IR 05000263/2009004
Download: ML092990580
Text
October 26, 2009
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 AND POWER UPRATE REVIEW INSPECTION REPORT 05000263/2009004
Dear Mr. O'Connor:
On September 30, 2009, 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 October 8, 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. The findings involved violations 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. Additionally, three licensee-identified violations are listed in Section 4OA7 of this report. If you contest the subject or severity of a NCV, 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 Monticello Nuclear Generating Plant. 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 Monticello. 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 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), accessible from the NRC Web site 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. 50-263 License No. DPR-22
Enclosure:
Inspection Report 05000263/2009004
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: 05000263/2009004 Licensee: Northern States Power Company, Minnesota Facility: Monticello Nuclear Generating Plant Location: Monticello, MN Dates: July 1 through September 30, 2009 Inspectors: S. Thomas, Senior Resident Inspector L. Haeg, Resident Inspector J. Bozga, Reactor Engineer C. Brown, Reactor Engineer Observers: J. Corujo-Sandin, Reactor Engineer
Approved by: Kenneth 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
.............................................................3
1R04 Equipment Alignment
........................................................................4
1R05 Fire Protection
...................................................................................4
1R06 Flooding
.............................................................................................5
1R11 Licensed Operator Requalification Program
......................................6
1R12 Maintenance Effectiveness
...............................................................7
1R13 Maintenance Risk Assessments and Emergent Work Control
..........7
1R15 Operability Evaluations
......................................................................8
1R18 Plant Modifications
............................................................................9
1R19 Post-Maintenance Testing
...............................................................10
1R22 Surveillance Testing
........................................................................10
1EP6 Drill Evaluation
................................................................................14
4OA1 Performance Indicator Verification
.......................................................14
4OA2 Identification and Resolution of Problems
............................................16
4OA3 Follow-Up of Events and Notices of Enforcement Discretion
...............17
4OA5 Other Activities...................................................................................................22 4OA6
Management Meetings......................................................................................23 4OA7 Licensee-Identified Violations............................................................................23
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- T. O'Connor, Site Vice President
- J. Grubb, Plant Manager
- N. Haskell, Site Engineering Director
- K. Jepson, Business Support Manager
- S. Sharp, Operations Manager
- S. Radebaugh, Maintenance Manager
- M. Holmes, Radiation Protection/Chemistry Manager
- G. Salamon, Acting Regulatory Affairs Manager
Nuclear Regulatory Commission
- K. Riemer, Chief, Reactor Projects Branch 2
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened
- 05000263/2009004-01 NCV Preconditioning of Safety Related Pressure Switches During Surveillance Testing (Section 1R22)
- 05000263/2009004-02 NCV Failure To Appropriately Implement TS 3.6.4.3 (Section 40A3)
Closed
- 05000263/FIN-2008004-02 URI Potential Pre-Conditioning of Pressure Instruments/Switches (Section 1R22)
