ML20209D769
| ML20209D769 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/14/1987 |
| From: | Boardman J, Harrell P, Hunnicutt D, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20209D745 | List: |
| References | |
| 50-285-87-06, 50-285-87-6, NUDOCS 8704290355 | |
| Download: ML20209D769 (13) | |
See also: IR 05000285/1987006
Text
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APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-285/87-06
License:
,
Docket:
50-285
' Licensee: Omaha Public Power District
1623 Harney Street
s
Omaha, Nebraska 68102
Facility Name:
Fort Calhoun Station
Inspection At:
Fort Calhoun Station, Blair, Nebraska
Inspection Conducted:
March 1-31, 1987
Y! /y/P7
Inspector:
.
P. H. Harrell, Senior Resident Reactor
Date
Inspector
N
./R. Boardman,ReactorInspector,
Date
erations Section, Reactor Safety Branch
Approved:
N/
/ 'W87
D. M. Hunnicutt, Chief, Operations Section,
D8te '
Reactor Safety Branch
8704290353 870422
ADOCK 05000285
G
Ci M
ds/ar
D. Y Hunter, Chief, Reactor Project
Date
Section B, Reactor Projects Branch
Inspection Summary
Inspection Conducted March 1-31, 1987 (Report 50-285/87-06)
Areas Inspected:
Routine, unannounced inspection including operational safety
verifications, maintenance, surveillance, plant tours, safety related system
walkdown, security observations, in-office review of periodic and special
reports, preparation for refueling activities, refueling activities, review of
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the welding program, containment local leak rate testing, and followup on
Generic Letter 83-28 (Salem ATWS event).
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-Results: Within the 12 areas inspected, 1 violation (failure to maintain a log
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of entries into vital areas, paragraph 8) was identified.
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DETAILS
1.
Persons Contacted
- R. Andrews, Division Manager-Nuclear Production
- W. Gates, Plant Manager
C. Brunnert, Supervisor-0perations Quality Assurance
M. Core, Supervisor-Maintenance
T. Dexter, Supervisor-Security
- J. Fisicaro, Supervisor-Nuclear Regulatory and Industry Affairs
J. Foley, Supervisor-I&C and Electrical Field Maintenance
- J. Gasper, Manager-Administrative and Training Services
- R. Jaworski, Section Manager-Technical Services
M. Kallman, Supervisor-Security
L. Kusek, Supervisor-0perations
- D. Munderloh, Plant Licensing Engineer
T. McIvor, Supervisor-Technical
- K. Morris, Division Manager-Quality Assurance and Regulatory Affairs
R. Mueller, Plant Engineer
- A. Richard, Manager-Quality Assurance
G. Roach, Supervisor-Chemical and Radiation Protection
J. Kecy, Acting Reactor Engineer
- S. Willrett, Supervisor-Administrative Services and Security
- Denotes attendance at the monthly exit interview held on April 3, 1987.
- Denotes attendance at a meeting held by J. Boardman on March 20, 1987.
(see paragraph 15)
The inspector also contacted other plant personnel, including operators,
technicians, and administrative personnel.
2.
Followup on Previously Identified Items
(Closed) Open Item 285/8bO3-03:
Establishment of an inspection program
for type-86 lockout relays.
The licensee performed a review, in accordance with IE Bulletin 84-02
commitments, to establish a program for inspection of type-86 relays.
The
review performed by the licensee's engineering staff recommended that an
inspection program be established by plant personnel for inspection of
type-86 relays.
The licensee's plant staff disagreed with the engineering
staff's recommendation in that an additional inspection program was not
required.
The licensee's plant staff determined that an acceptable
program existed through the use of the established surveillance test
program.
Based on a review performed by the licensee's plant staff, it
was verified that each relay was tested on a monthly basis by the
performance of system surveillance tests.
The plant staff also noted
during the review that redundant relays existed for each safety-related
signal processed.
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The NRC inspector reviewed a selected sample of relays to verify that a
surveillance test was performed to verify proper relay operation. No
problems were noted during the review.
