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| {{#Wiki_filter:}} | | {{#Wiki_filter:August 13, 2021 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801 |
| | |
| | ==SUBJECT:== |
| | WATTS BAR NUCLEAR PLANT, UNIT 2 - REGULATORY AUDIT |
| | |
| | ==SUMMARY== |
| | |
| | RELATED TO REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CHANGE THE STEAM GENERATOR WATER LEVEL (EPID L-2021-LLA-0032) |
| | |
| | ==Dear Mr. Barstow:== |
| | |
| | By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 2, 2021, Tennessee Valley Authority (TVA) submitted a license amendment request that would amend the Watts Bar, Unit 2 Technical Specifications (TS) to change the steam generator (SG) water level requirement in Watts Bar, Unit 2 TS Limiting Condition for Operation (LCO) 3.4.7.b, RCS Loops |
| | - MODE 5, Loops Filled, and Surveillance Requirements (SR) 3.4.5.2, RCS Loops - MODE 3, SR 3.4.6.3, RCS Loops - MODE 4, and SR 3.4.7.2 from greater than or equal to () 6 percent |
| | (%) to 32%. The proposed change is needed to support the Watts Bar, Unit 2 Replacement SG (RSG) project. |
| | To enhance the review of TVAs request, the NRC staff conducted an audit of supporting documents on June 3, 2021. The staff audited the requested documents to confirm certain information relied upon in the license amendment request. A summary of the regulatory audit is enclosed. |
| | The NRC staff did not identify any significant issues during the audit. The staff also identified there is no additional information needed to complete the review of the subject license amendment request. |
| | Sincerely, |
| | /RA/ |
| | Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 |
| | |
| | ==Enclosure:== |
| | |
| | Regulatory Audit Summary cc: Listserv |
| | |
| | REGULATORY AUDIT |
| | |
| | ==SUMMARY== |
| | RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CHANGE THE STEAM GENERATOR WATER LEVEL TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391 |
| | |
| | ==1.0 BACKGROUND== |
| | |
| | A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of docketed and non-docketed information. The audit was conducted with the intent to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision. |
| | By {{letter dated|date=March 2, 2021|text=letter dated March 2, 2021}}, Tennessee Valley Authority (TVA) submitted a license amendment request that would amend the Watts Bar, Unit 2 Technical Specifications (TS) to change the steam generator (SG) water level requirement in Watts Bar, Unit 2 TS Limiting Condition for Operation (LCO) 3.4.7.b, RCS [Reactor Coolant System] Loops - MODE 5, Loops Filled and Surveillance Requirements (SR) 3.4.5.2, RCS Loops - MODE 3, SR 3.4.6.3, RCS Loops - MODE 4, and SR 3.4.7.2, RCS Loops - MODE 5, Loops Filled, from greater than or equal to () 6 percent (%) to 32%. The proposed change is needed to support the Watts Bar, Unit 2 Replacement SG (RSG) project. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff performed a preliminary review of the licensing amendment request (LAR) and determined that a regulatory audit would assist in the timely completion of the review. The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (Agencywide Documents Access and Management System (ADAMS) |
| | Accession No. ML19226A274). |
| | 2.0 AUDIT ACTIVITIES AND RESULTS The NRC staff conducted a regulatory audit that consisted of a remote audit on June 3, 2021. |
| | The audit plan was provided to TVA on May 24, 2021 (ADAMS Accession No. ML21144A074). |
| | The list of documents uploaded by the licensee in response to the NRC staffs request and examined by the audit team is provided in Section 4.0 below. |
| | The remote audit was conducted using an online portal and teleconferencing capabilities. The purpose of the audit was to (1) examine several analyses or documents referenced in the LAR but not provided as part of the LAR, and (2) identify any information that would be required from Enclosure |
| | |
| | the licensee to be provided on the docket for the NRC to render a staff finding to support the safety evaluation. |
| | The NRC staff examined the documents identified in Section 4.0 below and held an audit call with members of TVA on June 3, 2021, regarding the LAR under review. |
| | At the conclusion of the audit, the NRC staff determined that additional information would not be needed in order for the staff to complete the review of the LAR. |
| | 3.0 AUDIT PARTICIPANTS NRC R. Beaton N. Carte M. Mahoney TVA R. Wells G. Williams 4.0 DOCUMENTS PROVIDED IN ELECTRONIC READING ROOM Westinghouse Calculation CN-SCS-16-12, Revision 2, Watts Bar Unit 2 RSG [Replacement Steam Generator] Narrow Range Level Uncertainty for EOP [Emergency Operating Procedure] |
| | Applications and Technical Specifications Level Surveillances. |
| | Westinghouse LTR-SCS-21-42, Revision 0, Attachment 1, Watts Bar Unit 2: Bases for the Technical Specification Surveillance Limit for Steam Generator Level, May 28, 2021, Attachment to WAT-D-12773. |
| | TVA Drawing 20010E01, Sheet 1 of 3, Revision 2, General Arrangement TVA - Watts Bar 2 RSG. |
| | |
| | ML21217A222 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SNSB/BC NAME MMahoney RButler SKrepel DATE 08/10/2021 08/09/2021 08/10/2021 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona MMahoney DATE 08/10/2021 08/13/2021}} |
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MONTHYEARML21048A3242021-02-17017 February 2021 License Amendment Request for Application to Revise Technical Specifications to Adopt TSTF-205 -A Revision of Calibration, Channel Functional Test, and Related Definitions Project stage: Request RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-02-24024 February 2021 License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications Project stage: Request CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05)2021-03-0202 March 2021 License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05) Project stage: Request ML21105A0332021-03-0808 March 2021 ISFSI Emergency Plan License Amendment Request - Public Project stage: Request RA-21-0052, License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency2021-03-24024 March 2021 License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency Project stage: Request DCL-21-020, Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance2021-03-29029 March 2021 Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance Project stage: Request ML21089A0582021-03-30030 March 2021 NRR E-mail Capture - Acceptance Review - Watts Bar