IR 05000315/2011005

Inspection Report 05000315-11-005, 05000316-11-005; 10/01/2011 - 12/31/2011; D. C. Cook Nuclear Power Plant, Units 1 & 2; Inservice Inspection Activities and Refueling Outage Activities

ML120300211
Person / Time
Site:	Cook
Issue date:	01/30/2012
From:	John Giessner Division of Nuclear Materials Safety III
To:	Weber L Indiana Michigan Power Co
References
Preceding documents:	ML120300211 (30 January 2012)
Download: ML120300211 (39)

Text

January 30, 2012

Mr. Larry Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

SUBJECT: D. C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 - NRC INTEGRATED INSPECTION REPORT 05000315/2011005 and 05000316/2011005

Dear Mr. Weber:

On December 31, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your D. C. Cook Nuclear Power Plant, Units 1 and 2. The enclosed inspection report documents the results of this inspection, which were discussed on January 18, 2012, with Mr. J. Gebbie, 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. One NRC identified finding and one self-revealed finding of very low safety significance (Green) were identified during this inspection. These findings were determined to involve violations of NRC requirements. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy. If you contest 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 Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the D. C. Cook Nuclear Power Plant, Units 1 and 2. If you disagree with a cross-cutting aspect assignment 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 D. C. Cook Nuclear Power Plant, Units 1 and 2. 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 (PARS) component of NRC's Agencywide Document Access and Management 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/

John B. Giessner, Branch Chief Branch 4 Division of Reactor Projects Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74

Enclosure:

Inspection Report 05000315/2011005 and 05000316/2011005

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 05000315; 05000316 License Nos: DPR-58; DPR-74 Report No: 05000315/2011005; 05000316/2011005 Licensee: Indiana Michigan Power Company Facility: D. C. Cook Nuclear Power Plant, Units 1 and 2 Location: Bridgman, MI Dates: October 1 through December 31, 2011 Inspectors: J. Lennartz, Senior Resident Inspector P. LaFlamme, Resident Inspector E. Davidson, Reactor Systems Engineer T. Go, Health Physicist E. Sanchez Santiago, Reactor Inspector A. Shaikh, Reactor Inspector S. Shah, Reactor Inspector Approved by: John B. Giessner, Chief Branch 4 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

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

REPORT DETAILS

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

REACTOR SAFETY

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

1R01 Adverse Weather Protection

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

1R04 Equipment Alignment

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

1R05 Fire Protection

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

1R07 Annual Heat Sink Performance

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

1R08 Inservice Inspection Activities

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

1R11 Licensed Operator Requalification Program

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

1R13 Maintenance Risk Assessments and Emergent Work Control

12

1R15 Operability Evaluations

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

1R18 Plant Modifications

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

1R19 Post-Maintenance Testing

......................................................14

1R20 Outage Activities

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

RADIATION SAFETY

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

2RS0 2 Occupational ALARA Planning and Controls

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

OTHER ACTIVITIES

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

4OA2 Identification and Resolution of Problems

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

4OA3 Followup of Events and Notices of Enforcement Discretion

.........21 4OA6 Management Meetings .............................................................................22

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

D. Cantrell, Site Senior License Licensee

M. Carlson, Site Support Services Vice President

J. Chambers, Emergency Preparedness Manager

R. Ebright, Engineering Director

H. Etheridge, Licensing Manager

J. Gebbie, Site Vice President

R. Hall, ISI Program Owner

R. Keppeler, Maintenance Manager

Q. Lies, Plant Manager

J. Nimtz, Regulatory Affairs Senior Licensing Activities Coordinator

K. O'Conner, Compliance Manager

R. Pickard, Engineering Manager

M. Scarpello, Regulatory Affairs Manager

R. West, Regulatory Assurance

T. Woods, Performance Assurance Director

S. Vazquez, Operations Director

J. Giessner, Chief, Reactor Projects Branch 4 Nuclear Regulatory Commission

J. Lennartz,

D.C. Cook Senior Resident Inspector P. LaFlamme, D.C. Cook Resident Inspector

Attachment

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

05000315/2011005-01 Opened NCV Failure to Follow Procedure for PT Examination on ASME Class 1 Piping Weld (1R08)

