IR 05000285/2002005
| ML030210555 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/21/2003 |
| From: | Clay Johnson NRC Region 4 |
| To: | Ridenoure R Omaha Public Power District |
| References | |
| IR-02-005 | |
| Download: ML030210555 (24) | |
Text
January 21, 2003
SUBJECT:
FORT CALHOUN STATION - NRC INTEGRATED INSPECTION REPORT 50-285/02-05
Dear Mr. Ridenoure:
On December 28, 2002, the NRC completed an inspection at your Fort Calhoun Station. The enclosed report documents the inspection findings which were discussed on December 20, 2002, with Mr. Gary Gates, Vice President, Nuclear, and other members of your staff.
This inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure, will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
/RA/
Claude E. Johnson Project Branch C Division of Reactor Projects Docket: 50-285 License: DPR-40
Omaha Public Power District-2-
Enclosure:
NRC Inspection Report 50-285/02-05
REGION IV==
Docket:
50-285 License:
DPR-40 Report No.:
50-285/02-05 Licensee:
Omaha Public Power District Facility:
Fort Calhoun Station Location:
Fort Calhoun Station FC-2-4 Adm.
P.O. Box 399, Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska Dates:
September 29 through December 28, 2002 Inspectors:
J. Kramer, Senior Resident Inspector L. Willoughby, Resident Inspector P. Elkmann, Emergency Preparedness Inspector M. Murphy, Senior Reactor Engineer, Examiner G. Pick, Senior Physical Security Inspector M. Shannon, Senior Health Physicist J. Taylor, Reactor Inspector G. Werner, Senior Reactor Engineer, Examiner Approved By:
Claude E. Johnson, Chief, Project Branch C
SUMMARY OF FINDINGS Fort Calhoun Station NRC Inspection Report 50-285/02-05 IR 0500285-02-05; Omaha Public Power District; 09/29-12/28/2002; Fort Calhoun Station, Integrated Resident and Regional Report The inspection was conducted by Resident and Regional office inspectors. There were no findings of significance identified during this inspection period. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG 1649, "Reactor Oversight Process," Revision 3, dated July 2000.
Report Details Summary of Plant Status The unit operated at approximately 100 percent power throughout the inspection period.
1.
REACTOR SAFETY Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness 1R01 Adverse Weather Protection (71111.01)
a.
Inspection Scope During December 2002, the inspectors reviewed Procedure OI-EW-1, Extreme Weather, Revision 7, for responding to extreme weather and Updated Safety Analysis Report, Section 9.8, Revision 11, Raw Water System, Work Order 00122755, for installing stop logs and verified system lineups. The inspectors ensured cold weather preparations were completed to protect the following systems:
Raw water system
Intake structure and condensate tank heating b.
Findings No findings of significance were identified.
1R04 Equipment Alignments (71111.04)
a.
Inspection Scope The inspectors performed partial walkdowns of the following trains of equipment during outages, operation, or testing of licensee redundant trains. The inspectors verified critical portions of the following equipment to identify any discrepancies between the existing alignment and alignments as determined by system piping and instrumentation drawings and plant procedures:
Diesel Generator 2 during an outage of Diesel Generator 1 on October 2, 2002
High Pressure Safety Injection Pumps SI-2B and SI-2C during an outage of Pump SI-2A on October 29, 2002
High pressure safety injection piping and valves associated with the safety injection tanks located in containment during tour on October 31, 2002
Diesel-Driven Fire Pump FP-1B during an outage of Motor-Driven Fire Pump FP-1A on December 10, 2002
-2-b.
Findings No findings of significance were identified.
1R05 Fire Protection (71111.05)
.1 Routine Area Inspection a.
