ML20209C537
| ML20209C537 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/21/1986 |
| From: | Harrell P, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20209C519 | List: |
| References | |
| 50-285-86-21, NUDOCS 8609090046 | |
| Download: ML20209C537 (6) | |
See also: IR 05000285/1986021
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-285/86-21
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
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Inspection Conducted:
July 1-31, 1986
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Inspector:
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.H.' Wnior Resid@ntMFeactor
Date'
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' Approved:
/[]d, d -A -
D.7<. Hunter, Chief,' Project Section B
Dat'e
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Reactor Projects Branch
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Inspection Summary
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Inspection Con' ducted July 1-31,~1986 (Report 50-285/86-21)
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Areas' Inspected:
Routine, unannounced inspection including operational safety
verification, maintenance, surveillance, plant tours, safety-related system
walkdowns, security observations, and followup on a previously identified item.
Results: Within the seven areas inspected, two violations (failure to report a
nonfunctional fire barrier, paragraph 4, and failure to properly store CQE
material, paragraph 4) were identified.
8609090046 860902
ADOCK 05000285
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DETAILS
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1.
Persons Contacted
- W. Gates, Plant Manager
- C. Brunnert, Operations Quality Assurance Supervisor
M. Core, Maintenance Supervisor
D. Dale, Quality Control Inspector
- J. Flechr, Station Training Supervisor
J. Foley, I&C and Electrical Field Maintenance Supervisor
- J. Gasper, Administrative Services Manager
- J. Gass, Training Supervisor
M. Kallman, Security Supervisor
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L. Kusek, Operations Supervisor
- T. McIvor, Technical Supervisor
- R. Mueller, Plant Engineer
G. Roach, Chemical and Radiation Protection Supervisor
J. Tesarek, Reactor Engineer
S. Willrett, Administration Services and Security Supervisor
- Denotes attendance at the monthly exit interview.
The inspector also contacted other plant personnel, including operators,
technicians,;and administrative personnel.
2.
Followup on a Previously Identified Item
(Closed) Open Item 8602-04:
Issuance of revised Table 1 for the
Electrical Equipment Qualification Manual (EEQM)
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The licensee has issued a revision to the EEQM to provide a new Table 1.
Table 1 now includes the values of the uncertainties for.the plant
instrumentation loops.
3.
Operation'al Safety Verification
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The NRC inspector conducted reviews and observations of selected
activities to verify tha't facility operations were performed in
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conformance with the requirements established under 10 CFR, administrative
procedures, and the TS.
The NRC. inspector made several control room
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l. observations to verify:
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Proper shift staffing
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. Operator adherence to approved procedures and TS requirements
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Operability of' reactor protective system and engineered safeguards
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equipment
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Logs, records, recorder traces, annunciators, panel indications, and
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switch positions complied with the appropriate requirements
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Proper return to serv'ce of components
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" Maintenhnce orders (MO) initiated for equipment in need of
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- maintenance
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ApprOpYIsle Cuisdust of t uiitrol s'ousu drid ulher licensed operators
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No violations or deviations were noted.
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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 reauirements of radiation work permits
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Work activities performance in accordance with approved procedures
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During a plant tour, the NRC inspector noted that extraneous material was
piled on top of the paper sacks containing boric acid.
The extraneous
material consisted of piping, tools, and rags.
The sacks of boric acid
are used by the licensee for boration of the reactor coolout system.
The licensee purchased and maintained the boric acid as CQE material.
Criterion XIII of Appendix B to 10 CFR Part 50 and Section 7.3, " Storage,
Shipping, and Handling," of the licensee's QAP require that CQE material
be stored such that da.nage or deterioration will be prevented.
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licensee has established a program to erect temporary CQE storage areas
for CQE material whenever the material is stored inside the plant.
The
licensee failed to store the boric acid in a temporary CQE area, thus
providing the potential for damage or deterioration to the acid.
The
failure to properly control the storage of CQE material in the plant is an
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apparent violation.
