ML20127M241
| ML20127M241 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/26/1985 |
| From: | Harrell P, Martin L, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20127M213 | List: |
| References | |
| 50-285-85-11, IEIN-84-06, IEIN-84-6, NUDOCS 8507010163 | |
| Download: ML20127M241 (11) | |
See also: IR 05000285/1985011
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APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection-Report:
50-285/85-11
License:
Docket: 50-285
Licensee: Omaha Public Power District
.1623 Harney Street
Omaha, Nebraska 68102
Facility Name:
Fort Calhoun Station
Inspection At:
Fort Calhoun Station, Blair, Nebraska
Inspection Conducted: May 1-31, 1985
Inspector:
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andON
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L. A. Yandell, Senior Resident Reactor Inspector,
Ddte
Fort Calhoun Station
Inspector: . )
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k4f. H5rrell, JCsident Reactor Inspector,
IFate /
Arkansas Nuclear One
Approved:
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L. E. Martin, S t1on Chief, Project Section A,
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Reactor Pro
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8507010163 850626
ADOCK 05000285
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Inspection Summary
Inspection Conducted May 1-31, 1985 (50-285/85-11)
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Areas Inspected: _ Routine, unannounced inspection of. licensee's actions on
previous inspection findings, operational safety verification, surveillance
testing, surveillance program, maintenance activities,_ followup of
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IE Information Notices, and followup of LERs.
The inspection involved 135
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inspector-hours onsite by two NRC inspectors, of which 22 were offshift hours.
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Results: -Within the seven areas inspected, one violation was identified
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(failure to follow procedures
paragraph 5).
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DETAILS
1.
Persons Contacted
- R. L. Andrews, Division Manager, Nuclear Production
- W. G. Gates, Manager, Fort Calhoun Station
- R. L. Jaworski, Section Manager, Technical Services
- T. J. McIvor, Manager, Technical Support
- J. K. Gasper, Manager, Administrative Services
- K. C. Hyde, Test Engineer
J. J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs
L. T. Kusek, Supervisor, Operations
M. R. Core, Supervisor, Maintenance
J. J. Fluehr, Supervisor, Station Training
C. J. Brunnert, Operations Supervisor, Quality Assurance (QA)
8. L. Saucier, Inspector, QA
L. H. Bnrcherding, Inspector, QA
- Denotes attendance at the May 17, 1985, exit interview.
- Denotes attendance at the May 17 and June 10, 1985, exit interviews.
The NRC inspectors also talked with and interviewed other licensee
employees during the inspection.
These employees included licensed and
unlicensed operators, craftsmen, engineers, and office personnel.
2.
Licensee Action on Previous Inspection Findings
a.
(Closed) Open Item 285/8217-01, " Housekeeping." The licensee failed
to include the controlled area of the plant in the Zone IV category.
The licensee has issued a revision to Administrative Procedure A-G-6,
" Housekeeping," to require that the controlled area of the plant be
kept in Zone IV.
This item is considered closed.
b.
(Closed) Open Item 285/8312-07, " Alternate Shutdown." The licensee
failed to list all valves required to be manipulated during alternate
shutdown operations.
Emergency Operating Procedure (EOP) EP-24-A,
" Forced Evacuation of the Control Room Due to Fire," has been revised
to include HCV-2809A and HCV-28838 in the list of the valves to be
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manipulated during cold shutdown.
This item is considered closed.
c.
(Closed) Open Item 285/8312-08, " Fuse Not Labeled." Repair
instructions for the raw water system provided in E0P EP-24-A,
require that the standby fuse in Switchgear 1A4, Unit 12 be pulled.
The licensee had not provided a label in Unit 12 to indicate which
was the standby fuse.
The NRC inspector verified that the fuse has
been labeled and the label clearly indicates which is the stendby
fuse.
This item is considered closed.
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d.
(Closed) Open-Item 285/8312-09, " Incorrect Procedure." The licensee
issued E0P EP-24-A which incorrectly identified the conductors to be
jumpered for the repair of HCV-348.
The licensee has issued a
revision to E0P EP-24-A to correctly identify the conductors to be
used.
This item is considered closed.
e.
(Closed) Open Item 8410-02, " Procedure Not Issued." The licensee had
failed to issue a procedure to implement 10 CFR Part 50, Appendix B,
Criterion XVI, Corrective Action.
The licensee has issued Quality
Assurance Department Procedure, QADP-17, " Control of Deficiencies and
Corrective Action," to implement criterion XVI of Appendix B.