05000315/2011005-02 NCV Failure to Follow the Clearance Procedure During Maintenance on Safety-Related Equipment (1R20)

05000315/2011005-01 Closed NCV Failure to Follow Procedure for PT Examination on ASME Class 1 Piping Weld (1R08)

05000315/2011005-02 NCV Failure to Follow the Clearance Procedure During Maintenance on Safety-Related Equipment (1R20) 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. - 12-IHP-5040-EMP-004, Plant Winterization and De-Winterization, October 27, 2011 1R01 Adverse Weather Protection -

AR 2011-0919, 12-DFPWS-1B-13 Found Tripped -

AR 2011-12648, Hole in Siding on Screenhouse While Performing Winterization -

AR 2011-3900, Sub Panel 12-WST, Heater Needs to Be Replaced -

PMP-5055-001-001, Winterization/ Summerization, October 31, 2011 - Seasonal Readiness Affirmation, November 3, 2011 - 1-OHP-4021-009-001, Placing the Containment Spray System in Standby Readiness, Revision 15 1R04 Equipment Alignment - 1-OHP-4030-156-017W, West Motor Driven Auxiliary Feed Water System Test, Revision 7 - 2-OHP-4021-008-002, Placing Emergency Core Cooling System in Standby Readiness, Revision 24 - 2-OHP-4030-208-053V, E.C.C.S. Valve Position Verification, Revision 6 -

AR 2010-12863, CAQ - Condition Adverse to Quality -

AR 2010-12863-1, Evaluate Valves Found Closed that Should Have Been Open -

AR 2010-12863-2, Document Basis for Mis-positioning Classification -

AR 2010-12863-3, Revise 1-OHP-4021-002-011 -

AR 2010-12863-4, Revise 2-OHP-4021-002-011 -

AR 2010-9131, Mis-positioning of 2-FMO-231 While Performing PM on 2-FMO-232 -

AR 2011-12340, 2-MRV-243 is Leaking By Slightly -

AR 2011-12817, U1 No. 3 S/G Blowdown Low Sample Flow -

AR 2011-12995, Dry Boric Acid on 1-RH-113E -

AR 2011-13003, Discolored Boric Acid on Packing Leak -

AR 2011-13043, 1-CTS-130W Has White Dry Boric Acid on the Packing Gland -

AR 2011-13047, 1-IMO-314 Has White Dry Boric Acid on the Packing -

AR 2011-13149, U1 RWST Doghouse and Hatch Leading to RWST Pipe Tunnel Leak -

AR 2011-2604, 2-IRV-303 Control Switch Found Out of Position -

GT-2010-4505, NSRB Action Items -

AR 2010-1610, Sprinkler Head Needing Evaluation 1R05 Fire Protection -

AR 2011-0119, Fire Hose Connection Degraded -

AR 2011-0822, U-2 CRCV Halon Bottles Surveillance Failed -

AR 2011-10034, Unexpected FP Annunciator -

AR 2011-10308, Fusible Link Missing from Door to Supplemental Cooling -

AR 2011-13546, Damaged Fire Proofing Material on Cable Tray - FHA, Fire Hazards Analysis, Revision 15 - Fire Pre-Plan, Revision 9

Attachment - 12-EHP-8913-001-002, Heat Exchanger Inspection for CD EDG Jacket Water Cooler, October 7, 2011 1R07 Annual Heat Sink Performance -

AR 2011-10958, 1-HE-15W, West Comp Cooling Water HX Zebra Mussel Shells -

AR 2011-11292, Fresh Water Shrimp Found in ESW Sys in 1-HE-47-ABS & Piping -

AR 2011-11831, Degraded Component Found during U1C24 Outage -

AR 2011-12175, Increased Silt and Mussels Noted During Sampling -

AR 2011-12222, CCW Heat Exchangers Configuration -

WOT 55353929-19, Unit 1 East Component Cooling Water Heat Exchanger, October 9, 2011 - 12

