IR 05000263/2018003

NRC Integrated Inspection Report 05000263/2018003 and 07200058/2018001

ML18304A214
Person / Time
Site:	Monticello
Issue date:	10/31/2018
From:	Kenneth Riemer NRC/RGN-III/DRP/B2
To:	Church C Northern States Power Company, Minnesota
References
IR 2018001
Download: ML18304A214 (20)

Text

October 31, 2018

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT NRC INTEGRATED INSPECTION REPORT 05000263/2018003 AND 07200058/2018001

Dear Mr. Church:

On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Monticello Nuclear Generating Plant. On October 16, 2018, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection. Further, the inspectors documented a licensee-identified violation determined to be of very low safety significance, in this report. The NRC is treating this violation as a Non-Cited Violation (NCV)

consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of the 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 copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at the Monticello Nuclear Generating Plant. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Kenneth Riemer, Chief Branch 2 Division of Reactor Projects

Docket Nos. 50-263;72-058 License No. DPR-22

Enclosure:

IR 05000263/2018003; 07200058/2018001

cc: Distribution via LISTSERV

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting an integrated quarterly inspection at the Monticello Nuclear Generating Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Findings and violations being considered in the NRCs assessment are summarized in the table below.

Licensee-identified non-cited violations are documented in report section: 71111.12.

Maintenance Effectiveness.

List of Findings and Violations

None.

Additional Tracking Items

None.

TABLE OF CONTENTS

PLANT STATUS

INSPECTION SCOPES

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

REACTOR SAFETY

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

OTHER ACTIVITIES - BASELINE

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

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

INSPECTION RESULTS

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

EXIT MEETINGS AND DEBRIEFS

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

DOCUMENTS REVIEWED

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

PLANT STATUS

Monticello began the inspection period operating at approximately 100 percent power and

operated at or near full power with the following exceptions. Power was subsequently returned

to 100 percent after completion of each activity.

• August 11, 2018Power was reduced to approximately 65 percent for power

suppression testing with an attempt to identify the location of a potential small fuel clad

defect; and

September 15, 2018Power was reduced to approximately 75 percent for control rod

sequence exchange and quarterly turbine testing.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in

effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with

their attached revision histories are located on the public website at http://www.nrc.gov/reading-

rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared

complete when the IP requirements most appropriate to the inspection activity were met

consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection

Program - Operations Phase. The inspectors performed plant status activities described in

IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem

Identification and Resolution. The inspectors reviewed selected procedures and records,

observed activities, and interviewed personnel to assess licensee performance and compliance

with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.01Adverse Weather Protection

Impending Severe Weather (1 Sample)

The inspectors evaluated readiness for impending adverse weather conditions for severe

thunderstorms and high winds on August 3, 2018.

71111.04Equipment Alignment

Partial Walkdown (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1) Division 2 Control Room Ventilation (CRV) / Emergency Filtration Train (EFT) Protected

during Division 1 Emergent Maintenance; July 2, 2018;

(2) Division 1 CRV / EFT protected during Division 2 Maintenance; July 17, 2018; and

(3) 12 Reactor Protection System (RPS) MG Set G-4B protected during Division 1

Maintenance; August 13, 2018.

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the

Emergency Diesel Generator Emergency Service Water system while protected during

Division 1 Service Water Maintenance system on September 4, 2018.

71111.05AQFire Protection Annual/Quarterly

Quarterly Inspection (5 Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas:

(1) Fire Zone 13B - Reactor FeedPump & Lube Oil Reservoir Room on July 18, 2018;

(2) Fire Zone 13C - Turbine Building 911 MCC on July 18, 2018;

(3) Fire Zone 16 - Corridor Turbine Building East & West on July 18, 2018;

(4) Fire Zone 23A - Intake Structure Pump Room on July 18, 2018; and

(5) Fire Zone 23B - Intake Structure Corridor on July 18, 2018.

71111.06Flood Protection Measures

Internal Flooding (1 Sample)

Circulating Water/Service Water Pumps Room/Intake Structure on August 30, 2018.

Underground Cables (1 Sample)

The inspectors evaluated cable submergence protection in the following vaults:

(1) Cable Vault CP 100 on July 17, 2018;

(2) Cable Vault CP 102 on July 17, 2018;

(3) Cable Vault NMH 301 on July 17, 2018;

(4) Cable Vault NMH 302 on July 17, 2018;

(5) Cable Vault NMH 303 on July 17, 2018;

(6) Cable Vault NMH 304 on July 17, 2018;

(7) Cable Vault NMH 309 on July 17, 2018;

(8) Cable Vault NMH 310 on July 17, 2018; and

(9) Cable Vault NMH 337 on July 17, 2018.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated SEG # RQ-SS-17E (Design Basis Earthquake with

Reactor Water Cleanup (RWCU) Leak Requiring Reactor scram) on August 6, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated plant down power to 65 percent for power suppression

testing on August 11, 2018.

