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| | number = ML12005A228 | | | number = ML12005A228 |
| | issue date = 01/18/2012 | | | issue date = 01/18/2012 |
| | title = Watts Bar Nuclear Plant, Unit 2 - Status of Operating License Application Review Regarding Fire Protection Program (TAC No. ME2731) | | | title = Status of Operating License Application Review Regarding Fire Protection Program |
| | author name = Raghavan L | | | author name = Raghavan L |
| | author affiliation = NRC/NRR/DORL/LPWB | | | author affiliation = NRC/NRR/DORL/LPWB |
| | addressee name = Skaggs M D | | | addressee name = Skaggs M |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000391 | | | docket = 05000391 |
| | license number = | | | license number = |
| | contact person = Milano P D | | | contact person = Milano P |
| | case reference number = TAC ME2731 | | | case reference number = TAC ME2731 |
| | document type = Letter | | | document type = Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 18, 2012 Mr. Michael D. Skaggs Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
| January 18, 2012 Mr. Michael D. Skaggs Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 WATTS BAR NUCLEAR PLANT, UNIT 2 -SUBMITTAL ISSUES WITH OPERATING LICENSE APPLICATION REVIEW REGARDING FIRE PROTECTION PROGRAM (TAC NO. ME2731) | | |
| | ==SUBJECT:== |
| | WATTS BAR NUCLEAR PLANT, UNIT 2 - SUBMITTAL ISSUES WITH OPERATING LICENSE APPLICATION REVIEW REGARDING FIRE PROTECTION PROGRAM (TAC NO. ME2731) |
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| ==Dear Mr. Skaggs:== | | ==Dear Mr. Skaggs:== |
| I am writing to followup on recent discussions between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives from your staff regarding the resolution of issues arising from the NRC staff's review of your operating license (OL) application for Watts Bar Nuclear Plant (WBN), Unit 2, Specifically, the staff is currently reviewing Tennessee Valley Authority's (TVA's) submittals relating to Section 9.5,1, "Fire Protection Program," of the WBN Unit 2 Final Safety Analysis Report. As part of its review process, the staff identified several issues and held numerous meetings and telephone discussions to resolve the identified issues. The staff continues to identify additional issues with your submittals. | | |
| | I am writing to followup on recent discussions between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives from your staff regarding the resolution of issues arising from the NRC staff's review of your operating license (OL) application for Watts Bar Nuclear Plant (WBN), Unit 2, Specifically, the staff is currently reviewing Tennessee Valley Authority's (TVA's) submittals relating to Section 9.5,1, "Fire Protection Program," of the WBN Unit 2 Final Safety Analysis Report. As part of its review process, the staff identified several issues and held numerous meetings and telephone discussions to resolve the identified issues. |
| | The staff continues to identify additional issues with your submittals. |
| During a meeting on December 21, 2011, we discussed a number of comments that the staff has raised about the latest revision of the as-designed fire protection report, which TVA submitted on November 30, 2011. In this revision to the report, TVA incorporated changes to implement its responses to a series of requests for additional information from the NRC staff, During the discussions, the staff presented concerns it had with inconsistencies in the information presented in several areas of the report. Further, the staff noted that TVA must specifically describe any deviations from the requirements for fire protection of safe shutdown capability in the report rather than rely only on a proposed method for evaluating the capability of installed fire protection features. | | During a meeting on December 21, 2011, we discussed a number of comments that the staff has raised about the latest revision of the as-designed fire protection report, which TVA submitted on November 30, 2011. In this revision to the report, TVA incorporated changes to implement its responses to a series of requests for additional information from the NRC staff, During the discussions, the staff presented concerns it had with inconsistencies in the information presented in several areas of the report. Further, the staff noted that TVA must specifically describe any deviations from the requirements for fire protection of safe shutdown capability in the report rather than rely only on a proposed method for evaluating the capability of installed fire protection features. |
