ML082840361

Status of Regulatory Framework for the Completion of Operating License Review (Tac MD9424)

ML082840361
Person / Time
Site:	Watts Bar
Issue date:	10/10/2008
From:	Milano P Watts Bar Special Projects Branch
To:	Bhatnagar A Tennessee Valley Authority
Milano P, NRR/DORL , 415-1457
References
NUREG-0847, TAC MD9424
Download: ML082840361 (24)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 10, 2008 Mr. Ashok Bhatnagar Senior Vice President Nuclear Generation Development and Construction 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: WAITS BAR NUCLEAR PLANT, UNIT 2 - STATUS OF REGULATORY FRAMEWORK FOR THE COMPLETION OF OPERATING LICENSE REVIEW (TAC NO. MD9424)

Dear Mr. Bhatnagar:

By letters dated January 29 and March 13, 2008, Tennessee Valley Authority (TVA) provided to the Nuclear Regulatory Commission (NRC) its framework for the completion of construction and licensing activities for Watts Bar Nuclear Plant (WBN) Unit 2. In this regard, TVA identified the Unit 2 licensing basis that was reviewed and approved concurrent with the WBN Unit 1 operating license review process. The NRC staff's previous review for WBN Unit 1, and a portion for Unit 2, was documented in NRC Report NUREG-0847, "Safety Evaluation Report

[SER] Related to the Operation of Watts Bar Nuclear Plant, Units 1 and 2," through Supplement 20.

The NRC staff performed an initial assessment of the status presented by TVA and reviewed the information in the SER and its Supplements in order to independently identify whether the topic sections had or had not been previously approved and documented for Unit 2. In a letter dated May 8, 2008, the staff forwarded the results of its initial assessment and identified the topics that it considered as remaining open and to be completed within the operating license review scope. The NRC staff found that many of the existing licensing review topics have already been addressed. However, the staff did not completely agree with TVA's position regarding the status of all topics and requested additional information from TVA to resolve certain differences between the NRC and TVA scoping assessments. On June 16,2008, TVA responded to the request for additional information, addressing all SER supplements pertinent to a given topic, and revised the overall status summary of the regulatory framework originally provided in the March 13, 2008, letter.

The NRC staff reviewed the revised regulatory framework master table in TVA's letter of June 16, 2008, focusing especially on the information supporting the reconciliation of prior status differences. On the basis of this review, the staff completed its assessment of the regulatory framework for WBN Unit 2 operating license review. Those SER topic items that the NRC staff considers open are listed in the enclosed Table 1. Thus, TVA will need to include these open topic items in future submittals or amendments to the Final Safety Analysis Report.

The detailed results of the staff's overall assessment of the regulatory framework can be found in the Table 2. Although many of the topic areas in Table 2 have been adequately documented and are considered closed, the NRC staff recognizes that there may be circumstances that could result in the need to re-open a previously closed topic.

A. Bhatnagar -2 Using the results of NRC's assessment, TVA should revise its regulatory framework status to match the staff's current reconciliation and assessment. In particular, TVA should maintain the list of open items from Table 2 and then update the information as actions are completed, proper documentation submitted to the NRC staff for review, and the NRC staff documents its review and acceptance in an SER Supplement. If TVA or the NRC staff determines that a previously reviewed and completed item needs to be re-opened, TVA should add the item to the list and highlight this action as having occurred. TVA is also requested to provide an update to the status, including references to TVA and NRC supporting documentation, at least every 6 months. The NRC staff will use this information to verify the completion of open actions and to coordinate the need for independent validation of implementation through inspections.

If you have questions regarding the staff's assessment or actions requested of TVA, please contact me at 301-415-1457.

Sincerely, Patrick D. Milano, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391

Enclosures:

Tables 1 and 2, Regulatory Framework Status for TVA Watts Bar Unit 2 cc w/encls: See next page

Ashok S. Bhatnagar Tennessee Valley Authority WATTS BAR NUCLEAR PLANT UNIT2 cc:

Mr. Gordon P. Arent General Counsel New Generation Licensing Manager Tennessee Valley Authority Tennessee Valley Authority 6A West Tower 5A Lookout Place 400 West Summit Hill Drive 1101 Market Street Knoxville, TN 37902 Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, Plant Manager Senior Resident Inspector, Unit 2 Watts Bar Nuclear Plant Watts Bar Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 1260 Nuclear Plant Road Spring City, TN 37381 Spring City, TN 37381 Mr. Lawrence E. Nanney, Director Mr. Michael K. Brandon, Manager Tennessee Dept. of Environmental Health &

