IR 05000327/2019011
| 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:
Report Numbers:
05000327/2019011 and 05000328/2019011
Enterprise Identifier: I-2019-011-0036
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?
- 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
Calculations
MDQ0000682018000101 Material Aging for PORV Target Rock Solenoid Valves
(SQNEQ-SOL-002)
Revision 0
Calculations
SCG1S596
Maintenance Rule for Structures and License Renewal
Structures Monitoring Program Inspections
Revision 13
Corrective Action
Documents
CR 1002259
OE - Foreign Material Damages Steam Generator
Tube Sheet
03/20/2015
Corrective Action
Documents
CR 1002268
OE - Performance Shortfalls During Mechanical
Maintenance Activities
03/20/2015
Corrective Action
Documents
CR 1002270
NOER - Loss of Breaker Configuration Control PER
965728
03/20/2015
Corrective Action
Documents
CR 1002275
NOER - Missed Surveillance on New Components
03/20/2015
Corrective Action
Documents
CR 1002293
OE - Loss of Jet Pump Plug Seals in Reactor Vessel
03/20/2015
Corrective Action
Documents
CR 1003153
OE - BFN Loss of Inventory from Reactor Cavity
03/23/2015
Corrective Action
Documents
CR 1017143
Found Cracks in the Cover on Vital Battery #2
04/22/2015
Corrective Action
Documents
CR 1023172
NOER - Reactor Trip due to Loss of Main Condenser
Vacuum
05/07/2015
Corrective Action
Documents
CR 1023175
NOER - PER Classification and Level of Significance
05/07/2015
Corrective Action
Documents
CR 1023207
OE - Ice Bed Increasing Temperature Trends
05/07/2015
Corrective Action
Documents
CR 1025764
Oil Bubbler is at 20% Recommend Minor Maintenance
to Fill Reservoir
05/14/2015
Corrective Action
Documents
CR 1064736
Evaluate DCN 23085 - Kirk Key Interlocks
07/30/2015
Corrective Action
Documents
CR 1084294
NRC NCV 2015-007-02 - 50.59/Modifications
Inspection
09/21/2015
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
Corrective Action
Documents
CR 1106765
1-LCV-3-148 not Able to be Operated in Manual
11/20/2015
Corrective Action
Documents
CR 1116558
2-FSV-43-55 Failed 2-SI-SXV-000-204.0 Valve Stroke
2/16/2015
Corrective Action
Documents
CR 1121723
2-FSV-43-61 Has no Light Indication While Valve is
Closed
01/05/2016
Corrective Action
Documents
CR 115765
Potential Transformer (PT) in Compartment #3
2/01/2006
Corrective Action
Documents
CR 1169090
Post Accident Monitoring (2-XX-55-6L) for Valve 2-
FCV-43-61 Indicates Intermediate Position
05/09/2016
Corrective Action
Documents
CR 1181710
NRC CDBI DG Bldg Ventilation System and Tornado
Impact
06/14/2016
Corrective Action
Documents
CR 1187308
Operations Request POE - Instrument Calibration
Issues
06/30/2016
Corrective Action
Documents
CR 1227157
Potential Error Trap with Breaker UNIDs
10/26/2016
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
Corrective Action
Documents
CR 1254470
CRs Closed to WOs Without Correct Coding in WO
01/25/2017
Corrective Action
Documents
CR 1254937
NOER was not Generated for CR 1241933
01/26/2017
Corrective Action
Documents
CR 1255171
Gaps in Extent of Condition Review of QA Finding
RCA 1155352
01/26/2017
Corrective Action
Documents
CR 1255177
Trend in Site CAP Procedure Adherence to NPG-SPP-
2.300
01/26/2017
Corrective Action
Documents
CR 1269767
A212 ABSCE Breach Resulting in Both Trains of
ABGTS Inoperable for Both Units
03/07/2017
Corrective Action
Documents
CR 1290969
Snapshot Assessment - PD - SQN-PI-SSA-17-007 -
OE Coordinators
05/02/2017
Corrective Action
Documents
CR 1301718
Unit 1 TDAFW Suction Pressure Gauge Found
Isolated
05/30/2017
Corrective Action
CR 1303852
06/05/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
CR 1305710
Procedure Change Request for 2-SI-SXV-003-219.S
06/10/2017
Corrective Action
Documents
CR 1311223
QA ID: The Chemical Hygiene Plan was not reviewed
during 2016 (SSA1707)
06/26/2017
Corrective Action
Documents
CR 1311501
QA ID: SSA1707: Inconsistent performance of
surveillance procedure requirements