The
NRC inspector reviewed the procedure and it appears that the
procedure effectively implements the requirements for corrective
action.
This item is considered closed.
3.
Operational Safety Verification
The NRC inspector performed activities as described below to ascertain
that the facility is being maintained in conformance with regulatory
requirements and that the licensee's management control system is
effectively discharging its responsibilities during power operation,
The NRC inspector made several control room observations to verify
a.
proper shift manning, operator adherence to approved procedures,
adherence to selected Technical Specifications, and operability of
the reactor protective system and engineered safeguards equipment.
Selected logs, records, recorder traces, annunciators, panel
indications, and switch positions were reviewed to verify compliance
with regulatory requirements.
The licensee's equipment control was
reviewed for proper implementation by reviewing maintenance order
status and the tag-out log, and by verifying selected safety-related
tag-outs.
The NRC inspector observed several shift turnovers,
b.
The NRC inspector toured the plant at various times to assess plant
and equipment conditions.
The following items were observed during
these tours:
general plant conditions
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vital area barriers not degraded or appropriately manned by
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security personnel
adherence to requirements of radiation work permits (RWPs)
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proper use of protective clothing and respirators
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plant housekeeping and cleanliness practices including fire
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hazards and the control of combustible material
work activities being performed in accordance with approved
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activities
physical security
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HP instrumentation is operable and calibrated
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The NRC inspector verified operability of the following
c.
safety-related systems by performing a walkdown and switch
verification of the accessible portions of the system:
High Pressure Safety Injection System per Checklist SI-1-CL-A
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Low Pressure Safety Injection System per Checklist SI-1-CL-B
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"A" and "B" Monitor Tank secured lineup per checklist contained
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in Operating Procedure 01-WDL-3, Steps IV. A.18 and IV.B.18
Plant Electrical Distribution per Checklists EE-1-CL-A and
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EE-2-CL-A
Nos. 1 and 2 Diesel Generator - Starting Air Systems per
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Checklists DG-1-CL-A and DG-2-CL-A
Nos.1 and 2 Diesel Generator - Fuel Oil System per
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Checklists DG-1-CL-8 and DG-2-CL-B
d.
The NRC inspector observed portions of Containment Purge 85023,
reviewed the discharge permit, and noted the following:
the X/Q log was maintained, the readings were within limits, and
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the shift supervisor review was performed
the limiting X/Q was established
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VIAS was tested using RM 061
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the stack dewpoint and annubar readings were taken
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the tritium sampler was in place and the sample was taken
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the recommended release rate was established, and the actual
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flow was lower than that authorized
radioactivity analyses were performed
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the required effluent monitors and recorders were operational
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the required auxiliary building exhaust fans were operating
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OI-VA-1.Section IV.G was attached to the permit
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the initial reading of the stack flow integrator was noted on
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the recorders
the operations checklist to CMP 4.5 was complete and signed off
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by the shift supervisor
the permit was reviewed and signed off properly, and the
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termination time was established
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e.
The NRC inspector observed portions of Discharge Permit 85060 for "B"
Monitor Tank.
The NRC inupector verified that a tank sample had been
taken and analyzed, that all radiological and chemical discharge
limits were satisfied in the discharge tunnel, that the operations
checklist was completed and signed off, that the maximum release rate
was established, and that the shift supervisor had signed off the
permit.
The NRC inspector observed the discharge being secured from
AI-100 in the Auxiliary Building.
f.
The NRC inspector attended the entrance and exit interviews of
licensee's Safety Audit and Review Committee (SARC) Audit No. 2-85
conducted the week of May 6th.
This audit was conducted to
" determine whether commitments to the NRC and/or appropriate
corrective action to various problems are executed in a timely and
effective manner."
It was noted that plant QA auditors were utilized
to address a substantial portion of the approved audit checklist.
The NRC inspector reviewed the checklist, observed the auditors
during the inspection, and discussed their observations with regard
to specific LERs, Operations Incidents Reports, and NRC inspection
reports.
No violations or deviations were identified.
4.
