ML090570741

NUREG-0847, Supp. 21, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2

ML090570741
Person / Time
Site:	Watts Bar
Issue date:	02/28/2009
From:	Milano P, Raghavan L Watts Bar Special Projects Branch
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NUREG-0847 S6
Download: ML090570741 (52)

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• U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment NUREG-0847 Supplement 21 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391 Tennessee Valley Authority Office of Nuclear Reactor Regulation AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material As of November 1999, you may electronically access NUREG-series publications and other NRC records at NRC'S Public Electronic Reading Room at http://www.

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• U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment NUREG-0847 Supplement 21 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391 Tennessee Valley Authority.

Manuscript Completed:

February 2009 Date Published:

February 2009 Prepared by L. Raghavan P.D. Milano Office of Nuclear Reactor Regulation

ABSTRACT This report supplements the safety evaluation report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1 985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), Supplement No. 15 (June 1995), Supplement No. 16 (September 1995), Supplement No. 17 (October 1995), Supplement No. 18 (October 1995), Supplement No. 19 (November 1995) and Supplement No. 20 (February 1996)issued by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission (NRC) with respect to the application filed by the Tennessee Valley Authority (TVA), as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant (WBN) Units 1 and 2 (Docket Nos. 50-390 and 50-391).In Supplement No. 20 the NRC staff concluded that WBN Unit 1 met all applicable regulations and guidance as stated in the SER and supplements.

Based on satisfactory findings from all applicable inspections, on February 7, 1996, the NRC issued a full-power operating license to WBN Unit 1 to authorize operation up to 100-percent power.In this and future Supplements to the SER, the staff will document its evaluation of TVA's application for a license to operate WBN Unit 2.This supplement provides information specific to the operating license review for WBN Unit 2 regarding the status of the items remaining for resolution, which were outstanding at the time that TVA deferred construction of Unit 2 and were not evaluated and resolved as part of the licensing of WBN Unit 1.iii

TABLE OF CONTENTS Paqe ABSTRACT ..........................

...............................

iii ABBREVIATIONS

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... vii 1 INTRODUCTION AND DISCUSSION

........ .................

... 1-1 1.1 Introduction

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....1-1 1.7 Summary of Outstanding Issues ....... .................

....1-3 1.13 Implementation of Corrective Action Programs and Special Programs 1-19 1.13.1 Corrective Action Programs .........

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...1-21 1.13.2 Special Programs ..........

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...1-22 1.14 Implementation of Applicable Bulletin and Generic Letter Requirements 1-22 17 QUALITY ASSURANCE

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...17-1 17.3 Quality Assurance Program ..........

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...17-1 17.3.1 Authorization to Transfer Code Symbol Stamps ...........

...17-1 APPENDIX A CHRONOLOGY OF RADIOLOGICAL REVIEW OF WATTS BAR. ...A-1 NUCLEAR PLANT, UNIT 2, OPERATING LICENSE REVIEW V

ABBREVIATIONS AC alternating current ADAMS Agencywide Documents Access and Management System AMSAC anticipated transient without scram mitigation system actuation circuitry ASME American Society of Mechanical Engineers.ATWS anticipated transient without scram BL Bulletin BWR boiling-water reactor CAP corrective action program CFR Code of Federal Regulations DC direct current ECCS emergency core cooling system ESF engineered safety feature FSAR final safety analysis report GDC general design criterion GL generic letter IE Office of Inspection and Enforcement IEB Office of Inspection and Enforcement Bulletin LOCA loss-of-coolant accident LTOP low-temperature overpressure protection NPP Nuclear Performance Plan NRC Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulation NUREG report prepared by NRC staff OL operating license PORV power-operated relief valve PWR pressurized-water reactor QA quality assurance RPV reactor pressure vessel RV relief valve SER safety evaluation report SG steam generator SP special program SRP Standard Review Plan SSER Supplement to the SER SV safety valve TMI Three Mile Island TS technical specification TVA Tennessee Valley Authority WBN Watts Bar Nuclear Plant WBNPP Watts Bar Nuclear Performance Plan vii

1 INTRODUCTION AND DISCUSSION 1.1 Introduction The Watts Bar Nuclear Plant (WBN or Watts Bar) is owned by the Tennessee Valley Authority (TVA) and is located in southeastern Tennessee approximately 50 miles northeast of Chattanooga.

The facility consists of two Westinghouse-designed four-loop pressurized-water reactors (PWRs) within ice condenser containments.

In June 1982, the Nuclear Regulatory Commission staff (NRC staff or staff) issued a safety evaluation report (SER), NUREG-0847, "Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant Units 1 and 2," regarding the application by the TVA for licenses to operate WBN Units 1 and 2. The SER was followed by SER Supplement No. 1 (SSER 1, September 1982), Supplement No. 2 (SSER 2, January 1984), Supplement No. 3 (SSER 3, January 1985), and Supplement No. 4 (SSER 4, March 1985). After Supplement No. 4 (SSER 4) was issued, Watts Bar licensing activities were put on hold because of problems identified at TVA plants.A large number of deficiencies were identified shortly before the WBN Unit 1 operating license (OL) was expected to be issued. As a result, the NRC sent a letter to TVA on September 17, 1985, requesting information under Section 50.54(f) of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) on TVA's plans to address the deficiencies for its operating and construction activities at Watts Bar and TVA's other nuclear facilities.

In response to this letter, TVA developed a nuclear performance plan (NPP) to address corporate and site-specific issues relating to a wide variety of material, design, and programmatic deficiencies.

At about the same time, TVA suspended construction of WBN Unit 2, with major structures in place and equipment installed, while it focused on completing WBN Unit 1.TVA submitted its NPP to the NRC on November 1, 1985. The NRC staff issued its safety evaluation of the revised NPP, through Revision 4, in July 1987 as NUREG-1232, Volume 1,"Safety Evaluation Report on Tennessee Valley Authority:

Revised Corporate Nuclear Performance Plan." In addition to its corporate NPP, TVA prepared separate plans to address site-specific problems at each of its nuclear plants.The NRC staff reviewed components of the NPP for WBN Unit 1 and, as documented in NUREG-1232, Volume 4, "Safety Evaluation Report on Tennessee Valley Authority:

Watts Bar Nuclear Performance Plan, Watts Bar Unit 1" (January 1990), endorsed the general approaches of various corrective actions. The NRC staff determined that when fully implemented, the proposed corrective actions should address the identified deficiencies for Unit 1.The NRC staff documented the satisfactory resolution of NPP topics for WBN Unit 1 in the later supplements to NUREG-0847 (Supplements 5 through 20). In Supplement No. 20, the staff concluded that WBN Unit 1 met all applicable regulationsand guidance as stated in the SER and supplements, and based on satisfactory findings from all applicable inspections, the NRC issued an OL to WBN Unit 1 on February 7, 1996, authorizing operation up to 100-percent power (full-power OL).On August 3, 2007, TVA notified the Director of the Office of Nuclear Reactor Regulation (NRR)of its intention to complete construction activities at WBN Unit 2. On December 3, 2007, TVA informed the NRC that it was resuming unrestricted construction activities under the existing construction permit and would request an OL, pursuant to 10 CFR Part 50, "Domestic Licensing 1-1 of Production and Utilization Facilities." To ensure operational fidelity between the units and, at the same time, demonstrate that WBN Unit 2 complies with applicable NRC regulatory requirements.

TVA will align the licensing and design bases of WBN Units 1 and 2 to the fullest extent practicable.

