IR 05000263/2019003

Integrated Inspection Report 05000263/2019003 and 07200058/2019001

ML19319A809
Person / Time
Site:	Monticello
Issue date:	11/14/2019
From:	Julio Lara NRC/RGN-III
To:	Church C Northern States Power Co
References
EA-14-193 IR 2019001, IR 2019003
Download: ML19319A809 (26)

Text

ber 14, 2019

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2019003 AND 07200058/2019001

Dear Mr. Church:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On October 22, 2019, the NRC inspectors discussed the results of this inspection with Mr. C. Church, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

Additionally, this inspection focused on assessing one open Condition (V.9) related to Confirmatory Order EA-14-193, issued December 21, 2015 (ML15344A459). Previously Confirmatory Order Conditions V.1, V.2, V.3, V.4, V.5, V.6, V.7, and V.8 were closed in NRC Inspection Report (IR) Nos. 05000263/2017008, 07200058/2017001, 05000263/2018004 and 07200058/2018002. The inspector review of Condition V.9 was satisfactory and the Condition is closed.

The NRC has determined that the results of this inspection, in conjunction with previously completed inspection activities related to interim milestones, provide adequate assurance that the required terms as directed by the December 21, 2015, Confirmatory Order have been satisfied by Northern States Power Company, Minnesota. Confirmatory Order EA-14-193 is closed. 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 Mohammed Shuaibi Acting for/

Julio F. Lara, Director Division of Reactor Projects Docket No. 05000263 and 07200058 License No. DPR-22

Enclosure:

As stated

Inspection Report

Docket Number: 05000263 and 07200058 License Number: DPR-22 Report Number: 05000263/2019003 and 07200058/2019001 Enterprise Identifier: I-2019-003-0062 and I-2019-001-0151 Licensee: Northern States Power Company, Minnesota Facility: Monticello Nuclear Generating Plant Location: Monticello, MN Inspection Dates: July 01, 2019 to September 30, 2019 Inspectors: N. Egan, Sr Physical Security Inspector T. Go, Health Physicist L. Haeg, Senior Resident Inspector D. Krause, Resident Inspector V. Myers, Senior Health Physicist P. Negrete, Security Specialist V. Petrella, Reactor Inspector K. Pusateri, Resident Inspector J. Robbins, Reactor Inspector N. Shah, Project Engineer M. Ziolkowski, Sr Physical Security Inspector P. Zurawski, Senior Resident Inspector Approved By: Hironori Peterson, Chief Branch 3 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at 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 of more than minor significance were identified.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000263/2019-002-00 LER 2019-002-00 for 71153 Closed Monticello Nuclear Generating Plant, Two Manual Primary Containment Isolation Valves Found Open Resulting in a Condition Prohibited by Technical Specification OR EA-14-193 Confirmatory Order for NDE 92702 Closed on Dry Cask Condition V.9

PLANT STATUS

Monticello began the inspection period operating at approximately 100 percent power and, with the following exceptions, remained at that level throughout the inspection period. Environmental temperature and canal discharge temperatures resulted in power reductions to the following approximate power levels: July 15, 2019 (90 percent); July 18, 2019 (90 percent); and July 19, 2019 (80 percent). On September 14, 2019, the unit was down-powered to 73 percent for quarterly turbine valve testing. The unit was returned to 100 percent after each power reduction.

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.

71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.03)

(1) The inspectors evaluated readiness for impending adverse weather conditions for extreme hot weather affecting Canal Discharge Temperatures on July 16, 2019

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

(1) 12 Standby Liquid Control (SBLC) System protected while 11 SBLC in maintenance on August 5, 2019

(2) Reactor Core Isolation Cooling (RCIC) System while protected on September 17, 2019 (3) #13, 250 VDC System while protected on September 18, 2019

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) The inspectors evaluated system configurations during a complete walkdown of the "A" Reactor Protection System (RPS) train that was protected while troubleshooting "B" RPS train on July 23, 2019

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

(1) Fire Zone (FZ) 03-A - Recirculation Motor Generator area on July 26, 2019

(2) FZ 13-C - Turbine Building 911 level motor control center on July 30, 2019

(3) FZ 31-A - Emergency Filtration Train, 1st Floor - Division I on August 6, 2019

(4) FZ 13-B - Rx Feed Water Pump and Lube Oil Reservoir on September 7, 2019

(5) FZ 05-C - Fuel Pool Skimmer Tank Room on September 27, 2019

71111.06 - Flood Protection Measures Inspection Activities - Underground Cables (IP Section 02.02c.)

