Letter Sequence Request |
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Results
Other: CNL-14-201, Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report, CNL-15-174, Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request, CNL-15-214, Updated Pages for As-Constructed Fire Protection Report, ML12207A080, ML13051A045, ML13081A002, ML13081A003, ML14265A449, ML15175A508
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MONTHYEARML1015401332010-06-10010 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Accident Dose 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 ML1016002782010-07-12012 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Accident Dose Project stage: RAI ML11129A1582011-05-0606 May 2011 Request for Additional Information Regarding Fire Protection Report, Project stage: Request ML1115201192011-05-26026 May 2011 Response to Request for Additional Information Regarding Fire Protection Report. Project stage: Response to RAI ML1120303872011-07-27027 July 2011 Request for Additional Information Regarding Incore Instrumentation System Project stage: RAI ML11215A1322011-07-29029 July 2011 Response to Request for Additional Information Regarding June 28, 2011 NRC Audit- Steam Line Break (Slb) and Other Miscellaneous RAIs Project stage: Response to RAI ML11227A2572011-08-0505 August 2011 Request for Additional Information (RAI) Group 6 Regarding Fire Protection Report Project stage: Request ML11230A3852011-08-15015 August 2011 Transmittal of Revised Unit 1 / Unit 2 As-Designed Fire Protection Report Project stage: Request ML13060A2252011-09-30030 September 2011 Response to Request for Additional Information Group 7 Regarding Fire Protection Report, (TAC No. ME3091) (Public Version) Project stage: Response to RAI ML11286A0382011-09-30030 September 2011 OL - Draft RAIs on Fire Protection - Group 8 Project stage: Request ML11286A0352011-09-30030 September 2011 OL - Additional Draft RAI on Fire Protection - Group 8 Project stage: Request ML11306A0902011-10-28028 October 2011 Response to Request for Additional Information Group 8 Regarding Fire Protection Report Project stage: Response to RAI ML1207905812012-03-23023 March 2012 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1, Fire Protection Group 8 Project stage: RAI ML12142A0262012-05-17017 May 2012 OL - Request for Additional Information Regarding Fire Protection Review Group 10 Project stage: RAI ML12153A3742012-05-30030 May 2012 Watts, Unit 2, Response to Request for Additional Information Project stage: Response to RAI ML12163A0532012-06-0707 June 2012 OL - Request for Additional Information on Fire Protection Project stage: RAI ML12179A1692012-06-25025 June 2012 OL - Draft Need for Information on Fire Protection Report Project stage: Request ML12181A5312012-06-27027 June 2012 Resolution of Concerns with Fire Protection Report (Fpr) Operator Manual Action (OMA) 732 and Response to Requests for Additional Information Project stage: Response to RAI ML12207A0802012-07-19019 July 2012 Resolution of Concerns with Fire Protection Report Operator Manual Action 732 - Commitment Schedule Update Project stage: Other ML13051A0452013-02-14014 February 2013 Updated Response to NRC Bulletin 2011-01, Mitigation Strategies Project stage: Other ML13081A0042013-03-13013 March 2013 Transmittal of Revised Unit 1/Unit 2 As-Designed Fire Protection Report Project stage: Request ML13081A0032013-03-13013 March 2013 Revised Watts Bar Nuclear Plant Unit 1/Unit 2 As-Designed Fire Protection Report. Part 2 of 2 Project stage: Other ML13081A0022013-03-13013 March 2013 Revised Watts Bar Nuclear Plant Unit 1/Unit 2 As-Designed Fire Protection Report. Part 1 of 2 Project stage: Other CNL-14-022, Withdrawal of Application to Update Watts Bar Unit 1 License Condition 2.F to Allow Two-Unit Operation (WBN-TS-13-18)2014-02-18018 February 2014 Withdrawal of Application to Update Watts Bar Unit 1 License Condition 2.F to Allow Two-Unit Operation (WBN-TS-13-18) Project stage: Withdrawal ML14265A4492014-09-18018 September 2014 Watts Bar, Unit 2 - Transmittal of Unit 1/Unit 2 As-Constructed Fire Protection Report Project stage: Other CNL-14-201, Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report2014-10-27027 October 2014 Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report Project stage: Other CNL-14-235, Transmittal of Part V of the Unit 1/Unit 2 Fire Protection Report2015-01-0909 January 2015 Transmittal of Part V of the Unit 1/Unit 2 Fire Protection Report Project stage: Request ML15175A5082015-06-24024 June 2015 Watts Bar, Unit 2 - Transmits Unit 1/Unit 2 As-Constructed Fire Protection Report (TAC No. ME3091) Project stage: Other CNL-15-174, Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request2015-08-27027 August 2015 Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request Project stage: Other CNL-15-214, Updated Pages for As-Constructed Fire Protection Report2015-10-0707 October 2015 Updated Pages for As-Constructed Fire Protection Report Project stage: Other 2012-05-30
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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 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-24-060, 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) 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-24-024, 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-24-033, 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 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-24-007, 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) 2024-09-05
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Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 15, 2011 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - TRANSMITTAL OF REVISED UNIT 1 I UNIT 2 AS-DESIGNED FIRE PROTECTION REPORT (TAC NO. ME3091)
Reference:
TVA Letter to NRC dated August 5, 2011, "Watts Bar Nuclear Plant, Unit 2 -
Request for Additional Information (RAI) Group 6 'Fire Protection Report' (TAC NO.