Recognizing the benefit of operational fidelity between the two WBN units and safe operation of WBN unit 1 since 1996, the Commission in staff requirements memorandum SECY-07-0096, "Staff Requirements

-Possible Reactivation of Construction and Licensing Activities for the Watts Bar Nuclear Plant Unit 2," dated July 25, 2007, directed the staff to use the current licensing basis for Unit 1 as the reference basis for the review and licensing of Unit 2.In its review. of TVA's operating licensing application, the NRC staff will use the set of topics covered in (1) SER (NUREG-0847) and its supplements through No. 20, (2) NPP issues in NUREG-1232, Volume 4, (3) the WBN Final Safety Analysis Report (FSAR) through amendment No. 91 (FSAR version approved for both Units 1 and 2), and (4) NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants" (SRP). The NRC staff based its numbering for the review topics is based on NUREG-0847, adding new subsections as needed to incorporate additional topics from the NPP, SRP, and generic issues.For convenience of tracking and reporting, it numbered the topics at the subsection level (i.e., X.Y.Z, where X is the chapter number, Y is the section number, and Z is the subsection number). For example, the "Residual Heat Removal" review topic is subsection 5.4.3 in the table of contents.In addition to the guidance in the SRP, the NRC staff issues generic requirements or recommendations in the form of technical reports, bulletins, and generic letters (GLs). Each of these documents carries its own applicability, work scope, and acceptance criteria; some of which are applicable to Watts Bar Unit 2. This SSER also addresses the review and implementation status of applicable generic issues.As noted above, the NRC staff wrote this SER and its supplements to agree with the format and scope outlined in the SRP (NUREG-0800).

Issues raised during the SRP review that were not closed out when the SER was published were categorized as outstanding issues, confirmatory issues, and proposed license conditions (see Sections 1.7, 1.8, and 1.9, respectively).

Each of the following sections and appendices of this supplement is numbered the same as the section or appendix of the SER that is being updated, and the discussions are supplementary to, and not in lieu of, the discussion in the SER, unless otherwise noted. For example, Appendix A continues the chronology of the safety review and Appendix E continues to list the principal contributors to this supplement.

New appendices will be added as necessary.

Chapters 1 through 23 were assigned from NUREG-0847 (SER). The staff has added chapters addressing the overall assessment of the facility, NPP, generic issues, action items from NUREG-0737, "Clarification of TMI [Three Mile Island] Action Review Standard Requirements," issued November 1980, and other regulatory topics. These items appear in the SER table of contents as chapters 24 through 27. Additional chapters may be included later.In this and future SSERs, the staff will document its evaluation of TVA's application for a license to operate WBN Unit 2.1-2 The Project Manager is Patrick D. Milano, who may be contacted by calling (301) 415-1457 or by writing to the following address: Mr. Patrick D. Milano U.S. Nuclear Regulatory Commission Mail Stop O-8H4 Washington, D.C. 20555 1.7 Summary of Outstanding Issues By letters dated January 29 and March 13, 2008, TVA submitted its framework for the completion of construction and licensing activities for WBN Unit 2. TVA identified the Unit 2 licensing basis that was reviewed and approved concurrent with the WBN Unit 1 CL review process. The NRC staff documented its previous review of WBN Unit 1, and a portion for Unit 2, in NUREG-0847, through Supplement No. 20.The NRC staff made an initial assessment of the status presented by TVA and reviewed the information in the SER and its supplements to independently determine whether the topic sectionshad been previously approved and resolved for WBN Unit 2. By letter dated May 8, 2008, to TVA, 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 OL review scope.The NRC staff found that many of the existing licensing review topics had already been addressed.

The staff also identified certain differences between the NRC and TVA scoping assessments.

On June 16, 2008, TVA provided additional information to address these differences 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 and completed its assessment of the regulatory framework for WBN Unit 2 CL review. The staff documented the detailed results of its overall assessment of the regulatory framework in a letter dated October 10, 2008.The staff's overall assessment of the regulatory framework is summarized below with the relevant document in which the issue was last addressed shown in parentheses.

In its future submittals or amendments to the FSAR, TVA should address the topics identified as open. The staff will review the open topics using the WBN Unit 1 current licensing basis as its reference.

The staff will document the results of its review in future SER supplements.

It should be noted that, although many of the topic areas may have been adequately documented and are considered closed, the NRC staff recognizes that there may be circumstances that could result in the need to reopen a previously closed topic.Issue Status Section (1) Site Envelope 2.0.0 (2) Geography and Demography 2.1.0 (3) Site Location and Description Resolved (SER) 2.1.1 (4) Exclusion Area Authority and Control Resolved (SER) 2.1.2 (5) Population Distribution Open (NRR) (SER) 2.1.3 (6) Conclusions Open (NRR) (SER) 2.1.4 (7) Nearby Industrial, Transportation, and 2.2.0 Military Facilities 1-3 Issue Status (8) Transportation Routes (9) Nearby Facilities (10) Conclusions (11) Meteorology (12) Regional Climatology (13) Local Meteorology (14) Onsite Meteorological Measurements Program (15) Short-Term (Accident)

Atmospheric Diffusion Estimates (16) Long-Term (Routine)

Diffusion Estimates (17) Hydrologic Engineering (18) Introduction (19) Hydrologic Description (20) Flood Potential (21) Local Intense Precipitation in Plant Area (22) Roof Drainage (23) Ultimate Heat Sink (24) Groundwater (25) Design Basis for Subsurface Hydrostatic Loading (26) Transport of Liquid Releases (27) Flooding Protection Requirements (28) Geological, Seismological, and Geotechnical Engineering (29) Geology (30) Seismology (31) Surface Faulting (32) Stability of Subsurface Materials and Foundations (33) Stability of Slopes (34) Embankments and Dams (35) References (36) Design of Structures, Components, Equipment, and Systems (37) Introduction (38) Conformance With General Design Criteria (39) Conformance With Industry Codes and Standards (40) Classification of Structures, Systems and Components Open (NRR)Open (NRR)Open (NRR)Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Open (NRR)Open (NRR)Open (Inspection)

Resolved Resolved (SER)(SER)(SER)(SER)(SER)(SER)(SER)(SSER 14)(SER)(SSER 14)(SER)(SER)(SER)(SER)(SER)(SER)(SER)(SER)(SSER 3)(SER)(SER)(SER)(SER)(SER)(SER)(SER)(SSER 3)(SSER 9)(SSER 11)(SER)(SER)(SER)(SER)(SSER 14)Section 2.2.1 2.2.2 2.2.3 2.3.0 2.3.1 2.3.2 2.3.3 2.3.4 2.3.5 2.4.0 2.4.1 2.4.2 2.4.3 2.4.4 2.4.5 2.4.6 2.4.7 2.4.8 2.4.9 2.4.10 2.5.0 2.5.1 Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved 2.5.2 2.5.3 2.5.4 2.5.5 2.5.6 2.6.0 3.0.0 3.1.0 3.1.1 3.1.2 3.2.0 1-4 Issue Status Section (41) Seismic Classifications (42) System Quality Group Classification (43) Wind and Tornado Loadings (44) Wind Loading (45) Tornado Loading (46) Flood Level (Flood) Design (47) Flood Protection (48) Missile Protection (49) Missile Selection and Description (50) Structures, Systems, and Components to be Protected from Externally Generated Missiles (51) Barrier Design Procedures (52) Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping (53) Plant Design for Protection Against Postulated Piping Failures in Fluid System Outside Containment (54) Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping (55) Leak-Before-Break Evaluation Procedures (56) Seismic Design Resolved Open (NRR)Resolved Resolved Resolved Resolved Resolved Resolved Open (NRR)Open (NRR)Resolved Resolved Open (NRR)Open (NRR)(SER)(SSER (SSER (SSER (SSER (SER)(SSER (SSER (SSER (SER)(SER)(SER)3.2.1 3)5)6)8)3)7)9)(SER)(SSER 9)(SSER 14)(SER)(SSER 2)(SER)(SER)(SSER 6)(SSER 11)(SER)(SSER 14)(SER)(SSER 14)(SSER 5)(SSER 12).(SER)(SSER 6)(SER)(SSER 6)(SSER 9)(SSER 16)(SER)(SSER 6)(SSER 8)(SSER 11)(SSER 16)3.2.2 3.3.0 3.3.1 3.3.2 3.4.0 3.4.1 3.5.0 3.5.1 3.5.2 3.5.3 3.6.0 3.6.1 3.6.2 3.6.3 3.7.0 3.7.1 3.7.2 (57) Seismic Input (58) Seismic Analysis Open (NRR)1-5 Issue Status Section (59) Seismic Subsystem Analysis (60) Seismic Instrumentation (61) Design of Seismic Category I Structures (62) Steel Containment (63) Concrete and Structural Steel Internal Structures (64) Other Seismic Category I Structures (65)(66)(67)Foundations Mechanical Systems and Components Special Topics for Mechanical Components (68) Dynamic Testing and Analysis of Systems, Components, and Equipment (69) ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures (70) Control Rod Drive Systems (71) Reactor Pressure Vessel Internals (72) Inservice Testing of Pumps and Valves (73) Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment.

