IR 05000331/2009002
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May 12, 2009
Mr. Richard Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT: DUANE ARNOLD ENERGY CENTER NRC INTEGRATED INSPECTION REPORT 05000331/2009002
Dear Mr. Anderson:
On March 31, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Duane Arnold Energy Center. The enclosed report documents the inspection results, which were discussed on April 2, 2009, with you and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, two NRC-identified and one self-revealed finding of very low safety significance were identified, two of which involved violations of NRC requirements.
However, because of the very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating these issues as non-cited violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy. Additionally, a licensee identified violation is listed in Section 4OA7 of this report. If you contest the subject or severity of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Duane Arnold Energy Center. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, and the NRC Resident Inspector at Duane Arnold Energy Center. The information you provide will be considered in accordance with Inspection Manual Chapter 0305. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's 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).
Sincerely,/RA/
Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Docket No. 50-331 License No. DPR-49
Enclosure:
Inspection Report 05000331/2009002
w/Attachment:
Supplemental Information cc w/encl: M. Nazar, Senior Vice President and Chief Nuclear Officer M. Ross, Managing Attorney A. Khanpour, Vice President, Nuclear Engineering D. Curtland, Plant Manager S. Catron, Manager, Regulatory Affairs M. Mashhadi, Senior Attorney T. Jones, Vice President, Nuclear Operations, Midwest Region P. Wells, Vice President, Nuclear Safety Assessment R. Hughes, Director, Licensing and Performance Improvement D. McGhee, Iowa Dept. of Public Health Chairman, Linn County, Board of Supervisors R. McCabe, Chairman, Regional Assistance Committee, DHS/FEMA Region VII M. Rasmusson, State Liaison Officer
SUMMARY OF FINDINGS
......................................................................................................... 1
REPORT DETAILS
..................................................................................................................... 4 Summary of Plant Status.........................................................................................................
REACTOR SAFETY
...................................................................................................... 4
1R04 Equipment Alignment
............................................................... 4
1R05 Fire Protection
......................................................................... 5
1R07 Annual Heat Sink Performance
................................................ 6
1R08 Inservice Inspection Activities
.................................................. 6
1R11 Licensed Operator Requalification Program
............................. 8
1R12 Maintenance Effectiveness
...................................................... 9
1R13 Maintenance Risk Assessments and Emergent Work Control
.. 9
1R15 Operability Evaluations
.......................................................... 10
1R18 Plant Modifications
................................................................. 18
1R19 Post-Maintenance Testing
..................................................... 19
1R20 Outage Activities
.................................................................... 20
1R22 Surveillance Testing
RADIATION SAFETY
.................................................................................................. 23 2OS1 Access Control to Radiologically Significant Areas (71121.01) ................ 23 2OS2 As-Low-As-Is-Reasonably-Achievable (ALARA) Planning And Controls (71121.02) ............................................................................................... 27 2PS3 Radiological Environmental Monitoring Program And Radioactive Material Control Program (71122.03)
OTHER ACTIVITIES
.................................................................................................... 32
4OA1 Performance Indicator Verification
.............................................. 32
4OA2 Identification and Resolution of Problems
................................... 35
4OA3 Follow-Up of Events and Notices of Enforcement Discretion
...... 36
4OA5 Other Activities......................................................................................... 39 4OA6
Management Meetings ............................................................................ 41 4OA7 Licensee-Identified Violations .................................................................. 41
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- R. Anderson, Site Vice President
- D. Curtland, Plant General Manager
- B. Eckes, NOS Manager
- S. Catron, Licensing Manager
- J. Cadogan, Engineering Director
- B. Kindred, Security Manager
- J. Morris, Training Manager
- C. Dieckmann, Operations Manager
- G. Rushworth, Assistant Operations Manager
- P. Giroir, Operations Support Manager
- R. Porter, Chemistry & Radiation Protection Manager
- M. Davis, Emergency Preparedness Manager
- M. Lingenfelter, Design Engineering Manager
- J. Swales, Design Engineering Supervisor
- K. Kleinheinz, Maintenance Manager
- D. Albrecht, Radwaste Supervisor
- N. McKenney, General Supervisor Radiation Protection
- D. Johnson, Radwaste Operator/Chem Tech, Radiation Environmental Technician
- C. Harberts, Refuel Floor Project Manager
- D. Barta, Licensing Nuclear Regulatory Commission
- K. Feintuck, Project Manager, NRR
- K. Riemer, Chief, Reactor Projects Branch 2
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened
- 05000331/2009002-01 URI An Internal Contamination Occurred while Cleaning RPV Studs and Washers on the Refuel Floor at Duane Arnold (Section 2OS2.3)
- 05000331/2009002-02 FIN Cooling Tower Riser Break Leads to Manual Reactor Scram (Section 4OA3.1)
- 05000331/2009002-03 NCV Failure to perform required actions for existing LCO conditions during in-vessel fuel movements (Section
1R15.1.b)
- 05000331/2009002-04 NCV Failure to Consider Design Basis Load in Evaluation for Continued Operation (1R15.2.b)
Attachment
Closed
- 05000331/FIN-2009002-02 FIN Cooling Tower Riser Break Leads to Manual Reactor Scram (Section 4OA3.1)
- 05000331/FIN-2009002-03 NCV Failure to perform required actions for existing LCO conditions during in-vessel fuel movements (Section
- 1R15.1.b)
- 05000331/LER-2009-002-00 LER Outdoor Liquid Radwaste Storage Tank Radioactive Concentration Limit Exceeded
- 05000331/FIN-2005002-02 URI Failure to Include the Analysis of Thermal Movements in Piping Modifications (1R15.2)
- 05000331/FIN-2009002-04 NCV Failure to Consider Design Basis Load in Evaluation for Continued Operation (1R15.2.b)
- Attachment
LIST OF DOCUMENTS REVIEWED
The following is a list of documents reviewed during the inspection.
- Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
- Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. Section 1R04
- LOOP-LOCA Test; Revision 0
- OI 730A3; Control Building Ventilation System Valve Lineup; Revision 7
- Section 1R05
- FHA-400; Fire Hazards Analysis; Revision 9
- AFP-08; Reactor Building Standby Gas Treatment System and MG Set Rooms; Revision 24
- AFP-17; Turbine Building Condenser Bay, Heater Bay, and Steam Tunnel; Revision 24
- AFP-18; Turbine Building North Turbine Building Ground Floor and Tube Pulling Area; Revision 28
- AFP-19; Turbine Building South Turbine Building Ground Floor; Revision 25
- AFP-20; Aux Boiler Room, Emergency Diesel Generator Rooms, and Generator Day Tank Rooms; Revision 29
- AFP-25; Control Building Cable Spreading Room; Revision 26
- CAP 063274; Scaffold Issues for 1G21 'B' SBDG [Standby Diesel Generator] room Fire Protection Impairment Request
- FPR-09-7037; Remove Existing Concrete Curbing on Both Sides of Door to 'B' EDG Room and Replace with Removable Steel Curbing Section 1R07 Heat Exchanger Thermal Performance and Trending Program; Revision 8 General Maintenance Procedure
- GMP-Mech-26; Heat Exchangers; Revision 10 CWO A66164; Re-repair the Pass Divider Plate on 'A' RHR Heat Exchanger, 1E201A
- PWO 1144176; Perform UT Examination of Heat Exchanger Shell - 1E201A
- PWO 1144177; Open, Inspect, and Clean Service Water Side of Heat Exchanger - 1E201A
- PWO 1144178; Perform Eddy Current Examination on Designated Tubes - 1E201A
- Section 1R08
- ACP 1211.5; Nondestructive Examination Procedure Magnetic Particle (Dry or wet Visible)
- MT-1; Revision 10
- Attachment
- ACP 1211.10; Nondestructive Examination Procedure Visual Examination of Component Supports
- VT-3; Revision 10
- Apparent Cause Evaluation (ACE)
- 001828; Description Error on
- NIS-2
- CAP 047392; Indication Found by Surface Examination
- CAP 063771; Indication Identified in
- RRH-F002A Weld
- CAP 050093; Trend Fabrication and Welding
- CA 045128; Proceduralize Filler Metal Verification
- CA 045592; Wrong Welding Procedure Used
- CA 045702; Schedule for Non-Overlayed
- CA 045834; Evaluate NDE for Underground Pipe
- CA 049173;
- UT 75% of Risk Informed Coverage Achieved Procedure Qualification Record;
- GMP 102-311-GS-PQR; dated July 24, 1987
- OTH 020420; STP for Visual Exam of Ground Above Buried Pipe Liquid Penetrant Examination Report
- PT-07-09; Pipe to Pipe Weld
- CSB-F004; dated February 16, 2007 Liquid Penetrant Examination Report
- SM-1-1; dated January 2, 1976 Procedure Qualification Record;
- WP-6; dated January 8, 1991 Radiographic Report and Film; Weld 6 N2G,
- RRG-F002A; dated November 17, 1978 Radiographic Report and Film; Weld 6 N2H,
- RRH-F002A; dated November 17, 1978
- Radiographic Report and Film; Weld 2 N2G
- RRG-F002A; dated November 1, 1978 Radiographic Report and Film; MO4423, welds W2, W3 and W5; dated February 8, 2009 Repair/Replacement Plan; MO4424; dated July 29, 2008 STP NS540004B; Visual Examination of Ground Area Above ASME Section XI Service Water Loop B Buried Piping; dated September 21, 2008
- Ultrasonic Examination Report
- FWA-J002; dated February 13, 2007 Ultrasonic Examination Report
- FP-PE-B31-P1P1-GTSM-001; dated January 9, 2006 Welding Performance Qualification; B. Scott; dated January 28, 2009 Welding Performance Qualification; G. Beer; dated January 28, 2009 Zetec OmniScanPA; Procedure for Encoded, Manually Driven, Phased Array Ultrasonic Examination of Dissimilar Metal Piping Welds; Revision D
- Section 1R11
- ACP 110.1; Conduct of Operations; Revision 22 Abnormal Operating Procedure (AOP) 264; Loss of Recirculation Pump(s); Revision 1
- OI 264; Reactor Recirculation System; Revision 105
- Section 1R12
- OI 442; Circulating Water System; Revisions 70 and 71
- CAP 063586; NCAQ - Circulating Water Pressure Transmitter Plugged During Circ Pipe Failure Event Attachment
