IR 05000327/2019011

Biennial Problem Identification and Resolution Inspection Report 05000327/2019011 and 05000328/2019011

ML19204A190
Person / Time
Site:	Sequoyah
Issue date:	07/23/2019
From:	Omar Lopez-Santiago Division Reactor Projects II
To:	James Shea Tennessee Valley Authority
Reeder D
References
IR 2019011
Download: ML19204A190 (26)

Text

July 23, 2019

SUBJECT:

SEQUOYAH NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000327/2019011 AND 05000328/2019011

Dear Mr. Shea:

On June 27, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Sequoyah Nuclear Plant, Units 1 and 2. On June 20 and 27, 2019, the inspectors discussed the results of this inspection with Mr. Matthew Rasmussen and other members of your staff. The results of this inspection are documented in the enclosed report.

As stated in your 2017 Annual Assessment Letter (ML18059A143), dated February 28, 2018, the International Atomic Energy Association (IAEA) Operational Safety Review Team (OSART)

inspection completed at your facility in 2017, entitled you to a one-time credit to the baseline inspection of the Reactor Oversight Process (ROP). As such, NRC inspection hours expended during this problem identification and resolution inspection were reduced by approximately 50 percent.

The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.

Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment (SCWE) and interviewed station personnel to evaluate the effectiveness of these programs. This review was also a follow-up to the NRC Confirmatory Order (CO) EA-17-022, dated July 27, 2017 (ML17208A647). Based on the teams reviews, observations, and the results of these interviews, the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available. No NRC-identified or self-revealing findings were identified during this inspection. However, NRC inspectors identified one Severity Level IV violation with no associated finding. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance or severity of the violation 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.

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/

Omar R. López-Santiago, 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:

05000327/2019011 and 05000328/2019011

Licensee:

Tennessee Valley Authority

Facility:

Sequoyah Nuclear Plant, Units 1 and 2

Location:

Soddy-Daisy, TN 37379

Inspection Dates:

June 03, 2019 to June 27, 2019

Inspectors:

J. Seat, Project Engineer

M. Checkle, Senior Allegations Coordinator

N. Childs, Resident Inspector

W. Deschaine, Project Engineer

Approved By:

Omar R. López-Santiago, Chief

Reactor Projects Branch 5

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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.

List of Findings and Violations

Failure to Adequately Implement Requirements of Confirmatory Order EA-17-022,

Commitment V.1.b.3 Cornerstone Significance Cross-Cutting Aspect Report Section Not Applicable NCV 05000327,05000328/2019011-

Open/Closed Not Applicable 92702 The inspectors identified a Severity Level IV NCV for the licensees failure to adequately implement requirements of Confirmatory Order (CO) EA-17-022, Commitment V.1.b.3. Specifically, the licensee failed to ensure that new supervisory employees completed safety conscious work environment (SCWE) training within three months of their hire or promotion effective date.

Additional Tracking Items

None

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.

OTHER ACTIVITIES - BASELINE

71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)

The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.

• Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems.

• Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.

• Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

92702 CONF - Enforcement Related Order Follow-Up-Only Enforcement Related Order Follow-Up-Only

The inspectors reviewed commitments associated with four items from Confirmatory Order EA-17-022, issued to TVA on July 27, 2017.

(1) Commitment V.1.b.2: This commitment and action required that training be provided within one year and on an annual basis thereafter to, at a minimum, all working status nuclear business group supervisory employees, contractor supervisory employees involved in nuclear-related work activities, human resource staff involved in the adverse employment action process, employee concerns program staff, contract technical stewards for nuclear-related work activities, and the personnel in the TVA Office of General Counsel who are engaged in nuclear-related work activities. TVA identified 419 individuals at Sequoyah and TVA Corporate who were required to complete the training. The inspectors verified that the list of individuals included first line supervisors and above, contract technical stewards, human resources personnel, and employee concerns program personnel. The inspection was only completed for Sequoyah and TVA Corporate.

(2) Commitment V.1.b.3: This commitment and action required that new supervisory employees complete initial training through in-person or computer-based training within three months of their hire or promotion effective date. The training also required, at a minimum, a discussion of the training material with personnel in the TVA Office of General Counsel who are engaged in nuclear-related work activities. This commitment applied to new supervisory employees who were not included in the initial training specified in Commitment V.1.b.2. The inspectors reviewed records of Sequoyah and TVA Corporate employees and contractors who were hired or promoted into supervisory positions after July 28, 2018, to verify that personnel had completed the specified training within three months of their hire or promotion effective date. The inspection was only completed for Sequoyah and TVA Corporate.

(3) Commitment V.1.d.1: Inspectors performed an independent review of recent Adverse Employment Action and Executive Review Board (ERB) packages at Sequoyah and TVA Corporate. Specific activities included review of the background information associated with recent ERBs, associated SCWE Mitigation Plan Screening, SCWE Mitigation Plans, and results of recent pulse surveys conducted as a result of adverse actions taken against employees. The inspection was only completed for Sequoyah and TVA Corporate.

(4) Commitment V.1.e.1: This commitment required TVA to conduct an independent nuclear safety culture (NSC) assessment at Sequoyah and TVA Corporate by July 2018, evaluate the results and develop, implement, and track to completion, corrective actions to address weaknesses identified through the assessment. The inspectors reviewed corrective actions and enhancements associated with the 2018 nuclear safety culture assessments at Sequoyah (CR 1404011) and TVA Corporate (CR 1416534) to verify that corrective actions were implemented and tracked to completion. The inspection was only completed for Sequoyah and TVA Corporate.

INSPECTION RESULTS

Assessment 71152B

1. Corrective Action Program Effectiveness

Based on the samples reviewed, the team determined that the licensees corrective action program (CAP) complied with regulatory requirements and self-imposed standards. The licensees implementation of the CAP adequately supported nuclear safety.