71111.12Maintenance Effectiveness

Routine Maintenance Effectiveness (2 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities associated

with the following equipment and/or safety significant functions:

(1) High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC)

Steam Isolation Valves Conductive Heat Rise Environment Qualification Variance on

September 10, 2018; and

(2) C Main Steam Isolation Valve (MSIV) packing leak and packing consolidation on

September 13, 2018.

71111.13Maintenance Risk Assessments and Emergent Work Control (4 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent

work activities:

(1) Off-Gas Samples Indicated Potential Cladding Defect on August 12, 2018;

(2) 11 Standby Liquid Control (SBLC) Accumulator Leakage on August 13, 2018;

(3) HPCI Shaft Guard Rubbing on September 18, 2018; and

(4) A Core Spray Check Valve Leak by on September 11, 2018.

71111.15Operability Determinations and Functionality Assessments (4 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

(1) Holes in A Control Room Emergency Filtration (CREF) Fan Boot on July 3, 2018;

(2) 12 Emergency Diesel Generator Governor Oil Leak on July 30, 2018;

(3) 11 & 12 SBLC Accumulator Parts not safety related on August 15, 2018; and

(4) A Core Spray Inoperable on September 11, 2018.

71111.18Plant Modifications (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) EC-26181 - Open Phase Vulnerability Project Modification on July 17, 2018; and

(2) EC-28450 - Security Physical Upgrades Project - EWS IDS and cameras on

August 20, 2018.

71111.19Post Maintenance Testing (6 Samples)

The inspectors evaluated the following post maintenance tests:

(1) RCIC MO-2096 Post Maintenance Test (PMT), OPS-D311-07 on August 7, 2018;

(2) 15 Installation Air and Service Dryer PMT, AI-1100 on August 13, 2018;

(3) PVC-2459 PMT; B Core Spray Line PCV Repair on August 31, 2018;

(4) RV-1992 PMT; 13 Residual Heat Removal (RHR) Pump Suction RV on

September 5, 2018;

(5) 0255-04-III-1A, RHR Comprehensive Pump and Valve Tests, P-202A PMT-13 RHR

Pump September 7, 2018; and

(6) A Core Spray Pressure Station Check Valve Repair Post Maintenance Testing (PMT)

on September 12, 2018.

71111.22Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (4 Samples)

(1) 0466-02; B EFT Filter Efficiency and Leak Tests on July 17, 2018;

(2) 1339; ECCS Pump Motor Cooler Flush on July 19, 2018;

(3) 0187-01B; 11 Emergency Diesel Generator/11 Emergency Service Water (ESW)

Monthly Pump and Valve Tests on August 14, 2018; and

(4) 0288-08-IA-1 RCIC Quality Pump and Valve Test on August 7, 2018.

In Service Testing (1 Sample)

(1) 0255-11-IA-7; ESW SW-101 & 102 Valve Test on July 2, 2018.

71114.02Alert and Notification System Testing (1 Sample)

The inspectors evaluated the maintenance and testing of the alert and notification system on

September 17-20, 2018.

71114.03Emergency Response Organization Staffing and Augmentation System (1 Sample)

The inspectors evaluated the readiness of the Emergency Response Organization on

September 17-20, 2018.

71114.05Maintenance of Emergency Preparedness (1 Sample)

The inspectors evaluated the maintenance of the emergency preparedness program on

September 17-20, 2018.

71114.06Drill Evaluation

Emergency Planning Drill (1 Sample)

The inspectors evaluated the MNGP 8-29-2018, Emergency Preparedness Full Scale

Drill including Joint Information Center and Off-site Response Organizations on

August 29, 2018.

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification (6 Samples)

The inspectors verified licensee performance indicators submittals listed below:

(1) MS06: Emergency AC Power Systems - 1 Sample (July 1, 2017 June 30, 2018);

(2) MS07: High Pressure Injection Systems - 1 Sample (July 1, 2017 June 30, 2018);

(3) MS08: Heat Removal Systems - 1 Sample (July 1, 2017 June 30, 2018);

(4) EP01: Drill/Exercise Performance - 1 Sample (3rd quarter 2017 2nd quarter 2018);

(5) EP02: Emergency Response Organization Drill Participation - 1 Sample

(3rd quarter 2017 2nd quarter 2018); and

(6) EP03: Alert And Notification System Reliability - 1 Sample

(3rd quarter 2017 2nd quarter 2018).

