7, 8, 11, 12, and 13)
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R. P. Mullikin, Project Inspector
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D. M. Hunnicutt, Chief, Operations Section
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Reactor Safety Branch
(pars. 9 and 10)
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G.~ A. Pjft;k
eactor Inspector
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(pars. % a
10)
8610270366 861022
ADOCK 05000482
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J. M. Sharkey, Inspection Specialist
Date
'(pars. 4, 5, 6, and 8)
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Approved:
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H'. Flu ~nter, Chief,, Project Section B
Date
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Reactor Projects Branch
Inspection Summary
Inspection Conducted July 6 to August 2, 1986 (Report 50-482/86-17)
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Areas Inspected: Routine, unannounced inspection including plant status;
followup on previously identified NRC items; LER review; operational safety
verification; engineered safety features system walkdown; onsite followup of
events; monthly surveillance observation; QA program annual review; design
changes; core thermal power evaluation; and radwaste processing.
Results: Within the 11 areas inspected, one violation was identified
(failure to perform activities in accordance with specified procedure,
paragraph 4).
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DETAILS
1.
Persons Contacted
Principal Licensee Personnel
G. L. Koester, Vice President-Nuclear
+*J.-A. Bailey, Interim Site Director
+ F. T. Rhodes, Plant Manager
- G. D. Boyer, Deputy Plant Manager
+ R. M.~ Grant, Director-Quality
M. Estes, Superintendent of Operations
'i. D. Rich, Superintendent of Maintenance
+*M. G. Williams, Superintendent of Regulatory, Quality, and
Administrative Services
0. L. Maynard, Manager Licensing
+*K. Peterson, Licensing
+*G. Pendergrass, Licensing
+*W. M. Lindsay, Supervisor Quality Systems
+*C. J. Hoch, QA Technologist
+*W. J. Rudolph, QA Manager-WCGS
+ C. G. Patrick, Superintendent of Quality Evaluations
+ C. E. Parry, Superintendent of Quality Engineering
+*A. A. Freitag, Vanager Nuclear Plant Engineering-WCGS
+ D. A. Liston, Nuclear Plant Engineering
M. Megehee, Compliance Engineer
B. McKinney, Superintendent of Technical Support
+ P. E. Nichols, QA-Wichita
+ L. W. Stevens, ISEG
+ C. F. Kesinger, HP Training Coordinator
M. Isom, Health Physics Supervisor-Radwaste
R. C. Richardson, Radwaste Coordinator
J. Ives, Jr. , Manager Health Physics
- G. A. McClelland, QA Auditor
- S. A. Henry, Chemistry Supervisor
- J. Hawthorne, Chemistry Supervisor
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
August 4, 1986.
+ Denotes those personnel in attendance at the exit meeting held on
July 18, 1986.
2.
Plant Status
The plant operated in Mode 1 during this inspection period except during
the time periods described below:
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On July 24,1986 the plant was shut down to Mode 3 to repair a stator
cooling water leak in the main generator. During the controlled
shutdown, the reactor tripped.at approximately 13 percent power due to a
1o-10 steam generator water level condition. The plant was returned to
Mode 1 on July 26, 1986.
3.
Followup on Previously Identified NRC Items
(Closed) Violation (482/8526-02): Temporary changes not incorporated in
procedure as required.
The NRC inspector verified by review that the licensee's surveillance
procedure cover sheet has been revised to require that the test
performer verify that the latest revision of the surveillance test is
being used. This item is closed.
(Closed) Violation (482/8535-05): Failure to follow housekeeping
requirements.
The licensee took immediate action and cleaned up the areas which
created the housekeeping concerns identified in this violation. On
subsequent walkdowns, the NRC inspectors have observed that housekeeping
was being maintained as required. This violation is closed.
(Closed) Violation (482/8538-01): Failure to establish procedures for
certain activities that could affect the performance of safety-related
equipment.
The NRC inspector, by review of documents and plant walkdowns, verified
the following licensee actions related to this violation:
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Section 5.3.2 of Administrative Procedure ADM 01-034, Revision 8,
" Housekeeping and Cleanliness Control," has been revised to state
that hoist hooks shall be fully raised and ladders returned to
their designated storage location.
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Permanent storage brackets for ladders have been installed at
seventeen locations in the plant and have been identified by signs.
