IR 05000263/2018004

NRC Integrated Inspection Report 05000263/2018004 and 07200058/2018002

ML19039A087
Person / Time
Site:	Monticello
Issue date:	02/06/2019
From:	Hironori Peterson NRC/RGN-III
To:	Church C Northern States Power Company, Minnesota
References
EA-14-193 IR 2018002, IR 2018004
Download: ML19039A087 (16)

Text

urc UNITED STATES ruary 6, 2019

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT NRC INTEGRATED INSPECTION REPORT 05000263/2018004 AND 07200058/2018002

Dear Mr. Church:

On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Monticello Nuclear Generating Plant. On January 8, 2019, 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 findings or violations of more than minor significance were identified during this inspection.

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/

Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-263;72-058 License No. DPR-22

Enclosure:

IR 05000263/2018004; 07200058/2018002

REGION III==

Docket Nos: 50-263;72-058 License No: DPR-22 Report No: 05000263/2018004; 07200058/2018002 Enterprise Identifier: I-2018-004-0022 Licensee: Northern States Power Company, Minnesota Facility: Monticello Nuclear Generating Plant Location: Monticello, MN Dates: October 1 through December 31, 2018 Inspectors: P. Zurawski, Senior Resident Inspector D. Krause, Resident Inspector L. Haeg, Senior Resident Inspector - Prairie Island G. Hansen, Senior Emergency Preparedness Inspector J. Seymour, Operator License Examiner R. Edwards, Senior Health Physicist R. Baker, Senior Operations Engineer Approved by: H. Peterson, Branch Chief Branch 3 Division of Reactor Projects Enclosure

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.

List of Findings and Violations No findings or violations were identified.

Additional Tracking Items Type Issue Number Title Report Status Section Confirmatory EA-14-193, V.1 Restoration of 92702 Closed Order Compliance Condition Confirmatory EA-14-193, V.3 Project Plan Progress 92702 Closed Order and Changes Condition

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.

• November 3, 2018Power was reduced to approximately 92 percent for control rod

sequence exchange;

• November 16, 2018Power was reduced to approximately 9 percent as part of a forced

outage due main generator hydrogen seal leakage. Upon completion of outage

activities, power was returned to 100 percent on November 23, 2018;

• November 24, 2018Power was reduced to approximately 95 percent for control rod

sequence exchange;

• November 30, 2018Power was reduced to approximately 95 percent for control rod

sequence exchange;

• December 11, 2018Power was reduced to approximately 94 percent for control rod

sequence exchange; and

• December 21, 2018Power was reduced to approximately 92 percent for control rod

sequence exchange 2018.

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

71111.04Equipment Alignment

Partial Walkdown (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1) 12 Emergency Diesel Generator (EDG) fuel oil system on October 15, 2018;

(2) Div 2 125 VDC System (D2, D20, D21, D221) on October 23, 2018;

(3) A Control Room Ventilation Damper VD-9216A on November 1, 2018;

(4) Reactor Core Isolation Cooling (RCIC) Protected during High Pressure Coolant Injection

Maintenance on December 17, 2018; and

(5) High Pressure Coolant Injection (HPCI) System on December 19, 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 02-B, East HCU on October 29, 2018;

(2) Fire Zone 02-C, West HCU on October 29, 2018;

(3) Fire Zone 08, Cable Spreading on October 29, 2018;

(4) Fire Zone 01-B, 11 Residual Heat Exchanger/Core Spray Room on December 18, 2018;

and

(5) Fire Zone 03-A, Recirculation Motor Generator Set Room on December 18, 2018.

71111.11QLicensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated SEG # RQ-SS-82 (RCIC Failure, Loss of Control Rod

Drive (CRD) and Scram Discharge Volume (SDV) Failure, Blowndown) and SEG # RQ-SS-141

(Recirculation Pump High Vibration with High Power Hydraulic Anticipated Transient Without a

Scram (ATWS)) on October 3, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated control room licensed operator performance as part of

forced outage 1F01 on November 16, 2018, during reactor downpower activities and

November 21, 2018, during power ascension activities.