71152Problem Identification and Resolution

Annual Follow-Up of Selected Issues (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program

related to the following issues:

(1) Potential Defect and Noncompliance to Appendix B/Part 21 (CAPs 501000008094

and 50100009601) on July 23, 2018. The basis for this corrective action review was to

perform a programmatic review of the licensees operating experience evaluation

process as related to 10 CFR Part 21 notifications from vendors. Inspector focus during

the in-depth review included the following performance attributes: Operating experience. (1 Sample)

(2) Independent Spent Fuel Storage Installation (ISFSI) Contractor Stop Work Conditions

(CAPs 501000013804 and 501000014624) on August 13, 2018. As part of daily

corrective action reviews, the inspectors noted two corrective action documents

associated with ISFSI campaign contractor-related issues that resulted in work

stoppage. The inspectors concluded further in-depth review was warranted because of

contractor control issues during the previous ISFSI loading campaign and since the most

recent two contractor issues occurred within an approximate three week period and

resulted in stop work conditions. Inspector focus during the in-depth review included an

evaluation of the licensees corrective action process for the following performance

attributes: Identification; Classification; Evaluation; and Completion of corrective actions. (1 Sample)

OTHER ACTIVITIESTEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1Operation of an Independent Spent Fuel Storage Installation at Operating Plants

The inspectors evaluated the licensees operation of the independent spent fuel storage

installation from September 10, 2018, to September 27, 2018. Specifically, the inspectors

evaluated:

(1) the material and radiological condition of the ISFSI and loaded storage modules

through performing a walkdown and independent radiological surveys on

September 13, 2018;

(2) a heavy lift of the loaded transfer cask from the cask processing area to the transfer

trailer on September 13, 2018;

(3) welding of the final pass of Dry Shielded Canister (DSC) No. 20 Outer Top Cover Plate

(OTCP) port cover in accordance with Welding Procedure Specification

No. TN P8-P8-GT1 on September 11, 2018, for DSC No. 20;

(4) non-destructive evaluations, including helium leak testing as applicable, of the Inner

Top Cover Plate and OTCP weld for DSC No. 20 in accordance with

Procedure Nos. HTPT-DSC-ORANO and MSLT-DSC-AREVA on September 11 and

September 12, 2018;

(5) processing of DSC No. 20 for storage on September 11, 2018, including blowdowns

and vacuum drying;

(6) transport to the ISFSI pad and insertion into the horizontal storage module (HSM) of

DSC No. 20 on September 13, 2018;

(7) the fuel selection for DSC No. 20, loaded on September 10, 2018; and

(8) changes screened and evaluated using 10 CFR 72.48 that involved temporarily

bypassing an area radiation monitor near a loaded transfer cask and a change to the

Emergency Action Level applicable to the ISFSI.

INSPECTION RESULTS

Licensee Identified Non-Cited Violation

71111.12Maintenance Effectiveness

This violation of very low safety significant was identified by the licensee and has been

entered into the licensee corrective action program and is being treated as a Non-Cited

Violation, consistent with Section 2.3.2 of the Enforcement Policy.

Enforcement:

Violation: The licensee identified a finding of very low safety significance (Green) and

associated NCV of 10 CFR 50.49, Environmental qualification of electric equipment

important to safety for nuclear power plants; which requires, in part, that equipment qualified

by test must be preconditioned by natural or artificial aging to its end of life or a shorter

designated life considering all significant types of degradation which can have an effect on

equipment function.

Contrary to the above, on June 2, 2018, the licensee determined that EQ

evaluation 608000000032, of MO-2034, MO-2035, MO-2075, and MO-2076 (HPCI and

RCIC Steam Line Isolation Valves) internal actuator cables, failed to consider the temperature

rise due to the high temperature process fluid in the vicinity of the affected components when

aging (preconditioning) them and the unaccounted temperature rise shortened the life of

some components to the point that they were no longer EQ qualified to the end of planned

life. The unaccounted for process fluid temperature increases were verified by the licensee

when thermography of the associated valves was performed. The licensee performed a

prompt operability determination, entered the issue into the corrective action program (CAP)

as CAP 501000012766 and performed a thermal life analysis engineering evaluation.

Long-term corrective actions include replacement of the internal actuator cables during the

next refueling outage.

Significance/Severity Level: This finding was more than minor because the performance

deficiency was associated with the equipment performance attribute of the Mitigating Systems

cornerstone and adversely affected its objective to ensure the availability and capability of

systems that respond to initiating events to prevent undesirable consequences. Specifically,

HPCI and RCIC Steam Line Isolation Valves are designed to provide reactor coolant pressure

boundary, required for a safe reactor shutdown following a Design Basis Accident or

transient. The finding was of very low safety significance (Green) because it was a design or

qualification deficiency, did not involve an actual loss of safety system, did not represent

actual loss of a safety function of a single train for greater than its Technical

Specification (TS) allowed outage time, and did not represent an actual loss of function of one

or more non-TS trains of equipment designated as high safety-significant in accordance with

the licensees maintenance rule program for >24 hrs.