06/27/2017
Corrective Action
Documents
CR 1313355
Inadequate chain size used for temporary equipment
seismic restraint
07/03/2017
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
Corrective Action
Documents
CR 1321168
Corrective Action for CR 1303852 did not resolve
condition identified
07/25/2017
Corrective Action
Documents
CR 1323549
QAID Improper use of N/A (SSA 1708)
08/01/2017
Corrective Action
Documents
CR 1323551
QA Records from ALARA not being transmitted to
08/01/2017
Corrective Action
Documents
CR 1323555
QAID Temporary Shielding forms not properly filled out
(SSA 1708)
08/01/2017
Corrective Action
Documents
CR 1323558
QAID Recommendation on temporary shielding
support (SSA 1708)
08/01/2017
Corrective Action
Documents
CR 1324371
Follow-up on CR 1324282 from SQN RP - RW Audit
08/03/2017
Corrective Action
Documents
CR 1334122
NRC Regulatory Issue Summary (RIS) 2017-04
08/31/2017
Corrective Action
Documents
CR 1336290
Cable Tray Supports out of Tolerance
09/07/2017
Corrective Action
Documents
CR 1341686
Cable Tray Supports out of Tolerance
09/25/2017
Corrective Action
Documents
CR 1343410
SGI records
09/29/2017
Corrective Action
Documents
CR 1364616
OE - Part 21 2017-52-00 Fisher Type 461 Valve Plug
Machining
2/04/2017
Corrective Action
CR 1366082
2/07/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
CR 1366200
Unit 1 Lower Compartment Cooler Motor EQ
Qualification
2/072017
Corrective Action
Documents
CR 1372336
Fatigue Rule Violation
2/28/2017
Corrective Action
Documents
CR 1378392
M-B ERCW Pump stopped due to rising bearing temps
01/18/2018
Corrective Action
Documents
CR 1380592
Equipment relocated during installation of plexi-glass
01/24/2018
Corrective Action
Documents
CR 1381347
NCV 2017008-01, Unjustified Qualified Life for Target
Rock PORVs
01/26/2018
Corrective Action
Documents
CR 1381348
NCV 2017008-02, Inadequate Qualification for Reactor
Lower Compartment Cooler Motors
01/26/2018
Corrective Action
Documents
CR 1391505
Deficiencies identified during mock 95001 inspection
2/28/2018
Corrective Action
Documents
CR 1394115
OE - NRC Information Notice 2018-02
03/08/2018
Corrective Action
Documents
CR 1403173
Boric acid valve leaking badly near BAT pump 1A
04/09/2018
Corrective Action
Documents
CR 1403747
SGI Records
04/09/2018
Corrective Action
Documents
CR 1403761
SGI Records
04/09/2018
Corrective Action
Documents
CR 1403896
Boric acid leak on Unit 2 emergency boration FT
instrument line
04/10/2018
Corrective Action
Documents
CR 1403944
SGI Records
04/10/2018
Corrective Action
Documents
CR 1403950
SGI Records
04/11/2018
Corrective Action
Documents
CR 1404549
1-LT-62-130 VCT Level Indication Failed Low
04/11/2018
Corrective Action
Documents
CR 1404590
LL BOP/NSSS DCS Loss of 62-130A
04/11/2018
Corrective Action
CR 1407364
U1R22 Outage WO Screening - FIN resources
04/20/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
CR 1408522
Issues found during performance of 1-SI-SXP-062-
203.0
04/24/2018
Corrective Action
Documents
CR 1408611
Troubleshoot CCP 1A Pump Vibration After U1R22
Rebuild
04/24/2018
Corrective Action
Documents
CR 1410388
Grout base plate under 1A CCP post U1R22
05/01/2018
Corrective Action
Documents
CR 1413732
Non-cited Violation (NCV) 05000327/328/2018001-01
05/11/2018
Corrective Action
Documents
CR 1413734
Non-cited Violation (NCV) 05000327/328/2018001-02
05/11/2018
Corrective Action
Documents
CR 1414850
NRC Identified Green NCV 390/2018410
05/15/2018
Corrective Action
Documents
CR 1416612
Vibration Point 8H in Alert Range
05/21/2018
Corrective Action
Documents
CR 1433166
Suspect B Train EGTS FS-65-44 Failed
07/22/2018
Corrective Action
Documents
CR 1436225
EGTS Licensee Event Report Required Information
08/02/2018
Corrective Action
Documents
CR 1443992
OE - Review NRC IN 18-09 Electrical Arc Flash
08/30/2018
Corrective Action
Documents
CR 1444099
Found leads lifted for an alarm on 1B diesel
08/31/2018
Corrective Action