71111.11ALicensed Operator Requalification Program and Licensed Operator Performance

Operator Exams (1 Sample)

The inspectors reviewed and evaluated requalification examination results on

November 27, 2018.

71111.12Maintenance Effectiveness

Routine Maintenance Effectiveness (3 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities associated

with the following equipment and/or safety significant functions:

(1) A control room ventilation (CRV) Damper VD-9216A [Vertical Slice] on

October 23, 2018;

(2) Main generator hydrogen leakage on October 29, 2018; and

(3) Maintenance Rule Assessment [(a)(3) periodic evaluation] on November 1, 2018.

71111.13Maintenance Risk Assessments and Emergent Work Control (5 Samples)

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

work activities:

(1) Failure of 152-502 (11 EDG output breaker) to close on October 15, 2018;

(2) A CRV Damper VD-9216A Failure [Vertical Slice] on October 22, 2018;

(3) Main Generator H2 Leakage on October 29, 2018;

(4) C outboard (OB) Main Steam Isolation Valve (MSIV) failure to close on

November 19, 2018; and

(5) Failure of Heating Boiler on December 27, 2018.

71111.15Operability Determinations and Functionality Assessments (5 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

(1) Reactor Building Crane Rail Crack on October 1, 2018;

(2) 12 Residual Heat Removal Service Water (RHRSW) motor low viscosity related oil use

on October 2, 2018;

(3) B CRV Damper failure on October 15, 2018;

(4) Control Room Ventilation Damper VD-9216A failure to open on October 23, 2018; and

(5) 12 Emergency Service Water (ESW) Pump differential pressure outside acceptance

criteria on October 30, 2018.

71111.18Plant Modifications (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Temporary Modification on Stator Water Cooling Purge Flow on October 31, 2018.

71111.19Post Maintenance Testing (6 Samples)

The inspectors evaluated the following post maintenance tests:

(1) 11 EDG air start Solenoid Post Maintenance Testing (PMT) on October 15, 2018;

(2) 152-502 (11 EDG output breaker) installation PMT on October 16, 2018;

(3) A CRV Damper VD-9216A Replace PMT [Vertical Slice] on October 31, 2018;

(4) C OB MSIV PMT on November 21, 2018;

(5) HPCI Oil Leak PMT on December 20, 2018; and

(6) B residual heat removal service water (RHRSW) Quarterly PMT on

December 27, 2018.

71111.20Refueling and Other Outage Activities (1 Sample)

The inspectors evaluated forced outage [1F01 Cycle 29] activities from

November 16, 2018 to November 22, 2018. The forced outage was caused by main

generator hydrogen seal leakage and, while the unit was at lower power operations, the

licensee de-inerted and inspected the drywell for a slow increasing trend in drywell

unidentified leakage rate. Inspectors observed power reduction activities, entered and

inspected the drywell for unidentified leakage, and observed power ascension activities.

71111.22Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (5 Samples)

(1) 14 ESW Quarterly Surveillance on October 22, 2018;

(2) A OB MSIV ECO on November 20, 2018;

(3) 0255-03-IA-1-2; B Core Spray Quarterly Pump and Valve Tests on

November 20, 2018;

(4) 0028-01; Reactor Lo-Lo Level Emergency Core Cooling System (ECCS) Initiation

Surveillance on November 28, 2018; and

(5) 0058; HPCI Steam Line High Area Temperature Test and Calibration on

December 17, 2018.

71114.04Emergency Action Level and Emergency Plan Changes (1 Sample)

The inspectors completed the evaluation of submitted Emergency Action Level and

Emergency Plan changes on November 16, 2018. This evaluation does not constitute

NRC approval.

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification (2 Samples)

The inspectors verified licensee performance indicators submittals listed below:

(1) MS09: Residual Heat Removal Systems-1 Sample

(October 1, 2017 - September 30, 2018); and

(2) MS10: Cooling Water Support Systems-1 Sample

(October 1, 2017 - September 30, 2018).