Storage of ladders was discussed at the safety committee meeting
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held on April 2, 1986. Safety meetings were used to train
employees in the use of ladders.
During subsequent plant walkdowns, the NRC inspectors have not
identified any further instances where ladders and hoists could have
affected the operation of safety-related equipment. This violation is
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closed.
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(Closed) Violation (482/8523-01): Failure to follow plant procedures.
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The NRC inspector reviewed the letter which was issued to all
organizations which may be called upon to perfonn work in the plant and
verified that it was discussed with the appropriate personnel.
In addition,
since this violation was first identified no other similar violations
have been discovered. This violation is closed.
(Closed) Violation (482/8530-01): Test port not reclosed in accordance
with procedure.
The NRC inspector reviewed five randomly selected procedures which
remove plugs in HVAC test ports and verified the procedures included
clear requirements to reinstall plugs in test ports.
In addition, field
inspections by NRC inspectors have failed to identify any similar
violations to date. This violation is closed.
(Closed) Violation (482/8530-02):
Inadequate procedure.
The NRC inspector reviewed STS IC-275A and STS IC-275B and verified that
the requirement for damper movement had been removed.
In addition, the
sample results of the containment atmosphere drawn at 2100 CST on
July 26, 1985, was reviewed for abnormal results. This violation is
closed.
4.
Review of Licensee Event Reports
During this inspection period, the NRC inspectors performed followup on
selected Wolf Creek LERs. The LERs were reviewed to ensure:
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The corrective action stated in the report has been properly
completed.
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Responses to the events were adequate.
Responses to the events met license conditions, commitments, or
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other applicable regulatory requirements.
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The information contained in the report satisfied applicable
reporting requirements.
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That any generic issues were identified,
The report conformed to the guidelines contained in NUREG-1022 and
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Supplements 1 and 2.
The following LERs were reviewed and closed.
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482/85-041-00, "ESF Actuation and Reactor Trip"
482/85-042-00, " Engineered Safety Features Actuation and Reactor
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Trip"
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482/85-043-00, "Feedwater Isolation and Auxiliary Feedwater
Actuation"
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482/85-044-00, "ESF Actuation-Feedwater Isolation, Auxiliary
Feedwater Actuation, Steam Generator Blowdown
and Sample Isolation"
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482/85-045-00, " Reactor Trip and Engineered Safety Features
Actuation"
'482/85-046-00, " Engineered Safety Features Actuation and Reactor
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Trip"
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482/86-019-00, " Technical Specification Required Shutdown Due To
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Unidentified Reactor Coolant System Leakage"
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482/86-033-00, " Technical Specification-Late Verification of Fuel
Oil Properties"
The NRC inspectors had the following comments:
ApplicableportionsofAdministrativeProcedure'ADM01-033,
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'" Instructions Describing Reportability, Review, and Documentation
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of Licensee Event Reports (LERs), and Defect Deficiencies,"
Revision 15, were reviewed for agreement with LER reporting
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requirements,
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In general, the quality and adequacy of the licensee's LERs has
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been improving.
However, minor deficiencies were noted in the LER
information requirements. For example, five out of six LERs
reviewed did not discuss whether any previous similar events at the
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plant were known to.the licensee. These deficiencies were
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discussed with the licensee during this inspection period.
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During an inspection of control room area radiation monitor
instrunentation and chart recorders while following up on LER 482/86-019-00, the NRC inspector noted that Chart Recorder GT RR-58,
" Unit Ventilation Effluent Release Rate," and GH RR-51, "Radwaste
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Building Effluent Release Rate," were not scaled, but did have a tag
saying 0 to 100. None of the licensed operators questioned knew
what units the chart recorders used.
Instrumentation and control
informed the NRC inspector that the chart recorders were calibrated
from 10E1 to 10E13 micro Ci/sec. The licensee committed to install
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the correct scales.
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-0n July 18,1986,'during a review of completed surveillances
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related to LER 482/86-033-00, the NRC inspector observed that
STS CH-008A, " Emergency Diesel Fuel Storage Tank," performed on
June 1, 1986, was Revision 3 and that the data sheet for STS CH-0088,
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" Emergency Diesel Fuel Storage Tank," had been used. The plant safety
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STS CH-C08A, Revision 4 had been issued on May 14, 1986. The
records review indicated that the appropriate tank was sampled and
that the sample data met the TS criteria. This failure of the test
performer to use the correct procedure and revision, even though he
had signed off in Section 1 of the cover sheet that he had used the
correct procedure and revision, and failure of the surveillance
ost-performance review cycle to discover this error is a violation.