3.
Operational Safety Verifications
The NRC inspector conducted reviews and observations of selected
activities to verify that facility operations were performed in
confomance with the requirements established under 10 CFR, administrative
procedures, and the Technical Specifications (TS). The NRC inspector made
several control room observations to verify:
Proper shift staffing
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Operator adherence to approved procedures and TS requirements
.
Operability of reactor protective system and engineered safeguards
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equipment
Logs, records, recorder traces, annunciators, panel indications, and
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switch positions complied with the appropriate requirements
Proper return to service of components
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Maintenance orders (MO) initiated for equipment in need of
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maintenance
Appropriate conduct of control room and other licensed operators
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During a control room tour at approximately 11:00 a.m. on March 9,1987,
the NRC inspector noted that the licensee had taken the 480-volt electrical
distribution bus, MCC 3A2, out of service at 7:00 a.m. to perform preventive
maintenance activities. By removing the MCC from service with the reactor
coolant temperature greater than 300 degrees, the licensee had entered a
TS limiting condition for operation (LCO). The LC0 of TS 2.7(2)f requires
that the licensee place MCC 3A2 back in service within 8' hours or enter an
action statement that required the plant to be placed in a cold shutdown
,
condition within the following 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />. The licensee placed MCC 3A2 back
in service at 2:42 p.m. and exited the TS LC0.
During discussions with operations personnel, the NRC inspector detemined
that licensee personnel were not aware that taking MCC 3A2 out of service
caused the plant to be placed in an LC0. Upon notification by the NRC
inspector, actions were taken by the licensee to ensure the MCC was
returned to service as soon as possible. Management personnel stated that
the failure to recognize the plant was in an LCO was an inadvertent
oversight by operations personnel. This occurrence was discussed by plant
management with operations personnel to increase their awareness level of
the need to verify that plant conditions do not cause an unknown entry
into an LCO.
In addition, the outage planning data base was updated by
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the licensee to ensure that no MCCs were removed from service during future
outages when the reactor coolant temperature was above 300 degrees.
No violations or deviations were identified.
4.
Plant Tours
The NRC inspector conducted plant tours at various times to assess plant
and equipment conditions. The following items were observed during the
tours:
General plant conditions
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Equipment conditions, including fluid leaks and excessive vibration
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Plant housekeeping and cleanliness practices including fire hazards
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and control of combustible material
Adherence to the requirements of radiation work permits
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Work activities performance in accordance with approved procedures
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During tours of the plant, the NRC resident inspector noted the following
items:
An individual was entering the containment building with a
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respirator; however, the individual's security badge indicated that
he was not qualified to wear a respirator. The licensee places a
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white dot on the security badge to indicate that an individual is
qualified for respirator use.
In this case, the individual with the
respirator did not have a white dot on his security badge.
The NRC inspector called the apparent problem to the attention of the
security guard stationed at the containment access door. The
security guard stopped the individual from entering containment and
determined that the individual intended to use the respirator. The
individual explained that he was respirator qualified and that when
his badge was issued, the white dot was inadvertently left off. The
security guard checked with the individual responsible for respirator
qualification and detennined that the individual attempting to enter
containment was not respirator qualified.
The security guard instructed
the individual to leave the area immediately.
In discussions with the licensee, management personnel stated that
they felt the general employee training program was adequate to
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ensure that unqualified personnel did not use respirators.
Management personnel stated that they felt that the problem discussed
above was a problem with a particular individual. This conclusion
was based on the fact that no other instances of this type had been
reported during the current refueling outage. The individual
involved was provided individualized instruction in what
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qualifications were required for him to be allowed to wear a
respirator.
Fire Doors 989-11 and 1011-1 were found not to be functioning
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properly in that the doors wouldn't always close.
By not closing,
the fire barriers associated with the doors became nonfunctional.
Upon notification by the NRC inspector, the licensee repaired the
doors.
During a tour of containment on March 27, 1987, the plant manager and
maintenance supervisor found a contract quality control (QC) inspector
sleeping.