Surveillance Testing
The NRC inspector witnessed portions of the following surveillance tests:
ST-RM-1, F.2 (Monthly) Area Monitor Checks
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ST-RM-2, F.2 (Monthly) Process Monitor Checks
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ST-ISI-SI-1, F.1 (Quarterly) Safety Injection Valves Inservice
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Testing
ST-ISI-CVCS-3, F.1 (Quarterly) Chemical and Volume Control System
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Pump Test
ST-RPS-1, F.3 (Monthly) Power Range Safety Channels Test
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ST-CEA-1, F.4 (81-Weekly) Control Element Assembly Check
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ST-ESF-5, F.1 (Monthly) Automatic Load Sequencer Check
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In the above surveillance tests, the NRC inspector verified where
applicable that:
testing was scheduled in accordance with Technical Specification
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requirements
procedures were being followed
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calibrated test equipment was being used
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qualified personnel were performing the tests
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limiting conditions for operation were being met
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test data were being accurately recorded
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No violations or deviations were identified.
5.
Surveillance Program
The NRC inspector reviewed the surveillance program to verify the program
is being conducted in accordance with approved procedures as required by
the Technical Specifications, inservice inspcction program for pumps and
valves, and the approved fire protection /p r eention program.
The review included the following verifications:
.A' selected sample of surveillances required by the Technical
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Specifications are being performed in accordance with properly
approved procedures.
Surveillance tests for pumps and valves identified in the licensee's
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approved inservice inspection (ISI) program are being performed in
accordance with approved procedures.
The procedures used to perform Technical Specification and ISI
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activities are technically adequate and are written so they can be
understood and used by the technicians performing the surveillance.
Surveillances are being performed at the frequency required by the
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Technical Specifications-and the ISI program.
New or revised surveillance procedures are being issued, when
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required, in response to recently issued Technical Specification
amendments.
Surveillance procedures are written in a format that provides
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prerequisites, acceptance criteria, and instructions for returning
systems or components to service.
Completed surveillance tests are being filed and retained in a
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records system in accordance with requirements.
During performance of the above reviews, the NRC inspector noted that
there were discrepancies in one of the surveillance tests.
The
discrepancies were of a minor editorial nature.
The licensee was notified
of the discrepancies and agreed to correct the procedure.
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The NRC inspector' reviewed the surveillance records completed during the
last refueling outage which ended in-July 1984.
During a review of the
test records, the NRC inspector noted that six surveillance tests were not
in the: files.
Upon notification by the NRC inspector of the missing
tests, the licensee initiated a search for the missing tests.
The results
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of the search revealed that three tests had been inadvertently filed with
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the completed monthly surveillances instead of the refueling outage
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surveillance tests. One of the tests had not been reviewed by the
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performing group's supervisor, and two completed tests could not be
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located. The failure to account for completed surveillance tests in the
files is an apparent violation.
(285/8511-01)
Based on the review of past NRC inspection reports and discussions with
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NRC personnel, the maintenance of all types of QA records has been a
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continuing problem for the licensee.
No other violations or deviations were identified.
6.
Maintenance Activities
The NRC inspector witnessed portions of the work performed on the
following maintenance items:
Safety-Related Design Change Order (SRDCO) 85-7/MR-FC-84-29, "RPS
a.
Dual Potentiometer Upgrade." The licensee experienced the failure of
three dual potentiometer modules as reported in LERs 83-05, 83-06,
and 83-07.
An investigation was performed to determine the cause of
the failure (see NRC Inspection Report 50-285/84-04, paragraph 6.e) and
the ifcensee decided to replace all 36 modules in the reactor
protective system.
The NRC inspector reviewed the work package and
noted the following:
The Pre-Installation Modification Control Sheet (Form H) was
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filled out properly, purchase order information was present, and
PRC approvals were obtained.
The Engineering Evaluation and Assistance Request (Form A) was
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completed and contained appropriate approval signatures.
The Safety Evaluation (FC-154) was filled out and approved.
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The SRDC0 was filled out and approved by QA, Quality Control
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(QC), and the plant manager.
The PRC approved work procedure contained signed off
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prerequisites, QC hold points, materials identification
information, applicable Technical Specification requirements,
and the approved drawing list.
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On separate occasions the NRC inspector observed the work performed
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on Channels A and C, verified that procedure signoffs were current,
and confirmed that appropriate jumper log entries were made. The NRC
inspector observed portions of Calibration Procedure CP-A/APD after
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work was complete on Channel A and Surveillance Test ST-RPS-12, F.2
to verify operability,
b.
Maintenance Order (MO) 851270, " Charging Pump CH-1C."
on the charging pump was identified by the operator who prepared the
M0.
The NRC inspector verified that the M0 was properly signed off,
that Tag-Out 85-358 was assigned, and that the applicable Technical
Specification was referenced.
