IR 05000263/2011005
| ML12032A263 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/01/2012 |
| From: | Riemer K R NRC/RGN-III/DRP/B2 |
| To: | O'Connor T J Northern States Power Co |
| References | |
| IR-11-005 | |
| Download: ML12032A263 (58) | |
Text
February 1, 2012
Mr. Timothy Site Vice President Monticello Nuclear Generating Plant Northern States Power Company, Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT: MONTICELLO NUCLEAR GENERATING PLANT - NRC INTEGRATED INSPECTION REPORT 05000263/2011005
Dear Mr. O'Connor:
On December 31, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Monticello Nuclear Generating Plant. The enclosed report documents the inspection findings, which were discussed on January 11, 2012, 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. Two NRC-identified and three self-revealed findings of very low safety significance were identified during this inspection. Five of these findings were determined to involve violations of NRC requirements. Additionally, the NRC has determined that a traditional enforcement Severity Level IV violation occurred.
This traditional enforcement violation was identified with an associated finding. Further, licensee-identified violations which were determined to be of very low safety significance are listed in this report. 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 Monticello Nuclear Generating Plant. 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 Monticello Nuclear Generating Plant. 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/
Kenneth Riemer, Branch Chief Branch 2 Division of Reactor Projects Docket No. 50-263 License No. DPR-22
Enclosure:
Inspection Report 05000263/2011005
w/Attachment:
Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-263 License No: DPR-22 Report No: 05000263/2011005 Licensee: Northern States Power Company, Minnesota Facility: Monticello Nuclear Generating Plant Location: Monticello, MN Dates: October 1 through December 31, 2011 Inspectors: S. Thomas, Senior Resident Inspector P. Voss, Resident Inspector R. Walton, Inspector, DRS C. Zoia, Inspector, DRS M. Munir, Reactor Inspector K. Stoedter, Prairie Island Senior Resident Inspector P. Zurawski, Prairie Island Resident Inspector J. Beavers, Emergency Preparedness Inspector M. Phalen, Senior Health Physicist, DRS S. Bell, Health Physicist, DRS
Approved by: K. Riemer, Branch Chief Branch 2 Division of Reactor Projects Enclosure
SUMMARY OF FINDINGS
........................................................................................................... 1
REPORT DETAILS
....................................................................................................................... 5 Summary of Plant Status
REACTOR SAFETY
....................................................................................................... 5
1R01 Adverse Weather Protection
............................................................. 5
1R04 Equipment Alignment
........................................................................ 6
1R05 Fire Protection
.................................................................................. 7
1R06 Flooding
............................................................................................ 7
1R11 Licensed Operator Requalification Program
..................................... 8
1R12 Maintenance Effectiveness
............................................................. 11
1R13 Maintenance Risk Assessments and Emergent Work Control
....... 12
1R15 Operability Determinations and Functional Assessments
.............. 14
1R18 Plant Modifications
.......................................................................... 16
1R19 Post-Maintenance Testing
.............................................................. 16
1R20 Other Outage Activities