(1) Vaults 2MH01, 2MH02, 2MH03, 2MH04, CP100, NMH301, NMH302 on August 2, 2019

71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)

(1) 11 Emergency Diesel Generator (EDG) Emergency Service Water (ESW) Heat Exchanger on July 15, 2019

71111.07T - Heat Sink Performance Triennial Review (IP Section 02.02)

(1) Residual Heat Removal Division 2 Heat Exchanger, E-200B

(2) 13 Residual Heat Removal Pump Motor Cooler, P-202C

(3) Ultimate Heat Sink, Section 02.02d, specifically Sections 02.02d.6 and 02.02d.7 were completed

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during minimum shift staffing activities arising from labor actions on September 5, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated Licensed Operator Requalification; MT-LOR-19D-001V, Crew 2 on August 12, 2019

(2) The inspectors observed and evaluated Licensed Operator Requalification; Monticello Emergency Preparedness Evaluated Exercise on September 10, 2019

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

(1) Structural Monitoring of Condensate Storage Tanks on August 28, 2019

(2) 11 and 12 Emergency Diesel Generators on August 29, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

(1) CV-3134: "D" Moisture Separator Drain Tank Drain Valve failure on July 15, 2019

(2) G-6: Security Diesel Engine Cycling issues on July 15, 2019

(3) DPIS-2-129B, Recirculation Loops DP-LPCI Select interlock; Troubleshoot and Repair, on September 15, 2019

(4) VD-9051B, "A" Control Room Ventilation Fresh Air Damper Excessive Oil Leak on September 25, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

(1) Control Rod Drives (CRD) Refurbished without ASME X1 RR Plan on August 1, 2019

(2) Emergency Core Cooling System (ECCS) Instrumentation Recirculation Riser Differential Pressure Instrumentation Switch (DPIS) failed on August 15, 2019

(3) 12 ESW Pump Discharge Check valve missed IST Surveillance on August 22, 2019

(4) Drywell Spray Valve thrust exceeding design basis on September 9, 2019

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(1) Use of low-side switches for DPIS-2-129B, high side failed on August 16, 2019

(2) Removed bad temperature signal point from TR-2-2-31; 11 Recirculation Pump, on September 30, 2019

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

(1) OPS-G-3A, 11 EDG #2 Air start Post Maintenance Test (PMT) on July 16, 2019

(2) RM-7858A, A Stack WRGM PMT on July 18, 2019

(3) 12 EDG PMT on July 23, 2019

(4) OPS-PCIV-2092; RCIC Cooling Water to Barometric Condenser PMT/TRS on September 8, 2019

(5) MO-1751; 11 Core Spray Injection Outboard Isolation Valve PMT on September 11, 2019

71111.22 - Surveillance Testing Surveillance Tests (other) (IP Section 03.01)

(1) "A" Standby Gas Treatment System Filtration Test on July 20, 2019

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 0255-09-IA-1; Recirculation System Valve Operability Test on September 10, 2019

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) 0255-01-IIC-2; Reactor Heat Removal (RHR) System Loop "B" Biennial Leakage Inspection on August 21, 2019

FLEX Testing (IP Section 03.02) (1 Sample)

(1) #12 Flex 480V Portable Diesel Generator G-507 on July 16, 2019

71114.06 - Drill Evaluation Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1) Monticello Full-Scale Emergency Preparedness Drill on August 6, 2019 Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

(1) Licensed Operator Requalification; (DEP) MT-LOR-19D-001V, Crew 1 on August 19,

71124.05 - Radiation Monitoring Instrumentation Walk Downs and Observations (IP Section 02.01)

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

(1) The inspectors reviewed the following:

Portable Survey Instruments

• RO-20 Ion Chamber SN RO79; Calibration Due Date 03/14/2020

• Ludlum Model 9-3; SN 93-1; Calibration Due Date 10/04/2019

• RO-2 SN RO46; Calibration Due Date 03/03/2020

• Portable ARM DRM-2 MGP SN 534030; Calibration Due Date 06/10/2020

• Alpha/Beta Counter iSolo Canberra No. 2; Calibration Due Date 11/28/2019 Source Check Demonstration

• Telepole TP-5; Calibration Due Date 09/11/2020

• Small Article Monitor (SAM); Source Checked on 09/12/2019

• ARGOS 2-B at 931' Elevation Turbine Building; Calibrated on 09/12/2019 Area Radiation Monitors and Continuous Air Monitors

• A-1 Refuel Floor Low Range

• A-2 Refuel Floor High Range

• A-6 1001' Decon Area

• A-7 985' Sample Hood

• A-8 Reactor Clean Up Demineralizer Area

• A-19 Chemistry Lab

• F-1 Off-Gas Stg Bldg Foyer

• F-2 Off Gas Stg Foyer High Range

• RM-79932 DryWell CAM Rad Monitor at 935' Elevation Reactor Building Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

• ARGOS 2-B at 931' Turbine Building; Calibrated on 09/12/2019

• Small Article Monitor (SAM)

• PM-3 GEM-5; Canberra Portal Monitors

Calibration and Testing Program (IP Section 02.02) (1 Sample)

The inspectors evaluated the calibration and testing program implementation.

(1) The inspectors reviewed the following:

Alarm Setpoint and Calibration Method Check of Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

• Small Article Monitor (SAM); Source Checked on 09/12/2019

• ARGOS 2-B at 931' Turbine Building; Calibrated on 09/12/2019 Failure to Meet Calibration or Source Check Acceptance Criteria

• ARGOS 2-B at 931' Turbine Building; Calibrated on 09/12/2019

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walk Downs and Observations (IP Section 02.01)

The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:

(1)

• Reactor Building Wide Range Gaseous Monitors

• Plant Stack Wide Range Gaseous Monitors

• Service Water Liquid Monitor

• Discharge Canal Liquid Monitor

• Turbine Building Normal Waste Sump Liquid Monitor

• Standby Gas Treatment Filtration System Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)

The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:

(1)

• Plant Stack Wide Range Gaseous Effluent Monitor Train "A"

