Text

February 5, 2010

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 05000263/2009005

Dear Mr. O'Connor:

On December 31, 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 January 7, 2010, 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, the NRC has determined that one Severity Level IV violation of NRC requirements occurred. Additionally, one self-revealed finding of very low safety significance was identified involving a violation 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, four licensee-identified violations are listed in Section 4OA7 of this report.

If you contest the subject or severity of 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 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 the Monticello Nuclear Generating Plant. The information that 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). ADAMS is accessible from the NRC Website 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 05000263/2009005

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: 05000263/2009005 Licensee: Northern States Power Company, Minnesota Facility: Monticello Nuclear Generating Plant Location: Monticello, MN Dates: October 1 through December 31, 2009 Inspectors: S. Thomas, Senior Resident Inspector L. Haeg, Resident Inspector P. Zurawski, Resident Inspector, Prairie Island T. Go, Health Physicist M. Bielby, Senior Operations Engineer D. Reeser, Operations Engineer J. Bozga, Reactor Inspector M. Garza, Emergency Response Specialist

Observers: J. Corujo-Sandin, Reactor Engineer P. Smagacz, 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

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

1R06 Flooding

Main article: IP 71111.06

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

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

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

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

........13

1R15 Operability Evaluations

Main article: IP 71111.15

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

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

1R22 Surveillance Testing

Main article: IP 71111.22

........................................................................18

1EP4 Emergency Action Level and Emergency Plan Changes

Main article: IP 71114.04

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

1EP6 Drill Evaluation

Main article: IP 71114.06

................................................................................20

RADIATION SAFETY

...................................................................................................20 2OS1 Access Control to Radiologically Significant Areas (71121.01).........................20 2OS2 As-Low-As-Is-Reasonably-Achievable Planning and Controls (71121.02)........21 2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)....22

OTHER ACTIVITIES

....................................................................................................25

4OA1 Performance Indicator Verification

Main article: IP 71151

.......................................................25

4OA2 Identification and Resolution of Problems

Main article: IP 71152

............................................28

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

Main article: IP 71153

...............30 4OA5 Other Activities...................................................................................................31 4OA6 Management Meetings......................................................................................32 4OA7 Licensee-Identified Violations............................................................................33

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

W. Paulhardt, Assistant Plant Manager

S. Sharp, Operations Manager

S. Radebaugh, Maintenance Manager

M. Holmes, Radiation Protection/Chemistry Manager

S. Speight, Regulatory Affairs Manager

J. Sorensen, Fleet Training General Manager

P. Norgaard, Licensed Operator Requalification Training Supervisor

M. Petersen, Fleet Training Supervisor

M. Walter, Training Manager

J. Temple, RP ALARA Specialist

R. Latham, Radiation Protection/Chem. General Supervisor

G. Holthaus, Senior Emergency Preparedness Coordinator Nuclear Regulatory Commission

K. Riemer, Chief, Reactor Projects Branch 2

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000263-2009005-01 NCV Inadequate Maintenance Procedure for 'A' SBGT System (Section 1R12)

05000263-2009005-02 NCV Failure to Make Required Eight Hour Event Report per 10 CFR 50.72(b)(3)(v) (Section 1R13)

05000263/2009005-03 URI MSPI Basis Document does not Reflect Current Plant Configuration for RHRSW (Section 4OA1)

Closed

05000263/FIN-2009005-01 NCV Inadequate Maintenance Procedure for 'A' SBGT System (Section 1R12)

05000263-2009005-02 NCV Failure to Make Required Eight Hour Event Report per 10 CFR 50.72(b)(3)(v) (Section 1R13)

05000263/LER-2009-005-00 LER Failed Fusible Link on Door 18 (Section 4OA3)

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 C.4-B.08.03.A; Heating Boiler; Revision 06

EC-15007; Temporary Heating Plan Section 1R04 2155-10; Motor Control Center Checklist

MCC-133; TB East 911'; Revision 09

2155-13; Motor Control Center Checklist

MCC-143; TB East 931'; Revision 13

System Health Report; HPC High Pressure Coolant Injection; dated 11/5/2009

Section 1R05 Strategy A.3-23-B; Intake Structure Corridor; Revision 5

Strategy A.3-06; Refuel Floor; Revision 6

Strategy A.3-33; EFT Building Third Floor; Revision 6

Strategy A.3-31-B; EFT Building 1st Floor (Div II); Revision 12 Strategy A.3-19-B; Essential MCC Area (No. 142 & 143 931' Elevation); Revision 10 Strategy A.3-19-C; F.W. Pipe Chase; Revision 5. Section 1R11 Simulator Scenario