The QC inspector was performing tool accountability activities,
but no work was in progress at the time of the discovery.
The contract QC
inspector was terminated shortly thereafter.
The NRC inspector discussed
the incident with the chemistry and radiation protection (CARP) supervisor
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to verify that health physics (HP) technicians were aware of.their
responsibility of ensuring individuals did not sleep in radiation areas.
The CARP supervisor stated that the HP technicians were aware of their
responsibility.
The plant manager discussed the incident with all plant
supervisors and stressed that any individual caught sleeping on duty would
be disciplined.
No violations or deviations were identified.
5.
Safety-Related System Walkdown
The NRC inspector walked down accessible portions of the following
safety-related system to verify system operability.
Operability was
determined by verification of selected valve and switch positions.
The
system was walked down using the drawing and procedure noted:
Shutdown cooling system (Procedure 01-SC-1, Revision 24, and
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Drawing E-23866-210-130, Revision 38)
During the walkdown, the NRC inspector noted minor discrepancies of an
editorial nature between the drawing, procedure, and plant as-built
conditions for the selected areas checked.
None of the conditions noted
affected the operability or safe operation of the system.
Licensee
personnel stated that the noted minor discrepancies would be corrected.
No violations or deviations were identified.
6.
Monthly Maintenance Observations
The NRC inspector reviewed and/or observed selected station maintenance
activities on safety-related systems and components to verify the
maintenance was conducted in accordance with approved procedures,
regulatory requirements, and the TS.
The following items were considered
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during the reviews and/or observations:
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The TS limiting conditions for operation were met while systems or
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components were removed from service
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Approvals were obtained prior to initiating the work
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Activities were accomplished using approved M0s and were inspected,
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as applicable
Functional testing and/or calibrations were performed prior to
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returning components or systems to service
Quality control records were maintained
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Activities were accomplished by qualified personnel
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Parts and materials used were properly certified
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Radiological and fire prevention controls were implemented
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The NRC inspector reviewed and/or observed the following maintenance
activities:
Rebuilding of main steam safety valves (M0 870946)
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Replacement of insulation on 4160-volt buses (M0 863672)
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Change out of sleeve bearings on electrical breakers (M0 845331)
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Repair of a battery charger (M0 817548)
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Replacement of a bonnet gasket on a safety injection valve
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(M0 858023)
No violations or deviations were identified.
7.
Monthly Surveillance Observations
The NRC inspector observed selected portions of the performance of and/or
reviewed completed documentation for the TS required surveillance testing
on safety-related systems and components.
The NRC inspector verified the
following items during the testing:
Testing was performed by qualified personnel using approved
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procedures
Test instrumentation was calibrated
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The TS limiting conditions for operation were met
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Removal and restoration of the affected system and/or component were
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accomplished
Test results conformed with TS and procedure requirements
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Test results were reviewed by personnel other than the individual
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directing the test
Deficiencies identified during the testing were properly reviewed and
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resolved by appropriate management personnel
The NRC inspector observed and/or reviewed the documentation for the
following surveillance test activities.
The procedures used for the test
activities are noted in parenthesis.
Channel B safety injection actuation signal test (ST-ESF-2-F.2)
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Auxiliary feedwater pump monthly cieck (ST-FW-1-F.2)
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Exercising of ventilation air valves (ISI-VA-1-F.1)
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Calibration of containment pressure switch (CP-D/765)
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No violations or deviations were identified.
8.
Security Observations
The NRC inspector verified the physical security plan was being
implemented by selected observation of the following items:
The security organization was properly manned
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Persor.nel within the protected area (PA) displayed their
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identification badges
Vehicles were properly authorized, searched, and escorted or
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controlled within the PA
Persons and packages were properly cleared and checked before entry
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into the PA was permitted
The effectiveness of the security program was maintained when
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security equipment failure or impairment required compensatory
measures to be employed
During this inspection, the NRC inspector noted that the licensee had not
established a program for maintaining a log for persons entering vital
areas not equipped with security badge card readers.
