Text

November 9, 2009

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

SUBJECT: DUANE ARNOLD ENERGY CENTER INTEGRATED INSPECTION REPORT 05000331/2009004

Dear Mr. Costanzo:

On September 30, 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 October 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 findings of very low safety significance were identified. Each finding involved a violation of NRC requirements. However, because of their very low safety significance, and because 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. 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 the Duane Arnold Energy Center. The information that 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 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 05000331/2009004

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-331 License No: DPR-49 Report No: 05000331/2009004 Licensee: FPL Energy Duane Arnold, LLC Facility: Duane Arnold Energy Center Location: Palo, IA Dates: July 1 through September 30, 2009 Inspectors: R. Orlikowski, Senior Resident Inspector R. Baker, Resident Inspector T. Go, Health Physicist L. Haeg, Resident Inspector, Monticello Nuclear Generating Plant B. Cushman, Resident Inspector, Quad Cities Nuclear Power Station R. Russell, Emergency Preparedness Inspector C. Scott, Reactor Engineer Observers: M. Audrain, Materials Engineer

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

SUMMARY OF FINDINGS

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

REPORT DETAILS

.......................................................................................................................3 Summary of Plant Status...........................................................................................................3

REACTOR SAFETY

.......................................................................................................3

1R01 Adverse Weather Protection

Main article: IP 71111.01

.....................................................3

1R04 Equipment Alignment

Main article: IP 71111.04

................................................................4

1R05 Fire Protection

Main article: IP 71111.05

...........................................................................5

1R06 Flooding

Main article: IP 71111.06

....................................................................................6

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

.............................7

1R12 Maintenance Effectiveness

Main article: IP 71111.12

.......................................................8

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

..8

1R15 Operability Evaluations

Main article: IP 71111.15

.............................................................9

1R18 Plant Modifications

Main article: IP 71111.18

..................................................................12

1R19 Post-Maintenance Testing

Main article: IP 71111.19

......................................................13

1R22 Surveillance Testing

Main article: IP 71111.22

................................................................13

1EP2 Alert and Notification System Evaluation

Main article: IP 71114.02

................................15

1EP3 Emergency Response Organization Augmentation Testing

Main article: IP 71114.03

...15

1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies

Main article: IP 71114.05

.................................................................................................16

1EP6 Drill Evaluation

Main article: IP 71114.06

........................................................................19

RADIATION SAFETY

...................................................................................................20 2PS2 Radioactive Material Processing and Transportation (71122.02)..............20

OTHER ACTIVITIES

.....................................................................................................23

4OA1 Performance Indicator Verification

Main article: IP 71151

...............................................23

4OA2 Identification and Resolution of Problems

Main article: IP 71152

....................................26 4OA5 Other Activities..........................................................................................30 4OA6 Management Meetings..............................................................................30

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

K. Kleinheinz, Engineering Director

B. Kindred, Security Manager

R. Minear, Training Manager

C. Dieckmann, Operations Manager

G. Rushworth, Assistant Operations Manager

R. Porter, Chemistry & Radiation Protection Manager

M. Davis, Emergency Preparedness Manager

M. Lingenfelter, Design Engineering Manager

J. Swales, Design Engineering Supervisor

G. Pry, Maintenance Manager

D. Albrecht, Radwaste Supervisor

R. Patrilla, Radwaste Instructor

M. Heerman, Radwaste Shipper in Training

N. McKenney, General Supervisor Radiation Protection

T. Zimmerman, EP Coordinator

J. Mac Intyre, EP/Scheduling Coordinator

Nuclear Regulatory Commission

K. Feintuck, Project Manager, NRR

K. Riemer, Chief, Reactor Projects Branch 2

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000331/2009004-01 NCV Failure to Perform an Immediate Operability Determination for the 'B' Standby Diesel Generator (1R15)

05000331/2009004-02 NCV Failure to Maintain EAL Scheme for River Low Level ((1EP5.b1)

05000331/2009004-03 URI Adequacy of the licensee's critique for the May 20, 2009, EP Drill (1EP5.b2)

Closed

05000331/FIN-2009004-01 NCV Failure to Perform an Immediate Operability Determination for the 'B' Standby Diesel Generator (1R15)

