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August 7, 2009

Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 INTEGRATED INSPECTION REPORT 05000237/2009-003; 05000249/2009-003

Dear Mr. Pardee:

On June 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Dresden Nuclear Power Station, Units 2 and 3. The enclosed report documents the inspection results, which were discussed on July 15, 2009, with Mr. T. Hanley 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. The report documents one NRC-identified finding and one self-revealed finding of very low safety significance (Green). Both of these findings were determined to involve violations of NRC requirements. However, because of the very low safety significance and because they are entered into your corrective action program, the NRC is treating these findings as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest any NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, 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 NRC Resident Inspector at Dresden. 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 Dresden. 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, its enclosure, and your response (if any) will be made 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 J. Benjamin, Acting For/ Mark A. Ring, Chief Branch 1 Division of Reactor Projects Docket Nos. 50-237; 50-249 License Nos. DPR-19; DPR-25

Enclosure:

Inspection Report 05000237/2009-003; 05000249/2009-003

w/Attachment:

Supplemental Information cc w/encl: Site Vice President - Dresden Nuclear Power Station Plant Manager - Dresden Nuclear Power Station Manager Regulatory Assurance - Dresden Nuclear Power Station Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director - Licensing and Regulatory Affairs Manager Licensing - Clinton, Dresden, and Quad Cities Associate General Counsel Document Control Desk - Licensing Assistant Attorney General J. Klinger, State Liaison Officer, Illinois Emergency Management Agency Chairman, Illinois Commerce Commission

SUMMARY OF FINDINGS

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

REPORT DETAILS

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

REACTOR SAFETY

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

1R01 Adverse Weather Protection

Main article: IP 71111.01

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

1R04 Equipment Alignment

Main article: IP 71111.04

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

1R05 Fire Protection

Main article: IP 71111.05

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

1R07 Annual Heat Sink Performance

Main article: IP 71111.07

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

1R11 Licensed Operator Requalification Program (71111.11Q & A) ......................... 8 1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

...... 10

1R15 Operability Evaluations

Main article: IP 71111.15

................................................................ 11

1R18 Plant Modifications

Main article: IP 71111.18

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

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

1R20 Outage Activities

Main article: IP 71111.20

.......................................................................... 17

1R22 Surveillance Testing

Main article: IP 71111.22

.................................................................... 17

1EP6 Drill Evaluation

Main article: IP 71114.06

RADIATION SAFETY

................................................................................................. 19 2PS1 Access Control to Radiologically Significant Areas (71121.01)

OTHER ACTIVITIES

................................................................................................... 24

4OA1 Performance Indicator (PI) Verification

Main article: IP 71151

............................................. 24

4OA2 Identification and Resolution of Problems

Main article: IP 71152

......................................... 26

4OA3 Event Follow-up

Main article: IP 71153

................................................................................ 31

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

T. Hanley, Site Vice President

S. Marik, Station Plant Manager

H. Bush, Radiation Protection Manager

B. Finely, Security Manager

D. Glick, Shipping Specialist

J. Griffin, Regulatory Assurance - NRC Coordinator

D. Gronek, Operations Director

J. Hansen, Corporate Licensing

L. Jordan, Training Director

R. Kalb, Chemistry

P. Karaba, Maintenance Director

M. Kluge, Design Engineer

D. Leggett, Nuclear Oversight Manager

R. Laburn, Radiation Protection

M. Marchionda, Regulatory Assurance Manager

M Overstreet, Lead Radiation Protection Supervisor

P. O'Connor, License Operator Requalification Training Lead

M. Overstreet, Lead Radiation Protection Supervisor

C. Podczerwinski, Maintenance Rule Coordinator

P. Quealy, Emergency Preparedness Manager

E. Rowley, Chemistry

R. Rybak, Regulatory Assurance

J. Sipek, Engineering Director

N. Starcevich, Radiation Protection Instrumentation Coordinator

J. Strmec, Chemistry, Environmental and Radwaste Manager

S. Taylor, Regulatory Assurance Manager

S. Vercelli, Work Management Director NRC

M. Ring, Chief, Division of Reactor Projects, Branch 1

J. Benjamin, Project Engineer IEMA

R. Zuffa, Illinois Emergency Management Agency

R. Schulz, Illinois Emergency Management Agency

Attachment

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened:

