IR 05000298/1987007
| ML20215H320 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/09/1987 |
| From: | Dubois D, Jaudon J, Plettner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215H307 | List: |
| References | |
| 50-298-87-07, 50-298-87-7, NUDOCS 8704200262 | |
| Download: ML20215H320 (14) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-298/87-07 License: DPR-46
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Docket: 50-298 Licensee: Nebraska Public Power District (NPPD)
P. O. Cox 499 Colu:1 bus, NE 68601 Facility Nme: Cooper Nuclear Station (CNS)
Inspectico At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted: fiarch 1-31, 1987
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Inspectors:
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-//2/#7 E. A. Plettner, Resident Inspector, (RI)
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D. L. DuBois, Senior Resideelt I.ispector, (SRI)
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Inspection Summary Inspection Conducted March 1-31, 1987 (Report 50-298/87-07)
Areas Inspected:
Routine, unannounced inspection of licensee actions on previous inspection findings, licensee event reports followup, operational-safety verification, and monthly surveillance and maintenance observations.
Results: Within the areas inspected, no violations or deviations were identifie _ _ - _ _ _____ _.
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Persons Contacted Principal Licensee Employees
- G. R. Horn, Division Manager of Nuclear Operations
- J. M. Meacham, Senior Manager, Technical Support
- R. Brungardt, Manager, Operations C. R. Goings, Regulatory Compliance Specialist
- E. M. Mace, Manager, Engineering j
- D. R. Robinson, Supervisor, Operations Quality Assurance
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L. F. Bednar, Senior Staff Engineer R. D. Black, Supervisor, Operations J. R. Flaherty, Supervisor, Plant Engineering
- H. A. Jantzen, Supervisor, Instrument and Control L. P. Clark, Supervisor, Electrical J. L. Peaslee, Surveillance Coordinator M. E. Hawkins, Foreman, Instrument and Control G. A. Schmielau, Foreman, Instrument and Control
- D. L. Reeves, Senior Staff Engineer M. E. Unruh, Maintenance Planner / Scheduler
- P. L. Ballinger, Supervisor, Operations Engineering
- D. M. Norvell, Manager, Maintenance The NRC inspectors also interviewed other licensee employees during the course of the inspection.
- Denotes those present during exit interview April 3, 1987.
2.
Licensee Action of Previous Inspection Findings The following items of noncompliance or deviation were reviewed by the NRC inspectors to verify that the licensee's response to the items identified in previous inspection reports are now in conformance with regulatory requirements and that corrective measures were completed in a timely manner.
(Closed) Violation (298/8531-02):
Failure to Maintain Housekeeping.
This item involved examples of poor housekeeping practices and the accumulation of materials adverse to fire safety in certain areas of the reactor building.
Identified deficiencies included the following:
Seseral large boxes of refuse and other trash were found in doorways
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and access areas of the Residual Heat Removal "B" Heat Exchanger room and the High Pressure Coolant Injection room.
The material would have limited access of personnel and fire equipmen..
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A fire hose located at elevation 882 ft. in the southwest quadrant of
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the reactor building was covered with personal clothing.
An electric motor associated with radiation wastes effluents monitor
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(TB-486) located at elevation 903 ft. on the south wall of the reactor building had a plastic pail positioned atop the motor.
A number. of aerosol cans containing flannable material were found in
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the 4160 Volt Switchgear Room within three feet of switchgear equipment containing electric heaters.
Corrective actions taken by the licensee included the following:
Conducting discussions on housekeeping practices at subsequent
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monthly safety meetings.
Revising Maintenance Procedure 7.0.1, " Work Item Tracking-Corrective
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Maintenance," to increase middle management involvement in housekeeping practices.
Providing more positive controls on cleaning paraphernalia.
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Installing appropriate cabinets for storage of flannable materials.
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The RI verified that adequate corrective actions were performed by the licensee by his review of the following:
Monthly Safety Meeting record, dated March 20, 1986
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Maintenance Procedure 7.0.1, " Work Item Tracking, Corrective
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Maintenance," Revision 6, dated November 7, 1986 Tool Crib records controlling the procurement and return of cleaning
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paraphernalia Routine walkthroughs of the reactor facilities conducted by several NRC inspectors have confirmed adequate housekeeping practices, and the installation of flannable storage cabinets has been completed.