Open (NRR)Resolved Open (NRR)Resolved Resolved Open (NRR)Resolved Open (NRR)Resolved Open (NRR)Resolved Resolved Open (NRR)Open (NRR)Open (NRR)(SER)(SSER 6)(SSER 7)(SSER 8)(SSER 9)(SSER 12)(SER)(SER)(SSER 9)(SER)(SSER 3)(SER)(SSER 7)(SER)(SSER 14)(SSER 16)(SER)(SER)(SSER 6)(SSER 13)(SER)(SSER 14)(SER)(SSER 3)(SSER 4)(SSER 6)(SSER 7)(SSER 8)(SSER 15)(SER)(SER)(SER)(SSER 5)(SSER 12)(SSER 14)(SSER 18)(SSER 20)(SER)(SSER 1)(SSER 3)(SSER 4)(SSER 5)(SSER 6)(SSER 8)(SSER 9)(SSER 15)3.7.3 3.7.4 3.8.0 3.8.1 3.8.2 3.8.3 3.8.4 3.9.0 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 2 3.10.0 3.11.0 (74)Environmental Qualification of Mechanical and Electrical Equipment 1-6 Issue Status Section 3.13.0 (75) Threaded Fasteners

-ASME Code Class 1, 2, and 3 (76)(77)(78)(79)(80)Reactor Introduction Fuel System Design Description Thermal Performance (81) Mechanical Performance (82) Surveillance (83) Fuel Design Considerations (84) Nuclear Design (85) Design Basis (86) Design Description (87) Analytical Methods (88) Summary of Evaluation Findings (89) Thermal-Hydraulic Design (90) Performance in Safety Criteria (91) Design Bases (92) Thermal-Hydraulic Design Methodology (93) Operating Abnormalities (94) Loose Parts Monitoring System (95) Thermal-Hydraulic Comparison (96) N-1 Loop Operation (97) Instrumentation for Inadequate Core Cooling Detection (TMI Action Item II.F.2)Open (NRR)Open (NRR)Open (NRR)Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (NRR)Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Resolved Open (Inspection)

Open (NRR)(SER)(SSER 13)(SER)(SSER 2)(SER)(SSER 2)(SSER 10)(SSER 13)(SER)(SSER 2)(SER)(SER)(SSER 13)(SER)(SSER 13)(SSER 15)(SER)(SSER 13)(SER)(SSER 13)(SER)(SER)(SSER 12)(SER)(SSER 6)(SSER 8)(SSER 12)(SSER 13)(SSER 16)SER dated 6/13/89 (SER)(SSER 13)(SER)(SSER 3)(SSER 5)(SSER 16)(SER)(SER)(SER)(SSER 10)4.0.0 4.1.0 4.2.0 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 4.3.0 4.3.1 4.3.2 4.3.3 4.3.4 4.4.0 4.4.1 4.4.2 4.4.3 4.4.4 4.4.5 4.4.6 4.4.7 4.4.8 1-7 Issue Status (98) Summary and Conclusion (99) Reactor Materials (100) Control Rod Drive Structural Materials (101) Reactor Internals and Core Support Materials (102) Functional Design of Reactivity Control Systems (103) Reactor Coolant System and Connected Systems (104) Summary Description (105) Integrity of Reactor Coolant Pressure Boundary (106) Compliance with Codes and Code Cases (107) Overpressurization Protection (108) Reactor Coolant Pressure Boundary Materials (109) Reactor Coolant System Pressure Boundary Inservice Inspection and Testing (110) Reactor Coolant Pressure Boundary Leakage Detection Open (NRR)Resolved Resolved Resolved Open (NRR)Resolved Resolved Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (NRR)Resolved Resolved Open (NRR)(SER)(SER)(SER)(SER)(SER)(SSER (SSER (SER)(SER)(SSER (SSER (SER)5)6)2)15)(111)(112)(113)Reactor Vessel and Internals Modeling Reactor Vessel Reactor Vessel Materials (114) Pressure-Temperature Limits (SER)(SSER 10)(SSER 12)(SSER 16)(SER)(SSER 9)(SSER 11)(SSER 12)(SER)(SSER 11)(SSER 14)(SER)(SSER 16)(SER)(SER)(SER)(SSER 1)(SSER 4)(SER)(SSER 2)(SSER 5)(SSER 10)(SSER 11)(SER)Section 4.4.9 4.5.0 4.5.1 4.5.2 4.6.0 5.0.0 5.1.0 5.2.0 5.2.1 5.2.2 5.2.3 5.2.4 5.2.5 5.2.6 5.3.0 5.3.1 5.3.2 5.3.3 5.4.0 5.4.1 5.4.2 5.4.3 5.4.4 (115)(116)(117)(118)Reactor Vessel Integrity Component and Subsystem Design Reactor Coolant Pumps Steam Generators (119) Residual Heat Removal System (120) Pressurizer Relief Tank Resolved 1-8 Issue Status Section (121) Reactor Coolant System Vents (TMI Action Item II.B.1)(122)(123)(124)(125)(126)(127)(128)Engineered Safety Features Engineered Safety Feature Materials Metallic Materials Organic Materials Postaccident Emergency Cooling Water Chemistry Containment Systems Containment Functional Design (129) Containment Heat Removal Systems (130) Secondary Containment Functional Design (131) Containment Isolation Systems (132) Combustible Gas Control Systems (133) Containment Leakage Testing (134) Fracture Prevention of Containment Pressure Boundary (135) Emergency Core Cooling System (136) System Design Open (Inspection)

Resolved Resolved Resolved Open (NRR)Open (NRR)Resolved Open (Inspection)