• Service Water Liquid Effluent Monitor

• Turbine Building Normal Waste Sump Liquid Monitor

Sampling and Analysis (IP Section 02.03) (1 Sample)

The inspectors reviewed the following:

(1) Radioactive Effluent Sampling and Analysis Activities

• Plant Stack Continuous Discharge Sampling

• Reactor Building Continuous Discharge Sampling

• Turbine Building Normal Waste Sump Discharge Sampling

Instrumentation and Equipment (IP Section 02.04) (1 Sample)

The inspectors reviewed the following radioactive effluent discharge system surveillance test results:

(1) Standby Gas Treatment System

Dose Calculations (IP Section 02.05) (1 Sample)

The inspectors reviewed the following to asses public dose:

(1) Liquid and Gaseous Discharge Permits

• Drywell Purging via Stack, MTGB2018-101

• Plant Stack Continuous, MTGC2019-026

• Reactor Building Vent Continuous, MTCG2019-032 Annual Radiological Effluent Release Reports

• 2017 Annual Radiological Effluent Release Report

• 2018 Annual Radiological Effluent Release Report Abnormal Gaseous or Liquid Tank Discharges

• Abnormal Liquid Discharge, MTLB2007-002

71124.07 - Radiological Environmental Monitoring Program Site Inspection (IP Section 02.01)

The inspectors evaluated the radiological environmental monitoring program implementation.

(1) The inspectors reviewed the following:

Walkdowns, Calibrations, and Maintenance Record Review

• Air Station M-1 Location within 11 miles at Sector NW (Control)

• Air Station M-2 Location within 0.8 miles at Sector SE

• Air Station M-3 Location within 0.6 miles at Sector ESE

• Air Station M-4 Location within 0.8 miles at Sector SSE

• Air Station M-5 Location within 2.6 miles at Sector SE

• TLD M09A County Road 75, 0.38 miles at Sector SSW

• TLD M10A County Road 75, 0.38 miles at Sector SW

• TLD M07A Parking Lot H, 0.47 miles at Sector SSE

• TLD M04S Pinewood School, 2.3 miles at Sector SE

• TLD M06S Monticello Public Works. 2.6 miles at Sector SE

• No. 5829; REMP Air Samplers Calibration; dated 02/13/2018

• Dose Assessment for Operation of MNGP During 2018 Calendar Year Calculation

• 154-Rascal Data Validation MET/Rad Data Sources; dated 07/23/2019 Environmental Sample Collections and Preparation Observation

• River Water M-8(c) Upstream of the Plant within 1000 ft Upstream of the Plant Intake

• River Water M-9 Downstream of the Plant within 1000 ft Downstream of the Plant Discharge

• Vegetation M-41 Training Center within 0.8 miles at Sector SSE

• Vegetation M-42 Biology Station Road within 0.6 miles at Sector SE Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement

• River Water Sampling Upstream M-8; water frozen entire month, no composite for 2018

• Air Station M-2; station lost power from the service drop, sampler was restarted on 06/08/2018 with temporary power

• Fish Samples M-8 and M-9; invertebrate samples were collected late due to unsafe river conditions; Spring 2018

• M-8 on the 4th Quarter 2018 quarterly composites were not collected; due to frozen water; dated 11/07/2018 Sampling Program for the Potential of Licensed Material Entering Groundwater

• Monitoring Well MW-9A has indicated elevated tritium level; tritium plume originated from process water that migrated through turbine building; it was discovered in 2009 and corrected in 2011 after analysis and remediation

• Monitoring Well MW-10; tritium is regularly identified on this well part of the groundwater monitoring of below grade piping under the Turbine Building Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)

(1) The inspector reviewed licensee's actions as a result of a leak through MW-9A surveillance originated from process water that migrated through turbine building that was discovered in 2009 and it was corrected in 2011. Ongoing surveillance per Groundwater Protection Initiative at the time of the inspection.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification MS06: Emergency AC Power Systems (IP Section 02.05)

(1) Unit 1 (07/01/2018 - 06/30/2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) Unit 1 (07/01/2018 - 06/30/2019)

MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)

(1) Unit 1 (07/01/2018 - 06/30/2019)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) Unit 1 01/01/2018 - 12/31/2018 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) Unit 1 01/01/2018 - 12/31/2018 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) Unit 1 01/01/2018 - 12/31/2018

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action and adverse condition monitoring programs for potential adverse trends involving safety system leakage that might be indicative of a safety issue during the weeks of September 16 & 23, 2019.

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Repeat issues with RCIC Primary Containment Isolation Valve (PCIV) instrumentation on September 30, 2019

(2) Repetitive leaking vent/siphon quick connect fitting prior to completing sealing operations on Dry Shielded Canisters dated February 6 through September 30, 2019

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

(1) LER 2019-002, Two Manual Primary Containment Isolation Valves found open resulting in a condition prohibited by Technical Specifications (ADAMS accession:

ML19221B735.) Inspector review of the circumstances of this LER was conducted as part of Inspection Report 05000263/2019002. A Green Non-Cited Violation of Technical Specification 5.4.1.a had been identified in Section 71153 of that report.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===92702 - Follow-up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders Follow-up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders (1 Sample)

(1) The inspectors reviewed documents to determine if adequate corrective actions had been implemented associated with Confirmatory Order (CO) EA-14-193, and NRC IR Nos. 05000263/2015008 and 07200058/2014001. Specifically, the inspectors evaluated the corrective actions associated with CO Condition V.9: Completion Letter.