This item is closed.
(Closed) Violation (298/8531-03):
Failure to Properly Log and Signoff Surveillance Discrepancies.
This item involved Surveillance Procedurcs (SP) 6.4.5.1, " Fire Protection System Monthly Inspection," Revision 38, dated November 7, 1985, and SP 6.4.5.2, " Fire Protection System Annual Inspection," Revision 30, dated Noventer 7,1985. Both procedures required that all discrepancies shall be recorded in the shift supervisors log. The following were noted:
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Annual inspections dated February 13 and May 15, 1985, identified
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discrepancies not recorded in the shift supervisors log.
Monthly inspections dated August 4, September 2, 28, and October 29,
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1985, had nonconformance work items initiated without the shift supervisor's signature on Attachment "A."
The following corrective actions were taken by the licensee:
The discrepancies resulting from the monthly and annual inspections
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were added in the shift supervisor's log.
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The nonconformance work items identified in the monthly inspections
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dated August 4, September 2, 28, and October 29, 1985, were signed to indicate that work items were initiated.
All shift and control room supervisors were instructed on-
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surveillance procedure requirements.
The surveillance coordinator reviewed completed surveillance
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procedures for appropriate signatures.
The RI verified adequate licensee corrective actions by his review of the following:
Applicable shift supervisor logs were revised to verify that they
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included the required entries.
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Affected nonconformance work items were signed as required.
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CNS letter (serial CNS5865076) was signed by all shift and control
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room supervisors indicating they had reviewed the surveillance procedure requirements.
The RI conducted a personal interview with the surveillance
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coordinator and verified that he had received appropriate instructions for performing an adequate review of completed
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surveillance procedures.
This item is closed.
(Closed) Violation (298/8532-01)
Lack of Procedural Guidance For Calibration of Test Equipment.
This item involved procedures which did not define the requirements for the calibration of certain gauges used in connection with safety-related activities.
Pressure gauges used for Local Leak Rate Testing (LLRT) to fulfill Technical Specification requirement 4.7.A.2.F, were calibrated but lacked procedures to define and document calibration requirements (i.e.,
tolerances, frequencies, and standards).
Corrective action taken by the licensee was to add the pressure gauges to Instrument and Control (I&C)
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Procedure 7.5.4.2, " Pressure Test Gauge Calibration," by August 1,1986.
The RI reviewed I&C Procedure 7.5.4.2, Revision 19, dated May 1, 1986, and
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verified that appropriate changes had been added.
This item is closed.
(Closed) Violation (298/8611-01):
Failure to Include Quality Assurance (QA) Requirements in Purchase Orders.
This item involved Purchase Order Nos. 251173 and 251900, which failed to l
include all applicable quality standards. Corrective actions taken by the licensee were to correct the two purchase orders immediately, to update the approved supplier list, and to instruct all station QA personnel on purchase order review and use of the approved supplier list. The RI reviewed Purchase Orders 251173 and 251900 and the approved suppliers list to verify that appropriate changes were made to those documents. Also, the RI reviewed training records dated June 3,1986, and verified that all
station QA personnel were instructed in the areas of purchase order review and the use of the approved supplier list.
This item is closed.
(Closed) Violation (298/8612-01):
Failure to Meet Seismic Requirements.
i This item involved the inadequate seismic support of emergency diesel generators Class I Switchgear Cabinets EG-1 and EG-2. On March 18, 1986, the licensee discovered that Switchgear Cabinets EG-1 and EG-2 were not anchored by welding or bolting. The licensee immediately welded Switchgear Cabinets EG-1 and EG-2 to the embedded channel located directly beneath the switchgear cabinets.
In addition, the licensee reviewed all safety-related floor mounted switchgears construction records and performed as-built inspections of the cabinets to determine the seismic support requirements for and the present as-built seismic mounting of the switchgear cabinets. All seismic support discrepancies were corrected during the fall 1986 refueling outage. The licensee documented and modifications in Design Change (DC)86-136 and Work Item (y structural performed those reviews, inspection findings, and necessar WI)86-4699. A synopsis of the licensee activities were reported to the NRC in Licensee Event Reports 50-298/86-009 and 50-298/86-009, Revision 1.