Corrective Action Reference: 501000012766

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public

disclosure. No proprietary information was documented in this report.

On September 20, 2018, the inspectors presented the emergency preparedness program

inspection results to Mr.

M. Antony, Operations Manager, and other members of the

licensee staff.

On September 27, 2018, the inspectors presented the independent spent fuel storage

installation inspection results to Mr.

C. Church, Site Vice President, and other members of

the licensee staff via telephone conference.

On October 16, 2018, the inspectors presented the quarterly integrated inspection results to

Mr.

C. Church, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01Adverse Weather Protection

- 1444; Pre and Post Severe Weather Inspection Checklist; Revision 16

- A.6; Acts of Nature; Revision 58

71111.04Equipment Alignment

- 2201; Plant Prestart Checklist CRV-EFT System; Revision 10

- DBD-B.08.01.02; Emergency Diesel Generator Emergency Service Water System;

Revision 5

- ESP-RPP-0379-02; Div 2 RPS - Electrical Protection Assembly; Revision 2

- NE-36771-4; Reactor Protection Power System Distribution Panel Y40 &Y50; Revision 77

- NH-170037; Main Control Room CRV/EFT System; Revision 84

- NH-170037-1; Main Control Room Breathing Air Supply System; Revision 78

- NH-36664; P&ID RHR Service Water & Emergency Service Water Systems; Revision 95

71111.05Fire Protection Annual/Quarterly

- Strategy A.3-13-B, Fire Zone 13-B; Rx Feed Pump and Lube Oil Reservoir Room;

Revision 13

- Strategy A.3-13-C, Fire Zone 13-B; Turbine Building 911 Elevation East MCC Area;

Revision 11

- Strategy A.3-16, Fire Zone 16; Corridor; Turbine Building East & West

(Elevations 911 and 931); Revision 18

- Strategy A.3-23-A, Fire Zone 23-A; Intake Structure Pump Room; Revision 14

Strategy A.3-23-B, Fire Zone 23-B; Intake Structure Corridor; Revision 9

71111.06Flood Protection Measures

- DBD-S.04; Intake Structure; Revision 7

- NF-36763; Raceways, Grounding & Direct Buried Cable Runs - South Turbine Generator

Building; Revision 81

- NSPM Calculation 07-021; Reactor Building, Turbine Building, & Intake Structure Water Height

- Internal Flooding; Revision 1-A

- NSPM Calculation 07-029; Reactor Building, Turbine Building, & Intake Structure Water Height

- Internal Flooding; Revision 0-B

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

- 2300; Reactivity Adjustment; August 11, 2018

- SEG#: M-8117S-703; Power Suppression Testing; Revision 1

- SEG#: RQ-SS-17E; Design Basis Earthquake with RWCU Leak Requiring Reactor Scram;

Revision 0

- SEG#: RQ-SS-17E; Training Cycle Simulator Crew Evaluation; August 8, 2018

- Type 2 ODMI 501000015242; Offgas Sample Data Indicates That a Minor Cladding Defect

has Occurred; August 8, 2018

- Work Order (WO) 700041635; Power Suppression Testing; August 11, 2018

71111.12Maintenance Effectiveness

- WO 700041635; Power Suppression Testing; August 11, 2018

- CAP 501000014730; ACE EOC MO-2036, HPCI Turbine Supply Steam Valve

- Apparent Cause Evaluation (ACE) 501000012880; Apparent Cause Evaluation for Steam

Leak from Valve Packing on AO-2-86C, C Outboard MSIV; July 25, 2018

- Style9000EVSP-LE; Valve Stem Packing Installation Instructions; Revision 01-17

- CAP 501000001962; Process Fluid Heat Rise on HPCI

- CAP 501000002002; Process Fluid Heat Rise on RCIC

- POD 500000279598; Update Prompt Operability Review HPCI/RCIC Steam Line Isolation