Problem Identification: The team determined that most conditions that required generation of a condition report (CR) by licensee procedure, NPG-SPP-22.300, Corrective Action Program, had been appropriately entered into the CAP. The team observed members at the Management Review Committee (MRC) and Plant Screening Committee (PSC) meetings appropriately questioning and challenging condition reports to ensure clarification of issues and appropriate entry into the CAP. Based on the samples reviewed, the team determined that the licensee trended equipment and programmatic issues, and appropriately identified problems in condition reports. Additionally, the team concluded that personnel were identifying trends at low levels. The inspectors performed walkdowns, reviewed CRs, and reviewed system health and trending reports for the Auxiliary Feedwater System (AFW) and Chemical and Volume Control System (CVCS). Based on the inspectors' reviews and walkdowns of accessible portions of those systems, the inspectors determined that deficiencies were being identified and placed in the CAP. Overall, the team determined that the licensee is identifying problems at the proper threshold and entering them into the corrective action program.

Problem Prioritization and Evaluation: Based on the review of corrective action documents sampled by the inspection team during the onsite period, the team concluded that problems were generally prioritized and evaluated in accordance with the licensees CAP procedures as described in NPG-SPP-22.300, Corrective Action Program." Operability and reportability determinations were performed when conditions warranted, and the evaluations generally supported the conclusions. The causal analyses reviewed, appropriately considered the extent of condition or problem, generic issues, and previous occurrences of the issue. In general, the team determined the technical adequacy and depth of evaluations was appropriate. The team noted that the documented justification for extending some corrective action due dates lacked detail, however, the extensions appeared acceptable based on the nature of the corrective action. Overall, the team determined that the licensees process for evaluating and prioritizing issues once they had been entered into the corrective action program supported nuclear safety.

Effectiveness of Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that corrective actions were timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. For significant conditions adverse to quality, the corrective actions directly addressed the cause and effectively prevented recurrence. The inspectors reviewed condition reports and effectiveness reviews to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to preclude repetition were generally sufficient to ensure corrective actions were properly implemented and were effective. The inspectors reviewed corrective action documents for NRC findings issued since the last problem identification & resolution (PI&R) biennial inspection. The team determined that corrective actions completed or planned were adequate to address the NRC findings, and completion dates for open actions were reasonable.

2. Use of Operating Experience (OE)

Based on a review of selected documentation related to operating experience issues, the team determined that the licensee was generally effective in screening industry and NRC OE for applicability to the plant. Industry OE was evaluated at either the corporate or plant level depending on the source and type of document. Relevant information was forwarded to the applicable department for further action or informational purposes. Operating experience issues requiring action were entered into the CAP for tracking and closure. The team determined that the licensee's use of industry and NRC OE was effective, and the program adequately supported nuclear safety. The team did note that procedural requirements related to OE screening timeliness were vague, however, the team did not identify any instances where OE was not screened in a timely manner.

3. Self-Assessments and Audits

The team determined that the scopes of assessments and audits were adequate. Self-assessments were generally detailed and critical. The team verified that CRs were created to document areas for improvement and findings resulting from self-assessments, and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.

4. Safety Conscious Work Environment

Based on a sample size of approximately 35 individuals, interviewed from a cross-section of plant employees at Sequoyah and the TVA Corporate office, the team found no evidence of challenges to a safety-conscious work environment at either location. The following departments were sampled: Nuclear Oversight - Quality Assurance (52% sample),

Maintenance (12% sample), Chemistry (6% sample), Radiation Protection (8% sample),

Emergency Preparedness (6% sample), and Licensing (15% sample). Employees interviewed were willing to raise nuclear safety concerns through at least one of the several means available.

Interviewees were asked a series of questions in a semi-structured interview format.

Follow-up questions were asked as necessary to facilitate a full understanding of employees perceptions of the work environment. Questions included:

• Do you feel like your department encourages people to raise nuclear, radiological, or regulatory safety concerns (including challenging actions or decisions believed to be unsafe)?

• Do you feel like you can raise nuclear, radiological, or regulatory safety concerns safety concerns without fear of retaliation?

• Are you aware of any instance where someone experienced a negative reaction from a supervisor or manager for raising a nuclear, radiological, or regulatory safety issue?

• Do you believe other employees may be hesitant to raise nuclear, radiological, or regulatory safety concerns? Why? What would make them hesitant?

• Do you believe management is aware of these issues? Have actions been taken to address the situation?

• If you did not feel comfortable using your chain of command, are there other avenues you would use to raise a nuclear safety concern?

• In the past 6 months, has the environment in your department gotten better, worse, stayed the same?

• Would you feel comfortable using the Employee Concerns Program (ECP) if you had a nuclear safety concern?

• Do you feel like you are able to be open when participating in ECP pulsing surveys or other work environment assessments?

• Are you aware of the proposed changes regarding the ECP program at TVA?

• Do you feel like the new ECP structure would still provide independence from management?

Prior to the inspection, the licensee made fleet-wide communications regarding proposed changes to the ECP. When queried about the proposed ECP changes during the interviews, 31% of those interviewees were concerned that the proposed structure of the ECP would not provide independence from management, however, most would still be willing to use the ECP.

Minor Violation 71152B Minor Violation: 10 CFR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," states, in part, "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."

Contrary to the above, on August 15, 2017, the licensee failed to accomplish activities affecting quality in accordance with established procedures. Specifically, the licensee did not follow procedure NPG-SPP-22.300, "Corrective Action Program," Revision 9, step 3.7.6.B.1, which requires that corrective action controls (CA Control Flag in Maximo) be applied to work orders (WOs) credited for closure of a condition report requiring corrective actions. CR 1313355, which documented undersized seismic restraints securing temporary equipment, was closed to WO 118888040 without applying the required corrective action controls. WO 118888040 was later closed without sufficient evidence to demonstrate that appropriate actions had been taken to correct the condition identified in CR 1313355. The failure to apply corrective action controls to WO 118888040, per NPG-SPP-22.300, was a performance deficiency.