ME3091)"
The purpose of this letter is to transmit a revision to the WBN Unit 1/Unit 2 Fire Protection Report (FPR) and to address two questions received from the Staff regarding the FPR Feasibility and Reliability evaluations (F&R evaluations) for Unit 2. Enclosure 1 contains the Unit 1/Unit 2 FPR in its entirety for completeness. Additionally, revision bars are utilized throughout the enclosed document to identify the changes. The main purpose of this FPR revision is to include the modifications required to reduce the number of Operator Manual Actions (OMAs) required for Unit 2 operation. provides an update to the summary listing of Fire Protection commitments that was submitted in the referenced letter. This update is based upon items addressed by this letter.
This summary listing contains a description of the commitment, the status (open or closed), as well as pertinent references (initiating, closing, etc.). The commitment date for one item has been updated based on the current project schedule.
The following provides the two NRC questions regarding the FPR OMA Feasibility and Reliability evaluations for Unit 2 and TVA's responses:
- 1. It appears the OMA times contained in the reportare for each individualaction and are not added up to show that the time requiredfor all the actionsthat a specific AUO has to perform is less than the available time. In other words are the times cumulative or individual?
- 2. It appears the demonstratedtravel time does not account for any margin. ;-(p
U.S. Nuclear Regulatory Commission Page 2 August 15, 2011 The following discussion is based on the F&R evaluations contained in the July 1, 2011 letter.
Some of the section numbers may change in the August 15, 2011 submittal, but the concepts/justifications will still be the same.
Question I The times quoted in the FPR Part VII, Section 8 for Unit 2 are cumulative times for all required actions based upon Unit 1 walkdowns (see Part VII, Section 8.2.a, last sentence). The walkdowns for Unit 1 were performed for each of the fire protection Abnormal Operating Instructions (AOIs) demonstrating the timing for the specific actions in that particular AOI in the order performed by that AOI. Even if multiple AOIs required the same actions by an operator, the OMA sequence was validated again in conjunction with validation of the OMAs performed by the other operators. The demonstrated times for the OMAs for a given AOI are cumulative times accounting for all required OMAs. Since the time of the Unit 1 validation, the OMAs have been categorized as either "green box" (required for safe shutdown) or "orange box" (important to safety). The validation walkdowns included all OMAs within a given AOI (both green and orange) and thus the times in the F&R evaluations are total cumulative times.
It appears the confusion lies in the presentation of the information in the FPR. FPR Part VII, Section 8 discusses the OMAs required for each fire room (e.g., for fire room 692-Al B, Section 8.3.1.3 for OMA 1047, Section 8.3.1.4 for OMAs 1159 and 1160, Section 8.3.1.5 for OMA 1164 and Section 8.3.1.6 for OMA 1165). These sections contain the Unit 1 demonstrated times for each OMA required for safe shutdown (i.e., green box) having a required performance time of less than 120 minutes, as validated by the associated AOI. Then, Section 8.3.1.7 describes the staffing required to accomplish all of the OMAs (i.e., green box and orange box) within the required time. The F&R of each green box OMA of required times less than 120 minutes is evaluated in its corresponding section (e.g., 8.3.1.3.a and 8.3.1.3.b for OMA 1047). For this fire room, OMA 1047 is the sole action performed by the designated AUO, and thus the demonstrated time for OMA 1047 used for both the F&R evaluations is quite clear.
However, for other fire rooms, the presentation of the information could be confusing. For example, fire room 737.0-AlA (FPR Section 8.3.25) requires AUO #3 to perform five actions (Section 8.3.25.12.c). They are the same five actions demonstrated for Unit 1. The discussion of F&R in Sections 8.3.25.3 through 8.3.25.11 discusses each action as if it were an individual, discrete action. In reality, the demonstrated times quoted in the sections (e.g., 8.3.25.11 .a and 8.3.25.11 .b) are the cumulative time used by the operator in performing not only that action, but also any preceding actions. The OMAs are not discussed/presented in the order performed by the AUO and thus the times do not appear to be cumulative even though in actuality they are cumulative. Additionally, the demonstrated times account for orange box OMAs (e.g., 1044) and OMAs with required times greater than 120 minutes even though these OMAs are not evaluated in the report.
In a few places the report shows the same time for two actions (e.g., OMAs 1022 and 1023 in Sections 8.3.15.3 and 8.3.15.4). In this case the time is cumulative for both actions to be performed. The actions are performed in the same area and thus only a single cumulative time was recorded.
U.S. Nuclear Regulatory Commission Page 3 August 15, 2011 Question 2 NUREG-1852 Section 4.2.2 describes two methods of ensuring adequate time is estimated for operator action performance time.
- a. Conservatively estimate the time to envelope all possible uncertainties. The second sentence at the top of page 4-4 indicates that 100% margin should be adequate (but not required) to envelope all uncertainties. The acceptance criteria in FPR Part V, Section 2.1.2.1.a uses this approach.
- b. Specifically account for each uncertainty and add additional time to the demonstrated performance time to account for the uncertainties applicable to each situation. The acceptance criteria in FPR Part V, Section 2.1.2.1.b uses this approach.
There are no new regulatory commitments in this letter. If you have any questions, please contact William Crouch at (423) 365-2004.
I declare under the penalty of perjury that the foregoing is true and correct. Executed on the 1 5 th day of August, 2011.
Respectfully, David Stinson Watts Bar Unit 2 Vice President
Enclosures:
- 1. Revised Unit I / Unit 2 As-Designed "Fire Protection Report
- 2. Summary Listing of Fire Protection Commitments cc (Enclosures):
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