05000331/FIN-2009004-02 NCV Failure to Maintain EAL Scheme for River Low Level ((1EP5.b1)

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; Seasonal Readiness; Revision 0

OP-AA-102-1002 (DAEC); Seasonal Readiness; Revision 0

ENG-CS-233; Basis for Requirements in Procedure

SP 1039; Revision 0

CAP 068159; NCAQ [Condition Not Adverse to Quality] - Loose Poles at 'B' Well

Section 1R04 Operating Instruction (OI) 149A1; RHR System Electrical Lineup; Revision 3

OI 149A4; 'B' RHR System Valve Lineup and Checklist; Revision 4

OI 149A6; RHR System Control Panel Lineup; Revision 2

OI 410A1; RWS System Electrical Lineup; Revision 9

OI 410A2; 'A' RWS System Valve Lineup and Checklist; Revision 18

OI 710A1; Intake Structure HVAC System Electrical Lineup; Revision 3

OI 710A2; Intake Structure HVAC System Valve Lineup; Revision 2

CAP 068380; NCAQ - LCO [Limiting Condition for Operation] Paperwork Not Properly Filled Out

OI 151A1; Core Spray System Electrical Lineup; Revision 3

OI 151A2; 'A' Core Spray System Valve Lineup and Checklist; Revision 4

OI 151A4; 'B' Core Spray System Valve Lineup and Checklist; Revision 4

OI 151A6; Core Spray System Control Panel Lineup; Revision 2

CAP 061456; CAQ [Condition Adverse to Quality] - 'B' Core Spray Discharge Line Hi Pressure Unexpected Alarm

CAP 061497; CAQ - Unexpected Alarm 1C03C C-2, 'B' Side Core Spray Discharge Line Hi Pressure

CAP 062140; CAQ - Core Spray Valves V21-0073 and

MO-2135 Potential Seat Leakage

CAP 062661; CAQ -

CAP 47017 Closed Without Identifying Leaking Valves

CAP 065994; CAQ - 'B' Core Spray Discharge Header Pressure Rose Approximately 30 PSIG

in 18 Hours

CAP 066026; CAQ - 'B' Core Spray High Pressure Unexpected 1C03 (C-2) Annunciator

WO A80361; Check Valve May Be Leaking Back From Reactor During STP 3.5.101B WO A80362;

MO-2135 May Be Leaking Through Backwards Core Spray System Checklist/Health Report; 07/07/2009

OI 150A1; Reactor Core Isolation Cooling System Electrical Lineup; Revision 2

OI 150A4; Reactor Core Isolation Cooling System Control Panel Lineup; Revision 3

OI 150A2; Reactor Core Isolation Cooling System Valve Lineup and Checklist; Revision 12

BECH-M113; Piping and Instrument Drawing (P&ID) RHR Service Water and Emergency Service Water Systems; Revision 64

OI 454A4; 'B' ESW System Valve Lineup and Checklist; Revision 10

OI 454A6; ESW System Control Panel Lineup; Revision 2

Attachment Section 1R05 Administrative Control Procedure (ACP) 1412.2; Control of Combustibles; Revision 36

ACP 1412.3; Control of Ignition Sources; Revision 23

ACP 1412.4; Impairments to Fire Protection Systems; Revision 55

AFP 14; Turbine Building North Basement Reactor Feed Pump Area and Turbine Lube Oil Tank Area; Revision 30

AFP 16; Turbine Building Condensate Pump Area, Elevation 734'-0"; Revision 25

AFP 69; Yard Main Transformer 1X1; Revision 3

AFP 70; Yard Standby Transformer 1X4; Revision 4

AFP 71; Yard Startup Transformer 1X3; Revision 3

AFP 72; Yard Auxiliary Transformer 1X2; Revision 2

AFP 34; Radwaste Building Drum Filling, Storage, and Shipping, Elevation 757'-6"; Revision 25

AFP 36; Radwaste Building Precoat and Access Area - Elevation 786', Control Room and Heating, Ventilation, and Air Conditioning Equipment Room; Revision 25

