Text

August 9, 2010

Mr. Christopher Vice President NextEra Energy Duane Arnold, LLC 3277 DAEC Road Palo, IA 52324-9785

SUBJECT: DUANE ARNOLD ENERGY CENTER INTEGRATED INSPECTION REPORT 05000331/2010003

Dear Mr. Costanzo:

On June 30, 2010, 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 July 15, 2010, with Mr. K. Kleinheinz 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, the inspectors identified two findings of very low safety significance which involved violations of NRC requirements and one Severity Level IV violation. Because of their very low safety significance and since the issues were entered into your corrective action program, the NRC is treating the issues as non-cited violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy. Additionally, two licensee-identified violations are 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 cross-cutting aspect assigned to 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 the Duane Arnold Energy Center. . In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website 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 05000331/2010003

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServe Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-331 License No: DPR-49 Report No: 05000331/2010003 Licensee: NextEra Energy Duane Arnold, LLC Facility: Duane Arnold Energy Center Location: Palo, IA Dates: April 1 through June 30, 2010 Inspectors: R. Orlikowski, Senior Resident Inspector R. Murray, Resident Inspector R. Baker, Resident Inspector A. Scarbeary, Reactor Engineer P. Smagacz, Reactor Engineer M. Mitchell, Health Physicist Observers: None

Approved by: Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

........................................................................................................... 1

REPORT DETAILS

....................................................................................................................... 4Summary of Plant Status

REACTOR SAFETY

....................................................................................................... 41R01Adverse Weather Protection (71111.01) ........................................................... 41R04Equipment Alignment (71111.04) ...................................................................... 61R05Fire Protection (71111.05AQ) ............................................................................ 71R06Flood Protection Measures (71111.06) ............................................................. 81R11Licensed Operator Requalification Program (71111.11) ................................... 91R12Maintenance Effectiveness (71111.12) ........................................................... 101R13 Maintenance Risk Assessments and Emergent Work Control (71111.13) ...... 101R15Operability Evaluations (71111.15) .................................................................. 111R18Plant Modifications (71111.18) ........................................................................ 151R19Post-Maintenance Testing (71111.19) ............................................................. 181R20Outage Activities (71111.20) ........................................................................... 181R22Surveillance Testing (71111.22) ...................................................................... 191EP6Drill Evaluation (71114.06)

RADIATION SAFETY

................................................................................................... 212RS8Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation (71124.08)

OTHER ACTIVITIES

..................................................................................................... 254OA1Performance Indicator Verification (71151) ..................................................... 254OA2Identification and Resolution of Problems (71152) .......................................... 264OA3Follow-Up of Events and Notices of Enforcement Discretion (71153) ............. 284OA5Other Activities ................................................................................................. 314OA6Management Meetings .................................................................................... 314OA7Licensee-Identified Violations .......................................................................... 32

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

C. Costanzo, Site Vice President

D. Curtland, Plant General Manager

B. Eckes, NOS Manager

S. Catron, Licensing Manager

B. Murrell, Licensing Engineer Analyst

K. Kleinheinz, Engineering Director

B. Kindred, Security Manager

B. Simmons, Training Manager

G. Rushworth, Acting Operations Manager

T. Erger, Assistant Operations Manager

P. Giroir, Operations Support Manager

R. Porter, Chemistry & Radiation Protection Manager

M. Davis, Emergency Preparedness Manager

M. Lingenfelter, Design Engineering Manager

C. Kress, Maintenance Manager (Acting)

M. Heermann, Radwaste Shipper in Training

J. Karrich, ALARA Coordinator

R. Schlueter, ALARA Coordinator

W. Render, Instructor, DAEC Operator Training

L. Swenzkinski, Sr. Licensing Engineer

Nuclear Regulatory Commission

K. Feintuch, Project Manager, NRR

K. Riemer, Chief, Reactor Projects Branch 2

Attachment

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000331/2010003-01 NCV Failure to Follow the Procedures for Performing Operability Determinations (1R15)

05000331/2010003-02 NCV Failure to Adequately Define Requirements and Prescribe a Procedure Appropriate for Plant Conditions (1R18)

05000331/2010003-03 NCV Failure to Submit LER per 10 CFR 50.73(a)(2)(v)(A) and (D). (4OA3.3)