Inspection Scope The inspectors performed routine fire inspection tours and reviewed relevant records for the following plant areas important to reactor safety:
Fire Area 1 - Safety Injection and Containment Spray Pump Area I
Fire Area 2 - Safety Injection and Containment Spray Pump Area II
Fire Area 6 - Zone 6.5 - Shutdown Heat Exchanger Area I
Fire Area 6 - Zone 6.6 - Shutdown Heat Exchanger Area II
Fire Area 13 - Mechanical penetration area
Fire Area 30 - Containment
Fire Area 33 - Component cooling heat exchanger area The inspectors observed the material condition of plant fire protection equipment, the control of transient combustibles, and the operational status of barriers. The inspectors compared in-plant observations with commitments in the licensees Updated Fire Hazards Analysis Report.
b.
Findings No findings of significance were identified.
.2 Fire Drill a.
Inspection Scope The inspectors observed a plant fire drill on December 3, 2002, to evaluate the readiness of licensee personnel to prevent and fight fires. The inspectors placed an inspection emphasis on proper donning of fire gear, use of a self-contained breathing apparatus, entry into the fire area, fire brigade leader directions, and simulated use of firefighting equipment and communications. The inspectors attended the evaluators critique following the drill scenario.
b.
Findings No findings of significance were identified.
-3-1R11 Licensed Operator Requalification (71111.11)
.1 Biennial Review of the Licensed Operator Requalification Program a.
Inspection Scope This inspection evaluated licensed operator performance in mitigating the consequences of events, since poor licensed operator performance results in increased risk through increased operator recovery rates and licensed personnel-induced common-cause error rates assumed in the licensees individual plant examinations.
This inspection effort of the licensed operator requalification program included the following major areas: (1) facility operating history; (2) requalification written examinations and operating tests; (3) licensee training feedback system; (4) licensee remedial training program; (5) conformance with operator license conditions; and (6) conformance with simulator requirements specified in 10 CFR 55.46.
Operator performance since the last requalification program evaluation was assessed to determine if performance deficiencies have been addressed through the requalification training program.
Examination security measures and procedures were evaluated for compliance with 10 CFR 55.49. The licensees sample plan for the written examinations was evaluated for compliance with 10 CFR 55.59 and NUREG-1021 as referenced in the facility requalification program procedures. In addition, the inspectors: (1) reviewed the number of applicants and pass/fail results of the written examinations, individual operating tests, and simulator operating tests; (2) interviewed personnel regarding the policies and practices for administering examinations; (3) observed the administration of two dynamic simulator scenarios to one requalification crew by facility evaluators; (4) observed four facility evaluators administer two in-plant job performance measures to four licensed operators; and (5) observed four facility evaluators administer three simulator job performance measures in the control room simulator in a dynamic mode to four licensed operators.
The inspectors reviewed the licensee's process for revising and maintaining an up-to-date licensed operator continuing training program, including the use of feedback from plant events and industry experience information.
The inspectors verified the adequacy and effectiveness of the remedial training conducted since the last requalification examinations and the training planned for the current examination cycle to ensure that identified licensed operator or crew performance weaknesses during training and plant operations were addressed.
Remedial training and examinations for examination failures were reviewed for compliance with facility procedures and responsiveness in addressing areas failed. The inspectors also reviewed the remediation documented for nine individuals and two crews, which involved six written examination failures and five simulator examination failure. These failures were from routine examinations given during the cycle not from the biennial examinations.
-4-Maintenance of license conditions was evaluated for compliance with 10 CFR 55.53 by review of facility records, procedures, and tracking systems for licensed operator training, qualification, and watchstanding.
The inspectors assessed the adequacy of the facility licensees simulation facility for use in operator licensing examinations. The inspectors also assessed the effectiveness of the facility licensees process for continued assurance of simulator fidelity in regard to identifying, reporting, correcting, and resolving simulator discrepancies via a corrective action program. The facility does not use the simulator for satisfying experience requirements at this time.
b.
Findings No findings of significance were identified.
.2 Quarterly Review of Licensed Operator Requalification Activities a.
Inspection Scope The inspectors reviewed licensed operator requalification training activities, including the licensed operators performance and the evaluators critique. The inspectors compared performance in the simulator on October 15, 2002, with performance observed in the control room during this inspection period.
