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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

Main article: IP 71111.01

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

1R04 Equipment Alignment

Main article: IP 71111.04

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

1R05 Fire Protection

Main article: IP 71111.05

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

1R06 Flooding

Main article: IP 71111.06

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

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

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

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

..........7

1R15 Operability Evaluations

Main article: IP 71111.15

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

1R18 Plant Modifications

Main article: IP 71111.18

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

...............................................................10

1R22 Surveillance Testing

Main article: IP 71111.22

........................................................................10

1EP6 Drill Evaluation

Main article: IP 71114.06

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

4OA1 Performance Indicator Verification

Main article: IP 71151

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

4OA2 Identification and Resolution of Problems

Main article: IP 71152

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

4OA3 Follow-Up of Events and Notices of Enforcement Discretion

Main article: IP 71153

...............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

CAP 01188550; Possible Failure of 5A-K8D to Fully Reset during Test 0011-A

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 01191917; Front Standard / EPR Oil Level Out-of-Specification

CAP 01192925;

MO-2076; RCIC Steam Line Isolation Outboard 0255-08-IA-1; RCIC Quarterly Pump and Valve Tests; Revision 64

WO 388449;

MO-2076; RCIC Steam Line Isolation Outboard

253-01; SBGT 'A' Train Quarterly Test; Revision 39 Section 1R15

CAP 01193840; Error/Wrong Input in Calculation (CA)06-104, 480V Motor Terminal Voltage

CAP 01056182; Motor Terminal Voltages Could Drop Below 90% Rated

II.05; Chemistry Limits & Sampling Frequencies; Revision 20

CA 04-042; MNGP AST - Post LOCA pH Analyses; Revision OA

CAP 01194499; CALC 96-080 and 97-044 Operator Action < 10 Minutes

CAP 01079705; Modify EDG Silencer Lines to Restore the EDGs Within a Reasonable Time Frame

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

WO 384617;

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

EC 10856; Restoration of PRNMS DIDA RPS Trips

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

WO 376486; Restoration of PRNMS DIDA RPS Trips Condition Evaluation

01187408; Required 1AR Testing to Verify as a Qualified Offsite Power Source; Revisions 0, 1, and 2

Attachment Section 1R22

CAP 01191073; Loose Bolt on 11 EDG Exhaust Manifold Flange

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

MSPI Unreliability Index Derivation Report for Emergency AC Power Systems;

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 01164976; Unplanned Technical Specification Action Entry due to RCIC Inoperability

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

CAP 01190129; Failure to Promptly Identify Failed SBGT Surveillance

CAP 01189968; 'A' SBGT Flow not Within Band 4

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 01200258; NRC Violation - SBGTS 'A' - Station Did Not Enter TS Action

CAP 01181868; Manifold Equalizing Valve Failure Causes 'B' Main Steam Line Flow Isolation Instrumentation to Become Inoperable Attachment