Screening: The inspectors determined the performance deficiency was minor. The inspectors answered "no" to the more than minor screening questions in IMC 0612 Appendix B, "Issue Screening," dated January 1, 2018.

Enforcement:

The licensee initiated CR 1526428 to address this minor violation. The licensee performed walkdowns to verify that temporary equipment secured with undersized seismic restraints was no longer present. This failure to comply with procedural requirements constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Failure to Adequately Implement Requirements of Confirmatory Order EA-17-022, Commitment V.1.b.3 Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000327,05000328/2019011-01 Open/Closed

Not Applicable 92702 The inspectors identified a Severity Level (SL) IV NCV for the licensees failure to adequately implement requirements of Confirmatory Order EA-17-022, Commitment V.1.b.3. Specifically, the licensee failed to ensure that new supervisory employees completed safety conscious work environment (SCWE) training within three months of their hire or promotion effective date.

Description:

Confirmatory Order (CO) EA-17-022, issued to TVA on July 27, 2017, requires, in part, that certain personnel complete initial and recurring SCWE training. Specifically, commitment V.1.b.3 in CO EA-17-022 requires that: New supervisory employees shall complete initial training through in-person or computer-based training within three months of their hire or promotion effective date. The training shall require, at a minimum, a discussion of the training material with personnel in the TVA Office of General Counsel who are engaged in nuclear related work activities.

On December 26, 2018, the licensee identified two nuclear business group employees and one contractor employee at Sequoyah who were hired into or promoted to supervisory positions after July 27, 2018, but who did not complete the specified SCWE training within three months of their hire or promotion effective date. The licensee entered this issue into their CAP as CR 1478023. At the time this CR was written, the licensee did not realize that this training requirement was also applicable to supplemental workers.

In March of 2019, at an NRC Inspection Exit Meeting at Watts Bar, TVA was notified that the 90-day SCWE requirement does apply to supplemental workers. The licensee completed an extent of condition review and identified four contractor employees involved in nuclear related work activities who were new to supervisory positions and did not complete the training in the three-month time period.

Corrective Actions: The licensee entered this issue into their corrective action program on December 26, 2018 and took immediate action to ensure all Sequoyah employees had completed the training by February 6, 2019. A CR was written on December 26, 2018, with actions to perform an apparent cause analysis of the incorrect due dates and track actions at the TVA Corporate level. The licensee initiated a CR on March 5, 2019, to document the missed SCWE training for new contractor supervisory employees.

Corrective Action References: CR 1477482, CR 1477964, CR 1484364, CR 1478023, CR 1497144

Performance Assessment:

The licensees failure to ensure that new supervisory employees completed SCWE training within three months of their hire or promotion effective date was in violation of commitment V.1.b.3 in Confirmatory Order Modifying License (EA-17-022). The inspectors determined that this violation was associated with impeding the regulatory process and subject to traditional enforcement as described in the NRC Enforcement Policy, dated May 15, 2019.

Enforcement:

The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address this violation which impedes the NRCs ability to regulate using traditional enforcement to adequately deter non-compliance.

Severity: The inspectors determined this violation constituted a more than minor traditional enforcement violation associated with failure to implement the requirements of CO EA-17-022. The inspectors determined that the failure to ensure that current and future CO requirements continue to be met could potentially impact safety. Specifically, in this example, failure to ensure new supervisory employees complete SCWE training in a timely manner could cause missed opportunities to identify and/or prevent an environment where individuals would be hesitant to raise nuclear safety concerns for fear of retaliation. The violation is more than minor because it was not isolated to one or two individuals. The inspectors determined that the licensees failure to implement the requirements of the Confirmatory Order is considered an SL IV violation, consistent with Section 2.2.2.d of the NRC Enforcement Policy, dated May 28, 2019.

Violation: Commitment V.1.b.3 in Confirmatory Order EA-17-022, issued to TVA on July 27, 2017, requires, in part, that: New supervisory employees shall complete initial training through in-person or computer-based training within three months of their hire or promotion effective date. The training shall require, at a minimum, a discussion of the training material with personnel in the TVA Office of General Counsel who are engaged in nuclear related work activities.

Contrary to the above, from July 28, 2018 to March 5, 2019, the licensee failed to ensure that new supervisory employees completed SCWE training within three months of their hire or promotion effective date. Specifically, two new Sequoyah supervisory employees and five new contractor supervisory employees involved in nuclear related work activities did not complete the SCWE training within three months as required.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On June 20, 2019, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Matthew Rasmussen and other members of the licensee staff.

• On June 27, 2019, the inspectors presented the confirmatory order follow-up inspection results to Mr. Matthew Rasmussen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Calculations

MDQ0000682018000101 Material Aging for PORV Target Rock Solenoid Valves

(SQNEQ-SOL-002)

