IR 05000298/1986010

Insp Rept 50-298/86-10 on 860301-31.No Violations or Deviations Noted.Major Areas Inspected:Refueling Preparations,Spent Fuel Shipment,Training,Operational Safety Verification & Maint Observations

ML20204A511
Person / Time
Site:	Cooper
Issue date:	05/01/1986
From:	Dubois D, Jaudon J, Plettner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20204A507	List: IR 05000298/1986010 ML20204A506
References
50-298-86-10, NUDOCS 8605120296
Download: ML20204A511 (11)

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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-298/86-10 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: March 1-31, 1986 Inspector: - I6t/u 7 6 E. A. Plettner, Resident Inspector, (RI) Date'

Inspector: 3 M D. L. DuBois, Senior Resident Inspector, (SRI) Date Approved: __ M S d J -Ja on, Chief', Project Section A, Date act Project Branch 8605120296 DR 860506 ADOCK 05000298 PDR J. -

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DETAILS Persons Contacted

+ R. Horn, Division Manager of Nuclear Operations

+ L. Reeves, Training Manager

+J. Sayer, Acting Technical Staff Manager

+R. Brungardt, Operations Manager

+V. L. Wolstenholm, QA Manager

+J. M. Meacham, Technical Manager

+ R. Goings, Regulatory Compliance Specialist W. Crawford, Maintenance Supervisor R. Black, Operations Supervisor D. Vanderkamp, Shift Supervisor, Crew C R. Beilke, Chemistry and Health Physics Supervisor H. T. Hitch, Acting Administrative Services Manager R. A. Jansky, Operations Training Supervisor T. R. Sanders, SR0/R0 Instructor Contractor from GE The NRC inspectors also interviewed other licensee operations, maintenance, and administrative personne + Indicates presence at exit meeting held March 31, 198 . Preparation for Refueling A previous inspection was conducted in this area during the period January 1 - February 28, 1986. That inspection concerned the receipt and interim dry storage of new fuel assemblies. The results of that inspection were documented in NRC Raport 50-298/86-02. This inspection completes the inspection of refueling preparations.

. The RI held discussions with fuel handling personnel, observed new fuel inspection and storage activities, verified new fuel storage pool location

! accountability records and status board updates, and reviewed licensee procedure and records concerning the inspection, channeling, and storage of new fuel assemblies. The Nuclear Performance Procedure (NPP) No. 10.23,

"Unirradiated Fuel Inspection and Channeling and Control Blade Inspection,"

Revision 0, dated October 1,1984, was reviewed for technical adequacy prior to the commencement of new fuel handling activitie The RI reviewed the following completed licensee documents applicable to the inspection, transfer, and storage of new fuel assemblies:

NPP 10.21, Attachment "A," page 1 of 6, "Special Nuclear Material Transfer Form," and Page 3 of 6, " Fuel Movement Data Sheet - SNM Transfer other than Refueling Outage."

NPP 10.22, Attachment "A," Pages 3 of 4 and 4 of 4, "New Fuel and Channel Handling - Material and Equipment Checklists."

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NPP 10.23, Attachment "A," " Fuel Assemblies Check Sheet."

NPP 10.23, Attachment "B," " General Electric Discrepancy Report."

NPP 10.23, Attachment "C," " Fuel Channel Inspection Results."

Spent Fuel Pool fuel location status boards lecated on the refueling floor and in the control roo On March 21, 1986, the RI observed the following licensee activities associated with the handling, inspection, transfer, and storage of new fuel assemblies:

. Removal from metal shipping containers (MSC).

. Transfer to the inspection stand and subsequently to storage in the spent fuel poo . Removal of plastic shipping spacer . General inspection and cleaning of new fue . Dimensional measurements taken of fuel rod spacings, spring lengths, channel spacing, and channel fastener torqu . Channeling of fuel bundles in the new fuel inspection stan MSC N Fuel Bundle N Channel N LYD 860 6826 D I-1280 LYD 861 6856 D I-2023 LYD 904 6900 D I-2023 LYD 902 6853 D I-0382 LYD 868 6818 D I-0382 LYD 883 6817 D These discussions, observations, and reviews were conducted to verify that the licensee used and adhered to approved and technically adequate procedures during the conduct of fuel inspection channeling, and storage activities. Also, the RI verified that documentation of the above activities was complete and accurat No violations or deviations were identified in this are . Spent Fuel Shipment The NRC inspectors inspected the licensee's activities associated with a shipment of spent fuel from CNS. Included in that inspection were observations and reviews of applicable procedures, documentation, surveys, inspections, and shipping document preparatio .