QHP-5050-NDE-001, Liquid Penetrant Examination, Revision 7 1R08 Inservice Inspection Activities - 12-QHP-5050-NDE-006, Visual Examination:

VT-1 and

VT-3, Revision 4 -

AR 00828718, Evidence of Leakage and BA at Flange Connection, March 30, 2008 -

AR 00828718/552855170, Data Sheet 1 and BA Evaluation for

AR 00828718, March 30, 2008 -

AR 00863314, 1-GFW-R-179, Identified Discrepancies during Visual Exam, January 13, 2010 -

AR 10011030, I1C23 Section XI Repair/Replacements Planned to Wrong Code, January 11, 2010 -

AR 10013050, 1-GCCW-L-236, Identified Discrepancies during

VT-3 Exam, January 13, 2010 -

AR 2010-10059, 1

QDA-11 Boric Acid Found by Drain Valve, September 29, 2010 -

AR 2010-10346, #24 RCP Seal Leakage, November 1, 2010 -

AR 2010-10356, Boric Acid was Identified on the CTS Spray Nozzle, October 6, 2010 -

AR 2010-11945, Boric Acid Leak in U2 Containment Basement from Crane Wall Penetrations, November 5, 2010 -

AR 2010-11945-2, Data Sheet 1 and BA Evaluation for

AR 2010-11945, November 5, 2010 -

AR 2010-12391-1, Data Sheet 1 and BA Evaluation for

AR 2010-12414, November 17, 2010 -

AR 2010-12414, 2-RH-117 has an Active Packing Leak, November 17, 2010. -

AR 2010-12414, Data Sheet 1 and BA Evaluation for

AR 2010-12912, November 17, 2010 -

AR 2010-12518, BA Identified on 2-NS-621 (RC Loop No. 3 HL Sample Shutoff valve), November 19, 2010 -

AR 2010-12518-1, Data Sheet 1 and BA Evaluation for

AR 2010-12518, November 17, 2010 -

AR 2010-12606, U1 Seal Table Fittings Leak, November 22, 2010. -

AR 2010-12912, Leakage at Various Components during RHR

VT-2 Inspections, November 17, 2010 -

AR 2010-9182, Missing Weld Data on CVCS Vent Line Weld during U2C18, September 13, 2010 -

AR 2011-11103, Reactor Vessel Upper Head Examination Results, September 28, 2011 -

AR 2011-11127, Boric Acid Date Sheet 1 Evaluations not Retrievable, September 28, 2011 -

AR 2011-11130, NRC Identified Liquid Penetrant Examination Concerns, September 28, 2011 -

AR 2011-11191, Reportable Indications Noted During ISI PT Examination, September 29, 2011 -

AR 2011-11316, Foreign Objects Discovered on the Secondary Side of

SG 12, October 1, 2011 -

AR 2011-11394, Seven Foreign Objects were Discovered in the Tubesheet Area in

SG 13 during Remote Secondary Side Inspections, October 4, 2011 -

AR 2011-11547, Step Change in Steam Generator Eddy Current Indication Count, October 5, 2011 -

AR 2011-11552, Lack of Detailed Evaluation of Unsupported Piping, October 5, 2011 -

AR 2011-11572, Wrong ASME XI Code Table Referenced in ISI Evaluation, October 5, 2011

Attachment -

AR 2011-2165, 2-ICM-265 Boric Acid Leak, February 18, 2011 -

AR 2011-9135, NRC Information Notice 2011-15, Steel Containment Degradation, August 11, 2011 - AR

GT 2011-11754, Documentation of As-Left SG Tube Plugging, October 11, 2011 - AREVA 51-9041323-003, DC Cook Unit 1 Final Steam Generator Condition Monitoring and Operational Assessment Evaluation for U1C21, October 5, 2010 - ASME Procedure Qualification Record number 136, WPS 8.1TS, Revision 1 - Cook Nuclear Plant Steam Generator Program Unit 1 Primary Side Integrity Plan, Revision 5 - Evaluation Report No. U1-EV-11-001/008, Evaluation of PT Indications on 1-SI-22-06F, September 30, 2011 -

