IR 05000298/1986022
| ML20214K267 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/12/1986 |
| From: | Dubois D, Jaudon J, Plettner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20214K261 | List: |
| References | |
| 50-298-86-22, NUDOCS 8608210010 | |
| Download: ML20214K267 (8) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
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NRC Inspection Report:
50-298/86-22 License: DPR-46 Docket: 50-298 Licensee: Nebraska Public Power District (NPPD)
P. O. Box 499 Columbus, NE 68601 Facility Name: Cooper Nuclear Station (CNS)
Inspection At:
Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted:
July 1-3!, 1986 Inspectors:
A.d.Ad/6TMo 8 # 80 E. A. Plettner, Resident Inspector, (RI)
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ofs Senibr Refident Inspector, (SRI)
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the P. Qa n Chief, Project Section A, Date Reacto Project Branch hbk kOchk
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, Inspection Summary Inspection Conducted July 1-31, 1986 (Report 50-298/86-22)
Areas 7nspected:
Routine, unannounced inspection of spent fuel shipments, operational safety verification, and monthly surveillance and maintenance activities.
Results: Within the areas inspected, no violations or deviations were identified.
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Persons Contacted Principal Licensee Employees
- G. R. Horn, Division Manager of Nuclear Operations
- J. M. Meacham, Technical Manager
- J. Sayer, Acting Technical Staff Manager
- C. R. Goings, Regulatory Compliance Specialist
- V. L. Wolstenholm, Quality Assurance Manager
- R. Brungardt, Operations Manager
- L. G. Kuncl, Vice President-Nuclear
- H. Parris, Assistant to the President of Nebraska Public Power District NRC Personnel
- D. L. DuBois, Senior Resident Inspector
- E. A. Plettner, Resident Inspector
- Denotes those present during exit interview July 31, 1986.
2.
Spent Fuel Shipment The NRC inspectors inspected the licensee's activities associated with one shipment of spent fuel from CNS.
Included in that inspection were observations and reviews of applicable procedures, documentation, surveys, inspections, and shipping document preparation.
The NRC inspectors verified by review of licensee documentation, through discussions with responsible personnel, and by independent inspection that the licensee completed the following:
Receiving inspection of railcars and shipping casks
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Shipping docuenents
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Advance notification of and approval by affected state and federal
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agencies.
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Proper placarding of the transport vehicles Appropriate labeling of the spent fuel shipping casks
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Establishment of provisions for response by escorts and local law
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enforcement agencies
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Testing of communications systems
. Continual manning of the licensee's communications center (Movement
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Control)
Terting of fuel and cask handling cranes, hoists, and tools
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Proper loading and sealing of the spent. fuel shipping casks
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. Surveillance of area radiation monitors, ventilation systems, and -
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spent fuel. pool water level and chemistry Update of fuel location and accountability records-
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Applicable quality assurance audits and inspections
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U.S. Department of Energy and U.S. NRC, " Nuclear Material
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Transaction Report," DOE /NRC Form 741 Bill of Lading
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CNS Health Physics Procedure 9.5.3.7, " Cask IF-300 Shipment,"
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Revision 3, dated December 26, 1985 CNS Nuclear Performance Procedure 10.27, " Cask IF-300 Handling and
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Shipping," Revision 6, dated July 17, 1986 CNS HP-138, " Contamination Survey - Sample Count Data Sheets"
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CNS HP-141, " Contamination Survey - Railroad Car for IF-300
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Irradiated Fuel Shipping Cask" CNS HP-142, " Contamination Survey of IF-300 Shipping Casks"
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CNS HP-143, " Radiation Survey of IF-300 Shipping Cask"
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CNS HP-608, " Spent Fuel Shipment Checkoff Sheet and Certificate of
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Compliance of Number 9001 Conditions for Shipping Spent Fuel" CNS HP-14a, " Radioactive Material Shipment Record"
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The following independent radiation and contamination surveys were performed by the~RI and verified to be satisfactory:
' Contact radiation surveys of the shipping casks
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Radiation surveys at a distance of 2 meters from the cask transport
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vehicles
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-5-Contamination surveys of the shipping casks surfaces
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. Contamination surveys of the cask transport vehicles
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The spont' fuel shipment lef t the CNS on July 14, 1986. The shipment consisted of 2 spent fuel shipping casks, each of which contained 18 spent fuel bundles.
The shipment was transported to the G.E. Morris Operation Complex, Morris, Illinois.
The spent fuel casks identification number were:
IF-301'
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IF-302
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The observati.ons, reviews, and independent measurements were conducted to
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verify that spent fuel handling and shipment operations were in conformance with the' req'uirements established in the CNS Operating License and Technical Specification.
No violations or deviations were identified in this area.
3.