The inspectors placed an inspection emphasis on high-risk licensed operator actions, operator activities associated with the emergency plan, and previous lessons-learned items. These items were evaluated to ensure that operator performance was consistent with protection of the reactor core during postulated accidents.
b.
Findings No findings of significance were identified.
1R12 Maintenance Rule Implementation (71111.12)
a.
Inspection Scope The inspectors reviewed the implementation of the requirements of the Maintenance Rule (10 CFR 50.65) to verify that the licensee had conducted appropriate evaluations of equipment functional failures, maintenance preventable functional failures, the unplanned capacity loss factor, and system unavailability. The inspectors reviewed root causes and corrective action determinations for equipment failures and reviewed performance goals for ensuring corrective action effectiveness. The inspectors discussed the evaluations with the licensee personnel. The following components were reviewed:
Raw Water Pump AC-10C breaker
Component Cooling Water Heat Exchanger Raw Water Inlet Valve HCV-2881A
-5-b.
Findings No findings of significance were identified.
1R13 Maintenance Risk Assessments and Emergent Work Evaluation (71111.13)
a.
Inspection Scope The inspectors reviewed the licensees risk assessments for equipment outages as a result of planned and emergent maintenance to evaluate the licensees effectiveness in assessing risk for the activities. The inspectors compared the licensees risk assessment and risk management activities against requirements of 10 CFR 50.65 (a)(4). The inspectors discussed the planned and emergent work activities with planning and maintenance personnel. The inspectors verified that plant personnel were aware of the appropriate licensee-established risk category, according to the risk assessment results and licensee program procedures. The inspectors reviewed the effectiveness of risk assessment and risk management for the following activities:
Inoperability of Diesel Generator 1 and the fast transfer of 4.16 kV Bus 1A3 on October 2, 2002
Continuing to operate Raw Water Pump AC-10B following failure of Surveillance Test OP-ST-RW-3011, AC-10B Raw Water Pump Quarterly Inservice Test, on October 10, 2002.
- Inoperability of Circulating Water Pump CW-1B and Raw Water Pumps AC-10B and AC-10C on October 21, 2002
Inoperability of Circulating Water Pump CW-1A, Raw Water Pump AC-10A, Motor-Driven Fire Pump FP-1A, and Steam-Driven Auxiliary Feedwater Pump FW-10 on December 4, 2002 b.
Findings No findings of significance were identified.
1R14 Personnel Performance During Nonroutine Plant Evolutions (71111.14)
.1 Failure of Feedwater Recirculation Valve a.
Inspection Scope The inspectors reviewed operator response when Feedwater Pump FW-4A Recirculation Valve FCV-1151A failed open on October 21, 2002. The inspectors discussed the event with licensed operators and Operations management. The inspectors reviewed the steam generator level strip-charts in the control room and Condition Report 200203647 that documented the event.
-6-b.
Findings No findings of significance were identified.
.2 Water Line Break a.
Inspection Scope The inspectors reviewed operator response to the potable water/fire protection water line break on October 23, 2002. The inspectors discussed the operator response to the event and water conservation actions with plant management. The inspectors observed the area containing the damaged section of the water line. The inspectors reviewed Condition Reports 220203687, 220203691, and 200203702 that documented the event.
b.
Findings No findings of significance were identified.
.3 4 kV Bus 1A3 Ground a.
Scope On June 10, 2002, the inspectors reviewed the licensees performance following the electrical grounding of Bus 1A3 (Condition Report 200202238). The inspectors initially responded to the event using Inspection Procedure 71111.14, "Personnel Performance Related to Non-Routine Plant Evolutions and Events." However, since the inspection period ended on June 29, 2002, and the licensees evaluation of this event was still in progress, the inspectors documented the results of their inspection in the next integrated inspection report (50-285/02-04) using Inspection Procedure 71111.15, Operability Evaluations.
b.
Findings No findings of significance was identified.
1R15 Operability Evaluations (71111.15)
a.
