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Category:Letter type:CNL
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) CNL-23-005, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2023-12-26026 December 2023 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-043, – Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 – Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report 2024-09-24
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML21027A3942020-12-0707 December 2020 TVA Response to Notice of Violations (EA-19-092) ML20198M4202020-07-0808 July 2020 William Bill Sprinkle, Response to Apparent Violation, IA-20-018 L-19-048, Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-0422019-09-12012 September 2019 Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-042 ML16344A0482016-12-0909 December 2016 Reply to Notice of Violation (EA-16-117) CNL-15-217, Reply to Notice of Violation (EA-15-112)2015-10-16016 October 2015 Reply to Notice of Violation (EA-15-112) CNL-15-152, Reply to Notice of Violation (EA-15-075)2015-07-24024 July 2015 Reply to Notice of Violation (EA-15-075) CNL-15-079, Reply to Notice of Violation (EA-14-179)2015-05-0101 May 2015 Reply to Notice of Violation (EA-14-179) ML13204A3832013-07-18018 July 2013 Reply to Notice of Violation (EA-13-019) 391/2013611-01, -02, and -03 Related to Tva'S Commercial Grade Dedication Program ML13192A0332013-07-0303 July 2013 Reply to a Notice of Violation; EA-13-018 IR 05000391/20106032012-07-17017 July 2012 Units 1 & 2 - Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML12202A0102012-07-17017 July 2012 Units 1 & 2 - Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML12172A4122012-06-18018 June 2012 Tennessee Valley Authority - Reply to Notice of Violation 05000391-10-603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML12160A3522012-06-0707 June 2012 Reply to Notice of Violation 391/2012612-01 - Failure to Correct a Condition Adverse to Quality Associated with Containment Spray Pump Layup and Preventive Maintenance ML11164A1412011-06-0909 June 2011 Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML11105A1502011-04-11011 April 2011 Request for Extension for Time to Respond to Severity Level IV, Non-Cited Violation 05000390-11-008-01 ML1109605912011-03-31031 March 2011 Response to Non-Cited Violations 05000390-10-005-03, Failure to Use Worst Case 6900 Vac Bus Voltage in Design Calculations ML1033002172010-11-24024 November 2010 Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers ML1028804932010-10-15015 October 2010 Denial of Notice of Violation (NOV) 05000391-2010603-08, Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Additional Information ML1025204352010-09-0707 September 2010 Denial of Notice of Violation, 05000391/2010603-08, Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers ML0908306622009-03-23023 March 2009 Denial of Non-Cited Violation 05000390-08-05-04, Carbon Dioxide System in Fire Area 48 Failed to Meet Design Criterion ML0416002752004-06-0303 June 2004 & Watts Bar Nuclear Plant - Interim Safeguards and Security Compensatory Measures Reports & Notices of Violation - Reply to Notices of Violation ML0322000402003-07-25025 July 2003 National Pollutant Discharge Elimination System Permit No.TN0020158 - Response to Notice of Violation ML0316701792003-06-0404 June 2003 National Pollutant Discharge Elimination System (NPDES) Permit No. TN0020168 - Response to Notice of Violation 2020-07-08
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L44 150501 002 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-079 May 1, 2015 10 CFR 2.201 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2- REPLY TO NOTICE OF VIOLATION (EA-14-179)
Reference:
NRC letter dated April 7, 2015, "Notice of Violation (NRC Inspection Report No. 05000391/2015614, and Investigation Report No. 2-2013-011 , Watts Bar Nuclear Plant)"
Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 2.201 , Tennessee Valley Authority's (TVA) response to Notice of Violation EA-14-179 is enclosed.
As previously presented during the Nuclear Regulatory Commission Region II pre-decisional enforcement conference held on March 6, 2015, TVA accepts the violation and recognizes the importance of the finding . Accordingly, TVA has developed and implemented corrective actions to ensure the identified discrepancies have been corrected and will not recur.
The enclosure provides TVA's reply to the violation , including a detailed description of the corrective steps taken and the results achieved. TVA is in full compliance and will be ready by June 15, 2015 for a traditional enforcement follow-up inspection.
There are no new regulatory commitments made in this letter. Should you have questions regarding this response, please contact Gordon Arent at (423) 365-2004.
Enclosure:
Reply to Notice of Violation cc: See Page 2
U.S. Nuclear Regulatory Commission CNL-15-079 Page 2 May 1, 2015 cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Jessie Quichocho U.S. Nuclear Regulatory Commission MS 08G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Fred Brown, Deputy Regional Administrator for Construction U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Office of Enforcement U.S. Nuclear Regulatory Commission 4A15A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738
WATTS BAR NUCLEAR PLANT, UNIT 2 ENCLOSURE REPLY TO NOTICE OF VIOLATION Description of the Violation 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
TVA Procedure MAI-5.1B, Wedge Bolt (WB) Anchor Installation, Revision 21, is the implementing/controlling process for anchor bolt installation, and includes the requirements for perpendicularity of newly installed wedge bolt anchors.
