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| | number = ML13252A009 | | | number = ML13252A009 |
| | issue date = 08/29/2013 | | | issue date = 08/29/2013 |
| | title = Watts Bar Nuclear Plant, Unit 1, Submittal of the Details of the Planned Drill to the Revised Flood Mode Operation Abnormal Operating Instruction (Aoi). 7.01, Maximum Probable Flood. | | | title = Submittal of the Details of the Planned Drill to the Revised Flood Mode Operation Abnormal Operating Instruction (Aoi). 7.01, Maximum Probable Flood. |
| | author name = Shea J W | | | author name = Shea J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| | page count = 3 | | | page count = 3 |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 August 29, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 |
| | |
| | ==Subject:== |
| | Submittal of the Details of the Planned Drill to the Revised Watts Bar Nuclear Plant Flood Mode Operation Abnormal Operating Instruction (AOI) 7.01, "Maximum Probable Flood" |
| | |
| | ==Reference:== |
| | : 1. Letter from TVA to NRC, "Tennessee Valley Authority (TVA) - Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2013 (ML13080A073) |
| | : 2. Letter from TVA to NRC, "Application to Revise Watts Bar Nuclear Plant Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01)," dated July 19, 2012 (ML12236A164) |
| | On March 12, 2013, the Tennessee Valley Authority (TVA) submitted an extension request regarding the flooding hazard reevaluation report required by the March 12, 2012, NRC Request for Information for Recommendation 2.1, Flooding (Reference 1). Included in Reference 1 is a status of flood hazard interim actions and a list of additional actions planned. One of the additional actions planned described in Reference 1 was revision of the Watts Bar Nuclear Plant (WBN) flood mode operation Abnormal Operating Instruction (AOI) 7.01, "Maximum Probable Flood." Revisions to the AOI have been made to facilitate more efficient transition to flood mode operation at WBN. To ensure the AOI can be appropriately implemented, TVA committed to perform a drill to the revised AOI by December 31, 2013. TVA also committed to provide details of the planned drill by August 29, 2013. |
| | Printed on recycled paper |
| | |
| | U.S. Nuclear Regulatory Commission Page 2 August 29, 2013 The purpose of this letter is to provide the details of the proposed drill. The drill will involve participation by TVA emergency organizations to include a Control Room Operations cell, Technical Support Center (TSC), Operations Support Center (OSC), and a Central Emergency Control Center (CECC) cell. OSC teams will be simulated to be dispatched to the field after being briefed. No actual plant equipment will be operated or modified during the drill. |
| | The scenario is based on the most limiting preparation time event for WBN as described in section 2.4.14.10 of the proposed WBN, Unit 1, Updated Final Safety Analysis Report (UFSAR) |
| | License Amendment Request dated July 19, 2012 (Reference 2). This scenario is the 1/2 Probable Maximum Flood (PMF) rain event with subsequent seismically induced failure of both Norris and Tellico dams. |
| | This Drill will not be utilized to formally address elements contained within Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline," for performance indicators regarding Drill/Exercise Performance (DEP). |
| | The Drill Goals are to: |
| | : 1. Demonstrate that the emergency response organization can effectively utilize the revised flood mode operating instructions and procedures to simulate implementation of actions required during an extreme flooding event. |
| | : 2. Demonstrate that emergency response procedures are adequate and identify any need for improvement or revision. |
| | : 3. Allow personnel to demonstrate and test the capabilities of the emergency response organization to protect the health and safety of plant personnel and the general public in accordance with the Nuclear Power - Radiological Emergency Plan (NP-REP), Site Emergency Plan Implementing Procedures (EPIPs), and the CECC EPIPs. |
| | : 4. Provide an interactive scenario to ensure proficiency of onsite and offsite emergency response capabilities. |
| | : 5. Provide training for emergency response personnel. |
| | : 6. Visibly demonstrate safe operations during the execution of the drill. |
| | This letter contains no new regulatory commitments. If you have questions regarding this matter, please contact Kevin Casey at (423) 751-8523. |
| | Res a.tfully, 7JW. Sheai |
| | ,Vice President, Nuclear Licensing cc: See Page 3 |
| | |
| | U.S. Nuclear Regulatory Commission Page 3 August 29, 2013 cc: |
| | NRC Regional Administrator - Region II NRC Director - NRC Headquarters NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant, Unit 1}} |
|
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Category:Letter