482/8617-01)
5.
Operational Safety Verification
The NRC inspectnrs 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
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with licensee personnel, independent verification of safety system
status and limiting conditions for operations, and reviewing facility
records. The NRC inspectors, by observation and direct interview,
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
residual heat removal system and the emergency diesel generators.
The NRC inspectors also visually inspected safety components for
leakage, physical damage, and other impairments that could prevent them
from performing their designed function.
No violations or deviations were identified.
6.
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 fcr damage or other
conditions that could degrade system performance.
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The ESF system walked down during this inspection period and the
documents utilized by the NRC inspectors during the walkdown are listed
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below:
System
Documents
Essential Service Water (EF)
Drawing M-K2EF01, Revision 14, ESW
P&ID(Q)
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Drawing M-02EF01, Revision 10, ESW
P&ID(Q)
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Drawin M-02EF02, Revision 12, "ESW
P&ID Q)"
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STS EF-001, Revision 3, " Essential
Service Water Valve Check"
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' Checklist CKL EF-120, Revision 8,
" Essential Service Water Valve,
Breaker, and Switch Lineup"
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No, violations ~or deviations were identified.
7.
Onsite Followup'of Event
The NRC' inspectors performed onsite followup of a reactor trip that
' occurred on July 24,'1986, due to a 10-10 steam generator water level
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condition. The NRC inspectors reviewed logs and computer printouts and
discussed the~ trip.with cognizant personnel. The NRC inspectors
verified the licensee had responded to the event in accordance with
procedures and had notified the NRC as required in a timely fashion.
The reactor trip occurred at approximately 13 percent power during a
controlled reactor plant shutdown to Mode 3 to support maintenance on
the main turbine generator. The 10-10 level in the steam generator was
caused while the steam generator feedwater was being transferred from
the main feedwater regulator valves to the bypasses. The licensee has
experienced this same problem during previous plant startups and
shutdowns and is evaluating methods to eliminate the problem. The
subsequent startup on July 26, 1986, was accomplished with no
significant problems.
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No violations or deviations were identified.
8.
Monthly Surveillance Observation
[TheNRCinspectorsobservedselectedportionsoftheperformanceof
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surveillance testing and/or reviewed completed surveillance test
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procedures to verify that surveillance activities were performed in
accordance with technical specifications (TS) requirements and
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administrative procedures. The NRC inspectors considered the following
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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.
Technical Specification limiting conditions for operation (LCO)
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Test. data was accurate and complete. Where appropriate, the NRC
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 administrative procedures.
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The surveillance was perfonned 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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STN IC-500, Revision 0, " Channel Calibration Radwaste Building
Corridor Basement Area Radiation Monitor SDRE01," performed
July 23, 1986
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STS RE-006, Revision 2. "E0L Core MTC Measurement," performed
July 11, 1986
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STS SE-001, Revision 5, " Power Range Adjustment to Calorimetric,"
performed July 11, 1986
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STS SE-001, Revision 6, " Power Range Adjustment to Calorimetric,"
performed July 27, 1986
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STS B8-004, Revision 4, "RCS Water Inventory Balance," performed
July 29, 1986
No violations or deviations were identified.
9.
Quality Assurance (QA) Program Annual Review
a.
QA Program Implementation
Duringapreviousinspection(IR 50-482/86-16) the NRC inspector
had reviewed the WCGS onsite and offsite review committees. The
licensee had a method for informing supervisory persunnel of new
regulatory requirements by routing to them Inspection and
Enforcement Bulletins (IEB), Generic Letters (GL), Information
Notices (IN), and so forth.
During this period, the NRC inspector examined the implementation
of the QA audit program and their records program.
b.
Audit Program
Through discussions with licensee personnel, review of the
essential elements manual and review of sunmary documentation, an
understanding of the audit program was obtained.
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The basis of the audit program was the essential elements manual,
which summarizes into 39 topics (essential elements) the licensee's
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commitments and/or requirements reflected in 10 CFR Part 50,
ANSI 18.7 (Quality Assurance for the Operational Phase of Nuclear
Power Plants), WCGS TS, and the Final Safety Analysis
Report (FSAR).
