IR 05000327/2021004

Integrated Inspection Report 05000327/2021004 and 05000328/2021004

ML22035A043
Person / Time
Site:	Sequoyah
Issue date:	02/07/2022
From:	Tom Stephen NRC/RGN-II/DRP/RPB5
To:	Jim Barstow Tennessee Valley Authority
References
IR 2021004
Download: ML22035A043 (20)

Text

February 7, 2022

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000327/2021004 AND 05000328/2021004

Dear Mr. Barstow:

On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah Nuclear Plant, Units 1 and 2. On February 1, 2022, the NRC inspectors discussed the results of this inspection with Mr. Tom Marshall, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection.

Licensee-identified violations, which were determined to be of very low safety significance and Severity Level IV, are documented in this report. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Sequoyah Nuclear Plant, Units 1 and 2. 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/

Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000327 and 05000328 License Numbers: DPR-77 and DPR-79 Report Numbers: 05000327/2021004 and 05000328/2021004 Enterprise Identifier: I-2021-004-0019 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Soddy Daisy, TN 37379 Inspection Dates: October 01, 2021 to December 31, 2021 Inspectors: S. Downey, Senior Reactor Inspector D. Hardage, Senior Resident Inspector N. Childs, Resident Inspector B. Kellner, Senior Health Physicist D. Lanyi, Senior Operations Engineer K. Miller, Resident Inspector A. Nielsen, Senior Health Physicist Approved By: Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Sequoyah Nuclear Plant, Units 1 and 2, 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. Licensee-identified non-cited violations are documented in report section: 7115

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 05000327,05000328/20 LER 2021-003-00 for 71153 Closed 21003-00 Sequoyah Nuclear Plant,

Units 1 and 2, Exceeded Breach Margin Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable LER 05000328/2021001-00 LER 2021-001-00 for 71153 Closed Sequoyah Nuclear Plant,

Unit 2, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency LER 05000327/2021002-00 LER 2021-002-00 for 71153 Closed Sequoyah Nuclear Plant,

Unit 1, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency

PLANT STATUS

Unit 1 began the inspection period at rated thermal power (RTP) and remained at or near RTP for the entire inspection period.

Unit 2 began the inspection in end of life coastdown at 76 percent of RTP. On October 2, 2021, the unit shutdown for refueling outage 2R24. On November 7, 2021, the reactor was started up and the unit was returned to RTP on November 12, 2021. The unit remained at or near RTP for the remainder of the 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 performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities, and completed on-site portions of IPs. 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

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:

Unit 1 and 2 Refueling Water Storage Tank on December 3, 2021 Unit 1 and 2 Steam Vault Rooms on December 3, 2021

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 2 residual heat removal (RHR) system with both trains in service for cooldown in Mode 5 with reactor coolant system (RCS) level below the flange on October 5, 2021

(2) Unit 2 RHR system with both aligned for low pressure safety injection in Mode 3 following realignment from 2R24 on November 5, 2021

(3) Unit 1 auxiliary feedwater (AFW) system alignment with 1B-B motor driven AFW pump inoperable due to steam generator level control valve issues on November 17, 2021

(4) Vital Instrument Board 1-I with invertor 1-I out of service for functional testing on December 14, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Emergency Diesel Generator Building, Elevation 722' on October 20, 2021

(2) Unit 2 Reactor Building Annulus on October 29, 2021

(3) Unit 2 Lower Containment on October 31, 2021

(4) Unit 2 Upper Containment on October 31, 2021

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from October 11-November 17, 2021:

1. Magnetic Particle Examination a. Weld RMSW-1, Steam Generator 1 nozzle to shell weld, ASME Class 2 2. Ultrasonic Examination a. Weld RHRS-168, pipe to elbow weld, ASME Class 1 b. Weld RMSW-1, Steam Generator 1 nozzle to shell weld, ASME Class 2 c. Weld SI-1897, socket weld, ASME Class 1 d. Reactor Vessel Head nozzles and partial penetration welds, ASME Class 1 The Inspectors evaluated the licensees boric acid control program performance.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

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

(1) Annual Review of Licensee Requalification Examination Results: The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 13, 2021, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.

The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on December 10, 2021

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 main control room during Unit 2 shutdown for U2R24 refueling outage on October 1-2, 2021.