Nuclear Plant, Unit 2 - CNL-21-016 - LAR to Revise TS to Change SG Secondary Side Water Level to Accommodate RSGs (L-2021-LLA-0032) Project stage: Acceptance Review RS-21-007, Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 02021-04-0707 April 2021 Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 Project stage: Request ML21104A1622021-04-14014 April 2021 NRR E-mail Capture - (External_Sender) Salem Generating Station - Incidental Take Reports: Atlantic Sturgeon 04/13/2021 Project stage: Request WBL-21-020, Annual Non-Radiological Environmental Operating Report - 20202021-04-20020 April 2021 Annual Non-Radiological Environmental Operating Report - 2020 Project stage: Request LR-N21-0036, LR-N21-0036 LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-04-28028 April 2021 LR-N21-0036 LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Project stage: Other ML21119A1412021-04-29029 April 2021 License Amendment Request, Revise Technical Specifications Administrative Controls Section 5.5.7 Regarding the Frequency for Performing Certain Ventilation Filter Testing Project stage: Request ML21144A0742021-05-24024 May 2021 NRR E-mail Capture - Watts Bar Nuclear Plant, Unit 2 - Audit Plan for SG Water Level Change LAR Project stage: Approval ML21217A2222021-08-13013 August 2021 Regulatory Audit Summary Related to Request to Revise Technical Specifications to Change the Steam Generator Water Level Project stage: Other ML21252A0912021-09-0909 September 2021 NRR E-mail Capture - Request for Comments on Proposed Issuance of Amendments to Watts Bar Nuclear Plant, Unit 2 - Revise Steam Generator Secondary Side Water Level Project stage: Approval ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level Project stage: Approval 2021-03-08
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Category:Audit Report
MONTHYEARML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML21217A2222021-08-13013 August 2021 Regulatory Audit Summary Related to Request to Revise Technical Specifications to Change the Steam Generator Water Level ML18115A1382018-07-10010 July 2018 Staff Review of the Seismic Probabilistic Risk Assessment Associated with the Implementation of the Near-Term Task Force Recommendation 2.1: Seismic (CAC Nos. MF9879 and MF9880; EPID L-2017-JLD-0044 ML15345A4242015-12-23023 December 2015 Audit Report Related to License Amendment Request to Revise Technical Specification 4.2.1, Fuel Assemblies ML15334A1252015-12-23023 December 2015 Audit of the Licensee'S Management of Regulatory Commitments ML15294A2032015-10-30030 October 2015 NRC Report for the Audit of Tennessee Valley Authority'S Flood Hazard Reevaluation Report Submittals Relating to the Near-Term Task Force Recommendation 2.1-Flooding for Browns Ferry, Units 1,2 & 3, Sequoyah, Units 1 & 2, and Watts Bar, Uni ML14323A5622014-12-0303 December 2014 Report for the Audit Regarding Implementation of Licensing Preservation Program ML14211A3462014-08-18018 August 2014 Report for the Westinghouse Audit in Support of Reliable Spent Fuel Instrumentation Related to Order EA-12-051 ML14128A1292014-05-15015 May 2014 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML13343A0362013-12-20020 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13022A4012013-02-0707 February 2013 Audit of the Licensee'S Management of Regulatory Commitments ML1110306242011-04-27027 April 2011 Accident Analyses Audit Report Westinghouse Documents Relating to Final Safety Analysis Report Accident Analyses ML1034005992011-01-20020 January 2011 Commercial Grade Dedication of Hardware and Software Used in the Post Accident Monitoring System Audit Report ML0929300102009-10-21021 October 2009 Audit of the Licensee'S Management of Regulatory Commitments ML0621204692006-11-22022 November 2006 Plant Audit Report--Watts Bar Unit 1 Nuclear Plant New Sump Design in Response to Audit Report ML0615900812006-07-0303 July 2006 Letter, Audit of the Licensee'S Management of Regulatory Commitments ML0419101202004-07-0606 July 2004 LTR-04-0425 - Richard Schneider Ltr Final TVA Control Area Readiness Audit 2024-07-25
[Table view] Category:Letter
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 IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 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 ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan 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 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public 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), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 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 ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 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 IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information 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 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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) ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report 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) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) 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-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report 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-24-025, 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 ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 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-24-028, 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-24-029, 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 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 2024-09-05
[Table view] |
Text
August 13, 2021 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REGULATORY AUDIT
SUMMARY
RELATED TO REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CHANGE THE STEAM GENERATOR WATER LEVEL (EPID L-2021-LLA-0032)
Dear Mr. Barstow:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 2, 2021, Tennessee Valley Authority (TVA) submitted a license amendment request that would amend the Watts Bar, Unit 2 Technical Specifications (TS) to change the steam generator (SG) water level requirement in Watts Bar, Unit 2 TS Limiting Condition for Operation (LCO) 3.4.7.b, RCS Loops
- MODE 5, Loops Filled, and Surveillance Requirements (SR) 3.4.5.2, RCS Loops - MODE 3, SR 3.4.6.3, RCS Loops - MODE 4, and SR 3.4.7.2 from greater than or equal to () 6 percent
(%) to 32%. The proposed change is needed to support the Watts Bar, Unit 2 Replacement SG (RSG) project.