Revision 0

71152B

Calculations

SCG1S596

Maintenance Rule for Structures and License Renewal

Structures Monitoring Program Inspections

Revision 13

71152B

Corrective Action

Documents

CR 1002259

OE - Foreign Material Damages Steam Generator

Tube Sheet

03/20/2015

71152B

Corrective Action

Documents

CR 1002268

OE - Performance Shortfalls During Mechanical

Maintenance Activities

03/20/2015

71152B

Corrective Action

Documents

CR 1002270

NOER - Loss of Breaker Configuration Control PER

965728

03/20/2015

71152B

Corrective Action

Documents

CR 1002275

NOER - Missed Surveillance on New Components

03/20/2015

71152B

Corrective Action

Documents

CR 1002293

OE - Loss of Jet Pump Plug Seals in Reactor Vessel

03/20/2015

71152B

Corrective Action

Documents

CR 1003153

OE - BFN Loss of Inventory from Reactor Cavity

03/23/2015

71152B

Corrective Action

Documents

CR 1017143

Found Cracks in the Cover on Vital Battery #2

04/22/2015

71152B

Corrective Action

Documents

CR 1023172

NOER - Reactor Trip due to Loss of Main Condenser

Vacuum

05/07/2015

71152B

Corrective Action

Documents

CR 1023175

NOER - PER Classification and Level of Significance

05/07/2015

71152B

Corrective Action

Documents

CR 1023207

OE - Ice Bed Increasing Temperature Trends

05/07/2015

71152B

Corrective Action

Documents

CR 1025764

Oil Bubbler is at 20% Recommend Minor Maintenance

to Fill Reservoir

05/14/2015

71152B

Corrective Action

Documents

CR 1064736

Evaluate DCN 23085 - Kirk Key Interlocks

07/30/2015

71152B

Corrective Action

Documents

CR 1084294

NRC NCV 2015-007-02 - 50.59/Modifications

Inspection

09/21/2015

71152B

Corrective Action

Documents

CR 1104335

CRDM Cable Connection Issues Found During

Disconnection

11/15/2015

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

CR 1106765

1-LCV-3-148 not Able to be Operated in Manual

11/20/2015

71152B

Corrective Action

Documents

CR 1116558

2-FSV-43-55 Failed 2-SI-SXV-000-204.0 Valve Stroke

2/16/2015

71152B

Corrective Action

Documents

CR 1121723

2-FSV-43-61 Has no Light Indication While Valve is

Closed

01/05/2016

71152B

Corrective Action

Documents

CR 115765

Potential Transformer (PT) in Compartment #3

2/01/2006

71152B

Corrective Action

Documents

CR 1169090

Post Accident Monitoring (2-XX-55-6L) for Valve 2-

FCV-43-61 Indicates Intermediate Position

05/09/2016

71152B

Corrective Action

Documents

CR 1181710

NRC CDBI DG Bldg Ventilation System and Tornado

Impact

06/14/2016

71152B

Corrective Action

Documents

CR 1187308

Operations Request POE - Instrument Calibration

Issues

06/30/2016

71152B

Corrective Action

Documents

CR 1227157

Potential Error Trap with Breaker UNIDs

10/26/2016

71152B

Corrective Action

Documents

CR 1240813

0-MI-MRR-003-461.0 Needs to be Revised - TDAFW

Mech Overspeed Trip Linkage Spring Setting is

Incorrect

2/10/2016

71152B

Corrective Action

Documents

CR 1254470

CRs Closed to WOs Without Correct Coding in WO

01/25/2017

71152B

Corrective Action

Documents

CR 1254937

NOER was not Generated for CR 1241933

01/26/2017

71152B

Corrective Action

Documents

CR 1255171

Gaps in Extent of Condition Review of QA Finding

RCA 1155352

01/26/2017

71152B

Corrective Action

Documents

CR 1255177

Trend in Site CAP Procedure Adherence to NPG-SPP-

2.300

01/26/2017

71152B

Corrective Action

Documents

CR 1269767

A212 ABSCE Breach Resulting in Both Trains of

ABGTS Inoperable for Both Units

03/07/2017

71152B

Corrective Action

Documents

CR 1290969

Snapshot Assessment - PD - SQN-PI-SSA-17-007 -

OE Coordinators

05/02/2017

71152B

Corrective Action

Documents

CR 1301718

Unit 1 TDAFW Suction Pressure Gauge Found

Isolated

05/30/2017

71152B

Corrective Action

CR 1303852

RP REP VANS

06/05/2017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71152B

Corrective Action

Documents

CR 1305710

Procedure Change Request for 2-SI-SXV-003-219.S

06/10/2017

71152B

Corrective Action

Documents

CR 1311223

QA ID: The Chemical Hygiene Plan was not reviewed

during 2016 (SSA1707)

06/26/2017

71152B

Corrective Action

Documents

CR 1311501

QA ID: SSA1707: Inconsistent performance of

surveillance procedure requirements

06/27/2017

71152B

Corrective Action

Documents

CR 1313355

Inadequate chain size used for temporary equipment

seismic restraint

07/03/2017

71152B

Corrective Action

Documents

CR 1313866

OE-Green-WBN-NOER-17-014-Unplanned LCO 3.7.5

entry due to time delay relay failure

07/05/2017

71152B

Corrective Action

Documents

CR 1321168

Corrective Action for CR 1303852 did not resolve

condition identified

07/25/2017

71152B

Corrective Action

Documents

CR 1323549

QAID Improper use of N/A (SSA 1708)

08/01/2017

71152B

Corrective Action

Documents

CR 1323551

QA Records from ALARA not being transmitted to

EDMS

08/01/2017

71152B

Corrective Action

Documents

CR 1323555

QAID Temporary Shielding forms not properly filled out

(SSA 1708)

08/01/2017

71152B

Corrective Action

Documents

CR 1323558

QAID Recommendation on temporary shielding

support (SSA 1708)