Closed

05000331/FIN-2010003-01 NCV Failure to Follow the Procedures for Performing Operability Determinations (1R15)

05000331/FIN-2010003-02 NCV Failure to Adequately Define Requirements and Prescribe a Procedure Appropriate for Plant Conditions (1R18)

05000331/FIN-2010003-03 NCV Failure to Submit LER per 10 CFR 50.73(a)(2)(v)(A) and (D). (4OA3.3)

Discussed

None

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 1R01

OP-AA-102-1002 (DAEC); Seasonal Readiness; Revision 2

NG-271K; Plant Return to Normal Operation Checklist; Revision 3

CAP 074921; NCAQ [Condition not Adverse to Quality] - Summer Readiness Period Items not completed

CAP 070674; CAQ [Condition Adverse to Quality] - INPO Identified - Switchyard Concrete Control Cable Troughs are Full of Water Abnormal Operating Procedure (AOP) 304; Grid Instability; Revision 10

Section 1R04 Operating Instruction (OI) 170A1; Standby Gas Treatment (SBGT) System Electrical Lineup; Revision 8

OI 170A2; "A" SBGT System Valve Lineup and Checklist; Revision 4

OI 170A4; "B" SBGT System Valve Lineup and Checklist; Revision 2

OI 170A6; SBGT System Control Panel Lineup; Revision 3

OI 324A1; SBDG 1G-31 System Electrical Lineup; Revision 2

OI 324A3; SBDG 1G-31 System Valve Lineup and Checklist; Revision 10

OI 324A7; SBDG 1G-31 System Control Panel Lineup; Revision 3

OI 324A10; SBDG Standby/Readiness Condition Checklist; Revision 11

OI 304.1A1; 4160V/480V Nonessential Electrical Distribution System Electrical Lineup;

Revision 6

OI 304.2A1; 4160V/480V Essential Electrical Distribution System Electrical Lineup; Revision 1

OI 304.1A3; 4160V/480V Nonessential Electrical Distribution system Startup Transformer Control Panel Lineup; Revision 3

OI 304.2A10; 4160V/480V Essential Electrical Distribution System Control Panel Lineup;

Revision 1

OI 317.1A2; 120 VAC Regulated AC Distribution 1Y11 and 1Y21 Electrical Lineup (In-service); Revision 11

OI 317.1A4; 120 VAC Regulated AC Distribution 1D15/1Y1A and 1D25/1Y2A Panel Lineup

(In-Service); Revision 1

OI 317.1A6; 120 VAC Regulated AC Distribution 1Y16 and 1Y26 Panel Lineup

(In-Service); Revision 1

OI 317.1A8; 120 VAC Regulated AC Distribution 1Y10 and 1Y20 Panel Lineup (In-Service); Revision 3

OI 357A4; 120 VAC Uninterruptible Power Supply System 1D45/1Y4 Panel Lineup

(In-Service); Revision 3

CAP 074326; Water Puddle on floor of 1A3 Switchgear Room Under Cable Trough on South Wall; dated April 6, 2010

CAP 074151; NCAQ - Update Walkdown Guidance to Include Water Intrusion Concerns; dated March 29, 2010

Attachment

CAP 074025; NCAQ - CAP on Water on the Floor in the 1A3 Switchgear was Closed without Evaluation; dated March 23, 2010

CAP 054681; NCAQ - CAP on Water on the Floor in the 1A3 Switchgear was Closed without Evaluation; dated March 30. 2010

CAP 073553; NCAQ - Vulnerabilities to Water Intrusion; dated March 2, 2010

CAP 068364; NCAQ - Water on floor in 1A3 Essential Switchgear Room; dated July 11, 2009

CAP 068274; NCAQ - Electrical Switchgear/MCC Water Intrusion Walkdown Results;

dated July 7, 2009

CAP 070228; CAQ - Startup Transformer Duct Leakage; dated October 6, 2009

CAP 070149; CAQ - Water Intrusion Causes Unexpected Alarm: Aux Trans to 1A1 Brkr 1A101 Trip; dated October 1, 2009

Corrective WO A99319; Water Dripping from Bottom of Non-Seg Bus Coming from 1X3 to 1A1