Licensing and Industry Affairs Conservation Watts Bar Nuclear Plant Division of Radiological Health Tennessee Valley Authority 3rd Floor, L&C Annex P.O. Box 2000 401 Church Street Spring City, TN 37381 Nashville, TN 37243-1532 Mr. William R. Campbell, Jr. Mr. Larry E. Nicholson, General Manager Chief Nuclear Officer and Performance Improvement Executive Vice President Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place 3R Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Vice President County Executive Watts Bar Unit 2 375 Church Street Watts Bar Nuclear Plant Suite 215 Tennessee Valley Authority Dayton, TN 37321 P.O. Box 2000 Spring City, TN 37381 County Mayor P. O. Box 156 Mr. Michael D. Skaggs Decatur, TN 37322 Site Vice President Watts Bar Nuclear Plant Mr. John C. Fornicola, General Manager Tennessee Valley Authority Nuclear Assurance P. O. Box 2000 Tennessee Valley Authority Spring City, TN 37381 3R Lookout Place 1101 Market Street Ms. Ann P. Harris Chattanooga, TN 37402-2801 341 Swing Loop Road Rockwood, TN 37854

Table 1.

Topics Open in NUREG-0847 Watts Bar Nuclear Plant Unit 2 Subsection Title 2.1.3 Population Distribution 2.1.4 Conclusions 2.2.1 Transportation Routes 2.2.2 Nearby Facilities 2.2.3 Conclusions 2.4.8 Design Basis for Subsurface Hydrostatic Loading 2.4.9 Transport of Liquid Releases 3.2.2 System Quality Group Classification 3.6.0 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 3.7.0 Seismic Design 3.7.1 Seismic Input 3.7.2 Seismic Analysis 3.7.3 Seismic Subsystem Analysis 3.8.0 Design of Seismic Category I Structures 3.8.3 Other Seismic Category I Structures 3.9.1 Special Topics for Mechanical Components 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures 3.9.6 Inservice Testing of Pumps and Valves 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment 4.2.1 Description 4.2.2 Thermal Performance 4.2.3 Mechanical Performance 4.2.5 Fuel Design Conclusions 4.3.1 Design Basis 4.3.2 Design Description 4.3.3 Analytical Methods 4.3.4 Summary of Evaluation Findings Page 1 of 4

Table 1, continued.

Topics Open in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 Subsection Title 4.4.2 Design Bases 4.4.3 Thermal-Hydraulic Design Methodology 4.4.4 Operating Abnormalities 4.4.5 Loose Parts Monitoring System 4.4.8 Instrumentation for Inadequate Core Cooling Detection (1I.F.2) 4.4.9 Summary and Conclusion 5.1.0 Summary Description 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection 5.3.1 Reactor Vessel Materials 5.3.2 Pressure-Temperature Limits 5.3.3 Reactor Vessel Integrity 5.4.3 Residual Heat Removal System 6.2.1 Containment Functional Design 6.2.2 Containment Heat Removal Systems 6.2.5 Combustible Gas Control Systems 6.2.6 Containment Leakage Testing 6.3.1 System Design 6.3.2 Evaluation 6.3.3 Testing 6.3.5 Conclusions 6.4.0 Control Room Habitability 6.5.1 ESF Atmosphere Cleanup Systems 6.6.0 Inservice Inspection of Class 2 and 3 Components 7.1.1 General 7.1.3 Design Criteria 7.2.1 System Description 7.2.5 Steam Generator Water Level Trip 7.2.6 Conclusions 7.3.0 Engineered Safety Features System 7.3.1 System Description 7.3.6 Conclusions 7.4.2 Safe Shutdown from Auxiliary Control Room 7.5.2 Post-Accident Monitoring System Page 2 of 4

Table 1, continued.

