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
uly 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 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 Enclosure
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 Report Aspect Section Not Applicable NCV 05000327,05000328/2019011- Not Applicable 92702
Open/Closed 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 Report Aspect Section Not Severity Level IV Not 92702 Applicable NCV 05000327,05000328/2019011-01 Applicable Open/Closed 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 Type Designation Description or Title Revision or
Procedure Date
71152B Calculations MDQ0000682018000101 Material Aging for PORV Target Rock Solenoid Valves Revision 0
(SQNEQ-SOL-002)
71152B Calculations SCG1S596 Maintenance Rule for Structures and License Renewal Revision 13
Structures Monitoring Program Inspections
71152B Corrective Action CR 1002259 OE - Foreign Material Damages Steam Generator 03/20/2015
Documents Tube Sheet
71152B Corrective Action CR 1002268 OE - Performance Shortfalls During Mechanical 03/20/2015
Documents Maintenance Activities
71152B Corrective Action CR 1002270 NOER - Loss of Breaker Configuration Control PER 03/20/2015
Documents 965728
71152B Corrective Action CR 1002275 NOER - Missed Surveillance on New Components 03/20/2015
Documents
71152B Corrective Action CR 1002293 OE - Loss of Jet Pump Plug Seals in Reactor Vessel 03/20/2015
Documents
71152B Corrective Action CR 1003153 OE - BFN Loss of Inventory from Reactor Cavity 03/23/2015
Documents
71152B Corrective Action CR 1017143 Found Cracks in the Cover on Vital Battery #2 04/22/2015
Documents
71152B Corrective Action CR 1023172 NOER - Reactor Trip due to Loss of Main Condenser 05/07/2015
Documents Vacuum
71152B Corrective Action CR 1023175 NOER - PER Classification and Level of Significance 05/07/2015
Documents
71152B Corrective Action CR 1023207 OE - Ice Bed Increasing Temperature Trends 05/07/2015
Documents
71152B Corrective Action CR 1025764 Oil Bubbler is at 20% Recommend Minor Maintenance 05/14/2015
Documents to Fill Reservoir
71152B Corrective Action CR 1064736 Evaluate DCN 23085 - Kirk Key Interlocks 07/30/2015
Documents
71152B Corrective Action CR 1084294 NRC NCV 2015-007-02 - 50.59/Modifications 09/21/2015
Documents Inspection
71152B Corrective Action CR 1104335 CRDM Cable Connection Issues Found During 11/15/2015
Documents Disconnection
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action CR 1106765 1-LCV-3-148 not Able to be Operated in Manual 11/20/2015
Documents
71152B Corrective Action CR 1116558 2-FSV-43-55 Failed 2-SI-SXV-000-204.0 Valve Stroke 12/16/2015
Documents
71152B Corrective Action CR 1121723 2-FSV-43-61 Has no Light Indication While Valve is 01/05/2016
Documents Closed
71152B Corrective Action CR 115765 Potential Transformer (PT) in Compartment #3 12/01/2006
Documents
71152B Corrective Action CR 1169090 Post Accident Monitoring (2-XX-55-6L) for Valve 2- 05/09/2016
Documents FCV-43-61 Indicates Intermediate Position
71152B Corrective Action CR 1181710 NRC CDBI DG Bldg Ventilation System and Tornado 06/14/2016
Documents Impact
71152B Corrective Action CR 1187308 Operations Request POE - Instrument Calibration 06/30/2016
Documents Issues
71152B Corrective Action CR 1227157 Potential Error Trap with Breaker UNIDs 10/26/2016
Documents
71152B Corrective Action CR 1240813 0-MI-MRR-003-461.0 Needs to be Revised - TDAFW 12/10/2016
Documents Mech Overspeed Trip Linkage Spring Setting is
Incorrect
71152B Corrective Action CR 1254470 CRs Closed to WOs Without Correct Coding in WO 01/25/2017
Documents
71152B Corrective Action CR 1254937 NOER was not Generated for CR 1241933 01/26/2017
Documents
71152B Corrective Action CR 1255171 Gaps in Extent of Condition Review of QA Finding 01/26/2017
Documents RCA 1155352
71152B Corrective Action CR 1255177 Trend in Site CAP Procedure Adherence to NPG-SPP- 01/26/2017
Documents 22.300