PDI-UT-2, Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds, Revision E -

PMP-5070-ISI-002, Inservice Inspection Program Implementation, Revision 11, Pages 11-12 -

PO 01534635, Receipt Inspection of Safety-related/ Safety Interfaced Material and Equipment, CMTR, April 16, 2010 -

PO 01540327, Receipt Inspection of Safety-related/ Safety Interfaced Material and Equipment, CMTR, February 3, 2010 -

PO 01541405, Receipt Inspection of Safety-related/ Safety Interfaced Material and Equipment, CMTR, March 8, 2010 - PT Report No. C35884.06, PT Examination Report for 1-SI-71-02S-HL 1-8, March 13, 1997 - PT Report No. C35884-06, PT Examination Report for 1-SI-22-06F, March 13, 1997. - PT Report No. U1-PT-11-007, PT Examination Report for 1-SI-71-02S-HL 1-8, October 3, 2011 - PT Report No. U1-PT-11-008, PT Examination Report for 1-SI-22-06F, September 30, 2011. - UT Report 1C24_UT03, Ultrasonic Examination Report, September 29, 2011 - UT Report No. 1C24_UT04, Ultrasonic Examination Report, September 29, 2011 - UT Report No. 1C24_UT15, Ultrasonic Examination Report, October 3, 2011 - UT Report WN22-NS-1, Ultrasonic Examination of Weld No. 1-N3B, March 25, 2010 - UT Report WN247-NS-1, Ultrasonic Examination of Weld No. 1-N1A, March 25, 2010 - UT Report WN338-NS-1, Ultrasonic Examination of Weld No. 1-N2B, March 23, 2010 -

UT-95, Ultrasonic Examination of Austenitic Piping Welds, Revision 6 - VT Report U1-VT-11-026, Visual Examination for Boric Acid Detection Report, October 7, 2011 - Welder Performance Qualification Sheet

SNS 736, August 11, 2011 - Welder Performance Qualification

SNS-1161, August 24, 2011 - Welder Performance Qualification

SNS-1246, September 2, 2011 - Welder Performance Qualification

SNS-530, August 25, 2011 - Welder Performance Qualification

SNS-735, August 3, 2011 - Welding

PQR 136, February 10, 1976 - Welding

PQR 219, January 16, 1990 - Welding

PQR 256, August 7, 1989 - Welding

PQR 258, August 7, 1989 - WPS 1-8.1TS Welder Procedure Specification, Revision 4 - WPS 8.1TS Welder Procedure Specification, Revision 2 - 1-OHP-4021-002-005 RCS Draining, Revision 47 1R13 Maintenance Risk Assessments and Emergent Work Control - 1-OHP-4021-002-013 Reactor Coolant System Vacuum Fill - 1-OHP-4022-019-001 ESW System Loss/Rupture, Revision 7 - 2-OHP-4022-013-007, RCS RTD Instrument Malfunction, Revision 005

Attachment -

AR 2011-11416, 1-ICM-311 Has Open Pullout Thrust Above the Max Allowable -

AR 2011-11738, 1-NLI-1000 Tripped Off -

AR 2011-12123, 2-STN-340 is Clogging due to Excessive Debris -

AR 2011-13107, Unit 2 RCS Loop 3 Thot Channel Failed Low Momentarily -

AR 2011-13131, Belt has Come Off Unit 2 West Control Air Dryer Blower - Control Room Logs, October 6-7, October 10-14, October 17-18, November 8-9,

December 13-15, 2011 - Daily work activity schedule, October 6-7, October 10-14, October 17-18, November 8-9, December 13-15, 2011 - IPTE Briefing Guide for RCS Vacuum Fill, October 16, 2011 - IPTE Briefing Guide, Dual ESW Bay Cleaning, October 6, 2011 -

PMP-2291-OLR-001, Online Risk Management, Part 1, Configuration Risk Assessment, October 6-7, October 10-14, October 17-18, November 8-9, December 13-15, 2011 -