Open (NRR)Open (NRR)Resolved Resolved Open (NRR)Open (NRR)Open (NRR)Resolved Open (NRR)(SER)(SSER (SSER (SER)(SER)(SER)(SER)(SSER 3)(SSER 5)(SSER 7)(SSER 12)(SSER 14)(SSER 15)(SER)(SSER 7)(SER)(SSER 16)(SER)(SSER 3)(SSER 5)(SSER 7)(SSER 12)(SER)(SSER 4)(SSER 5)(SSER 8)(SER)(SSER 4)(SSER 5)(SSER 19)(SER)(SSER 4)(SER)(SER)(SSER 6)(SSER 7)(SSER 11)(SER)(SSER 5)(SER)(SSER 2)(SSER 9)(SER)(SER)2)12)5.4.5 6.0.0 6.1.0 6.1.1 6.1.2 6.1.3 6.2.0 6.2.1 6.2.2 6.2.3 6.2.4 6.2.5 6.2.6 6.2.7 6.3.0 6.3.1 6.3.2 6.3.3 6.3.4 6.3.5 (137)Evaluation (138) Testing (139)(140)Performance Evaluation Conclusions 1-9 Issue Status Section (141) Control Room Habitability (142) Engineered Safety Feature (ESF) Filter Systems (143) ESF Atmosphere Cleanup Systems (144) Fission Product Cleanup System (145) Fission Product Control System (146) Ice Condenser as a Fission Product Cleanup System (147) Inservice Inspection of Class 2 and 3 Components (148)(149)(150)(151)(152)(153)(154)(155)(156)(157)(158)Instrumentation and Controls Introduction General Comparison with Other Plants Design Criteria Reactor Trip System System Description Manual Trip Switches Testing of Reactor Trip Breaker Shunt Coils Anticipatory Trips Steam Generator Water Level Trip Open (NRR)Open (NRR)Resolved Resolved Resolved Open (NRR)Open (NRR)Resolved Open (NRR)Resolved Open (NRR)Resolved Resolved Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Resolved Resolved Resolved Open (Inspection)(SER)(SSER 5)(SER)(SER)(SER)(SER)(SSER 10)(SSER 15)(SER)(SSER 13)(SSER 16)(SER)(SER)(SSER 4)(SSER 15)(SER)(SER)(SSER 13)(SSER 15)(SER)(SER)(SER)(SER)(SSER 2)(SSER 14)(SER)(SSER 13)(SER)(SSER 13)(SER)(SSER 13)(SSER 14)(SER)(SSER 2)(SER)(SER)(SER)(SSER 3)(SER)(SSER (SSER (SSER (SSER 5)11)16)18)6.4.0 6.5.0 6.5.1 6.5.2 6.5.3 6.5.4 6.6.0 7.0.0 7.1.0 7.1.1 7.1.2 7.1.3 7.2.0 7.2.1 7.2.2 7.2.3 7.2.4 7.2.5 7.2.6 7.3.0 7.3.1 7.3.2 7.3.3.7.3.4 7.3.5 (159) Conclusions (160) Engineered Safety Features System (161) System Description (162) Containment Sump Level Measurement (163)(164)(165)Auxiliary Feedwater Initiation and Control Failure Modes and Effects Analysis IE Bulletin 80-06 1-10 Issue Status (166) Conclusions (167)(168)(169)(170)(171)(172)(173)Systems Required for Safe Shutdown System Description Safe Shutdown from Auxiliary Control Room Conclusions Safety-Related Display Instrumentation

System Description

Post-accident Monitoring System (174) IE Bulletin 79-27 (175)Conclusions (176) All Other Systems Required for Safety (177) System Description (178) Residual Heat Removal System Bypass Valves (179) Upper Head Injection Manual Control (180) Protection Against Spurious Actuation of Motor-Operated Valves (181) Overpressure Protection during Low Temperature Operation (182) Valve Power Lockout (183) Cold Leg Accumulator Valve Interlocks and Position Indication (184) Automatic Switchover From Injection to Recirculation Mode (185) Conclusions Open (NRR)Resolved Open (NRR)Resolved Resolved Open (NRR)Open (Inspection)

Open (Inspection)

Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved Open (NRR)Resolved (SER)(SER)(SSER (SSER (SSER (SSER (SER)7)9)14)15)(SER)(SER)(SER)(SER)(SER)(SER)(SSER 4)(SER)(SER)(SER)(SER)(SSER 4)(SER)(SER)(SSER 7)(SSER 13)(SER)(SER)(SER)(SER)(SER)(SSER 9)(SSER 14)(SER)(SER)(SSER 13)(SER)(SER)(SSER 7)(SER)Section 7.3.6 7.4.0 7.4.1 7.4.2 7.4.3 7.5.0 7.5.1 7.5.2 7.5.3 7.5.4 7.6.0 7.6.1 7.6.2 7.6.3 7.6.4 7.6.5 7.6.6 7.6.7 7.6.8 7.6.9 7.7.0 7.7.1 7.7.2 7.7.3 7.7.4 7.7.5 7.7.6 7.7.7 7.7.8 7.8.0 (186)(187)(188)Control Systems Not Required for Safety System Description Safety System Status Monitoring System (189) Volume Control Tank Level Control System (190) Pressurizer and Steam Generator Overfill (191) IE Information Notice 79-22 (192) Multiple Control System Failures (193) Conclusions (194) Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)(195) NUREG-0737 Items 1-11 Issue Status Section (196) Relief and Safety Valve Position Indication (TMI Action Item ll.D.3)(197) Auxiliary Feedwater System Initiation and Flow Indication (TMI Action Item II.E.1.2)(198) Proportional Integral Derivative Control Modification (TMI Action Item II.K.3.9)(199) Proposed Anticipatory Trip Modification (TMI Action Item II.K.3.10)

(200) Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (TMI Action Item II.K.3.12)

(201) Data Communication Systems (202) Electric Power Systems.(203) General (204) Offsite Power System (205) Compliance with GDC 5 (206) Compliance with GDC 17 (207) Compliance with GDC 18 (208) Evaluation Findings (209) Onsite Power Systems (210) Onsite AC Power System Compliance with GDC 17 (211) Onsite DC System Compliance with GDC 17 Open (NRR)Open (Inspection)

Open (Inspection)

Open (Inspection)