92709 - Licensee Strike Contingency Plans Licensee Strike Contingency Plans ===

(1) On August 31, 2019, at midnight, the contract between the United Security Professionals (USP) Local 2, who represent security supervisors, and G4S expired.

In preparation for the strike/lockout, the NRC inspectors evaluated the adequacy of the licensees contingency plan. The inspectors assessed the adequacy of the strike/lockout staffing levels, staff training and qualifications, safety conscious working environment, and site access in meeting operational and security requirements.

92711 - Continued Implementation of Strike Plans During An Extended Strike Continued Implementation of Strike Plans During An Extended Strike

(1) On August 31, 2019, at midnight, the contract between the United Security Professionals (USP) Local 2, which represents MNGPs security supervisors, and G4S expired. During the strike/lockout, the NRC inspectors evaluated the adequacy of the licensees implementation of its contingency plan. The inspectors assessed:

1. The augmented security supervisor force transition of duty

2. The continuity of security force operation

3. The impact of plant operations, minimum staffing requirements, safety conscious working environment, and site access

92712 - Resumption of Normal Operations After A Strike Resumption of Normal Operations After A Strike

(1) On September 6, 2019, a tentative contract between the United Security Professionals (USP) Local 2, which represents MNGPs security supervisors, and G4S was reached. On September 9, 2019, MNGPs security supervisors returned to duty. The contract was ratified on September 24, 2019. During the resumption of normal operations following the strike/lockout, the NRC inspectors evaluated the adequacy of the licensees transition from a strike/lockout condition to normal plant operation.

INSPECTION RESULTS

Observation: Adverse Condition Monitoring Program - Safety System Leakage 71152 The inspectors did a semi-annual review, in aggregate, of safety system leakage issues being monitored as part of the licensee's adverse condition monitoring program. Programmatic requirements and processes were also reviewed to determine whether active safety system leakage adverse conditions were being appropriately tracked, managed, and resolved. The inspectors also reviewed whether the licensee was appropriately monitoring adverse conditions by establishing criteria or set points for which further evaluation or action was designated. The inspectors determined, overall, that the licensee was effectively managing adverse conditions and no concerns were identified as part of this review.

Observation: RCIC Primary Containment Isolation Valve Issues 71152 As part of routine corrective action program document reviews, the inspectors noted a trend in repetitive issues with reactor core isolation cooling primary containment isolation instrumentation. Specifically, inspector's noted Quality Management Issue (QIM)501000030703 identified differential pressure indicating switch (DPIS) DPIS-13-84 (RCIC High Steam Flow Isolation) had been found out of its As-Found tolerances on August 13, 2019 during its quarterly calibration. Review of the calibration history for this component determined that the DPIS had been outside of its As-Found tolerances six times in the last two years. In each case the DPIS was restored to within As-Left tolerances with no issues.

Inspectors reviewed licensee actions to the QIM and determined the licensee appropriately implemented its corrective program in regard to identification, disposition, and correction of the issue. Given the trend, the inspectors also reviewed the licensee's extent of condition and determined it included a review of calibration history for RCIC high steam flow isolation DPIS (13-83) as well as both HPCI high steam flow switches (DPIS-23-76A & DPIS23-76B).

Overall, the licensee evaluation of the As-Found switch out of tolerances were a result of drift between calibrations and remained in the conservative direction. Inspectors determined the licensee established an action to evaluate expanding the DPIS set-point bands. Overall, the inspectors did not identify any concerns as part of this review.

Observation: Dry Canister Vent/Siphon Helium Leakage 71152 As part of routine corrective action reviews, the inspectors noted two licensee-identified issues relating to dry storage canister vent/siphon helium leakage. Inspectors determined these issues to be noteworthy of further review because of an open dry cask storage Confirmatory Order. Inspectors determined the licensee appropriately documented the two issues in its corrective action system. The inspectors reviewed licensee corrective actions associated with each issue and did not have any concerns. Additionally, the inspectors determined that as part of the licensee's extent of condition review, two additional helium leakage issues had been identified by the licensee. Similar reviews were conducted by the inspectors with no concerns identified. Overall, inspectors determined the licensee adequately implemented its corrective action program no concerns were identified as part of this review.

Confirmatory Order Confirmatory Order for NDE on Dry Cask Condition V.9 92702 (Closed) OR

Description:

Condition V.9 stated "Upon completion of all terms of the Confirmatory Order, Xcel Energy shall submit to the NRC a letter discussing its basis for concluding that the Order has been satisfied." On March 26, 2016, Xcel Energy submitted a letter to describe the completion of actions taken to satisfy all the CO conditions. With the submission of the completion letter on March 26, 2019, CO Condition V.9 is considered complete. Previously CO Conditions V.1, V.2, V.3, V.4, V.5, V.6, V.7, and V.8 were closed in NRC Inspection Report (IR) Nos.

05000263/2017008, 07200058/2017001, 05000263/2018004 and 07200058/2018002.