05000237/2009003-01 URI Failure of 2/3 Emergency Diesel Generator (EDG) Due to

05000249/2009003-01 Lube Oil Leak On Y-Strainer

05000249/2009003-02 NCV Failure to Have a Procedure to Sample and Establish Administrative Controls for pH in the Torus

05000237/2009003-03 NCV Instrument Air Isolation Valve Mispositioning on

05000249/2009003-03 April 26, 2009 Closed:

05000249/2009003-02 NCV Failure to Have a Procedure to Sample and Establish Administrative Controls for pH in the Torus

05000237/2009003-03 NCV Instrument Air Isolation Valve Mispositioning on

05000249/2009003-03 April 26, 2009 237/2009-002-00 LER Unit 2 High Pressure Coolant Injection Suction Valve Fails to Close 237/2008-002-00 LER Unit High Pressure Coolant Injection [HPCI] System Declared Inoperable Discussed: None.

Attachment

LIST OF DOCUMENTS REVIEWED

The following is a partial list of documents reviewed during the inspection.

Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections or 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.

1R01 Adverse Weather Protection (71111.01) -

IR 923788, "Common Line Blockage on Chemical Injection to EDG Cooling Water" -

WO 01198342, "D2/3 QTR TS D/G CLG WTR PMP TEST For IST Program Surveillance (Quarterly 2/3 Diesel Generator Cooling Water Pump in-service test)," April 3, 2009 -

IR 918277,"NRC Concern Missile Hazards Near TR2" 1R04 Equipment Alignment (71111.04) - Drawing M-374 "Diagram of High Pressure Coolant Injection Piping" Rev CQ -

DOP 2300-M1/E1 "Unit 3 HPCI System Checklist" Rev 36 -

DOP 2300-01 "High Pressure Coolant Injection (HPCI) System Standby Operation" Rev 39 1R05 Fire Protection (71111.05) - Fire Pre-Plan for FZ 8.2.5.D, Revision 8 - Fire Pre-Plan for FZ 8.2.5.E, Revision 8 - Fire Pre-Plan for FZ 8.2.5.E, Revision 8 - Fire Pre-Plan for FZ 1.1.2.5.A, Revision 8 1R07 Heat Sink Performance -

WO 1172779, "D2 An PM Perform Hx Thermal Performance Test - 2B LPCI Hx" -

WO1168983, "D3 An PM Perform Hx Thermal Performance Test - 3B LPCI Hx" 1R11 Licensed Operator Requalification Program (71111.11Q) - NRC Requalification Exam 2007-2009 Cycle 11: Scenarios

OPEX-AU Rev. 01 and

OPEX-AX Rev. 00 - NRC Requalification Exam 2007-2009 Cycle 11:Scenarios

OPEX-T Rev. 10 and

OPEX-AV Rev. 01 - Requalification Examination Results/Calendar Year 2009 1R12 Maintenance Effectiveness (71111.12) -

IR 908112, "Roof Drain Penetration Leaking on 2/3 EDG Governor" -

IR 926605, "Oil Leak on the 2/3 DG Turbo Lube Oil Y-Strainer" 1R15 Operability Evaluations (71111.15) -

IR 894307, "Contingency Maint on the

2-2301-6 MOV" -

IR 894450, "MOV

2-2301-6 Valve Binding Observed" -

IR 900649, "HPCI

2-2301-6 Valve Design Information Discrepancies" Attachment - OpEval # 09-002, Rev. 000,