Resolved Resolved Resolved Open (NRR)Resolved Resolved Resolved Open (NRR)Resolved Open (NRR)(SER)(SSER 5)(SSER 14)(SER)(SER)(SER)(SSER 4)(SER)(SER)(SER)(SSER 13)(SER)(SSER 2)(SSER 3)(SSER 13)(SSER 14)(SSER 15)(SER)(SER)(SER)(SER)(SSER 2)(SSER 7)(SSER 9)(SSER 10)(SSER 13)(SSER 14)(SSER 18)(SSER 20)(SER)(SSER 2)(SSER 3)(SSER 13)(SSER 14)(SER)(SSER 2)(SSER 3)(SSER 7)(SSER 13)(SSER 14)(SSER 15)(SSER 16)7.8.1 7.8.2 7.8.3 7.8.4 7.8.5 7.9.0 8.0.0 8.1.0 8.2.0 8.2.1 8.2.2 8.2.3 8.2.4 8.3.0 8.3.1 8.3.2 8.3.3 (212) Evaluation Findings 1-12 Issue Status Section (213)(214)(215)(216)(217)Station Blackout Auxiliary Systems Fuel Storage Facility New-Fuel Storage Spent-Fuel Storage Resolved Resolved Open (NRR)(218) Spent Fuel Pool Cooling and Cleanup System (219) Fuel-Handling System (220)(221)Water Systems Essential Raw Cooling Water and Raw Cooling Water System (222) Component Cooling System (Reactor Auxiliaries Cooling Water System)(223) Demineralized Water Makeup System (224) Potable and Sanitary Water Systems (225) Ultimate Heat Sink (226) Condensate Storage Facilities (227) Process Auxiliaries (228) Compressed Air System (229) Process Sampling System (230) Equipment and Floor Drainage System (231) Chemical and Volume Control System (232) Heating, Ventilation, and Air Conditioning Systems (233) Control Room Area Ventilation System (234) Fuel-Handling Area Ventilation System (235) Auxiliary Building and Radwaste Area Ventilation System (236) Turbine Building Area Ventilation System Open (NRR)Open (NRR)Open (NRR)Open (NRR)Resolved Resolved Resolved Resolved Resolved Open (NRR)Resolved Resolved Resolved Resolved Resolved Resolved (SER)(SSER 10)(SER)(SER)(SSER 5)(SSER 15)(SSER 16)(SER)(SSER 11)(SSER 15)(SER)(SSER 3)(SSER 13)(SER)(SSER 9)(SSER 10)(SSER 18)(SER)(SSER 5)(SER)(SER)(SSER 9)(SER)(SER)(SSER 12)(SER)(SER)(SSER 3)(SSER 5)(SSER 14)(SSER 16)(SER)(SER)(SER)(SSER 9)(SER)(SER)(SER)8.4.0 9.0.0 9.1.0 9.1.1 9.1.2 9.1.3 9.1.4 9.2.0 9.2.1 9.2.2 9.2.3 9.2.4 9.2.5 9.2.6 9.3.0 9.3.1 9.3.2 9.3.3 9.3.4 9.4.0 9.4.1 9.4.2 9.4.3 9.4.4 1-13 Issue Status (237) Engineered Safety Features Ventilation System (238) Other Auxiliary Systems (239) Fire Protection (240) Communications System (241)(242)Lighting System Emergency Diesel Engine Fuel Oil Storage and Transfer System (243) Emergency Diesel Engine Cooling Water System (244) Emergency Diesel Engine Starting Systems (245) Emergency Diesel Engine Lubricating Oil System (246) Emergency Diesel Engine Combustion Air Intake and Exhaust System (247) Steam and Power Conversion System (248) Summary Description (249) Turbine Generator (250) Turbine Generator Design (251) Turbine Disc Integrity (252) Main Steam Supply System (253) Main Steam Supply System (Up to and Including the Main Steam Isolation Valves)(254) Main Steam Supply System (255) Steam and Feedwater System Materials (256) Secondary Water Chemistry Open (NRR)Resolved Open (NRR)Resolved Open (NRR)Resolved Open (NRR)Open (NRR)Open (NRR)Resolved Open (NRR)Resolved Resolved Resolved Open (NRR)Resolved Resolved Open (NRR)(SER)(SSER 9)(SSER 10)(SSER 11)(SSER 14)(SSER 16)(SSER 19)(SER)(SSER 10)(SSER 18)(SSER 19)(SER)(SSER 5)(SER)(SER)(SSER 5)(SSER 9)(SSER 10)(SSER 11)(SSER 12)(SER)(SSER 5)(SSER 11)(SER)(SSER 5)(SSER 10)(SER)(SSER 3)(SSER 5)(SSER 10)(SER)(SSER 5)(SSER 10)(SER)(SER)(SSER 5)(SER)(SSER 12)(SER)(SER)(SER)(SSER 19)(SER)(SER)(SER)(SSER 5)Section 9.4.5 9.5.0 9.5.1 9.5.2 9.5.3 9.5.4 9.5.5 9.5.6 9.5.7 9.5.8 10.0.0 10.1.0 10.2.0 10.2.1 10.2.2 10.3.0 10.3.1 10.3.2 10.3.3 10.3.4 10.4.0 (257)Other Features 1-14 Issue Status (258) Main Condenser (259) Main Condenser Evacuation System (260) Turbine Gland Sealing System (261) Turbine Bypass System (262) Condenser Circulating Water System (263) Condensate Cleanup System (264) Condensate and Feedwater Systems (265) Steam Generator Blowdown System (266) Auxiliary Feedwater System (267) Radioactive Waste Management (268) Summary Description (269) Liquid Waste Management (270) Gaseous Waste Management (271) Solid Waste Management System (272) Process and Effluent Radiological Monitoring and Sampling Systems (273) Evaluation Findings (274) NUREG-0737 Items (275) Wide-Range Noble Gas, Iodine, and Particulate Effluent Monitors (TMI Action Items II.F.1(1) and II.F.1(2))

(276) Primary Coolant Outside Containment (TMI Action item III.D.1.1)

(277) Radiation Protection (278) General (279) Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable (ALARA)(280) Radiation Sources Resolved Resolved Resolved Open (NRR)Resolved Resolved Resolved Resolved Resolved Open (NRR)Resolved Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (Inspection)

Open (NRR)Open (NRR)Open (NRR)Open (NRR)(SER)(SSER 9)(SER)(SER)(SER)(SSER 5)(SER)(SER)(SER)(SSER 14)(SER)(SER)(SSER 14)(SER)(SSER 16)(SER)(SSER 4)(SSER 16)(SER)(SSER 8)(SSER 16)(SER)(SSER 16)(SER)(SSER 16)(SSER 20)(SER)(SSER 8)(SSER 16)(SER)(SER)(SSER 5)(SSER 6)(SER)(SSER 5)(SSER 6)(SSER 10)(SSER 16)(SER)(SSER 10)(SSER 14)(SER)(SSER 14)(SER)(SSER 14)Section 10.4.1 10.4.2 10.4.3 10.4.4 10.4.5 10.4.6 10.4.7 10.4.8 10.4.9 11.0.0 11.1.0 11.2.0 11.3.0 11.4.0 11.5.0 11.6.0 11.7.0 11.7.1 11.7.2 12.0.0 12.1.0 12.2.0 12.3.0 1-15 Issue Status (281) Radiation Protection Design Features Open (NRR)(282) Dose Assessment (283) Health Physics Program Open (NRR)Open (NRR)(284)(285)NUREG-0737 Items Plant Shielding (286) High Range In-Containment Monitor (TMI Action Item II.F.1.(3))

(287) In-Plant Radioiodine Monitor (TMI Action Item II.D.3.3)(288) Conduct of Operations (289) Organization Structure of the Applicant (290) Management and Technical Organization (291) Corporate Organization and Technical Support (292) Plant Staff Organization (293) Training (294) Licensed Operator Training Program Open (NRR)Open (NRR)Open (NRR)Resolved Resolved Resolved Open (NRR)Resolved Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (Inspection)(SER)(SSER 10)(SSER 14)(SSER 18)(SER)(SSER 14)(SER)(SSER 10)(SSER 14)(SER)(SSER 14)(SSER 16)(SER)(SSER 5)(SER)(SSER 16)(SER)(SSER 16)(SER)(SER)(SER)(SSER 8)(SER)(SSER 9)(SSER 10)(SER)(SER)(SSER 13)(SSER 20)(SER)(SSER 13)(SSER 20)(SER)(SSER 13)(SSER 20)(SER)(SSER 8)(SER)(SER)(SSER 9)(SSER 10)Section 12.4.0 12.5.0 12.6.0 12.7.0 12.7.1 12.7.2 12.7.3 13.0.0 13.1.0 13.1.1 13.1.2 13.1.3 13.2.0 13.2.1 13.2.2 13.3.0 13.3.1 13.3.2 13.3.3 13.4.0 13.5.0 13.5.1 13.5.2 (295)(296)(297)Training for Nonlicensed Personnel Emergency Preparedness Evaluation Introduction (298) Evaluations of the Emergency Plan (299)Conclusions (300) Review and Audit (301)(302)(303)Plant Procedures Administrative Procedures Operating and Maintenance Procedures 1-16 Issue Status (304)NUREG-0737 Items Open (Inspection)

Open (NRR)(305) Physical Security Plan (306)(307)(308)(30Q9)(310)(311)(312)(313)(314)(315)Physical Security Organization Physical Barriers Access Requirements Detection Aids Communications Test and Maintenance Requirements Response Requirements Personnel Reliability Land Vehicle Bomb Control Program Initial Test Program (316) Accident Analyses (317) General Discussion (318) Normal Operation and Anticipated Transients (319) Loss-of-Cooling Transients (320) Increased Cooling Inventory Transients (321) Change in Inventory Transients (322) Reactivity and Power Distribution Anomalies (323) Conclusions (324) Limiting Accidents (325) Loss-of-Coolant Accident (LOCA)Open (Inspection)