Topics Open in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 Subsection Title 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC) 7.8.1 Relief and Safety Valve Position Indication (1I.D.3) 8.2.2 Compliance With GDC 17 8.3.1 Onsite AC Power System Compliance With GDC 17 8.3.3 Evaluation Findings 9.1.2 Spent Fuel Storage 9.1.3 Spent Fuel Pool Cooling and Cleanup System 9.1.4 Fuel Handling System 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) 9.3.2 Process Sampling System 9.4.5 Engineered Safety Features Ventilation System 9.5.2 Communication Systems 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System 9.5.6 Emergency Diesel Engine Starting Systems 9.5.7 Emergency Diesel Engine Lubricating Oil System 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System 10.2.0 Turbine Generator 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves) 10.3.4 Secondary Water Chemistry 10.4.4 Turbine Bypass System 11.1.0 Summary Description 11.4.0 Solid Waste Management System 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems 11.6.0 Evaluation Findings 11.7.0 NUREG-0737 Items 11.7.2 Primary Coolant Outside Containment (1II.D.1.1) 12.1.0 General 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable 12.3.0 Radiation Sources 12.4.0 Radiation Protection Design Features 12.5.0 Dose Assessment Page 3 of 4

Table 1, continued.

Topics Open in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 Subsection Title 12.6.0 Health Physics Program 12.7.1 Plant Shielding (1I.B.2) 12.7.2 High Range Incontainment Monitor (1I.F.1(3))

12.7.3 Inplant Radioiodine Monitor (1II.D.3.3) 13.1.3 Plant Staff Organization 13.3.1 Introduction 13.3.2 Evaluation of the Emergency Plan 13.3.3 Conclusions 13.4.0 Review and Audit 13.5.1 Administrative Procedures 13.6.0 Physical Security Plan 15.2.0 Normal Operation and Anticipated Transients 15.2.1 Loss of Cooling Transients 15.2.3 Change in Coolant Inventory Transients 15.2.4 Reactivity and Power Distribution Anomalies 15.3.1 Loss-of-Coolant Accident 15.3.2 Steamline Break 15.3.3 Feedwater System Pipe Break 15.3.4 Reactor Coolant Pump Rotor Seizure 15.3.5 Reactor Coolant Pump Shaft Break 15.4.1 Loss-of-Coolant Accident 15.4.2 Main Steamline Break Outside of Containment 15.4.3 Steam Generator Tube Rupture 15.4.4 Control Rod Ejection Accident 15.4.5 Fuel-Handling Accident 15.4.6 Failure of Small Line Carrying Coolant Outside Containment 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures 16.0.0 Technical Specifications 18.1.0 General 18.2.0 Conclusions Page 4 of 4

Table 2.

Status of NUREG-0847 Review Topics Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

1.0.0 Introduction and General Discussion 1.1.0 Introduction 1.1.1 Metrication 1.1.2 Proprietary Information 1.1.4 Additionallnformation 1.2.0 General Design Description 1.3.0 Comparison With Similar Facility Designs 1.3.1 Comparison With the Sequoyah Nuclear Plant 1.3.2 Comparison With Other Facilities 1.4.0 Identification of Agents and Contractors 1.5.0 Summary of Principal Review Matters 1.6.0 Modifications to the Watts Bar Facility During the Course of NRC Review 1.7.0 Summary of Outstanding Issues 1.8.0 Confirmatory Issues 1.9.0 License Conditions 1.10.0 Unresolved Safety Issues 2.0.0 Site Envelope 2.1.0 Geography and Demography 2.1.1 Site Location and Description Yes 2.1.2 Exclusion Area Authority and Control Yes 2.1.3 Population Distribution No 2.1.4 Conclusions No 2.2.0 Nearby Industrial, Transportation, and Military Facilities 2.2.1 Transportation Routes No 2.2.2 Nearby Facilities No 2.2.3 Conclusions No 2.3.0 Meteorology 2.3.1 Regional Climatology Yes 2.3.2 Local Meteorology Yes 2.3.3 Onsite Meteorological Measurements Program Yes

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 1 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

2.3.4 Short-Term (Accident) Atmospheric Diffusion Estimates Yes 2.3.5 Long-Term (Routine) Diffusion Estimates Yes 2.4.0 Hydrologic Engineering 2.4.1 Introduction Yes 2.4.2 Hydrologic Description Yes 2.4.3 Flood Potential Yes 2.4.4 Local Intense Precipitation in Plant Area Yes 2.4.5 Roof Drainage Yes 2.4.6 Ultimate Heat Sink Yes 2.4.7 Groundwater Yes 2.4.8 Design Basis for Subsurface Hydrostatic Loading No 2.4.9 Transport of Liquid Releases No 2.4.10 Flooding Protection Requirements and Technical Specifications Yes 2.5.0 Geological, Seismological, and Geotechnical Engineering Yes 2.5.1 Geology Yes 2.5.2 Seismology Yes 2.5.3 Surface Faulting Yes 2.5.4 Stability of Subsurface Materials and Foundations Yes 2.5.5 Stability of Slopes Yes 2.5.6 Embankments and Dams Yes 2.6.0 References 3.0.0 Design of Structures, Components, Equipment, and Systems 3.1.0 Introduction 3.1.1 Conformance With General Design Criteria Yes 3.1.2 Conformance With Industry Codes and Standards Yes 3.2.0 Classification of Structures, Systems, and Components Yes 3.2.1 Seismic Qualification Yes 3.2.2 System Quality Group Classification No 3.3.0 Wind and Tornado Loadings 3.3.1 Wind Loading Yes 3.3.2 Tornado Loading Yes 3.4.0 Flood Level (Flood) Design