An NRC review of the final as-welded condition of EG-1 and EG-2 switchgear cabinets was documented in NRC Inspection Report 50-298/86-12. The R1 reviewed DC 86 136 and WI 86-4699 to verify that the licensee had completed all documented reviews and modifications as committed. DC 86-136 has not been closed pending the completion of revisions to applicable as-built drawings. The RI inspected various switchgears to confirm installation of seismic restraints.
This item is closed.
l (Closed) Violation (298/8614-01):
Deficiency of As-Built Instrument j
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This item involved the as-built instrument drawings for the Standby Liquid Control (SLC) and Core Spray System Loop "A."
In both instances the system valve checklist and applicable as-built drawings were not in agreement.
Instr..ent related valves contained on the valve checklist were not numbered or labeled on the applicable as-built drawing. The RI compared System Operating Procedure (SOP) 2.2.74, " Standby Liquid Control System," Revision 15, dated August 1,198E, Appendix A, " Valve Checklist,"
with as-built Drawing Burns & Roe 2045 for the Standby Liquid Control
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System, as-built Drawing NPPD 1.D-13 for the Standby Liquid Control System, as-built Drawing GE117C3314 for the Standby Liquid Control System to verify that all instrument related valves were numbered or labeled on l
the applicable as-built drawings. Also, the RI compared SOP 2.2.9, " Core Spray System," Revision 26, dated August 1, 1985, Appendix A, " Valve l
Checklist," with as-built Drawing NPPD 1.D.-7 for the Core Spray System, l
as-built Drawing NPPD 1.D.-21 for the Core Spray System, and as-built Drawing GE117C3303 for the Core Spray System to verify that the instrument related valves were numbered or labeled on the applicable as-built drawings.
This item is closed.
(Closed) Violation (298/8614-02):
Failure to Follow Procedures.
This item involved CNS Surveillance Procedures (SP) 6.1.25, "RBM Calibration and Functional / Functional Test," Revision 18, dated August 22, 1985; SP 6.2.2.5.12, "RHR Loop A & B Pump and Valve Control Logic Functional Test," Revision 10, dated November 13, 1984; and SP 6.3.1.8,
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" Electrical Penetration Leak Check," Revision 4, dated October 9,1984.
In each example above, station personnel had failed to follow the requirements of the procedure. Corrective actions taken by the licensee were counseling the individuals involved, conducting weekly shift crew meetings on the topic of failure to follow procedures, and performing a review of each procedure identified above. The licensee's review revealed that SP 6.1.25 required revision to separate steps containing paragraphs with several action statements into several steps containing a single action statement; SP 6.3.1.8 required a revision to include a note requiring "All as-found readings for a group of penetrations must be recorded before proceeding to Step 4."
The RI conducted personal interviews with the individuals involved to confirm individual instruction. The RI reviewed weekly shift crew meeting attendance sheets covering the period July 23 through September 3, 1986, and verified that all station operating personnel were present for those briefings. Additionally, the RI reviewed SP 6.1.25, Revision 19, dated May 15, 1986, and SP 6.3.1.8, Revision 5, dated August 7, 1986, to verify appropriate procedural revisions were completed.
This item is closed.
(Closed) Violation (298/8614-03):
Inadequate Procedure.
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ll This item involved Station Operating Procedure (SOP) 0.4, " Preparation,,
Review, and Approval of Procedures," Revision 5, dated April 17, 1986.
The procedure failed to clearly define the proper control of clerical changes to approved procedures. Corrective actions taken by the licensee were revising Procedure 0.4 to define the proper controls for clerical changes and training the procedure specialist and clerk on the specifics described in the new revision of Procedure 0.4.
The RI reviewed 50P 0.4, Revision 7, dated July 2, 1986, to verify appropriate changes were completed. The RI conducted personal interviews with both individuals and confirmed they received adequate procedural instruction.
This item is closed.
(Closed) Violation (298/8621-01): Failure to Have a Procedure for Controlling Activities Affecting Quality.