................................................................... 17
1R22 Surveillance Testing
....................................................................... 23
1EP4 Emergency Action Level and Emergency Plan Changes
RADIATION SAFETY
................................................................................................... 25
2RS8 Occupational Dose Assessment
OTHER ACTIVITIES
..................................................................................................... 27
4OA1 Performance Indicator Verification
....................................................... 27
4OA2 Identification and Resolution of Problems
........................................... 28
4OA3 Follow-Up of Events and Notices of Enforcement Discretion
.............. 31 4OA6 Management Meetings ...................................................................................... 37 4OA7 Licensee-Identified Violations ........................................................................... 38
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- T. O'Connor, Site Vice President
- J. Grubb, Plant Manager
- W. Paulhardt, Operations Manager
- N. Haskell, Site Engineering Director
- K. Jepson, Assistant Plant Manager
- S. Radebaugh, Maintenance Manager
- M. Holmes, Chemistry Manager
- A. Zelie, Radiation Protection Manager
- P. Kissinger, Regulatory Affairs Manager
- J. Sternisha, Corporate General Manager - Training
- M. Peterson, Corporate General Supervisor - Simulators
- P. Norgaard, Supervisor Operations Continuing Training
- G. Holthaus, Sr. Emergency Preparedness Coordinator
Al Zelie, Radiation Protection Manager
- S. O'Connor, Regulatory Affairs Analyst
Nuclear Regulatory Commission
- K. Riemer, Chief, Reactor Projects Branch 2
Attachment
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened
- 05000263/2011005-01 NCV 'E' Condensate Demineralizer Alarm Response Procedure Limits Exceeded (Section 1R13)
- 05000263/2011005-02 NCV Inadequate Completion of CAPRs Associated with 2RS to 2R Feeder Cable Testing (Section 1R20.1)
- 05000263/2011005-03 NCV Rod Worth Minimizer Inoperable During Reactor Plant Startup (Section 1R20.2)
- 05000263/2011005-04 NCV Failure to Properly Block and Brace a Radioactive Package for Transport (Section 2RS8)
- 05000263/2011005-05 NCV Failure to Make a Required 60 Day Event Report Per 10 CFR 50.73(a)(2)(vii)(A-D) (Section 4OA3.5)
- 05000263/2011005-06 FIN Failure to Make a Required 60 Day Event Report Per 10 CFR 50.73(a)(2)(vii)(A-D) (Section 4OA3.5)
Closed
- 05000263/FIN-2011005-01 NCV 'E' Condensate Demineralizer Alarm Response Procedure Limits Exceeded (Section 1R13)
- 05000263/FIN-2011004-01 URI NOED for Emergency Diesel Generator Load Rejection Surveillance Requirement 3.8.1.7 (Section 1R15.2)
- 05000263/FIN-2011005-02 NCV Inadequate Completion of CAPRs Associated with 2RS to 2R Feeder Cable Testing (Section 1R20.1)
- 05000263/FIN-2011005-03 NCV Rod Worth Minimizer Inoperable During Reactor Plant Startup (Section 1R20.2)
- 05000263/FIN-2011005-04 NCV Failure to Properly Block and Brace a Radioactive Package for Transport (Section 2RS8)
- 05000263/FIN-2011004-03 URI Shipping and Transportation of a Radioactively Contaminated Condensate Demineralizer Vessel
(Section 2RS8)
- 05000263/LER-2011-006 LER Intake Structure Fire Suppression System Blockage (Section 4OA3.3)
- 05000263/FIN-2011005-05 NCV Failure to Make a Required 60 Day Event Report Per 10 CFR 50.73(a)(2)(vii)(A-D) (Section 4OA3.5)
- 05000263/FIN-2011005-06 FIN Failure to Make a Required 60 Day Event Report Per 10 CFR 50.73(a)(2)(vii)(A-D) (Section 4OA3.5)
- 05000263/LER-2011-007 LER Both Emergency Diesel Generators Declared Inoperable Due to Inadequate Surveillance (Section 4OA3.5)
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.