RQ-SS-72

Monticello Licensed Operator Examination Results; November 18, 2009

NRC License Maintenance Responsibilities,

OWI-01.08; Revision 11 Walkthrough Exam Summary,

QF-1073-01; Revision 1 Two-Year Plan; 05/18/2009

Six-Year Plan; 05/18/2009

Licensed Operator Requalification Training Program Description; Revision 0

Remediation Training Form; Multiple; Various Dates NRC

IP-71111.11B Self-Assessment; 2009 NRC Exam Security Requirements; Revision 1

PINGP 910; NRC Licensed Duty Quarterly Report Tracking Report; Revision 1

Licensed Operator Requalification Training Attendance Records; 2008-2009

Licensed Operator Requalification Training Feedback Summary Forms

QF-1050-01a;

Revision 3 Curriculum Review Committee, M-9100 Licensed Operator Requal, 2009 Meeting Minutes,

QF-1060-10; Revision 1

FP-T-SAT-80; Simulator Configuration Manager; Revision 3

FP-T-SAT-81; Simulator Testing and Documentation; Revision 5

SSP-01; Simulator Performance Test Procedure-Steady State Performance, 08-01-2008

FP-T-SAT-71; NRC Exam Security Requirements; Revision 1 NRC License Active Status Maintenance; Revision 8

XX-01, Simulator Performance Test Procedure-Simulator Real Time Measurement, 08-04-2008

XX-02,

SPTP-Simulator Repeatability; 08-04-2008

T-01,

SPTP-Manual Scram; 07-25-2008

T-03,

SPTP-Simultaneous Closure of All MSIV's; 07-25-2008

Attachment T-09,

SPTP-Maximum Steam Rupture in Containment; 07-28-2008 C.5.1-2006, Reactor Pressure Vessel Flooding (Bases); Revision 9

C.5-3205, Terminate and Prevent; Revision 6 Two Simulator Crew and Individual Evaluation Reports; Various Dates Six Licensed Operator Medical Records; Various Dates Four Simulator Scenarios for Annual License Examination Evaluation; Various Dates Job Performance Measures; Various Dates Two Written Examinations for Biennial License Examination; Various Dates Section 1R12 4

AWI-08.01.03; HELB Practices; Revision 15

CAP 01200304;

AO-2945 Failed to Open during 0253-01 'A' SBGT Quarterly Test

CAP 01109043;

AO-2944, 'B' SBGT Inlet Valve Appears Mechanically Bound

4171-02-PM; Standby Gas Treatment System Air Heater - 'B' Train; Revision 8

253-01; SBGT 'A' Train Quarterly Test; Revision 40 Operations Manual B.04.02-05; Secondary Containment/Standby Gas Treatment; Revision 23

CAP 01210817; NRC Feedback on Reportability of SBGTS Event Section 1R13 4

AWI-08.01.00; Fire Protection Program Plan; Revision 11

Operations Manual B.08.05-05; Fire Protection - System Operation; Revision 46

EC 14960; Cable Spreading Room Halon Low Pressure Performance 0327; Cable Spreading Room Halon Tank Weight and Pressure Test; Revision 17

CAP 01183755; Low Halon Pressure on Cable Spreading Room Cylinder

CAP 01204645; PCT Valves Inoperable due to Field Setup Not Matching Calculations

CAP 01204653;

AO-2377 Declared Inoperable due to Setup Issues

CAP 01204654;

AO-2896 Declared Inoperable due to Setup Issues

CAP 01204660;

AO-2387, Exact Field Dimensions Could not be Obtained 42321-PM; Primary Containment T-Seated Butterfly Valves; Revision 9

WO 392352;

MECH-AO-2896, Adjust Link and Lever Dimension

CAP 01209704; Incorrect Rotation on

MO-2006 Following 480V Bucket Swap

EC15312; Evaluate Condition of

MO-2006 Following Backseat

CAP 01210858; HPCI Steam Line Support Concerns

CAP 01210762; Cosmetic Damage to Grouted Fire Barrier

NH36249; High Pressure Coolant Injection System Steam Side P&ID; Revision 77

Section 1R15

OPR 1204430; Calculations were Found to Have Incorrect Input with Regards to Concrete Strength