The pump was repacked in accordance
with MP-CH-1, " Inspection and Repair of Charging Pumps." The NRC
inspector reviewed the work procedure and verified that initial
conditions were signed off, that RWP 125 was assigned to cover this
work, and that QC hold points were observed.
Qualified craftsmen
were assigned to the task and the NRC inspector noted that purchasing
information was identified on the M0.
Following repairs, the NRC
inspector observed performance of Surveillance Test ST-ISI-CVCS-3,
F.1, "CVCS Pump Test," to verify operability and noted that the MO
was signed off, the tags cleared, and the pump returned to service.
c.
MO 851135, "No. 2 Diesel Generator." During performance of a
surveillance test the licensee determined that the voltage regulator
could not provide sufficient control to maintain the power factor
within operating limits.
An approved PRC procedure was prepared to
cover this work and the NRC inspector noted that the shift supervisor
signoff was present, that procedure steps were signed off, and that
the safety analysis (FC-154) was completed and attached.
Procedure
Change 1477u was processed and incorporated properly.
The NRC
inspector observed the work in progress and verified that tags were
properly hung, that qualified craftsmen were assigned to the task and
that they exhibited safe work practices.
d.
MO 851641, " Nuclear Instrumentation (NI)." The SIGMA meter
providing temperature indication on the NI detector well cooling
channel was in alarm.
The MO was written to " calibrate or repair as
needed." The NRC inspector reviewed the M0 for proper approvals and
signoffs.
Calibration Procedure CP-734A, " Nuclear Detector Well
Cooling Temperature," was performed and it was determined that the
meter movement was inoperable.
The NRC inspector observed the
troubleshooting, installation of jumpers, and removal of the
instrument for repair.
The NRC inspector reviewed the jumper log for
proper entries and verified that the tags were cleared correctly
after the instrument was reinstalled.
e.
H0 851061, " Sampling System; PCV-2560." Valve PCV-2560 in the
Post-Accident Sampling System was not providing proper control and
repairs were initiated.
It was determined that new internals were
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required. The NRC inspector observed the work being performed and
noted that qualified craftsmen were assigned to the task, that
current technical manual information was present at the jobsite,
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that. isolation tags were properly hung, and that appropriate HP
precautions were observed. The NRC inspector reviewed the M0 for
completeness and proper approvals.
No violations or deviations were identified.
7.
Followup of IE Information Notices
The NRC inspector reviewed the licensee's program to handle IE Information
Notices.
This review included verification that the notices issued in
1984 were received by the licensee, entered into their licensing tracking
system, and distributed to appropriate personnel for review.
The NRC inspector reviewed the licensee's actions taken in response to IE
'Information Notice 84-06, " Steam Binding of Auxiliary Feedwater Pumps,"
issued on January 25, 1984. This issue was reviewed in more detail in
response to a request from the NRC Office of Inspection and Enforcement.
The NRC inspector determined that the licensee actions were as follows:
The auxiliary feedwater (AFW) piping is monitored once per shift by
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touching the pipe. A permanent local temperature indicating device
is scheduled for installation during the 1985 outage.
AFW operating and surveillance procedures were reviewed but revisions
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were not required with regard to check valve leakage because the
auxiliary feedwater piping and check valves are not placed inservice
dwing testing or normal operation of the pump except for the
refueling outage tests.
Procedure 01-AFW-2, " Auxiliary Feedwater System Operation - Special
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Procedures," was revised to provide guidance on detecting and
correcting AFW pump steam binding.
The licensee is performing periodic leakage tests of the AFW check
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valves and periodic inspections of the AFW discharge isolation
valves.
No violations or deviations were identified.
. 8. , Followup of Licensee Event Reports (LERs)
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LERs83-005, 83-006, and 83-007, " Failed RPS Dual Potentiometer Modules."
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This item was discussed in NRC Inspection Report 50-285/84-04 and remained
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open pending replacement of these modules by the licensee. Based on
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reconinendations contained in Combustion Engineering Letter CE-18074-1528
dated January 26, 1984, the licensee elected to replace all Bell & Howell
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Model 3846 12-01 modules with upgraded Bell & Howell Model 20-320. Work-
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Order 908 was issued to cover procurement of 60 potentiometers and this
work was completed this reporting period under SRDC0 85-7/MR-FC-84-29.
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The corrective actions taken by the licensee appeared to be adequate.
9.
Exit Interview
The NRC inspector met with licensee representatives on May 17 and
June 10, 1985, to summarize the scope and findings of the inspection.
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