To enhance the review of TVAs request, the NRC staff conducted an audit of supporting documents on June 3, 2021. The staff audited the requested documents to confirm certain information relied upon in the license amendment request. A summary of the regulatory audit is enclosed.
The NRC staff did not identify any significant issues during the audit. The staff also identified there is no additional information needed to complete the review of the subject license amendment request.
Sincerely,
/RA/
Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Regulatory Audit Summary cc: Listserv
REGULATORY AUDIT
SUMMARY
RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CHANGE THE STEAM GENERATOR WATER LEVEL TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391
1.0 BACKGROUND
A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of docketed and non-docketed information. The audit was conducted with the intent to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision.
By letter dated March 2, 2021, Tennessee Valley Authority (TVA) submitted a license amendment request that would amend the Watts Bar, Unit 2 Technical Specifications (TS) to change the steam generator (SG) water level requirement in Watts Bar, Unit 2 TS Limiting Condition for Operation (LCO) 3.4.7.b, RCS [Reactor Coolant System] Loops - MODE 5, Loops Filled and Surveillance Requirements (SR) 3.4.5.2, RCS Loops - MODE 3, SR 3.4.6.3, RCS Loops - MODE 4, and SR 3.4.7.2, RCS Loops - MODE 5, Loops Filled, from greater than or equal to () 6 percent (%) to 32%. The proposed change is needed to support the Watts Bar, Unit 2 Replacement SG (RSG) project.
The U.S. Nuclear Regulatory Commission (NRC) staff performed a preliminary review of the licensing amendment request (LAR) and determined that a regulatory audit would assist in the timely completion of the review. The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML19226A274).
2.0 AUDIT ACTIVITIES AND RESULTS The NRC staff conducted a regulatory audit that consisted of a remote audit on June 3, 2021.
The audit plan was provided to TVA on May 24, 2021 (ADAMS Accession No. ML21144A074).
The list of documents uploaded by the licensee in response to the NRC staffs request and examined by the audit team is provided in Section 4.0 below.
The remote audit was conducted using an online portal and teleconferencing capabilities. The purpose of the audit was to (1) examine several analyses or documents referenced in the LAR but not provided as part of the LAR, and (2) identify any information that would be required from Enclosure
the licensee to be provided on the docket for the NRC to render a staff finding to support the safety evaluation.
The NRC staff examined the documents identified in Section 4.0 below and held an audit call with members of TVA on June 3, 2021, regarding the LAR under review.
At the conclusion of the audit, the NRC staff determined that additional information would not be needed in order for the staff to complete the review of the LAR.
3.0 AUDIT PARTICIPANTS NRC R. Beaton N. Carte M. Mahoney TVA R. Wells G. Williams 4.0 DOCUMENTS PROVIDED IN ELECTRONIC READING ROOM Westinghouse Calculation CN-SCS-16-12, Revision 2, Watts Bar Unit 2 RSG [Replacement Steam Generator] Narrow Range Level Uncertainty for EOP [Emergency Operating Procedure]
Applications and Technical Specifications Level Surveillances.
Westinghouse LTR-SCS-21-42, Revision 0, Attachment 1, Watts Bar Unit 2: Bases for the Technical Specification Surveillance Limit for Steam Generator Level, May 28, 2021, Attachment to WAT-D-12773.
TVA Drawing 20010E01, Sheet 1 of 3, Revision 2, General Arrangement TVA - Watts Bar 2 RSG.
ML21217A222 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SNSB/BC NAME MMahoney RButler SKrepel DATE 08/10/2021 08/09/2021 08/10/2021 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona MMahoney DATE 08/10/2021 08/13/2021