PMP-4100-SDR-001, Attachment 4, Shutdown Safety Contingency Planning Template, October 11, 2011 -

PMP-4100-SDR-001, Data Sheet 1, Schedule Change and Approval Form, October 9, 2011 -

PMP-4100-SDR-001, Plant Shutdown Safety and Risk Management, Revision 23 -

PMP-4100-SDR-002, Outage Risk Assessment and Management, Revision 0 - 1-EHP-4030-124-001 Data Sheet 1, October 21, 2001 1R15 Operability Evaluations - 1-EHP-4030-124-001 U1 Primary Containment Leak Rate Running Total, October 21, 2011 - 1-EHP-4030-195-249, Containment Divider Barrier Seal Surveillance Test, October 20, 2011 - 1-FCN-4458-R0-06, Field Change Notice for Installing Sealant on Divider Seal, Revision 0 - 1-OHP-4024-109 Drop 26, Annunciator 109 Response:

Boric Acid, Revision 14 - 12-MHP-4030-010-001, Ice Condenser Basket Weighing Surveillance, October 16, 2011 - 12-MHP-5021-010-002, Ice Condenser Ice Removal and Filling, October 16, 2011 - 12-MHP-5021-010-005, Ice Condenser Ice Baskets Removal, Inspection, Repair and Installation, October 16, 2011 - 2-TM-11-22-RO, Unit 2 CD Battery Ground Input Time Delay Temporary Modification, June 22, 2011 -

AR 2011-1485, 2CD Plant Battery Ground -

AR 2011-10279, U1C24 Aggregate Ice Basket Damage Evaluation -

AR 2011-11249, U1C24 failed LLRT 1-VCR-205 -

AR 2011-11393, Unable to Perform LLRT 025/026 Due to Leak by of 1-NSW-239-4 -

AR 2011-11748, Divider Barrier Seal Bar is Welded to the Stud -

AR 2011-11878, Divider Barrier Seal Configuration Does Not Match Surveillance Configuration -

AR 2011-11995, Minor Deficiencies Identified on Divider Barrier Seal U1C24 -

AR 2011-12314, 1-NCR-109 and 1-NCR-110 LLRT Greater Than Administrative Limit -

DCP 4458, Install New Divider Barrier Seal, Revision 0 -

PS-2-92044, Turbine Relay Panel Wiring Diagram, Revision 16 -

PS-2-91313, DC Distribution CAB's Battery CD Wiring Diagram, Revision 7 -

WO 55362068-01, Empty and Refill Ice Baskets Indentified By System Engineer and Repair Baskets as Required, October 15, 2011 - 12-MHP-5021-SCF-001, Scaffolding Guidelines, Revision 14 1R18 Plant Modifications -

1-3113A, Unit 1 ESW Pump Platforms Plan and Isometric View, Revision 1 -

1-5637E, Screen House Instrument Tubing Supply & Control Air, Revision 2

Attachment -

AR 00852461, Conduct Evaluation of Installed Platform vs. Seismic Calc -

AR 2011-14169, Engineering Eval of ESW Semi-Permanent Scaffold Interference -

AR 2011-14707, Unit 1 East and West ESW Semi Permanent Platform Impact -

AR 2011-5778, U1 ESW Platform Deviates From Approved Design -

AR 2011-6969, Interference Prevents Reinstallation of U1 West ESW Platform -

EC 49086, Unit 1 Essential Service Water Pump Platforms 7E and 7W, Revision 0 -

PMP-5020-RTM-001, Restraint of Transient Material, Revision 4 - 12-EHP-5074.MOV.002, Motor Operated Valve Setpoint Control, Revision 2 1R19 Post-Maintenance Testing - 12-MHP-5021-019-003, Essential Service Water Strainer Maintenance, December 14, 2011 - 12-OHP-4030-033-001, Supplemental Diesel Generator Testing, December 14, 2011 - 1-OHP-4021-032-001AB, DG1AB Operation, October 4, 2011 - 1-OHP-4030-132-027AB, AB Diesel Generator Operability Test, October 5, 2011 - 1-OHP-4030-132-217A, DG1CD Load Sequencing & ESF Testing, Revision 25 - 1-OHP-4030-156-017T, Turbine Driven Auxiliary Feed Water System Test, October 24, 2011 -