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 2 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?'

3.4.1 Flood Protection Yes 3.5.0 Missile Protection 3.5.1 Missile Selection and Description Yes 3.5.2 Structures, Systems, and Components To Be Protected From Externally Yes Generated Missiles 3.5.3 Barrier Design Procedures Yes 3.6.0 Protection Against the Dynamic Effects Associated with the Postulated No 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid No 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Yes Postulated Rupture of Piping 3.6.3 Leak-Before-Break Evaluation Procedures Yes 3.7.0 Seismic Design No 3.7.1 Seismic Input No 3.7.2 Seismic Analysis No 3.7.3 Seismic Subsystem Analysis No 3.7.4 Seismic Instrumentation Yes 3.8.0 Design of Seismic Category I Structures No 3.8.1 Steel Containment Yes 3.8.2 Concrete and Structural Steel Internal Structures Yes 3.8.3 Other Seismic Category I Structures No 3.8.4 Foundations Yes 3.9.0 Mechanical Systems and Components 3.9.1 Special Topics for Mechanical Components No 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment Yes 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and No 3.9.4 Control Rod Drive Systems Yes 3.9.5 Reactor Pressure Vessel Internals Yes 3.9.6 Inservice Testing of Pumps and Valves No 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical No 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment No

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 3 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

3.13.0 Threaded Fasteners - ASME Code Class 1, 2, and 3 [SRP TOG]

4.0.0 Reactor 4.1.0 Introduction 4.2.0 Fuel System Design 4.2.1 Description No 4.2.2 Thermal Performance No 4.2.3 Mechanical Performance No 4.2.4 Surveillance Yes 4.2.5 Fuel Design Conclusions No 4.3.0 Nuclear Design 4.3.1 Design Basis No 4.3.2 Design Description No 4.3.3 Analytical Methods No 4.3.4 Summary of Evaluation Findings No 4.4.0 Thermal-Hydraulic Design 4.4.1 Perfomance in Safety Criteria Yes 4.4.2 Design Bases No 4.4.3 Thermal-Hydraulic Design Methodology No 4.4.4 Operating Abnormalities No 4.4.5 Loose Parts Monitoring System No 4.4.6 Thermal-Hydraulic Comparison Yes 4.4.7 N-1 Loop Operation Yes 4.4.8 Instrumentation for Inadequate Core Cooling Detection (II.F.2) No 4.4.9 Summary and Conclusion No 4.5.0 Reactor Materials 4.5.1 Control Rod Drive Structural Materials Yes 4.5.2 Reactor Internals and Core Support Materials Yes 4.6.0 Functional Design oJ Reactivity Control Systems Yes 5.0.0 Reactor Coolant System and Connected Systems 5.1.0 Summary Description No 5.2.0 Integrity of Reactor Coolant Pressure Boundary 5.2.1 Compliance With Codes and Code Cases Yes

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 4 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?'

5.2.2 Overpressure Protection Yes 5.2.3 Reactor Coolant Pressure Boundary Materials Yes 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing No 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection No 5.2.6 Reactor Vessel and Internals Modelling 5.3.0 Reactor Vessel 5.3.1 Reactor Vessel Materials No 5.3.2 Pressure-Temperature Limits No 5.3.3 Reactor Vessel Integrity No 5.4.0 Component and Subsystem Design 5.4.1 Reactor Coolant Pumps Yes 5.4.2 Steam Generators Yes 5.4.3 Residual Heat Removal System No 5.4.4 Pressurizer Relief Tank Yes 5.4.5 Reactor Coolant System Vents (1I.B.1) Yes 6.0.0 Engineered Safety Features 6.1.0 Engineered Safety Features Materials 6.1.1 Metallic Materials Yes 6.1.2 Organic Materials Yes 6.1.3 Postaccident Emergency Cooling Water Chemistry Yes 6.2.0 Containment Systems 6.2.1 Containment Functional Design No 6.2.2 Containment Heat Removal Systems No 6.2.3 Secondary Containment Functional Design Yes 6.2.4 Containment Isolation System Yes 6.2.5 Combustible Gas Control Systems No 6.2.6 Containment Leakage Testing No 6.2.7 Fracture Prevention of Containment Pressure Boundary Yes 6.3.0 Emergency Core Cooling System Yes 6.3.1 System Design No 6.3.2 Evaluation No 6.3.3 Testing No