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

(1) The inspectors observed and evaluated a simulator examination scenario on November 29, 2021.

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 (SSCs) remain capable of performing their intended function:

(1) Failure of the backplate connection of the Stationary Gripper Card in 2BD Power Cabinet on May 24, 2021

(2) Failure of B Auxiliary Air Compressor load control pressure switch on June 10, 2021

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) 2A safety injection pump shaft replacement and inboard bearing equivalency due to damaged shaft and bearing identified on October 8, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

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) Unit 2, Yellow shutdown risk week of October 2-9, 2021, while RCS level was below Rx flange level for reactor disassembly, including review of defense in depth protected equipment for U2R24.

(2) Unit 2, Yellow shutdown risk week of October 10-14, 2021, while RCS level was below Rx flange level and during Rx core offload, including review of defense in depth protected equipment for U2R24.

(3) Unit 2, Yellow shutdown risk week of October 22-27, 2021, while RCS level was below Rx flange level for reactor reassembly and for RCS fill and vent, including review of defense in depth protected equipment for U2R24.

(4) Units 1 and 2, the week of October 31-November 6, 2021, including Unit 2 Yellow shutdown risk and unit transition from Mode 5 to Mode 3.

(5) Units 1 and 2, the week of December 12-18, 2021, including planned maintenance on 1-I vital inverter and 2A RHR pump.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) During interlocking valve strokes, 2-FCV-63-11, RHR Heat Exchanger B to Safety Injection Pump suction, stroked in wrong direction and tripped on thermals (Condition Reports (CR) 1728862, 1728885)

(2) Leak on Main Steam boot seal on penetration X-13D identified during containment integrated leak rate test (CR 1731577)

(3) Essential raw cooling water leak on 2B-B Control Rod Drive Mechanism Cooler (CR 1733327)

(4) 2B-B 714 penetration room cooler leak (CR 1738092)

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) Design Equivalent Change Package SQN-21-050, H-08 Thermal Sleeve Modification

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)

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

(1) Work Order (WO) 116616411, Replace valve 2-VLV-067-1506, on October 18, 2021

(2) WO 121722819, Clean and Inspect 2A1 Component Cooling System Heat Exchanger, on October 18, 2021

(3) WO 121640286, 2-FCV-072-020B, Containment Sump Spray Header B Flow Control Valve, refurbish valve, on October 17, 2021

(4) WO 120475863, Cut Out and Replace Penetration 2-PENE-302-0009-B, on October 24, 2021

(5) WO 122336767, 480V FLEX Diesel Generator, diesel generator B would not pass load test, on October 21, 2021

(6) WO 122484774, Safety injection pump full flow test following pump shaft replacement, on October 30, 2021

(7) WO 121642918, Disassemble/Inspect Unit 2 turbine driven AFW pump on, November 6, 2021

(8) WO 121324634, 2-VLV-63-553, SIS Loop 2 cold leg injection check valve, clean, inspect, and rebuild if necessary, on November 5, 2021

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated U2R24 activities from October 1-November 9, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) 2-SI-OPS-088-001.0, Phase A Isolation Test, on October 3, 2021

(2) 0-SI-OPS-063-129.B, 1B-B SI Pump Casing, Suction, and Discharge Piping Vent on

December 23, 2021 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) 0-SI-SLT-067-258.2, Containment Isolation Valve Local Leak Rate Test Lower Compartment Essential Raw Cooling Water, on October 7, 2021

Ice Condenser Testing (IP Section 03.01) (1 Sample)

(1) 0-SI-MIN-061-105.0, Ice Condenser - Ice Weighing, on October 24, 2021

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) The inspectors observed and evaluated a simulator drill scenario which included loss of a charging pump, a large break loss of coolant accident, and emergency plan classifications on November 29,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas, pre-job briefings for work inside containment, and labels on boxes in the auxiliary building.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Observed workers exiting Unit 2 containment and exiting the Radiologically Controlled Area (RCA).