AR 2011-11501, 1AB EDG Trip on Air Chest Press Extreme High -

AR 2011-11544, Packing Follower on 1-WMO-717 Does Not Engage with Valve -

AR 2011-11690, PMT Completed Without Paperwork in Hand -

AR 2011-12364, 1-FRV-220 Failed Initial Closed Stroke Timing -

AR 2011-12525, Time Delay Relay Out of Spec -

AR 2011-13097, PMT Performed Without the hardcopy WOT in Hand -

AR 2011-14406, SDG 1 Failed to Start Due To Over Cranking -

AR 2011-14463, Supplemental Diesel Thermostat Wiring -

AR 2011-14539, PMT Performed Without Hardcopy in Hand - Control Room Logs for October 4, 2011 -

MD-12-ESW-073-N, PPM Evaluation of 1-WMO717 Packing Load, Revision 2 -

PMP-2010-PRC-003, Procedure and Work Instruction Use and Adherence, Revision 28 -

PMP-2291-WMP-001, Work Management Process Flowchart, Revision 17 -

PS-12-91703, SDG Diesel Generator Power Distribution Wiring Diagram, Revision 7 -

TDB-1-Figure 19.9, Diesel Generator Pot Settings, Revision 35 -

TDB-1-Figure-15.2, Safety-related Pump Inservice Test Vibration Reference, Revision 99 -

TDB-1-Figure-19.1, Power Operated Valve Stroke Time Limits, Revision 110 -

TDB-1-Figure-19.8, Safety-related Throttled Valves, Revision 27 -

WO 55242107-31, 1-QT-506 Inspect/Adjust Balance Chamber Pressure, October 24, 2011 -

WO 55269127-05, PMT for 1-PRV-1-AB Thru 1-PRV-4-AB Replacement, October 4, 2011 -

WO 55317901-02, 1-HE-47-ABS, PMT, October 4, 2011 -

WO 55342182-22, 1-OME-150-AB, PMT Testing, October 4, 2011 -

WO 55353602-05, 1-WMO-717, Perform Leak Inspection, October 6, 2011 -

WO 55363619-04, 1-FRV-220-VB, Ops Stroke, October 22, 2011 -

WO 55380904-04, Unit 2W ESW PMT, December 16, 2011 - 12-EHP-4050-FHP-301, Core Reload, Unit 1 Cycle 24 Core, Request # U1C24-9 1R20 Outage Activities - 1-OHP-4021-001-001, Plant Heatup From Cold Shutdown to Hot Standby, Revision 056 - 1-OHP-4021-001-002, Reactor Start Up, Revision 45 - 1-OHP-4021-002-005, RCS Draining, Revision 047 - 1-OHP-4021-001-006, Power Escalation, October 26, 2011

Attachment - 1-OHP-4021-002-013, Reactor Coolant System Vacuum Fill, Attachment 6, Vacuum Fill Contingencies, Revision 19 - 1-OHP-4030-001-002, Containment Inspection Tours, Revision 031 - 1-OHP-4030-127-041, Refueling Integrity, Revision 17 - 1-OHP-4030-127-037, Refueling Surveillance, Revision 14 - 1-OHP-4030-132-217A, DG1CD Load Sequencing & ESF Testing, Revision 24 -