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 5 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?'

6.3.4 Performance Evaluation Yes 6.3.5 Conclusions No 6.4.0 Control Room Habitability No 6.5.0 Engineered Safety Feature (ESF) Filter Systems 6.5.1 ESF Atmosphere Cleanup Systems No 6.5.2 Fission Product Cleanup System Yes 6.5.3 Fission Product Control System Yes 6.5.4 Ice Condenser as a Fission Product Control System Yes 6.6.0 Inservice Inspection of Class 2 and 3 Components No 7.0.0 Instrumentation and Controls 7.1.0 Introd uction 7.1.1 General No 7.1.2 Comparison with Other Plants Yes 7.1.3 Design Criteria No 7.2.0 Reactor Trip System Yes 7.2.1 System Description No 7.2.2 Manual Trip Switches Yes 7.2.3 Testing of Reactor Trip Breaker Shunt Coils Yes 7.2.4 Anticipatory Trips Yes 7.2.5 Steam Generator Water Level Trip No 7.2.6 Conclusions No 7.3.0 Engineered Safety Features System No 7.3.1 System Description No 7.3.2 Containment Sump Level Measurement Yes 7.3.3 Auxiliary Feedwater Initiation and Control Yes 7.3.4 Failure Modes and Effects Analysis Yes 7.3.5 IE Bulletin 80-06 Yes 7.3.6 Conclusions No 7.4.0 Systems Required for Safe Shutdown 7.4.1 System Description Yes 7.4.2 Safe Shutdown from Auxiliary Control Room No 7.4.3 Conclusions Yes

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 6 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

7.5.0 Safety-Related Display Instrumentation 7.5.1 System Description Yes 7.5.2 Post-Accident Monitoring System No 7.5.3 IE Bulletin 79-27 Yes 7.5.4 Conclusions Yes 7.6.0 All Other Systems Required for Safety 7.6.1 System Description Yes 7.6.2 Residual Heat Removal System Bypass Valves Yes 7.6.3 Upper Head Injection Manual Control Yes 7.6.4 Protection Against Spurious Actuation of Motor-Operated Valves Yes 7.6.5 Overpressure Protection During Low Temperature Operation Yes 7.6.6 Valve Power Lockout Yes 7.6.7 Cold Leg Accumulator Valve Interlocks and Position Indication Yes 7.6.8 Automatic Switchover From Injection to Recirculation Mode Yes 7.6.9 Conclusions Yes 7.7.0 Control Systems Not Required for Safety 7.7.1 System Description Yes 7.7.2 Safety System Status Monitoring System Yes 7.7.3 Volume Control Tank Level Control System Yes 7.7.4 Pressurizer and Steam Generator Overfill Yes 7.7.5 IE Information Notice 79-22 Yes 7.7.6 Multiple Control System Failures Yes 7.7.7 Conclusions Yes 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation No 7.8.0 NUREG-0737 Items Yes 7.8.1 Relief and Safety Valve Position Indication (II.D.3) No 7.8.2 Auxiliary Feedwater System Initiation and Flow Indication (11.E.1.2) Yes 7.8.3 Proportional Integral Derivative Control Modification (11.K.3.9) Yes 7.8.4 Proposed Anticipatory Trip Modification (11.K.3.1 0) Yes 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (11.K.3.12) Yes 7.9.0 Data Communication Systems

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 7 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