EA 14-193

EXIT MEETINGS AND DEBRIEFS

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

• On October 22, 2019, the inspectors presented the integrated inspection results to Mr. C. Church, Site Vice President and other members of the licensee staff.

• On July 25, 2019, the inspectors presented the Radioactive Gaseous/Liquid Effluent Treatment and REMP Inspections inspection results to Mr. D. Barker, Plant Manager and other members of the licensee staff.

• On August 23, 2019, the inspectors presented the Exit Meeting inspection results to Mr. D. Barker, Plant Manager and other members of the licensee staff.

• On September 13, 2019, the inspectors presented the Radiation Monitoring inspection results to Mr. C. Church, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 501000029549 Down Power due to Environmental Conditions 0

Documents 501000029601 River Appropriation Limits Reached 0

71111.04Q Drawings NE-36640-4 250V DC Distribution & Panel Schedule D31, D33 76

NH-36251 P&ID RCIC (Steam Side) 80

NH-36252 P&ID RCIC (Water Side) 82

NH-36253 Standby Liquid Control System 80

NX-7879-4 Standby Liquid Control System Process Diagram 002

Miscellaneous B.09.09-01 250 VDC System; Function and General Description of 3

System

Procedures 0913-01 No. 13 250 VDC Battery Operability Check (Division 1) 35

71111.04S Drawings NE-36771-4 Reactor Protection Power System Distribution Panel Y40 & 77

Y50

NX-7834-63 Elementary Diagram RPS MG Set Control 075

NX-7834-67-10 Elementary Diagram Reactor Protection System 76

Miscellaneous B.09.12-05 Reactor Protection Power Supplies - System Operation 31

71111.05Q Fire Plans A.3-03-A Fire Strategy for Zone 3-A - Recirculation Motor Generator 8

Set Room

A.3-05-C Fire Strategy for Zone 5-C - Fuel Pool Room 6

A.3-13-B Fire Strategy for Zone 13-B - Turbine Building (Feed Water 13

Pump Area) - Elevation 911

A.3-13-C Fire Strategy for Zone 13-C - Turbine Building Basement - 11

MCC Area East

A.3-31-A Fire Strategy for Zone 31-A - Emergency Filtration Train 11

Building - 1st Floor (Division 1)

71111.06 Calculations07-021 Reactor Building, Turbine Building, & Intake Structure Water 1-A

Height - Internal Flooding

07-029 Reactor Building, Turbine Building, & Intake Structure Water 0-B

Height - Internal Flooding

Drawings NF-36763 Raceways, Grounding & Direct Buried Cable Runs - South 81

Turbine Generator Building

Miscellaneous DBD-S.04 Intake Structure 7

71111.07A Work Orders 700040957 EDG ESW Heat Exchanger Performance Test 08/29/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.07T Calculations07-045 RHR Pump Motor Model 5K511DT5410 Cooling Coil 2A

Minimum Flow Evaluation

97-056 Determination of RHR Heat Exchanger U-Values and K- 3

Values at Various Flow Conditions

Calibration LT-1852 and LT-1853 Calibration Records

Records

Corrective Action 01517655 13 RHR Motor Outlet Cooling Flow Less Than Required 04/03/2016

Documents 501000007157 13 RHR Motor Flow < 2 gpm via FI-4955 01/11/2018

501000021445 P-109D Low Pressure During Surveillance 12/27/2018

501000026135 B FSW Leak in Elbow 04/23/2019

Corrective Action 501000030960 NRC Question 08/19/2019

Documents 501000030967 2019 UHS - A.6 River Temp Question 08/20/2019

Resulting from 501000031066 2019 UHS - OG Comp Leak Into Cooling SYS 08/22/2019

Inspection

Drawings NH-36664 P&ID RHR Service Water & Emergency Service Water 95

Systems

NH-36665 P&ID Service Water System & Make-Up Intake Structure 104

Miscellaneous 11 CW PMP Pit Level and the 12 CW PMP Pit Level Trend

Report

1R29 SW/MIC Results Summary Table

1R28 SW/MIC Results Summary Table

IST-ESW Pump 14 Vibration Trends

IST-ESW Pump 13 Vibration Trends

IST - ESW Pump 12 Vibration Trends

IST - ESW Pump 11 Vibration Trends

IST - RHRSW Pump 14 Vibration Trends

IST - RHRSW Pump 13 Vibration Trends

IST - RHRSW Pump 12 Vibration Trends

IST - RHRSW Pump 11 Vibration Trends

NDE Reports XCEL11-MN1-03 Final Eddy Current Inspection Report NO: XCEL#11-MN1- 03/24/2011

of Residual Heat Removal RHR HX E-200B for

Monticello Nuclear Generating Plant RFO25 - March 2011

Procedures A.6 Acts of Nature 60

Inspection Type Designation Description or Title Revision or

Procedure Date

EWI-11.01.14 Buried Piping and Tanks Inspection 1

FP-PE-FAC-01 FAC Program 17

FP-PE-SW-01 SW/MIC Program 14

FP-PE-UPT-01 Underground Piping and Tanks Integrity Program 2

Work Orders 00394234 PM 4058-1 ("A" RHR Room MTR Cooler Cleaning & Test) 04/09/2011