MONTHYEARCNL-24-080, Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2024-11-20020 November 2024 Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) CNL-24-064, Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R52024-11-0404 November 2024 Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R5 CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-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 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 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 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) 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 ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection 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 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO 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-24-010, 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-24-024, 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report 2024-09-05
[Table view] |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 August 29, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Submittal of the Details of the Planned Drill to the Revised Watts Bar Nuclear Plant Flood Mode Operation Abnormal Operating Instruction (AOI) 7.01, "Maximum Probable Flood"
Reference:
- 1. Letter from TVA to NRC, "Tennessee Valley Authority (TVA) - Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2013 (ML13080A073)
- 2. Letter from TVA to NRC, "Application to Revise Watts Bar Nuclear Plant Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01)," dated July 19, 2012 (ML12236A164)
On March 12, 2013, the Tennessee Valley Authority (TVA) submitted an extension request regarding the flooding hazard reevaluation report required by the March 12, 2012, NRC Request for Information for Recommendation 2.1, Flooding (Reference 1). Included in Reference 1 is a status of flood hazard interim actions and a list of additional actions planned. One of the additional actions planned described in Reference 1 was revision of the Watts Bar Nuclear Plant (WBN) flood mode operation Abnormal Operating Instruction (AOI) 7.01, "Maximum Probable Flood." Revisions to the AOI have been made to facilitate more efficient transition to flood mode operation at WBN. To ensure the AOI can be appropriately implemented, TVA committed to perform a drill to the revised AOI by December 31, 2013. TVA also committed to provide details of the planned drill by August 29, 2013.
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 August 29, 2013 The purpose of this letter is to provide the details of the proposed drill. The drill will involve participation by TVA emergency organizations to include a Control Room Operations cell, Technical Support Center (TSC), Operations Support Center (OSC), and a Central Emergency Control Center (CECC) cell. OSC teams will be simulated to be dispatched to the field after being briefed. No actual plant equipment will be operated or modified during the drill.
The scenario is based on the most limiting preparation time event for WBN as described in section 2.4.14.10 of the proposed WBN, Unit 1, Updated Final Safety Analysis Report (UFSAR)
License Amendment Request dated July 19, 2012 (Reference 2). This scenario is the 1/2 Probable Maximum Flood (PMF) rain event with subsequent seismically induced failure of both Norris and Tellico dams.
This Drill will not be utilized to formally address elements contained within Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline," for performance indicators regarding Drill/Exercise Performance (DEP).
The Drill Goals are to:
- 1. Demonstrate that the emergency response organization can effectively utilize the revised flood mode operating instructions and procedures to simulate implementation of actions required during an extreme flooding event.
- 2. Demonstrate that emergency response procedures are adequate and identify any need for improvement or revision.
- 3. Allow personnel to demonstrate and test the capabilities of the emergency response organization to protect the health and safety of plant personnel and the general public in accordance with the Nuclear Power - Radiological Emergency Plan (NP-REP), Site Emergency Plan Implementing Procedures (EPIPs), and the CECC EPIPs.
- 4. Provide an interactive scenario to ensure proficiency of onsite and offsite emergency response capabilities.
- 5. Provide training for emergency response personnel.
- 6. Visibly demonstrate safe operations during the execution of the drill.
This letter contains no new regulatory commitments. If you have questions regarding this matter, please contact Kevin Casey at (423) 751-8523.
Res a.tfully, 7JW. Sheai
,Vice President, Nuclear Licensing cc: See Page 3
U.S. Nuclear Regulatory Commission Page 3 August 29, 2013 cc:
NRC Regional Administrator - Region II NRC Director - NRC Headquarters NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant, Unit 1