71152B Corrective Action CR 1269767 A212 ABSCE Breach Resulting in Both Trains of 03/07/2017
Documents ABGTS Inoperable for Both Units
71152B Corrective Action CR 1290969 Snapshot Assessment - PD - SQN-PI-SSA-17-007 - 05/02/2017
Documents OE Coordinators
71152B Corrective Action CR 1301718 Unit 1 TDAFW Suction Pressure Gauge Found 05/30/2017
Documents Isolated
71152B Corrective Action CR 1303852 RP REP VANS 06/05/2017
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents
71152B Corrective Action CR 1305710 Procedure Change Request for 2-SI-SXV-003-219.S 06/10/2017
Documents
71152B Corrective Action CR 1311223 QA ID: The Chemical Hygiene Plan was not reviewed 06/26/2017
Documents during 2016 (SSA1707)
71152B Corrective Action CR 1311501 QA ID: SSA1707: Inconsistent performance of 06/27/2017
Documents surveillance procedure requirements
71152B Corrective Action CR 1313355 Inadequate chain size used for temporary equipment 07/03/2017
Documents seismic restraint
71152B Corrective Action CR 1313866 OE-Green-WBN-NOER-17-014-Unplanned LCO 3.7.5 07/05/2017
Documents entry due to time delay relay failure
71152B Corrective Action CR 1321168 Corrective Action for CR 1303852 did not resolve 07/25/2017
Documents condition identified
71152B Corrective Action CR 1323549 QAID Improper use of N/A (SSA 1708) 08/01/2017
Documents
71152B Corrective Action CR 1323551 QA Records from ALARA not being transmitted to 08/01/2017
Documents EDMS
71152B Corrective Action CR 1323555 QAID Temporary Shielding forms not properly filled out 08/01/2017
Documents (SSA 1708)
71152B Corrective Action CR 1323558 QAID Recommendation on temporary shielding 08/01/2017
Documents support (SSA 1708)
71152B Corrective Action CR 1324371 Follow-up on CR 1324282 from SQN RP - RW Audit 08/03/2017
Documents
71152B Corrective Action CR 1334122 NRC Regulatory Issue Summary (RIS) 2017-04 08/31/2017
Documents
71152B Corrective Action CR 1336290 Cable Tray Supports out of Tolerance 09/07/2017
Documents
71152B Corrective Action CR 1341686 Cable Tray Supports out of Tolerance 09/25/2017
Documents
71152B Corrective Action CR 1343410 SGI records 09/29/2017
Documents
71152B Corrective Action CR 1364616 OE - Part 21 2017-52-00 Fisher Type 461 Valve Plug 12/04/2017
Documents Machining
71152B Corrective Action CR 1366082 SQN DBA EQ 201700X 12/07/2017
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents
71152B Corrective Action CR 1366200 Unit 1 Lower Compartment Cooler Motor EQ 12/072017
Documents Qualification
71152B Corrective Action CR 1372336 Fatigue Rule Violation 12/28/2017
Documents
71152B Corrective Action CR 1378392 M-B ERCW Pump stopped due to rising bearing temps 01/18/2018
Documents
71152B Corrective Action CR 1380592 Equipment relocated during installation of plexi-glass 01/24/2018
Documents
71152B Corrective Action CR 1381347 NCV 2017008-01, Unjustified Qualified Life for Target 01/26/2018
Documents Rock PORVs
71152B Corrective Action CR 1381348 NCV 2017008-02, Inadequate Qualification for Reactor 01/26/2018
Documents Lower Compartment Cooler Motors
71152B Corrective Action CR 1391505 Deficiencies identified during mock 95001 inspection 02/28/2018
Documents
71152B Corrective Action CR 1394115 OE - NRC Information Notice 2018-02 03/08/2018
Documents
71152B Corrective Action CR 1403173 Boric acid valve leaking badly near BAT pump 1A 04/09/2018
Documents
71152B Corrective Action CR 1403747 SGI Records 04/09/2018
Documents
71152B Corrective Action CR 1403761 SGI Records 04/09/2018
Documents
71152B Corrective Action CR 1403896 Boric acid leak on Unit 2 emergency boration FT 04/10/2018
Documents instrument line
71152B Corrective Action CR 1403944 SGI Records 04/10/2018
Documents
71152B Corrective Action CR 1403950 SGI Records 04/11/2018
Documents
71152B Corrective Action CR 1404549 1-LT-62-130 VCT Level Indication Failed Low 04/11/2018
Documents
71152B Corrective Action CR 1404590 LL BOP/NSSS DCS Loss of 62-130A 04/11/2018
Documents
71152B Corrective Action CR 1407364 U1R22 Outage WO Screening - FIN resources 04/20/2018