00440540 PM 4058-1 ("A" RHR Room MTR Cooler Cleaning & Test) 04/20/2013

00491126 PM 4126 (Inspect West Service Water Bay) 04/24/2015

00491127 PM 4125 (Inspect East Service Water Bay) 05/07/2015

00504142 P-202C/MTR, Replace Motor Cooling Coil 09/01/2015

00519464 1136-02 RHR Heat Exchanger Efficiency Test - DIV II 02/23/2017

00529075 0255-11-III-3 13 ESW Pump Flow Test 04/03/2016

00531773 1404-01 11 EDG ESW Heat Exchanger PRFM Test 11/22/2016

00533934 PM 4126 (Inspect West Service Water Bay) 05/14/2017

00534534 0255-05-IA-1-2 "B" RHRSW QRTRLY PMP & Valve Test 06/30/2016

00534919 0255-11-III-3 13 ESW Pump Flow Test 07/07/2016

00535068 0255-05-IIC-1 RHRSW System Leakage Test - Loop A 04/25/2017

00535069 0255-11-IIC-1 ESW System Leakage Test - Loop A 04/22/2017

00535070 0255-11-IIC-3-1 EDG-ESW Loop A Leak TST-Access 07/10/2016

Compon

00535071 0255-11-IIC-3-2 EDG/ESW Leak Test - Loop A Buried 11/22/2016

Piping

00540063 0255-05-IA-1-2 "B" RHRSW QRTRLY Pump & Valve Test 09/30/2016

00540526 0255-11-III-3 13 ESW Pump Flow Test 10/14/2016

00545290 0255-05-IA-1-2 "B" RHRSW QRTRLY Pump & Valve Test 12/28/2016

00545647 0255-11-III-3 13 ESW Pump Flow Test 01/06/2017

00549811 0255-05-IA-1-2 "B" RHRSW QRTRLY Pump & Valve Test 03/30/2017

00550108 0255-11-III-3 13 ESW Pump Flow Test 04/04/2017

00554448 0255-05-IA-1-2 "B" RHRSW QRTRLY Pump & Valve Test 06/30/2017

00554799 0255-11-III-3 13 ESW Pump Flow Test 07/06/2017

533935 E Service Water Bay 09/22/2016

700014461 RHR Heat Exchanger Efficiency Test 12/18/2018

700014471 "B" RHRSW Quarterly Pump and Valve Tests 12/28/2017

700017684 13 ESW Quarterly Pump and Valve Tests 10/05/2017

Inspection Type Designation Description or Title Revision or

Procedure Date

700017685 13 ESW Quarterly Pump and Valve Tests 01/11/2018

700021812 Comprehensive 12 RHRSW Pump and Valve Tests 04/02/2018

700026492 RHR Pump 13 and Core Spray Pump 11 Motor Cooler 06/18/2018

Chemical Cleaning

700027873 "B" RHRSW Quarterly Pump and Valve Tests 05/11/2018

700028135 13 ESW Quarterly Pump and Valve Tests 07/05/2018

700028543 West Service Water Bay Inspection/Dredging 05/14/2019

700028562 EDG ESW Heat Exchanger Performance Test 09/05/2018

700031712 RHR Service Water System Leakage Test - Loop B 04/24/2019

700031715 Emergency Service Water System Leakage Test - Loop B 05/06/2019

700031716 EDG-ESW System Leakage Test Loop B Accessible 08/09/2018

Pressure Boundary Components

700032957 13 ESW Comprehensive Pump and Valve Test 04/04/2018

700033107 "B" RHRSW Quarterly Pump and Valve Tests 06/26/2018

700033331 13 ESW Quarterly Pump and Valve Tests 10/10/2018

700033406 East Service Water Bay Inspection/Dredging 04/27/2019

700036565 "A" RHRSW Quarterly Pump and Valve Tests 12/06/2018

700037422 "B" RHRSW Quarterly Pump and Valve Tests 09/27/2018

700037458 "B" RHRSW Quarterly Pump and Valve Tests 12/28/2018

700038490 13 ESW Quarterly Pump and Valve Tests 01/09/2019

700042061 12 Emergency Diesel Generator / 12 ESW Quarterly Pump 02/01/2019

and Valve Tests

700045733 "B" RHRSW Quarterly Pump and Valve Tests 03/29/2019

700046070 13 ESW Quarterly Pump and Valve Tests 04/12/2019

700050083 "B" RHRSW Quarterly Pump and Valve Tests 06/27/2019

700054695 MT:1:ESW:ESW5-4-HBD 1

700054695 Pipe 1

71111.11Q Miscellaneous Monticello Nuclear Generating Plant Emergency Plan Full 09/10/2019

Exercise

MT-LOR-19D- Simulator Exercise Guide (Crew 2) 4

001V - RQ-SS-

113

71111.12 Corrective Action 501000018660 11 Emergency Diesel Generator Failed to Load 10/15/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 501000020519 12 EDG Oil Temperature Trending Down 0