The discussion of
this apparent violation contains safeguards information, as defined in
10 CFR Part 73.21; therefore, the details of this apparent violation are
provided in Appendix A and the Attachment to this inspection report.
9.
In-Office Review of Periodic and Special Reports
In-office review of periodic and special reports was performed by the NRC
resident inspector and/or the Fort Calhoun project inspector to verify the
following, as appropriate:
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Reports included the information required by appropriate NRC
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requirements
Test results and supporting information were consistent with desigr.
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predictions and specifications
Determination that planned corrective actions were adequate for
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resolution of identified problems
Detennination as to whether any information contained in the report
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should be classified as an abnormal occurrence
The following reports were reviewed:
Monthly operations report for February 1987
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Core reload methodology changes for Cycle 11, dated March 18, 1987
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Amendment for a change to the TS related to testing of the emergency
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diesel generators, dated March 13, 1987
Notification of raising the current cold leg temperature, dated
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March 11, 1987
Revised schedule and justification for replacement of Valcor valves,
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dated March 4, 1987
No violations or deviations were identified.
10. Preparation for Refueling
The NRC inspector reviewed selected procedures to verify that the
technical and administrative requirements provided in the procedures
adequately incorporated controls and requirements stated in the TS, codes,
and standards. The procedures reviewed were evaluated to verify that
controls had been established for the following elements:
Receipt, inspection, and storage of new fuel and control element
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assemblies (CEA)
Fuel handling, transfer, and core verification
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Inspection of irradiated fuel
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Preoperational checkout of refueling equipment
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Handling and movement of the reactor core internals
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Establishment of administrative measures for the activities such as
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lines of supervision, shif t manning, radiation monitoring,
comunications, and training
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The NRC inspector reviewed the following procedures for the elements
listed above.
Number
Title
Revision
Procedure for CEA
3
Unloading, Inspection, and
Storage of Individual CEAs
Reactor Core Refueling
18
Procedure
Visual Inspection of
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Irradiated Fuel
HP-FH-2
Refueling Equipment
10
Preoperational Maintenance
Polar Crane Annually or
7
at Refueling Inspection
HP-RC-7-2-A
Upper Guide Structure
20
and ICI Plate Removal
Fuel Receipt Procedure
11
The i4RC inspector witnessed activities related to the receipt, inspection,
and storage of new fuel and CEAs. The inspector verified that the
inspections were performed in accordance with the requirements established
by Procedures SP-NFR-1 and SP-CEA-3. The selected verifications performed
by the inspector included determination that the personnel performing the
inspections were qualified, documentation was accurately completed, and
the fuel and CEAs were properly handled.
Based on the observations and
reviews perfonred by the NRC inspector, it appeared that the fuel and CEAs
were inspected and handled appropriately.
The NRC inspector also observed and/or reviewed completed documentation of
other selected portions of preparation for refueling activities. The
activities included fuel handling equipment and crane operational
verification, proper operation of radiation monitors, and verification
that the source range monitors operated properly.
Prior to contencement of outage activities, the licensee issued a
refueling cutage manual. This manual provided a single reference source
for the various activities related to the outage. The information
provided in the manual included a description of the outage organization
and responsibilities; time, place, and subject of the various outage
meetings; administrative information; and a discussion of how to properly
perform activities that have been previously identified as problem areas.
No violations or deviations were identified.
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11. Review of Welding Program
During this inspection period, the NRC resident inspector assisted an NRC
welding specialist from Region IV in a detailed review of the licensee's
welding program. During the review, a violation of the failure to
properly control special prccesses was identified. The results of the
program review are provided in NRC Inspection Report 50-285/87-08.
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12. Followup on Generic Letter 83-28
Generic Letter (GL) 83-28 was issued by the NRC to require licensees to
implement corrective actions based on the Salem ATWS event. This portion
of the inspection was performed to verify that the licensee had properly
implerented a program for post-trip reviews. The requirements for
post-trip reviews are provided in GL 83-28 as Items 1.1 and 1.2.