- CAP 064965; NCAQ - Ineffective Corrective Actions Associated with 'B' Cooling Tower Failure
- CAP 064267; CAQ - Cooling Tower Replacement Design Error - Lack of Support for the Riser Piping Calculation 1-B-10; Cooling Tower Risers; Revision 0 Calculation
- CAL-M09-013; Mechanical Loads on Cooling Tower Risers; Revision 1
- CAP 063310; NCAQ- Circ Water Startup Challenge
- CAP 064961; NCAQ - Valve Found out of Position During Lineup
- ECP-1884; Repair/Replace 'B' West Riser
- WRC A84341; Identified transmitter as Erratic and Possible Plugged DAEC System Checklist/Health Report for Condensate Heat Removal System DAEC Maintenance Rule Program Module 0; Overview; Revision 3 DAEC Maintenance Rule Program Module 0 Attachment 3; Startup Systems Containing Components Performing Maintenance Rule Risk-Significant or Standby Function at DAEC; Revision 3f DAEC Performance Criteria Basis Document; On-site Distribution SUS 4.00, 5.00, 6.00, 7.00, 17.00, 57.00; Revision 7 DAEC Maintenance Rule System Goals for RED (a)(1) Systems; Revision 34 DAEC System Checklist/Health Report for SUS 4.00 On-Site Distribution 4KV System Monitoring and Reporting Tool System Report; dated March 16, 2009
- Section 1R13 Work Planning Guideline 1; Work Process Guideline; Revisions 26, 27, and 28 Work Planning Guideline 2; On-Line Risk Management Guideline; Revision 45 and 46
- WM-AA-1000; Work Activity Risk Management Process; Revision 1
- PI-AA-100-1002; Guideline for Failure Investigation Process; Revision 0
- CAP 062956; 'A' Recirc Motor Generator Scoop Tube Lock Issue ODMI Initiation Corrective Work Order (CWO) A80328; 'A' Recirculation Scoop Tube Locked Up due to 'High Deviation' on B31-K49A
- CAP 062892; NCAQ - Abnormal Annunciator Activation
- CAP 065411; Manual Turbine Trip while Starting Up
- CAP 065432; Plant Shutdown from Mode One Due to Turbine Bearing Abnormalities
- CAP 065486; Issues from Observation of Turbine Generator Bearing #9 Installation
- CAP 065489;
- PI 3106, Turbine Lube Oil Pressure, Low Out of Specification CWO A100499; Inspect and Repair or replace #9 Bearing
- CAP 065897; RHR Logic Surveillance Not Performed as Scheduled Today Attachment Surveillance Work Order S015225; Perform STP 3.3.5.1-37 - RHR Logic System Functional Test-Operating CWO A100499; Inspect and Repair or replace #9 Bearing Maintenance Risk Evaluations for Work Week 9903; Revision 0 and 1 DAEC On-line Schedule for Work Week 3 Maintenance Risk Evaluations for Work Week 9904; Revisions 0, 1, 2, and 3
- DAEC On-line Schedule for Work Week 4 Maintenance Risk Evaluations for Work Week 9912; Revisions 0 and 1 DAEC On-line Schedule for Work Week 12
- Section 1R15
- ACP 102.17; Pre/Post-Job Briefs and Infrequently Performed Tests and Evolutions; Revision 42
- EN-AA-203-1001; Operability Determinations / Functionality Assessments; Revision 1
- LI-AA-01; Regulatory Margin Corrective Action Strategy; Revision 1
- CAP 062744; CAQ - Deficiencies Noted by NRC in Several Immediate Operability Determinations STP 3.8.1-02; One Standby Diesel Generator Inoperable; Revision 3
- CAP 062919; TS LCO 3.8.1.b Required Action B.3 Exited Prematurely
- OTH 037267; Guidance on RHRSE/ESW Availability on Loss of Room Ventilation
- CAP 064489; CAQ - CDR Position Indication Logged Inoperative with Core Alterations in Progress
- ACE 001925; CAQ - CDR Position Indication Logged Inoperative with Core Alterations in Progress System Description 856.1; Reactor Manual Control and Rod Position Information Systems; Revision 5
- OI 856.3; Rod Position Information System; Revision 8 STP 3.9.1-01; Refueling Interlocks Channel Functional Testing; Revision 10
- Operations Electronic Log System Shift Log Entries; dated February 8, 2009 through February 17, 2009 CWO A75306; Troubleshoot and Repair/Replace Rod Position Indication Probe for Control Rod 14-23 CWO A81530; Troubleshoot and Repair/Replace Rod Position Indication Probe for Control Rod 22-19