MAI-5.1B, Revision 21, Section 6.2.6.D, states that wedge bolt anchors shall be installed to within 5 degrees of perpendicular. Newly installed wedge bolt anchors exceeding this requirement are removed and replaced per Section 6. 4 or approval of the deviation obtained from Site Engineering.
Contrary to the above, on or about December 19, 2011, contract employees assigned to install anchor bolts for overhead base plates, which support safety related ventilation in the containment building, willfully failed to remove and replace, or obtain site engineering approval for, newly installed wedge bolt anchors that exceeded 5 degrees of perpendicular, as required by TVA Procedure MAI-5. 1B. Specifically, out of tolerance anchor bolts on hangers 86-1541 and 86-1545 were bent (straightened) to within 5 degrees of perpendicular utilizing a non-approved modified tool. All four overhead base plates of hangers 86-1541 and 86-1545 had at least one bent (weakened) bolt.
This is a Severity Levell// violation (Enforcement Policy Sections 2.2.1.d, 6.5).
TVA Response TVA does not dispute the facts as described by the Nuclear Regulatory Commission and accepts the violation. As noted in the Notice of Violation, the violation did not result in any actual consequences; the issue was self-identified and corrected during construction.
Reason for the Violation On or about December 19, 2011, a General Foreman and Foreman performed work, or directed employees to perform work, outside of the scope of the work order, invoking shortcuts to get the work completed, contrary to TVA procedure MAI-5.1 8, Wedge Bolt (WB)
Anchor Installation. TVA's extent of condition review determined that the inappropriate work was isolated to one crew.
CNL-15-079 E-1
Corrective Steps That Have Been Taken And The Results Achieved Upon notification of the events and circumstances surrounding this violation, Employee Concerns Program (ECP) personnel initiated file ECP-2012-WC-279-11. A Problem Evaluation Report (PER 635002) was generated to enter the concern into the Corrective Action Program and TVA completed an apparent cause evaluation. The apparent cause evaluation prompted corrective actions which corrected the nonconforming anchor bolt installations.
Following discovery, management directed a work stoppage of anchor bolt installation.
Craft work on drilling and installing anchor bolts was stopped, and anchor bolt installation retraining was conducted with emphasis on strict procedure use and adherence. This retraining also focused on criteria for contacting Engineering and obtaining Engineering authorization before drilling into rebar or other embedded features, emphasized that bending of bolts is not procedurally allowed and that scanning for rebar must occur prior to boring holes in concrete for anchor bolt installation. Additionally, a directive was issued and disseminated to applicable craft personnel to provide requirements for personnel to perform rebar scanning prior to boring holes for anchor bolts. Disciplinary actions were taken against the responsible individuals where violations of procedures and/or processes took place, including the removal of site access for the responsible Foreman.
The apparent cause evaluation and an extent-of-condition review included the following.
- Interviews were conducted with involved personnel.
- A walk down of the Unit 2 Reactor Building Annulus and South Fan Room was conducted where the bending of anchor bolts and fabrication of unapproved tools was alleged to have occurred.
- Work Orders (WOs) and their associated Drawing Revision Authorizations (DRAs) and Field Change Requests (FCRs) were reviewed where work was performed in the identified areas by the responsible individuals.
- Accountability Logs for Unit 2 Upper and Lower Containment were also reviewed to determine employees' whereabouts in comparison to the date and time recorded in the work logs of associated Work Orders.
- Rebar scanning and internal inspections using boroscoping tools were utilized to confirm design compliance and mitigate destructive testing.
The results of the interviews, walkdowns, and rebar scanning identified a baseline of suspected areas. Ultrasonic testing, fiberscope/boroscope, and destructive testing (concrete chipping to expose rebar) were used on selected hangers in Reactor Building South Fan Room and Annulus to determine the extent of damage and repairs needed. The final scope of bent bolts and damaged rebar was determined to be limited to baseplates for Hangers 197-4001, located in the Reactor Building South Fan Room, and 86-1541 and 86-15451ocated in the upper dome of the Unit 2 Reactor Building.
CNL-15-079 E-2
To address the three (3) specific locations for potential for bent bolts and damaged rebar, TVA issued work orders as outlined below.
- 1. Removed portions of Heating Ventilation and Air Conditioning (HVAC) Support 197-4001 to allow removal of baseplate bolting, inspection of base plate bolt holes for cut rebar, and inspection of any anchor bolt damage. No nicks or cuts were found in adjacent rebar. Bolts were also examined by a Field Engineer and no adverse conditions were found.
- 2. Removed portions of HVAC Support 86-1541 to allow removal of baseplate bolting, inspection of base plate bolt holes for cut rebar, and inspection of any anchor bolt damage. Inspection of Section E-E baseplate revealed the meridional reinforcement was damaged during the installation of the four anchor bolts, and the bottom right anchor bolt was bent. Inspection of Section E1-E1 baseplate revealed the one meridional reinforcement was damaged during the installation of the bottom right anchor bolt, and the bottom right anchor bolt was bent. The condition of the reinforcement for both sections E-E and E1-E1 was evaluated and determined to be acceptable-as-is. All anchor bolts were removed, a structural repair of concrete performed, new anchor bolts were installed, and the plate was modified as required.
