IR 05000298/1986023

Insp Rept 50-298/86-23 on 860801-31.No Violation or Deviation Noted.Major Areas Inspected:Plant Trips - Safety Sys Challenges,Spent Fuel Shipments,Operational Safety Verification & Monthly Surveillance & Maint Activities

ML20210F928
Person / Time
Site:	Cooper
Issue date:	09/18/1986
From:	Dubois D, Jaudon J, Plettner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20210F874	List: IR 05000298/1986023 ML20210F869
References
50-298-86-23, NUDOCS 8609250305
Download: ML20210F928 (10)

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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection Report:. 50-298/86-23 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)-

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Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted: August 1-31, 1986 Inspectors: [. E. A. Plettner, Resident Inspector, (RI)

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,t i h*, Inspection Summary -

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t, Inspection Conducted August 1-31, 1986 (Repo.t 50-298/86-23)

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w ...oe9c,' Areas Inspected:

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Rc uti ne ,. ., unannounced inspection of plant trips - safety

% system challenges? spent. fuel shipments, operational safety verification, and u ' monthly surveilldnce.a,nd raintenance activitie .

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Yr Res'ultsi E Within the'~five areas inspected, no violations or deviations were

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DETAILS

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1.- Persons Contacted Principal Licensee Employees ,

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• G. R. Horn, Division Manager of Nuclear Operationss .

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• J. M. Meacham, Technical Manager . .

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• C. R. Goings, Regulatory Compliance Specialist i

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• F. Aldennan, Fire Chief . ' '

• R. Beilke, Chemistry & Health Physics Supervisor ,

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• S. Woerth, " Acting" Technical Staff Manager" ,

• H. T. Hitch, Plant Services Manager , ,' , ,

The NRC inspectors also interviewed other licensee employees'during the '~ ~

course of the inspectio ,

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• Denotes those present during exit interview September 3,~ 198 . Plant Trips - Safety System Challenges i

The NRC inspectors held discussions with operations shift personnel and reviewed control room records including log entries, recorder traces, and computer printouts associated with an unscheduled reactor scram that occurred on August 13, 1986, at 1:20 p.m. The reactor was at 90 percent of rated power and in steady state operating conditions prior to the scram.

On August 13, 1986, Main Steam Line High Radiation Relay SA-K7A, was being replaced in accordance with Maintenance Work Request (MWR 86-3059. Relay 5A-K7A, located in Reactor Protection System (RPS)) Channel "A", had previously failed to actuate

Annunciator 9-5-2/3-3, " Main Steam Line High-High Radiation Trip," during the conduct of Surveillance Procedure 6.1.4, " Main Steam Line Process Radiation Monitor Calibration and Functional / Functional Test,"

Revision 32, dated July 10, 1986. A half scram and half Group 1 isolation s was inserted in RPS Channel "A" as required by the CNS Technical Specifications during that maintenance activity. While disconnecting the relay coil power supply lead from the relay terminal board, intermittent arcing occurred; this generated radio interference which caused an RPS Channel "B" Main Steam Line High-High Radiation Trip. The simultaneous presence of both RPS Channel "A" and "B" trips caused a full reactor scram and full Group 1 isolation. As a result of the rapid closure of the Main Steam Isolation Valves (MSIV), Groups 2, 3, 6, and 7 isolations also occurre Safety-relief valves actuated to maintain reactor pressure. The High

. Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) systems pumps started and restored reactor water level to normal. The standby gas treatment system started on the Group 6 isolation. Both emergency diesel generators automatically started but were not required to supply power to their respective vital, 4160V AC

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busses because of the successful transfer of those busses to the emergency transformer. No other safety systems were required to operate. The

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licensee made notification of the event to the NR Following the scram, the plant operators opened the MSIVs and established reactor water level control using the RCIC pump and pressure control using the main steam bypass system. The plant was cooled down to approximately 350*F, and miscellaneous maintenance'was performed.. The reactor was restarted on August 14,1986,-and the main turbine was loaded on August 15, 198 The licensee subsequently confinned that the cause of the RPS Channel "B" Main Steam Line High-High Radiation Trip was the production of radio frequency energy caused by the intermittent arcing which occurred while disconnecting relay 5A-K7A. That energy was transmitted to the remaining main steam line radiation monitors electronic drawers that were located in -

the immediate vicinit The NRC inspectors attended several licensee Safety Operations Review Consnittee (SORC) Meetings. Those meetings provided assurance that the licensee had thoroughly reviewed the scram and that.those reviews indicated that plant startup.could be authorize The NRC inspectors observed the licensee's performance of the following procedures:

. GOP 2.0.5, " Shift Communicators Responsibility," Revision 1, dated February 13, 1986

. GOP 2.1.2, Attachment A, " Scram Recovery Checklist," Revision 25,

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. GOP 2.1.4, " Normal Shutdown from icwer," Revision 24, dated June 19, 1986