(285/8621-01)
Upon notification by the NRC inspector, the licensee evaluated the boric
acid and determined that no deterioration or damage had occurred.
The
licensee established a temporary CQE area for the boric acid and has
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maintained the area for boric acid storage since notification of the
problem by the NRC inspector.
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During-a plant tour, the NRC inspector also noted that a portion of the
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fire barrier between the upper and lower electrical penetration rooms had
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not been; functional.(intact) fer seme time.
The licensee is currently in
the-process of installing a stairway between these two areas.
During this
period of construction, the fire barrier has been breached by a hole
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approximately 8 feet by 10 feet.
The NRC inspector reviewed past station
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logs.and noted that the fire barrier has no'. been functional since
approximat'ely May 15, 1986. The review also indicated that the licensee
verified the operability of the fire detectors in the upper electrical
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penetration: room and established an hourly fire patrol.
The fire patrol
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has been m'aintained since the barrier was nonfunctional.
The NRC
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'in'spector' requested the licensee provide a copy of the report the licensee
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sent to the NRC notifying the NRC of a fire barrier being nonfunctional
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for.an' extended period of time.
The licensee. informed the NRC inspector
that a report had not been sent.
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TS 2.19(7), requires that a nonfunctional fire barrier be restored withing
,7 days or a-written report be prepared and submitted to the NRC within an
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additional,30 days.
The licensee did not prepare or submit a letter to
the NRC within.the required timeframe.
This is an apparent violation.
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(285/8621-02)
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When it was verified that a report had not been submitted, the licensee-
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immediately completed and transmitted the report to the NRC.
5.
Security Observations
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The NRC inspector verified the physical 'ecurity plan was-being
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implemented by selected observation of the following items:
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The security organization is properly manned.
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Personnel within the protected area (PA) display their identification
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badges.
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Vehicles are properly authorized, searched, and escorted or
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controlled within the PA.
Persons and packages are properly cleared and checked before entry
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into the PA is permitted.
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The effectiveness of the security program is maintained when security
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equipment failure or impairment requires compensatory measures to be
employed.
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No violations or deviations were identified.
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6.
Safety-Related System Walkdowns
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The NRC inspector walked down accessible portions af the following
safety-related systems to verify system operability.
Operability was
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determined by verification of selected valve and switch positions.
The
systems were walked down using the drawings and procedures noted in
parenthesis.
Main steam system (Drawing M-252, Revision 40 and Procedure OI-MS-2,
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Revision 14)
Main feedwater system (Drawing M-253, Revision 51 and
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Procedure OI-FW-2, Revision 15)
During the walkdowns, the NRC inspector noted minor discrepancies of an
editorial nature between the drawings, procedures, and plant as-built
conditions for the selected areas checked.
None of the conditions noted
affected the oper6bility or safe operation of the systems.
Licensee
personnel stated that the noted minor discrepancies would be corrected.
No violations or deviations were identified.
7.
Monthly Maintenance Observation
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
during the reviews and/or observations:
The TS limiting conditions for operation were met while systems or
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components were removed from service.
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.
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Functional testing and/or calibrations were performed prior to
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returning components or systems to service.
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. 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
activitids:'
Troubleshooting transformer for security systems power supply
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(M0 862447)
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Inspection and installation of cable tray covers (M0 862038)
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No violations or deviations were noted.
8.
Monthly Surveillance Observation
The NRC inspector observed selected portions of the performance of and/or
reviewed completed docume.itation 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 persannel 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
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Monthly auxiliary' feedwater pump check (ST-FW-1-F.2)
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Emergency diesel generator monthly test (ST-ESF-6-F.2)
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No violations or deviations were identified.
9.
Exit Interview
TheNRCinspec$ormetwith'Mr.W.G. Gates (PlantManager)andother
members of the'0 PPD staff at the end of this inspection. At this meeting,
the NRC inspector summarized the scope of the inspection and the findings.