- MO 1905
- CAP 065287; NCAQ - Insulation Fell Off of Piping Operability Recommendation (OPR)
- 000313; CAQ - Insulation Fell Off of Piping
- OPR 000396; CAQ - STP 3.4.2-01 Daily Jet Pump Operability with Recirc Pumps at Minimum Speed Attachment
- OPR 000397; CAQ - 'A' SBLC Pump 1P230A Leak
- OBD 000314; CAQ - 'A' SBLC Pump 1P230A Leak CA040021; Corrective Action for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated March 30, 2005 CA040134; Corrective Action for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated April 22, 2005 CA040203; Corrective Action for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated May 10, 2005 CA041828; Corrective Action for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated January 6, 2006
- CA042817; Corrective Action for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated April 14, 2006 CA050263; Corrective Action for CAP057980: CAQ - NRC Commitment Not Met in Past Operability Calculation for CA42817; dated July 22, 2008
- CAL-080-312; Calculation: 7RB Containment Atmosphere Control -
- HLE-023; Revision 2 CAP035317;
- HLE-023 Piping Calculations Don't Include Thermal Movement of the Drywell; dated March 18, 2005
- CAP039338; Two Supports on
- HLE-21/38 Require Modification Due to Drywell Thermal Movement; dated December 14, 2005 CAP057980; CAQ - NRC Commitment Not Met in Past Operability Calculation for CA42817; dated May 28, 2008 CE002404; Condition Evaluation for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated March 22, 2005 DAEC Letter
- NG-05-2178 to NRC; Subject:
- Additional Information Regarding Unresolved Item 500331/2005002-02; dated December 12, 2005 DAEC Letter
- NG-06-0305 to NRC; Subject:
- Withdrawal of
- NG-05-2178; dated April 3, 2006 DAEC Letter
- NG-06-0375 to NRC; Subject:
- Voluntary Licensee Event Report No. 2006-002-00;
dated June 1, 2006
- DGC-M-100; DAEC Engineering Design Guide:
- Stress Analysis and Support Design of Seismic Category I Piping Systems; Revision 7 Drawing M119AC-04511; Containment Atmosphere Control, Pipe Support, Mark No.
- HLE-23-H-11; Revision 3
- Drawing M119AC-04547; Containment Atmosphere Control, Pipe Support, Mark No.
- HLE-23-SR-47; Revision 3 Drawing M119AC-11853; Containment Atmosphere Control, Pipe Support, Mark No.
- HLE-23-SS-47; Revision 1 IE05-P108274-240; Operability Evaluation of Drywell Water Piping at Penetrations X-24A and
- X-24B; Revision 1 IE05-P108274-241; Operability Evaluation of Drywell Water Piping at Penetrations X-23A and X-23B; Revision 1 IE05-P106464-500; Evaluation of Instrument Piping from Penetration X-108A; Revision 0 IE05-P106464-520; Evaluation of Instrument Piping from Penetration X-108C; Revision 0 IE05-P108274-240; Operability Evaluation of Drywell Water Piping @ Penetrations X-24A and X-24B; Revision 1
- IE05-P108274-241; Operability Evaluation of Drywell Water Piping @ Penetrations X-23A and X-23B; Revision 1 IE05-P108274-600; Operability Evaluation of 3"-HEL-31 @ Penetration X48; Revision 1 IE05-P108274-610; Operability Evaluation of Containment Atmosphere Control Piping @ Penetration X25; Revision 1
- Attachment IE05-P108274-610; Operability Evaluation of Containment Atmosphere Control Piping @ Penetration X25; Revision 2 IE05-P108274-620; Operability Evaluation of Instrument Piping @ Penetration X-108C; Revision 1 IE05-P108274-630; Operability Evaluation of Instrument Piping @ Penetration X46E; Revision 1 IE05-P108274-640; Operability Evaluation of Instrument Piping @ Penetration X40D; Revision 1
- LER 2006-002-00; Voluntary Licensee Event Report: Drywell Penetrations Calculations Do Not Account for Thermal Movement; dated June 1, 2006 OBD000246; Operable But Degraded Determination for CAP035317:
- HLE-023 Piping Calculations Don't Include Thermal Movements of the Drywell; dated March 22, 2005 OPR000308; Operability Recommendation: Containment Atmosphere Control System Piping; Revision 0 OPR000313; Operability Recommendation: Well Water Piping from Drywell HVAC (HLE034) Pressure Boundary; Revision 0 OPR000314; Operability Recommendation: RBCCW from Drywell (HLE029) Pressure Boundary; Revision 0 OPR000315 Operability Recommendation: RBCCW to Drywell (HLE028) Pressure Boundary; Revision 0
- OPR000316; Operability Recommendation: Nitrogen Piping to Drywell (HLE021) Pressure Boundary; Revision 0 OPR000318; Operability Recommendation: Well Water Piping to Drywell HVAC (HLE032) Pressure Boundary; Revision 0 Reedy Engineering, Inc. Position Paper; Scope: Identification of ASME Code Requirements for Evaluating Operability of Piping Systems Affected by Anchor Movements Caused by Design Conditions of Containment Vessel; dated June 21, 2005
- Section 1R18 Modification Work Order
- 1146469; Installation of
- ECP-1865 "Changes to the Air Supply for the Refueling Platform 1S081"
- ECP-1865; Changes to the Air Supply for the Refueling Platform 1S081 5059SCRN
- 030620; DAEC 10
- CFR 50.59 Screening for
- ECP-1865 Engineering Fleet Procedure
- FP-E-MOD-04; Design Inputs; Revision 3 Engineering Fleet Procedure
- FP-E-MOD-06; Design Description; Revision 3
- Engineering Fleet Procedure
- FP-E-MOD-08; Engineering Change Notices; Revision 2
- CAP 062738; Installation of Instrument Air to the Refuel Platform Deficiencies Engineering Change Notice
- CAP 063796; Indication Report
- INR-IVVI-09-03 Feedwater Sparger at 315 degrees
- RFO 21
- WM-AA-1000-F02; Data Sheet 2-Site level High Risk Integrated Review; Revision 0; Activity Risk Review to Replace Pin Keeper on the 315 degrees Feedwater Sparger
- OBD 000258; CAQ - Calculation
- CAL-E02-003 Shows SBDG Voltage Dips less than UFSAR/RG 1.9 Requirements (RFO 21)
- CAP 063830;
- ECP 1748 did not Identify need for SBDG Emergency Shutdown
- CAP 063870; Construction Acceptance Testing Issues related to
- ECP 1748
- LOOP-LOCA Testing
- ACP 1403.3; Modification Acceptance Test Control Program; Revision 10
- Attachment Drawing M015-006,1A.-WIP; Diesel Generator 1G21 Start Circuit A and B Governor Control and Excitation Control; Revision 7A Modification Acceptance Test (MAT) for
- ECP-1748; 1G21 - 'B' Emergency Diesel Generator Governor Replacement; Revision 1 CWO A80549; Received Control Power Failure Alarm and SBDG Failed to come up to Speed during LOOP Test
- PWO 1145733; Facilitate Tuning of New Governor
- PWO 1136141; 1G021/Governor Upgrade - Post Modification and Acceptance Testing
- PWO 1145735; 1C094 New Governor Controls and Wiring Installation MAT for
- ECP 1835B; 'B' SBDG Voltage Regulator Upgrade
- PWO 1145734; 1C094 Old Governor Controls and Wiring Removal
- PWO 1144550; Replace Voltage Regulator Card
- CAP 063881; Perform Aggregate Review -
- ECP 1748 - SBDG Governor Modification Activity Issues
- CAP 063870; Construction Acceptance Testing Issues Related to
- ECP 1748
- CAP 064015; 1G021 SBDG Governor Oil too High when Checked on the Operating Check List
- CAP 064034; 1G21 Tuning Delayed Due to Missing Alarm Card
- CAP 063654; 1G021 Governor Modification Wrong Wire
- CAP 063830;
- ECP-1748 did not identify need for SBDG Emergency Shutdown Switch Cable
- CAP 063704; Significant Delays to SBDG Modification Installation due to Insufficient Human Performance Tool use
- CAP 063786; 1G021 Wiring for Hydraulic Governor
- CAP 063803; Lack of Ownership and Point of Contact for
- ECP-1748 SBDG Governor Modification
- Section 1R19
- CAP 063692; Refuel Bridge Main Hoist Raise - Joystick Problem
- CAP 063738; North / South Refueling Bridge Joystick
- STP 3.9.101; Refueling Interlocks Channel Functional Testing; Revision 11 STP NS810001; Refueling Platform Inspection; Revision 23
- PWO 1148592; Perform Repairs to the Refueling Platform Indicating and Control Devices (Load Cell, Z-Positioner, Joystick, etc.) STP 3.8.1-07B; 'B' LOOP/LOCA Test