Documents
CR 1447183
OE - IN-18-10, Thermal Sleeve Flange Wear Leads to
Stuck Control Rod
09/13/2018
Corrective Action
Documents
CR 1449176
OE - NRC Regulatory Issue Summary 2018-04
09/20/2018
Corrective Action
Documents
CR 1463962
Inability to timely retrieve design records
11/07/2018
Corrective Action
Documents
CR 1471007
EQ Binder SQN-SOL-002 baseline evaluation
11/29/2018
Corrective Action
Documents
CR 1476565
Minor Void Found in Emergency Boration Line Above
1-FT-62-137
2/18/2018
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
Corrective Action
Documents
CR 1482178
SQN Site Records List does not agree with NPG-SPP-
2.300 records (QA audit SSA1901)
01/14/2019
Corrective Action
Documents
CR 1482468
QA ID: Department OE Coordinators have not
completed the required JFG (SSA1901)
01/15/2019
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
Corrective Action
Documents
CR 1483225
Revision recommendation for NPG-SPP-22.300
01/17/2019
Corrective Action
Documents
CR 1483228
Revision recommendation for NPG-SPP-22.500
01/17/2019
Corrective Action
Documents
CR 1483291
Re-evaluate NPG-SPP-22.500 as quality related
01/17/2019
Corrective Action
Documents
CR 1485069
2019 WBN PI&R Inspection - Issues with CR 1414850
01/24/2019
Corrective Action
Documents
CR 1488033
Non-cited Violation (NCV) 2018004-02
2/04/2019
Corrective Action
Documents
CR 1489420
Revise security procedure
2/08/2019
Corrective Action
Documents
CR 1490857
Rx Power Does not Respond Correctly to Manual
Make-ups Calculated to Maintain Power Stable
2/14/2019
Corrective Action
Documents
CR 1490951
Evaluation of trend intrusion issues in manholes across
2/14/2019
Corrective Action
Documents
CR 1491065
Establish and sustain a culture of excellence in PU&A
in Chemistry
2/14/2019
Corrective Action
Documents
CR 1494149
OE - WBN Integrated Inspection Report Nov 2018
Findings
2/27/2019
Corrective Action
Documents
CR 1498586
DCN 21287 contained an incorrect calculation for main
steam line radiation release rate
03/13/2019
Corrective Action
Documents
CR 1500107
SQN-PI-FSA-19-002, PI&R Self Assessment
03/18/2019
Corrective Action
Documents
CR 1500629
OE - IN-2019-01, Inadequate Evaluation of Temporary
Alterations
03/20/2019
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.
Corrective Action
Documents
CR 1503045
2017 SQN EQ DBA Inspection: ASCO valves potential
performance deficiencies, SLD
03/28/2019
Corrective Action
Documents
CR 1503045
2017 SQN EQ DBA Inspection - ASCO valves potential
performance deficiencies
03/28/2019
Corrective Action
Documents
CR 1506308
Non-cited Violation (NCV) 2018412-01
04/09/2019
Corrective Action
Documents
CR 1506325
Replace U1 LCC Fan Motors during U1R24
04/09/2019
Corrective Action
Documents
CR 1506831
Review Unusual Event at Brunswick Unit 1 which
required a shutdown
04/10/2019
Corrective Action
Documents
CR 1509174
Respond to NRC RIS 2019-02, Preparation and
Scheduling of Operator Licensing Examinations
04/18/2019
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
Corrective Action
Documents
CR 1510464
CR 1485069 did not document department manager
approval
04/23/2019
Corrective Action
Documents
CR 1510873
SQN-PI-FSA-19-002 - Objective 7 - Deficiencies noted
in CRs 1403944, 1441458, and 1403761
04/24/2019
Corrective Action
Documents
CR 1510985
SQN-PI-FSA-!(-002 - Objective 7 PD - A Review of
NCV 2017008-01
04/24/2019
Corrective Action
Documents
CR 1511003
SQN-PI-FSA-19-002 - Objective 7 PD - A Review of
NCV 2017008-02
04/24/2019
Corrective Action
Documents
CR 1511249
SQN-PI-FSA-19-002 Objective 7 PD (1500107-033)
LER-2018-001-00
04/25/2019
Corrective Action
Documents
CR 1512747
Non-cited Violation (NCV) 05000327/328/2019010-01
05/01/2019
Corrective Action
Documents
CR 1514352
QA elevation on protected equipment
05/06/2019
Corrective Action
Documents
CR 1516824
NCV 2019-02, Failure to account for heat rise in
Foxboro/Weed instruments
05/15/2019