AFP 03; Reactor Building HPCI, RCIC, and Radwaste Tank Rooms; Revision 26

AFP 35; Radwaste Treatment and Access Area, Elevation 773'-6"; Revision 24

AFP 13; Refueling Floor Elevation 855'-0"; Revision 25

FHA-400; Fire Hazards Analysis; Revision 9

Fire Plan - Volume 1, Program; Revision 56

Section 1R06 Maintenance

WO 1151250; Remove Asbestos Conduit Seals in Manholes 1MH109, 1MH110, 1MH111, 1MH112, & 1MH113

Maintenance

WO 1151251; Remove Asbestos Conduit Seals in Manholes 2MH207, 2MH208, 2MH209, 2MH210, & 2MH211

CAP 068682; CAQ - Missed Hourly Firewatch and FPLCO Entry During 1B9 Outage

CAP 068665; NCAQ - Standing Water in Manhole 2MH207

CAP 068541; NCAQ - Standing Water in Manhole 1MH109

CAP 068502; CAQ - Poor Planning/Design for

ECP 1855

CAP 068494; NCAQ - Intake Manhole Sump Pump Mod Installation Delayed

CAP 068498; CAQ - TS LCO 3.8.7 Condition D and 3.7.2 Condition A for

WO 1151250 Exited Prematurely

CAP 068976; Documentation of Water Levels in Manholes during NRC Inspections Duane Arnold Energy Center Individual Plant Examination, Section 3.3.6 'Internal Flooding Analysis', November 1992

CAP 069548; 'A' Core Spray took longer to drain than anticipated; 09/08/2009

CAP 052312; CAQ - Long-term drain blockage condition; 09/07/2007 WO A78787; Inspect and cleanout the floor drain MRD002 in Torus Bay 10.

Section 1R11 Audit 09-02 Evaluation Scenario Guide; Revision 0

ACP 110.1; Conduct of Operations; Revision 22

AOP 255.2; Power/Reactivity Abnormal Change; Revision 32

CAP 069168; NCAQ - Not Able to Perform

OI-304.1 Section 7.6 in Simulator Training Due to Mod ECP1748 Deficiency

CAP 069192; LOR Simulator Scenario Debrief Did Not Identify All Operator Performance Issues

LORT Simulator Scenario performed on September 15th, 2009

Attachment Section 1R12 DAEC Maintenance Rule Program Module 0; Overview; Revision 3 DAEC Performance Criteria Basis Document; HPCI System

SUS 52.00; Revision 3 Summary of DAEC Maintenance Rule System Goals for RED (a)(1) Systems; dated July 30, 2009

DAEC System Checklist/Health Report for

SUS 52.00 HPCI System

DAEC Performance Criteria Basis Document; RWS System SUS 9.00, 10.01, 10.02, 10.03;

Revision 3

STP NS100102B; B RWS and Screen Wash System Vibration Measurement and Operability Test; Revision 5

CAP 066713; CAQ - HPCI Suction from Torus Pipe Support

HBB-8-SR-3 Wall Plate Gap

CAP 066750; CAQ - HPCI Torus Suction Pipe Support

HBB-8-SR-3 Not in Accordance with Design

CAP 069028; 1F036B [River Water Intake Traveling Screen] Making Rubbing Noise and Jumps Once in a While

CAP 069089; 'B' RWS Pump Inoperable Due to Failed ASME Specifications

CAP 069090; 'B' Side RWS Screen Wash Didn't Initiate When Expected

CAP 069162; 'B' RWS Inoperable

CAP 069190; Results of 'B' RWS Pit Inspection

CAP 069202; Differential Pressure for RWS Pump 1P117B in ASME Alert Range NS100102B; 'B' RWS and Screen Wash System Vibration Measurement and Operability Test;

Revision 4

BECH-M129; RWS System Intake Structure; Revision 38

BECH-M146; Service Water System Pumphouse; Revision 82

CAP 067180; CAQ - CV1956A: The Internals Inspection Results Unsatisfactory Duane Arnold Energy Center System Overview Report of Control Building Heating, Ventilation, and Air Conditioning; Date July 30, 2009