| As a result of the staffs issues and concerns, TVA stated that it would determine the specific elements in the program requiring revision and the schedule for providing a revised fire protection report. TVA stated that these actions would be completed by the first week of January 2012. TVA has since stated during a teleconference that the revised fire protection report will be submitted by February 24, 2012. The accuracy of this assessment and completion of any ensuing revisions to the fire protection documentation supporting the OL review is critical for the NRC staff to complete its review. In particular, it has already impacted the ability for the staff to present the results of its findings to M. Skaggs -2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated. | | As a result of the staffs issues and concerns, TVA stated that it would determine the specific elements in the program requiring revision and the schedule for providing a revised fire protection report. TVA stated that these actions would be completed by the first week of January 2012. TVA has since stated during a teleconference that the revised fire protection report will be submitted by February 24, 2012. |
| | The accuracy of this assessment and completion of any ensuing revisions to the fire protection documentation supporting the OL review is critical for the NRC staff to complete its review. In particular, it has already impacted the ability for the staff to present the results of its findings to |
| | |
| | M. Skaggs -2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated. |
| Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones. | | Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones. |
| We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule. | | We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule. |
| Sincerely, L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv M. Skaggs -the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated. | | Sincerely, L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv |
| | |
| | M. Skaggs - 2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated. |
| Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones. | | Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones. |
| We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule. | | We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule. |
| Sincerely, IRA by P. Milano fori L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv DISTRIBUTION: | | Sincerely, IRA by P. Milano fori L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv DISTRIBUTION: |
| PUBLIC LPWB Reading File RidsNrrDorlLpwb Resource RidsNrrLABClayton Resource RidsNrrPMWatlsBar2 Resource RidsNrrDraAfpb Resource RidsRgn2MailCenter Resource RidsOgcRp Resource RidsOpaMailCenter RHaag. R-II TNazario. | | PUBLIC LPWB Reading File RidsNrrDorlLpwb Resource RidsNrrLABClayton Resource RidsNrrPMWatlsBar2 Resource RidsNrrDraAfpb Resource RidsRgn2MailCenter Resource RidsOgcRp Resource RidsOpaMailCenter RHaag. R-II TNazario. SRI, R-II RidsAcrsAcnw_MailCTR Resource ADAMS Accession No ML12005A228 *via email |
| SRI, R-II RidsAcrsAcnw_MailCTR Resource ADAMS Accession No ML 12005A228 | | :1 OFFICE LPWB/PM LPWB/LA AFPB/BC OGC NLO LPWB/BC LPWB/PM AKlein NAME PMilano BClayton DRoth SCampbell LRaghavan * |
| *via email OFFICE:1 LPWB/PM LPWB/LA AFPB/BC OGC NLO LPWB/BC LPWB/PM NAME PMilano BClayton AKlein (wI comments) | | (wI comments) |
| DRoth SCampbell LRaghavan
| | DATE 01110/12 01/06/12 01/09/12 01/17/12 01/18/12 12130111 OFFICIAL AGENCY RECORD}} |
| * DATE 01110/12 01/06/12 01/09/12 01/17/12 01/18/12 12130111 OFFICIAL AGENCY RECORD}}
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Letter Sequence Other |
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Results
Other: CNL-14-077, Responses to Degraded Voltage Issue Requests for Additional Information, ML102290358, ML102290360, ML102290361, ML102290362, ML102290363, ML102290364, ML102290365, ML102290366, ML102290367, ML102290368, ML102290383, ML102290384, ML102290385, ML102290386, ML102290387, ML102290388, ML102290389, ML102290390, ML102290391, ML102290392, ML102290403, ML102290404, ML102290405, ML102290406, ML102290407, ML102290408, ML102290409, ML102290410, ML102290411, ML102290414, ML102290439, ML102290440, ML102290441, ML102290442, ML102290443, ML102290444, ML102290445, ML102290446, ML102290447, ML102290448, ML102290458, ML102290459, ML102290460, ML102290461, ML102290462, ML102290463, ML102290464, ML102290465, ML102290466... further results
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MONTHYEARML1001916862010-01-11011 January 2010
Final Safety Analysis Report, Amendment 97, Section 8 - Electric Power Through 8E-12
Project stage: Request
ML1005500072010-03-11011 March 2010
Request for Additional Information Related to Licensee'S Final Safety Analysis Report Amendment 95 Related to Section 4.2.2, Reactor Vessel Internal Components
Project stage: RAI
ML1010405732010-04-0909 April 2010
Response to NRC Request for Additional Information Regarding Licensee'S Final Safety Analysis Report (FSAR) Amendment Related to Section 4.2.2, Reactor Vessel Internal Components.