OPR 1204777 Turbine Bypass Valve Capacity is Less than What is Stated in Licensing

Documents

for Current Operating Cycle

CAP 1200170; Pickup Voltage on 480v MCC Contactors not Periodically Tested

CAP 1200723; P-111B Calculated Starter Voltage Lower than Expected

CAP 1202633; B4319 Contactor Failed Degraded Voltage Testing

CAP 1136111; Manual Isolations Required after HELB in Turbine Building

EC 14776; Isolation of Feedwater Crack in Steam Chase

CAP 1194493; Feedwater HELB Crack in Main Steam Chase Attachment Section 1R19

CAP 01208120; TS Impact of Restoring V-EF-18B from Maintenance Questioned

4460-14-PM; V-EF-18B Lubrication and Inspection; Revision 6

WO 379869;

PM 4460-14 V-EF-18B

WO 347705; Perform 4946-PM Ac Induction 4KV/480V Motor Offline Testing

CAP 01201990; CRV Post-Maintenance Testing Required 3.0.3 Entry

WO 388007; Investigate/Repair Auto-Start Circuitry for 'A' CRV

255-06-III-1; HPCI Comprehensive Pump and Valve Tests; Revision 16

CAP 01210814; NRC Feedback on Retraction of CREFT SSFF

CAP 01211484; 150G-505, 152-505 Ground Relay not Within Acceptance Criteria 0255-03-IA-1-1; 'A' Core Spray Quarterly Pump and Valve Test; Revision 50 Section 1R22 0533; Containment Sump Flow Measurement Instrumentation; Revision 15

255-11-III-4; 14 ESW Quarterly Pump and Valve Test; Revision 53 1069; HPCI Flow Control System Dynamic Test Procedure; Revision 20

CAP 1210821; Unexpected Annunciator Received during Startup of HPCI

Section 1EP4 Monticello Nuclear Generating Plant Emergency Plan; Revision 31 Monticello Nuclear Generating Plant Emergency Plan; Revision 32 A.2-101; Classification of Emergencies; Revision 40

A.2-101; Classification of Emergencies; Revision 41 Section 2OS1

WO-385617;

RWP-372; Comprehensive HPCI Run Including HPCI Steam Supply Line to Visually Check for Vibration; dated December 16, 2009 4-AWI-04.05.13; Control of Items in the Spent Fuel Pool; Revision 7 R.07.02; Area Posting, Special Status Signs and Hot Spot Stickers; Revision 35

CAP-01173234; Improper Boundaries of HCA Could Allow Contamination Out-Skirting of

HCA Boundaries at the Entrance of CRD Rebuild Facility; dated March 16, 2009

CAP-01173307; Worker Entered CA without Protective Clothing into RHR Room; dated April 17, 2009

RWP-00000886-01; SRV Change-Out; Locked High Radiation Area (LHRA); dated March 19, 2009

CAP-01173835; Condenser Room Contamination Control; dated March 19, 2009

CAP-01173891; Improper RP work Practices during Scaffold Erection; dated March 18, 2009

CAP-

01175853; RP Dose Rate Labeling Issues of HP Turbine Diaphragms from HP Turbine Causes Work Delays; dated March 31, 2009

CAP-01176558; Incorrect Guidance Caused Unnecessary Dose Received in the Drywell; dated April 3, 2009

R.01.04; Control of Personnel in High Radiation and Airborne Areas; Revision 21

R.13.08; Radiological Work Plan for Underwater Diving; Revision 6 R.13.03; Monticello Nuclear Generating Plant; Radiography; Revision 11 R.13.08; Radiological Work Plan for Underwater Diving; Revision 6

Attachment Section 2OS2 4-AWI-08.04.01; Radiation Protection Plan; Revision 27

ALARA Report from the Coordinator; Monticello Nuclear Generating Plant 2009 Monticello Nuclear Generating Plant; Long Term Dose Reduction Plan 2008 -2012; Revision 3 CD 9.2; Nuclear Department Corporate Directive; Radiation Dose Guidelines; dated November 11, 2008

CAP-01179081;