. GOP 2.1.5, " Emergency Shutdown from Power," Revision 7, . dated March 27, 1986 -

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l . E0P No. 1, " Reactor Pressure Vessel (RPV) Controls "-Revision 2,

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dated April 4, 1986

. E0P No. 2, " Primary Containment Control," Revision 2, dated April 4,

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. Scram Report No. 86-02, dated August 13, 1986 The inspections, reviews, discussions, and observations were conducted to verify that: the plant responded as designed; plant personnel perfonned ininediate and followup corrective actions; and there were no unreviewed safety questions. Also, the NRC inspectors verified that facility operations were in conformance 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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5 Spent Fuel Shipments The NRC inspectors inspected the licensee's activities associated with two shipments of spent fuel from CNS. Included in those inspections were observations and reviews of applicable procedures, documentation, surveys, inspections, and shipping document preparatio 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

. Shipping documents

. Advance notification of and approval by affected state and federal agencies

. Proper placarding of the transport vehicles

., Appropriate labeling of the spent fuel shipping casks ,

. Establishment of provisions for response by escorts.and local law

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enforcement agencies ,

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. Training of escort personnel ,

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. Testing of communications systems , _ 1 ,,

. Continual manning of the licensee's communications center.(Movement ' '

Control)

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. Testing of fuel and cask handling cranes, hoists, and tools s

. Proper loading and sealing of the spent fuel shipping casks

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Surveillance of area radiation monitors, ventilation systems, and spent fuel pool water level and chemistry

. Update of fuel location and accountability records

. Applicable quality assurance audits and. inspections

. U.S. Department of Energy and U.S. NRC, " Nuclear Material Transaction Report," DOE /NRC Form 741 l

. Bill of Lading

. CNS Health Physics Procedure 9.5.3.7, " Cask IF-300 Shipment,"

Revision 3, dated December 26, 1985-

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-CNS Nuclear Performance Procedure 10.27, " Cask IF-300 Handling and 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 Irradiated Fuel Shipping Cask"

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CNS HP-142, " Contamination Survey of IF-300 Shipping Casks"

. CNS HP-143, " Radiation Survey of IF-300 Shipping Cask"

, CNS HP-608, " Spent Fuel Shipment Checkoff Sheet and Certificate of

. Compliance of Number 9001 Conditions for Shipping Spent FuelE

. CNS HP-14a, " Radioactive Material Shipment Record" The following independent radiation and contamination surveys were performed by the NRC inspectors and verified to be satisfactory:

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. Contact radiation surveys of the. shipping casks .

. -Radiation surveys at a distance of two meters from the cask transport

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. Contamination surveys of the shipping casks'surfacesw _ . .

. Contamination surveys of the cask transport vehicles The spent fuel shipments left the CNS on August 6 and 26,1986.= Each

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shipment consisted of 2 spent fuel ~ shipping casks, each of which contained-18 spent fuel bundles. The shipments were transported to the G.E. Morris Operation Complex, Morris, Illinois. . The spent fuel casks identification numbers were:

i . Shipment No. 1 - Casks IF-301 and IF-302

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. Shipment No. 2 - Casks IF-301 and IF-302 j The observations, reviews, and independent. measurements were conducted to

' verify that spent fuel handling and shipment operations were in l conformance with the requirements established in the CNS Operating License l

and Technical Specificatio No violations or deviations were identified in this area.

, Operational Safety Verification l

l 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:

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. -Minimum shift manning requirements were me . Technical Specification requirements were observe . Plant operations were conducted using approved procedure . Plant logs and records were complete, accurate, and indicative of

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actual system conditions and configurations.

f . System pumps, valves, control switches, and power supply breakers were properly aligne . Licensee systems lineup procedures / checklists, plant drawings, and as-built configurations were in agreement.

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Instrumentation was accurately displaying process variables and

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protection system status to be within permissible operational limits

for operation.

i . When plant equipment was found to be inoperable or when equipment was removed from service for maintr.nence, it was properly . identified and redundant equipment was verified to be operable.- Also, the NRC inspectors verified that applicaMe limiting conditions for operation were identified and maintsine . Equipment safety clearance reccrds were complete'and indicated that affected components were removed from and returned.to service in a

correct and approved manne . Maintenance work requests were initiated for equipment discovered to require repair or routine preventive upkeep,' appropriate priority was assigned, and work commenced in a timely manner. '

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. Plant equipment conditions such as cleanliness, lea'k' age, lubrication, and cooling water were controlled and adequately maintained.