CAP 068703; CAQ - CV1956A Failed to Open when A ESW Pump Started for Bromination

CAP 068808; CAQ - CV1956A, Indications of Stem Galling

CAP 068996; CV1956A Disc Binding

CAP 056820; NCAQ - 1P088B Discharge Flow was Indicating Low

CAP 062216; CAQ - 'A' ESW Pump Secured due to Inadequate System Flow

CAP 068952; ESW Pump Minimum Flow Required During Planned Maintenance on ESW

System Loads

CAP 069007; Inoperability of ESW not Considered in Work Order Planning for SBDG Fuse Replacement WO A95781; CV1956A Failed to Open, Plan Corrective WO to Blue Check Disc and Lap Seats as Required to achieve Proper Fit Up

CAP 067773; CAQ - Flowserve didn't Provide Adequate Controls over Sub-tier Supplier for

CV-1956A

CAP 067864; ORG / Challenge Board Actions for

ECP-1811 (CV-1956A/B)

CAP 067413; CAQ - Excess Air Pressure May Cause

CV-1956A to Stick Closed

BECH-M113; P&ID RHR Service Water and ESW Systems; Revision 64

BECH-M169<2>; Control Building Cooling Chilled Water System; Revision 17

BECH-M169<3>; Control Building Chillers 1VCH001A and 1VCH001B; Revision 12

Attachment Section 1R13 Work Planning Guideline 1; Work Process Guideline; Revisions 32 and 33 Work Planning Guideline 2; On-Line Risk Management Guideline; Revisions 52 and 53

WM-AA-1000; Work Activity Risk Management Process; Revisions 1 and 3 Maintenance Risk Evaluations for Work Week 9928; Revisions 0, 1, and 2

DAEC On-line Schedule for Work Week 28

Maintenance Risk Evaluations for Work Week 9931; Revisions 0, 1, 2, 3, 4, and 5

DAEC On-line Schedule for Work Week 31

Corrective WO A95563; Replace and Test Relay P110500-1, RCIC Div 1 Leak Detection Power Monitor Relay Maintenance Risk Evaluations for Work Week 9933; Revisions 0, 1, 2, and 3

DAEC On-line Schedule for Work Week 33

Maintenance Risk Evaluations for Work Week 9935; Revisions 0, 1, 2, 3, 4, and 5

DAEC On-line Schedule for Work Week 35

CAP 068265; CAQ - Annunciator 1C04B (C-4) RCIC Steam Leak Det Logic Power Failure Activated

CAP 068703; CAQ - CV1956A Failed to Open When 'A' ESW Pump Started for Bromination

CAP 067132; CAQ - CV1956A Failed to Open When 'A' ESW Pump Started for 'A' SBDG STP

3.8.1-04A

CAP 068815; CAQ - Thermography Anomaly in 1C118 (Diesel Generator 1G-21 Control Relay)

WO 1151790; Clean Fuse Holder and Replace Fuse

WO A94323; Remove Existing Fuse, Clean Fuse Block and Install Replacement Fuse

CAP 069268; 1D1 125 VDC Battery Was Not Guarded

CAP 069269; Wrong Gaskets Ordered for HPCI Rupture Disc Replacement

CAP 069301; Weld Rod Package Not Marked with Date and Time Prior to Opening

CAP 069317;

EOP-2 (Primary Containment Control) Entered During HPCI STP on High Torus Temp > 95F

NG-003F; Operation Decision Making Action Plan Working Form for

CV-1068 Stuck in the 50%

Open Position; Meeting Held September 24, 2009

WO A96351; Determine if Foreign Material is Preventing Movement of Valve by Attempting to Open DAEC On-line Schedule for Work Week 39

Maintenance Risk Evaluations for Work Week 9939; Revision 0

Maintenance Risk Evaluations for Work Week 9937; Revisions 0, 1, 2, and 3

CAP 069517; 'C' Well Piping Underground Leak.