71152Problem Identification and Resolution

Semiannual Trend Review (1 Sample)

The inspectors reviewed the licensees corrective action program for trends that might be

indicative of a more significant safety issue.

(1) Semi-Annual Trend (May 2018 through October 2018) on October 29, 2018.

Annual Followup of Selected Issues (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program

related to the following issues:

(1) Operator Work Arounds (OWAs) to evaluate the licensees implementation of its

program on December 10, 2018. The basis for this review was that OWAs which cannot

be implemented effectively can increase the baseline core damage or large early release

frequency.

OTHER ACTIVITIESTEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

2702Follow-Up on Traditional Enforcement Actions Including Alternative Dispute Resolution

Confirmatory Orders

The inspectors reviewed documents to determine if adequate corrective actions had been

implemented associated with Confirmatory Order (CO) EA-14-193, NRC Inspection

Report (IR) No. 05000263/2015008 and 07200058/2014001. Specifically, the inspectors

evaluated the corrective actions associated with:

(1) CO Condition V.1: Restoration of Compliance; and

(2) CO Condition V.3: Project Plan Progress and Changes.

INSPECTION RESULTS

Observation 71152 - Semi Annual Trend Review

The inspectors reviewed the licensees corrective action program, during the period of

May 2018 through October 2018, for trends that might be indicative of a more significant

safety issue. During the inspection period, the licensee identified four notable trends: MSIV

packing torque; Fluctuations in Xe133/Xe138 ratio; Rise in Drywell Unidentified Leakrate; and

Main Generator Hydrogen Leakage. As part of routine corrective action program reviews, the

inspectors also noted emerging trends in these areas during the inspection period.

The inspectors performed focused reviews of licensee evaluations for each trend area,

conducted ancillary searches of the corrective action program and held discussions with

licensee management to verify that inputs to these trend evaluations were appropriately

scoped. The inspectors also reviewed interim actions taken by the licensee for each of the

four areas to mitigate the trends until more substantive and final corrective actions were

taken. The inspectors did not identify any concerns with the licensees interim actions during

the inspection period and determined that the scope of each evaluation was appropriate.

In mid-November ongoing licensee evaluation of the main generator hydrogen cooler flange

gasket leakage ultimately led to a forced outage. As part of this outage, licensee

management conservatively decided to de-inert the drywell to further investigate the

increased trend in drywell unidentified leakrate. The inspectors monitored licensee actions to

resolve the hydrogen cooler flange leakage and further investigate the drywell unidentified

leakage. The inspectors did not identify any concerns with the licensees actions.

Observation 71152 - Annual Sample Review

The inspectors reviewed the licensees OWA program since those that cannot be

implemented effectively can increase the baseline core damage or large early release

frequency. Inspector review focused on the period of January 2018 through December 2018

to verify the licensee identifies OWA issues at an appropriate threshold, entering them in the

corrective action program, and planning or taking appropriate corrective actions. Further, the

inspectors considered plant conditions including the cumulative effects of other OWAs.

Overall, the inspectors evaluation included review of the following Performance Attributes of

Table 1 to Inspection Procedure 71152: Classification/Prioritization;

Complete/Accurate/Timely Documentation; and Corrective Action commensurate with safety

significance.

Specifically, inspectors reviewed the licensees operator work around program which is

documented in fleet procedure FP-OP-OB-01, Operator Burden Program. The licensees

Operator Burden Program is made up of four components: Operator Work Arounds, Operator

Burdens, Operator Challenges and, Control Room Deficiencies. Operator Work Arounds

represent the most severe challenges to safe operation of the plant. Operator Burdens are

the next most severe challenges to the operator. Operator Challenges are impactful on the

day to day operation of the plant but not to the level of an Operator Burden. Finally, Control

Room Deficiencies degrade the performance in the main control.