Inspection Scope The inspectors reviewed selected operability evaluations to verify that the evaluations provided adequate justification that the equipment could still meet its Technical Specification, Updated Safety Analysis Report, and design bases requirements. The inspectors also discussed the evaluations with cognizant licensee personnel. The inspectors reviewed the operability evaluations and cause assessments for the following:
Surveillance testing of Diesel Generator 2 with Raw Water Pump AC-10C considered inoperable
-7-
Placing incorrect oil in safety-related pumps, Condition Report 200203464 b.
Findings No findings of significance were identified.
1R16 Operator Workarounds (71111.16)
a.
Inspection Scope The inspectors reviewed operator workarounds to evaluate their cumulative effect on the operators ability to implement abnormal or emergency procedures. The inspection included a review of criteria and processes used for identifying and tracking deficiencies as operator workarounds. The review also focused on the length of time the identified workarounds had been in existence and efforts initiated to resolve them.
b.
Findings No findings of significance were identified.
1R19 Postmaintenance Testing (71111.19)
a.
Inspection Scope The inspectors observed and/or reviewed postmaintenance testing for the following activities to verify that the test procedures and activities adequately demonstrated system operability:
Work Order Package 00112219-01 for the replacement of Diesel Generator 1 starting Switches D1-63 and D1-74 on October 2, 2002
Work Order Package 00129976-01 for replacement of Control Switch HC-2852A for Raw Water Pump AC-10C on October 28, 2002
Work Order Package 00129974-01 for replacement of Raw Water Pump AC-10C breaker on October 28, 2002
Work Order Package 00104857-01 for the lube coupling, oil change, and oil sampling of High Pressure Safety Injection Pump SI-2A and Procedure OP-ST-SI-3021, Room 21 Safety Injection/Containment Spray Pumps and Valve Exercise Inservice Test, Revision 0, on October 29, 2002
Motor-Driven Fire Pump FP-1A pump replacement and Procedure SE-ST-FP-0002, Fire Protection System Motor-Driven Fire Pump Full Flow Test, Revision 16, on December 11, 2002 The inspectors determined that the effect of testing on the plant had been adequately addressed. It was also determined that the tests were adequate for the scope of the
-8-maintenance work performed and that the acceptance criteria were clear and consistent with design and licensing basis documents.
b.
Findings No findings of significance were identified.
1R22 Surveillance Testing (71111.22)
a.
Inspection Scope The inspectors observed and/or reviewed the performance and documentation for the following surveillance tests to verify that the structures, systems, and components were capable of performing their intended safety functions and to assess their operational readiness:
Procedure OP-ST-RW-3011, AC-10B Raw Water Pump Quarterly Inservice Test, Revision 23, on October 8, 2002
Procedure OP-ST-DG-0002, Diesel Generator 2 Check, Revision 37, performed on December 11, 2002
Procedure OP-ST-DG-0001, Diesel Generator 1 Check, Revision 36, performed on December 26, 2002 b.
Findings No findings of significance were identified.
1EP2 Alert Notification System Testing (71114.02)
a.
Inspection Scope The inspectors discussed with the licensee changes made in the installed systems and testing programs for offsite siren and tone alert radio systems between September 2000 and September 2002 to determine the adequacy of licensee methods for testing the alert and notification system in accordance with 10 CFR Part 50, Appendix E. The licensees siren testing program was compared with the guidance of NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, and Federal Emergency Management Agency document REP-10, Guide for the Evaluation of Alert and Notification Systems for Nuclear Power Plant. The inspectors also reviewed the notification system test procedures listed below.
- EPDM-2, Emergency Preparedness Test Program, Revision 13
EPT-01, Alert Notification System Silent Test, Revision 11
EPT-02, Alert Notification System Growl Test, Revision 16
EPT-03, Alert Notification System Complete Cycle Test, Revision 9
-9-b.
Findings No findings of significance were identified.
1EP3 Emergency Response Organization Augmentation Testing (71114.03)
a.