08/01/2017

71152B

Corrective Action

Documents

CR 1324371

Follow-up on CR 1324282 from SQN RP - RW Audit

08/03/2017

71152B

Corrective Action

Documents

CR 1334122

NRC Regulatory Issue Summary (RIS) 2017-04

08/31/2017

71152B

Corrective Action

Documents

CR 1336290

Cable Tray Supports out of Tolerance

09/07/2017

71152B

Corrective Action

Documents

CR 1341686

Cable Tray Supports out of Tolerance

09/25/2017

71152B

Corrective Action

Documents

CR 1343410

SGI records

09/29/2017

71152B

Corrective Action

Documents

CR 1364616

OE - Part 21 2017-52-00 Fisher Type 461 Valve Plug

Machining

2/04/2017

71152B

Corrective Action

CR 1366082

SQN DBA EQ 201700X

2/07/2017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71152B

Corrective Action

Documents

CR 1366200

Unit 1 Lower Compartment Cooler Motor EQ

Qualification

2/072017

71152B

Corrective Action

Documents

CR 1372336

Fatigue Rule Violation

2/28/2017

71152B

Corrective Action

Documents

CR 1378392

M-B ERCW Pump stopped due to rising bearing temps

01/18/2018

71152B

Corrective Action

Documents

CR 1380592

Equipment relocated during installation of plexi-glass

01/24/2018

71152B

Corrective Action

Documents

CR 1381347

NCV 2017008-01, Unjustified Qualified Life for Target

Rock PORVs

01/26/2018

71152B

Corrective Action

Documents

CR 1381348

NCV 2017008-02, Inadequate Qualification for Reactor

Lower Compartment Cooler Motors

01/26/2018

71152B

Corrective Action

Documents

CR 1391505

Deficiencies identified during mock 95001 inspection

2/28/2018

71152B

Corrective Action

Documents

CR 1394115

OE - NRC Information Notice 2018-02

03/08/2018

71152B

Corrective Action

Documents

CR 1403173

Boric acid valve leaking badly near BAT pump 1A

04/09/2018

71152B

Corrective Action

Documents

CR 1403747

SGI Records

04/09/2018

71152B

Corrective Action

Documents

CR 1403761

SGI Records

04/09/2018

71152B

Corrective Action

Documents

CR 1403896

Boric acid leak on Unit 2 emergency boration FT

instrument line

04/10/2018

71152B

Corrective Action

Documents

CR 1403944

SGI Records

04/10/2018

71152B

Corrective Action

Documents

CR 1403950

SGI Records

04/11/2018

71152B

Corrective Action

Documents

CR 1404549

1-LT-62-130 VCT Level Indication Failed Low

04/11/2018

71152B

Corrective Action

Documents

CR 1404590

LL BOP/NSSS DCS Loss of 62-130A

04/11/2018

71152B

Corrective Action

CR 1407364

U1R22 Outage WO Screening - FIN resources

04/20/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71152B

Corrective Action

Documents

CR 1408522

Issues found during performance of 1-SI-SXP-062-

203.0

04/24/2018

71152B

Corrective Action

Documents

CR 1408611

Troubleshoot CCP 1A Pump Vibration After U1R22

Rebuild

04/24/2018

71152B

Corrective Action

Documents

CR 1410388

Grout base plate under 1A CCP post U1R22

05/01/2018

71152B

Corrective Action

Documents

CR 1413732

Non-cited Violation (NCV) 05000327/328/2018001-01

05/11/2018

71152B

Corrective Action

Documents

CR 1413734

Non-cited Violation (NCV) 05000327/328/2018001-02

05/11/2018

71152B

Corrective Action

Documents

CR 1414850

NRC Identified Green NCV 390/2018410

05/15/2018

71152B

Corrective Action

Documents

CR 1416612

Vibration Point 8H in Alert Range

05/21/2018

71152B

Corrective Action

Documents

CR 1433166

Suspect B Train EGTS FS-65-44 Failed

07/22/2018

71152B

Corrective Action

Documents

CR 1436225

EGTS Licensee Event Report Required Information

08/02/2018

71152B

Corrective Action

Documents

CR 1443992

OE - Review NRC IN 18-09 Electrical Arc Flash

08/30/2018

71152B

Corrective Action

Documents

CR 1444099

Found leads lifted for an alarm on 1B diesel

08/31/2018

71152B

Corrective Action

Documents

CR 1447183

OE - IN-18-10, Thermal Sleeve Flange Wear Leads to

Stuck Control Rod

09/13/2018

71152B

Corrective Action

Documents

CR 1449176

OE - NRC Regulatory Issue Summary 2018-04

09/20/2018

71152B

Corrective Action

Documents

CR 1463962

Inability to timely retrieve design records

11/07/2018

71152B

Corrective Action

Documents

CR 1471007

EQ Binder SQN-SOL-002 baseline evaluation

11/29/2018

71152B

Corrective Action

Documents

CR 1476565

Minor Void Found in Emergency Boration Line Above

1-FT-62-137

2/18/2018

71152B

Corrective Action

CR 1477034

Gas void observed during performance of 1-SI-OPS-

2/19/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

2-040.A U1 CCP piping vent

71152B

Corrective Action

Documents

CR 1482178

SQN Site Records List does not agree with NPG-SPP-

2.300 records (QA audit SSA1901)

01/14/2019

71152B

Corrective Action

Documents

CR 1482468

QA ID: Department OE Coordinators have not

completed the required JFG (SSA1901)