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
Corrective Action
Documents
CR 1525798
OE - Issues with OE Reviews in Accordance with
NPG-SPP-22.600
06/18/2019
Corrective Action
Documents
CR 655554
Loop 4 TDAFW LCV failed stroke time
2/12/2012
Corrective Action
Documents
CR 660015
OE review of WBN-NOER-12-079
2/21/2012
Corrective Action
Documents
CR 663698
Review of WBN-NOER-12-106 AFW valve stroke time
01/04/2013
Corrective Action
Documents
CR 740635
SGTR accident analysis issue related to maintenance
06/14/2013
Corrective Action
Documents
CR 750649
SQN review of Byron U2 scram from loss of main
generator stator cooling
07/09/2013
Corrective Action
Documents
CR 751276
SQN review of Vogtle U2 manual reactor scram due to
high RCP seal leak off
07/10/2013
Corrective Action
Documents
CR 791573
SQN review of Davis-Besse scram from RCP motor
faulty electrical connections
10/10/2013
Corrective Action
Documents
CR 915358
Unit 2 main turbine high vibration
07/30/2014
Corrective Action
Documents
CR 959976
Aging management review for ground water in
distribution board
11/24/2014
Corrective Action
Documents
CR 965728
Procedure swap performed with step marked N/A that
resulted in configuration control issue
2/10/2014
Corrective Action
Documents
CR 973446
2B MDAFW system check valve backleakage
01/05/2015
Corrective Action
Documents
CR 981733
Low oil on 2A MDAFWP inboard pump bearing
01/27/2015
Corrective Action
Documents
Resulting from
Inspection
CR 1522084
Broken UNID tag
06/04/2019
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
Corrective Action
Documents
Resulting from
Inspection
CR 1525710
Individual missed 2018 SCWE Training - CO issue
06/18/2019
Corrective Action
Documents
Resulting from
Inspection
CR 1525830
NRC ID - ERB package documentation error - CO
issue
06/18/2019
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
Corrective Action
Documents
Resulting from
Inspection
CR 1525869
NOER-SQN-17-003 has incorrect event date
06/18/2019
Corrective Action
Documents
Resulting from
Inspection
CR 1526184
Extension request reason insufficient
06/19/2019
Corrective Action
Documents
Resulting from
Inspection
CR 1526337
Incorrect Maximo attachments
06/20/2019
Corrective Action
Documents
Resulting from
Inspection
CR 1526428
Inadequate response to CRs
06/20/2019
Engineering
Changes
DCN 23813
Replace Steam Generator Blowdown Containment
Isolation Sample Valves
Revision 1
Miscellaneous
U2 Function 043-E (a)(1) plan
Revision 2
Miscellaneous
Quality Assurance Master Audit Schedule 2019-2020
08/29/2017
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
Miscellaneous
Sequoyah Nuclear Plant - Closeout of Generic Letter 2008-01
04/22/2011
Miscellaneous
Operations Standing Order List
06/05/2019
Miscellaneous
Chemical and Volume Control System (CVCS) Health
Report Scorecard
1st Quarter
2019
Miscellaneous
SQN Maintenance Rule List - SSCs in (a)(1) Status
since June 2017
Miscellaneous
Unit 1 MCR Deficiencies List
06/05/2019
Miscellaneous
Unit 2 MCR Deficiencies List
06/05/2019
Miscellaneous
System #333 Health Report Screenshot
Miscellaneous
CDE 2855
2-FSV-43-61 PAM indication inoperable for 30 days
08/28/2015
Miscellaneous
CDE 2884
2-FSV-43-61 no light indication in main control room
01/04/2016
Miscellaneous
CDE 2886
2-FSV-43-55 Failed 2-SI-SXV-043-204.0
2/09/2015
Miscellaneous
CDE 2903
2-FSV-43-61 PAM instrument had dual light position
indications
05/10/2016
Miscellaneous
Management Review Committee Package
06/06/2019
Miscellaneous
Plant Screening Committee Package
06/05/2019
Miscellaneous
QA-SQ-18-006
Sequoyah Nuclear Plant - Quality Assurance Site
Report
03/14/2018
Miscellaneous
QA-SQ-19-002
Sequoyah Nuclear Plant - Quality Assurance Site
Report
2/07/2019
Miscellaneous
QA-SQ-19-004
Sequoyah Nuclear Plant - Quality Assurance Site
Report
03/11/2019
Miscellaneous
QA-SQ-19-006
Sequoyah Nuclear Plant - Quality Assurance Site
Report
04/08/2019
Miscellaneous
QA-SQ-19-008
Sequoyah Nuclear Plant - Quality Assurance Site