Inspection Scope The inspectors discussed with the licensee changes made in the installed systems and testing programs for automatic phone dialing systems and paging systems between September 2000 and September 2002 to determine the licensees ability to staff emergency response facilities in accordance with the licensee emergency plan and the requirements of 10 CFR Part 50, Appendix E. The inspectors also reviewed EPDM-9, Use, Maintenance and Testing of the Interactive Notification System, Revision 2, and EPT-34, Perform Augmentation or Notification Drills, Revision 22.
b.
Findings No findings of significance were identified.
1EP4 Emergency Action Level and Emergency Plan Changes (71114.04)
a.
Inspection Scope The inspectors completed an on-site review of Revision 11 to Section G and Revision 30 to Section H of the Fort Calhoun Station Emergency Plan, submitted August 8, 2002, against their previous revisions and against 10 CFR 50.54(q) to determine if the revisions decreased the effectiveness of the plan. The inspectors also reviewed EPDM-6, Review of Procedure Changes, Revision 3, and EPT-16, Review and Update RERP/ EPIPS/OSC-1 EALS, Revision 7.
b.
Findings No findings of significance were identified.
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies (71114.05)
a.
Inspection Scope The inspectors reviewed the following documents related to the licensees corrective action program to determine the licensees ability to identify and correct problems in accordance with the requirements of 10 CFR 50.47(b)(14) and 10 CFR Part 50, Appendix E.
- Standing Order SO-R-2, Condition Reporting and Corrective Actions, Revision 20
-10-
EPT-56, Real Event Reports, Revision 0
Summary Report, Notification of Unusual Event, February 15, 2002
Quality Assurance Audit Report 4, 02-QUA-029, Emergency Response Plan and Implementing Procedure, March 2002
Quality Assurance Audit Report 4, 01-QUA-030, Emergency Response Plan and Implementing Procedure, March 2001
EP 00-252, 2000 Emergency Preparedness Self Assessment Report, Revision 1, November 2000
Emergency Preparedness Assessment, Site Report, United Services Alliance, September 2002
Station drill and exercise critiques dated January, May, July, and October 2001 and January, March, and July 2002
Summaries of 160 corrective actions assigned to the emergency preparedness department between September 2000 and August 2002 b.
Findings No findings of significance were identified.
1EP6 Drill Observation (71114.06)
a.
Inspection Scope On November 5, 2002, the inspectors observed aspects of the emergency preparedness drill from the simulator and the emergency operations facility. The purpose of the observations was to evaluate operator performance, licensee event classification, notification of state and local authorities, and the adequacy of protective action recommendations. The inspectors attended the licensees postdrill critiques and discussed observations with licensee management.
b.
Findings No findings of significance were identified.
-11-2.
RADIATION SAFETY Cornerstone: Occupational Radiation Safety 2OS2 ALARA Planning and Controls (71121.02)
a.
Inspection Scope The inspectors interviewed radiation workers and radiation protection personnel throughout the radiologically controlled area and conducted independent radiation surveys of selected work areas. No work was performed in high exposure or high radiation areas during this inspection. Therefore, this aspect of the above procedure could not be evaluated. The following items were reviewed and compared with regulatory requirements to assess the licensees program to maintain occupational exposure as low as is reasonably achievable (ALARA):
ALARA program procedures
Quality Assurance Audit 58
Radiation Protection Department 2002 Self-Assessment
Processes used to estimate and track exposures
Plant collective exposure history for the past 3 years, current exposure trends, and 3-year rolling average dose information
Four ALARA planning packages and associated radiation work permits for work activities that resulted in some of the highest personnel collective exposures during the 2002 Refueling Outage (ALARA Package 02-02, Minor Maintenance, ALARA Package 02-03, Snubber Work, ALARA Package 02-13, Transfer Tube Flange Work, and ALARA Package 02-28, Air Operated Valve Maintenance Work)
Hot spot reduction and temporary shielding programs
Radiological work planning
A summary of ALARA and radiological worker performance related corrective action reports written since April 1, 2002 (eight condition reports were reviewed in detail: 200200974, 200201120, 200201541, 200201909, 200202175, 200202250, 200202337, and 200202954)
Declared pregnant worker dose monitoring controls b.