The essential elements are subdivided into
attributes which can be objectively evaluated.
To audit a plant area, the auditor prepared the audit plan from the
essential elements manual type of concern.
Upon completion of the
audit, if any discrepancies existed, methods existed that allowed
execution of corrective actions as appropriate.
Quality assurance
audit frequencies, as required by TS, were on a biennial schedule.
The audits were planned on an annual basis; however, if the
essential element was voluminous, the audit may have been scheduled
in segments over a two year period to assure that the minimum audit
requirements would be met.
In addition to the mandatory audits,
lower tiered audits and surveillances were scheduled to support the
main audit.
The following audit packages were reviewed:
Audit No.
Title
TE 50140-K116
Corrective Action dated 6/4/86
TE 50140-K096
Assignment Of Authority, Organization, and
Program Description
TE 50140-K086
Corrective Action dated 12/9/85
TE 50140-K066
Records Management
TE 50140-K005
Quality Assurance Records
The audits generally lasted four weeks.
Auditors conducted
entrance and exit summaries with the plant organization prior to
start and at conclusion of the audit.
The audit report clearly
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defined the audit scope and results.
Personnel conducting the
audit were qualified as determined by NRC inspector review of
training records.
The audit questions and areas of interest
reflected the requirements in the essential elements' manual.
The
audited organizations' response to audit findings were in writing,
were timely, and adequately addressed the findings and
recommendations.
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c.
Records Program
During this inspection, the NRC inspector reviewed Section 6.10 of
the facility TS, ANSI N45.2.9-1974 (Requirements For Collection,
Storage, and Maintenance Of Quality Assurance Records For Nuclear
Power Plants), and the WCGS procedures listed below:
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ADM 01-045, Revision 3, " Document Control Supervisor Duties
and Responsibilities"
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ADM 07-046, Revision 16, " Records, Administrative, and
Storage"
The WCGS records program was described in ADM 07-406. Maintenance
and retention periods for records were described in the TS and
various procedures.
The Document Control (DC) Supervisor was
assigned responsibility of maintaining the QA records and ensuring
implementation of the record storage controls.
Responsibilities
had been assigned with controls established to ensure transfer and
retention of construction phase records.
The controls (ADM
Procedure 07-406) established for record storage were in accordance
with FSAR commitments; i.e., ANSI N45.2.9-1974.
This procedure
described the storage facility; designated the DC supervisor as
custodian of the QA vault; described the filing / retrieval system
utilized; established a method to verify that records were in
agreement with the transmittal document; made provisions for
governing access to files and maintaining accountability of records
removed from storage; established methods for correcting
information, filing supplemental information and disposing of
superseded records with the required reviews and approvals
specified.
Individual section supervisors; i.e., instrumentation and control,
maintenance, et cetera, were responsible for establishing retention
periods of records not covered by the FSAR, TS, 10 CFR, and for
authorizing the disposal of records no longer required.
The NRC inspector verified through discussions with licensee
personnel and a tour of the QA vault that:
The environmental
conditions and fire suppression system were in accordance with
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commitments; records were listed on an index; records were readily
retrievable from designated files and were not stored loosely but
were firmly attached in folders; and records were stored in
suitable file cabinets.
No violations or deviations were identified.
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10.
Design Changes and Modifications
The NRC inspector reviewed design changes and modifications that the
licensee had determined were not required to be approved by NRC and
verified they were in conformance with TS and 10 CFR Part 50.'59.
a.
Design Changes
The NRC inspector selected three design changes that were to be
submitted with the annual report to the NRC that is required by
For each of the design changes the NRC
inspector verified:
That the changes were reviewed and approved in
a technically adequate manner in accordance with 10 CFR Part 50.59;
that the design changes were reviewed and approved according to TS;
and that established procedures were used.
The three design change summaries follow:
(1)
Plant Modification Request (PMR) 01446, Revision 0, was
originated to reinstall flow elements EM-FE924, 925, 926,
and 927, which were originally installed backwards.
(2)
Safety Evaluations (SE) 86-SE-31 was originated to reverse
the wires on Terminals TB4-8-01 and TB4-8-04 in Panel RP05BC
for the emergency diesel generator "A" day tank level control
circuit to make the wiring agree with the schematic.
