IR 05000461/2020004

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Integrated Inspection Report 05000461/2020004; 07201046/2020001
ML21040A365
Person / Time
Site: Clinton  Constellation icon.png
Issue date: 02/09/2021
From: Kenneth Riemer
NRC/RGN-III/DRP/B1
To: Rhoades D
Exelon Generation Co, Exelon Nuclear Generation Corp
References
IR 2020001
Download: ML21040A365 (21)


Text

February 9, 2021

SUBJECT:

CLINTON POWER STATION - INTEGRATED INSPECTION REPORT 05000461/2020004; 07201046/2020001

Dear Mr. Rhoades:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Clinton Power Station. On January 14, 2021, the NRC inspectors discussed the results of this inspection with Mr. T. Chalmers, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding did not involve a violation of NRC requirements.

If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Clinton Power Station. 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Kenneth R. Riemer, Chief Branch 1 Division of Reactor Projects

Docket Nos. 05000461, 07201046

License No. NPF-62

Enclosure:

As stated

Inspection Report

Docket Number:

05000461; 07201046

License Number:

NPF-62

Report Number:

05000461/2020004; 07201046/2020001

Enterprise Identifier: I-2020-004-0059

Licensee:

Exelon Generation Company, LLC

Facility:

Clinton Power Station

Location:

Clinton, IL

Inspection Dates:

October 1, 2020 to December 31, 2020

Inspectors:

J. Beavers, Senior Resident Inspector

J. Dalzell, Reactor Inspector

N. Fields, Reactor Operations Engineer

M. Garza, Emergency Preparedness Inspector

G. Hansen, Sr. Emergency Preparedness Inspector

C. Mathews, Illinois Emergency Management Agency

D. Sargis, Resident Inspector

Approved By:

Kenneth R. Riemer, Chief

Branch 1

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Clinton Power Station, 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

Failure to Determine Extent of Cause Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green FIN 05000461/2020004-01 Open/Closed

[H.12] - Avoid Complacency 71152 The inspectors identified a Green finding when the licensee failed to determine the extent of cause for a root cause in accordance with PI-AA-125-1001, "Root Cause Analysis Manual," Revision 6. Specifically, the licensee failed to identify that lack of technical rigor in the station's FLEX modification caused the FLEX output breaker settings to have been left at factory settings without an analysis.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near rated thermal power for the entire inspection period.

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 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:

lake/river screen house, fire pump house, and FLEX equipment storage buildings

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1)reactor core isolation cooling system on October 8, 2020

(2) Division 3 emergency diesel generator on November 23, 2020 (3)

'B' control room ventilation train on November 23, 2020 (4)

'C' residual heat removal train on November 24, 2020 (5)

'A' feed water train on November 24, 2020 (6)safety direct current power system on December 2, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire Zone A-1b, auxiliary building general access area, elevation 737' on October 6, 2020
(2) Fire Zone A-1a, auxiliary building general access area, elevation 707' on October 6, 2020
(3) Fire Zone D-12, diesel generator building Division 1 diesel generator and day tank room, elevation 712' on November 20, 2020
(4) Fire Zone D-5(a,b), diesel generator building Division 1 diesel fuel tank room, elevation 737' on November 20, 2020
(5) Fire Zone M-1, screen house Division 1 shutdown service water pump room and Fire Zone M-2(a,b), elevation 699'; Divisions 2 & 3 shutdown service water pump room, elevation 699' on November 20, 2020
(6) Fire Zone M-3, screen house 'B' fire pump room and Fire Zone M-4, elevation 699';

screen house 'A' fire pump room, elevation 699' on November 20, 2020

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on November 20, 2020.

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Division 4 inverter room cooler 1VX014AA

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered between October 22 and November 20, 2020.