- 05000263/FIN-2009004-01 NCV Preconditioning of Safety Related Pressure Switches During Surveillance Testing (Section 1R22)
- 05000263/FIN-2009004-02 NCV Failure To Appropriately Implement TS 3.6.4.3 (Section 40A3)
- 05000263/LER-2009-001-00 LER Containment Overpressure not Ensured in the Appendix R Analysis (Section 40A3)
- 05000263/LER-2009-001-01 LER Containment Overpressure not Ensured in the Appendix R Analysis (Section 40A3)
- 05000263/LER-2009-003-00 LER Main Steam Line 'B' Flow Isolation Instrumentation Inoperable Due to Leaking Equalizing Manifold Valve (Section 40A3)
- 05000263/LER-2009-004-00 LER Missed Technical Specification Action for Failed Technical Specification Surveillance on Standby Gas Treatment System (Section 40A3)
- 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 A.6; Acts of Nature; Revision 31 Operations Work Instruction (OWI)-01.04; Operations General Procedural Guidance; Revision 17 1444; Post Severe Weather Checklist; Revision 7 Section 1R04 2201; Plant Prestart Checklist
- CRV-EFT System; Revision 8 2154-23; RHR Service Water System Prestart Valve Checklist; Revision 30 2154-06; Standby Gas Treatment Prestart Valve Checklist; Revision 11 2154-23; Residual Heat Removal System Prestart Checklist; Revision 44 Section 1R05 Strategy A.2-19-A; Make-up Demineralizer Area; Revision 5 Strategy A.3-32-B; EFT Building Second Floor (Div II) Strategy A.3-04-E; Reactor Building Plenum Strategy A.3-15-A; NO. 12 DG Room; Revision 7 Section 1R06
- EWI-08.19.01; Cable Condition Monitoring Program; Revision 1
- WO 378965; Inspection of Manholes for Water or Evidence of Water; Revision 1
- WO 376794; Perform Visual Inspection of Manhole Section 1R11 SEG
- RQ-SS-94
- Section 1R12
- CAP 01190374; 1AR Exceeded the Maintenance Rule Unavailability Time
- CAP 01198910; 1AR Maintenance Rule Unavailability Time Exceeded Unavailability Log for 1AR Transformer; March 2006 - September 2009 Monticello Maintenance Rule 4.16 kV Station Auxiliary Basis Document; Revision 7 Section 1R13 0011-A; Turbine Control Valve Fast Closure Scram Test and Calibration (>30% of Rated); Revision 11
- Attachment
- WO 385899; P-140A; 11 EPR Pump Discharge Filter Leak Operations Manual B.05.09-05; Main Steam Pressure Control; System Operation; Revision 10
- CAP 01192925;
- MO-2076; RCIC Steam Line Isolation Outboard 0255-08-IA-1; RCIC Quarterly Pump and Valve Tests; Revision 64
- MO-2076; RCIC Steam Line Isolation Outboard
- 253-01; SBGT 'A' Train Quarterly Test; Revision 39 Section 1R15
- CAP 01056182; Motor Terminal Voltages Could Drop Below 90% Rated
- II.05; Chemistry Limits & Sampling Frequencies; Revision 20
- CAP 01194499; CALC 96-080 and 97-044 Operator Action < 10 Minutes
- CAP 01086218; Station Evaluation and Review of NRC Violation in
- IR 2007-06
- Safety Evaluation by the Division of Reactor Licensing; U.S. Atomic Energy Commission in the Matter of Northern States Power Company Monticello Nuclear Generating Plant, Unit 1; Docket Number 50-263; March 18, 1970 1487; Site Housekeeping Quarterly Inspection; Revision 5 A.6; Acts of Nature; Revision 31 Section 1R18
- CAP 01190596;
- CV-1003 ('C' MSDT Dump) is Lifting/Leaking by - Thermal Performance
- WO 387692; Install T-Mod to Control
- CV-1004 Section 1R19
- CAP 01180958; Division
- II 250V Battery Monitoring Panel Readings Unusual
- ELEC-Y-81, Ground Investigation and Repair
- OWI-03.05; Safety Function Determination Program; Revision 2
- Operations Manual C.4-B.09.13.G; Loss of Y-80; Revision 11
- CAP 1195955; Question on Pre-Service Testing Adequacy for Operability
- WO 386503-07; 14 RHRSW Pump Comprehensive Test
- 214-PM; RHR Service Water Pump Replacement; Revision 3
- 255-05-IA-1-2; 'B' RHRSW Quarterly Pump and Valve Tests; Revision 68
- 255-05-III-4A; Comprehensive 14 RHRSW Pump and Valve Tests; Revision 18
- WO 383957; 3A-K40 Relay Replacement 4858-04-OCD; 1AR Reserve Transformer Maintenance Isolation; Revision 13