(2) Observed surveys of dry active waste trash released from contaminated areas.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) reactor head disassembly

(2) seal table thimble retraction

(3) containment spray valve refurbishment

(4) refuel floor work in a contaminated area High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) undervessel access

(2) tritiated drain collection tank Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensees radiological work planning by reviewing the following:

(1) Sequoyah Nuclear Plant - Unit 1 Refueling Outage 23 (U1R23) As Low As Reasonably Achievable (ALARA) Report

(2) Sequoyah Nuclear Plant - Unit 2 Refueling Outage 23 (U2R23) ALARA Report

(3) Sequoyah Nuclear Plant - Unit 1 Refueling Outage 24 (U1R24) ALARA Report

(4) ALARA Plan number 2021-005, U2 Transfer Canal and Equipment Pit Entries for Design Change Notice #23874 (Fuel Handling System Upgrade)

Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (4 Samples)

The inspectors evaluated dose estimates and exposure tracking by reviewing the following as low as reasonably achievable planning documents:

(1) ALARA Plan 2020-013, U2 Fuel Transfer System Post - Job Review

(2) Sequoyah Dose Excellence Plan 2021-2025 (Draft)

(3) ALARA Plan number 2021-005 Work in Progress Review, U2 Transfer Canal and Equipment Scope Change (Fuel Handling System Upgrade)

(4) Sequoyah U2R24 Daily Dose Reports from October 3-October 8, 2021, (outage daily dose accrual report, individual ALARA Plan dose accrual, significant radiological work complete/upcoming, etc.)

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (3 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls.

(1) The inspectors reviewed ALARA and radiological work control requirements contained in the following Radiation Work Permits (RWPs):

RWP 21210002, U2R24- HRA - U-2 Aux Bldg. & Annulus to include Satellite RCA's (Radiologically Controlled Areas)

RWP 21210022, U2R24- HRA - U-2 Aux Bldg. & Annulus to include Satellite RCA's (Respiratory Protection Required)

RWP 21240012, U2R24 - U-2 Upper Containment (CTMNT) / 734' Equipment Zone / 734' General Area & Top of Pressurizer - High Radiation Area (HRA)

RWP 21240013, U2R24 - U-2 Upper CTMNT / 734' Equipment Zone / 734' General Area & Top of Pressurizer - Locked High Radiation Area (LHRA)

(Respiratory Protection Required)

RWP 21240022, U2R24 - U-2 Upper CTMNT / 734' Equipment Zone / 734' General Area & Top of Pressurizer - HRA (Respiratory Protection Required)

(2) The inspectors reviewed the following ALARA Plans:

b. ALARA Plan Number 2021-211, Reactor Assembly and Disassembly c. ALARA Plan Number 2021-214, U2R24 Radiation Protection Support d. ALARA Plan Number 2021-227, U2R24 RCP Maintenance (MS, MMG, MEG)e. ALARA Plan Number 2021-223, Scaffolding (U2R24)

(3) The inspectors reviewed TEDE-ALARA (Total Effective Dose Equivalent) evaluations for the following work activities:

TEDE-ALARA Evaluation: 2021-014, Change out Rx head O-ring (RWP Number: 21240022 ALARA Plan 2021-211)

TEDE-ALARA Evaluation: 2021-016, Inspection and Repair of 2-72-20 (RWP Number(s): 21210021 and 21210022, ALARA Plan 2021-228)

Radiation Worker Performance (IP Section 03.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance during:

(1) Reactor head disassembly

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) ===

(1) August 29, 2020-September 8, 2021

71152 - Problem Identification and Resolution (PI&R)

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends with the control room annunciator system malfunctions that might be indicative of a more significant safety issue.

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

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000327, 328/2021-003-0, Exceeded Breach Margin Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable. ADAMS accession:

ML21292A181. The circumstances surrounding this LER are documented in the results section.

(2) LER 05000328/2021-001-00 for Sequoyah Nuclear Plant, Unit 2, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency. ADAMS accession:

ML21350A186. The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER; therefore, no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

(3) LER 05000327/2021-002-00 for Sequoyah Nuclear Plant, Unit 1, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency. ADAMS accession:

ML21265A503. The circumstances surrounding this LER are documented in the results section.

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR Part 50, Appendix B, Criterion V, requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

0-TI-SXX-00-016.0, Breaching of the Shield Building, ABSCE, or ECRPB Barriers, is the quality procedure that the licensee implements when breaching the auxiliary building secondary containment enclosure (ABSCE) boundary when conducting maintenance.

Breach Permits require an individual to be positioned in the main control room (MCR) with the sole responsibility of notifying field personnel at the breach site in case an emergency closure of the breach is required.