Abnormal Operating Procedure (AOP) 408

Entered Abnormal Operating Procedure

408; Well Water System Abnormal Operations; Revision 26

OP-AA-104-1007; Online Aggregate Risk; Revision 0

Section 1R15 Operability Recommendation (OPR)

000402; Minor Bolting Issues Found During SFU Walk Down Required by CA [Corrective Action]

0052742

CAP 068030; CAQ - Two Flange Studs Appear to Be Loose on AV7322B

CA 0052742; CAQ - Two Flange Studs Appear to Be Loose on AV7322B

CAP 068263; Minor Bolting Issues Found During SFU Walk Down Required by

CA 0052742

OPR 000404; CAQ - Candle Fire While Running 1G-31

CAP 068652; CAQ - Candle Fire While Running 1G-31

CAP 068709; CAQ - Difficulty Closing 1A311

CAP 069217; Candle Fire on A SBDG

Attachment Corrective WO A95262; Check Tightness of Ring Catcher Inspection Port Bolting on Both Four Barrel Manifolds

OI 324; SBDG System; Revision 93

CAP 068394; HPCI Response Time Testing STP Does Not Recognize HPCI LCO Entry

CAP 068320; HPCI Response Time Testing Correction Factor Outside of Band

OPR 000403; HPCI Response Time Testing Correction Factor Outside of Band

STP NS520002; HPCI Response Time Correction Factor Verification; Revision 1

OPR 000405; Thermography Anomaly in 1C118 (Diesel Generator 1G21 Control Relay and Terminal Panel) Infrared Thermography Inspection Report for Div 'B' SBDG STP Rte-33; August 2, 2009

CAP 068815; CAQ - Thermography Anomaly in 1C118 (Diesel Generator 1G-21 Control Relay)

CAP 069502; A SBLC Pump Declared Inoperable, Pumps above ASME Limits

STP 3.1.7-01; SBLC Pump Operability Test; Revision 27; Performance Date September 4, 2009

at 0940 STP 3.1.7-01; SBLC Pump Operability Test; Revision 27; Performance Date September 4, 2009 at 1645

STP 3.1.7-03; SBLC System Boron Concentration Test; Revision 21; Performance Date September 5, 2009

CAP 070040; A SBDG Air Start Piping Support Discrepancy

CAP 070061;

CAP 070040 (Air Start Piping Issues on a SBDG) Issues

OP-AA-102-1003 (DAEC); Guarded Equipment (DAEC Specific Information); Revision 0

Section 1R18 White Paper on

CV-1068 Flow Accelerated Corrosion Evaluation; Al Thomas, DAEC Flow Accelerated Corrosion Engineer

BECH-M103<3>; P&ID Main Steam Moisture Separators and Reheaters; Revision 12 WO A963515; Valve

CV-1068 is in Intermediate Position.

Troubleshoot to determine if Problem is a Controller or Valve Concern

CAP 069846; Unexpected Moisture Separator Reheater Second Stage Drain Tank 1T-92B Hi Level

TM-09-25;

CV-1068 Valve Gag to Prevent Valve Traveling Fully Closed Section 1R19 Corrective WO A95563; Replacement and Calibration of Relay P110500-1 Due to Failure STP 3.0.0-01; Instrument Checks; Revision 95

CAP 068265; Repeat Event - CAQ - Annunciator 1C04B (C-4) Activated Apparent Cause Evaluation

001967; CAQ - Annunciator 1C04B (C-4) 'RCIC Steam Leak Det Logic Power Failure' Activated

WO 1146179; Inspect and Repair, Per Procedure, 1B3448

CAP 068414; The Case is Cracked on the Forward Contactor for 1B3448

WO 1146579; Perform Annual Inspection and Oil Change on 1K090B

CAP 068845; Post Maintenance Testing Failed on 1K090B Due to Leaking Gasket

CAP 068826; 1BR9-200 Would Not Close Using Handswitch

CAP 069138; 1K090B Instrument Air Compressor Manual Drain Valve V30-700 is Leaking through Closed Seat

WO 1147266; Calibrate Flow Instrument Loop Per Procedure Equipment-Specific Maintenance Procedure (EMP) I.PDT-G080-01; G.E. Type 555 D/P Transmitters Dry Calibration, Section A; Revision 15 EMP I.II-G080-01; Linear Calibration, Section A; Revision 5

Attachment EMP I.ER-H260-01; Honeywell Vultronik Recorders Non-Linear Calibration, Section B;