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents
71152B Corrective Action CR 1408522 Issues found during performance of 1-SI-SXP-062- 04/24/2018
Documents 203.0
71152B Corrective Action CR 1408611 Troubleshoot CCP 1A Pump Vibration After U1R22 04/24/2018
Documents Rebuild
71152B Corrective Action CR 1410388 Grout base plate under 1A CCP post U1R22 05/01/2018
Documents
71152B Corrective Action CR 1413732 Non-cited Violation (NCV) 05000327/328/2018001-01 05/11/2018
Documents
71152B Corrective Action CR 1413734 Non-cited Violation (NCV) 05000327/328/2018001-02 05/11/2018
Documents
71152B Corrective Action CR 1414850 NRC Identified Green NCV 390/2018410 05/15/2018
Documents
71152B Corrective Action CR 1416612 Vibration Point 8H in Alert Range 05/21/2018
Documents
71152B Corrective Action CR 1433166 Suspect B Train EGTS FS-65-44 Failed 07/22/2018
Documents
71152B Corrective Action CR 1436225 EGTS Licensee Event Report Required Information 08/02/2018
Documents
71152B Corrective Action CR 1443992 OE - Review NRC IN 18-09 Electrical Arc Flash 08/30/2018
Documents
71152B Corrective Action CR 1444099 Found leads lifted for an alarm on 1B diesel 08/31/2018
Documents
71152B Corrective Action CR 1447183 OE - IN-18-10, Thermal Sleeve Flange Wear Leads to 09/13/2018
Documents Stuck Control Rod
71152B Corrective Action CR 1449176 OE - NRC Regulatory Issue Summary 2018-04 09/20/2018
Documents
71152B Corrective Action CR 1463962 Inability to timely retrieve design records 11/07/2018
Documents
71152B Corrective Action CR 1471007 EQ Binder SQN-SOL-002 baseline evaluation 11/29/2018
Documents
71152B Corrective Action CR 1476565 Minor Void Found in Emergency Boration Line Above 12/18/2018
Documents 1-FT-62-137
71152B Corrective Action CR 1477034 Gas void observed during performance of 1-SI-OPS- 12/19/2018
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents 062-040.A U1 CCP piping vent
71152B Corrective Action CR 1482178 SQN Site Records List does not agree with NPG-SPP- 01/14/2019
Documents 22.300 records (QA audit SSA1901)
71152B Corrective Action CR 1482468 QA ID: Department OE Coordinators have not 01/15/2019
Documents completed the required JFG (SSA1901)
71152B Corrective Action CR 1482669 Biennial fleet wide self assessment of the OE program 01/15/2019
Documents not performed as required by NPG-SPP-22.500
71152B Corrective Action CR 1483225 Revision recommendation for NPG-SPP-22.300 01/17/2019
Documents
71152B Corrective Action CR 1483228 Revision recommendation for NPG-SPP-22.500 01/17/2019
Documents
71152B Corrective Action CR 1483291 Re-evaluate NPG-SPP-22.500 as quality related 01/17/2019
Documents
71152B Corrective Action CR 1485069 2019 WBN PI&R Inspection - Issues with CR 1414850 01/24/2019
Documents
71152B Corrective Action CR 1488033 Non-cited Violation (NCV) 2018004-02 02/04/2019
Documents
71152B Corrective Action CR 1489420 Revise security procedure 02/08/2019
Documents
71152B Corrective Action CR 1490857 Rx Power Does not Respond Correctly to Manual 02/14/2019
Documents Make-ups Calculated to Maintain Power Stable
71152B Corrective Action CR 1490951 Evaluation of trend intrusion issues in manholes across 02/14/2019
Documents SQN
71152B Corrective Action CR 1491065 Establish and sustain a culture of excellence in PU&A 02/14/2019
Documents in Chemistry
71152B Corrective Action CR 1494149 OE - WBN Integrated Inspection Report Nov 2018 02/27/2019
Documents Findings
71152B Corrective Action CR 1498586 DCN 21287 contained an incorrect calculation for main 03/13/2019
Documents steam line radiation release rate
71152B Corrective Action CR 1500107 SQN-PI-FSA-19-002, PI&R Self Assessment 03/18/2019
Documents
71152B Corrective Action CR 1500629 OE - IN-2019-01, Inadequate Evaluation of Temporary 03/20/2019
Documents Alterations
71152B Corrective Action CR 1503036 2017 SQN EQ DBA Inspection: Foxboro/Weed 03/28/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents Transmitter heat rise issue, SLD.