Findings No findings of significance were identified.
-12-4.
OTHER ACTIVITIES 4OA1 Performance Indicator Verification (71151)
.1 Drill and Exercise Performance a.
Inspection Scope The inspectors reviewed the following documents related to drill and exercise performance in order to verify the accuracy of the licensees reported performance indicator data:
EPDM-14, Emergency Preparedness Performance Indicator Program, Revision 4
EPIP OSC-1, Emergency Classification, Revision 35
EPIP EOF-6, Dose Assessment, Revision 32
EPIP EOF-7, Protective Action Guidelines, Revision 13
Drill schedules for Calendar Years 2001 and 2002
Drill scenarios and timelines
Drill packages, consisting of participant logs, notification forms, and dose assessment forms
Drill evaluation worksheets and records
Performance indicator summary sheets
Performance indicator reports for the fourth quarter of Calendar Year 2001 and for the first and second quarters of Calendar Year 2002 b.
Findings No findings of significance were identified.
.2 Emergency Response Organization Drill Participation a.
Inspection Scope The inspectors reviewed the following records related to emergency response organization participation in order to verify the accuracy of the licensees reported data:
-13-
Emergency response organization rosters for the fourth quarter of Calendar Year 2001 and for the first and second quarters of Calendar Year 2002
List of valid drills for emergency response participation credit
List of key emergency response organization positions
Drill participation summary records for 119 emergency responders
Detailed drill participation records for a sample of 8 emergency responders
Performance indicator summary sheets
Performance indicator reports for the fourth quarter of Calendar Year 2001 and for the first and second quarters of Calendar Year 2002 b.
Findings No findings of significance were identified.
.3 Alert and Notification System a.
Inspection Scope The inspectors reviewed a 100 percent sample of siren testing records for the fourth quarter of Calendar Year 2001 and for the first and second quarters of Calendar Year 2002 to verify the accuracy of data reported for this performance indicator.
b.
Findings No findings of significance were identified.
.4 Emergency ac Power System Unavailability and Residual Heat Removal System Unavailability a.
Inspection Scope The inspectors reviewed the licensees performance indicator data for the fourth quarter of 2001 and the first three quarters of 2002 to verify its accuracy and completeness.
The inspectors reviewed NEI 99-02, Regulatory Assessment Performance Indicator Guideline, and licensee operating logs. The inspectors discussed the status of the performance indicators and compilation of data with licensee personnel.
b.
Findings No findings of significance were identified.
-14-4OA2 Identification and Resolution of Problems (71152)
a.
Inspection Scope The inspectors reviewed the licensees followup to a Notification of Potential Defect per 10 CFR Part 21. The inspectors reviewed, K-Line Mechanism Failures to Charge and Close, notification made by ABB Inc. on May 6, 2002. The notification discussed the failures of circuit breakers to charge and close. The inspectors reviewed the licensees process outlined in NOD-QP-21, Operating Experience Review (OER) Program, to determine adherence to the process. The inspectors also reviewed the licensees evaluation of the notification.
b.
Findings No findings of significance were identified.
4OA3 Event Followup (71153)
Licensee Event Report Reviews a.
Inspection Scope The inspectors reviewed the following licensee event reports to determine the significance of the issues. The inspectors evaluated each issue to determine: (1) the risk significance of the issue using the guidance contained in Inspection Manual Chapter 0612, Power Reactor Inspection Reports; (2) whether the licensee placed the issue in the corrective action program; and (3) whether any enforcement would be necessary.
.1 (Closed) Licensee Event Report 50-285/02-001-00: Contraband Found in a Vehicle During Entrance Search to the Site Protected Area The inspectors reviewed this licensee event report and Condition Report 200103774 that documented the event. The inspectors concluded that the licensee had performed all appropriate actions. No findings of significance were identified. This licensee event report is closed.
.2 (Closed) Licensee Event Report 50-285/02-S01-00: Possible Error in Classification of SAFEGUARDS Material After discussing this possible classification error with personnel in the Office of Nuclear Security and Incident Response, the inspectors determined that the material in question was not and that no deficiency had actually occurred.