Switchgear Room

OI 454A2; 'A' ESW System Valve Lineup and Checklist; Revision 10

OI 324A4; SBDG 1G-21 System Valve Lineup and Checklist; Revision 13

ACP 1410.9; Locked Valve Program; Revision 7

Integrated Plant Operating Instruction (IPOI) 7; Special Operations; Revision 109

Section 1R05

ACP 1203.53; Fire Protection; Revision 14

AFP 09; Reactor Building Closed Cooling Water Heat Exchanger Area, Equipment Hatch Area, and Jungle Room El. 812'-0"; Revision 27

AFP 21; Turbine Building North Turbine Operating Floor; Revision 24

AFP 22; South Turbine Operating Floor, EL. 780'-0"; Revision 25

AFP 24; Control Building 1A4, 1A3 Essential Switchgear Rooms; Revision 28

AFP 07; Reactor Building Laydown Area, Corridor and Waste Tank Area and Spent Resin Tank Room elevation 786'-0"; Revision 30

AFP 26; Control Building Control Room Complex; Revision 32

AFP 27; Control Building Control Room HVAC Room; Revision 25 Section 1R06

CAP 074522; NCAQ - Lifting of 1MH109 & 2MH207 did not have a critical lift

AR 395197395197 Water Intrusion of 1MH109

Section 1R11 Evaluation Scenario Guide (ESG)

DEP-PI; Revision 0

ESG 2010C-055; Revision 0

ESG 133; Revision 0

ACP 110.1; Conduct of Operations; Revision 24 IPOI 5; Reactor Scram; Revision 53

AOP 901; Earthquake; Revision 3

Emergency Operating Procedure 1; [Reactor Pressure Vessel] Control; Revision 16

Emergency Operating Procedure 2; Primary Containment Control; Revision 15

DAEC Emergency Action Level Notification Form; NOTE 5; Revision 12 Emergency Plan Implementing Procedure (EPIP) 1.1; Determination of Emergency Action Levels; Revision 28

Emergency Action Level Matrix - Hot Modes; Revision 8

Attachment Section 1R12 DAEC Performance Criteria Basis Document: Control Building HVAC; Revision 7 System Overview Report for Control Building HVAC; Period 2010-1

WM-AA-1000; Work Activity Risk Management; Revision 6

ACP 109.3; Complex Troubleshooting Process; Revision 2

PI-AA-100-1002; Guideline for Failure Investigation Process; Revision 1 WO A98774; Remove and Inspect Oil Pump due to Copper Concentration in Oil system Corrective WO A97371; Replace 'A' Chiller Compressor with a Rebuilt Compressor Apparent Cause Evaluation (ACE)

001980; CAQ - 'A' Control Building Chiller 1VCH001A Trip

CAP 074880; CAQ - TREND - Multiple Failures of the 'A' Chiller Lube Oil Pump

ACE 002049; CAQ - 'A' Control Building Chiller Trip

CAP 074863; CAQ - 'A' Control Building Chiller Trip

CAP 075070; NCAQ - 1VCH001A, 'A' CBC is Potentially Damaged Equipment-Specific Maintenance Procedure

CKTBKR-G080-02; General Electric Company 4160 Volt Circuit Breaker (Magne Blast) Model

AM-4.16; Revision 35

WO 1116572; Reactor Recirculation MG Set 1G-201B

WO 1128255; Reactor Recirculation MG Set 1G-201B

WO 1144074; Reactor Recirculation MG Set 1G-201B

CAP 074793; CAQ - Closure of 1A204 When Racking Breaker Up

CAP 074877; CAQ - 1A104 Breaker Racked-In without Extra Precautions

OI 264; Reactor Recirculation System; Revision 116 DAEC Plant Level Performance Criteria Basis Document; Unplanned Capability Loss Factor; Revision 2

DAEC Unplanned Capability Loss Factor Data; August 1997 through February 2010

Section 1R13

OP-AA-102-1003 (DAEC); Guarded Equipment (DAEC Specific Information); Revision 7

WPG-2; On-Line Risk Management Guideline; Revision 36 IPOI 8; Outage and Refueling Operations; Revision 65 DAEC Planned Outage Risk Profile