This item involved the licensee's failure to have a procedure for providing necessary guidance and control to ensure that amendments to license documents (i.e., Technical Specification (TS) and Updated Safety Analysis Report (USAR)), resulted in approved revisions to appropriate station procedures. Specifically, Surveillance Procedures 6.2.4.1, " Daily Surveillance (Technical Specification)," and Nuclear Performance
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Procedure (NPP) 10.1, "APRM Calibration," had not been revised to reflect
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the requirements of CNS Technical Specification Amendment 94, dated September 24, 1985. Corrective actions taken by the licensee included revision of Procedures 6.2.4.1 and 10.1 to reflect the TS requirements and (
development of a new procedure to provide guidance and controls for incorporating licensing amendments into station procedures. The RI reviewed SP 6.2.4.1, Revision 51, dated December 19, 1985, and NPP 10.1 Revision 15, dated December 5,1985, to verify that appropriate procecure revisions were completed. Also, the RI reviewed Administration Procedure 0.29, " Administrative Control of Licensee Amendments," Revision 0, dated October 30, 1986, and determined that the procedure was adequate in providing the appropriate guidance and controls to incorporate licensing amendment changes into station procedures.
I This item is closed.
(Closed) Violation (298/8627-02):
Failure to Have an Adequate Refueling Procedure.
This item involved Nuclear Performance Procedure (NPP) 10.25, " Refueling," '
Revision 6, dated August 7, 1986. The procedure failed to specify the need to ensure that the refueling mast be fully retracted before moving the refueling bridge between the fuel pool and the reactor cavity.
Licensee corrective actions included issuance of a directive in the Standing Night Order Log to operating personnel stating that movement between the fuel pool and the reactor cavity be accumplished with the refueling mast fully retracted and revision of NPP 10.25 to inchde the directive stated above. The RI reviewed NPP 10.25, Revision 8, dated I
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February 12, 1987, to verify that appropriate entries and changes were complete.
This item is closed.
(Closed) Violation (298/8627-05):
Inadequate Cleanliness Controls.
This item involved the licensee's failure to maintain suitable cleanliness controls in the High Pressure Coolant Injection (HPCI) room during pneumatic wire brush cleaning operations.
A pneumatic wire brush had been used to clean the threaded portions of bolts removed during disassembly of the HPCI turbine without taking proper precautions to contain the residue materials.
The resulting residue material had been deposited on the auxiliary lube oil pump motor and nearby turbine components. The SRI notified the licensee of the inadequate clean ~,iness conditions, and work was immediately halted. Additional corrective actions taken by the licensee included inspecting the motor internals and turbine components for cleanliness and a briefing for all maintenance department mechanical personnel on the topic of housekeeping and good maintenance practices.
The RI reviewed the licensee's corrective actions and determined those actions were complete.
This item is closed.
(Closed) Violation (298/8627-06):
Failure to Provide Adequate Controls in a Special Test Procedure.
This item involved Special Test Procedure 86-08, " Inspect 1E Board Mounted Switch Gear," dated October 18, 1986.
The procedure was inadequate because it failed to identify the removal of an insulating devica called a
" boot" from a set of relay contacts on an undervoltage relay.
- orrective actions taken by the licensee were to revise 50P 2.2.17, " Emergency Station Service Transformer," to include appropriate steps to ensure removal of the boot and for the operations supervisor would to conduct weekly shift crew meetings on the topics of placing insulating devices on undervoltage relay contacts and the change to Procedure 2.2.17.
The RI reviewed 50P 2.2.17, Revision 8, dated December 29, 1986, and weekly shift crew meeting attendance sheets during the period of November 24, 1986, through February 5, 1987, to verify that licensee corrective actions were complete.
This item is closed.
(Closed) Violation (298/8636-03):
Failure to Follow Procedure.
This item involved the licensee's failure to have the latest revision of Nuclear Performance Procedure (NPP) 10.25, " Refueling," in the Refueling Floor Procedure Book.
Corrective actions taken by the 71censee were to place the correct revision of NPP 10.25 into the Refueling Floor Procedure Book and to add the procedure to the Control Room Procedure Distrfbution List.
The RI reviewed the Refueling Floor Procedure Book and Contro'. Roem l
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Procedure Distribution List and verified that licensee corrective actions vere complete.
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This item is closed.
3.