Revision 3

WO A94390; Replace LS3701 and Calibrate Per Procedure EMP I.LIS-G050-01; GEMS Model 31924 Level Indicating Switches Calibration, Section A; Revision 5

CAP 069035; Trend CAP - Trend in Drywell Floor Drain Leakage

CAP 069279; Containment Leakage Monitoring Notifications

OI 920; Drywell Sump System; Revision 38

WO A93410; Strainer Packing Leak

Section 1R22 STP 3.3.1.1-05; Reactor High and Lo Water Level (HPCI, RCIC, RPS [Reactor Protection System], PCIS [Primary Containment Isolation System]) Instrument Channel Calibration; Revision 7 WO A76492; Replace 3 Way Valve Manifold: Work During STP 3.3.1.105

CAP 054727; NCAQ -

LIS 4592D-V-15 LP Isolation Does Not Isolate Properly

CAP 068519; Valve V46-0031 RHRSW Pump A Disc Isolation Valve Degraded

CAP 068518; Revise STP NS16004A/B to Permanently Incorporate

DCF 47657

CAP 068488; 1P22A Differential Pressure outside Acceptance Criteria STP NS160004A; RHR Service Water Operability Test and Comprehensive Pump Test; Revision 1

STP 3.5.3-02; RCIC System Operability Test; Revision 26

STP 3.8.1-06B; 'B' SBDG Operability Test (Fast Start); Revision 6

STP 3.8.1-01; Offsite Power Sources; Revision 3

OI 324A9; SBDG Operating Checklist; Revision 9

OI 324A10; SBDG Standby/Readiness Condition Checklist; Revision 10

CAP 068709; Difficulty Closing 1A311

CAP 064137; 'B' SBDG Governor Mode Select Bypass Testing

CAP 066658; SBDG STP Operability in Parallel

STP 3.4.5-01; Calibration of Equipment Drain Sump and Floor Drain Sump Flow Integrators; Revision 10 STP 3.3.5.1-14; 'A' Core Spray Logic System Functional Test; Revision 1

WO S016291; Core Spray Logic System Functional Test 'A' Drawing 791E419RS; Elementary Diagram Core Spray System; Revision 25

Section 1E02 An Offsite Emergency Plan Prompt ANS Addendum for the Duane Arnold Energy Center; November 1985

Duane Arnold Energy Center Outdoor Warning System/ANS Upgrade Project Federal Emergency Management Agency

REP-10 Final Design Report Supplement; Revision 0;

Appendix P; dated January 6, 2009 Letter from Federal Emergency Management Agency to Mr. J. Michael Davis concerning approval of the siren upgrade package; dated January 30, 2009

CE 007565; Evaluate Extent of Condition for Other Sirens in EPZ; dated July 16, 2009

CAP 059419; Siren Found Inoperable; dated August 8, 2008

CAP 059530; Gap Exists in Organization for Supporting EP Siren Maintenance; dated August 13, 2008

Attachment

CAP 049492; Alert and Notification System (ANS) Testing Needs Improvement; dated

May 3, 2007

CAP 049493; Siren Work Order Process Needs Improvement; dated May 3, 2007

Section 1E03 Duane Arnold Energy Center Emergency Telephone Book; dated July 2009 2009 State Annual EAL Training Attendance Sheet; dated January 28, 2009

PDA-EPR-ERO; Emergency Response Organization Training and Qualification Manual, Qualification Requirements for Various Positions

Section 1E05

PI-AA-204; Nuclear Process Description, Condition Identification and Screening Process; Revision 4

PDA-08-006; Nuclear Oversight Quality Report, 2008 EP Assessment; dated February 20, 2008

PDA-08-023; Nuclear Oversight Quality Report, 2008 Emergency Planning Program,

July 14, 2008

PDA-09-023; Nuclear Assurance Report, Emergency Preparedness; dated July 20, 2009

Event Summary Report for Notification of Unusual Event and

ACE 001860; Unusual Event Declared Based on Loss of Communications Capability; dated August 17, 2008

CAP 058387; Loss of FPLE DA Emergency Operations Facility; dated June 17, 2008

CAP 058386; Loss of Ability to Contact Linn County Sheriff Office; dated June 17, 2008