- Section 1R01 1151; Winter Checklist; Revision 70 C.4-B.08.03.A; Loss of Heating Boiler; Revision 8
- Section 1R04 2154-13; RCIC System Prestart Valve Checklist; Revision 25 2121; Plant Prestart Checklist RCIC System; Revision 14
- NH-36251; RCIC (Steam Side); Revision 78
- NH-36252; RCIC (Water Side); Revision 77
- B.02.03-05; RCIC - System Operation; Revision 24 B.02.03-01; RCIC - Function and General Description of System; Revision 5 B.08.13-06; Control Room Heating and Ventilation and
- EFT-Figures; Revision 7
- B.08.13-03; Control Room Heating and Ventilation and
- EFT-Instrumentation and Controls;
- Revision 13
- B.08.13-05; Control Room Heating and Ventilation and EFT- System Operation; Revision 20 0466-02; 'B' EFT Filter Efficiency and Leak Tests; Revision 34
- CAP 01273527; V-EAC-14A high discharge pressure
- B.08.13-01; Control Room Heating and Ventilation and EFT- Function and General Description of System; Revision 10
- B.08.13-02; Control Room Heating and Ventilation and
- EFT-Description of Equipment; Revision 9
- NH-170037; Main Control Room CRV/EFT System; Revision 80 Section 1R05 Pre-Fire Strategy A.3-16; Corridor, Turbine Building East & West (Elevations 911' and 931'); Revision 11
- Pre-Fire Strategy A.3-17; Turbine Building North Cable Corridor 941; Revision 5
- Pre-Fire Strategy A.3-29; Security Diesel Building; Revision 6
- Pre-Fire Strategy A.3-8; Cable Spreading Room; Revision 12 Pre-Fire Strategy A.3-33; EFT Building Third Floor; Revision 6 Section 1R06
- CA-07-029; Reactor and Turbine Building & Intake Structure Water Height for Internal Flooding
- CA-07-021; Reactor Building, Turbine Building & Intake Structure Water Height - Internal Flooding
- CA-07-018; Service Water Break Flow Calculations
- CA-06-084; Fire Protection Break Flow Calculation for Postulated Internal Flooding Scenarios
- PRA-CALC-04-001; Flood Areas
- PRA-CALC-04-003; Flood Source Identification Attachment
- PRA-CALC-04-004, Flood Initiating Event Frequencies
- PRA-CALC-04-005; Equipment Vulnerabilities to Flooding
- PRA-CALC-04-006; Flood Scenarios and Effects Section 1R11
- FP-T-SAT-60; Systematic Approach to Training Overview; Revision 11
- FP-T-SAT-71; NRC Exam Security Requirements; Revision 7
- FP-T-SAT-80; Simulator Configuration Management; Revision 6
- FP-T-SAT-81; Simulator Testing and Documentation; Revision 6
- FP-OP-CTC-01; Control of Time Critical Operator Actions; Revision 2
- OWI-01.08; NRC License Maintenance Responsibilities; Revision 16
- OWI-03.07; Time Critical Operator Actions; Revision 1
- QF-1081-01; Simulator Performance Test Procedure; Revision 2 M9100 LOR Biennial Training Plan 2010/2011; Revision 0
- MT-LOR-1D-002L; License Maintenance; October 6, 2011
- MT-LOR-JIT-005S; Power Restoration from 45 Percent Power; August 5, 2011
- MT-LOR-JIT-003S; Startup JITT
- AR 1247711; >25 Percent LOR Crew Failure; November 4, 2010
- JPM C.4-1-002; Revision 1
- JPM B.09-13-007; Revision 0
- Simulator Exercise Guide
- RQ-SS-120; Revision 0 Simulator Exercise Guide
- RQ-SS-121; Revision 0 Various LOR Feedback Summaries Various Remedial Training Packages 2010-2011
- Various NRC License Status Reports 1Q2009
- Various SWO's 2010 - 2011 Various AR's 2010 - 2011 NOS Quarterly Assessment Reports, 3rd Quarter 2010; 1st Quarter 2011; 2nd Quarter 2011 Monticello Simulator Annual Certification Report; 1996, 1999
- Simulator Transient Performance Test 2003; Reviewed February 19, 2004