OM-AA-101-1000; Shutdown Risk Management; Revision 0

OP-AA-102-1003; Guarded Equipment; Revision 0

OP-AA-102-1003 (DAEC); Guarded Equipment (DAEC Specific Information); Revision 1

OP-AA-104-1007; Online Aggregate Risk; Revision 0 DAEC On-line Schedule for Work Week 9020 Maintenance Risk Evaluations for Work Week 9020; Revisions 0, 1, and 2

DAEC On-line Schedule for Work Week 9021

Maintenance Risk Evaluations for Work Week 9021; Revisions 0, and 1

General Maintenance Procedure;

GMP-ELEC-20; Main Transformer Backfeed; Revision 10 Shift Logs for 24-27 May 2010 Work Week 9022 Preview Maintenance Risk Evaluations for Work Week 9022; Revisions 0, 1, 2, 3, and 4

Work Week 9024 Preview; Revision 0

Work Week 9024 Preview; Revision 1

Work Week 9024 Preview; Revision 2

Attachment DAEC On-line Schedule for Work Week 9024 DAEC On-line Schedule for Work Week 9026

Maintenance Risk Evaluations for Work Week 9026; Revisions 0

Section 1R15

EN-AA-203-1001; Operability Determinations/ Functionality Assessments; Revision 2

ACP 110.1; Conduct of Operations; Revision 24

OPR 000427; Well Water Leaking into drywell impact on Primary Containment Adverse Condition Monitoring and Contingency Plan; Increased Drywell Leakage;

Revisions 1, 2, 3

CAP 074069; NCAQ - Well water leaking into drywell impact on Primary Containment

CAP 074958; Possible Pipe Support Issue Identified

OPR 000431; Perform Prompt Operability Determination on Pipe Support Issue with 'B' Control Building Chiller Water Essential Loop

HBD-159

CAP 072404; NCAQ - MSL [Main Steam Line] Steam Leakage Detection Panels 1C193A-D

and 194A-D Switch Corrosion STP 3.3.6.1-05; Main Steam Line Tunnel High Temperature Channel Functional Test; Revision 7

CAP 074937; CAQ - Spurious Group 1 Isolation Signal

CAP 072477; CAQ - Unexpected Half Group 1 Isolation Signal

WO A94796; Determine if TIS4479 was the Cause of the Spurious Half Group 1 Isolation Documented in

CAP 0749367

CAP 059248; CAQ - Main Steam Line Tunnel Temperature Greater than Acceptance Criteria in

3.0.0-01

WO 1382725; QEV- 7602B Control Air Quick Exhaust Valve Leaking By

STP 3.6.4.3-05; Standby Gas Treatment Operation with Heaters on (Post Maintenance Only); Revision 4

OI 170; Standby Gas Treatment System; Revision 56 STP 3.7.9-03; CB/ SBGTS Instrument Air Compressors System Leakage and Capacity Test;

Revision 4

AR 393381393381 1K004 Duty Cycle is 100%

AR 393382393382 1K3 Duty Cycle is 73%

BECH-M176<2>; P&ID Reactor Building Ventilation System; Revision 21

BECH-M173; P&ID & Air Flow diagram Standby Filter Unit Control Building; Revision 56

AR 393732393732 HPCI Room Upper Level Temps Above Calc Assumptions Section 1R18

OPR 000427; Well Water Leaking into drywell impact on Primary Containment Adverse Condition Monitoring and Contingency Plan; Increased Drywell Leakage;

Revisions 1, 2, and 3

CAP 072511; CAQ - Increase in Unidentified Drywell Leakage Observed After Reactor Core Isolation Cooling STP

CAP 073599; NCAQ - Increase in Unidentified Drywell Leakage

CAP 073913; CAQ - TREND - Drywell Equipment Drain Sump Leakage Increasing

CAP 074440; CAQ - TREND - Increase in Torus Level

STP 3.0.0-01; Instrument Checks; Revision 106

DAEC 50.59 SCRN#1913; STP 3.0.0-01 - PWRs 19842/19826 and STP 3.4.4-01 -

PWR 19843 STP 3.4.4-01; Reclassification of Drywell Leakage; Revision 3

Attachment

CAP 075107;

AOP-915 Vulnerability with Starting ESW Pump 1P099B WO A104152; Emergency Service Water Pump 1P99B