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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 cask . Shipping document . Advance notification of and approval by affected state and federal agencie . Proper placarding of the transport vehicle . Appropriate labeling of the spent fuel shipping cask . Establishment of provisions for response by escorts and iocal law enforcement agencie . Training of escort personne . Testing of connunications system . Continual manring of the licensee's communications center (Movement

Control).

. Testing of fuel and cask handling cranes, hoists, and tool . Proper loading and sealing of the spent fuel shipping cask . Surveillance of area radiation monitors, ventilation systems, and spent fuel pool water level and chemistr . Update of fuel location and accountability record . Applicable quality assurance audits and inspection . U. S. Department of Energy and U. S. NRC " Nuclear Material Transaction Report," DOE /NRC Form 74 . Bill of Ladin . CNS Health Physics Procedure 9.5.3.7, " Cask IF-300 Shipment,"

Revision 3, dated December 26, 198 . CNS Nuclear Performance Procedure 10.27, " Cask IF-300 Handling and Shipping," Revision 4, dated December 21, 198 . CNS HP-138, " Contamination Survey - Sample Count Data Sheets."

. 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 Fuel."

. CNS HP-14a, " Radioactive Material Shipment Record."

The following independent radiation and contamination surveys were performed by the NRC inspectcrs and verified to be satisfactory:

. Contact radiation surveys of the shipping casks

. Radiation surveys at a distance of two reters from the cask transport vehicles

. Contamination surveys of the shipping casks surfaces

. Contamination surveys of the cask transport vehicles The SRI reviewed CNS Procedure 10.26, Revision 4, dated February 21, 1986, for detail and technical adequacy. The licensee incorporated into Procedure 10.27 specific handling instructions for the G.E. Type IF-300 spent fuel shipping cask. Also included within Procedure 10.27 was Attachment "A," " Cask IF-300 Handling and Loading" Checkoff Sheet. The checkoff sheet provided two functions: it identified important steps used in the receipt, inspection, preparation, movement, loading with fuel, leak testing, decontamination, loading of the cask onto the transport vehicle, and final preparation for shipping; and it provided a checkoff list including spaces for signatures and/or initials of personnel who performed or witnessed the performance of key steps of the procedure. The SRI verified that Attachment "A" of Procedure 10.27 was properly completed, signed, and date The spent fuel shipment left the CNS on March 13, 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 numbers were IF-302 and IF-30 The observations, reviews, and independent measurements were conducted to verify that spent fuel handling and shipment operations were in conformance with the requirements established in the CNS Operating License and Technical Specificatio No violations or deviations were identified in this are _

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4. Non-Licensed Staff Training The purpose of this inspection was to determine if the licensee had met the general training requirements of the Technical Specifications, paragraph 6. Twenty individual training records encompassing the period from January 1983 to March 1986 were inspected for f requency of General Employee Training (GET). Records were selected at random and included individuals from all occupational categories. The NRC inspector noted that licensee procedure 0.17 required GET tracking annually (plus 25%), while technical specifications allowed u; to two years for this training. The inspection revealed that three individuals had exceeded the procedure allowed time frame by from G to 34 days for Security Refresher Training. Also, two individuals had exceeded the procedural allowed time frame by from 12 to 46 days for Emergency Plan Refresher Training. All refresher training met the technical specifications requirements. The inspector concluded that this was not a violation, because Technical Specifications were not violated, but that it indicated a potential breakdown in management contro Personnel interviews of plant personnel with various employment times and occupational classifications revealed an apparent weak general knowledge of radiological health and safety. Most individuals displayed good general knowledge in the areas of controlled access and security, emergency plan, and industrial safet Completion of formal classroom training plans for non-licensed staff is anticipated for the month of August 1986, when the Institute of Nuclear Power Operations (INP0) arrives for accreditatio . Licensed Operator Training The purpose of this part of the inspection was to verify license compliance with requalification training requirement Personnel interviews with licensed operations personnel revealed that training had been given in specific tasks assigned, such as major plant system tests, refueling and special procedure Review of R0 and SR0 training records revealed proper documentation of training in all areas required by the Cooper Nuclear Power Station Requali-fication Plan. It should be noted that appropriate corrective measures were taken for the individuals that failed a section of the requalification exam and for those people who scored less than 80 percent in a section. As of the closing date of this report period, two individuals have not taken the required exam in the required lecture series and one individual has not attended the required lecture series and taken the required examination to fulfill the requirements of the requalification plan. These individuals have until May 1, 1986, to meet the requirements. Personnel interviews were conducted with R0's and SR0's to ensure that the actual training received corresponded to the recorded data.