Project stage: Response to RAI
ML1011303512010-05-0505 May 2010
Request for Withholding Information from Public Disclosure (Tac No. ME2731)
Project stage: Withholding Request Acceptance
ML1014500842010-06-23023 June 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Reactor Systems, Nuclear Performance and Code Review, Ansd Plant Systems
Project stage: RAI
ML1015402502010-06-24024 June 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review, Plant Systems, and Testing (Tac Nos. ME2731 and ME3091)
Project stage: RAI
ML1017903992010-06-28028 June 2010
Request for Additional Information (RAI) Regarding Licensee'S Final Safety Analysis Report Amendment Related to Section 4.2.2, Reactor Vessel Internal Components
Project stage: Request
ML1016200062010-06-29029 June 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review (Tac No. ME2731)
Project stage: RAI
ML1015304742010-07-0202 July 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Mechanical and Civil Engineering Systems
Project stage: RAI
ML1016000262010-07-0808 July 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report, Amendment Related to Quality and Vendor Branch Review
Project stage: RAI
ML1015303542010-07-12012 July 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Electrical Engineering Systems
Project stage: RAI
ML1018001562010-07-15015 July 2010
Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Chapter 8, Electric Power
Project stage: RAI
ML1023003272010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-4A (Dwg No. 1-47W845-5, R38)
Project stage: Other
ML1022904652010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-2 (Dwg No. 1-47W845-2, R76)
Project stage: Other
ML1023003282010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-4B (Dwg No. 1-47W845-7, R14)
Project stage: Other
ML1023003292010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-5 (Dwg No. 1-47W611-67-1, R8)
Project stage: Other
ML1023003302010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-6 (Dwg No. 1-47W611-67-2, R5)
Project stage: Other
ML1023003312010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-8 (Dwg No. 1-47W611-67-4, R5)
Project stage: Other
ML1023003322010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-9 (Dwg No. 1-47W611-67-5, R10)
Project stage: Other
ML1023003332010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-10 (Dwg No. 1-47W610-67-1, R27)
Project stage: Other
ML1023003342010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-10 Sh a (Dwg No. 1-47W610-67-1A, R16)
Project stage: Other
ML1023003352010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-11 (Dwg No. 1-47W610-67-2, R15)
Project stage: Other
ML1023003432010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-12 Sh a (Dwg No. 1-47W610-67-3A, R7)
Project stage: Other
ML1023003442010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-13 (Dwg No. 1-47W610-67-4, R17)
Project stage: Other
ML1023003452010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-11 Sh a (Dwg No. 1-47W610-67-2A, R8)
Project stage: Other
ML1023003462010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-12 (Dwg No. 1-47W610-67-3, R12)
Project stage: Other
ML1023003472010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5, R14)
Project stage: Other
ML1023003482010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5A, R2)
Project stage: Other
ML1023003492010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-16 (Dwg No. 1-47W859-4, R23)
Project stage: Other
ML1023003502010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-17 (Dwg No. 1-47W859-3, R18)
Project stage: Other
ML1023003512010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-18 (Dwg No. 1-47W859-2, R36)
Project stage: Other
ML1023003522010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-19 (Dwg No. 1-47W859-1, R47)
Project stage: Other
ML1023003602010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-23 (Dwg No. 1-47W611-70-1, R9)
Project stage: Other
ML1023003612010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-20 (Dwg No. 1-47W610-70-1, R23)
Project stage: Other
ML1023003622010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-21 (Dwg No. 1-47W610-70-2, R29)
Project stage: Other
ML1023003632010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-21A (Dwg No. 1-47W610-70-2A, R15)
Project stage: Other
ML1023003642010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-22 (Dwg No. 1-47W610-70-3, R17)
Project stage: Other
ML1023003652010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-24 (Dwg No. 1-47W611-70-2, R11)
Project stage: Other
ML1023003672010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-25 (Dwg No. 1-47W611-70-3, R4)
Project stage: Other
ML1023003682010-08-0505 August 2010
Final Safety Analysis Report Figure 9.2-25A (Dwg No. 1-47W611-70-4, R4)
Project stage: Other
ML1023003692010-08-0505 August 2010
Final Safety Analysis Report Figure 9.3-1 (Dwg No. 1-47W610-32-1, R15)
Project stage: Other
ML1022903652010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-7 (Dwg No. 1-45W760-211-9, R16)
Project stage: Other
ML1023003972010-08-0505 August 2010
Final Safety Analysis Report Figure 9.5-25A (Dwg No. 1-47W610-82-2, R7)
Project stage: Other
ML1023003982010-08-0505 August 2010
Final Safety Analysis Report Figure 9.5-25B (Dwg No. 1-47W610-82-3, R7)
Project stage: Other
ML1023003992010-08-0505 August 2010