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 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during power restoration from 90 percent to full power, completion of 24-hour Division 1 emergency diesel generator run, and subsequent fast start of Division 1 emergency diesel generator on November 20, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated annual dynamic simulator testing on November 18, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1)condensate polishing system (2)nuclear system protection system self-testing

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1)planned Yellow risk while switching Division 2 battery to swing battery charger, Work Order 4801239

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Action Request 4373461, "RCIC [reactor core isolation cooling] Pump Oil Cooler Issue"
(2) Action Request 4376204, "ERAT [emergency reserve auxiliary transformer] Static Var Compensator Thyristor Monitor"
(3) Action Request 4375036, "Received Unexpected Annunciator 5006-2L, LPRM [local power range monitor] Upscale Alarm"

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1)revision to secondary containment tornado design criteria

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) Work Order 1849500, "Stroke of 1SX041A and 1SX041B after Replacement of Instrument Air Regulator"
(2) Work Order 4776173, "High Pressure Core Spray Pump Run after System Outage Window"
(3) Work Order 5058517, "Reactor Core Isolation Cooling Comprehensive Test after System Outage Window"
(4) Work Order 5088240, "1VF07Y Failed to Open During VG [standby gas treatment]

'A' Shutdown and VF [fuel building ventilation] Startup"

(5) Work Order 5099146, "Signs of Component Failure 0AP25E-4B (0VC24YB Damper Bucket) after Rebuild"
(6) Work Order 5099742, "'B' Reactor Recirculating Pump Flow Control Valve"

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Work Order 4918018, "Reactor Core Isolation Cooling Remote Shutdown Operability Checks"
(2) Work Order 4820186, "9080.13 Emergency Diesel Generator 1A 24-Hour Run and Hot Restart"
(3) Work Order 5093459, "9071.01 Fire Pump 'B' Operability Run"
(4) Work Order 5048393, "9030.01C06 1B21-N692ABEF Reactor Water Low Level 2 Channel Functional"

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the following maintenance and testing of the alert and notification system:
  • annual siren inspection and maintenance records for the period from September 2018 to September 2020
  • monthly alert notification system (siren) tests for the period from September 2018 to September 2020

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the emergency preparedness organization.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors completed an evaluation of submitted emergency action level and emergency plan changes on December 2, 2020. This evaluation does not constitute NRC approval.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

EP01: Drill/Exercise Performance (IP Section 02.12)===

(1)01/01/2019 - 06/30/2020

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) 01/01/2019 - 06/30/2020

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) 01/01/2019 - 06/30/2020

71152 - Problem Identification and Resolution

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) FLEX diesel generator breaker set to factory settings (2)unplanned reactivity events during

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

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

(1) The inspectors evaluated the licensees activities related to the long-term operation and monitoring of its independent spent fuel storage installation (ISFSI). The inspectors reviewed relevant documentation and interviewed personnel remotely during the week of November 16, 2020. The inspector performed an onsite walkdown of the ISFSI pad and haul path and evaluated the material condition of the ISFSI pad and HI-STORM FW casks on November 16, 2020. The inspector utilized licensee personnel and radiological instrumentation to verify that radiological conditions on the ISFSI pad were as expected during the walkdown.

The inspectors evaluated the following change reviews:

  • changes to the licensee's 10 CFR 72.212 report performed since October 1, 2018
  • procedural changes primarily stemming from lessons learned or operating experience since the licensee's previous loading campaign

INSPECTION RESULTS

Failure to Determine Extent of Cause Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems

Green FIN 05000461/2020004-01 Open/Closed

[H.12] - Avoid Complacency 71152 The inspectors identified a Green finding when the licensee failed to determine the extent of cause for a root cause in accordance with PI-AA-125-1001, "Root Cause Analysis Manual,"

Revision 6. Specifically, the licensee failed to identify that lack of technical rigor in the station's FLEX modification caused the FLEX output breaker settings to have been left at factory settings without an analysis.

Description:

On June 26, 2020, the licensee wrote Action Request 4352937 documenting that the FLEX diesel generator output breakers did not have an engineering analysis to determine the correct breaker settings. Both FLEX diesel generator output breakers were still set to the factory default settings. Upon discovery of the condition, it was uncertain if the FLEX diesel generators would have been able to supply power without tripping the output breaker. The licensee evaluated the condition and determined that the breaker would not trip if it were supplying power and that there was less margin in the calculation than would normally be acceptable. The licensee adjusted the breaker settings to provide a more acceptable margin.