Section 1R19 WO A101998; Replace Oil Pump 1P283A on A CB Chiller

CAP 074880; CAQ -TREND - Multiple Failures of the A Chiller Lube Oil Pump WO A102198; Replace SV4401 Due to Through Wall Valve Body Nitrogen Leakage General Maintenance Procedure;

GMP-ELEC-08; ESG Grayboot Connections; Section D;

Revision 14

STP 3.4.3-03; Manual Opening and Exercising of the ADS and LLS Relief Valves; Revision 8 STP 3.6.2.1-01; Suppression Pool Water Temperature Surveillance; Revision 5

CAP 074859; CAQ - A104176 Identified N2 Leak on PSV4401

ACP 114.9; Event Response Procedure; Revision 19

WO A98773; Compressor 1K032A Check Valve Inspect, Repair, Replace

WO A99479; Perform an Oil System Flush and Inspection Due to High Levels of Copper Found in Oil Sample

BECH-M169<3>; P&ID Control Building Chillers 1VCH001A and 1VCH001B; Revision 12 STP NS540003B; B Emergency Service Water Operability Test and Comprehensive Pump Test; Revision 6

STP 3.3.3.1-09 ESWB; B ESW Valve Position Indicator Verification-Operating; Revision 0

STP 3.3.3.2-07; Remote Shutdown Panel Functional Test for ESW RWS, 1V-AC-11, 1V-SF-21, and Pump Ammeters; Revision 5

WO 1382725; QEV- 7602B Control Air Quick Exhaust Valve Leaking By

STP 3.6.4.3-05; Standby Gas Treatment Operation with Heaters on (Post-Maintenance Only); Revision 4

OI 170; Standby Gas Treatment System; Revision 56

STP 3.7.9-03; CB/ SBGTS Instrument Air Compressors System Leakage and Capacity Test; Revision 4

AR 393381393381 1K004 Duty Cycle is 100%

AR 393382393382 1K3 Duty Cycle is 73%

BECH-M176<2>; P&ID Reactor Building Ventilation System; Revision 21

BECH-M173; P&ID & Air Flow diagram Standby Filter Unit Control Building; Revision 56 STP 3.8.7-01; Low Pressure Coolant Injection (LPCI) Swing Bus AC and DC Undervoltage Transfer Test; Revision 10

AR 394432394432 Unexpected Annunciator 1C08A C-8 Instrument AC 1Y11 Undervoltage

AR 394407394407 Time to Trip at Max Allowed During Swing Bus STP

WO 1148366 (1282866); Tie Bkr from MCC 1B34A/1B44A and 1B3

AR 394218394218 1B3401 Cal & Inspect Power Shield Test Failed

Section 1R20 Reactivity Management Plan for Planned Reactor Shutdown for Drywell Leakage; May 2010 Reactivity Management Plan for Reactor Startup from Planned Outage; May 2010

IPOI 2; Startup; Revision 118

ACP 102.17; Pre/Post-Job Briefs and Infrequently Performed Tests and Evolutions; Revision 43

IPOI 1; Startup Checklist; Revision 125 NextEra Energy Duane Arnold, Letter A-290b; Startup Readiness Review Meeting Outage Management Guideline 8; Outage Close-Out Guideline; Revision 8

CAP 074533; NCAQ - Plant Readiness for Operations Following 5/10 Planned Outage

DAEC Health Physics (HP) Survey 10-575; Drywell 757' Attachment DAEC HP Survey 10-592; Drywell below 826' DAEC HP Survey 10-581; Drywell below 821'

DAEC HP Survey 10-578; Drywell 805' DAEC HP Survey 10-566; Drywell 775' DAEC HP Survey 10-561; Drywell 742'

DAEC HP Survey 10-576; Drywell Under-Vessel Platform

CAP 074912; Drywell MAL [Material Accountability Log] discrepancies at closeout

IPOI 7 Attachment 2; Primary Containment Closeout; Revision 109

OI 149; Residual Heat Removal; Revision 114

CAP 074740; Initiated Manual Reactor Scram Due to Rising Turbine Vibrations;

CAP 074737; Received Main turbine High Vibration Alarm (1C07B-B2) Alarm During Shutdown

IPOI 8; Outage and Refueling Operations; Revision 65

CAP 074856; Issues Identified During the 4/29 Drywell Inspection

IPOI 5; Reactor Scram; Revision 53 IPOI 3; Power Operations (35% - 100% Rated Power); Revision 117 IPOI 7; Special Operations; Revision 109