WO-00372646 Exceeded the Dose Estimate; dated April 22, 2009

CAP-01181227; 1843 mrem was Received for Final Drywell Cleaning; dated May 7, 2009

CAP-01175551; Dose Estimate was Exceeded on

WO-345547-02; dated March 29, 2009

CAP-01180004; DW Shielding Installation Exceeded the Dose Estimate; dated April 28, 2009 Nuclear Oversight First Quarter 2009 Assessment Report for Monticello Nuclear Oversight Second Quarter 2009 Assessment Report for Monticello

WO-00378893; Install General Lead Shielding in Drywell; RP ALARA Task; dated December 17, 2009

TE-0272; Work Order Dose Report for

RFO-24

QF-1207;

WO-00344150; Radiological Work Assessment Form ALARA Review Checklist:

Replace Degraded Insulation Blankets in Drywell; dated March 10, 2009

QF-1203; Radiological Work Assessment Form; dated March 9, 2009

QF-1226; Radiological Work Assessment Form Post Job Review:

WO-00344150; dated September 24, 2009

QF-1207;

WO-00368058; Radiological Work Assessment Form ALARA Review Checklist;

SRV Change-Out Main Valve and Topwork Test SRV Discharge; dated February 11, 2009

QF-1226; Radiological Work Assessment Form Post Job Review; Drywell SRV Work; date September 14, 2009

QF-1207;

WO-00367391; Radiological Work Assessment Form ALARA Review Checklist; Drywell Scaffold Support; dated March 10, 2009

QF-1226; Radiological Work Assessment Form Post Job Review; Drywell Scaffold Support; dated September 24, 2009

QF-1207;

WO-00367391; Radiological Work Assessment Form ALARA Review Checklist;

ISI Nozzle Examination; dated March 5, 2009 Section 2OS3

CAP 01130721; DARM No. 9 in RW with Past Due Function Check; dated February 17, 2009

CAP 01169907; Unexpected Annunciator Refuel Floor Area High Radiation Spurious;

March 31, 2009

CAP 01174121; RP Department Lacks Alarm Response Procedure on

AMS-4; June 15, 2009

CAP 0118338; Received Unexpected Sewer Radiation Monitor Alarm; July 8, 2009

CAP 01186986;

DARM-10 Failed the Routine Monthly Function Check; August 8, 2009

CAP 01148748; Received Unexpected OFF Gas ARM/CAM Trip Annunciator; October 27, 2008

CAP 011115517; Unable to Calibrate ARGOS

AZ-8 due to High Background; October 22, 2008

CAP 01138756; SJAE CAM Found in Alarm Status; May 5, 2008

CAP 01151658; Portable DARM Dose Rate Alarmed on Refueling Bridge with Unknown Cause; December 23, 2008

CAP 01164448; SJAE CAM Trending Upward; February 16, 2009

CAP 01196576; ARGOZ AZ5 Failed Daily Function Check- Head Detector; September 13, 2009

CAP 01201573; ARGOZ

AZ-5 Failed Function Check during Daily Source Check;

October 12, 2009

CAP 01114825; Fire Brigade Leader did not Use Glasses Insert with SCBA during Fire Brigade Drill; November 24, 2007

CAP 01125177; Monthly SCBA Inspection not Performed by the Due Dates; March 10, 2008

Attachment

CAP 01141376; Missing SCBA Mask Inserts in Alternate Fire Brigade Room; December 20, 2008

R-05-07; SCBA Inspection and Functional Check; Revision 20 Snapshot Summary for RP Instrument Program

SAR 01094362 Snapshot Self Assessment of MNGP Respiratory Protection Program

5719; NMC CAM Calibration Data Sheets; Revision 17; 2008 - 2009

5848;

AMS-4 Calibration Data Sheets; Revision 0; 2009 - 2009

5598-01; Semiannual Smear Counter Functional Checks; Revision 2

R-09-31; NMC Continuous Air Monitors; Revision 16 Part 61; Waste Stream Activities (uCi/gram); Condensate Resin; Dry Active Waste; Reactor Water Clean-Up (RWCU); July 2008

R-11-08; Selection and Entry of 10 CFR Part 61 Correlation Factors; Revision 7

Technical Basis Document No.04-002; Evaluation of the Canberra Argos Zeus-4G Personnel Contamination Monitor; March 25, 2005 0386; Drywell Particulate Monitor Calibration; Revision 24 R-09-66; Operation of MG Telepole Dose Rate Instrument; Revision 1