71152B Corrective Action CR 1503045 2017 SQN EQ DBA Inspection: ASCO valves potential 03/28/2019
Documents performance deficiencies, SLD
71152B Corrective Action CR 1503045 2017 SQN EQ DBA Inspection - ASCO valves potential 03/28/2019
Documents performance deficiencies
71152B Corrective Action CR 1506308 Non-cited Violation (NCV) 2018412-01 04/09/2019
Documents
71152B Corrective Action CR 1506325 Replace U1 LCC Fan Motors during U1R24 04/09/2019
Documents
71152B Corrective Action CR 1506831 Review Unusual Event at Brunswick Unit 1 which 04/10/2019
Documents required a shutdown
71152B Corrective Action CR 1509174 Respond to NRC RIS 2019-02, Preparation and 04/18/2019
Documents Scheduling of Operator Licensing Examinations
71152B Corrective Action CR 1510339 SQN-PI-FSA-10-002 - Objective 7 - Appendix R 04/23/2019
Documents Triennial Inspection CR 1276596 has not been
resolved timely
71152B Corrective Action CR 1510464 CR 1485069 did not document department manager 04/23/2019
Documents approval
71152B Corrective Action CR 1510873 SQN-PI-FSA-19-002 - Objective 7 - Deficiencies noted 04/24/2019
Documents in CRs 1403944, 1441458, and 1403761
71152B Corrective Action CR 1510985 SQN-PI-FSA-!(-002 - Objective 7 PD - A Review of 04/24/2019
Documents NCV 2017008-01
71152B Corrective Action CR 1511003 SQN-PI-FSA-19-002 - Objective 7 PD - A Review of 04/24/2019
Documents NCV 2017008-02
71152B Corrective Action CR 1511249 SQN-PI-FSA-19-002 Objective 7 PD (1500107-033) 04/25/2019
Documents LER-2018-001-00
71152B Corrective Action CR 1512747 Non-cited Violation (NCV) 05000327/328/2019010-01 05/01/2019
Documents
71152B Corrective Action CR 1514352 QA elevation on protected equipment 05/06/2019
Documents
71152B Corrective Action CR 1516824 NCV 2019-02, Failure to account for heat rise in 05/15/2019
Documents Foxboro/Weed instruments
71152B Corrective Action CR 1519228 Gas/water Flow Noted During Cold Leg Injection Piping 05/23/2019
Documents Vent
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action CR 1525798 OE - Issues with OE Reviews in Accordance with 06/18/2019
Documents NPG-SPP-22.600
71152B Corrective Action CR 655554 Loop 4 TDAFW LCV failed stroke time 12/12/2012
Documents
71152B Corrective Action CR 660015 OE review of WBN-NOER-12-079 12/21/2012
Documents
71152B Corrective Action CR 663698 Review of WBN-NOER-12-106 AFW valve stroke time 01/04/2013
Documents
71152B Corrective Action CR 740635 SGTR accident analysis issue related to maintenance 06/14/2013
Documents
71152B Corrective Action CR 750649 SQN review of Byron U2 scram from loss of main 07/09/2013
Documents generator stator cooling
71152B Corrective Action CR 751276 SQN review of Vogtle U2 manual reactor scram due to 07/10/2013
Documents high RCP seal leak off
71152B Corrective Action CR 791573 SQN review of Davis-Besse scram from RCP motor 10/10/2013
Documents faulty electrical connections
71152B Corrective Action CR 915358 Unit 2 main turbine high vibration 07/30/2014
Documents
71152B Corrective Action CR 959976 Aging management review for ground water in 11/24/2014
Documents distribution board
71152B Corrective Action CR 965728 Procedure swap performed with step marked N/A that 12/10/2014
Documents resulted in configuration control issue
71152B Corrective Action CR 973446 2B MDAFW system check valve backleakage 01/05/2015
Documents
71152B Corrective Action CR 981733 Low oil on 2A MDAFWP inboard pump bearing 01/27/2015
Documents
71152B Corrective Action CR 1522084 Broken UNID tag 06/04/2019