CAP 074769; NCAQ - Foundation Anchorage for 1E009 Degraded

CAP 074863; A CB Chiller Risk Assessment for Mode 2

Section 1R22 STP 3.3.3.2-09A; Reactor Water Level and Pressure Instruments (Loops A and C) Calibration; Revision 2 STP 3.5.1-02B; B Low Pressure Coolant Injection System Operability Tests; Revision 4

STP NS490003B; B Residual Heat Removal System Leakage Inspection Walkdown; Revision 0

STP 3.8.1-04A; A Standby Diesel Generator Operability Test (Slow Start From Norm Start Air;

Revision 5

OI 324A9; SBDG Operating Checklist; Revision 10

OI 324A10; SBDG Standby/Readiness Condition Checklist; Revision 11 STP 3.3.6.1-09; Primary Containment Isolation, Groups 2 and 4, Logic System Functional Test;

Revision 12

WO 1362726; MA 4KV Emergency Bus Undervoltage Relay Calibration 'B'

STP 3.3.8.1-04B; 1A4 4KV Emergency Bus Undervoltage Relay Calibration; Revision 2 STP 3.4.6-01; Reactor Coolant Iodine Activity; Revision 6

Section 1EP6 Emergency Action Level-01; Emergency Action Level Matrix - Modes 1, 2, 3; Revision 8 Emergency Action Level-02; Emergency Action Level Matrix - Modes 4, 5; Revision 7 EPIP 1.2; Notifications; Revision 40

EPIP 6.1; Drill and Exercise Program; Revision 2

Section 2RS08 Shipment

RSR 09-13; Control Rod Drive Boxes; May 20, 2009 Shipment

RSR 09-29; Dry Active Waste; July 16, 2009

Shipment

RSR 09-30; Resin High Integrity Container; September 8, 2009

Shipment

RSR 09-31; Resin High Integrity Container; September 14, 2009

Shipment

RSR 10-03; Dry Active Waste; February 20, 2010

ACE 001977; Exclusive Use Vehicle Left Site Without the Required Release Survey, May 15, 2010

Attachment

AR 391373391373 Crane Control Room Door is Sticking; May 19, 2010

AR 391376391376 Faded Radioactive Material Tag on Mixed Waste Container; May 19, 2010

AR 391378391378 Compressed Gas Cylinders Not Stored Properly; May 19, 2010

AR 391547391547 Housekeeping Issues Identified During NRC Walkdown; May 20, 2010

AR 391548391548 Procedure Issues Found during NRC Audit of Radiation Protection and Radwaste Shipping; May 20, 2010

CAP 055031; It Appears That Procedures Do Not Fully Address 49

CFR 173.410;

January 25, 2008

CAP 057329; Shipping Containers Purchased From Non-QSL Supplier; July 15, 2008

CAP 059191; Materiel Condition Issues from Nuclear Oversight Walkdowns; August 6, 2008

CAP 060735; Condensate Phase Separator tank Line Plugged; October 3, 2008

CAP 061289; Observed Increases in Reactor Water Cleanup Resin Trap Differential Pressure;

October 24, 2008

CAP 061451; Criticality Monitoring During New Fuel Receipt; October 31, 2008

CAP 062148; Resin Transfer Line Plugged; December 5, 2008

CAP 062179; Area Radiation Monitor Alarm during Reactor Water Cleanup Backwash;

December 8, 2008

CAP 062370; Defective Bolt Closure Points In Outer Nuclear Fuel Box Lids; December 17, 2008

CAP 065797; Radiological Issues Identified during a Walkdown in the Low level Radwaste Building; March 17, 2009

CAP 069233; Exclusive Use Vehicle Left Site Without the Required Release Survey;

August 24, 2009

CAP 070305; Low Level Radwaste House Keeping Issue; October 8, 2009

071642; Unexpected Area radiation Monitor Alarm in Waste Collector Tank Room;

December 4, 2009

CAP 071722; Unexpected Area radiation Monitor Alarm in Waste Collector Tank Room; December 10, 2009

CAP 072851; High Radwaste Resin Inventory; February 17, 2010

CAP 074652; Discrepancy in Labeling; April 20, 2010

CAP 074976; High Integrity Container Cage Redesign; May 4, 2010 Health Physics Procedure (HPP) 3103.08; Container and Material Labeling; Revision 7