The NRC Office of Nuclear Reactor Regulation (NRR) performed a review of
the documentation submitted by the licensee in response to the
requirements of GL 83-28.
Based on the review, NRR issued a safety
evaluation report (SER) on October 22, 1985, for Item 1.1 and on June 13,
1985, for Item 1.2.
The SERs issued by NRR concluded that the licensee's
post-trip review data and information capabilities were acceptable. The
NRC inspector performed a review to verify that the licensee had
implemented a program for post-trip review as stated in the SERs. The
program implementation was verified by review of the documentation listed
below.
A sequence-of-events computer printout to verify that the types of
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parameters available during post-trip reviews included the items
required by the SER
Procedure OP-1 "liaster Checklist for Startup or Trip Recovery," to
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verify that post-trip review and permission for restart
responsibilities were clearly defined
Post-trip review packages compiled during past reactor trips to
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verify that the appropriate documentation (e.g., completed startup
procedures, sequence-of-events printouts, instrument recorder
tracings and strip charts, etc.) was available
Based on the review performed by the NRC inspector, it appears that the
licensee has implemented an adequate post-trip review program.
Items 1.1
and 1.2 of GL 83-28 are considered closed.
No violations or deviations were identified.
13. Refueling Activities
The NRC inspector reviewed / observed various activities performed during
refueling to verify the activities were performed in accordance with the
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TS and approved licensee procedures. The activities observed / reviewed
included the following:
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Proper shift staffing by qualified individuals was provided
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Containment integrity was established and maintained
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Good housekeeping and loose object control on the refueling bridge
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Fuel handling operations were perfonned in accordance with approved
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The proper refueling cavity water level was maintained
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Chemistry sampling was perfonned at the frequency specified in the TS
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During observation / review of the above activities, no problems were noted
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by the NRC inspector. During this inspection period, the licensee
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offloaded all fuel assemblies into the spent fuel pool to check for fuel
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integrity. The fuel integrity checks were made due to an increase in the
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iodine level in the reactor coolant system during the past fuel cycle.
Any fuel assemblies that were found to be leaking will not be returned to
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the core, but will be replaced with a nonleaking assembly. This
inspection of refueling activities will continue into the next inspection
period.
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No violations or deviations were identified.
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14. Containment Local Leak Rate Testing
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The NRC inspector verified through observation and records review that the
local leak rate test program for testing of mechanical and electrical
penetrations was being performed in accordance with TS requirements. The
NRC inspector observed / reviewed the following items.
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All electrical and mechanical penetrations listed in the TS were
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tested in accordance with the licensee's approved procedure
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Procedure ST-CONT-2, " Containment Local Leak Detection Tests - Type B,"
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provided the appropriate instructions for testing of penetrations
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The test equipment used was in current calibration
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The pressure used for testing conformed to the pressure specified in
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the TS
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Repairs were initiated for any penetrations discovered to be leaking
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Action was taken to verify that the maximum allcwable leakage rate
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was not exceeded upon discovery of a leaking penetration
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Based on the reviews performed during the inspection period, it appeared
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that the licensee was implementing an appropriate leak rate testing
program. At the end of this inspection period, the licensee had not
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completed the testing of all penetration assemblies. This portion of this
inspection will be continued into the next inspection period.
No violations or deviations were identified.
15. Exit Interview
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The NRC inspector met with Mr. R. L. Andrews (Division Manager - Nuclear
Production) and other members of the licensee staff at the end of this
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inspection.~ At this meeting, the NRC inspector sumarized the scope of
the inspection and the findings,
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Mr. J. Boardman met with licensee personnel on March 20, 1987, to provide
information related to a proposed inspection in the area of corrective
action programs. During the meeting, Mr. Boardman outlined the scope and
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nature of the inspection and submitted a request for copies of licensee
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documentation associated with the inspection. Licensee personnel stated
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that the documentation would be provided in the near future. See
paragraph 1 of this inspection report for meeting attendees.
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