For calendar year 2018, nuclear safety significant equipment conditions identified in the

licensees corrective action system were sampled and reviewed against criteria established

for the above four classification levels defined in the Operator Burden Program. Inspectors

determined that, for calendar year 2018, the licensee had not identified any nuclear safety

significant equipment issues which met the criteria to be defined as an operator work

around. The last such classification had been identified by the licensee in 2017. Inspector

review noted equipment issues categorized in one of the remaining three lower operator

burden categories had occurred. Inspector review concluded those issues were properly

identified and categorized with FP-OP-OB-01 criteria. Further, the inspectors evaluated the

licensees resolution of operator burden issues and had no concerns. Lastly, the inspectors

noted the licensee keeps operator burden issues visible to site staff and management through

its Plant Status Report which is updated on a daily basis. Inspectors found commensurate

operator burden issue status between the corrective action program and daily plant status

reports. Overall, inspectors determined the licensee appropriately classifies and resolves

equipment issues requiring some form of compensatory operator action. The inspectors did

not identify any concerns with the licensees operator burden program.

Confirmatory Title IP#

Order EA-14-193, V.1 Restoration of Compliance (Closed) 92702

Description:

EA-14-193, Condition V.1, Restoration of Compliance, was initially documented in NRC IR

No. 05000263/2015008 and 07200058/2014001 (ML15355A459). CO Condition V.1 states

the licensee shall restore compliance to 10 CFR Part 72 to DSCs 11 through 16 within 5

years of the date the NRC takes final action upon the September 29, 2015, exemption request

pending for DSC 16 (ML15275A023), or the exemption request is withdrawn, whichever is

earlier.

Corrective Action Reference: CAP 01509878; NRC Confirmatory Order: Violations Spent

Fuel Cask NDE; January 26, 2016.

Basis: To restore compliance, the licensee submitted an exemption request to the NRC for

DSC 16 on September 29, 2015 (ML15275A023), and an exemption request for DSCs 11-15

on October 18, 2017 (ML17296A205).

On June 15, 2016, the NRC approved the exemption request for DSC 16 (ML16167A036)

restoring DSC 16 to compliance. On September 20, 2018, the NRC approved the exemption

request for DSCs 11-15 (ML18262A378) restoring DSCs 11-15 to compliance. As such,

DSCs 11-16 were restored to compliance within 5 years of the date the NRC took final action

upon the September 29, 2015, exemption request for DSC 16.

No violations were identified and CO Condition V.1 is considered complete.

Confirmatory Title IP#

Order EA-14-193, V.3 Project Plan Progress and Changes (Closed) 92702

Description:

EA-14-193, Condition V.3, Project Plan Progress and Changes, was initially documented in

NRC IR No. 05000263/2015008 and 07200058/2014001 (ML15355A459). CO Condition V.3

states within 180 calendar days after submittal of the DSCs 11 through 16 project plan, Xcel

Energy shall submit a letter to the Director, DNMS, Region III, regarding progress under the

plan, and any non-editorial changes to the plan. A letter providing a progress update and any

non-editorial plan changes shall be provided every 360 calendar days thereafter to the

Director, DNMS, Region III, until the plan is completed.

Corrective Action Reference: CAP 01509878; NRC Confirmatory Order: Violations Spent

Fuel Cask NDE; January 26, 2016.

Basis: On December 12, 2016, Xcel Energy submitted a project plan to the Director, DNMS,

NRC Region II

I. Subsequent updates to the project plan were received on June 6, 2017

(ML17157B356), and June 1, 2018 (ML18152A165). As such, progress updates were

provided by Xcel Energy every 360 calendar days after the initial project plan until the plan

was complete.

No violations were identified and CO Condition V.3 is considered completed.

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 November 27, 2018, the inspector discussed the completed 2018 Licensed Operator

Requalification Program annual operating test inspection results with Mr.

R. Becker,

Operator Licensing Program Administrator;

• On November 29, 2018, the inspector presented the emergency preparedness program

inspection results to Mr.