01/15/2019

71152B

Corrective Action

Documents

CR 1482669

Biennial fleet wide self assessment of the OE program

not performed as required by NPG-SPP-22.500

01/15/2019

71152B

Corrective Action

Documents

CR 1483225

Revision recommendation for NPG-SPP-22.300

01/17/2019

71152B

Corrective Action

Documents

CR 1483228

Revision recommendation for NPG-SPP-22.500

01/17/2019

71152B

Corrective Action

Documents

CR 1483291

Re-evaluate NPG-SPP-22.500 as quality related

01/17/2019

71152B

Corrective Action

Documents

CR 1485069

2019 WBN PI&R Inspection - Issues with CR 1414850

01/24/2019

71152B

Corrective Action

Documents

CR 1488033

Non-cited Violation (NCV) 2018004-02

2/04/2019

71152B

Corrective Action

Documents

CR 1489420

Revise security procedure

2/08/2019

71152B

Corrective Action

Documents

CR 1490857

Rx Power Does not Respond Correctly to Manual

Make-ups Calculated to Maintain Power Stable

2/14/2019

71152B

Corrective Action

Documents

CR 1490951

Evaluation of trend intrusion issues in manholes across

SQN

2/14/2019

71152B

Corrective Action

Documents

CR 1491065

Establish and sustain a culture of excellence in PU&A

in Chemistry

2/14/2019

71152B

Corrective Action

Documents

CR 1494149

OE - WBN Integrated Inspection Report Nov 2018

Findings

2/27/2019

71152B

Corrective Action

Documents

CR 1498586

DCN 21287 contained an incorrect calculation for main

steam line radiation release rate

03/13/2019

71152B

Corrective Action

Documents

CR 1500107

SQN-PI-FSA-19-002, PI&R Self Assessment

03/18/2019

71152B

Corrective Action

Documents

CR 1500629

OE - IN-2019-01, Inadequate Evaluation of Temporary

Alterations

03/20/2019

71152B

Corrective Action

CR 1503036

2017 SQN EQ DBA Inspection: Foxboro/Weed

03/28/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

Transmitter heat rise issue, SLD.

71152B

Corrective Action

Documents

CR 1503045

2017 SQN EQ DBA Inspection: ASCO valves potential

performance deficiencies, SLD

03/28/2019

71152B

Corrective Action

Documents

CR 1503045

2017 SQN EQ DBA Inspection - ASCO valves potential

performance deficiencies

03/28/2019

71152B

Corrective Action

Documents

CR 1506308

Non-cited Violation (NCV) 2018412-01

04/09/2019

71152B

Corrective Action

Documents

CR 1506325

Replace U1 LCC Fan Motors during U1R24

04/09/2019

71152B

Corrective Action

Documents

CR 1506831

Review Unusual Event at Brunswick Unit 1 which

required a shutdown

04/10/2019

71152B

Corrective Action

Documents

CR 1509174

Respond to NRC RIS 2019-02, Preparation and

Scheduling of Operator Licensing Examinations

04/18/2019

71152B

Corrective Action

Documents

CR 1510339

SQN-PI-FSA-10-002 - Objective 7 - Appendix R

Triennial Inspection CR 1276596 has not been

resolved timely

04/23/2019

71152B

Corrective Action

Documents

CR 1510464

CR 1485069 did not document department manager

approval

04/23/2019

71152B

Corrective Action

Documents

CR 1510873

SQN-PI-FSA-19-002 - Objective 7 - Deficiencies noted

in CRs 1403944, 1441458, and 1403761

04/24/2019

71152B

Corrective Action

Documents

CR 1510985

SQN-PI-FSA-!(-002 - Objective 7 PD - A Review of

NCV 2017008-01

04/24/2019

71152B

Corrective Action

Documents

CR 1511003

SQN-PI-FSA-19-002 - Objective 7 PD - A Review of

NCV 2017008-02

04/24/2019

71152B

Corrective Action

Documents

CR 1511249

SQN-PI-FSA-19-002 Objective 7 PD (1500107-033)