- Simulator Core Tests, Cycle 25; 2010
- Simulator Annual Performance Tests, Cycle 25, 2010 - Transient Tests - Steady State Performance Test - Repeatability Test - Real-time Test Simulator Performance Test Procedure, Scram No. 119; March 15, 2007 Simulator Certification, "Four Year Simulator Certification Report"; January 27, 1999 Action Request
- 0130747; Simulator Deviation Form Paperwork not Completed Correctly;
- October 5, 2011
- Attachment Section 1R12
- AR 01232295; 16 Air Compressor Accruing Maintenance Rule Unavailability due to 16 Dryer Issue; November 18, 2010
- AR 01237553; 16 Air Compressor Maintenance Rule Unavailability Red; October 16, 2010
- AR 01250179; Operator Burden Tracking GAR; September 17, 2010
- SW-125-1 Difficult to Operate; September 20, 2010
- AR 01254974; 12 Motor Generator Set Oil Cooler has High Vibrations; October 21, 2010
- ES-8 Controller Communication Error with 17 Air Compressor; October 23, 2010
- AR 01255460; Unable to Meet Schedule due to Problems with 17 Air Compressor;
- October 24, 2010
- AR 01261895; Valves
- SW-125-1 and
- SW-125-2 Require Frequent Replacement; December 8, 2010
- AR 01262514; Air Compressor 17 Low Oil Level Following Preventive Maintenance;
- December 10, 2010
- AR 01264496; Device Installed without Temporary Modification Processed; December 29, 2010
- AR 01273017; Oil Level Low on 17 Air Compressor; February 28, 2011
- AR 01279330; Low Suction and Discharge Pressure on Cooling Skid for K-1G; April 6, 2011
- AR 01289993; Evaluate Adverse Trend with Air Compressor Cooling Pumps; August 25, 2011
- SW-125-1 Leaking by Badly; August 31, 2011
- AR 01303250; 17 Air Dryer Inlet and Exhaust Valve Assembly Fails to Cycle;
- September 11, 2011
- AR 01308110; Coolant Pump Suction Pressure is Low for 16 Air Compressor; October 13, 2011
- FP-E-SE-02; Component Classification; Revision 6
- Maintenance Rule (a)(1) Action/Performance Improvement Plan; S-122 - 16 Air Dryer and
- K-1F - 16 Air Compressor; September 29, 2010
- Monticello Maintenance Rule Program Basis Document; Reactor Recirculation System;
- Revision 0 Monticello Maintenance Rule Program Basis Document; Service Water System; Revision 2
- NH-36041; Piping and Instrumentation Drawing for Service Water System; Revision N
- Operations Manual Section B.08.04.01; Instrument and Service Air; Revision 10
- WO 416725; 12 Motor Generator Set Oil Cooler Valve has High Vibrations; July 30, 2011
- SW-125-1 Fully Closed Water Leaking by Seat Badly; October 17, 2011
- WR 72391; Disassemble and Inspect Valve
- SW-125-2; September 28, 2011
- Section 1R13
- Operation Manual, B.08-05; Fire Protection
- CAP 01312079; Maximum Differential Pressure Exceeded for T-7E C.6-080-DPAH-2215; Vessel T-7E D/P High; Revision 0 B.06.06-05, Part C; Placing Flow Indicating Controller in Automatic and Setpoint; Revision 29
- QF-0571; Troubleshooting Plan-Reactor Scram during Turbine Generator Quarterly Testing
- 1040-01; Turbine Generator Quarterly Steam Turbine Inspection Report-Front Standard Inspection for Monticello Nuclear Plant, Unit 1; November 5, 2007
- Monticello Front Standard Inspection-Initial Findings; December 1, 2011
- 2 MN Turbine Monticello Nuclear Plant Reactor Scram Report; June 25, 1973
- Attachment
- WO 00446169; Troubleshooting WO for Control Valve Fast Closure Relay
- WO 00446481; Disassemble/Inspect turbine Front Standard Components
- NX-8435-150-2; Turbine Control Diagram; Revision 79