Consequently, the inspectors administratively closed this licensee event report.
-15-4OA6 Meetings Exit Meeting Summary The inspectors presented the inspection results to Mr. G. Gates, Vice President, Nuclear, and other members of licensee management at the conclusion of the emergency preparedness inspection on October 4, 2002. The licensee acknowledged the findings presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
The inspectors presented the inspection results to Mr. D. Bannister, Plant Manager, and other members of licensee management at the conclusion of the radiation safety inspection on October 11, 2002. The licensee acknowledged the findings presented.
The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
The inspectors presented the inspection results to Mr. G. Gates, Vice President, Nuclear, and other members of the licensee management at the conclusion of the residents inspection on December 20, 2002. The licensee acknowledged the findings presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
ATTACHMENT SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee D. Bannister, Plant Manager B. Blume, Manager, Planning and Scheduling G. Cavanaugh, Licensing Supervisor S. Coufal, Acting Supervisor, Radiation Protection P. Cronin, Manager, Shift Operations G. Gates, Vice President, Nuclear S. Gebers, Corporate Health Physicist J. Herman, Manager, Nuclear Licensing J. Mattice, Supervisor, Radiation Protection M. Puckett, Manager, Radiation Protection C. Simmons, Supervisor, Emergency Planning H. Sefick, Manager, Security and Emergency Planning K. Steele, Supervisor, Radiation Protection D. Weaver, Supervisor, Operations and Technical Training R. Westcott, Manager, Training ITEMS OPENED, CLOSED, AND DISCUSSED Closed During this Inspection 50-285/02-001-00 LER Contraband Found in a Vehicle During Entrance Search to the Site Protected Area (Section 4OA3.1)
50-285/02-S01-00 LER Possible Error in Classification of SAFEGUARDS INFORMATION Material (Section 4OA3.2)
LIST OF DOCUMENTS REVIEWED Procedures and Documents SO-O-1, Conduct of Operations, Revision 49 Licensed Operator Requalifications Training Program Master Plan, Revision14 EPIP-OSC-1, Emergency Classification, Revision 35 OPD-4-19, Reactivity Management, Revision 4 NPM-3.06, Management of New Core Designs and Operating Strategies, Revision 2
-2-PED-NEI-4, Interface Requirements for Reload Analysis Process, Revision 14 ANSI/ANS - 3.5 - 1985, Nuclear Power Plant Simulators for Use in Operator Training Desktop Guide for OPPD Fort Calhoun Plant Cycle Simulator Core Model Update, dated 4/19/02 Nuclear Training Desktop Guide Nuclear Operations Division Training Simulator Administrative Manual Memorandum, dated September 17, 2002, Cycle 21 Low Power Physics Testing Report Job Performance Measures Job Performance Measure, JPM-0305A, Place Battery Charger in Service, Revision 5 Job Performance Measure, JPM-0153, Emergency Boration from Outside the Control Room, Revision 8 Job Performance Measure, JPM-0019P, Loss of Component Cooling Water, Revision 2 Job Performance Measure, JPM-0119, Startup of Charging and Letdown, Revision 13 Job Performance Measure, JPM-0312, Hot Bus Transfer of 480 Volt Busses, Revision 9 Simulator Dynamic Scenarios Simulator Scenario, SSG: 84210a, UHE and Station Blackout (SBO), Revision 1 Simulator Scenario, SSG: 84202, SGTR, Revision 1 Miscellaneous Written requalification examinations for the week of September 23, 2002 Simulator Deficiency Reports for 2001 and 2002 Procedure Change Request, EC 25436, dated 8/24/00 Remedial Training for Cycle 2001 - 2002 Simulator Maintenance and Modifications 2001 - 2002 2002 Operations Performance Indicators Request for Training Forms 2001 - 2002
-3-Condition Reports 200200663 200200289 200202852 200202861 200203099 200202569 200103783 200202966 200206660 200200182 200103383