Licensee Event Reports Followup The following Licensee Event Reports (LERs) were closed on the basis of the SRI's.inoffice reviews, reviews of licensee documentation, and discussions with licensee personnel:
LER 86-009, Revision 1. " Emergency Diesel Generators 1 & 2 Switchgear Mounting Anomaly-Supplemental Information" LER 86-014, "Inidvertent Isolation of Reactor Water Cleanup System" LER 86-015, " Loss of Emergency Transformer Supply Due to Lightning"
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LER 86-016 " Reactor Scram During HFA Relay Replacement" lLER86-017,"ClosureofHPCISteamSupplyValve" LER 86-018;'" Failure to Monitor Reactor Water Conductivity" LER 86-019, " Reactor Water Cleanup Group III Isolation" LER 86-020, " Loss of Emergency Transformer Due to Lightning" LER 86-021, " Loss of Emergency Transformer Supply" LER 86-022, "firoup Isolations and RPS Trip During Reactor Shutdown"
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LER 86-023, " Apparent Unnecessary Operation of an Engineered Safety Feature" LER 86-024, "RWCU Group III Isolation" LER 86-025, " Inadvertent Auto-Start of Diesel Generator #2" LER 86-026 " Emergency Diesel Generator Cylinder Head Cracking" LER 86-026, Revision 1, " Emergency Diesel Generator Cylinder Head Cracking-Supplemental Infonnation" LER 86-027, " Safety Related Instrument Rack Seismic Deficiencies" LER 86-028, " Standby Gas Treatment System Seismic Design Deficiencies" LER 86-029, " Loss of Emergency Transfonner Supply causing Emergency Diesel Generator Auto-Start" m
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LER 86-030, " Inadvertent Bumping of Relay Causes Auto-Start of Emergency Diesel Generator" LER 86-031, " Unplanned Actuation of Group 11 and VI Containment Isolation Circuitry as a Result of Short Circuit During Design Change Modification Activities" LER 86-032, " Main Steam Safety Relief Valve Setpoint Drift and Stuck i
Pilot Valve Inoperability Discovered During Scheduled Valve Testing and Refurbishment" i
LER 86-033, " Residual Heat Removal and Core Spray Pump Motor Deficiencies Believed to be Caused by High Cycle Fatigue Loading which were Discovered During Inspection" LER 86-034 " Storage of Fuel in the Spent Fuel Storage Pool with U-235 I
Loading in Excess of Technical Specification Limits Due to Pel.let l
Design Changes & Manufacturer Variances"
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LER 86-035, " Unplanned Challenge to an Engineered Safety Feature Due to Personnel Error While Troubleshooting" 4.
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 walkdowns to verify that:
f Minimum shift manning requirements were met,
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f 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.
Instrumentation was accurately displaying process variables and
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protection system status was within permissible limits for operation.
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l removed from service for maintenance, it was properly identified and redundant equipment was verified to be operable. Also, the NRC inspectors verified that applicable Umiting conditions for operation were identified and maintained.
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Equipment safety clearance records were complete 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, appropriate priority was assigned, and work commenced in a timely manner.
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The conditions of the plant and equipment such as cleanliness,
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leakage, lubrication, and cooling water were controlled and i
adequately maintained.
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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:
High Pressure Coolant Injection (HPCI)
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Core Spray "A"
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The SRI independently verified the following clearance orders for proper placement / restoration of affected components:
87-211, Service Water Pump "0"
.87-214, Sparger Pump "C"
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The tours, reviews, and observations were conducted to verify that facility 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 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.
Procedures conformed to Technical Specification requirements.
Tests prerequisites were completed including conformance with
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applicable limiting conditions for operation, required administrative approval, and availability of calibrated test equipment.
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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 tested was returned to service.
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The RI observed the licensee's performance of the following surveillance test on the indicated date:
March 24, 1987: SP. 6.1.29, "APRM System (Flow Bias and Startup Calibration and/or Functional Test)," Revision 15, dated December 28, 1986.
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.
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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 equipment 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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consnencement of work activities.
Work was performed by qualified personnel in accordance with approved
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procedures.
Radiological controls, cleanliness practices, and appropriate fire
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prevention precautions were implemented and maintained.
Quality control checks and postmaintenance surveillance testing were
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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 following maintenance activities on the indicated dates:
March 17, 1987: Work Item (WI) 87-0752, Reactor Water
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March 27, 1987: WI 87-0623, Thermostat Control for Alternate
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Shutdown Room March 27, 1987: WI 87-1054, Main Reactor Feedpump "A"
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March 27, 1987: WI 87-0827, Service Water Pump Motor "D"
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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.
7.
Exit Interviews Exit interviews 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 and at a summary exit interview on April 3,1987.
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