- NX-8435-150-1; Turbine Control Diagram; Revision 80
- Section 1R15
- CAP 01308390; SR 3.3.2.1 May not be Using an Independent Channel
- EC 18939; Revise Channel Check Criteria for Selected ASDS Instruments; October 20, 2011
- SCR 11-0478; Revised Select ASDS Instrument Channel Check Criteria; Revision 0
- OSP-MSC-0573; Miscellaneous Operations Monthly Surveillances; Revision 6 0000-E; Operations Daily Log-Part E Completed 10-16-2011; Revision 92
- NH-94670; Suppression Pool Temperature Monitoring System Cable Scheme Division I& Division II
- 0452; Suppression Pool Temperature Monitoring System (SPOTMOS) Instrument Calibration White Paper for Surveillance Procedure
- OSP-MSC-0573 Operability Discussion;
- October 19, 2011
- CAP 01309248; Clarification of Daily Rounds 0000-E Step 1 may be Warranted
- CAP 01312380;
- CRD-111/50-31 has Excessive Steam Leakage
- CRD-111/50-31 has Excessive Steam Leakage Section 1R18
- WO 371354-23; Install T-Mod for Keep Fill
- EC 18936; Furmanite Leak Seal for
- CV-6-13
- EC 18988; Bypass Interlock
- POS-2375 for 11 Reactor Feedwater Pump
- WO 00444230-09; Install TMOD for
- LY-4107, Found Out of As-Found Tolerance
- ISP-ASD-0574; Reactor Flooding Level Instrument Channel Calibration; Revision 3
- AWI-04.05.06; Post-Maintenance Testing; Revision 18
- WO 00444229; Raw Water Alarm Rec. on 11 EDG during Scram-Replace Pump; October 24, 2011
- NX-9525-21; Emergency Service Water Pumps P111A & P111B; Revision 76
- CAP 01307712; Received Unexpected Annunciator
- WO 00444232; 13 Bus Failed to Re-energize; October 24, 2011
- CAP 01309399; 13 Bus Failed to Re-energize
- NE-36399-6; 1R Transformer SEC
- ACB 152-302 Control; Revision L
- NX-7823-4-4; Primary Containment Isolation System
- NX-7834-67-7; Reactor Protection System
- NF-100338; RPS Channel A1 Analog Trip Cabinet C-304A Elementary Diagram
- WO 378987-01; Replace K61A and K62A Agastat Relays Work Plan
- 378987-01; Replace K61A and K62A Agastat Relays; Revision 17
- WO 378987-01; Post Maintenance Testing and Return To Service Instructions; Revision 5
- WO 393055-02; Replace K61C and K62C Agastat Relays Attachment
- Work Plan
- 393055-02; Replace K61C and K62C Agastat Relays; Revision 6
- WO 378987-01; Post Maintenance Testing and Return To Service Instructions; Revision 5
- Section 1R20
- CAP 01309402; 2R Transformer Lockout
- CAP 01151583; Cable Condition Monitoring Program Ineffective
- CAP 01151315; Water Found in Manhole Containing Cables for 2R Transformer
- CAP 01151402; Cable to 2R Transformer Not In Cable Monitoring Program
- CAP 01314953; Ops Crew Failed to Recognize RWM Bypassed before Mode Change C.1; Startup Procedure; Revision 71 0074; Control rod Drive Exercise; Revision 55
- 212; Rod Worth Minimizer Operability Test; Revision 28
- 2150; Plant Prestart Checklist; Revision 39
- CAP 01309460;
- CAP 01309400; Turbine Bypass Valve Position Indication Failed
- WO 00446169; Troubleshooting WO for Control valve Fast Closure Relay
- WO 00446481; Disassemble/Inspect Turbine Front Standard Components
- Section 1R22
- OSP-EDG-053-12; EDG Load Test; Revision 0 L-MT-11-062; Request for Enforcement Discretion to Allow for Performance of EDG Load Reject Testing in Accordance With a Revised Surveillance Test Methodology; October 3, 2011
- OSP-EDG-053-11; EDG Load Test; Revision 1
- M9112L-09A-005; Power Range Neutron Monitor; Revision 0
- ISP-NIP-0586; 2-of-4 Voter Channel Functional Test; Revision 3