HPP 3107.02; Surveys for Shipment of Radioactive Material; Revision 9

HPP 3107.05; Release of Items from the Radiologically Controlled Area; revision 12

HPP 3111.24; Radiological Posting Associated With a Radwaste High Integrity Container Evolution; Revision 13

PDA08-007; Duane Arnold Energy Center Nuclear Assurance report: Radioactive Waste Control; March 3, 2008 PDA09-008; Duane Arnold Energy Center Nuclear Assurance report: Radioactive Waste Control; April 17, 2009

RCE 1085; Unsecured Locked high Radiation Area-High Integrity Container Cage Gate;

Revision 2 Radwaste Handling (RWH) Procedure 3401.7; Controls for Disposal of Irradiated Components; Revision 5

RWH 3404.1; General Requirements for Cask Handling; Revision 23

RWH 3404.2; Compliance for Radiolytic Gas Generation in Radwaste Containers/Casks;

Revision 6

RWH 3404.4; Cask Handling Requirement for 14-210L, 14-210H, and 14-215; Revision 15

RWH 3404.9; Cask Handling Requirements Chem-Nuclear Systems (CNS) 14-195H; Revision 0

RWH 3404.10; Cask Handling Requirements for

CNS 14-215H; Revision 0

RWH 3404.11; LWT Cask Operating Procedure; Revision 2

RWH 3405.4; Inspection Handling and Control of High Integrity Containers; Revision 21

Attachment

RWH 3405.6; Inspection, Handling and Control of Sealand Containers; Revision 3

RWH 3406.1; Waste Classification and Characterization; Revision 8

RWH 3406.6; Characterizing Radioactive Material for Transport; Revision 8

RWH 3406.7; Verification of License To receive Radioactive Material; Revision 4

RWH 3406.10; Placarding of Radioactive Material Loads; Revision 7

RWH 3406.11; Guidelines for Blocking and Bracing Radioactive Material Loads; Revision 6

RWH 3406.12; Documentation for Radioactive Material shipments; Revision 10

RWH 3409.2; Sampling Instruction and Analysis of Radwaste Streams; Revision 11

RWH 3410.1; Process Control Program; Revision 16

RWH 3411.1; Inventory and Control of Hazardous and Mixed Waste Containers; Revision 6

RWH 3413.4; Quarterly Inspection of Interim On-site Storage Vaults; Revision 1

RWH 3411.7; Marking and Labeling of Hazardous Waste Containers Prior to Shipment;

Revision 4

08-002R; Radiological Engineering Calculation - 10CFR61 Basis for Duane Arnold Energy Center Dry Active Waste; Revision 0 08-003R; Radiological Engineering Calculation - 10CFR61 Basis for Duane Arnold Energy Center Condensate Resin; Revision 0

Technical Basis Document: Surface Contaminate Object Classification and Characterization;

Revision 0 Updated Final Safety Analysis Report/Duane Arnold Energy Center, Section 11; Revision 14

Section 4OA1

ACP 1402.4; NRC and WANO Performance Indicator Reporting; Revision 14

LI-AA-204-1001; NRC Performance Indicator Guidelines; Revision 0

NRC PI Data Calculation, Review and Approval Report for RCS Activity; Report Quarter No. 2

Year 2009; dated July 10, 2009

NRC PI Data Calculation, Review and Approval Report for RCS Activity; Report Quarter No. 3 Year 2009; dated October 6, 2009 NRC PI Data Calculation, Review and Approval Report for RCS Activity; Report Quarter No. 4

Year 2009; dated January 13, 2010

NRC PI Data Calculation, Review and Approval Report for RCS Activity; Report Quarter No. 1

Year 2010; dated April 12, 2010 NRC PI Data Calculation, Review and Approval Report for RCS Leakage; Report Quarter No. 2 Year 2009; dated July 6, 2009

NRC PI Data Calculation, Review and Approval Report for RCS Leakage; Report Quarter No. 3

Year 2009; dated October 5, 2009

NRC PI Data Calculation, Review and Approval Report for RCS Leakage; Report Quarter No. 4