8.0.0 Electric Power Systems 8.1.0 General Yes 8.2.0 Offsite Power System 8.2.1 Compliance With GDC 5 Yes 8.2.2 Compliance With GDC 17 No 8.2.3 Compliance With GDC 18 Yes 8.2.4 Evaluation Findings Yes 8.3.0 Onsite Power Systems Yes 8.3.1 Onsite AC Power System Compliance With GDC 17 No 8.3.2 Onsite DC System Compliance With GDC 17 Yes 8.3.3 Evaluation Findings No 8.4.0 Station Blackout 9.0.0 Auxiliary Systems Yes 9.1.0 Fuel Storage Facility 9.1.1 New Fuel Storage Yes 9.1.2 Spent Fuel Storage No 9.1.3 Spent Fuel Pool Cooling and Cleanup System No 9.1.4 Fuel Handling System No 9.2.0 Water Systems 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems No 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) No 9.2.3 Demineralized Water Makeup System Yes 9.2.4 Potable and Sanitary Water Systems Yes 9.2.5 Ultimate Heat Sink Yes 9.2.6 Condensate Storage Facilities Yes 9.3.0 Process Auxiliaries 9.3.1 Compressed Air System Yes 9.3.2 Process Sampling System No 9.3.3 Equipment and Floor Drainage System Yes 9.3.4 Chemical and Volume Control System Yes 9.4.0 Heating, Ventilation, and Air Conditioning Systems 9.4.1 Control Room Area Ventilation System Yes

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 8 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

9.4.2 Fuel Handling Area Ventilation System Yes 9.4.3 Auxiliary and Radwates Area Ventilation System Yes 9.4.4 Turbine Building Area Ventilation System Yes 9.4.5 Engineered Safety Features Ventilation System No 9.5.0 Other Auxiliary Systems 9.5.1 Fire Protection Yes 9.5.2 Communication Systems No 9.5.3 Lighting System Yes 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System No 9.5.5 Emergency Diesel Engine Cooling Water System Yes 9.5.6 Emergency Diesel Engine Starting Systems No 9.5.7 Emergency Diesel Engine Lubricating Oil System No 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System No 10.0.0 Steam and Power Conversion System 10.1.0 Summary Description Yes 10.2.0 Turbine Generator No 10.2.1 Turbine Generator Design Yes 10.2.2 Turbine Disc Integrity Yes 10.3.0 Main Steam Supply System Yes 10.3.1 Main Steam Supply System (up to and inclUding the Main Steam No 10.3.2 Main Steam Supply System Yes 10.3.3 Steam and Feedwater System Materials Yes 10.3.4 Secondary Water Chemistry No 10.4.0 Other Features 10.4.1 Main Condenser Yes 10.4.2 Main Condenser Evacuation System Yes 10.4.3 Turbine Gland Sealing System Yes 10.4.4 Turbine Bypass System No 10.4.5 Condenser Circulating Water System Yes 10.4.6 Condensate Cleanup System Yes 10.4.7 Condensate and Feedwater Systems Yes

"'Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 9 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?'

10.4.8 Steam Generator Blowdown System Yes 10.4.9 Auxiliary Feedwater System Yes 11.0.0 Radioactive Waste Management 11.1.0 Summary Description No 11.2.0 Liquid Waste Management Yes 11.3.0 Gaseous Waste Management Yes 11.4.0 Solid Waste Management System No 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems No 11.6.0 Evaluation Findings No 11.7.0 NUREG-0737Items No 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (1I.F.1(1) Yes and II.F.1(2))

11.7.2 Primary Coolant Outside Containment (111.0.1.1) No 12.0.0 Radiation Protection 12.1.0 General No 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably No 12.3.0 Radiation Sources No 12.4.0 Radiation Protection Design Features No 12.5.0 Dose Assessment No 12.6.0 Health Physics Program No 12.7.0 NUREG-0737 Items 12.7.1 Plant Shielding (II.B.2) No 12.7.2 High Range Incontainment Monitor (II.F.1(3)) No 12.7.3 Inplant Radioiodine Monitor (111.0.3.3) No 13.0.0 Conduct of Operations 13.1.0 Organizational Structure of the Applicant Yes 13.1.1 Management and Technical Organization Yes 13.1.2 Corporate Organization and Technical Support Yes 13.1.3 Plant Staff Organization No 13.2.0 Training 13.2.1 Licensed Operator Training Program Yes

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 10 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?'

