Letter Sequence Request |
---|
|
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
|
MONTHYEARML1001916862010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97, Section 8 - Electric Power Through 8E-12 Project stage: Request ML1015401332010-06-10010 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 ML11286A0352011-09-30030 September 2011 OL - Additional Draft RAI on Fire Protection - Group 8 Project stage: Request ML11286A0382011-09-30030 September 2011 OL - Draft RAIs 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 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 ML13081A0042013-03-13013 March 2013 Transmittal of Revised Unit 1/Unit 2 As-Designed Fire Protection Report Project stage: Request 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 2012-05-17
[Table View] |
|
---|
Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] |
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.
Enclosure 2 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 report are for each individual action and are not added up to show that the time required for all the actions that 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 demonstrated travel 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