Valves; July 6, 2018

- EE 608000000032; EQ Material Evaluation of HPCI/RCIC MOVs; No Date

- EE 608000000183; Update to Thermal Aging Evaluation performed in Engineering

Evaluation 608000000032; No Date

- CAP 501000012766; Thermography Results of HPCI/RCIC MOVs

- CAP 501000014669; ACE EOC AO-2-86A, A Outboard MSIV

- CAP 501000014688; ACE EOC AO-2-86D, D Outboard MSIV

- AOV12; Test Data Evaluation AOV Rising Stem Valve AO-2-86A; April 23, 2011

- WO 522228; Inspect and Replace Disc Trunnion Pin in AO-2-86C; April 25, 2017

- WO 522228; Inspect and Replace Disc Trunnion Pin in AO-2-86C; May 2, 2017

71111.13Maintenance Risk Assessments and Emergent Work Control

- 0255-06-IA-1; HPCI Quarterly Pump and Valve Test; September 18, 2018

- 0255-06-III-1; HPCI Comprehensive Pump and Valve Test; Revision 29

- 4150-01-PM; SBLC 11 Pump & Gear Motor; August 13, 2018

- 8906; UT System Full Check Following Draindown; September 12, 2018

- CAP 201000017071; HPCI Jack Bolt Connection Weld Crack

- CAP 501000015357; 11 SBLC Accumulator Leakage

- CAP 501000016705; CST 103-1/104-1 Failed to Seat

- CAP 501000016727; Procedure Does Not Identify AST Impact

- CAP 501000017012; HPCI Shaft Guard Rubbing - 0255-06-IA-1

- EC 7721; Vibration Measurement Mounting Pad for HPCI Drain Pump; No date

- NH-36248; P&ID Core Spray System; Revision 89

- NH-36250; P&ID High Pressure Coolant Injection System; Revision 86

- WO 700031258; 0255-03-IA-1-1, CSP A Quarterly Pump and Valve Test;

September 12, 2018

- WO 700042331; Repair/Replace CST-103-1 as needed; September 12, 2018

71111.15Operability Determinations and Functionality Assessments

- 0255-06-III-1; HPCI Comprehensive Pump and Valve Tests; Revision 29

- CAP 501000013909; Holes in A CREF Fan Boot

- CAP 501000016705; CST 103-1/104-1 Failed to Seat

- CAP 501000016727; Procedure does not Identify AST Impact

- CAP 501000017012; HPCI Shaft Guard Rubbing

- CAP 501000017071; HPCI Jacking Bolt Connection Weld Crack

- EC 7721; Vibration Measurement Mounting Pad for HPCI Drain Pump; No Date

- ECE 501000016705; CST 103-1/104-1 Failed to Seat; Revision 0

- EE 86-048; Jack Bolt Plates for HPCI Pump Alignment; No Date

- FP-OP-OL-01; Operability/Functionality Determination; Revision 21

- NH-36248; P&ID Core Spray System; Revision 89

- P&ID NH-36249; HPCI Hydraulic Control and Lubrication System; Revision 78

- P&ID NH-36250; High Pressure Coolant Injection System; Revision 86

71111.18Plant Modifications

- EC 28450; Engineering Change - Security Physical Upgrades Phase 2 Project (EWS IDS and

Cameras); January 25, 2018

- WO 7000009075-0080; EC-26181 Pre-Operational Testing Plan; Revision 1

- WO 7000009075-0080; Pre-Operational Testing from Bus 16 Open Phase Vulnerability

Project Controls and Equipment; Various Dates

71111.19Post Maintenance Testing

- P&ID NH-36250; High Pressure Coolant Injection System; Revision 86

- NH-36049; P&ID Instrument Air System; Revision 85

- WO 700009045; Precision PMT-D311-07, RCIC MO-2096 (250VDC Supply);

August 6, 2018

- WO 700014459; 13 RHR Pump Suction Relief Valve, RV-1992 PMT/RTS;

September 4, 2018

- WO 700029168; 15 Air Dryer Inlet and Exhaust Valve Assembly PMT; August 16, 2018

- WO 700030791; B CS Line PCV, PCV 2459 PMT; August 24, 2018

- WO 700040845; 13 RHR Pump, P202A PMT, 0255-04-III-1A, RHR Comprehensive Pump and

Valve Tests; September 6, 2018

- WO 700042331; Repair/Replace CST-103-1 as Needed; September 12, 2018

71111.22Surveillance Testing

- CAP 501000014395; Spare B CREF Boot Localized Degradation

- Ops Man B.08.01.03-01; RHR Service Water System; Revision 12

- P&ID NH-36664; RHR Service Water & Emergency Service Water Systems; Revision 95

- WO 700028129; 0255-11-IA-7, SW-101 and SW-102 Valve Operability Test; July 2, 2018

- WO 700028916-0011; B EFT Filter Efficiency and Leak Tests; Revision 38

- WO 700029232; 0187-01B, 11 Emergency Diesel Generator/11 ESW Monthly Pump & Valve

Tests; August 14, 2018

- WO 700030794; 0255-08-IA-1, RCIC Quarterly Pump and Valve Test; August 6, 2018

- WO-700029264-0010; ECCS Pump Motor Cooler Flush; Revision 38

71114.02Alert and Notification System Testing

- 1317; Emergency Alert Notification System Test; Revision 23

- 1359; Public Alert Notification Systems (PANS) Weekly Cancel Signal Test and Monthly

Activation Test; Revision 21

- 1408; Annual PANS Performance Review; Revision 9

- Annual Review of the Monticello Nuclear Generating Plants Public Alert and Notification