Contrary to the above, between August 18-20, 2021, on four occasions, the licensee blocked open door A118, which created a breach in the ABSCE boundary without a breach permit and without positioning an individual in the MCR with the sole responsibility of notifying field personnel at the breach site in case an emergency closure of the breach was required. This resulted in the inoperability of the auxiliary building secondary containment enclosure boundary and thus inoperability of both trains of the auxiliary building gas treatment system (ABGTS). The longest of these four occasions was 21 minutes.

Significance/Severity: Green. The inspectors assessed the significance of the finding using Appendix A, Significance Determination of Reactor Inspection Findings for At - Power Situations. Using IMC 0609, Appendix A, Exhibit 3, the inspectors determined that this finding was of very low safety significance (Green) because the finding only represents a degradation of the radiological barrier function provided for the auxiliary building.

Corrective Action References: CR 1715829, CR 1716097 Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR 50.72(b)(3)(v) requires, in part, that the licensee shall notify the NRC within eight hours of the occurrence of any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (C) control the release of radioactive material and (D) mitigate the consequences of an accident. Contrary to the above, on September 26, 2018, the Sequoyah Unit 1 ice condenser ice bed was inoperable for 32 minutes, from 11:01 pm until 11:33 pm, and the licensee did not notify the NRC within eight hours of the occurrence of a condition that at the time of discovery could have prevented the fulfillment of the safety function.

Significance/Severity: Severity Level IV. The inspectors reviewed Section 6.9.d.9 of the NRC Enforcement Policy and determined this violation was a Severity Level IV violation because the licensee failed to make a report required by 10 CFR 50.72, and that failure did not involve information that, had the report been made, would have caused the NRC to reconsider a regulatory position or undertake substantial further inquiry.

Corrective Action References: CR

EXIT MEETINGS AND DEBRIEFS

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

On October 8, 2021, the inspectors presented the Radiation Protection Inspection Exit Meeting inspection results to Tom Marshall, Site Vice President, and other members of the licensee staff.

On November 16, 2021, the inspectors presented the Baseline ISI Exit Meeting inspection results to Tom Marshall, Site Vice President, and other members of the licensee staff.

On February 1, 2022, the inspectors presented the integrated inspection results to Tom Marshall, 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 CR 1725961 'Freeze Protection Issue' - Not Able to Perform Section 6.9 10/04/2021

Documents CR 1728624 U2 RWST Cold Weather Protection Materials Deteriorated 10/15/2021

CR 1733699 Insulation Missing on N-B ERCW Pump Discharge 11/04/2021

Procedures 0-PI-OPS-000- Freeze Protection Revision 67

006.0

1-PI-EFT-234- Freeze Protection Heat Trace Functional Test Revision 46

706.0

71111.04 Corrective Action CR 1736493 1-LI-3-148 and 1-LI-3-171 (SG 3 and SG 4 Level Indications 11/17/2021

Documents for 1B-B AFW)

Corrective Action CR 1726212 Boron Accumulation on 2B RHR Pump Inboard Seal 10/05/2021

Documents

Resulting from

Inspection

Miscellaneous 0-GO-16, System Operability Checklist - AFW U1 Protected Equipment Revision 31

10

Procedures 0-SO-250-2 120 Volt AC Vital Instrument Power System Revision 75

0-SO-74-1 Residual Heat Removal System Revision 110

71111.05 Fire Plans DGB-0-722-00 Pre-Fire Plan - Diesel Generator Building, Elevation 722 Revision 6

RXB-0-679-02 Pre-Fire Plan - Reactor Building, Elevation 679 Revision 3

RXB-0-701-02 Pre-Fire Plan - Reactor Building Annulus Area Revision 3

RXB-0-734-02 Pre-Fire Plan - Reactor Building, Elevation 734 Revision 3

71111.08P Miscellaneous Review of Steam Generator Integrity Assessment Documents Revision 0

NDE Reports 180-9337960-000 Sequoyah, Unit 2 - U2R24 RVCH Penetration Examination Revision 001

Report

R-0450 Ultrasonic Examination of Weld SI-1897 10/06/2021

R-0480 Ultrasonic Examination of Weld RHRS-168 10/12/2021

R-0490 Magnetic Particle Examination of RMSW-1 10/14/2021

R-0494 Ultrasonic Examination of Weld RMSW-1 10/15/2021

Procedures NPG-SPP-09.7.4 Boric Acid Corrosion Control Program Revision

0007

71111.11Q Miscellaneous SEG SX-415 LOR Simulator Exam Loss of DEHC, CCP, Vital Instrument Revision 0