2-2301-6 (U2 HPCI Suct Vlv from CST) - MOV

2-2301-6 Root Cause Report, dated April 10, 2009 -

EC 374991, "Evaluate HPCI System Function with

2-2301-6 Valve Failed to Close," Revision 000 -

WO 1225564, "D2 1M EQ IST Alert Range Vlv Timing/Modified MOV Diag

2-2301" -

IR 924049, "Errors in Calculating New Low-Low CST Levels in

EC 374991"

-

IR 899954 "Thermal Overload Calculation for MOVs Is Non-Conservative" -

DRE-2-2301-5 "MIDACALC Results, Dresden, Unit 2, DC Motor Operated Gate Valve Calculation" Rev 4 - Curve Sheet

PTA 032480 "Overload Relay Time - Current Characteristics"

Rev 1 -

IR 812240, "3A Core Spray Pump Leaking Union Identified"

-

CY-AB-120-310, "Suppression Pool/Torus Chemistry," Revision 4 -

DES 6600-03, "Safety Related Contact Testing - Diesel Generators," Revision 02 - Drawing 12E-2351A, "Schematic Diagram Engine Control and Generator Excitation Standby Diesel Generator 2/3" -

IR 932854, "Ops Screening for Reportability - EDG Wiring Deficiency" -

DOA 6500-12, "Low Switchyard Voltage," Revision 18 -

DOS 6600-01, "Diesel Generator Surveillance Tests," Revision 109 1R18 Plant Modifications (71111.18) -

IR 908209, "Offgas Alarm Setpoint Not in Compliance with TS Appendix B" - Unit 2 License Amendment No. 163 - Unit 3 License Amendment No. 158 -

IR 918435, "3A SJAE Nozzle Replacement Causes Vacuum Transient"

-

DAN 902(3)-3 D-2, "Offgas Rad Monitor Hi" -

IR 920400, "Regulatory Commitment for Tech Spec Amendments 163 and 158" -

IR 920323, "NRC Questions Operations Response to U3 Off Gas Hi Rad Alarm" -

WO 1230547, "Offgas Alarm Setpoint Not in Compliance with TS Appendix B" -

WO 1231439, "Need a WO to Reset U3 OG Rad Monitors" 1R19 Post-Maintenance Testing (71111.19) -

WO 565281, "D2/3 6Y PM Standby Diesel Generator Inspection" -

DMS 6600-02, "Diesel Generator Mechanical Inspection and Preventive Maintenance (2 yr., 4 yr., 6 yr.)," Revision 30 -

DMS 6600-03, "Diesel Generator Mechanical Inspection and Preventive Maintenance (12 yr.), Revision 18 -

IR 910596, "NRC Inspector Questions SBLC DOS [Dresden operating surveillance] Acceptance Criteria" -

WO 01004810-09, "Ops PMT 3C Main Steam Line Electromatic RV" -

WO 01004810-08, "Perform

VT-2 Inspections Following Valve Replacement" 1R20 Outage Activities (71111.20) -

DGP 01-01, "Unit Startup," Revision 149

Attachment 1R22 Surveillance Testing (71111.22) -

DOS 1400-09, "2 Year U3 Core Spray Pump Comprehensive Test," Revision 5 - ASME OM Code - 2001, "Subsection ISTB, Inservice Testing of Pumps in Light-Water Reactor Nuclear Power Plants" -

IR 912765, "Leak Detection and Reduction Program" - Appendix A, "Unit NSO Daily Surveillance Log," Revision 116

-

IR 780436, "U3 Drywell Activity and DWEDS Flow Adverse Trend" -

IR 807998, "Red Phone Call Due to RCS Leakage Detection Instrumentation" -

IR 817021, "Increase in Cobalt Activity on Unit 3" -

IR 860747, "Drywell Activity Results Suspect" -

DOS 6600-12, "Diesel Generator Tests Endurance and Margin/Full Load Rejection/ECCS/Hot Restart," Revision 48 - Appendix X, "Technical Specification Action Statement Initiated Surveillances," Revision 30 - Technical Evaluation