System (PANS) Performance; January 12, 2017

- Annual Review of the Monticello Nuclear Generating Plants Public Alert and Notification

System (PANS) Performance; January 19, 2018

- ANS; Alert and Notification System Design Report; Revision 2

- CAP 501000000351; Sirens W-20 and W-21 Indicated Failures

- CAP 501000006158; Siren W52 Indicated Failure

- CAP 501000008087; ANS sirens W-11, 24, and 42 Batteries

- CAP 501000009754; EP ANS Siren Life Cycle Management

- Siren Testing and Maintenance Data; August 2016 through August 2018

71114.03Emergency Response Organization Staffing and Augmentation System

- 1317; Emergency Alert Notification System Test; Revision 23

- 5790-102-04; Emergency Call List - NUE; Revision 105

- 5790-104-04; Emergency Call List - Alert/Site Area/General; Revision 127

- A.2-001: Emergency Organization; Revision 57

- A.2-106; Activation and Operation of the TSC; Revision 42

- A.2-107; Activation and Operation of the OSC; Revision 39

- A.2-111; Activation and Operation of the Alternative Facilities During a Security Threat;

Revision 5

- A.2-802; Activation and Operation of the EOF; Revision 23

- CAP 501000000037; EP Augmentation Test Issues

- CAP 501000015058; MSRC - DEP Improvement Actions

- Current ERO Team Roster; August 31, 2018

- ERO Augmentation Drill Records; January 2016 - April 2018

- ERO Training and Qualification Records (Sample)

- FL-BEP; Fleet Emergency Plan Training Program Description; Revision 0

- MNGP 1317; Emergency Alert Notification System Test; Revision 26

- Monticello Nuclear Generating Plant On-Shift Staffing Analysis; Revision 5A

- MT-BEP; Monticello Emergency Plan Training Program Description; Revision 23

71114.05Maintenance of Emergency Preparedness

- 2017 Emergency Planning Guide and Calendar; No Date

- 2018 Emergency Planning Guide and Calendar; No Date

- A-EP-MNGP-2017-1; MNGP NOS Emergency Preparedness Audit - 2017;

February 14, 2017

- A-EP-MNGP-2018-1; MNGP NOS Emergency Preparedness Audit - 2018; May 14, 2018

- CAP 501000000419; EP Required Drill Not Completed

- CAP 501000007478; EP Equipment Not Functionally Checked

- CAP 501000008277; NOS Semiannual HP Drills

- CAP 501000008298; NOS Minor Issues with Backup EOF

- CAP 501000011189; EP Drill - Improvement Opportunities

- CAP 501000011197; EP Drill - EOF Communication Gaps Roll-up

- CAP 501000011321; EP Drill - Review EOF Physical Layout

- CAP 501000011743; Phone Issues in EOF

- CAP 501000014515; EP Exercise - Pre-staging

- EP Critique Report - RPSS Series Tabletop; April 24, 2018

- EP Critique Report - 2016 Q4 Table-Top Series w/DEP; February 27, 2017

- EP Critique Report - April 25th 2018 Full Scale Drill; May 25, 2018

- EP Critique Report - August 29, 2017 EP Exercise; September 22, 2017

- EP Critique Report - July 25th 2017 Full Scale Drill; August 8, 2017

- EP Critique Report - Medical Drill Report; November 29, 2017

- EP Critique Report - OSC Tabletop Drill; July 19, 2017

- FP-EP-SURV-05; Requirements for Annual Independent Review of EP Program; Revision 3

- KLD TR - 505; Monticello Nuclear Generating Plant Evacuation Time Estimate; Revision 1

- KLD TR - 966; Monticello Nuclear Generating Plant 2017 Population Update Analysis;

October 30, 2017

- MNGP 1225; Emergency Procedures Monthly Contact Verification; Revision 62

- MNGP 1230; Emergency Response Facility Instrumentation Functional Test; Revision 43

- MNGP 5791-900-01; Emergency Equipment Inventory; Revision 42

- Monticello Nuclear Generating Plant Emergency Plan; Revision 52

71114.06Drill Evaluation

- Scenario MNGP 8-29-2018; EP Full Scale Drill Scenario Including Joint Information Center

and Off-site Response Organizations; August 29, 2018

71151Performance Indicator Verification

- NRC Performance Indicator Data; Emergency Preparedness - Drill/Exercise Performance;

3rd Quarter 2017 - 2nd Quarter 2018

- NRC Performance Indicator Data; Emergency Preparedness - Alert and Notification System

Reliability; 3rd Quarter 2017 - 2nd Quarter 2018

- NRC Performance Indicator Data; Emergency Preparedness - ERO Readiness

3rd Quarter 2017 - 2nd Quarter 2018

- NRC Performance Indicator Data; Emergency Preparedness - MSPI AC Power;

3rd Quarter 2017 - 2nd Quarter 2018

- NRC Performance Indicator Data; Emergency Preparedness - MSPI Heat Removal;

3rd Quarter 2017 - 2nd Quarter 2018

- NRC Performance Indicator Data; Emergency Preparedness - MSPI High Pressure Injection;

3rd Quarter 2017 - 2nd Quarter 2018

71152Problem Identification and Resolution

- Monticello Nuclear Generating Plant Emergency Plan; Revision 52

- 9506; Dry Shielded Canister Sealing; Revisions 20 & 21

- CAP 501000005379; TN Issued Supplier Finding on DSC-21-30

- CAP 501000008094; OE-NRC Part 21 2018-02000 Velan Inc.