501000020848 11 EDG Coolant Leak 0

501000020998 12 DGN Engine Signature Analysis Results 0

501000021007 11 DGN Engine Signature Analysis Results 0

501000024068 Coolant Leak on 11 EDG 0

501000025369 11 EDG Procedure Step Not Within Band 0

501000025405 Portions of 11 EDG PM and Test Not Performed 0

501000027532 NRC Questions on 12 EDG 0

501000027722 Small Oil Leak on 11 EDG 0

501000028287 Monticello Nuclear Generating Plant Maintenance Rule 0

Condensate Storage Tank Condition Monitoring

501000029082 11 EDG Oil Seeps 0

501000029844 G-3A, 11 EDG Low Oil Level 0

501000030102 11 EDG Governor Leaking 0

501000030576 11 EDG Oil Pump Increased Oil Leak 0

Engineering 501000018660 11 Emergency Diesel Generator Failed to Load 1

Evaluations 602000006755 Maintenance Rule Functional, MSPI and Equipment 10/23/2018

Reliability Clock Reset Failure Evaluation

NUC2017147 Condensate Storage Tanks, Desludge, Inspection and 0

Repair

Miscellaneous 2019 Period 1 Plant Health Report--System Report, "Condensate and

Reactor Feedwater System"

2019 Period 1 System Report--Emergency Diesel Generator

Operability 501000018660 Past Operability Evaluation for 11 Emergency Diesel 10/24/2018

Evaluations Generator Failure to Load

Work Orders 00446817 1385 Periodic Structural Online Inspection 11/04/2013

700006331 1385 Periodic Structural Inspection 09/06/2018

700036105 Condensate Storage Tank Aging Management Walkdown 12/15/2018

Completion

71111.13 Corrective Action 501000029418 Security Diesel Test Abort due to Speed Control Issues 0

Documents 501000029526 CV-3134 Not Controlling Level 0

501000030792 DPIS-2-129B did not Reset 0

501000031945 VD-9051B Excessive Oil Leak 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 700059052 Diesel Engine Emergency Security Power 07/15/2019

700063297 VD-9051B Excessive Oil 09/17/2019

71111.15 Corrective Action 501000030066 Containment Spray Valves Thrust Exceeds Calculations 0

Documents 501000030237 CRDs Refurbished without ASME XI RR Plan 0

501000031053 ESWW-1-2 IST Test not Performed in 1R29 0

Engineering 601000001705 Use of Low Side Contact for DPIS-2-129B 0

Changes

Miscellaneous 2019-29-041 ASME Section XI Repair/Replacement Plan 08/05/2019

Procedures FP-PE-MOV-07 Motor Operated Valve Program 3

71111.18 Engineering 601000001574 Remove Bad Temperature from TR-2-2-31, Recirculating 05/31/2019

Changes Pump "A" Motor Temperature Element

601000001705 Low Side Output Switch for DPIS-2-129B 08/16/2019

71111.19 Work Orders 700023229 12 Emergency Diesel Generator #1 Air Start PMT 07/25/2019

700039721 11 Core Spray injection Outboard Valve PMT 09/12/2019

700039817 4100-2, 11 Diesel Generator G-3A #2 Air Start System 07/16/2019

700051669 Stack "A" Effluent Noble Gas Monitor PMT 07/20/2019

700052015 RCIC Quarterly Pump and Valve Tests 08/16/2019

71111.22 Work Orders 700020892-0010 "A" Train Standby Gas Treatment System Filter Tests 08/16/2017

700024592-0020 "A" Train Standby Gas Treatment System Filter Tests 02/08/2018

700040870 G-507-Flex Generator Annual Preventative Maintenance 07/15/2019

700052934 Recirculation System Valve Operability Test 08/25/2019

700054406 0253-01A, Standby Gas Treatment Train "A" Monthly Test 07/20/2019

700056662 Residual Heat Removal System Leakage Test - Loop B 08/20/2019

71114.06 Miscellaneous Monticello Emergency Plan Full Scale Drill Guide/Scenario 08/06/2019

MT-LOR-19D- Licensed Operator Requalifcation; (DEP) Crew 1 08/19/2019

001V

71124.05 Calculations Mirion Service Calibration of the Canberra Fastscan WBC System at the 02/20/2019

XCel Energy Monticello Nuclear Generating Plant

Calibration 0908-177 NSPM RP Instrument Response Investigation Report 02/14/2018

Records UTC516834

309888/3098889 NSPM RP Instrument Response Investigation Report 03/21/2018

AZ-11 UTZ ARGOS Calibration 09/12/2019

No:478971

Inspection Type Designation Description or Title Revision or

Procedure Date

Model 89-400 J.L. Shepherd & Associates Model 78-2M Calibrator 01/28/1991

NSP No. 248 Certificate of Radioactivity Calibration of Cs-137 Sealed 11/01/1981

Source No. 81622 Source Containment High Range Radiation Monitor

PM-7-1 UTC Portal Monitor Calibration PM-7 06/04/2018

310244

TP-5 UTC 515541 MG Telepole Calibration 09/11/2019

WO 700014151- Containment High Range Radiation Detectors Calibration 04/24/2019

20 Procedure

Corrective Action 501000009743 RP Procedure R.09.14 Outdated Info 03/20/2018

Documents

Corrective Action 501000031850 NRC Observation of Containment High Range Monitor Cal 09/13/2019

Documents Source Strength

Resulting from

Inspection

Procedures 0428-02 Containment High Range Radiation Detector Calibration 9

Procedure

R.09.14 Micro REM Calibration and Functional Check 10

R.09.62 ARGOS Contamination Monitors Function Check and 16

Calibration

71124.06 Calibration Radiation Safety Primary Calibration of Turbine Building Normal Waste Sump 3

Records And Control at Monticello Nuclear Generating Plant

Services

Technical Support

Document 17-004

Corrective Action 501000021912 "B" Stack Wide Range Gaseous Monitor Remains Non- 01/12/2019