The licensee performed a corrective action program evaluation for the condition and identified that the breaker settings were not discussed in Engineering Change 392335, which installed the breakers. The licensee determined that the cause was less than adequate technical rigor by the engineer responsible for the FLEX modification. The inspectors noted that this cause was nearly identical to the cause identified in Root Cause Report 4297570 for the FLEX diesel generator 1FX01KA being wired with its phase rotation out of phase from the plant equipment phase rotation. The phase rotation issue was previously identified as a Green finding identified in NRC integrated inspection report 05000461/2020001 as FIN 05000461/2020001-01 "FLEX Diesel Generator Phase Rotation Incorrect."

The inspectors reviewed Root Cause Report 4297570 to determine the similarities between the FLEX diesel generator phase rotation issue and the output breaker settings issue. The root cause identified was that engineers did not apply technical human performance fundamentals during selection of post-modification testing for the FLEX modification. The licensee conducted an extent-of-cause review for the root cause in accordance with PI-AA-125-1001, "Root Cause Analysis Manual," Revision 6. The extent-of-cause review evaluated all modifications that were completed by the responsible engineers to verify that post-modification testing was correct. The extent-of-cause did not review the modifications to verify overall adequacy or that the appropriate engineering rigor was applied to areas outside of post-modification testing.

Exelon procedure PI-AA-125-1006, "Investigation Techniques Manual," Revision 5, includes considerations for performing an extent-of-cause review. The manual stresses the importance of identifying how a cause could affect programs or processes other than the one that was already identified. When the licensee focused their extent-of-cause review on the adequacy of post-modification testing, they did not consider how the cause could affect other processes or programs that could have been affected by lack of technical rigor in implementing the FLEX modification. Specifically, the review did not identify that Engineering Change 392335 did not provide any analysis of the FLEX breakers; therefore, the breakers did not have any discussion for post-modification testing.

Corrective Actions: The licensee determined correct breaker settings and performed the change to support breaker functionality.

Corrective Action References: Action Request 4352937, "FLEX Diesel Generator Breaker Settings"

Performance Assessment:

Performance Deficiency: The licensee failed to determine the extent of cause for a root cause as required by PI-AA-125-1001. This led to the licensee failing to identify that the FLEX diesel generator output breaker settings were not evaluated and were set to factory default settings instead of site-specific settings.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, there was reasonable doubt as to the functionality of the FLEX generator output breakers until a detailed analysis was performed, and following the analysis, the licensee determined that the settings should be revised. This was similar to example 3.a in Inspection Manual Chapter 0612, Appendix E, "Examples of Minor Issues."

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors used Exhibit 2, "Mitigating Systems Screening Questions," Section E "Flexible Coping Strategies (FLEX)," and answered "No" to all questions. Therefore, the finding screens to Green or very low safety significance.

Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, when the licensee attempted to identify the extent of cause for the FLEX diesel generator phase rotation issue; they only focused on post-modification testing and did not attempt to identify other areas where lack of technical rigor could have impacted the FLEX implementation.

Enforcement:

Inspectors did not identify a violation of regulatory requirements associated with this finding.

Observation: Unplanned Reactivity Events in 2020 71152 The inspectors observations and assessments of trends related to several unplanned power changes over 2020 indicated an inconsistent range of response in assessment as well as communication with the support organizations and management. The inspectors determined that the lack of an off normal procedure to address unplanned power changes impacted the consistent application of process in both response and communication. All minor issues with each event were individually addressed in the quarter in which they occurred during the quarterly exits. The station did take note of the inspectors observations regarding the response to these events and is developing an off normal response procedure for unplanned power changes. The procedure is slated for completion by the first half of