AR 00083334, Dry Boric Acid on #2 RCP Flange Beneath Seal -

AR 2011-10304, Incomplete Fatigue Assessments -

AR 2011-10672, Boric Acid Leaks Identified in U1 Containment -

AR 2011-10705, Foreign Material Inside U1 Lower Containment -

AR 2011-10881, Steam Generators Snubbers Functional Testing -

AR 2011-11265, MTE Supervisor Violated Working Hours Requirement -

AR 2011-11416, 1-ICM-311 Has Open Pullout Thrust Above the Max Allowable -

AR 2011-11552, Lack of Detailed Engineering Evaluation of Unsupported Piping -

AR 2011-11591, Working Hour Limit Violation -

AR 2011-11629, Tripped 1CD EDG During Surveillance -

AR 2011-12240, Boric Acid Leaks, U1C24 300# Containment Leak Inspection -

AR 2011-12280, Boric Acid Leaks, U1C24

VT-2 Exam -

AR 2011-12301, T11D7 East CCP breaker failed timing per 1-OHP-4030-132-217A -

AR 2011-12357, Missile Block Lifting Lug Covers Need Screws -

AR 2011-133221, Unable to Find Completed Vacuum Fill Procedure -

AR 2011-13684, Inspect 1-PP-45-2 Main Flange -

AR 2011-9151, Third Quarter Boric Acid Walkdown 2011 -

DIT-S-06216-00, Unit 1 Cycle 23 End-of-Cycle Time to Boil Information, September 15, 2011 -

DIT-S-06218-00, Unit 1 Cycle 24 Beginning-of-Cycle Time to Boil Information, October 7, 2011 - DWG

1-5663, Unit 1 RCS Loop Details, Revision 11 -

ICP-01458, EDG Timing Relay Tolerances for 1-62-SIS-T11A8 & 1-62-SIS-T11D7, Revision 0 -

OHI-6100, RCS/PRZ Cooldown Record, September 21, 2011 -

PA-11-10, Fitness for Duty Performance Assurance Audit, October 12, 2011 -

PMP-2060-FFD-002, Performance of Fatigue Assessments, October 19, 2011 -

PMP-2110-CPS-001, Clearance Permit System, Revision 31 -

PMP-5030-001-001, Boric Acid Corrosion of Ferritic Steel Components and Materials, November 7, 2007 - TS 3.4.3, RCS Pressure and Temperature Limits - TS Bases 3.4.3, RCS Pressure and Temperature Limits - UFSAR Section 4.4.1, System Heatup and Cooldown Rates, Revision 21.2 - 1-EHP-4030-102-386 Multiple Rod Drop Measurements, Revision 11 1R22 Surveillance Testing - 1-EHP-4030-134-001, Unit 1 Primary Containment Leak Rate Running Total, October 21, 2011 - 1-OHP-4030-102-017, RCS Pressure Isolation Valves Leak Rate Surveillance Test, Revision 6 - 1-OHP-4030-156-017R, Auxiliary Feed Water Pump Response Time, October 24, 2011 - 2-OHP-4030-256-017E, East Motor Driven Auxiliary Feedwater System Test, November 10, 2011 -

AR 2011-10739, 1-SI-158-L2/L3 Is Exceeding the Leakage Limit -

AR 2011-12674, 1-WCR-962 Greater Than IST Max Limit - AR2011-11249, U1C24 Failed LLRT 1-VCR-205 - AR2011-11306, U1C24 Failed LLRT 1-CCW-243-25 - AR2011-11858, U1C24 As-Found LLRT Failure of 1-NS-357

Attachment - AR2011-12160, 1-R-157 Failed AF LLRT - AR2011-12314, 1-NCR-109 and 1-NCR-110 LLRT Greater Than Administrative Limit -

EHI-5300, DC Cook Nuclear Plant Containment leakage Rate Testing Program (Appendix J), Revision 7 -

OHI-4016, Conduct of Operations Guidelines -

TDB-1-Figure-15.1, Safety-related Pump Inservice Test Hydraulic Reference, Revision 121 -

TDB-1-Figure-19.1, Power Operated Valve Stroke Time Limits, Revision 110 -

WO55390806-04, 1-SI-158-L3 Perform Leak Inspection (PMT) -

WO55390811-04, 1-SI-158-L2 Perform Leak Inspection (PMT) - 2nd and 3rd Quarter 2011 Trend Reports 4OA2 Identification and Resolution of Problems -

AR 2011-0758, Cognitive Trend on Increase in MRULE Functional Failures -

AR 2011-14579, Trend Evaluation Deficiencies -

AR 2011-5342, Potential Trend with E8t Code -

AR 2011-9659, AFP Tube Plugging and FME -

AR 2011-9727, Adverse Trend: E3s2-Hoses/Tubing - Control Room Deficiencies sorted by Online/Outage, December 22, 2011 -