Board and Large Break LOCA

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Corrective Action CR 1727187 Bearing and shaft Damage to 2A Safety Injection Pump 10/08/2021

Documents CR 1727544 Bearing Parts Issue for Safety Injection Pump 10/11/2021

CR 1696187 Level 2 Evaluation Report for Unit 1 Reactor Trip Revision 1

CR 1700295 0-PS-32-88A Appears to be Malfunctioning 07/01/2021

Miscellaneous Flowserve Certificate of Conformance for Sequoyah 10/22/2021

Item # CKF871R (shaft assembly)

CDE #3149 2BD Power Cabinet Firing Circuit Failure 06/22/2021

CDE #3153 0-PS-32-88A is functioning incorrectly. The switch shows that 07/07/2021

it should be closed with no pressure input, but the switch is

open.

IEE-TVA-2021- Modification of Outboard (Thrust) Bearing ALE430H to be Revision 0

0142 Same Fit, Form, and Function as Inboard (Radial) Bearing

AKE439R

PEG Package # TVA Technical Evaluation - Safety Injection Pump, Revision 6

96B-000164 Non-Pressure Boundary Parts

Purchase Order Pump Shaft for 2A Safety Injection Pump (WO 122458422) Revision 0

7056390

Procedures NEDP-8.0 Evaluations for Procurement of Materials, Items, and Services Revision 7

NPG-SPP-04.001 Procurement of Material, Labor and Services Revision 12

NPG-SPP-04.002 Material Receipt and Inspection Revision 1

NPG-SPP-06.6 Inspection Program Revision 10

TI-4 Maintenance Rule Performance Indicator Monitoring, Revision 38

Trending, and Reporting - 10CFR50.65

TVA-NQA- Nuclear Quality Assurance Plan (NQAP) Revision 38

PLN89-A

Work Orders 122458647 Reassemble 2A Safety Injection Pump 10/27/2021

71111.13 Corrective Action CR 1725855 0-GO-015 Containment Isolation Valve Open Due to Time 10/04/2021

Documents Delay Response

Resulting from

Inspection

Procedures 0-GO-15 Containment Closure Control Revision 50

0-GO-16 System Operability Checklists Revision 30

0-SO-250-2 120 Volt AC Vital Instrument Power System Revision 75

NPG-SPP-07.3.4 Protected Equipment Revision 11

Inspection Type Designation Description or Title Revision or

Procedure Date

NPG-SPP-18.4.6 Control of Fire Protection Impairments Revision 20

71111.15 Corrective Action CR 1738946 2B-B 714 Pen Room Cooler Coil Replacement 11/30/2021

Documents CR 940772 714 Penetration Room Cooler 1B-B has Water Leaking Under 10/04/2014

Cooler onto Floor

CR 1733830 Additional Leak Discovered During Temporary Leak Repair 11/05/2021

Installation

Engineering EWR-21-DEM- 2-FCV-063-0011-B Overthrust Evaluation 10/18/2021

Evaluations 063-169

Operability CAR 1733830-01 PDO for CR 1733830 11/06/2021

Evaluations

Procedures NEDP-22 Operability Determinations and Functional Evaluations Revision 21

NPG-SPP-09.1.6 Operational Leakage from ASME Code Systems Revision 2

OPDP-8 Operability Process and Limiting Conditions for Operation Revision 28

Tracking

Work Orders 122554737 2B-B 714' Pen Room Cooler Leak 11/24/2021

71111.18 Engineering EWR-21-EPG- Evaluation of Sequoyah Unit 2 Thermal Sleeve ID and OD 10/20/2021

Evaluations 068-157 Wear Condition and Recommendations

71111.19 Procedures 0-SI-SLT -000- Type B Local Leak Rate Test Revision 19

257.0

0-SI-SXI-000- ASME Section XI Inservice Pressure Test Revision 25

201.0

0-SI-SXI-063- System Leakage Test of the RHR and SI Cold Leg, RHR Revision 10

300.2 Suction, & Hot Leg Injection Piping

0-SI-SXV-000- Testing of Category A and B Valves after Work Activities, Revision 7