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On January 14, 2021, the inspectors presented the integrated inspection results to Mr. T. Chalmers, Site Vice President, and other members of the licensee staff.
  • On October 15, 2020, the inspectors presented the emergency preparedness baseline inspection results to Mr. J. Kowalski, Plant Manager, and other members of the licensee staff.
  • On November 20, 2020, the inspectors presented the independent spent fuel storage installation (ISFSI) program review inspection results to Mr. T. Chalmers, Site Vice President, and other members of the licensee staff.
  • On December 2, 2020, the inspectors presented the IP 71114.04 exit meeting inspection results to Mr. D. Moore, Senior Manager - Emergency Preparedness, and other members of the licensee staff.
  • On December 14, 2020, the inspectors presented the annual licensed operator requalification examination inspection results to Mr. R. Tyler, Licensed Operator Lead Instructor, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

60855.1

Corrective Action

Documents

Selected Corrective Action Documents Created Since

October 2018

AR 4236199

60-Day Reporting Period for ISFSI ARERR Not Met

04/04/2019

AR 4355273

Unexpected Water Flowing Out of the MPC Drain Port

07/07/2020

AR 4364058

Forced Helium Drying Skid Issue: Braidwood

09/18/2020

Corrective Action

Documents

Resulting from

Inspection

AR 4385229

Errors in Survey Calculations

11/18/2020

AR 4385391

Spalling on South West Edge of ISFSI Pad

11/19/2020

Engineering

Changes

ECO 5018-65

Holtec Engineering Change Order

ISFSI 72.212-CR-

2018-001, ISFSI

2.212-CR-2018-

2, ISFSI 72.212-

CR-2018-003, ISFSI

2.212-CR-2018-

004, ISFSI 72.212-

CR-2019-001

2.212 Evaluation Report Change Requests

Miscellaneous

Clinton Power Station Unit 1 10 CFR 72.212 Evaluation

Report for the HI-STORM FW MPC Storage System

Docket 72-1046

2018 Annual Radiological Environmental Operating

Report Clinton Power Station - Docket Number 50-461

04/25/2019

2019 Annual Radiological Environmental Operating

Report Clinton Power Station - Docket Number 50-461

04/28/2020

2.48

Screening/Evaluation

209

Holtec 10 CFR 72.48 Screening/Evaluation for ECO

5018-65

0, 1

2.48-CL-2018-S-

2, 72.48-CL-2018-

S-023, 72.48-CL-

2018-S-024, 72.48-

CFR 72.48 Screenings and Evaluations

October

2018 to

October

20

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CL-2018-E-024,

2.48-CL-2018-S-

25, 72.48-CL-2018-

S-026, 72.48-CL-

2019-S-001, 72.48-

CL-2020-S-001

EP-AA-1003,

Addendum 3

Emergency Action Levels for Clinton Station

NO-AA-10

Quality Assurance Topical Report

U-604484

Clinton Power Station, October 1, 2016 to September 30,

2017, Independent Spent Fuel Storage Installation Annual

Radioactive Effluent Release Report

04/24/2019

U-604485

Clinton Power Station, October 1, 2017 to

September 30, 2018, Independent Spent Fuel Storage

Installation Annual Radioactive Effluent Release Report

04/25/2019

U-604577

Clinton Power Station, October 01, 2018 to September