Documents Functional

501000022675 Traceability for Stack and Reactor Building Vent Wide 02/01/2019

Range Gaseous Monitor Calibration

501000023937 Incorrect Calibration Coefficient In RADEAS 03/07/2019

Engineering 28235 Methodology for Determining Stack Noble Gas Release

Changes Rates

Procedures I.02.06 Airborne Continuous Release Report 3

I.02.08 Airborne Batch Release Report 3

I.02.09 Stack/Reactor Building Vent Sample Analysis 1

Inspection Type Designation Description or Title Revision or

Procedure Date

I.05.09 Stack/Vent Tritium Sampling 11

I.05.26 Stack Noble Gas Sampling 6

Work Orders 700021755-0010 Reactor Building Vent Wide Range Gas Monitor Calibration 03/21/2018

700034829-0010 Service Water Monitor Calibration 11/07/2018

700036453-0010 Stack Wide Range Gas Monitor Calibration 12/13/2018

700051669-0010 Stack "A" Effluent Noble Gas Monitor 07/15/2019

71124.07 Corrective Action 501000013464 Missed REMP Air Sample Plant Access Road 06/20/2018

Documents 501000013755 The M0-5S & M0-5SE Environmental REMP TLDs, One 06/28/2018

Came Up Missing, the Other Damaged

603000000923 Missed 2018 REMP Sample Tracking 01/03/2018

Corrective Action 501000030003 NRC Observation during REMP Walkdown; M-4 Air Sample 07/24/2019

Documents was Facing Away from the Plant

Resulting from

Inspection

Engineering 1015118 Priority Guideline For Implementing a Groundwater Protection 08/23/2017

Evaluations Index Worksheet Program at Nuclear Power Plants

AT-0175 10 CFR 50.75(g) Files 09/09/2009 -

07/30/2011

No. 8010; Docket ATI Environmental Midwest Lab; Annual Radiological 01/01/2018 -

No. 50-263 Environmental Operating Report 12/31/2018

Project #4583-01 2017 ANNUAL GROUNDWATER MONITORING REPORT 05/01/2017

from Carlson/McCain Engineering Report

Miscellaneous ODCM-07.01 Offsite Dose Calculation Manual; Radiological 25

Environmental Monitoring Program

Procedures 1.05.41 Annual Land Use Census and Critical Receptor Identification 10

1308 MET Tower Inspection Procedure 21

Self-Assessments 2018 ARERR 2018 Annual Radioactive Effluent Release Report 05/13/2019

71151 Miscellaneous QF0739 NRC Performance Indicator Data; Emergency Preparedness 08/27/2019

- MSPI AC Power; 3rd quarter 2017 - 2nd quarter 2018

QF0739 NRC Performance Indicator Data; Emergency Preparedness 08/27/2019

- MSPI High Pressure Injection Systems; 3rd quarter 2017 -

2nd quarter 2018

QF0739 NRC Performance Indicator Data; Emergency Preparedness 08/27/2019

- MSPI Heat Removal Systems; 3rd quarter 2017 - 2nd

Inspection Type Designation Description or Title Revision or

Procedure Date

quarter 2018

Procedures QF0445 NRC/INPO/WANO Collection and Submittal Forms Fuel 3

Performance

71152 Corrective Action 501000001614 DPIS-13-84 Out of asFfound 0

Documents 501000008279 DPIS-13-84 Found out of as Found 0

501000015236 DPIS-13-84 Out of as Found 0

501000019912 DPIS-13-84 Found Outside as-found 0

501000024127 V-EAC-14B (B CRV) Oil Pressure Low 0

501000027478 DPIS-13-84 Out of as-found 0

501000030703 DPIS-13-84 Out as-found 0

Procedures 501000027329 Drywell Identified Leakage 0

501000027677 PI-4430B Freon Leak 0

FP-OP-ACM-01 Adverse Condition Monitoring Plan Process 11/29/2016

71153 Miscellaneous 501000028365 Root Cause Evaluation Report: Primary Containment 1

Isolation Valves Found Open

2702 Corrective Action 500001400973 ISFSI DSC 15 Helium Leak When Sealing 0

Documents 501000018344 Unable to Complete DSC Siphon Cover Weld

501000018399 NRC Resident Questions 10-10-18 0

501000021865 DSC-14 Quick-Connect Leak During Closure 0

501000023368 DSC-12 Leaking Vent Fitting 0

Miscellaneous XcelEnergy Confirmatory Order, EA-14-193, Closure Letter 03/26/2019

50100021865 Prompt Operability Determination 0

2709 Procedures CD 11.5 Strike Contingency Plan 4

2711 Miscellaneous QF 1727 10CFR20 Work Hour Limits Waiver (Penrod) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Jelen) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Williams) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Broich) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Peterson) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Ergen) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Morgan) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Flood) 09/05/2019

QF 1727 10CFR20 Work Hour Limits Waiver (Maciej) 09/05/2019

Procedures FP-S-FMP-01 10CFR20 Fatigue Management Fleet Procedure 7

23