G. Holthaus, Site Principal Emergency Preparedness Coordinator,

and other members of licensee staff; and

• On January 8, 2019, the inspectors presented the quarterly integrated inspection results to

Mr.

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

DOCUMENTS REVIEWED

71111.04Equipment Alignment

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

- 2121; Plant Prestart Checklist RCIC System; Revision 15

- B.02.03-06; Reactor Core Isolation Cooling System; Revision 4

- B.08.11-05; Diesel Oil System Operation; Revision 42

- B.08.13-02; Control Room Heating and Ventilation and Emergency Filtration Train;

Revision 12

- DBD-B.09.10; 125 VDC System; Revision 5

- NE-36640-2; 125 VDC Distribution Electrical Scheme; Revision 80

- NE-93503-16; Damper VD-9216A Control; Revision 76

- NH-36051; P&ID Diesel Oil System; Revision 87

- NH-36249; High Pressure Coolant Injection System (Steam Side); Revision 83

- NH-36250; High Pressure Coolant Injection System (Water Side); Revision 86

71111.05Fire Protection Annual/Quarterly

- Strategy A.3-01-B, Fire Zone 01-B; 11 RHR / CS Room; Revision 10

- Strategy A.3-02-B, Fire Zone 2-B; East HCU Area; Revision 14

- Strategy A.3-02-C, Fire Zone 2-C; West HCU Area; Revision 13

- Strategy A.3-03-A. Fire Zone 03-A; Recirc MG Set Room; Revision 8

- Strategy A.3-08, Fire Zone 8; Cable Spreading Room; Revision 15

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

- 2167; Plant Startup; Revision 100

- 2300; Reactivity Maneuvering Procedure; Revision 0

- B.06.05-05; Condensate and Reactor Feedwater System Operation; Revision 54

- MT-LOR-JIT-024S; Reactor Deep Down-Power Evolution; Revision 0

- RQ-SS-141; Simulator Exercise Guide, Recirc Pump High Vibration with High Power Hydraulic

ATWS; Revision 1

- RQ-SS-82; Simulator Exercise Guide, RCIC Failure, Loss of CRD, SDV Failure, Blow-Down;

Revision 5

71111.12Maintenance Effectiveness

- B.06.02.02-05; Generator Hydrogen System Leakage - Large Leak; Revision 27

- B.08.13-02; Control Room Heating and Ventilation and Emergency Filtration Train;

Revision 12

- B.6.2.1/B.9.2; Monticello Maintenance Rule Program System Basis Document-Generator

Physical Design & Generation; Revision 1

- B.6.2.3; Monticello Maintenance Rule Program System Basis Document-Hydrogen Seal Oil

System; Revision 1

- B.6.2.4; Monticello Maintenance Rule Program System Basis Document-Stator Cooling;

Revision 1

- CAP 501000018975; VD-9216A Failed to Open

- CAP 501000019458; Change in Hydrogen Leak

- CAP 501000019750; Non-Sparking Torque Wrench not Available

- Monticello Maintenance Rule (a)(3) Assessment: April 1st 2016 to March 31st 2018;

June 29, 2018

- NE-93503-16; Damper VD-9216A Control; Revision 76

- QF1137; Type 1 Operational Decision Making Checklist - Main Generator (G-1) E-8A SE

Hydrogen Cooler; November 1, 2018

- WO 700044892; VD-9216A does not Stroke; October 26, 2018

- WO 700045079-0070; Floating End H2 Leak Repair; Revision 4

- WO 700045079-0070; High Risk Work Plan-Floating End H2 Leak Repair; November 1, 2018

71111.13Maintenance Risk Assessments and Emergent Work Control

- B.02.04-06; Operations Manual, Main Steam, Figures; Revision 5

- B.06.02.02-05; Generator Hydrogen System Leakage - Large Leak; Revision 27

- B.08.13-02; Control Room Heating and Ventilation and Emergency Filtration Train;