Final Safety Analysis Report Figure 9.5-25C (Dwg No. 1-47W610-82-4, R7)
Project stage: Other
ML1022903682010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-14B (Dwg No. 1-45W760-82-1, R17)
Project stage: Other
ML1022903672010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-9 (Dwg No. 1-45W760-211-11, R13)
Project stage: Other
ML1022903662010-08-0505 August 2010
Final Safety Analysis Report Figure 8.3-8 (Dwg No. 1-45W760-211-10, R12)
Project stage: Other
ML1022903622010-08-0505 August 2010
Final Safety Analysis Report Figure 8.1-3 (Dwg No. 1-45W700-1, R28)
Project stage: Other
ML1022903582010-08-0505 August 2010
Final Safety Analysis Report Figure 8.1.2 (Dwg No. 1-15E500-1, R31)
Project stage: Other
2010-06-28
[Table View] |
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Category:Letter
MONTHYEARIR 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
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-24-060, 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-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
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
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-24-033, 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
05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
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)
2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 18, 2012 Mr. Michael D. Skaggs Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - SUBMITTAL ISSUES WITH OPERATING LICENSE APPLICATION REVIEW REGARDING FIRE PROTECTION PROGRAM (TAC NO. ME2731)
Dear Mr. Skaggs:
I am writing to followup on recent discussions between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives from your staff regarding the resolution of issues arising from the NRC staff's review of your operating license (OL) application for Watts Bar Nuclear Plant (WBN), Unit 2, Specifically, the staff is currently reviewing Tennessee Valley Authority's (TVA's) submittals relating to Section 9.5,1, "Fire Protection Program," of the WBN Unit 2 Final Safety Analysis Report. As part of its review process, the staff identified several issues and held numerous meetings and telephone discussions to resolve the identified issues.
The staff continues to identify additional issues with your submittals.
During a meeting on December 21, 2011, we discussed a number of comments that the staff has raised about the latest revision of the as-designed fire protection report, which TVA submitted on November 30, 2011. In this revision to the report, TVA incorporated changes to implement its responses to a series of requests for additional information from the NRC staff, During the discussions, the staff presented concerns it had with inconsistencies in the information presented in several areas of the report. Further, the staff noted that TVA must specifically describe any deviations from the requirements for fire protection of safe shutdown capability in the report rather than rely only on a proposed method for evaluating the capability of installed fire protection features.
As a result of the staffs issues and concerns, TVA stated that it would determine the specific elements in the program requiring revision and the schedule for providing a revised fire protection report. TVA stated that these actions would be completed by the first week of January 2012. TVA has since stated during a teleconference that the revised fire protection report will be submitted by February 24, 2012.
The accuracy of this assessment and completion of any ensuing revisions to the fire protection documentation supporting the OL review is critical for the NRC staff to complete its review. In particular, it has already impacted the ability for the staff to present the results of its findings to
M. Skaggs -2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated.
Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones.
We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule.
Sincerely, L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv
M. Skaggs - 2 the Advisory Committee on Reactor Safeguards (ACRS). Based on TVA's date of February 24, 2012, the ACRS meeting scheduled in April 2012 has been moved to June 2012. Therefore, you need to keep the NRC staff informed on the progress so that any further changes to the ACRS schedule can be accommodated.
Please be advised that depending on the outcome of your activities in this matter, the NRC staff's review schedule will be revised and may impact the project milestones.
We request your continued attention to ensure that these actions are completed in a timely and thorough manner for the NRC staff to complete its licensing reviews and inspections consistent with your overall project schedule.
Sincerely, IRA by P. Milano fori L. Raghavan, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPWB Reading File RidsNrrDorlLpwb Resource RidsNrrLABClayton Resource RidsNrrPMWatlsBar2 Resource RidsNrrDraAfpb Resource RidsRgn2MailCenter Resource RidsOgcRp Resource RidsOpaMailCenter RHaag. R-II TNazario. SRI, R-II RidsAcrsAcnw_MailCTR Resource ADAMS Accession No ML12005A228 *via email
- 1 OFFICE LPWB/PM LPWB/LA AFPB/BC OGC NLO LPWB/BC LPWB/PM AKlein NAME PMilano BClayton DRoth SCampbell LRaghavan *
(wI comments)
DATE 01110/12 01/06/12 01/09/12 01/17/12 01/18/12 12130111 OFFICIAL AGENCY RECORD