. Areas of the plant were cleaa, unobstructed, and, free of fire ~

l hazard Fire suppression systems and emergency equipment were

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maintained in a condition of readines s

. Security measures and radiological controls.were adequat ,

The NRC inspectors performed a lineup verification of the following

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systems:

l . Residual Heat Removal (RHR) "A" Loop

! . Emergency Power The NRC inspectors witnessed a reactor startup and heatup on August 14-15, 1986. The reactor achieved criticality at 8:16 p.m., on August 14, 1986,

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.and the main generator was loaded-at 8:10 a.m. on August- 15,-1986. Those

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report. The following areas were observed or verified prior to, during, and following that startup:

. Operable status of required systems ,,

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. Crew shift manning

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. Usage of and adherence to approved procedures N .

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. Reactor instrumentation response . -

. Management authorization for startup ._

The NRC inspectors observed performance of the following plant procedures:

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. OP 2.0.6, " Reactor Post Trip Review and Restart ' Authorization Procedure," Revision 2, dated April 10, 1986,

. GOP 2.1.1.1, " Reactor Startup Review," Revision 0,' dated May 29, 1986

. GOP 2.1.1.2, " Technical Specifications Pre-Startup. Checks,"-

Revision 6, dated August 8, 1985

. GOP 2.1.2, " Hot Startup Procedure," Revision 25, dated April 24, 1986

. GOP 2.1.3, " Approach to Critical," Revision 10, dated March 27, 1986

. GOP 2.1.10, " Station Power Changes," Revision 11, dated July 24, 1986

. S0P 2.2.14. "22 KV Electrical System," Revision 23, dated May 15, 1986

. S0P 2.2.28, "Feedwater System," Revision 39, dated July-17, 1986

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L . S0P 2.2.56, " Main Steam and Turbine Bypass System," Revision 21, dated August 7, 1986 i . S0P 2.2.77, " Turbine Generator," Revision 26, dated March 13, 1986

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. S0P 2.2.55, " Main Condensor Gas Removal System," Revision 18, dated

March 27, 1986 The tours, reviews, and observations were conducted to verify that facility. operations were performed in accordance with the requirements

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established in the CNS Operating License and Technical Specificatio No violations or deviations were identified in this area.

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9 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 approved procedure .

Procedures conformed to Technical Specification requirement . Tests prerequisites were completed including conformance with applicable limiting conditions for operation, required administrative approval, and availability of calibrated test equipmen .

Test data was reviewed for completeness, accuracy, and conformance with established criteria and Technical Specification requirement .

Deficiencies were corrected in a timely manne .- The system was returned to service'.

The NRC inspectors" observed the licensee's perfonnance of the following surveillance tests on the indicated dates:

. August 4,1986, SP 6.3.12.1, " Diesel Generator Operability Test,"

Revision 17, dated March 6,1986

. August 11, 1986, SP 6.4.9.1, "RMA System Calibration and-Functional / Function Test," Revision 25, dated, June 19, 1986

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. August 11,1986, SP 6.1.14 (N), " North SDV High Water' Level Switches and Transmitters Functional Test," Revision 15, dated' October 8,1984 _

. August 14-15,1986, SP 6.2.2.2.3, " ADS Timer Calibration and Actuation Functional / Functional Test," Revision 19,' dated, January 30, 1986

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. SP 6.2.2.3.9P, "HPCI Auto Isolation Logic Steam Line Space Temperature Functional test," Revision 17, dated June 19, 1986

. SP 6.3.3.1, "HPCI Test Mode Surveillance Operation," Revision. 24, ,

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August 7, 1986

. SP 6.3.3.2, "HPCI Motor Operated Valve Operability Test,"

Revision 13, June 15, 1986

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. SP 6.3.6.1, "RCIC Test Mode Surveillance Operation," Revision 15,

- November 21, 1985

. SP 6.3.12.1, " Diesel Generator Operability Test," Revision 17, dated March 6, 1986 l

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. SP 6.1.26, " Rod Sequence Control System Functional' Test for Startup,"

Revision 11, dated October 27, 1983 The reviews and observations were conducted to verify that facility surveillance operations were performed in accordance with the requirements b

established in the CNS Operating License and Technical Specification, No violations or deviations were identified in this are . Monthly Maintenance Observation The NRC. inspectors observed preventive and corrective maintenance activities. These observations verified that:

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. . Limiting conditions for. operation were me ,. (Reciundant equipment was operabl . Equipmeilt' was adequately isolated and safety tagge ,

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. Appropriate administrative approvals were obtained prior to commencement of work activitie . Work was performed by qualified personnel in accordance with approved

- procedure . Radiological controls, cleanliness practices, and appropriate fire prevention precautions were implemented and maintaine . Quality control checks and postmaintenance surveillance testing were performed as require . Equipment was properly returned to servic These reviews and observation's were conducted to verify that facility maintenance operations were performed in accordance with the requirements established in the CNS Operating License and Technical Specificatio No violations or deviations were identified in this are . 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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