Revision 12

- C.4-B.08.03.A; Loss of Heating Boiler; Revision 20

- CAP 501000018660; 11 EDG Failed to Load

- CAP 501000018975; VD-9216A Failed to Open

- CAP 501000019045; Increased Generator H2 consumption

- CAP 501000019458; Change in Hydrogen Leak

- CAP 501000020063; Parts Tracking for Norgren Valve Assemblies

- CAP 501000020085; C Outboard MSIV Failed to Stroke

- NE-93503-16; Damper VD-9216A Control; Revision 76

- NH-170037; Main Control Room H&V/EFT System; Revision 84

- QF1137; Type 1 Operational Decision Making Checklist - Main Generator (G-1) E-8A SE

Hydrogen Cooler; November 1, 2018

- WO 700010045; Heating Boiler Fire Eye Controller; December 27, 2018

- WO 700042129; Steam Chase Walkdown for AO-2-86C; November 20, 2018

- WO 700044566; 11 DGN Failed to Load; October 15, 2018

- WO 700044892; VD-9216A does not Stroke; October 26, 2018

- WO 700045079; Floating End H2 Leak Repair; Revision 4

- WO 700045687; Heating Boiler Lockout; December 27, 2018

- WO 700045751; Make & Install Clamp on Main Generator; November 8, 2018

- WO 700045753; Heating Boiler Fuel Oil Shutoff; December 27, 2018

71111.15Operability Determinations and Functionality Assessments

- 0187-02A; 12 Emergency Diesel Generator/12 ESW Comprehensive Pump and Valve Tests;

Revision 47

- 3108; Pump/Valve/Instrument Record of Corrective Action; Revision 17

- 4-AWI-09.04.01; Inservice Testing Program; Revision 55

- B.08.13-02; Control Room Heating and Ventilation Emergency Filtration Train; Revision 12

- B.08.13-05; Control Room H&V and EFT; Revision 5

- CAP 501000017224; Noise noted in H-2 trolley rails

- CAP 501000017286; H-2 Rail Chip/Crack Identified

- CAP 501000017723; 12 RHRSW Oil Viscosity Outside Administrative Limits

- CAP 501000017725; Oil Storage Tote Usability in Question

- CAP 501000018116; RX BLDG Crane Post Load PT Tracking

- CAP 501000018579; VD-9093B - CRV Div 2 Tripped

- CAP 501000018975; Operability Determination-VD-9216A Failed to Open

- CAP 501000019355; Operability Determination-Pump dP in Alert Range

- CAP 501000019411; Crane Rail PT Bleed Out Increased

- DBD-B-.08.13; Control Room Heating, Ventilation, and EFT System; Revision 3

- H10.1; ASME Inservice Testing Program; Revision 40

- NE-93503-16; Damper VD-9216A Control; Revision 76

- WO 700032560; 90-day Comprehensive Inspection, Rx BLDG Crane; October 2, 2018

- WO 700042910; Noise Noted from H-2 Trolley; October 3, 2018

- WO 700043825; Dispose of Old Oil and Replace; October 7, 2018

- WO 700044647; CRV Supply Cross Connect Damper; October 15, 2018

71111.18Plant Modifications

- CAP 501000006420; Slight Increase in H2 from Historic Trend

- EC 601000000432; Stator Cooling System T Mod; Revision 2

71111.19Post Maintenance Testing

- CAP 501000021445; P-109D Low Pressure During Surveillance

- WO 700037509; 0255-05-IA-1-2, B RHRSW Quarterly Pump and Valve Tests;