- OI 324; Standby Diesel Generator System; Revision 90 CWO A93689; Set-up New DRU [Digital Reference Unit] and Replace the DRU
- CAP 064626; Main Steam Isolation Valve CV4413 Testing
- PWO 1148609; MSIV Inspection and Overhaul STP 3.6.1.1-04; Containment Isolation Valve Leak Tightness Test-Type C Penetrations-Main Steam System; Revision 18
- HCU 34-15 Vent Dragon Valve Broken in Mid-Position Attachment CWO A80812; Establish Freeze Seal and Replace the 1" Dragon Valve Internals or Replace Valve as Required General Maintenance Procedure
- GMP-Mech-03; Pipe Freeze Seals; Revision 20 50023,2008C-30; CRD Friction Testing; Revision 0 CWO A100499; Inspect and Repair or Replace Turbine Generator #9 Bearing, as Required Surveillance Work Order
- 013275; Perform STP NS930003-Main Turbine Overspeed System Tests STP NS930003; Main Turbine Overspeed Trip System Tests; Revision 11 CWO A82110; Perform TIFs for Troubleshooting: Replace FY4450F
- PWO 1139809; Calibrate FY4450E
- Section 1R20 Outage Management Guidelines-7; Outage Risk Management Guidelines; Revision 17;
- RFO 21 Outage Risk Plan Integrated Plant Operating Instruction (IPOI) 4 Attachment 1; Operations Manager/Reactor Engineer Recommendations for Shutdown; Revision 92 Shift Orders dated January 29, 2009 Reactivity Management Plan: Plant Shutdown; February 1, 2009
- IPOI 5; Shutdown; Revisions 93, 94, and 95 IPOI 8; Outage and Refueling Operations; Revision 56 IPOI 8 Attachment 3; Time-to-Boil Calculation; Revision 56 IPOI 8 Attachment 5; Daily Risk Assessment Checklists; Revision 56
- Refueling Procedure 403; Performance of Fuel Handling Activities; Revision 32
- ACP 1410.5; Clearance Program; Revision 96 IPOI 3; Power Operations (35% to 100% Rated Power); Revision 102 IPOI 7; Special Operations; Revision 107 IPOI 7; Special Operations; Attachment 2, Primary Containment Closeout; Revision 107
- IPOI 7; Special Operations; Attachment 1, Primary Containment Entry; Revision 107 IPOI 2; Startup; Revision 110 5059SCRN
- 034303; DAEC 10
- CFR 50.59 Screening for Core Modification Package 21 (ECP-1873)
- CAP 064640;
- RFO 21 Core Verification Successful with Two Minor Issues
- ACP 103.1; Nuclear Fuel and Core Design Control Program; Revision 30 STP 3.1.4-01; Scram Insertion Time Testing; Revision 17 STP 3.10.1-01; Non Nuclear Heat Class 1 System Leakage Pressure Test; Revision 31
- CAP 065122; NCAQ - STP 3.10.1-10 Hydro Difficulties IPTE Briefing Package for Reactor Startup 09-01; Startup from
- RFO 21; dated February 27, 2009
- ACP 102.17; Pre/Post-Job Briefs and Infrequently Performed Tests and Evolutions; Revision 42 Reactivity Management Plan: Plant Startup; March 3, 2009 Reactor Engineering Department Procedure 14; Hot-Notch and Estimated Critical Position; Revision 6 IPOI 1; Startup Checklist-Section 5.0 Startup Comments; Revision 123 Reactivity Management Plan: Downpower to take Generator Offline; March 5, 2009
- Reactivity Management Plan: Plant Startup; February 27, 2009
- NP-910; Plant Readiness for operations; Revision 8
- Attachment Section 1R22 STP 3.5.3-02; RCIC System Operability Test; Revision 25 STP NS500001; RCIC System Leakage Inspection Walkdown; Revision 4 STP 3.6.103; MSIV Trip/Closure Time Check; Revision 5
- CAP 064221; Question Concerning 'B' LOOP/LOCA Test Results
- CAP 064288; Extended 1A4 Loss during
- LOOP-LOCA Testing Delayed SBDG Testing
- CAP 064189;
- LOOP-LOCA Discrepancy STP 3.8.1-07B; 'B'
- LOOP-LOCA Test; Revision 26 STP 3.8.1-07A; 'A'
- LOOP-LOCA Test; Revision 26
- STP 3.6.1.1-13; Containment Isolation Valve Leak Tightness Test-Type C Penetrations-HPCI/RCIC Valves; Revision 4
- CV-2411 Failed Post-Maintenance LLRT
- CV-2410 Cannot be Fully Closed from Control Room STP 3.3.8.1-05B; 1A4 4KV Emergency Transformer Supply Undervoltage Calibration; Revision 0
- CAP 063486; Increased dose rates in the radwaste surge tank
- IT-088
- CAP 063094; Turbine Rollup Door Was Opened by Security Without Health Physics Present