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The inspector did not attend any training lectures; however, training material used to give the lecture was reviewed and verified to ensure that the technical content of information was adequate. Exams given at the end of the lecture were reviewed and verified for technical content als The pass rate for requalification exams given by the utility and the NRC over the last three calendar years are as follows: pass rate was 100% given by utility only pass rate was 65% given by utility and NRC pass rate was 87% given by utility and NRC The pass rate for replacement exams administered by NRC over the last three calendar years are as follows:

1983 75% pass rate for R0's No SR0s exams given 1984 86% pass rate for R0's 46% pass rate for SR0's 1985 100% pass rate for R0's 100% pass rate for SR0's Cooper Nuclear Power station is presently anticipating training accreditation by the Institute of Nuclear Power Operations (INPO) to be completed in August 198 The review of fonnal licensee training on the use of Emergency Operating Procedures (EOPs) was reported as in progress in NRC Report 50-298/86-0 The review was completed during this reporting perio No violations or deviations were identified in this are . 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 me . Technical Specification requirements were observe . Plant operations were conducted using approved procedure . Plant logs and records were complete, accurate, and indicative of actual system conditions and configuration . System pumps, valves, control switches, and power supply breakers were properly aligne .

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. Licensee systems lineup procedures / checklists, plant drawings, and ds-built Configurations were in agreemen . Instrumentation was accurately displaying process variables and protection system status to be within permissible operational limits for operatio . Plant equipment that was discovered to be inoperable or was removed from service for maintenance was properly identified, redundant equipment was verified to be operable, and applicable limiting conditions for operation were identified and maintaine . Equipment safety clearance records 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 manne . Plant equipment conditions such as cleanliness, leakage, lubrication, and cooling water were controlled and adequately maintaine . Areas of the plant were clean, unobstructed, and free of fire hazard Fire suppression systems and emergency equipment were maintained in a condition of readiness. It was noted that several plastic seals were missing from fire plug indicators. Corrective action was taken by the licensee in a timely manne . Security measures and radiological controls were adequat The NRC inspectors perfonned a lineup verification of the following systems:

. "A" Core Spray

. "A" Residual Heat Removal

. Standby Liquid Control during verification of the line up of the standby liquid control system using the valve checklist Appendix "A" of Standby Liquid Control System Procedure 2.2.74, Revision 15, dated August 1,1985, it was noted that four valves which deal with pressure transmitters and indicators are not shown on as-built System Drawing '

Number 2045. Licensee representatives indicated that these valves were shown on instrument drawings. This is considered unresolved pending a review of instrument drawings (8610-01).

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 Specificatio No violations or deviations were identified in this are .

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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 servic During a technical review of CNS Procedure 0.26. " Surveillance Program,"

. Revision 0, and CNS Technical Specification, the SRI noted that the Technical Specifications do not include a listing or definition of surveillance test frequencies, e.g., daily, weekly, monthly, quarterly, semiannually, annually, and refueling. The NRC inspector found that the licensee had provided definitions in Procedure 0.26 which lists and defines surveillance test frequencies with the exception of " daily" and " refueling."

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 Specificatio No violations or deviations were identified in this are . Monthly Maintenance Observation The NRC inspectors observed preventive and corrective maintenance activities on portions of the following systems components:

No.1 Emergency Diesel Generator Switchgear and Control Cabinets No. 2 Emergency Diesel Generator Switchgear and Control Cabinets

"C" Fire Pump The observations were conducted to verify that:

. Limiting conditions for operation were me . Redundant equipment was operabl .

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. Equipment was adequately isolated and safety tagge . Appropriate administrative approvals were obtained prior to commencement to 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 The following clearance orders were independently verified by the SRI for proper placement / restoration of associated components:

86-223, "C" Fire Pump 86-228, No. 2 Diesel Generator 86-229, "A" Reactor Equipment Cooling (REC) Pump 86-231, "B" REC Pump 86-232, "C" REC Pump 86-233, "D" REC Pump 86-234, No. 2 Diesel Generator 86-237, No.1 Diesel Generator Those reviews and observations were conducted to verify that facility maintenance 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 are . Unresolved Item An unresolved item is one about which more information is needed to determine if it is_ a violation, a deviation, or acceptable. There was one unresolved item in this report:

Paragraph Item Description 6 8610-01 Review of instrument

"as built" drawings

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10. 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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