206.0 Upon Release from a Hold Order, or When Transferred from

Other Documents

0-SO-360-225 480V FLEX Diesel Generator Revision 2

2-SI-SXP-003- Turbine Driven Auxiliary Feedwater Pump 2A-S Performance Revision 34

201.S Test

2-SI-SXP-063- Safety Injection Pumps 2A-A and 2B-B Comprehensive Revision 10

2.0 Performance and Check Valve Test

2-SI-SXV-063- Safety Injection Cold Leg Secondary Check Valve Integrity Revision 16

205.0 Test

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.20 Corrective Action CR 1727483 H-08 Thermal Sleeve Funnel Detached During Operation 10/10/2021

Documents CR 1727990 U2R24 Light Ice Baskets 10/13/2021

Corrective Action CR 1725498 2-VLV-068-0549, RCS Loop 1 Crossover Drain, has Dry Boric 10/02/2021

Documents Acid

Resulting from CR 1725499 2- VLV-68-0580, RCS Letdown Isolation Valve, Dry White 10/02/2021

Inspection Boric Acid Packing Leak

CR 1725502 2-VLV-68-558, RCS Loop 4 Crossover Drain has Dry White 10/02/2021

Boric Acid Packing Leak that Is Also Seeping Out Underneath

Gland Follower

CR 1725503 2-VLV-68-557, RCS Loop 4 Crossover Drain has Dry White 10/02/2021

Boric Acid Packing Leak that Is Also Seeping Out Underneath

Gland Follower

CR 1727894 Potential Boron/White Substance on #3 RCP Near the Pump 10/12/2021

Discharge

71111.22 Miscellaneous ICE - Vers SQ1.1 Sequoyah Unit 2 Ice Basket Weighing 10/24/2021

N2-88-400 Containment Isolation System Revision 21

71124.01 Corrective Action CR 1726667

Documents

Resulting from

Inspection

Miscellaneous Excel Alpha Tracking Characterization by System

Spreadsheet

Radiation Surveys SQN-M- 72-21 Valve Breach 04/22/2015

20150422-3

SQN-M- U2R24 U2 Raceway 10/02/2021

211001-15

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.02 Corrective Action Condition Reports (CRs); 1487173, 1514330, 1514913, Various

Documents 1535804, 1568357, 1570842, 1583027, 1605232, 1606583,

1659552, 1686156, 1689094, 1692866, 1708675, 1715840,

25620, and1725629

Miscellaneous U2R24 Temporary Shielding Requests TSRF 21-26 U2 Various

Raceway Doors and TSRF 21-39 Cavity Drain Line

RP standing Implementation of Elemental Cobalt Program 10/03/2021

Order 21-002,

Rev. 0

Site ALARA SAC 2019-06, SAC November 2020, SAC 2021-01, SAC Various

Committee (SAC) 2021-02, and 2021-03

Meeting Minutes

TSRF 21-21 Temporary Shielding Request Form (TSRF) - SRST Valve 09/12/2021

Gallery, valve AOV 77-49

Radiation Surveys SQN-M- U2 Inside Polar Cane Wall Post Shielding Survey 10/03/2021

211003-1

71152 Corrective Action CR 1705735 Unit 1 Annunciator System BETA Trouble 07/07/2021

Documents CR 1722790 Trend CR for Recent BETA Issues 09/21/2021

CR 1724565 Unit 2 Alarms Locked in on Diagnostic Error 9/28/2021

CR 1732357 Unit 1 'B' BETA Channel Alarm Windows are Dark 10/31/2021

CR 1742884 1-M6-C Numerous Half-Lit Annunciator and Unsilenceable 12/17/2021

Alarm

71153 Corrective Action CR 1450973 Unit 1 Ice Bed Recorder is Nonfunctional 09/28/2018

Documents CR 1709839 Ice Bed Temperature Recorder Values in Error 07/25/2021

CR 1711038 Past Instance of Ice Bed Inoperability Within Three Year 07/30/2021

Reportability Window

CR 1715829 ABSCE Challenge Due to Miscommunication of Standard 08/20/2021

Miscellaneous Alarm/Event Door A118 Open/Close Times 8/17/2021 thru 8/20/2021 08/23/2021

Report

Procedures 0-TI-SXX-000- Breaching of the Shield Building, ABSCE, ECRPB Barriers Revision 42

016.0

17