30, 2019, Independent Spent Fuel Storage Installation

Annual Radioactive Effluent Release Report

11/13/2020

U-604578

Clinton Power Station, October 01, 2019 to September

30, 2020, Independent Spent Fuel Storage Installation

Annual Radioactive Effluent Release Report

11/13/2020

Procedures

CPS 1019.05

Transient Equipment/Materials

CPS 1860.01C001

Operations Department Cold Weather Preparations

Checklist

9b

CPS 1893.04M913

Independent Spent Fuel Storage Facility Installation

(ISFSFI) Prefire Plan

0a

CPS 9000.01D001

Control Room Surveillance Log - Mode 1, 2, 3 Data Sheet

58d

CPS 9000.01D002

Control Room Surveillance Log - Mode 4, 5 Data Sheet

CY-AA-170-1001

Environmental Dosimetry - Performance Specifications,

Testing, and Data Analysis

ER-AA-450

Structures Monitoring

HPP-2226-200

MPC Loading at Clinton

HPP-2226-400

MPC Transfer at Clinton

HPP-2226-500

HI-STORM Movements

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

HPP-2226-600

MPC Unloading at Clinton

HPP-2226-700

Responding to Abnormal Conditions

OP-AA-108-111-

1001

Severe Weather and Natural Disaster Guidelines

OU-AA-3005

Conduct of Outage Services Manual T&RM

OU-AA-630-1000

Spent Fuel Loading Campaign Management

OU-AA-630-101

Dry Cask Storage/ISFSI Inspection Surveillance Program

OU-CL-800-81

DCS Campaign Preparations and Restoration

OU-CL-800-83

Spent Fuel Cask Contingency Actions

RP-AA-305

Holtec HI-TRAC Radiation Survey

RP-AA-306

Holtec HI-STORM Radiation Survey

RP-AA-307

Holtec Independent Spent Fuel Storage Installation

(ISFSI) Radiation Survey

RP-AA-401-1006

Controls for Independent Spent Fuel Storage (ISFSI)

Associated Activities

Radiation

Surveys

2019-046314

Outside Areas - ISFSI Pad Grid Survey

(per RP-CL-300-1004 - Sections 5.1-5.3)

06/15/2019

2019-046316

Outside Areas - ISFSI Pad Protected Area Fence Survey

(per RP-CL-300-1004 - Section 5.4)

06/15/2019

20-072193

Outside Areas - ISFSI Pad

05/04/2020

20-080757

Outside Areas - ISFSI Pad Grid Survey

(per RP-CL-300-1004 - Sections 5.1-5.3)

09/26/2020

20-080759

Outside Areas - ISFSI Pad Protected Area Fence Survey

(per RP-CL-300-1004 - Section 5.4)

09/26/2020

Self-

Assessments

AR 429608-02

Clinton Spent Fuel Loading Readiness Assessment

07/29/2020

NOSA-CPS-18-10

(AR 4177215)

Independent Spent Fuel Storage Installation Audit Report:

Clinton Power Station

11/14/2018

NOSA-CPS-20-10

Independent Spent Fuel Storage Installation Audit Report

10/02/2020

Work Orders

WO 4817969-01

ISFSI - DCS Eng Perform Annual Insp of ISFSI per

OU-CL-630-100

08/14/2019

WO 4978935-01

OP 9000.01 Control Room Surv Log for Mode 1/2/3,

D001-Weekly

11/17/2019

WO 5013563-01

OP 9000.01 Control Room Surv Log for Mode 1/2/3,

03/08/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

D001-Weekly

WO 5033760-01

ISFSI - DCS Eng Perform Annual Insp of ISFSI per

OU-CL-630-100

08/12/2020

71111.01

Procedures

WC-AA-107

Seasonal Readiness

71111.04

Drawings

M05-1004, Sheet 1

P&ID Reactor Feedwater (FW)