- RWP 09-30009; All Refuel Outage Support Work; Task 01 -06; Special Maintenance; Revision 3 Duane Arnold Refueling Outage No. 21; Refuel Floor and Project Kick-Off Meeting; dated February 1, 2009
- Duane Arnold Refueling Outage No. 21; Radiological Performance Improvement Initiatives; dated February 13, 2009
- ACP 1411.27; Rules for Conduct of Work in Radiologically Controlled Areas; Revision 28 Duane Arnold Inter Office Memo; Intake Occurred on February 6, 2009; dated February 12, 2009
- Health Physics Procedure (HPP) 3104.01; Control Access to High Radiation Areas and Above; Revision 47
- HPP 3104.07; Diving Operation Within the Radiological Areas; Revision 17
- HPP 3104.06; Control of Radiography Activities; Revision 16
- ACP 1411.13; Control of Locked High Radiation Areas and Above; Revision 22
- RWP 09-30023; Diving in the Reactor Cavity; Revision No. 02
- RWP 09-50380; Underwater Diving Work and Setup: Desludging, Inspection and Repair of the Torus Coating in the High Radiation Area
- Section 2OS2
- CAP 063690; Person Got Nasal Contamination While Cleaning Reactor Pressure Vessel Bolts On Reactor Building 5
- CAP 058043; Use of Warehouse second Floor Would be Counterproductive to Rad Dose Goals
- RFO-21; Dose Versus Goal for the Project: Total Dose Attachment ALARA Job Planning Checklist; Diving in the Reactor Cavity to Repair the Feedwater Sparger-354 and Associated Support ALARA Job Planning Checklist; Diving in Torus water to Vacuum Sludge and Repair Surface Coating; Perform General Area Work in Torus Proper and Support in Torus Rooms; RWP No. 50380 and 50382; dated February 2, 2009
- ACP 1408.30; Control of Diving; Revision 3
- Section 2PS3
- LER 2009-002-00; DAEC Outdoor Liquid Radwaste Storage Tank Concentration Limit Exceeded; dated March 5, 2009
- CAP 065914; REMP Air Sampling Enhancement Opportunity - New Air Sampling Station Located toward SE; dated March 18, 2009
- CAP 058271;
- NCAQ-UFSAR Not Updated with Groundwater Changes Identified from
- NEI 07-07 Initiative; dated June 11, 2008
- OTH 029324; Evaluation and Implementation of a Five-Year Review of SSCs and SCM for GWPP; dated May 28, 2008
- OTH 028222; Expanded Buried Pipe Program to Include Tritium Containing Piping; dated April 24, 2008
- Memorandum; Memo Describing the Progress Made Towards the Implementation of Groundwater Protection Program at Duane Arnold Site Before August 31, 2008; dated August 29, 2008
- FPL- Quick Hit Self-Assessment Checklist Industry Groundwater Protection Initiative-NEI 07-07; dated August 20-22, 2008
- CE 006513;
- NCAQ-UFSAR Not Updated with Groundwater Changes Identified from
- NEI 07-07; dated June 30, 2008
- CE 006500; During A Nuclear Oversight Audit Of The Implementation Of The Ground Water Protection Program, Weakness Were Noted In The Formal Analysis Of System Structures And Components; dated May 2008
- OTH 029213; Develop Tech Staff Training on GWPP; This Training Supports Technical Staff Professional Development; dated May 21, 2008 23 Revisions of ODAM Changes Reviewed form January 2007 Through March 2009 ODAM for Gaseous and Liquid Effluents; dated September 4, 2008
- ESP-1.0; Radiological Environmental Monitoring Quality Control Program; Revision 11
- ESP-4.1.1.1; General Water Quality Sample Collection; Revision 12
- ESP-4.1.2; Terrestrial Sampling Procedure; Revision 6
- ESP-4.3.1.2; Ambient Radiation Sampling; Revision 17
- ESP-4.3.1.3.A; Surface water Sampling Procedure; Revision 19
- ESP-4.3.1.5; Ground water Sampling Procedure; Revision 21
- ESP-4.3.1.5A; Environmental Sampling Procedure of site Monitoring Wells; Revision 2
- ESP-4.3.1.8; Vegetation Sampling Procedure; Revision 20
- ESP-4.3.1.16; Special Radiological Environmental Sampling; Revision 9
- ESP-4.3.1.17; REMP Surveillance of Site Construction Activities; Revision 1
- ESP-4.4; Land Use Census Environmental Procedure; Revision 12