Operational Safety Verification-The NRC inspectors observed control room operations, instrumentation, controls, reviewed. plant logs and records, conducted discussions with control room personnel, and performed system walk-downs to verify that:
Minimum shift manning requirements were met.
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Technical Specification requirements were observed.
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Plant operations were conducted using approved procedures.
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Plant logs and records were complete, accurate, and indicative of
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actual system conditions and configurations.
System pumps, valves, control switches, and power supply breakers
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were properly aligned.
Licensee systems lineup procedures / checklists, plant drawings, and
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as-built configurations were in agreement.
Instrumentation was accurately displaying process variables and
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protection system status to be within permissible operational limits for operation.
When plant equipment was found to be inoperable or when equipment was
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removed from service for maintenance, it was properly identified and redundan; equipment was verified to be operable. Also, the NRC inspectnrs verified that applicable limiting conditions for operation were identified and maintained.
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-6-Equipment safety clearance records were complet'a and indicated that
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affected components were removed from and returned to service in a correct and approved manner.
Maintenance work requests were initiated for equipment discovered to
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require repair or routine preventive upkeep, appropriato priority was assigned, and work commenced in a timely manner.
Plant equipment conditions such as cleanliness, leakage, lubrication,
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and cooling water were controlled and adequately maintained.
Areas of the plant were clean, unobstructed, and free of fire
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hazards.
Fire suppression systems and emergency equipment were maintained in a condition of readiness.
Security measures and radiological controls were adequate.
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The NRC inspectors performed a lineup verification of the following systems:
Reactor Core Spray (CS) "B" Loop
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Primary Containment Cooling and Nitrogen Inerting System (PC)
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Reactor Water Clean Up (RWCW)
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Automatic Depressurization System (ADS)
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Information received from the licensee with regards to IE Bulletin No. 86-02, " Static "0" Ring Differential Pressure Switches," and IE Notice No. 86-47, " Erratic Behavior of Static "0" Ring Differential Pressure (D/P) Switches," was reported in NRC Inspection Report 50-298/86-21, paragraph 5.
A written response dated July 25, 1986, from the licensee had information that conflicted with the information in NRC Inspection Report 50-298/86-21.
The information in Inspection Report 86-21 was that six static "0" ring switches were used in the Radioactive Waste Treatment System.
This was based upon a review of a list of switches by the licensee.
Follow up by the licensee indicated that these switches were only used in the turbine lube oil system.
The resident inspector confirmed that the licensee's initial written response to IEB 86-02 was correct.
The turbine lube oil system identified in the licensee's written response dated July 25, 1986, is a non-safety system.
No further action was required.
4.
Monthly Surveillance Observations
'The NRC inspectors observed Technical Specification required surveillance tests.
Those observations verified that:
Tests were accomplished by qualified personnel in accordance with
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approved procedures.
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-7-Procedures conformed to Technical Specification requirements.
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Tests prerequisites were completed including confonnance with
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applicable limiting conditions for operation, required administrative approval, and availability of calibrated test equipment.
Test data was reviewed for completeness, accuracy, and conformance
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with established criteria and Technical Specification requirements.
Deficiencies were corrected in a timely manner.
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The system was returned to service.
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The RI observed the licensee's performance of the following surveillance tests on the indicated dates:
July 7,1986, SP 6.3.12.1, " Diesel Generator Operability Test "
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Revision 17, dated March 6, 1986.
July 16, 1986, SP 6.3.3.1, "HPCI Test Mode Surveillance Operation,"
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Revision 23, dated June 12, 1986.
.f The reviews and observations were conducted to verify that facility
surveillance operations were performed in accordance with the requirements established in the CNS Operating License and Technical Specification.
No violations or deviations were identified in this area.
5.
Monthly Maintenance Observation The NRC inspectors observed preventive and corrective maintenance activities. These observations verified that:
Limiting conditions for operation were met.
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Redundant equipnent was operable.
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Equipment was adequately isolated and safety tagged.,
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Appropriate administrative approvals were obtained prior to
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coninencement of work activities.
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Work was performed by qualified person'nel in' accordance:w'ith' approved
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procedures.
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Radiological controls, cleanliness practices, and appropriate fire
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prevention precautions were implemented and' maintained, t
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performed as required.
Equipment was properly returned to service.
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The RI observed the licensee's performance of the maintenance test,.
I&C 7.5.2.1P, "SRM Quarterly Calibration Procedure," Revision 12, dated July 10, 1986.
These reviews and observations were conducted to verify that facility maintenance operations were performed in accordance with the requirements established in the CNS Operating License and Technical Specification.
No violations or deviations were identified in this area.'
6.
Exit Meetings Exit meetings were conducted at the conclusion of each portion of the inspection.
The NRC inspectors summarized the scope and findings of each inspection segment at those meetings.
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