(3)
SE 86-SE-44 was originated to demonstrate the operability of
reactor coolant system pressure isolation valves BB PV8702A
and EJ HV8701A by verifying that the measured leakage meets
the requirements of TS 4.4.6.2.2.
b.
The NRC inspector reviewed the WCGS program for temporary
modifications through review of Procedure ADM 02-101, Revision 15,
" Temporary Modifications." The NRC inspector verified that
temporary modifications were reviewed and approved according to
Section 6 of the TS and 10 CFR Part 50.59. The procedure assigned
each group supervisor responsibility for approving the temporary
modification as correct, necessary, and required the use of
detailed approved procedures. WCGS ADM Procedure 02-101 required:
That a temporary modification log be maintained; that all
outstanding temporary modifications were reviewed periodically; and
that temporary modifications be evaluated to determine the need for
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independent verification.
No violations or deviations were identified.
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11.
Core Thermal Power Evaluation
The NRC inspector verified that the licensee's calculation of core
thermal power was correct and that the procedure used was technically
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adequate.
On July 18, 1986, at 0610 CDT, the NRC inspector performed a
manual calorimetric using licensee Procedure STS SE-002, Revision 0,
" Manual Calculation of Reactor Thermal Power." At that time computer
point REV1118 was indicating 3407.3 MWth which corresponds to
99.89 percent of licensed full power.
The NRC inspector calculated a
power level of 99.82 percent of full power.
The NRC inspector then
verified that all nuclear instrumentation channels were reading greater
than 99.89 percent, but within acceptable margins.
The NRC inspector
reviewed STS SE-002 for technical adequacy, proper initial conditions,
appropriate prerequisites and good engineering practice.
The three
typographical errors and one usage of incorrect units found were given
to the Superintendent of Operations for correction. The correction
factor of 0.4 percent for reactor coolant pump (RCP) heat added was
found to be incorrect by 0.0254 percent, since this is within instrument
error, this difference is not significant and the reactor engineer was
notified of the difference.
The proper correction factor for RCP pump
heat is 0.3746 percent or 43.6 10E6 BTU /HR as identified in the
preoperational test procedure results report for SU9-0025, Revision 0,
" Reactor Coolant System Heat Loss." The NRC inspector on a random basis
verified the correct number was used in Startup Test SU7-SC03.2,
Revision 1, " Thermal Power and Statepoint Data Collection at 30 percent
Power," and SU7-SC03.8, Revision 1, " Thermal Power and Statepoint Data
Collection at 100 percent Power." The NRC inspector randomly reviewed
TS Surveillance STS SE-001, Revision 5, " Power Range Adjustment to
Calorimetric," performed on June 14-16, 1986, and verified that the
power range nuclear instruments were properly adjusted to agree with the
results of the heat balance and that data was reasonable, consistent
with previous data and properly recorded.
The NRC inspector by review of the STS master schedule verified that the
frequency of calorimetrics was as prescribed by the licensee's TS.
The NRC inspector by review of the appropriate surveillances verified
that the plant instruments and computer points used for calorimetrics
were calibrated in a traceable manor and that evaluation results were
reviewed, approved, and documented in accordance with procedures.
No violations or deviations were identified.
12.
Radwaste Processing
During this inspection period, the NRC inspectors observed activities
and reviewed procedures related to the processing of radwaste.
A vendor
was onsite processing primary and secondary evaporator bottoms
concentrates.
A licensee procedure was to provide valve lineups for
supplying the radsaste to the vendors processing equipment.
The vendor
would then use his own procedures to process the radwaste.
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In discussions with cognizant licensee personnel, the NRC inspectors
pointed out that the vendor's procedures and the licensee's procedures
had not been integrated together in that they did not reference each
other and that there was no definitive vehicle by which the vendor's
procedures were implemented or controlled for use onsite.
The licensee resolved this observation by establishing and implementing
Procedure STS HC-227, Revision 0, " Vendor Processing of Primary Resins
and Concentrates," which addressed interfaces with vendor procedures.
No violations or deviations were identified.
.13.
Exit Meeting
The NRC inspectors met with licensee personnel to discuss the scope and
findings of this inspection on August 4, 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.
7/14-18/86
D. Hunnicutt
QA Program and
86-17
Design Changes
(pars. 9
and10)
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