- 0032 ECCS Pump Start Permissive Sensor; Revision 19
- CAP 1143424; Preconditioning Question with Instrument Test/Cal Process
- CAP 1246324; Station Review of NRC IR Finding
- 2009004-01
- EC 15214; Acceptable Preconditioning of Select Pressure Switches; January 5, 2010
- 0051; Main Steam Line High Flow Group I Instrument Test; Revision 29
- Operations Manual B.02.04-01; Main Steam-Function and General Description of System; Revision 9 Operations Manual B.02.04-03; Main Steam-Instrumentation and Controls; Revision 8
- Attachment Section 1EP4 Monticello Emergency Plan; Revision 35 A.2-101; Classification of Emergencies; Revision 44
- A.2-201; On-Site Protective Action; Revision 17
- A.2-208; Core Damage Assessment; Revision 9 A.2-406; Off-Site Dose Projection; Revisions 22 and 23 A.2-504; Emergency Communicator Duties in the TSC and OSC; Revision 13
- A.2-801; Responsibilities of the Emergency Manager; Revision 14
- A.2-802; Activation and Operation of the EOF; Revision 13
- A.2-803; Emergency Communications at the EOF; Revision 10 A.2-807; Off-Site Dose Assessment and Protective Action Recommendations; Revision 20
- Section 4OA1 Monticello MSPI Derivation Report; Residual Heat Removal System; Unavailability Index, Unreliability Index, and Performance Limit Exceeded; November 4, 2011
- Monticello MSPI Derivation Report; Cooling Water System; Unavailability Index, Unreliability Index, and Performance Limit Exceeded; November 4, 2011
- CAP 01221333;
- MO-2009 Failed to Properly Operate during Procedure 1381
- CAP 01289462;
- BKR 152-503 (13 RHR pump) Failed to close
- CAP 01288036; Unplanned TS Action No. 13 RHR pump Unit Log Entries-RHR System; 4th Quarter 2010 through the 3rd Quarter 2011
- Unit Log Entries-RHRSW System; 4th Quarter 2010 through the 3rd Quarter 2011
- PRA-CALC-05-003; MSPI Basis Document; Revision 2
- SE-0455 Maintenance Rule Search-RHR System; 4th Quarter 2010 through the
- 3rd Quarter 2011
- SE-0455 Maintenance Rule Search-RHRSW System; 4th Quarter 2010 through the
- 3rd Quarter 2011
- NH-36246; Residual Heat Removal System; Revision 80
- NH-36247; Residual Heat Removal System; Revision 81
- FG-PA-KPI-01; PI Data Reporting; Revision 00
- FP-PA-PI-02; NRC/INPO/WANO PI Reporting; Revision 06
- QF-0445; NRC/INPO/WANO Data Collection and Submittal Forms; various dates Section 4OA2
- FP-OP-OL-01; Operability / Functionality Determination; Revision 9
- CAP 01309709; Items Identified by NRC on
- SC 11-05 Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guide
- SC 11-05; GEH Part 21 Communication-Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance; September 26, 2011
- Operator Burden Reports; October 26, 2011
- Outage Mode Change Reports; October 27, 2011
- OBD/OBN Status Reports; October 26, 2011 Open Operational Decision Making Issues; October 26, 2011
- CAP 00826605; GE Part 21 Notice (SC05-03) - Potential to Exceed Low Pressure TS Safety Limit Attachment
- CAP 01173169; Revise Technical Specifications for Core Spray
- CAP 01177862; Figure 3.4.9-1 of Technical Specifications is Non-Conservative
- CAP 01257284; Track the Revision of this Issue:
- 1973 HELB
- CAP 01263913;
- MO-2035, Incorrect Voltage Used in
- MOV-2035 Calculation
- CAP 01307211; Fire Fighting Strategy A.3-17 Fire Zone 17 Question
- CAP 01309006;
- CRD-101/30-43, Drv Insert Riser Isol Valve is Leaking Water Trend CAPs; dated July 2011 through December 2011