- 01187408; Required 1AR Testing to Verify as a Qualified Offsite Power Source; Revisions 0, 1, and 2
- Attachment Section 1R22
- CAP 01191151; G-3A, Exhaust Bolts not at Current Prescribed Torques 0007A; Condenser Low Vacuum Scram Instruments Test and Calibration Procedure; Revision 22 Section 1EP6 MNGP Emergency Plan Drill; July 8 & 9, 2009; Controller Manual; Revision 0
- CAP 01188769; General Emergency Classification Untimely during 7/08/09 Drill
- CAP 01188771; Follow-up Protective Action Recommendation Development Inaccurate/Untimely Section 4OA1 MSPI Basis Document;
- PRA-CALC-05-003; Revision 1 4
- AWI-04.08.11; NRC/WANO PIs and Monthly Operating Report Program; Revision 13
- EWI-04.08.11; NRC and WANO Performance Indicator - Data Collection; Revision 3
- FP-PA-PI-02; NRC/INPO/WANO Performance Indicator Reporting; Revision 6
- FG-E-MSPI-01; Mitigating System Performance Index; Revision 2 Unavailability Log for RCIC; July 2008 - June 2009
- MSPI Unavailability Index Derivation Report for Heat Removal System; July 2008 - June 2009 MSPI Unavailability Index Derivation Report for Emergency AC Power Systems; July 2008 - June 2009 MSPI Unavailability Index Derivation Report for High Pressure Injection System; July 2008 - June 2009
- MSPI Unreliability Index Derivation Report for Heat Removal System; July 2008 - June 2009
- July 2008 - June 2009 MSPI Unreliability Index Derivation Report for High Pressure Injection System; July 2008 - June 2009
- MSPI Performance Limit Exceeded Derivation Report for Emergency AC Power Systems; July 2008 - June 2009
- MSPI Performance Limit Exceeded Derivation Report for Heat Removal System; July 2008 - June 2009 MSPI Performance Limit Exceeded Derivation Report for High Pressure Injection System; July 2008 - June 2009
- CAP 01179631;
- MO-2110 (RCIC Test Return) did not Close as Expected During Surveillance Section 4OA3
- CAP 01176349; Containment Valves do not Appear to Meet Appendix R Requirements
- CAP 01186755; NRC Question Regarding Core Spray Flow Throttling for ASDS
- CAP 01186659; Station Needs to Revise Safety Significance for
- LER 2009-01
- AWI-08.01.00; Fire Protection Program Plan; Revision 11 4
- AWI-08.01.01; Fire Prevention Practices; Revision 34
- Operations Manual B.08.05-05; Fire Protection; Revision 45
- Attachment Operations Manual C.4-C; Shutdown Outside Control Room; Revision 32 Form 3067; Combustion Source Use Permit; Revision 12
- CA 01-177; Determination of Containment Overpressure Required for Adequate NPSH for Low Pressure ECCS Pumps Updated for Suction Strainer Debris Loading; Revision 1
- CAP 01181868; Manifold Equalizing Valve Failure Causes 'B' Main Steam Line Flow Isolation Instrumentation to Become Inoperable Attachment
LIST OF ACRONYMS
- USED [[]]
- AS [[]]
- AS [[]]
ME American Society of Mechanical Engineers
CAP Corrective Action Program
CRS Control Room Supervisor CS Core Spray
DRP Division of Reactor Projects
- HE [[]]
- HP [[]]
LCO Limiting Condition for Operation
- LO [[]]
CA Loss of Coolant Accident
- NF [[]]
- NP [[]]
- PA [[]]
RS Publicly Available Records
PI Performance Indicator
- PRN [[]]
- RHR [[]]
SW Residual Heat Removal Service Water
SDP Significance Determination Process SRO Senior Reactor Operator
SSC Systems, Structures, and Components
URI Unresolved Item Vdc Volts Direct Current
WO Work Order
T. O'Connor -2-
In accordance with
- NRC 's "Rules of Practice," a copy of this letter and its enclosure 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, Chief Branch 2 Division of Reactor Projects
Docket No. 50-263
License No.
- DPR -22 Enclosure: Inspection Report 05000263/2009004 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ
- DOCUME [[]]
- NT [[]]
- IN [[]]
- 2009004.DOC G Publicly Available G Non-Publicly Available G Sensitive G 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 [[]]
- RIII [[]]
- NAME [[]]
- RECORD [[]]
- PLANT [[]]
- NRC [[]]
- INTEGR [[]]
- ATED [[]]
- AND [[]]
- POWER [[]]
- UPRATE [[]]
- REVIEW [[]]
- INSPEC [[]]
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