- 3. Removed portions of HVAC Support 86-1545 to allow removal of baseplate bolting, inspection of base plate bolt holes for cut rebar, and inspection of any anchor bolt damage. Engineering reviewed the condition of the anchor bolts and reinforcement in the vicinity of baseplates J-J and J1-J1 on hanger 86-1545. On section J-J, the hoop reinforcement was damaged during the installation of both the bottom left and bottom right anchor bolt. The meridional reinforcement was damaged during the installation of the bottom right anchor bolt. The bottom left anchor bolt was bent. On Section J1-J1, the top-right anchor location rebar was nicked, and the top-right anchor bolt was bent. The condition of the reinforcements was evaluated and determined to be acceptable-as-is. All anchor bolts were removed, a structural repair of concrete was performed, and new anchor bolts and baseplates were installed.
Engineering analysis of the bent expansion anchors demonstrated they met design criteria requirements. The damaged rebar was also evaluated by Engineering, which concluded the damaged rebar would not have affected the structural integrity of the containment building, and that the containment building would have performed its required design safety function.
Related Corrective Actions As a result of this willful violation and a previous 2010 willful violation (EA-12-021) and subsequent alternate dispute resolution resulting in a Confirmatory Order by the NRC, TVA has taken a significant number of actions addressing expectations for assuring work activities are performed in a complete and accurate manner. Specifically, the following actions were taken.
- The Chief Nuclear Officer and the Senior Vice President of Nuclear Construction issued a joint communication to all Nuclear Power Group and Nuclear Construction employees regarding expectations for assuring work activities are performed and documented in a complete and accurate manner.
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- The executive management expectations (above) were reinforced through the use of fleet wide posters and communications. These communications specifically discussed 10 CFR 50.9, Completeness and Accuracy of Information, willful violations, and the consequences of non-compliance.
- TVA revised the existing Nuclear Power Group (NPG) procedure on procedure use and adherence NPG-SPP-01.2, "Administration of Site Technical Procedures" to reinforce the requirements of 10 CFR 50.9 and the need to ensure complete and accurate documentation of work completion steps. Additionally, TVA revised "Nuclear Construction Plant Procedure PP-1," "Watts Bar Nuclear Plant Unit 2 Procedure Control, BPP-01.2," "Administration of Site Technical Procedures" for Bellefonte, and BPP-01.1 "Administration of Site Technical Procedures" for Bellefonte and updated major contracts to include the requirement to comply with TVA's Procedure Use and Adherence procedures in 2012.
- TVA provided initial10 CFR 50.9 training in 2012 (manager, supervisor and craft-level) to employees at all Nuclear Construction sites.
- TVA provided refresher 10 CFR 50.9 training in 2014 (manager, supervisor and craft-level) to Watts Bar Unit 2 employees, which will continue every two years through 2016, or until construction is complete.
- TVA enhanced existing 10 CFR 50.9 related general employee training (GET) for new employees joining Nuclear Power Group and Nuclear Construction, and updated the associated annual requalification training.
- Within six months of issuance of the Confirmatory Order and prior to July 1, 2013, TVA performed checks of the WBN Unit 2 construction contractors and subcontractors via the Employee Concerns Program (ECP), to identify undue scheduling pressure issues.
Surveys were taken in December 2012 and May 2013. Issues identified were and continue to be addressed commensurate with safety and in accordance with TVA's Corrective Action Program.
In 2013,TVA performed effectiveness reviews of actions taken and actions planned, including those taken in response to the ECP checks described above. Based on the results of the effectiveness review, TVA implemented appropriate corrective actions.
Project Oversight:
Broader project oversight activities are also continually being performed to assess Unit 2 performance. These activities include the following.
- Independent Project Assurance organization established and began performing assessments in Summer 2012.
- Work environment (cultural risk) assessment was initiated in conjunction with Office of Inspector General (OIG) in January 2013. The purpose of this assessment is to improve dialogue, build trust and a better work environment, identify potential risks to the project, and help ensure the project is completed in accordance with regulatory requirements.
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- Nuclear Construction Review Board was established in April 2012. The board performs independent review I assessments in selected focus areas including nuclear safety culture work environment and safety concerns.
- Office of Inspector General (OIG) staff is located on site. Senior project management routinely interfaces with OIG staff as issues are identified and requests assistance with investigations as needed.
- Independent Project Review Team was established. The team provides insight to the TVA Nuclear Oversight Committee from independent nuclear experts and provides an independent perspective of nuclear safety culture.
Corrective Steps That Will Be Taken TVA will continue to provide refresher 10 CFR 50.9 training (manager, supervisor and craft-level) to Watts Bar Unit 2 employees every two years through 2016, or until construction is complete.
Date When Full Compliance Will Be Achieved TVA achieved full compliance in October 2013 when repair and reinstallation was complete for the HVAC hangers 86-1541 and 86-1545.
CNL-15-079 E-5