13.2.2 Training for Nonlicensed Personnel Yes 13.3.0 Emergency Preparedness Evaluation 13.3.1 Introduction No 13.3.2 Evaluation of the Emergency Plan No 13.3.3 Conclusions No 13.4.0 Review and Audit No 13.5.0 Plant Procedures 13.5.1 Administrative Procedures No 13.5.2 Operating and Maintenance Procedures Yes 13.5.3 NUREG-0737 Items Yes 13.6.0 Physical Security Plan No 13.6.1 Physical Security Organization 13.6.2 Physical Barriers 13.6.3 Access Requirements 13.6.4 Detection Aids 13.6.5 Communications 13.6.6 Test and Maintenance Requirements 13.6.7 Response Requirements 13.6.8 Personnel Reliability 13.6.9 Land Vehicle Bomb Control Program 14.0.0 Initial Test Program Yes 15.0.0 Accident Analysis 15.1.0 General Discussion Yes 15.2.0 Normal Operation and Anticipated Transients No 15.2.1 Loss of Cooling Transients No 15.2.2 Increased Cooling Transients Yes 15.2.3 Change in Coolant Inventory Transients No 15.2.4 Reactivity and Power Distribution Anomalies No 15.2.5 Conclusions Yes 15.3.0 Limiting Accidents Yes 15.3.1 Loss-of-Coolant Accident No 15.3.2 Steamline Break No

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 11 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?'

15.3.3 Feedwater System Pipe Break No 15.3.4 Reactor Coolant Pump Rotor Seizure No 15.3.5 Reactor Coolant Pump Shaft Break No 15.3.6 Anticipated Transients Without Scram Yes 15.3.7 Conclusions Yes 15.4.0 Radiological Consequences of Accidents Yes 15.4.1 Loss-of-Coolant Accident No 15.4.2 Main Steamline Break Outside of Containment No 15.4.3 Steam Generator Tube Rupture No 15.4.4 Control Rod Ejection Accident No 15.4.5 Fuel-Handling Accident No 15.4.6 Failure of Small Line Carrying Coolant Outside Containment No 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures No 15.5.0 NUREG-0737 Items 15.5.1 Thermal Mechanical Report (1I.K.2.13) Yes 15.5.2 Voiding in the Reactor Coolant System During Transients (1I.K.2.17) Yes 15.5.3 Installation and Testing of Automatic Power-Operated Relief Valve Isolation Yes System (1I.K.3.1), Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (1I.K.3.2) 15.5.4 Automatic Trip of Reactor Coolant Pumps (11.K.3.5) Yes 15.5.5 Small-Break LOCA Methods (11.K.3.30) and Plant-Specific Calculations Yes (11.K.3.31 )

15.6.0 Relative Risk of Low Power Operation Yes 16.0.0 Technical Specifications No 17.0.0 Quality Assurance 17.1.0 General Yes 17.2.0 Organization Yes 17.3.0 Quality Assurance Program Yes 17.4.0 Conclusions Yes 17.6.0 Maintenance Rule 18.0.0 Control Room Design Review 18.1.0 General No 18.2.0 Conclusions No

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is proVided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 12 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

19.0.0 Report of the Advisory Committee on Reactor Safeguards 20.0.0 Common Defense and Security 21.0.0 Financial Qualifications 22.0.0 Financial Protection and Indemnity Requirements 22.1.0 General 22.2.0 Preoperational Storage of Nuclear Fuel 22.3.0 Operating Licenses 23.0.0 Conclusions 24.0.0 Overall Assessment of the Quality of Construction, Operational Readiness, and Quality Assurance Effectiveness of Watts Bar Unit 1 24.1.0 Introduction 24.1.1 Purpose of the Assessment 24.1.2 Organization of the Chapter 24.2.0 Historical Overview of Construction Problems 24.3.0 Employee Concerns Programs 24.3.1 The Employee Concerns Special Program 24.3.2 Concerns Resolution Program 24.3.3 Conclusion 24.4.0 Recovery Plan 24.4.1 Nuclear Performance Plans 24.4.2 Corrective Action Program Plans and Special Programs 24.4.3 Conclusion 24.5.0 Significant Regulatory Issues 24.5.1 Welding 24.5.2 Electrical Cable Damage 24.5.3 Quality Assurance Records 24.5.4 Conclusion 24.6.0 Additional Activities 24.6.1 NRC Corrective Actions to Improve Its Regulatory Oversight 24.6.2 Special Inspections 24.6.3 Conclusion 24.7.0 Construction Stopped

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 13 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