Resolved Open (NRR)Open (NRR)Resolved Open (NRR)Open (NRR)Resolved Resolved Open (NRR)(SER)(SSER 3)(SSER 16)(SER)(SSER 1)(SSER 10)(SSER 15)(SSER 20)(SER)(SSER 3)(SSER 5)(SSER 7)(SSER 9)(SSER 10)(SSER 12)(SSER 14)(SSER 16)(SSER 18)(SSER 19)(SER)(SER)(SER)(SSER 13)(SSER 14)(SER)(SER)(SSER 18)(SER)(SSER 4)(SSER 7)(SSER 13)(SSER 14)(SER)(SSER 4)(SER)(SER)(SSER 12)(SSER 15)Section 13.5.3 13.6.0 13.6.1 13.6.2 13.6.3 13.6.4 13.6.5 13.6.6 13.6.7 13.6.8 13.6.9 14.0.0 15.0.0 15.1.0 15.2.0 15.2.1 15.2.2 15.2.3 15.2.4 15.2.5 15.3.0 15.3.1 1-17 Issue Status (326) Steamline Break (327) Feedwater System Pipe Break (328) Reactor Coolant Pump Rotor Seizure (329) Reactor Coolant Pump Shaft Break (330) Anticipated Transients Without Scram (331)(332)(333)Conclusions Radiological Consequences of Accidents Loss-of-Coolant Accident Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (Inspection)

Resolved Resolved Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (NRR)Open (NRR)Resolved Resolved (SER)(SSER 3)(SSER 14)(SER)(SSER 14)(SER)(SSER 14)(SER)(SSER 14)(SER)(SSER 3)(SSER 5)(SSER 6)(SSER 10)(SSER 11)(SSER 12)(SER)(SER)(SER)(SSER 5)(SSER 9)(SSER 15)(SSER 18)(SER)(SSER 15)(SER)(SSER 2)(SSER 5)(SSER 12)(SSER 14)(SSER 15)(SER)(SSER 15)(SER)(SSER 4)(SSER 15)(SER)(SER)(SER)(SSER 4)(SER)(SSER 4)Section 15.3.2 15.3.3 15.3.4 15.3.5 15.3.6 15.3.7 15.4.0 15.4.1 15.4.2 15.4.3 15.4.4 15.4.5 15.4.6 15.4.7 15.5.0 15.5.1 15.5.2 (334) Main Steamline Break Outside of Containment (335) Steam Generator Tube Rupture (336) Control Rod Ejection Accident (337) Fuel-Handling Accident (338) Failure of Small Line Carrying Coolant Outside Containment (339) Postulated Radioactive Releases as a Result of Liquid Tank Failures (340) NUREG-0737 Items (341) Thermal Mechanical Report (TMI Action Item II.K.2.13)

(342) Voiding in the Reactor Coolant System during Transients (TMI Action Item II.K.2.17) 1-18 Issue Status Section (343) Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (TMI Action Item II.K.3.1)

Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (TMI Action Item II.K.3.2)(344) Automatic Trip of Reactor Coolant Pumps (TMI Action Item II.K.3.5)(345) Small-Break LOCA Methods (l1.K.3.30) and Plant-Specific Calculations (I1.K.3.31)

(346) Relative Risk of Low-Power Operation (347) Technical Specification (348) Quality Assurance (349) General (350) Organization (351) Quality Assurance Program (352) Conclusions (353) Maintenance Rule (354) Control Room Design Review (355) General Resolved Open (Inspection)

Open (Inspection)

Resolved Open (NRR)Resolved Resolved Resolved Resolved Open (NRR)Open (NRR)(SER)(SSER 5)(SER)(SSER 4)(SSER 16)(SER)(SSER 4)(SSER 5)(SSER 16)(SER)(SER)(SER)(SER)(SSER 2)(SSER 5)(SSER 10)(SSER 13)(SSER 15)(SER)(SER)(SSER 5)(SSER 6)(SSER 15)(SSER 16)(SER)(SSER 16)15.5.3 15.5.4 15.5.5 15.6.0 16.0.0 17.0.0 17.1.0 17.2.0 17.3.0 17.4.0 17.6.0 18.0.0 18.1.0 18.2.0 (356) Conclusions 1.13 Implementation of Corrective Action Programs and Special Programs On September 17, 1985, the NRC sent a letter to the applicant, pursuant to 10 CFR 50.54(f), requesting that the applicant submit information on its plans for correcting problems concerning the overall management of its nuclear program and for correcting plant-specific problems.

In response to this letter, TVA prepared a corporate NPP that identified and proposed corrections to problems concerning the overall management of its nuclear program and a site-specific plan for Watts Bar entitled, "Watts Bar Nuclear Performance Plan" (WBNPP). TVA established 18 corrective action programs (CAPs) and 11 special programs (SPs) to address these concerns.The NRC staff documented its review and findings concerning the WBNPP in NUREG-1232, Volumes 1 and 4. Based on its review, the staff found the general approaches of various 1-19 corrective actions to be adequate and determined that, when fully implemented, the proposed corrective actions should address the identified deficiencies for Unit 1 and should be acceptable for Unit 2, if there are no changes. However, during its evaluation, the NRC staff found that several issues required additional information before the staff could complete its review. The NRC staff stated that it would continue to review and monitor these programs and would issue a revised evaluation in a supplement to NUREG-0847.

Starting in Supplement No. 5 to NUREG-0847, the NRC added a section on CAPs and SPs to provide the status of its review and TVA's implementation.

Supplements No. 5 through 20 of NUREG-0847 documented the satisfactory resolution and implementation of NPP topics for WBN Unit 1; however, no conclusions were stated for WBN Unit 2. Thus, this and future supplements will address the resolution of these NPP topics for WBN Unit 2.In its letter dated August 3, 2007, TVA stated its intention to resolve the Unit 2 CAPs and SPs using NUREG-1232 (Volume 4), NUREG-0847, and applicable regulations.

TVA also stated that, if it is necessary to modify the criteria, it will submit those changes to the NRC for review and approval.In a letter dated January 29, 2008, TVA gave the status of these CAPs and SPs and its commitments for WBN Unit 2. TVA also provided a separate listing of those CAP and SP items requiring NRC review and approval.

In this regard, TVA stated that it had evaluated these CAPs and SPs and determined that, with two exceptions (cable issues and electrical issues); they will be resolved using the methodology employed for Unit 1. In a letter dated May 29, 2008, as supplemented on January 14, 2009, TVA provided the program methods that it proposed to use to resolve these issues, which are different from the resolution used for WBN Unit 1. In this regard, TVA provided the differences and its justification for five subissues of the CAP cable issue. TVA also stated that, upon further consideration, it had decided to use the same approach as was used on Unit 1 for the electrical subissue pertaining to physical cable separation and electrical isolation.

Based on subsequent discussions with the staff, TVA has supplemented the CAP and SP summaries to provide additional information on the status of these programs, the basis for its proposed action, and the impact of these programs on other aspects of the licensing framework.