AH

Procedures

CPS 3310.01V001

Reactor Core Isolation Cooling Valve Lineup

CPS 3312.01V001

Residual Heat Removal Valve Lineup

17c

CPS 3402.01E001

Control Room HVAC Electrical Lineup

10e

CPS 3506.01C003

Diesel Generator 1C Pre-Start Checklist

6e

71111.05

Fire Plans

CPS 1893.04M100

707 Auxiliary Building General Access Area Prefire Plan

5a

CPS 1893.04M110

737 Auxiliary Building General Access Area Prefire Plan

6b

Procedures

CPS 1893.04M511

737 Diesel Generator Building Div 1 Diesel Generator &

Day Tank Room

6c

CPS 1893.04M800

699 Screen House Div 1 SX Pump Room Prefire Plan

5a

CPS 1893.04M801

699 Screen House Div 2&3 SX Pump Rooms and Tunnel

Prefire Plan

6a

CPS 1893.04M802

699 Screen House 'B' Fire Pump Room Prefire Plan

6a

CPS 1893.04M803

699 Screen House 'A' Fire Pump Room Prefire Plan

6a

71111.07A

Work Orders

WO 4789401

Inspect, Boroscope, Clean, Eddy Current, and Hydrolase

as Required

05/12/2020

71111.11A

Procedures

TQ-AA-150-F25

Clinton 2020 LORT Annual Exam Status Report

2/07/2020

71111.11Q Miscellaneous

ESG-LOR-10

Clinton Power Station Licensed Operator Training

Simulator Exercise Guide

71111.13

Work Orders

WO 4801239

OP Cross-Tie Div II DC MCC 1B / Swing Charger

1DC11E

10/26/2020

71111.19

Work Orders

WO 5058517

OP 9054.01C002 RCIC 1E51-C001 High Pressure

Operability Check

09/24/2020

WO 5088240

1VF07Y Failed to Open During VG 'A' Shutdown and VF

Startup

10/27/2020

WO 5099146

0AP25E-4B (0VC24YB Damper Bucket) Rebuild

WO 5099742

Leakcheck RR Subloop B1

71111.22

Corrective Action

Documents

AR 4371952

ATM B21N692B and F Gross Fail High Didn't Come in As

Expected

09/25/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

WO 4918018

OP 9054.05 RCIC Remote Shutdown Panel Operability

Checks

09/24/2020

WO 5048393

9030.01C06 Channel Functional RCIC Reactor Low Level

B21-N692ABEF

09/25/2020

WO 5093459

9071.01B21 Fire Pump Operability Run

11/23/2020

71114.02

Corrective Action

Documents

AR 4257968

EP-Siren Failures (CL06 & CL21)

06/19/2019

AR 4262593

EP ID: Trend IR; Multiple CPS Siren Failures

07/08/2019

AR 4336468

EP - Dewitt County Siren Controller Inoperable

04/17/2020

Miscellaneous

Exelon Nuclear Manager, Midwest Emergency

Preparedness Letter to Program Enhancement Manager,

Illinois Emergency Management Agency; Submission of

Clinton Power Station Public Alert and Notification System

(ANS) Design Report, Revision 3

10/01/2018

Clinton Station Monthly Siren Availability Reports

09/01/2018 -

09/30/2020

Clinton Primary Notification System (PNS) Maintenance

Reports

09/01/2018 -

09/30/2018

Semi-Annual Clinton Power Siren Reports

09/01/2018 -

09/30/2020

2019/2020 Emergency Planning for the Clinton Area

(Community Information Booklet)

07/19/2019

20/2021 Emergency Planning for the Clinton Area

(Community Information Booklet)

06/17/2020

U.S. Department of Homeland Security, FEMA Letter,

Subj: Backup Alert and Notification System

2/10/2012

KLD-TR-987

Clinton Power Station Alert and Notification System (ANS)