CAP 058377; Flood Damaged Sirens and Related Equipment; dated June 17, 2008

CAP 058292; Eight-hour Reportable Notification Made for Loss of Offsite Response Capability;

dated June 12, 2008

CAP 058279; Loss of Power to Siren Repeater; dated June 11, 2008

CAP 058235; Possible Loss of Two Siren Activation Points; dated June 10, 2008

CAP 067417; Appropriateness of Controller Interjection Questioned; dated May 20, 2009

CAP 068506; Evaluate Impact of 5/20/2009 ERO Training Drill Controller Interject; dated July 17, 2009

CAP 061050; NRC Concern with Adequacy of EALs for Low River Levels; dated

October 17, 2008

CAP 042883; Operability Recommendation for Intake Structure Fore-Bay Inspection Identified Significant Sand Accumulation; dated June 23, 2006

Condition Evaluation for the Sand Gates at the Intake Structure Are within One Foot of Being in the Full Up Position; dated July 18, 2006

CAP 068505; Review Adequacy of EALs HU 1.9 and HA 1.7; dated July 17, 2009

CAP 069930; Assess Operating Crew Table Top Drills; dated September 23, 2009

CAP 059302; MET Tower Computer Points out of Tolerance; dated August 4, 2008

CAP 066817; High Radiation Alarm for Kaman 4 Activated; dated April 24, 2009

CAP 054144; Nuclear Oversight Station Paging System Corrective Action Review; dated December 6, 2007

CAP 061267; 08IPX Review Notification Performed on June 30, 2008 for Possible DEP Failure; dated October 23, 2008

CAP 059835; DEP Failure - Delay of EAL Classification after Initiating Conditions Recognized;

dated August 26, 2008

AP 058809; Unexpected Annunciator for Drywell Equipment Leakage; dated July 10, 2008

CAP 068122; Was Correct EAL Declared for Unannounced Fire Drill; dated June 26, 2009

Attachment Section 1E06 Duane Arnold Emergency Preparedness Drill, September 16th, 2009 2009 ERO Dress Rehearsal Final Report; September 23, 2009

CAP 069730; 09DR - Controller Prompted Crew to Start all Reactor Building Supply and Exhaust Fans

CAP 069764; 09DR - Drill Validation Crew Response Different than Drill Operations Crew for

EOP-3

CAP 069762; 09DR - Controller Intervention to Prevent Crew from Scramming due to Conservative Action Based on Plant Conditions

CAP 069739; 09DR - Simulator Lead Controller Drill Interjection (DEP-PI Issue)

2PS3 Radioactive Material Processing and Transportation Program (71122.02)

AR-36733; Quick Hit Assessment Report; dated July 9, 2009

PI-AA-101-1001; Nuclear Fleet Guidelines; Quick Hit Assessments; Revision 2

RWH-3406.6; Characterizing Radioactive Material for Transport; Revision 8

RWH-3406.1; Waste Classification and Characterization; Revision 8

STP-NS790707; Radioactive Liquid Release Sampling and Analysis; Revision 0

RWH-3402.6; Radwaste Handling Procedure; Processing Contents of 1T-71A(B) Waste Sampling Tanks; Revision 30

RWH-3402.21; Radwaste Handling Procedure;

IT-60 Evaporator Bottom Tank Resin Transfer and Dewatering; Revision 25

RWH-3409.2; Radwaste Handling Procedure; Sampling Instructions and Analysis of Radwaste Stream; Revision 11

PDA-07-020; Assessment; Daily Quality Summary Rollup

PDA-08-007; FPLE Duane Arnold Nuclear Oversight Quality Report; dated March 3, 2008 2008 Annual Radioactive Material Release Report; dated April 22, 2009 08-003-R; 10 CFR Part 61 Compliance Data Technical Basis for DAEC Condensate Resin;

dated May 6, 2008

08-001-R; 10 CFR Part 60 Compliance Data Technical Basis for DAEC Reactor Water Clean-

Up Resin; dated June 10, 2008 08-002-R; 10 CFR Part 60 Compliance Data Technical Basis for DAEC DAW; dated