In a letter dated September 26, 2008, TVA provided the summaries of the CAPs and SPs describing proposed actions, current status of licensing review, analysis of conformance, effect on the FSAR, effect on the technical specifications and technical requirements manual, items requiring verification and inspection, and the interdependencies of these issues.The NRC staff reviewed the information provided by TVA and determined that, based on the TVA description and the staff's review (documented in NUREG-1232, Volume 4, and the applicable supplements of NUREG-0847), there is reasonable assurance that, when implemented as described, certain CAP and SP issues can be designated as acceptable for implementation at WBN Unit 2. In the September 26, 2008, letter, TVA identified and provided the bases for changes to the implementation of several CAP and SP issues. The NRC staff documented its conclusions regarding the status of the CAPs and SPs in a letter to TVA dated February 11, 2009. Section 1.13.1 provides a summary of the status.1-20 1.13.1 Corrective Action Programs No.Title Program Review Status (1) Cable Issues a. Silicon Rubber Insulated Cable b. Cable Jamming c. Cable Support in Vertical Conduit d. Cable Support in Vertical Trays e. Cable Proximity to Hot Pipes f. Cable Pull-Bys g. Cable Bend Radius h. Cable Splices i. Cable Sidewall Bearing Pressure j. Pulling Cables Through 900 Condulet and Flexible Conduit k. Computer Cable Routing System Software and Database Verification and Validation (2) Cable Tray and Tray Supports (3) Design Baseline and Verification Program (4) Electrical Conduit and Conduit Support (5) Electrical Issues a. Flexible Conduit Installations

b. Physical Cable Separation and Electrical Isolation c. Contact and Coil Rating of Electrical Devices d. Torque Switch and Overload Relay Bypass Capability for Active Safety-Related Valves e. Adhesive-Backed Cable Support Mount (6) Equipment Seismic Qualification (7) Fire protection (8) Hanger and Analysis Update Program (9) Heat Code Traceability (10) Heating, Ventilation, and Air-Conditioning Duct and Duct Supports (11) Instrument Lines (12) Prestart Test Program Plan Open (NRR)Resolved Resolved Resolved Open (NRR)Open (NRR)Resolved Open (NRR)Resolved Resolved Resolved Resolved Resolved Resolved Resolved Resolved (13) Quality Assurance (QA) Records Open (NRR)(14) Quality-List (0-List)Resolved 1-21 No. Title Program Review Status (15) Replacement Items Program (Piece Parts) Open (NRR)(16) Seismic Analysis Resolved (17) Vendor Information Program Resolved (18) Welding Resolved 1.13.2 Special Programs No. Title Program Review Status (1) Concrete Quality Program Resolved (2) Containment Cooling Resolved (3) Detailed Control Room Design Review Resolved (4) Environmental Qualifications Program Resolved (5) Master Fuse List Resolved (6) Mechanical Equipment Qualification Resolved (7) Microbiologically Induced Corrosion Resolved (8) Moderate Energy Line Break Flooding Resolved (9) Radiation Monitoring System Resolved (10) Soil Liquefaction Resolved (11) Use-As-Is Condition Adverse to Quality Resolved 1.14 Implementation of Applicable Bulletin and Generic Letter Requirements From time to time, the NRC staff issues generic requirements or recommendations in the form of orders, bulletins, generic letters, regulatory issue summaries, and other documents to address certain safety and regulatory issues. These are generally termed "generic communications." The documents specify actions that should be taken by construction permit holders, applicants, or licensees, as delineated in the document.

The NRC staff evaluates responses to required actions in these generic communications to determine whether safety issues are resolved or if additional actions need to be taken. The staff will also evaluate the appropriateness of implementation schedules and will complete these evaluations before issuing an OL.1-22 By letter dated September 7, 2007, and supplemented by letters on March 20, 2008, and July 29, 2008, TVA provided a summary of the status of its responses to NRC generic communications issued before 1995 for WBN Unit 2 and its initial responses to other bulletins and generic letters issued after WBN Unit 1 was licensed, including action items under NUREG-0737 and Supplement No. 1.The NRC staff has assessed the information presented by TVA and documented its results in letters to TVA dated May 28, 2008, and August 25, 2008. The staff's assessment categorized all generic communications as (1) already documented or otherwise resolved, (2) open because either further review is needed or inspection verification of completion or implementation needs to be conducted, and (3) "not applicable" because the technical specifications, equipment, design, specific circumstances, or special exemptions are clearly and undeniably not applicable (e.g., boiling-water reactor, Babcock and Wilcox design), or are items that apply or relate to WBN Unit 2 but do not require any further action or response.The table below identifies open issues that should be resolved.

It should be noted that, although many of the generic communications have been documented or otherwise resolved, the NRC staff has determined that there may be circumstances that could result in the need to reopen a previously closed topic.Correspondence No.Title (1) GL 80-14 TVA Action: NRC Action: (2) GL 80-77 TVA Action: NRC Action: (3) GL 82-28 TVA Action: NRC Action: (4) GL 83-28 Light-Water Reactor Primary Coolant System Pressure Isolation Valves Submit Technical Specifications for NRC Review.Review Technical Specifications Refueling Water Level -Technical Specifications Changes Submit Technical Specifications for NRC Review.Review Technical Specifications Inadequate Core Cooling Instrumentation System Open Open Required Actions Based on Generic Implications of Salem Anticipated Transient without Scram Events (Screened into the Items 4 through 7)Post-Maintenance Testing (reactor trip system components)

Submit Technical Specifications for NRC Review Review Technical Specifications (4.a) GL 83-28 (item 3.1)TVA Action: NRC Action: 1-23 Correspondence No.(4.b) GL 83-28 (3.2)TVA Action NRC Action (4.c) GL 83-28 (4.2)TVA Action NRC Action (4.d) GL 83-28 (4.5)TVA Action NRC Action (8) GL 86-09 TVA Action NRC Action (9) GL 88-20 TVA Action NRC Action (10) GL 88-20sl TVA Action NRC Action (11) GL 88-20s2 TVA Action NRC Action Title Post-Maintenance Testing (All Surveillance Requirement Components)

Submit Technical Specifications and NRC Review Review Technical Specifications Reactor Trip System Reliability (Preventive Maintenance and Surveillance Program for Reactor Trip Breakers)Submit Technical Specifications and NRC Review Review Technical Specifications Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment)

Submit Technical Specifications and NRC Review Review Technical Specifications Technical Resolution of Generic Issue B-59, (N-i) Loop Operation in BWRs and PWRs Submit Technical Specifications for NRC Review.Review Technical Specifications Individual Plant Examination for Severe Accident Vulnerability Open Open Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities

-10 CFR 50.54 Open Open Individual Plant Examination for Severe Accident Vulnerability.

Accident Management Strategies for Consideration in the Individual Plant Examination Process Open Open 1-24 Correspondence No.Title (12)GL 88-20s3 Individual Plant Examination for Severe Accident Vulnerability.

Completion of Containment Performance Improvement Program and Forwarding of Insights for Use in the IPE for Severe Accident Vulnerabilities TVA Action NRC Action Open Open (13) GL 88-20s4 TVA Action NRC Action (14) GL 88-20s5 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities Open Open Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities

-10 CFR 50.54(f)Open Open Guidelines on Developing Acceptable In-service Testing Programs The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.TVA Action NRC Action GL 89-04 TVA Action (15)NRC Action Open (16) GL 89-21 TVA Action NRC Action Request for Information Concerning Status of Implementation of Unresolved Safety Issue Requirements TVA provided status of unresolved safety issues on September 26, 2008.Open Resolution of Generic Issues 70, "PORV [power-operated relief valve] and Block Valve Reliability," and 94, "Additional LTOP [low-temperature overpressure]

Protection for PWRs" (17)GL 90-06 TVA Action NRC Action Submit Technical Specifications for NRC Review Review Technical Specifications 1-25 Correspondence No.Title (18) GL 92-08 TVA Action NRC Action (19)GL 95-03 TVA Action NRC Action (20) GL 96-06 TVA Action NRC Action GL 97-01 Thermo-Lag 330-1 Fire Barriers The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change Open Circumferential cracking of Steam Generator (SG) Tubes The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change Open Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change Open Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations The proposed approach has.been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change Open Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps Integrity During Design-Basis Accident Conditions The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open (21)TVA Action NRC Action (22) GL 97-04 TVA Action NRC Action 1-26 Correspondence No.Title (23) GL 97-05 TVA Action NRC Action (24) GL 97-06 TVA Action NRC Action GL 98-02 (25)TVA Action NRC Action (26) GL 98-04 SG Tube Inspection Techniques The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change Open Degradation of SG Internals The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Potential for Degradation of the ECCS and the Containment Spray System after a LOCA because of Construction and Protective Coating Deficiencies and Foreign Material in Containment The proposed approach-has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.-Open Control Room Habitability No action or documentation is provided to show the staff has reviewed the item for WBN Unit 2, and the resolution is through submittal of a technical specification.