R-09-60; Function Check and Calibration of

PM-7 Portal Monitor; Revision 9

R-09-62; ARGOS Contamination Monitors; Functional Check and Calibration; Revision 12 Section 4OA1 3530-08; NRC/WANO Performance Indicator RCS Activity Fuel Performance and Chemistry; Revision 10

3530-06; NRC/WANO Performance Indicator Radiation Safety and Exposure; Revision 5

Occupational Exposure/Public Exposure RETS/ODCM Occurrences from 1st Quarter 2008 through 3rd Quarter 2009, Reporting Periods Fuel Performance; Maximum I-131 Dose Equivalent Activity from 1st Quarter 2008 through 3rd Quarter 2009, Reporting Periods MSPI Basis Document;

PRA-CALC-05-003; Revision 1

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 RHR; July 2008 - June 2009

MSPI Unavailability Index Derivation Report for Heat Removal System; July 2008 - June 2009 MSPI Unreliability Index Derivation Report for Heat Removal System; July 2008 - June 2009

MSPI Performance Limit Exceeded Derivation Report for Heat Removal System; July 2008 - June 2009 Section 4OA2

CAP 01184276; Operations DRUM Identifies Adverse Trend in Tagout/Lockout Process

CAP 01184941; Adverse Trend:

Work Plan Changes Made Without Review and Approval

CAP 01202466; Adverse Trend in Double Disc Gate Valve LLRT Performance

3rd Quarter 2009 Operations Department Roll-up Meeting Results Attachment Section 4OA3 Operations Manual C.2-05; Power Operation - System Operation; Revision 36

CAP 01194446; Technical Specification 3.0.3 Entry due to Inoperable HELB/Flood Barrier

CAP 01103584; Door-18 Found Closed

CAP 01208146; NRC Issue Associated with

LER 2009-005

CAP 01195145; A Level CAP EFR not Completed as Required Root Cause Evaluation

01194357-02; Door-18 Fusible Link Failed Allowing the Door to Close, Thereby Invalidating Feed Water HELB Mitigation Attachment

LIST OF ACRONYMS

USED [[]]

ADAMS Agencywide Document Access Management System

ALARA As-Low-As-Is-Reasonably-Achievable

ARM Area Radiation Monitor

AS [[]]

ME American Society of Mechanical Engineers

AWI Administrative Work Instruction

CAM Continuous Air Monitor

CAP Corrective Action Program

CDF Core Damage Frequency

CDBI Component Design Bases Inspection

CE [[]]

DE Committed Effective Dose Equivalent

CFR Code of Federal Regulations

CR [[]]

EF Control Room Emergency Filtration

CRV Control Room Ventilation

CSR Cable Spreading Room DRP Division of Reactor Projects

EDG Emergency Diesel Generator

EFT Emergency Filtration Treatment

ESW Emergency Service Water

HELB High Energy Line Break

HP [[]]

CI High Pressure Coolant Injection

IMC Inspection Manual Chapter

IP Inspection Procedure

IST Inservice Test

JPM Job Performance Measure kV Kilovolt

LCO Limiting Condition for Operation

LER Licensee Event Report

LO [[]]

RT Licensed Operator Requalification Training

MCC Motor Control Center

MSPI Mitigating Systems Performance Index NCV Non-Cited Violation

NEI Nuclear Energy Institute

NRC U.S. Nuclear Regulatory Commission

OD [[]]

CM Offsite Dose Calculation Manual

PARS Publicly Available Records

PI Performance Indicator PM Post or Preventative Maintenance

RCA Radiologically Controlled Area

RCS Reactor Coolant System

RETS Radiological Effluent Technical Specification

RHR Residual Heat Removal

RHR [[]]

SW Residual Heat Removal Service Water

RP Radiation Protection

SAT Systems Approach to Training

SC [[]]

BA Self-Contained Breathing Apparatus

SBGT Standby Gas Treatment

SDP Significance Determination Process SRA Senior Reactor Analyst

SSC Systems, Structures, and Components

Attachment

TS Technical Specification

USAR Updated Safety Analysis Report

WO Work Order

T. O'Connor -2-

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 the

Monticello Nuclear Generating Plant. The information that 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 ).

ADAMS is accessible from the