Year 2009; dated January 12, 2010 NRC PI Data Calculation, Review and Approval Report for RCS Leakage; Report Quarter No. 1 Year 2010; dated April 7, 2010

NEI 99-02; Regulatory Assessment Performance Indicator Guideline; Revision 6

DAEC First Quarter 2010 PI Summary; Submitted April 21, 2010

Section 4OA2

CAP 074808; CAQ - TREND - 6 Mispositioning Events Have Occurred Since the Beginning of 2010

CAL-M05-004; HPCI Emergency Room Cooler Heat Transfer Calculation; Revision 8

CAL-M06-007; Room Heat Up Analysis for DAEC During Station Blackout; Revision 1

Attachment

CAL-234-025; Post Design Basis LOCA HPCI Room Temperature After Loss of 1VAC-14A & B; Revision 1

CAL-VC2-001; Ventilating, Cooling, and Heating Criteria & Data; Revision 1

CAL-VC1-009; Preliminary Information for Space Cooling; Revision 0

QUAL-SC100; Environmental Service Conditions Analysis; Revision 9

QUAL-SC101; Environmental and Seismic Service Conditions; Revision 16

DBD-T23-001; Primary Containment System; Revision 4

CAP 032586; Closure of

CAP 028523 Without Specified Corrective Actions Being Completed

CAP 069435; NCAQ - Ambient Temperature in the Diesel Generators Rooms is Approximately 110F

ACE 001879; Apparent Cause Evaluation for APRM Upscale Lights; Revision 1

ACP 1410.12; Operator Burden Program; Revision 20

Operator Burden Issues with Resolution Information; dated April 19, 2010

CAP 074309; Well Water Pressure Manipulations to Limit DW Leakage Constitute an OWA

CAP 073012; Conduct a Common Cause Evaluation for Control Room Degraded Instruments

CAP 073001; Ops Burden/ TSA KPI Recovery Strategy Section 4OA3

CAP 074645; NCAQ - CB5960 Auto-Recloser Cycled Repeatedly onto Faulted DAEC 36kV line

CAP 074642; CAQ - Loss of 1XR1

CAP 074647; CAQ - Security Alert Declared Due to Power Loss. Reference SEL 10-032.

CAP 074737; Received Main turbine High Vibration Alarm (1C07B-B2) Alarm During Shutdown

CE 008175; Initiated Manual Reactor Scram Due to Rising Turbine Vibrations;

IPOI 4; Shutdown; Revision 102 IPOI 5; Reactor Scram; Revision 53 IPOI 5; Attachment 1; Scram Report; Revision 53

RCE 001090; SCAQ [Significant Condition Adverse to Quality] - Initiated Manual Rx Scram Due to Rising Turbine Vibrations

Section 4OA3: AR 392462392462

NRC Questions Regarding

LER 2010-002: SSFF

RCE 1087; Turbine Bypass Valves Failed Open; Revision 0

CAP 072125; SCAQ - Both Turbine Bypass Valves Failed Open

CAP 072527; SCAQ - Missed Tech Spec Actions during January Bypass Valve Event

CAP 062246; NCAQ - BV1 False Open Signal- Need to restore Reliability & Implement Bridge Strategy

CAP 072313; CAQ -

EOC-RPT MCPR Penalty Was Not Installed When Bypass Valves

Failed Open

DAEC

LER 2010-002-00; Condition Prohibited By Technical Specifications

AR 392462392462 NRC Questions Regarding

LER 2010-002: SSFF

RCE 1087; Turbine Bypass Valves Failed Open; Revision 0

CAP 062246; NCAQ - BV1 False Open Signal- Need to restore Reliability & Implement Bridge Strategy

CAP 072313; CAQ -

EOC-RPT MCPR Penalty Was Not Installed When Bypass Valves Failed Open

DAEC

LER 2010-002-00; Condition Prohibited By Technical Specifications

Section 4OA7

AR 389822389822 Incorporate

CAP 069233 into 49CFR Subpart H Requalification; October 21, 2009

Attachment

CAP 069233; Duane Arnold Energy Center Clock Reset; Failure to Survey Vehicle Prior to Release; August 24, 2009

RWH 3406.5; Exclusive Use Vehicle Inspection; Revision 7 DAEC Radwaste Department Instructions: Receiving and Shipping Radioactive Material Shipments; Revision 0

Attachment