Documents
Resulting from
Inspection
71152B Corrective Action CR 1522525 Procedure NPG-SPP-22.300 change request 06/05/2019
Documents
Resulting from
Inspection
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action CR 1525710 Individual missed 2018 SCWE Training - CO issue 06/18/2019
Documents
Resulting from
Inspection
71152B Corrective Action CR 1525830 NRC ID - ERB package documentation error - CO 06/18/2019
Documents issue
Resulting from
Inspection
71152B Corrective Action CR 1525832 NPG-SPP-03.9 wording of Significant Gap Analysis not 06/18/2019
Documents matching NPG-SPP-22.300
Resulting from
Inspection
71152B Corrective Action CR 1525869 NOER-SQN-17-003 has incorrect event date 06/18/2019
Documents
Resulting from
Inspection
71152B Corrective Action CR 1526184 Extension request reason insufficient 06/19/2019
Documents
Resulting from
Inspection
71152B Corrective Action CR 1526337 Incorrect Maximo attachments 06/20/2019
Documents
Resulting from
Inspection
71152B Corrective Action CR 1526428 Inadequate response to CRs 06/20/2019
Documents
Resulting from
Inspection
71152B Engineering DCN 23813 Replace Steam Generator Blowdown Containment Revision 1
Changes Isolation Sample Valves
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, 05/09/2008
and Watts Bar Nuclear Plant Initial Response to NRC
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Miscellaneous Sequoyah Nuclear Plant - Closeout of Generic Letter 04/22/2011
2008-01
71152B Miscellaneous Operations Standing Order List 06/05/2019
71152B Miscellaneous Chemical and Volume Control System (CVCS) Health 1st Quarter
Report Scorecard 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 12/09/2015
71152B Miscellaneous CDE 2903 2-FSV-43-61 PAM instrument had dual light position 05/10/2016
indications
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 03/14/2018
Report
71152B Miscellaneous QA-SQ-19-002 Sequoyah Nuclear Plant - Quality Assurance Site 02/07/2019
Report
71152B Miscellaneous QA-SQ-19-004 Sequoyah Nuclear Plant - Quality Assurance Site 03/11/2019
Report
71152B Miscellaneous QA-SQ-19-006 Sequoyah Nuclear Plant - Quality Assurance Site 04/08/2019
Report
71152B Miscellaneous QA-SQ-19-008 Sequoyah Nuclear Plant - Quality Assurance Site 05/09/2019
Report
71152B Miscellaneous SQN-DC-V-13.9.8 Sequoyah Nuclear Plant - Auxiliary Feedwater System, Revision 29
Design Criteria Document
71152B Miscellaneous SQN-DC-V-27.2 Sequoyah Nuclear Plant - Chemical and Volume Revision 35
Control System, Design Criteria
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 Type Designation Description or Title Revision or
Procedure Date
Auxiliary Feedwater Pump Turbine
71152B Procedures 1-SI-IFT-068-067.4 Functional Test of Delta T/TAVG Channel IV Rack 13 Revision 28
Loop 1-T-68-67 (T-441/442)
71152B Procedures 1-SI-OPS-062-040.A Centrifugal Charging Pump 1A-A Casing, Suction, and Revision 42
Discharge Piping Venting
71152B Procedures NPG-SPP-03.4 Maintenance Rule Performance Indicator Monitoring, Revision 3
Trending and Reporting - 10CFR50.65
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- SSA1701 Site Audit Report, Corrective Action Program, 02/22/2017
Assessments Sequoyah Nuclear Plant (SQN), January 23-27, 2017
71152B Self- SSA1707 Site Audit Report, Chemistry, Effluent, and 07/17/2017
Assessments Environmental Monitoring, Sequoyah Nuclear Plant
(SQN), June 19-30, 2017
71152B Self- SSA1708 Site Audit Report, Radiation Protection, Radwaste, 08/10/2017