July 7, 2008

08-003-R; 10 CFR Part 60 Compliance Data Technical Basis for DAEC Condensate Resin;

dated May 6, 2008

RSR-07-57; 10 CFR Part 61 Sample Package; DAW Smear Composite, Condensate Resin, Reactor Water Clean-Up Resin to General Engineering Labs; dated October 15, 2007

RSR-07-46; Radioactive Material, Type B(M), 7, UN2917, RQ, Radionuclide; RWCU/Condensate Resin; dated May 29, 2007

RSR-09-27; Radioactive Material, Low Specific Activity (LSA-II), 7,

UN 3321, Fissile Excepted; Solid, Metal Oxides; dated July 13, 2009

RSR-09-19; Radioactive Material,

LSA-1, 7, UN2912, Fissile Excepted; dated March 6, 2009, 40' Sealand of Contaminated Laundry

RSR-09-22; Radioactive Material;

LSA-1, 7,

UN 2912; dated March 26, 2009; 20' Sealand Diver Platform

RSR-09-25; Radioactive Material, Surface Contaminated Object (SCO-II), 7, UN2913; dated June 23, 2009; "Clean" Electronic Equipment Boxes

RSR-09-18; Radioactive Material, Type A Package, 7,

UN 2915; dated March 5, 2009; Type A Containers of Contaminated Equipment Attachment

RSR-09-17; Radioactive Material, Type A Package, 7,

UN 2915; dated March 4, 2009; GE Metal Boxes

RSR-0913; Radioactive Material, Low Specific Activity (LSAII), 7, 3321, dated

February 20, 2009; 4' General Design Containers of Control Rad Boxes

RSR-08-13; Radioactive Material; Low Specific Activity (LSA-II), 7,

UN 3321, Fissile Excepted,

RQ-Radionuclide Condensate Resin Shipment; dated May 29, 2008

RSR-08-18; Radioactive Material, LSA II, 7,

UN 3321, Fissile Excepted; dated October 20, 2008; Dewatered Condensate Resin in Radlok 195, Poly HIC

Section 4OA1

NEI 99-02; Regulatory Assessment Performance Indicator Guideline; Revision 5

ACP 1420.4; NRC & WANO Performance Indicator Reporting; Revision 13

FPL Nuclear Administrative Procedure-206; NRC Performance Indicators; Revision 3

DAEC Open Work Order Report for the RCIC System DAEC Open Work Order Report for the HPCI System DAEC Open Work Order Report for the 'A' and 'B' SBDG Systems

DAEC Level A and B CAP Items Report for the RCIC System

DAEC Level A and B CAP Items Report for the HPCI System

DAEC Level A and B CAP Items Report for the 'A' and 'B' SBDG System DAEC MSPI Derivation Report for the Heat Removal System through June 2009 DAEC MSPI Derivation Report for the High Pressure Injection System through June 2009

DAEC MSPI Derivation Report for the Emergency AC Power System through June 2009

EPDM 1010, Performance Indicator Data Retrieval Worksheets, 3rd quarter 2008 through 1st Quarter 2009

EPDM 1013; Emergency Siren (ANS) and Siren Program; Monthly Siren Test Results, 3rd quarter 2008 through 1st Quarter 2009 EPDM 1016, ERO Augmentation Drill and Testing Program; dated November 2007 through June 2009

Emergency Response Organization ERO Drill Key Participation Indicator Report; 3rd quarter 2008 through 1st Quarter 2009

Section 4OA2

PI-AA-204; Condition Identification and Screening Process; Revision 4

PI-AA-205; Condition Evaluation and Corrective Action; Revision 3

DAEC Corrective Action Effectiveness Review Manual; Revision 3

ACP 101.11: Control of Posted Documents, Labels, and Signs; Revision 5

ACP 1410.11; Control of Operator Aids; Revision 4

ACP 1410.12; Operator Burden Program; Revision 18

CAP 069147; NCAQ - Operations Audits Not Completed and No Ops Manager Approval is Documented

CAP 069148; NCAQ - An Apparent Operator Aid is Not Being Controlled As Such

EN-AA-203-1001; Operability Determinations/Functional Assessments; Revision 1

CAP 068701; CAQ - Circuit Sensor Flanges not Shown on