24.7.1 Corrective Action Problems After Construction Restart 24.7.2 Strengthening the QA Organization 24.7.3 Conclusion 24.8.0 Integrated Assurance of Acceptable Construction Quality 24.8.1 Preoperational Testing 24.8.2 Program for Assurance of Completion and Assurance of Quality 24.8.3 TVA's Integrated Design Inspection 24.8.4 Licensing Review 24.8.5 Reconstitution of Construction Inspection Program 24.8.6 Conclusion 24.11.0 TVA's Operational Readiness 24.11.1 TVA's Activities To Demonstrate Operational Readiness 24.11.2 NRC's Activities to Substantiate Operational Readiness 24.11.3 Lessons Learned From Other NTOLs Applied to Watts Bar Unit 1 24.11.4 Conclusion 24.12.0 NRC's Overall Assessment 24.12.1 TVA's Employee Concern Program 24.12.2 Construction Quality of Watts Bar Unit 1 24.12.3 TVA's Qualifications to Operate Watts Bar Unit 1 Safely 24.12.4 Conclusion 25.0.0 Nuclear Performance Plan 25.1.0 Introduction 25.2.0 Corrective Actions 25.2.1 Cable Issues 25.2.2 Cable Tray and Tray Supports 25.2.3 Design Baseline and Verification Program 25.2.4 Electrical Conduit and Conduit Support 25.2.5 Electrical Issues 25.2.6 Equipment Seismic Qualification 25.2.7 Fire Protection 25.2.8 Hanger and Analysis Update Program 25.2.9 Heat Code Traceability

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 14 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

25.2.10 Heating, Ventilation, and Air-Conditioning Duct and Duct Supports 25.2.11 Instrument Lines 25.2.12 Prestart Test Program 25.2.13 QA Records 25.2.14 Q-List 25.2.15 Replacement Items Program (Piece Parts) 25.2.16 Seismic Analysis 25.2.17 Vendor Information Program 25.2.18 Welding 25.3.0 Special Programs 25.3.1 Concrete Quality Program 25.3.2 Containment Cooling 25.3.3 Detailed Control Room Design Review 25.3.4 Environmental Qualification Program 25.3.5 Master Fuse List 25.3.6 Mechanical Equipment Qualification 25.3.7 Microbiologically Induced Corrosion (MIC) 25.3.8 Moderate Energy Line Break Flooding 25.3.9 Radiation Monitoring System 25.3.10 Soil Liquefaction 25.3.11 Use-as-is CAQs 25.4.0 Implementation, Verification, and Closure of Corrective Actions 25.4.1 Corrective Action Program Plans and Special Programs 25.4.2 Quality Verification Process 25.5.0 Management and Organization 25.5.1 Introduction 25.5.2 Organizational and Management Improvements 25.5.3 Conclusions 25.6.0 Operational Readiness 25.7.0 Employee Concerns 25.8.0 Allegations 26.0.0 Generic Issues

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 15 of 16

Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in Subsection Title NUREG-0847?*

27.0.0 NUREG-0737 TMI Action Items 28.0.0 Other Regulatory Topics 28.1.0 License Conditions 28.2.0 Orders Appendix A - Chronology of Radiological Review of Watts Bar Nuclear Plant Units 1 and 2, Operating License Review Appendix B - Bibliography Appendix C - Nuclear Regulatory Commission Unresolved Safety Issues Appendix D - Evaluation of the Applicant's Control Room Design Appendix E - Principal Contributors Appendix F - Abbreviations

• Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements. No status is provided for administrative or descriptive topics.

Unresolved items are shown in bold italics. Page 16 of 16

October 10, 2008 A. Bhatnagar -2 Using the results of NRC's assessment, TVA should revise its regulatory framework status to match the staff's current reconciliation and assessment. In particular, TVA should maintain the list of open items from Table 2 and then update the information as actions are completed, proper documentation submitted to the NRC staff for review, and the NRC staff documents its review and acceptance in an SER Supplement. If TVA or the NRC staff determines that a previously reviewed and completed item needs to be re-opened, TVA should add the item to the list and highlight this action as having occurred. TVA is also requested to provide an update to the status, including references to TVA and NRC supporting documentation, at least every 6 months. The NRC staff will use this information to verify the completion of open actions and to coordinate the need for independent validation of implementation through inspections.

If you have questions regarding the staff's assessment or actions requested of TVA, please contact me at 301-415-1457.

Sincerely, lRAI Patrick D. Milano, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391

Enclosures:

Tables 1 and 2, Regulatory Framework Status for TVA Watts Bar Unit 2 cc w/encls: See next page DISTRIBUTION:

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DATE 10/10108 101 '0 108 101 10108 OFFICIAL RECORD COpy