362860, "Ultra Low Sulfur Diesel Fuel Evaluation," October 6, 2006. -

EC 363408, "Diesel Generator Ultra Low Sulfur Diesel (ULSD) Fuel Upgrade," Revision 0 -

DIS 1500-32, "Division I & II Low Pressure Coolant Injection ECCS Loop Selection Circuitry Logic System Functional Test," Revision 5 -

IR 907321, "NRC Identified Concern"

- DFPS 4123-07, "Unit 1 Fire Pump Capacity Check," Revision 38 -

IR 919301, "Oil Leak on U1 DFP Turbo Oil Line" -

IR 934963, "Procedural Discrepancies Identified During U1 DFP CAP Test" -

IR 935541, "U1 DFP Governor Need to be Adjusted" -

IR 935492, "Unit 1 DFP Fire Pump Surveillance Clarifications"

-

IR 898201, "2009 Byron CDBI Issue - Degraded Voltage 5-minute Time Period. 1EP6 Drill Evaluation (71114.06) - 2007-2009 Cycle 11; Scenarios

OPEX-T Rev. 10 and

OPEX-AV Rev. 01 2OS1 Access Control to Radiologically Significant Areas -

RP-AA-210; Dosimetry Issue, Usage and Control; Revision 15 -

RP-AA-460; Controls for High and Locked High Radiation Areas; Revision 17 -

RP-AA-460-002; Additional High Radiation Exposure Control; Revision 0 -

RP-AA-300; Radiological Survey Program; Revision 5 -

RP-AA-302; Determination of Alpha Levels and Monitoring; Revision 2 -

DFP 0800-39; Control of Material/Equipment Hanging in the Units 2 and 3 Spent Fuel Pools; Revision 14 - Report of Focused Area Self-Assessment; Control of Access to Radiologically Significant Areas; dated February 27, 2009 - ALARA Plan for

RWP 10009288; D3R20 Drywell Nuclear Instrumentation; Revision 0 - ALARA Plan for

RWP 10009306; D3R20 Drywell In-Service-Inspection Activities; Revision 0

- ALARA Plan for

RWP 10009298; D3R20 Drywell Control Rod Drive System Maintenance; Revision 1 -

RWP 10010249 and ALARA Plan; Remove Waste from Waste Concentrator "B" Vault; Revision 0 - Unit 2 and 3 Fuel Pool (non-fuel) Inventory; January 2009 -

RWP 10010183 and ALARA Plan; Unit 2 and 3 Dry Cask Storage Activities; Revision 0 -

TID-2009-006; Annual Bioassay Program Review; dated November 17, 2008

Attachment -

AR 00849512; Need to Lock Cranes/Hoists to Comply with Procedure; dated November 25, 2008 -

AR 00852691; Accounting of Non-Emergency High Radiation Area Keys Not Performed Daily; dated December 5, 2008 4OA1 Performance Indicator Verification -

CY-AA-130-3010-F-03; Dose Equivalent Iodine Determination; Calculations and Gamma Spectroscopy Results (selected periods between July 2008 and March 2009) -

CY-AA-130-300; Gamma Spectrometry; Revision 4 -

CY-DR-110-200; Plant System Sampling; Revision 16 -

LS-AA-2090; Monthly Data Elements for NRC Reactor Coolant System Specific Activity; July 2008 - March 2009 4OA2 Identification and Resolution of Problems -

AR 00880560; Sludge Found on Radwaste Basement Floor; dated February 9, 2009 -

AR 00884519; Main Concentrated Waste Tank; dated February 23, 2009 -

AR 00594354; Penetration in Waste Demin Vault Leaks into Radwaste Basement; dated February 21, 2007 -

AR 00811979; Resin on Floor of Radwaste Basement; dated August 28, 2008 - Troubleshooting Plan for Main Concentrated Waste Vault Sludge; undated

- Operator Challenge No. 50, "Unit 2 CRDs" - Operator Challenge No. 63, "Unit 2 Torus Level Increase" Attachment