Design Report

09/19/2018

Procedures

EP-AA-120-F-02

EP Staff Initial Developmental Checklist

H

EP-AA-112-200

TSC Activation and Operation

EP-AA-112-300

OSC Activation and Operation

EP-AA-112-400

EOF Activation and Operation

71114.03

Corrective Action

Documents

AR 4173268

EP ID: 1 Hour Responder Failed to Call During

Augmentation Drill

09/14/2018

AR 4249806

EP ID: 2nd Quarter ERO Augmentation Drill

05/17/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Miscellaneous

Quarterly Unannounced Off-Hours Call-In Augmentation

Drill Results

09/01/2018 -

09/30/2020

Emergency Response Organization Duty Roster

09/22/2020

Procedures

EP-AA-1003,

Addendum 1

On-Shift Staffing Technical Basis

EP-AA-112

Emergency Response Organization (ERO)/Emergency

Response Facility (ERF) Activation and Operation

EP-AA-112-100-F-06 ERO Notification or Augmentation

X

TQ-AA-113

ERO Training and Qualification

71114.04

Corrective Action

Documents

AR 4325295

Perform Impact Review of EAL Revisions from

EOP/SAMG, Rev. 4

03/10/2020

AR 4329864

NOS ID: Revise Standardized Emergency Plan

03/26/2020

AR 4334253

EPlan: CDAM 50.54(q) Potential Deficiencies

04/09/2020

Miscellaneous

Eval No. 19-29

Exelon Nuclear Standardized Radiological Emergency

Plan

09/04/2020

Eval No. 19-65

Exelon Nuclear Standardized Radiological Emergency

Plan

09/06/2019

Eval No. 19-79

Various Station Emergency Plan Annexes

11/08/2019

Eval No. 19-80

On-Shift Staffing Assessments

11/08/2019

71114.05

Corrective Action

Documents

AR 4335802

NOS ID: Increase communication with Warner Hospital

04/15/2020

AR 4335805

Communicate with Maroa FD About Their EP Role

04/15/2020

AR 4335859

NOS ID: Satellite Testing not Conducted by Required

Disciplines

04/15/2020

AR 4335887

Exercise/Drill Evaluated Reports and Communication Test

Forms Contain Documentation Errors

04/15/2020

AR 4336124

Annual Testing not Performed on 47 of 259 Public

Address (PA) Speakers in 2019

04/16/2020

Miscellaneous

Full Scale PI Drill Series Report

2/19/2018

Clinton 2020 1st Half Health Physics Drill Report

07/22/2020

Clinton Medical/Health Physics Drill Evaluation Report

11/15/2019

Clinton 2019 NRC Graded Exercise Evaluation Report

04/18/2019

TSC PI Focus Drill Report

03/09/2020

2019 NRC Pre-Exercise WANO Emergency Management

03/11/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Performance Evaluation

Clinton 2019 1st Half Health Physics Drill Report

05/31/2019

EP-AA-124-F-01

Quarterly Emergency Response Data System (ERDS)

Test Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Control Room/Simulator Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

CR/Simulator/TSC/OSC Equipment Test-TSC Software

and Reference Document Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Technical Support Center Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Operations Support Center Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Field Team Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Assembly Area Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Medical Response Kit Inventory Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Monthly NARS Communications Test Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Monthly ENS Communications Test Records

09/01/2018 -

09/30/2019

EP-MW-124-1001-F-

Quarterly Directors Hotline Test Records

09/01/2018 -

09/30/2020

EP-MW-24-1001-F-

Quarterly Operations Status Line Test Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Quarterly Damage Control Line Test Records

09/01/2018 -

09/30/2020

EP-MW-124-1001-F-

Quarterly Technical Support Line Test Records

09/01/2018 -

09/30/2020

KLD-TR-1002

Clinton Power Station 2018 Population Update Analysis

09/08/2018

KLD-TR-1181

Clinton Power Station 2020 Population Update Analysis

09/05/2020

Procedures

EP-AA-1000

Exelon Nuclear Standardized Radiological Emergency

Plan

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

EP-AA-1003

Exelon Nuclear Radiological Emergency Plan Annex for

Clinton Station

EP-AA-1003,

Addendum 2

Evacuation Time Estimates for Clinton Power Station

Plume Exposure Pathway Emergency Planning Zone

EP-AA-122

EP-AA-122; Drills and Exercise Program

EP-AA-124

Inventories and Surveillances

Self-

Assessments

NOSA-CPS-19-03

Emergency Preparedness Audit Report

03/15/2019

NOSA-CPS-20-03

Emergency Preparedness Audit Report

04/22/2020

71151

Miscellaneous

NRC Performance Indicator Data; Emergency

PreparednessDrill/Exercise Performance

01/01/2019 -

06/30/2020

NRC Performance Indicator Data; Emergency

PreparednessERO Readiness

01/01/2018 -

06/30/2020

NRC Performance Indicator Data; Emergency

PreparednessAlert and Notification System Reliability

01/01/2018 -

06/30/2020