- CAP 501000009601; OE-NRC Part 21 2017-55-01

- CAP 501000013534; Rigging Damaged Removing HSM Vent

- CAP 501000013804; NOS ID - Issues with Completion Review

- CAP 501000013908; Elevation of DFS Vendor Performance

- CAP 501000014661; Stop Work Order - ISFSI Loading Campaign

- CAP 501000016088; NRC Resident Questions 8-24-2018

- E-52166; Elevation of Vendor Performance on the Dry Fuel Storage Project; July 19, 2018

- E-52290; Recovery Plan for Missed QC Notification - MT 2018 P2P; Revision 3

- FP-MA-COM-02; Oversight and Control of Supplemental Personnel; Revision 6

- FP-PA-OE-01; Operating Experience Program; Revision 27

- OP-2014-001; Monticello Dry Fuel Storage Project Oversight Plan; Revision 4

- QF1814; Supplemental Worker Oversight Plan - Loading of NUHOMS Dry Storage Canister

(DSC 17-30) at Monticello During 2018; April 26, 2018

- SNFP-HQ-000-TN-0012; Xcel Agreement 0057901Contract, Schedule Q - Quality

Assurance/Quality Control Requirements; June 4, 2015

- SNFP-MT-2943-TN-0486; Request for Corrective Action in Area of Human Performance -

Corporate Elevation; July 6, 2018

- WO 700040764-10; Perform Concrete Repairs of HSM; June 25, 2018

60855.1Operation of an Independent Spent Fuel Storage Installation at Operating Plants

- 0000-A; Operations Daily Log - Mode 1; Revision 103

- 0000-B; Operations Daily Log - Mode 2; Revision 115

- 0000-D; Operations Daily Log - Mode 3; Revision 105

- 0000-E; Operations Daily Log - Mode 4; Revision 106

- 0000-H; Operations Daily Log - Mode 5; Revision 104

- 10 CFR 72.212 Evaluations Report; Revision 9

- 2017 Annual Radiological Environmental Operating Report; May 19, 2018

- 2017 Radiation Protection Survey Records of ISFSI HSMs

- 72.212-A; Monticello Nuclear Generating Plant Independent Spent Fuel Storage Installation

Fire Hazards Analysis; Revision 6

- 72.212-B; Monticello Nuclear Generating Plant Independent Spent Fuel Storage Installation

(ISFSI) 10 CFR72.212(b)(5)(iii) Radiological Evaluation; Revision 2

- A-ISFSI-MNGP-2018-1; 2018 Nuclear Oversight Monticello Nuclear Generating Plant ISFSI-

Independent Spent Fuel Storage Installation; April 6, 2018

- ALARA Review RWP -180105; 2018 ISFSI Campaign; April 20, 2018

- Calculation No. 11040-03; ISFSI Dose Rate Calculation based on Monticello Fuel Inventory;

Revision 2

- Calculation No. 11044-0503; Monticello ISFSI Radiological Assessment; Revision 1

- Calculation No. 11044-0504; Dose Rate Limits based on Monticello Fuel Inventory for HSM-H

loaded with 61BTH DSC; Revision 1

- CAP 607000000113; SnapShot Report: 2018 Inspection: NRC 60855.1 Operation of an

ISFSI

- CD 1.1; NSPM Quality Assurance Program Structure; Revision 16

- Document No. 11101-T-001; OS197 Lift Yoke Annual Load Test Procedure;

February 21, 2018

- EC 20702; Deviations of the MNGP ISFSI Loading Operations From the Standardized

NUHOMS UFSAR For the 2013 Loading Campaign; Revision 0

- EC 26930, Appendix F; Deviations of the ISFSI Loading Operation Procedures from the

NUHOMS Updated Final Safety Analysis Report (UFSAR)

- EE 608000000148; ISFSI Bundle Selection

- FCN-721004-1425; UFSAR Change Notice; Revision 0

- HTPT-DSC-ORANO; High Temperature Liquid Penetrant (PT) Examination Using the Color