LER-2018-001-00

04/25/2019

71152B

Corrective Action

Documents

CR 1512747

Non-cited Violation (NCV) 05000327/328/2019010-01

05/01/2019

71152B

Corrective Action

Documents

CR 1514352

QA elevation on protected equipment

05/06/2019

71152B

Corrective Action

Documents

CR 1516824

NCV 2019-02, Failure to account for heat rise in

Foxboro/Weed instruments

05/15/2019

71152B

Corrective Action

Documents

CR 1519228

Gas/water Flow Noted During Cold Leg Injection Piping

Vent

05/23/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

CR 1525798

OE - Issues with OE Reviews in Accordance with

NPG-SPP-22.600

06/18/2019

71152B

Corrective Action

Documents

CR 655554

Loop 4 TDAFW LCV failed stroke time

2/12/2012

71152B

Corrective Action

Documents

CR 660015

OE review of WBN-NOER-12-079

2/21/2012

71152B

Corrective Action

Documents

CR 663698

Review of WBN-NOER-12-106 AFW valve stroke time

01/04/2013

71152B

Corrective Action

Documents

CR 740635

SGTR accident analysis issue related to maintenance

06/14/2013

71152B

Corrective Action

Documents

CR 750649

SQN review of Byron U2 scram from loss of main

generator stator cooling

07/09/2013

71152B

Corrective Action

Documents

CR 751276

SQN review of Vogtle U2 manual reactor scram due to

high RCP seal leak off

07/10/2013

71152B

Corrective Action

Documents

CR 791573

SQN review of Davis-Besse scram from RCP motor

faulty electrical connections

10/10/2013

71152B

Corrective Action

Documents

CR 915358

Unit 2 main turbine high vibration

07/30/2014

71152B

Corrective Action

Documents

CR 959976

Aging management review for ground water in

distribution board

11/24/2014

71152B

Corrective Action

Documents

CR 965728

Procedure swap performed with step marked N/A that

resulted in configuration control issue

2/10/2014

71152B

Corrective Action

Documents

CR 973446

2B MDAFW system check valve backleakage

01/05/2015

71152B

Corrective Action

Documents

CR 981733

Low oil on 2A MDAFWP inboard pump bearing

01/27/2015

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1522084

Broken UNID tag

06/04/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1522525

Procedure NPG-SPP-22.300 change request

06/05/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1525710

Individual missed 2018 SCWE Training - CO issue

06/18/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1525830

NRC ID - ERB package documentation error - CO

issue

06/18/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1525832

NPG-SPP-03.9 wording of Significant Gap Analysis not

matching NPG-SPP-22.300

06/18/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1525869

NOER-SQN-17-003 has incorrect event date

06/18/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1526184

Extension request reason insufficient

06/19/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1526337

Incorrect Maximo attachments

06/20/2019

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 1526428

Inadequate response to CRs

06/20/2019

71152B

Engineering

Changes

DCN 23813

Replace Steam Generator Blowdown Containment

Isolation Sample Valves

Revision 1

71152B

Miscellaneous

U2 Function 043-E (a)(1) plan

Revision 2

71152B

Miscellaneous

Quality Assurance Master Audit Schedule 2019-2020

08/29/2017

71152B

Miscellaneous

Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant,

and Watts Bar Nuclear Plant Initial Response to NRC

05/09/2008

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Generic Letter 2008-01

71152B

Miscellaneous

Sequoyah Nuclear Plant - Closeout of Generic Letter 2008-01

04/22/2011

71152B

Miscellaneous

Operations Standing Order List

06/05/2019

71152B

Miscellaneous

Chemical and Volume Control System (CVCS) Health

Report Scorecard

1st Quarter

2019

71152B

Miscellaneous

SQN Maintenance Rule List - SSCs in (a)(1) Status

since June 2017

71152B

Miscellaneous

Unit 1 MCR Deficiencies List

06/05/2019

71152B

Miscellaneous

Unit 2 MCR Deficiencies List

06/05/2019

71152B

Miscellaneous

System #333 Health Report Screenshot

71152B

Miscellaneous

CDE 2855

2-FSV-43-61 PAM indication inoperable for 30 days

08/28/2015

71152B

Miscellaneous

CDE 2884

2-FSV-43-61 no light indication in main control room

01/04/2016

71152B

Miscellaneous

CDE 2886

2-FSV-43-55 Failed 2-SI-SXV-043-204.0

2/09/2015

71152B

Miscellaneous

CDE 2903

2-FSV-43-61 PAM instrument had dual light position

indications

05/10/2016

71152B

Miscellaneous

MRC

Management Review Committee Package

06/06/2019

71152B

Miscellaneous

PSC

Plant Screening Committee Package

06/05/2019

71152B

Miscellaneous

QA-SQ-18-006

Sequoyah Nuclear Plant - Quality Assurance Site

Report

03/14/2018

71152B

Miscellaneous

QA-SQ-19-002

Sequoyah Nuclear Plant - Quality Assurance Site

Report

2/07/2019

71152B

Miscellaneous

QA-SQ-19-004

Sequoyah Nuclear Plant - Quality Assurance Site

Report

03/11/2019

71152B

Miscellaneous

QA-SQ-19-006

Sequoyah Nuclear Plant - Quality Assurance Site

Report

04/08/2019

71152B

Miscellaneous

QA-SQ-19-008

Sequoyah Nuclear Plant - Quality Assurance Site

Report

05/09/2019

71152B

Miscellaneous

SQN-DC-V-13.9.8

Sequoyah Nuclear Plant - Auxiliary Feedwater System,

Design Criteria Document

Revision 29

71152B

Miscellaneous

SQN-DC-V-27.2

Sequoyah Nuclear Plant - Chemical and Volume

Control System, Design Criteria

Revision 35

71152B

Miscellaneous

UFSAR Chapter 13.9

License Renewal Program

Revision 26

71152B

Procedures

0-MI-MRR-003-461.0

Disassembly, Inspection, and Reassembly of the

Revision 26

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Auxiliary Feedwater Pump Turbine

71152B

Procedures

1-SI-IFT-068-067.4

Functional Test of Delta T/TAVG Channel IV Rack 13

Loop 1-T-68-67 (T-441/442)