December 27, 2018

- WO 700040981; HPCI Oil Leak PMT; December 18, 2018

- WO 700041247; 11 EDG Start Circuit #2 Air Relay Valve PMT; October 15, 2018

- WO 700042129; PMT for AO-2-86C; November 19, 2018

- WO 700044566;11 Emergency Diesel Generator PMT, October 16, 2018

- WO 700044892; VD-9216A Does Not Stroke; October 26, 2018

71111.20Refueling and Other Outage Activities

- 2300; Reactivity Maneuvering Steps; November 16, 2018

- B.06.02.02-05; Generator Hydrogen System Leakage - Large Leak; Revision 27

- CAP 501000002977; Drywell Floor Sump Rate of Change

- CAP 501000020114; Leakage Found During Drywell Inspection

- SEG# MT-LORJIT-024S; Reactor Deep Down-Power Evolution; Revision 0

71111.22Surveillance Testing

- WO 700037033; 0058, HPCI Steam Line High Area Temperature Test and Calibration

Procedure; Revision 34

- WO 700042129; Perform Fast Stroke for AO-2-86A; November 20, 2018

- WO 700035693; 0255-03-IA-1-2, CSP B Quarterly Pump and Valve Tests;

November 21, 2018

- WO 700034069; 0255-11-III-4, 14 ESW Pump and Valve Tests; October 22, 2018

- WO 700035697; 0028-01 RX LL LVL ECCS INIT XMTR CAL; November 26, 2018

71114.04Emergency Action Level and Emergency Plan Changes

- 5790-101-02; Emergency Action Level Matrix, Revisions; 10, 11, and 12

- A.2-101; Classification of Emergencies; Revision 52

- CAP 501000007470; E-PLAN Time Requirement not in EPIP

- CAP 501000012599; ISFSI EAL EU1.1 Dose Rates

- E-PLAN; Emergency Plan, Revisions; 48 through 51

- FL-BEP-EPT-001G; Emergency Preparedness Coordinator Job Familiarization Guide;

Revision 1

- FL-BEP-EPT-001L; Emergency Plan Change Review Process; Revision 0

- FL-BEP-EPT-001M; Conduct a 50.54(Q) Review Mentoring / Position Specific Guide;

Revision 2

- FP-R-EP-02; 10 CFR 50.54(q) Review Process; Revision 12

- LM-0616; Qualification Lookup for Qualification ID FL-BEP-EPT-001; Revision 0

- Monticello Nuclear Generating Plant 2017 Population Update Analysis; October 30, 2017

- Monticello Nuclear Generating Plant Development of Evacuation Time Estimates; Revision 1

- On-Shift Staffing Analysis; Revision 5

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-536; August 22, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-549; June 8, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-550; June 29, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-564; October 20, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-571, August 16, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-573; October 20, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-580; September 13, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2017-585; October 27, 2017

- QF-0724; 10 CFR 50.54(q) Review Form MT-2018-597; March 14, 2018

- QF-0724; 10 CFR 50.54(q) Review Form MT-2018-598; March 14, 2018

- QF-0724; 10 CFR 50.54(q) Review Form MT-2018-599; March 23, 2018

- QF-0724; 10 CFR 50.54(q) Review Form MT-2018-605; April 19, 2018

- QF-0724; 10 CFR 50.54(q) Review Form MT-2018-607; May 2, 2018

71151Performance Indicator Verification

- MSPI Margin Report (RHR and RHRSW) for September 2018

- NRC Performance Indicator Data; MSPI Cooling Water Systems; October 2017 through

September 2018

- NRC Performance Indicator Data; MSPI Residual Heat Removal; October 2017 through

September 2018

- PRA-CALC-17-006; MNGP PRA Input to the MSPI Basis Document; Revision 1

- UAI and URI MSPI Derivation Reports for RHR and RHRSW; September 2018

- Unavailability Logs for RHR and RHRSW; October 2017 through September 2018

71152Problem Identification and Resolution

- FP-OP-OB-01; Operator Burden Program; Revision 10

- Corrective Action Records (Operator Work Arounds); January 2018 through December 2018

- Plant Status Reports (Operator Burden Issues); January 2018 through December 2018

- Corrective Action Records (Safety Significant Trends); May 2018 through October 2018

2702Follow-Up on Traditional Enforcement Actions Including Alternative Dispute Resolution

Confirmatory Orders

- CAP 1509878; NRC Confirmatory Order: Violations Spent Fuel Cask NDE; January 26, 2016

14