Contrast Solvent-Removable Method; July 9, 2018

- LM-0311a Qualification Matrix; September 3, 2018

- L-MT-15-056; Exemption Request for Nonconforming Dry Shielded Canister Dye Penetrant

Examinations, Appendix D and E; September 29, 2015

- LR No. 721004-1425; 10 CFR Part 72.48 Screening; Revision 0

- Monticello Nuclear Generating Plant - Issuance of Amendment No. 197 to Adopt Changes to

the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184); March 6, 2018

- Monticello Nuclear Generating Plant Independent Spent Fuel Storage Installation (ISFSI)

CFR 72.212 Evaluations Report; Revision 9

- MSLT-DSC-AREVA; Helium Mass Spectrometer Leak Test Procedure; June 1, 2018

- MT-2018-616; 10 CFR 50.54(q) Review Form

- NCR 2018-175; Lower Trunnion/Transfer Trailer NCR; Revision 1

- NSPM-1; Quality Assurance Topical Report; Revision 13

- NUC-06.02; Selecting Fuel Bundles for ISFSI Storage; Revision 4

- NUH-06-113.54; Equipment Use Certificate; December 26, 2018

- NUHOMS Cask Number 20 Loading Report

- OP-2014-001; Monticello Dry Fuel Storage Project Oversight Plant; Revision 4

- Ops Man B.10.01-05; Dry Fuel Storage - ISFSI: System Operation; Revision 4

- Procedure No. 9503; Dry Shielded Canister Pre-Operational Testing; Revision 16

- Procedure No. 9504; Transfer Cask Lifting Yoke Inspection; Revision 11

- Procedure No. 9505; Preparations for Loading Dry Shielded Canister; Revision 20

- Procedure No. 9506; Dry Shielded Canister Sealing; Revision 25

- Procedure No. 9507; DSC Transport From Refueling Floor to ISFSI; Revision 27

- Procedure No. 9508; DSC Transfer From Transfer Cask to HSM; Revision 22

- Procedure No. 9513; HSM Equilibrium Temperature Monitoring; Revision 6

- CAP 501000016798; Legacy Debris Found on Fuel Bundles

- CAP 501000016850; Empty DSCs Staged for Loading

- CAP 501000016860; Yoke Lift Hook Depiction Opposite Use

- CAP 501000016883; DFS QA Delineation not per Contract

- CAP 501000016916; 2018 ISFSI Inspection - Bypass RF RadM

- CAP 501000016933; NRC Inspector Observations

- CAP 501000017145; ISFSI TS 5.4.1 Calc Improvements

- Qualifications for Welders, NDE PT Technicians, NDE PT QC, and NDE Helium Leak Test

Technician

- SCR-16-0082; 9506 Dry Shielded Canister Sealing Procedure Revision; Revision 0

- SCR-16-0126; Procedure B.10.01-05; Revision 0

- SCR-16-0127; Perform PM Inspection of JMR-86 HSM Door Lift Device; Revision 0

- SCR-16-0169; Evaluate Refuel Floor Loading When DSC Fuel Cask Staged on Floor;

Revision 0

- SCR-16-0235; Procedure 9507 Revision; Revision 0

- SCR-16-0275; Procedure 9507 Revision; Revision 0

- SCR-16-0297; Procedure 9508 Rev 16 Temporary Revision; Revision 0

- SCR-16-0357; Revision to 72.212-A; Revision 0

- SCR-18-0050; Implement MARLA Software for ISFSI Fuel Bundle Selection; Revision 0

- SCR-18-0087; Bypass A Fuel Pool Rad Monitor for Dry Shielded Canister Moves; Revision 0

- SCR-18-0094; Repair HSM Cracks on HSMs not Containing Spent Fuel; Revision 0

- SPM 5.5; RKI Eagle Model 101-TRB Hydrogen Monitor Operating Procedure; Revision 5

- SPM 9.2; NUHOMS 61BTH Type 1 or Type 2 DSC Closure Procedure; Revision 14

- Station ALARA Committee Notes; July 13, 2018

- TN Americas LLC Training Matrix; August 9, 2018

- WO 0054116401; JMR-86 - Inspect HSM Door Lift Device; September 14, 2016

- WO 700008685-0010 and WO 700017822-0010; Reactor Building Crane; December 15, 2017

- WO 700016840-0010; Hoisting Equipment and Rigging Inspection - Slings;

December 14, 2017

- WO 700016840-0020; Hoisting Equipment and Rigging Inspection - Slings;

December 18, 2017

- WO 700027108-0010; RX Building Crane - 90 Day Comprehensive Inspection; June 28, 2018

- WO 700034352-0370; Weekly Inspection of Staged DSCs; September 12, 2018

- WO 700034352-0370; Weekly Inspection of Staged DSCs; September 6, 2018

- WPS TN P8-P8-GT1; Welding Procedure Specification; Revision 3