Report
05/09/2019
Miscellaneous
SQN-DC-V-13.9.8
Sequoyah Nuclear Plant - Auxiliary Feedwater System,
Design Criteria Document
Revision 29
Miscellaneous
SQN-DC-V-27.2
Sequoyah Nuclear Plant - Chemical and Volume
Control System, Design Criteria
Revision 35
Miscellaneous
License Renewal Program
Revision 26
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
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
Procedures
1-SI-OPS-062-040.A
Centrifugal Charging Pump 1A-A Casing, Suction, and
Discharge Piping Venting
Revision 42
Procedures
NPG-SPP-03.4
Maintenance Rule Performance Indicator Monitoring,
Trending and Reporting - 10CFR50.65
Revision 3
Procedures
NPG-SPP-07.1.4
Work Management Prioritization - Online
Revision 9
Procedures
NPG-SPP-07.6
NPG Work Management Planning Procedure
Revision 15
Procedures
NPG-SPP-07.6
NPG Work Management Planning Procedure
Revision 16
Procedures
NPG-SPP-22.300
Corrective Action Program
Revision 14
Procedures
NPG-SPP-22.300
Corrective Action Program
Revision 15
Procedures
NPG-SPP-22.300
Corrective Action Program
Revision 12
Procedures
NPG-SPP-22.300
Corrective Action Program
Revision 10
Procedures
NPG-SPP-22.500
Operating Experience Program
Revision 7
Procedures
NPG-SPP-22.600
Issue Resolution
Revision 5
Procedures
OPDP-1
Conduct of Operations
Revision 43
Procedures
OPDP-11
Operational Decision-Making Issue Evaluation Process
Revision 6
Procedures
OPDP-4
Annunciator Disablement
Revision 7
Self-
Assessments
SSA1701
Site Audit Report, Corrective Action Program,
Sequoyah Nuclear Plant (SQN), January 23-27, 2017
2/22/2017
Self-
Assessments
SSA1707
Site Audit Report, Chemistry, Effluent, and
Environmental Monitoring, Sequoyah Nuclear Plant
(SQN), June 19-30, 2017
07/17/2017
Self-
Assessments
SSA1708
Site Audit Report, Radiation Protection, Radwaste,
Sequoyah Nuclear Plant (SQN), July 24-August 2,
2017
08/10/2017
Self-
Assessments
SSA1804
Site Audit Report, Maintenance, Sequoyah Nuclear
Station (SQN), March 26-April 6, 2018
04/20/2018
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
Work Orders
113086647
Replace Unit 2 PORVs
Work Orders
113574449
Replace current control unit for 2-FSV-043-0055-B
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
115152446
Replace Unit 2 PORVs
Work Orders
117485917
Steam Generator Blowdown #3 Isolation Valve has no
Light Indication in MCR
Work Orders
117715470
Calibrate TDAFWP inlet pressure indicator
Work Orders
117733991
Perform additional groundwater in-leakage repairs in
various yard areas
Work Orders
117910082
Inspect and clean 250 VDC battery board #2
Work Orders
118800008
Replace EGTS Train B electronic circuit board
Work Orders
118878733
DCN 23638 Stage 8 outage cable terminations and
modifications
Work Orders
118888040
Inadequate chain size used for temporary equipment
seismic restraint
Work Orders
118946474
Replace 1-RLY-62-108/CPBY-1A due to Part 21 issue
Work Orders
119111157
Perform groundwater in-leakage repairs in various
areas for the Auxiliary Building
Work Orders
119444328
Rewind or replace 1B-B LCC fan motor to resolve
NCV, CR 1381348
Work Orders
119444348
Rewind or replace 1C-A LCC fan motor to resolve
NCV, CR 1381348
Work Orders
119444352
Rewind or replace 1D-B LCC fan motor to resolve
NCV, CR 1381348
Work Orders
119448481
Rewind or replace 1A-A LCC fan motor to resolve
NCV, CR 1381348
Work Orders
119529017
1-LT-62-130 VCT level indication has failed low
Work Orders
119568924
Work Orders
119855356
Implement DCN 22643 Stage 6 to replace U1 PORV
334-B
Work Orders
119855374
Implement DCN 22643 Stage 5 to replace U1 PORV
Work Orders
20398985
Replace U1 1A-A LCC Fan Motors during U1R24
Work Orders
20398986
Replace U1 1D-B LCC Fan Motor during U1R24
Work Orders
20398987
Replace U1 1C-A LCC Fan Motor during U1R24
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
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
- 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