PMP-2291-WMP-001, Work Management Process Flowchart, Revision 17 -

PMP-7030-TND-001, Trend Analysis, April - September 2011 - Supplemental Diesel Generator Maintenance Rule Scoping Document, May 24, 2007 - Two-Year Unavailability Report for the Supplemental Diesel Generator System, December 12, 2011 - Unit 1 and Unit 2 Operator Burden Reports, December 21, 2011 - 1-OHP-4021-011-001, At Power Operation Including Load Swings, Revision 27 4OA3 Followup of Events and Notices of Enforcement Discretion - 1-OHP-4022-001-006, Rapid Power Reduction Response, November 25, 2011 - 1-OHP-4022-055-001, Loss of One Main Feed Pump, November 25, 2011 - 2-OHP-4021-028-001, Containment Ventilation, Data Sheet 1, Containment Air Temperature Monitoring, November 29, 2011 - 2-OHP-4022-028-001, Loss of Containment Chilled Water, November 29, 2011 -

AR 2011-130964, Received East MFPT Pump Thrust Bearing Hi Wear Alarm -

AR 2011-13616, South Heater Drain Pump Trip -

AR 2011-13813, Loss of Power to Transformer 7 -

AR 2011-13833, Procedure Deviation Used for Loss of Containment Cooling Abnormal -

AR 2011-13837, Containment Cooling Bus Undervoltage Alarm Failed to Alarm -

AR 2011-13910, Containment Chilled Water System Procedure Enhancements -

MD-12-HV-049-N, Revised Lower Containment Temperature Measurement Methodology, Revison 2 - NEI Position Statement, Guidance to Licensees on Complying with the Licensed Power Limit, Revision 0 -

OHI-4000, Conduct of Operations: Standards, Revision 63 -

OHI-4023, Abnormal/Emergency Procedure Users Guide -

RIS 2007-21, Adherence to Licensed Power Limits, Revision 1 - Safety Evaluation Regarding Endorsement of NEI Guidance for Adhering to the Licensed Thermal Power Limit, October 8, 2008

Attachment

LIST OF ACRONYMS

USED [[]]

ADAMS Agencywide Document Access Management System

ASME American Society of Mechanical Engineers

CAP Corrective Action Program

CFR Code of Federal Regulations

EDG Emergency Diesel Generator

ET Eddy Current

IMC Inspection Manual Chapter

ISI Inservice Inspection

IP Inspection Procedure

NCV Non-Cited Violation

NRC [[]]

U.S. Nuclear Regulatory Commission

OCC Outage Command Center

OSP Outage Safety Plan

PARS Publicly Available Records System

PT Liquid Dye Penetrant

RCS Reactor Coolant System

RFO Refueling Outage

SDP Significance Determination Process

SG Steam Generator

TS Technical Specification

UFSAR Updated Final Safety Analysis Report

UT Ultrasonic Examination

L. Weber -2- 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 (PARS) component of

NRC 's Agencywide Document Access and Management 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/

John

B. Giessner, Branch Chief Branch 4 Division of Reactor Projects Docket Nos. 50-315; 50-316 License Nos.

DPR-58; DPR-74

Enclosure: Inspection Report 05000315/2011005 and 05000316/2011005 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ

DOCUME [[]]

NT [[]]

NAME G:\

DRPIII \COOK\DC 2011 005.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy

OFFICE [[]]

RIII [[]]

NAME [[]]

JG iessner:dtp

DATE 01/30/12

OFFICI AL

RECORD [[]]

COPY Letter to

L. Weber from J. Giessner dated January 30, 2012.

SUBJEC T:

D. C.

COOK [[]]

NUCLEA R

POWER [[]]

PLANT ,

UNITS [[]]

1 AND 2 -

NRC [[]]

INTEGR [[]]

ATED [[]]

INSPEC [[]]

TION [[]]

REPO [[]]

RT 05000315/2011005 and 05000316/2011005