Assessments Sequoyah Nuclear Plant (SQN), July 24-August 2,
2017
71152B Self- SSA1804 Site Audit Report, Maintenance, Sequoyah Nuclear 04/20/2018
Assessments Station (SQN), March 26-April 6, 2018
71152B Self- SSA1901 Corrective Action, Chattanooga Office Complex (COC), 01/30/2019
Assessments Browns Ferry (BFN), Sequoyah (SQN) and Watts Bar
(WBN) Nuclear Plants, January 14-18, 2019
71152B Work Orders 113086647 Replace Unit 2 PORVs
71152B Work Orders 113574449 Replace current control unit for 2-FSV-043-0055-B
Inspection Type Designation Description or Title Revision or
Procedure 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
71152B Work Orders 120398985 Replace U1 1A-A LCC Fan Motors during U1R24
71152B Work Orders 120398986 Replace U1 1D-B LCC Fan Motor during U1R24
71152B Work Orders 120398987 Replace U1 1C-A LCC Fan Motor during U1R24
71152B Work Orders 120398988 Replace U1 1B-B LCC Fan Motor during U1R24
2702 Corrective Action 1322419 Action Implementation Tracking for Confirmatory Order
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents EA-17-022
2702 Corrective Action 1404011 Sequoyahs response to the Oak Ridge Associated
CONF Documents Universities nuclear safety culture assessment report
2702 Corrective Action 1416534 Track Corporate's response to NSC assessment.
CONF Documents
2702 Corrective Action 1448122 OE.01.NUC.01-Sustain TVA Nuclear Work
CONF Documents Environment
2702 Corrective Action 1451197-003 SCWE Mitigation Plan follow up actions for corporate
CONF Documents ERB case numbers CORP-2019-010, 011, 012, 013
and 014
2702 Corrective Action 1477964 LMS Curriculum NPG-TVA-400152, SCWE EA 17-022
CONF Documents incorrect due dates
2702 Corrective Action 1478023 LMS Curriculum NPG-TVA-400152, SCWE EA 17-022
CONF Documents is calculating incorrect due date
2702 Corrective Action 1484364 Action Tracking for SQN SCWE Refresher Training
CONF Documents
2702 Corrective Action 1492600 Safety Culture
CONF Documents
2702 Corrective Action 1497144 EA-17-022,Section V.1.b.3 90-day SCWE training
CONF Documents requirement not met
2702 Corrective Action 1525830 Discrepancy in ERB 2018-031 TVA Forms 41647 (item
CONF Documents # 3) and 41651 (item # 1)
Resulting from
Inspection
2702 Corrective Action 1526768 ECP Benchmarking not documented per NPG-SPP-
CONF Documents 22.102
Resulting from
Inspection
2702 Miscellaneous Sequoyah Nuclear Plant Nuclear Safety Culture April 2018
CONF Evaluation, prepared by Oak Ridge Associated
Universities
2702 Procedures Conduct of Operations Employee Concerns Revision 7
CONF
2702 Procedures 1193005 Business Plan Initiative OE.01.Nuc.01 (Improve TVA
Inspection Type Designation Description or Title Revision or
Procedure Date
CONF Nuclear Work Environment)
2702 Procedures ECP-1 Employee Concerns Staff Desktop Instruction 1 ECP Revision 0
CONF Administration
2702 Procedures NPG-SPP-01.7 Nuclear Safety Culture Revision 5
CONF
2702 Procedures NPG-SPP-01.7.1 Employee Concerns Program Revision 3
CONF
2702 Procedures NPG-SPP-01.7.2 Nuclear Safety Culture Monitoring Revision 13
CONF
2702 Procedures NPG-SPP-01.7.3 Conduct of Nuclear Safety Culture Assessments and Revision 4
CONF Organizational Effectiveness Surveys
2702 Procedures NPG-SPP-01.7.4 Adverse Employment Action and Executive Review Revision 1
CONF Board
2702 Procedures NPG-SPP-01.7.4 Adverse Employment Action and Executive Review Revision 3
CONF Board
2702 Procedures TVA-SPP-22.100 Change Management Revision 0
CONF
23