- ACP-1411.35 (Draft); The DAEC Groundwater Protection Program; Revision X
- ACP-1402.3; Regulatory Reporting Activities; Revision 34
- FORM
- HP-121; Health Physics Radioactive Spill Report Form; 2008 FPL Nuclear Fleet Ground Water Protection Program; Nuclear Program Description; revision No. 0; Effective Date May 5, 2008
- Attachment Final Report to FPL Energy from Environmental Inc, Midwest Laboratory; REMP for Duane Arnold energy Center; Reporting Period January - December, 2008; dated February 5, 2009 Environmental Inc, Midwest Laboratory; Appendix A; Inter-laboratory Comparison Program Results for 2008; dated February 2009
- Section 4OA1
- ACP 1402.4; NRC and WANO Performance Indicator Reporting; Revision 13 DAEC PI Report for Unplanned Scrams per 7000 Critical Hours for January 2008 through December 2008 DAEC PI Report for Unplanned Scrams with Complications for January 2008 through December 2008
- DAEC PI Report for Unplanned Power Changes per 7000 Critical Hours for January 2008 through December 2008
- NEI 99-02; Regulatory Assessment Performance Indicator Guideline; Revision 5 DAEC First Quarter 2008 PI Summary, April 9, 2008 DAEC Second Quarter 2008 PI Summary, July 14, 2008 DAEC Third Quarter 2008 PI Summary, October 9, 2008 DAEC Fourth Quarter 2008 PI Summary, January 14, 2009
- NRC PI Data Calculation, Review and Approval for Occupational Exposure Control Effectiveness and RETS/ODAM Radiological Effluent from the 1st Quarter 2008 through 4th Quarter 2008 Section 4OA2
- ACP 114.5; Action Request System; Revision 72
- PI-AA-204; Condition Identification and Screening Process; Revision 1
- PI-AA-105; Condition Evaluation and Corrective Action; Revision 0
- Section 4OA3 SpTP 213, "Increased Core Flow and Power Ascension Test to Greater Than 1880 MWth," Revision 0 SpTP 214, "Pressure Regulator Dynamic Tuning," Revision 0 Reactivity Management Plan: Rod/Flow Adjustments to Support Increased Core Flow; March 18, 2009
- WM-AA-1000-F01; Data Sheet 1-Work Activity Risk Evaluation; Revision 1; Increase Core Flow Portion of SpTP 213 "Increase Core Flow and Power Ascension Test to Greater Than 1880 MWth"
- WM-AA-1000-F02; Data Sheet 2-Site level High Risk Integrated Review; Revision 0; Increase Core Flow Portion of SpTP 213 "Increase Core Flow and Power Ascension Test to Greater Than 1880 MWth"
- ACP 102.17; Pre/Post-Job Briefs and Infrequently Performed Tests and Evolutions; Revision 42
- CAP 065972; Recirc Motor Data Collection Error during Increase Core Flow
- CAP 065978; Recirc Pump Speed Monitoring
- CAP 066055; Delay in Power Ascension Due to Procedure Issue
- NG-02-0187; Startup Test Report for Extended Power Uprate - Phase I; dated March 4, 2002
- NG-05-0516; Startup Test Report for Extended Power Uprate - Phase II; dated September 29, 2005
- ACP 110.1; Conduct of Operations; Revision 22
- RCE 1079; 'B' Cooling Tower West Riser Failure; Revision 0
- CAP 064965; Ineffective Corrective Actions Associated with the 'B' Cooling Tower Failure
- CAP 062934; NCAQ - MO4251 (Cooling Tower 1E-69B West Circulating Water Riser Isolation) Unreliability
- CAP 063310; NCAQ - Circulating Water Startup Challenge Event Notification 44821; Manual Reactor Scram due to Loss of Condenser Cooling
- CAP 049225;
- PWO 1136642 for
- CB-5560 not Completed as Scheduled in Week 16 IPOI 5; Reactor Scram; Revision 49
- Section 4OA5 SpTP 213, "Increased Core Flow and Power Ascension Test to Greater Than 1880 MWth," Revision 0 SpTP 214, "Pressure Regulator Dynamic Tuning," Revision 0
- NG-02-0187; Startup Test Report for Extended Power Uprate - Phase I; dated March 4, 2002
- NG-05-0516; Startup Test Report for Extended Power Uprate - Phase II; dated September 29, 2005
- Section 4OA7
- Attachment
LIST OF ACRONYMS
- USED [[]]
- HV [[]]
- LP [[]]
PI&R Problem Identification and Resolution PWO Preventative Work Order
Attachment
- UFS [[]]