- Monticello Performance Improvement and Sustainability Plan; Revision 1
- CAP 1308257; BOS Finding: Ineffective Use of Site DRUM to Detect Decline
- CAP 1276336; Adverse Trend in Outage Tagging
- FP-PA-OE-01; Operating Experience Program; Revision 16
- AWI-04.08.18; Performance Assessment Site Trending Program; Revision 0
- FG-PA-DRUM-01; Department Roll-Up Meeting manual-Department Performance Trending; Revision 12
- Performance Assessment Review Board Meeting Package; 12-6-2011
- CAP 01288446; Adverse Trend in Equipment Performance during Rx Startup
- CAP 01311051; Potential Adverse Trend in Unplanned LCO Entries
- CAP 01316075; Adverse Trend in Ops Performance
- CAP 01302978; Limited Support for Operating Experience Screen Team
- SAR 01294995; Department Roll-Up Meeting Results - Maintenance; 3rd Quarter 2011 Department Roll-Up Meeting Results - RP; 3rd Quarter 2011 Department Roll-Up Meeting Results - Capital Projects and Major Projects (EPU);
- 3rd Quarter 2011 Department Roll-Up Meeting Results - Engineering; 3rd Quarter 2011
- GAR 01300114; Department Roll-Up Meeting Results - Operations; 1st Quarter 2011
- GAR 01300114; Department Roll-Up Meeting Results - Operations; 2nd Quarter 2011
- SAR 01294995; Department Roll-Up Meeting Results - Maintenance; 1st and 2nd Quarter 2011
- SAR 01249160; Site Roll-UP Meeting Results - 1st and 2nd Quarter 2010 Department Roll-Up Meeting Results -
- RP-Chem; 3rd Quarter 2010
- SAR 01264947; Department Roll-Up Meeting Results - Maintenance; 4th Quarter 2010
- GAR 01256195; Department Roll-Up Meeting Results - Operations; 3rd Quarter 2010
- GAR 01268016; Department Roll-Up Meeting Results - Operations; 4th Quarter 2010
- Operations Manual B.09.06-01; 4.16 KV Station Auxiliary; Revision 10
- CAP 01309402; 2R Transformer Lockout
- CAP 01309399; 13 Bus Failed to Re-energize
- CAP 01307712; Received Unexpected Annunciator
- CAP 01309400; Turbine Bypass Valve Position Indication Failed Operations Manual C.1; Startup Procedure; Revision 70
- Attachment 2300; Reactivity Adjustment; Revision 5 2300 Attachment 1; Reactivity Management Plan; October 27, 2011
- CAP 01310321;
- PS-1177A did not Reset during Startup
- CAP 01310324; No. 1 BV Drifted Open while on PRO
- NF-36298-1; Rev 97; Electrical Single Line
- NF-36397; Rev Y; Meter & Relay Diagram
- NE-36399-6; Rev L; 1R Transformer Sec
- ACB 152-302 Control
- NE-36442-2; Rev 82; Generator Lock Out and Auto Transfer
- NE-36399-4B; Rev H; 2R Transformer Sec
- ACB 152-301 Control
- NE-36399-3; Rev J; 4.16 KV 2R Aux Tran Lockout Relay
- NE-36401-2; Rev V; Reactor Feed Pump P-2A
- ACB 152-104 Control
- NE-36404-3; Rev 76; Recir Pump MG Set
- ACB 152-103 Control
- NE-36394-2; Rev 76; Circulating Water Pump
- ACB 152-305
- NE-36399-2; Rev N; Auxiliary and Reserve Transformers
- NE-36399-3A; Rev J; Nos. 12 and 13 4.16 KV Lockout Relay
- WO 00444232 09; 13 Bus Failed to Re-energize; October 24, 2011
- WO 00444232 03; 13 Bus Failed to Re-energize; October 23, 2011
- WO 00444232 06; 13 Bus Failed to Re-energize; October 24, 2011 Vendor Manual for GE Magneblast Circuit Breaker Cable Testing Data Vendor Manual for Bus under Voltage Relay & Synch Check Relay
- CAP 01313496; Workers Entered Area Protected by Two Clearances While on One
- QF-0428; Human Performance Event Investigation Tool (HUEIT)-Missed 8-hour Notification; November 14, 2011 Operations Memo 11-64; New Narrative Log Standard Entries for 3.0.3 Entries;