Revision 28

71152B

Procedures

1-SI-OPS-062-040.A

Centrifugal Charging Pump 1A-A Casing, Suction, and

Discharge Piping Venting

Revision 42

71152B

Procedures

NPG-SPP-03.4

Maintenance Rule Performance Indicator Monitoring,

Trending and Reporting - 10CFR50.65

Revision 3

71152B

Procedures

NPG-SPP-07.1.4

Work Management Prioritization - Online

Revision 9

71152B

Procedures

NPG-SPP-07.6

NPG Work Management Planning Procedure

Revision 15

71152B

Procedures

NPG-SPP-07.6

NPG Work Management Planning Procedure

Revision 16

71152B

Procedures

NPG-SPP-22.300

Corrective Action Program

Revision 14

71152B

Procedures

NPG-SPP-22.300

Corrective Action Program

Revision 15

71152B

Procedures

NPG-SPP-22.300

Corrective Action Program

Revision 12

71152B

Procedures

NPG-SPP-22.300

Corrective Action Program

Revision 10

71152B

Procedures

NPG-SPP-22.500

Operating Experience Program

Revision 7

71152B

Procedures

NPG-SPP-22.600

Issue Resolution

Revision 5

71152B

Procedures

OPDP-1

Conduct of Operations

Revision 43

71152B

Procedures

OPDP-11

Operational Decision-Making Issue Evaluation Process

Revision 6

71152B

Procedures

OPDP-4

Annunciator Disablement

Revision 7

71152B

Self-

Assessments

SSA1701

Site Audit Report, Corrective Action Program,

Sequoyah Nuclear Plant (SQN), January 23-27, 2017

2/22/2017

71152B

Self-

Assessments

SSA1707

Site Audit Report, Chemistry, Effluent, and

Environmental Monitoring, Sequoyah Nuclear Plant

(SQN), June 19-30, 2017

07/17/2017

71152B

Self-

Assessments

SSA1708

Site Audit Report, Radiation Protection, Radwaste,

Sequoyah Nuclear Plant (SQN), July 24-August 2,

2017

08/10/2017

71152B

Self-

Assessments

SSA1804

Site Audit Report, Maintenance, Sequoyah Nuclear

Station (SQN), March 26-April 6, 2018

04/20/2018

71152B

Self-

Assessments

SSA1901

Corrective Action, Chattanooga Office Complex (COC),

Browns Ferry (BFN), Sequoyah (SQN) and Watts Bar

(WBN) Nuclear Plants, January 14-18, 2019

01/30/2019

71152B

Work Orders

113086647

Replace Unit 2 PORVs

71152B

Work Orders

113574449

Replace current control unit for 2-FSV-043-0055-B

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Work Orders

115152446

Replace Unit 2 PORVs

71152B

Work Orders

117485917

Steam Generator Blowdown #3 Isolation Valve has no

Light Indication in MCR

71152B

Work Orders

117715470

Calibrate TDAFWP inlet pressure indicator

71152B

Work Orders

117733991

Perform additional groundwater in-leakage repairs in

various yard areas

71152B

Work Orders

117910082

Inspect and clean 250 VDC battery board #2

71152B

Work Orders

118800008

Replace EGTS Train B electronic circuit board

71152B

Work Orders

118878733

DCN 23638 Stage 8 outage cable terminations and

modifications

71152B

Work Orders

118888040

Inadequate chain size used for temporary equipment

seismic restraint

71152B

Work Orders

118946474

Replace 1-RLY-62-108/CPBY-1A due to Part 21 issue

71152B

Work Orders

119111157

Perform groundwater in-leakage repairs in various

areas for the Auxiliary Building

71152B

Work Orders

119444328

Rewind or replace 1B-B LCC fan motor to resolve

NCV, CR 1381348

71152B

Work Orders

119444348

Rewind or replace 1C-A LCC fan motor to resolve

NCV, CR 1381348

71152B

Work Orders

119444352

Rewind or replace 1D-B LCC fan motor to resolve

NCV, CR 1381348

71152B

Work Orders

119448481

Rewind or replace 1A-A LCC fan motor to resolve

NCV, CR 1381348

71152B

Work Orders

119529017

1-LT-62-130 VCT level indication has failed low

71152B

Work Orders

119568924

1A CCP grout base plate

71152B

Work Orders

119855356

Implement DCN 22643 Stage 6 to replace U1 PORV

334-B

71152B

Work Orders

119855374

Implement DCN 22643 Stage 5 to replace U1 PORV

340A-A

71152B

Work Orders

20398985

Replace U1 1A-A LCC Fan Motors during U1R24

71152B

Work Orders

20398986

Replace U1 1D-B LCC Fan Motor during U1R24

71152B

Work Orders

20398987

Replace U1 1C-A LCC Fan Motor during U1R24

71152B

Work Orders

20398988

Replace U1 1B-B LCC Fan Motor during U1R24

2702

Corrective Action

22419

Action Implementation Tracking for Confirmatory Order

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

EA-17-022

2702

CONF

Corrective Action

Documents

1404011

Sequoyahs response to the Oak Ridge Associated

Universities nuclear safety culture assessment report

2702

CONF

Corrective Action

Documents

1416534

Track Corporate's response to NSC assessment.

2702

CONF

Corrective Action

Documents

1448122

OE.01.NUC.01-Sustain TVA Nuclear Work

Environment

2702

CONF

Corrective Action

Documents

1451197-003

SCWE Mitigation Plan follow up actions for corporate

ERB case numbers CORP-2019-010, 011, 012, 013

and 014

2702

CONF

Corrective Action

Documents

1477964

LMS Curriculum NPG-TVA-400152, SCWE EA 17-022

incorrect due dates

2702

CONF

Corrective Action

Documents

1478023

LMS Curriculum NPG-TVA-400152, SCWE EA 17-022

is calculating incorrect due date

2702

CONF

Corrective Action

Documents

1484364

Action Tracking for SQN SCWE Refresher Training

2702

CONF

Corrective Action

Documents

1492600

Safety Culture

2702

CONF

Corrective Action

Documents

1497144

EA-17-022,Section V.1.b.3 90-day SCWE training

requirement not met

2702

CONF

Corrective Action

Documents

Resulting from

Inspection

25830

Discrepancy in ERB 2018-031 TVA Forms 41647 (item

1. 3) and 41651 (item # 1)

2702

CONF

Corrective Action

Documents

Resulting from

Inspection

26768

ECP Benchmarking not documented per NPG-SPP-

2.102

2702

CONF

Miscellaneous

Sequoyah Nuclear Plant Nuclear Safety Culture

Evaluation, prepared by Oak Ridge Associated

Universities

April 2018

2702

CONF

Procedures

Conduct of Operations Employee Concerns

Revision 7

2702

Procedures

1193005

Business Plan Initiative OE.01.Nuc.01 (Improve TVA

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CONF

Nuclear Work Environment)

2702

CONF

Procedures

ECP-1

Employee Concerns Staff Desktop Instruction 1 ECP

Administration

Revision 0

2702

CONF

Procedures

NPG-SPP-01.7

Nuclear Safety Culture

Revision 5

2702

CONF

Procedures

NPG-SPP-01.7.1

Employee Concerns Program

Revision 3

2702

CONF

Procedures

NPG-SPP-01.7.2

Nuclear Safety Culture Monitoring

Revision 13

2702

CONF

Procedures

NPG-SPP-01.7.3

Conduct of Nuclear Safety Culture Assessments and

Organizational Effectiveness Surveys

Revision 4

2702

CONF

Procedures

NPG-SPP-01.7.4

Adverse Employment Action and Executive Review

Board

Revision 1

2702

CONF

Procedures

NPG-SPP-01.7.4

Adverse Employment Action and Executive Review

Board

Revision 3

2702

CONF

Procedures

TVA-SPP-22.100

Change Management

Revision 0