- December 14, 2011
- CAP 01203212; Opportunities were Missed to Resolve Fire System Blockage
- CAP 01302334; Sprinkler Piping In Intake Plugged with Clay-Like Debris
- CAP 01180222; Intake Structure Sprinkler Blockage 0324; Fire Protection System - Sprinkler System Tests; Revision 44
- RCE 01302334; Intake Structure Fire Sprinkler Piping Blockage; October 6, 2011
- WO 00384321; Intake Sprinkler Test Valve Plugged; August 27, 2011
- CAP 1306107; Largest Post-accident Load Greater than in Test
- CAP 1304620 Observation- E1 Engineering In-progress Work Activity
- OSP-EDG-053-11; EDG Load Test; Revision 1
- OSP-EDG-053-12; EDG Load Test; Revision 0
- CAP 01305683; CDBI FSA- Question on Definition of Post Accident Load in TS Notice of Enforcement Discretion (NOED) 11-3-001:
- Monticello Request for Enforcement Discretion to Allow for Performance of EDG Load Reiect Testing In Accordance with a Revised Surveillance Test Methodology; October 3, 2011
- 5863; Dewatering Resins in High Integrity Containers; Revision 14
- AR 01294652; Radioactive Shipment Container Punctured during Transport; July 14, 2011 Assessment 2010-002-5; Radiological Protection Including Radioactive Waste Control; June 2010
- CRSD11-049; Energy Solutions Condition Report; Excel Energy MNGP 0726-07-0013 GSAP; July 14, 2011
- Attachment
- FP-RP-RW-02; Radioactive Shipping Procedure; Revision 03 Monticello Shipment Log Index; 2009, 2010 and 2011
- Northern States Power Response to NRC IE Bulletin 79-19; September 25, 1979 NOS Observation Report 2011-007; Radiation Protection Including Radioactive Waste Control; May 2011
- Ops Manual B.07.03-05; Processing of Phase Separators or Spent Resin Tank Using Centrifuge/Hopper Bypass to Radwaste
- RDS-100 Dewatering System Operation; Revision 16 Radioactive Material Shipment Package 09-46; April 2009
- Radioactive Material Shipment Package 10-11; March 2010 Radioactive Material Shipment Package 10-23; May 2010 Radioactive Material Shipment Package 10-35; July 2010
- Radioactive Material Shipment Package 11-54; April 2011
- Radioactive Material Shipment Package 11-127; July 2011
- R.11.07; Sampling and Analysis of Radioactive Resins; Revision 13 R.11.08; Selection and Entry of 10 CFR Part 61 Correlation Factors; Revision 08
- Attachment
LIST OF ACRONYMS
- USED [[]]
- CA [[]]
PR Corrective Action To Prevent Recurrence
CDF Core Damage Frequency
CFR Code of Federal Regulations
CRV Control Room Ventilation DOT Department of Transportation
- EC [[]]
EFT Emergency Filtration Train ESW Emergency Service Water
IMC Inspection Manual Chapter IEL Initiating Event Likelihood
IP Inspection Procedure
IR Inspection Report
kV Kilovolt
- LE [[]]
- LO [[]]
- MS [[]]
PI Mitigating Systems Performance Index
NCV Non-Cited Violation
- NO [[]]
- PA [[]]
RS Publicly Available Records System
- RC [[]]
IC Reactor Core Isolation Cooling
RP Radiation Protection
- RW [[]]
Attachment
SPAR Standardized Plant Analysis Risk SRA Senior Reactor Analyst
SSC Structure, System, and Component
USAR Updated Safety Analysis Report URI Unresolved Item
WO Work Order
T. O'Connor -2-
In accordance with
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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely,
/RA/
Kenneth Riemer, Branch Chief
Branch 2
Division of Reactor Projects Docket No. 50-263 License No. DPR-22
Enclosure: Inspection Report 05000263/2011005 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