Open TVA Action NRC Action (27) GL 2003-01 TVA Action NRC Action 1-27 Correspondence No.Title (28) GL 2004-01 TVA Action NRC Action (29) GL 2004-02 TVA Action NRC Action (30) GL 2006-01 TVA Action NRC Action (31) GL 2006-02 Requirements for SG Tube Inspection The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Potential Impact of Debris Blockage on Emergency Recirculation during Design-Basis Accidents at PWRs The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open SG Tube Integrity and Associated Technical Specifications No action or documentation is provided to show the staff has reviewed the item for WBN Unit 2, and the resolution is through submittal of a technical specification.

Open Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Potentially Nonconforming Hemyc and MT Fire Barrier Configurations The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open (32)TVA Action NRC Action GL 2006-03 TVA Action NRC Action 1-28 Correspondence No.Title (34) G L 2007-01 TVA Action NRC Action (35) GL 2008-01 Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients Open; Complete testing of four additional cables Open Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems TVA Action NRC Action Open Open (36) BL 92-01 and Supplement 1 TVA Action NRC Action Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open (37)BL 96-01 Control Rod Insertion Problems (PWR)TVA Action NRC Action (38) BL 01-01 TVA Action NRC Action The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Circumferential Cracking of Reactor Pressure Vessel (RPV)Head Penetration Nozzles The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open RPV Head Degradation and Reactor Coolant Pressure Boundary Integrity The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open (39)BL 02-01 TVA Action NRC Action 1-29 1 1.Correspondence No.Title (40) BL 02-02 TVA Action NRC Action (41) BL 03-02 TVA Action NRC Action (42) BL 04-01 RPV Head and Vessel Head Penetration Nozzle Inspection Program The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Leakage from RPV Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at PWRs The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Security Officer Attentiveness The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open TVA Action NRC Action (43) BL 07-01 TVA Action NRC Action NUREG 0737 TMI Action Items (TVA letter dated September 14, 1981 applies to all of the following NUREG 0737 issues)(44) NUREG 0737 Item I.B.1.2 TVA Action NRC Action Independent Safety Engineering Group The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open 1-30 Correspondence No.(45) NUREG 0737 Item I.D.1 TVA Action NIRC Action (46) NUREG 0737 Item lI.B.3 TVA Action NRC Action (47) NUREG 0737 Item II.E.4.2 TVA Action NRC Action (48) NUREG 0737 Item II.F.2 TVA Action N RC Action (49) NUREG 0737 Item II.K.3.3 TVA Action NRC Action (50) NUREG 0737 Item II.K.3.10 TVA Action NRC Action Title Control Room Design Review (CRDR)The proposed approach has been approved for WBN Unit 1;the same approach will be proposed for use on WBN Unit 2 without change.Open Post-accident Sampling Submit. Technical Specifications for NRC Review Review Technical Specifications Containment Isolation Dependability Submit Technical Specifications for NRC Review Review Technical Specifications Instrumentation for Detection of Inadequate Core-Cooling Open Open Reporting SV/RV Failures/Challenges Submit Technical Specifications for NRC Review Review Technical Specifications Anticipatory Trip at High Power Submit Technical Specifications for NRC Review Review Technical Specifications 1-31 Correspondence No.Title (51) NUREG 0737 Item ll.0.1.1 TVA Action NRC Action (52) NUREG 0737 Item III.D.3.4 TVA Action NRC Action (53) IEB 75-08 TVA Action NRC Action (54) IEB 77-04 TVA Action NRC Action Primary Coolant Outside Containment No action or documentation is provided to show the staff has reviewed the item for WBN Unit 2, and the resolution is through submittal of a technical specification.

Open Control-Room Habitability The proposed approach has been approved for WBN Unit 1;the same approach.

will be proposed for use on WBN Unit 2 without change.Open PWR Pressure Instrumentation The item has been approved either for both units at WBN or explicitly for WBN Unit 2; however, a change to the original approval requires submittal of the technical specifications and staff review.*Review Technical Specifications Calculation Error Affecting Performance of a System for Controlling pH of Containment Sump Water Following a LOCA The item has been approved either for both units at WBN or explicitly for WBN Unit 2; however, a change to the original approval requires submittal of the Technical Specifications and staff review Review Technical Specifications 1-32 17 QUALITY ASSURANCE 17.3 Quality Assurance Program 17.3.1 Authorization to Transfer Code Symbol Stamps The regulations at Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 require that all nuclear construction activities be conducted in accordance with established quality assurance (QA) programs.

In 10 CFR 50.55a,"Codes and Standards," the NRC requires that systems and components of nuclear power reactors meet the requirements.of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). The ASME Code provides rules for the construction of boilers, pressure vessels, and nuclear components.

This includes requirements for materials, design, fabrication, examination, inspection, and stamping.

Items constructed in accordance with all of the applicable rules of the ASME Code are identified with the official ASME Code Symbol Stamp described in the governing section of the ASME Code. ASME has established procedures to authorize qualified organizations to perform various activities in accordance with the requirements of the ASME Code. Organizations that are authorized to use ASME Code Symbols for marking items or constructions that have been constructed and inspected in compliance with the ASME Code receive Certificates of Authorization.

ASME maintains the standing of the ASME Code Symbols for the benefit of the users, the enforcement jurisdictions, and the holders of the symbols, who comply with all requirements.

Construction activities are conducted in accordance with the requirements of the ASME Code Section I1l, "Rules for Construction of Nuclear Facility Components." ASME Code Section III includes requirements and guidance for establishing and executing QA programs for the design, construction, operation, and decommissioning of nuclear facilities.

Paragraph NCA-81 10,"General," of ASME Code Section III, Subsection 8100, "Authorization to Perform Code Activities," states that "[a]uthorization to use the official Code Symbol Stamps or to certify work by other means provided in this Section (see Table NCA-8100-1) will be granted by the Society for a 3-year period pursuant to the provisions set forth in this Subarticle." Paragraph NCA-8180 provides requirements for renewal of these certificates.

Through an accreditation program, ASME awards N-stamps and Certificates of Authorization to contractors for performing nuclear construction activities.

The Certificate of Authorization is recognized by the NRC as evidence that the N-stamp holder has a documented QA program that meets the requirements of Appendix B to 10 CFR Part 50. The nuclear plant constructor holding an N-stamp is required to complete N-5 Code Data Reports to certify that the required portions of the plant were constructed in accordance with ASME Code Section III and allow the applicant todocument completion of the plant as part of the Owner'sSection III requirements.

TVA's N-Certificate for construction of WBN Unit 2 expired in October, 1996. By letter dated February 1, 2008, as supplemented on July 2, 2008, TVA submitted a request for relief from certain requirements of the ASME Code for WBN Unit 2. TVA requested authorization to use, as an alternative, the provisions in ASME Code Case N-520-2, "Alternative Rules for Renewal of Active or Expired N-type Certificates for Plants Not in Active Construction, Section IIl, Division 1." Use of ASME Code Case N-520-2 would allow TVA to obtain a temporary Certificate of Authorization from ASME to complete and transfer documentation of the partially completed ASME Code Section III systems and components to the jurisdiction of a subcontractor who would be an ASME Code Section III N-Certificate Holder. The subcontractor 17-1 would complete the construction of the WBN Unit 2 systems and complete the associated N-5 Code Data Reports to certify that the required portions of the plant were constructed in accordance with ASME Code Section III and allow the applicant to document completion of the plant as part of the Owner'sSection III requirements.

In its supporting safety evaluation, dated October 2, 2008, the NRC concluded that ASME Code Case N-520-2 provides an acceptable level of quality and safety to the requirements of ASME Code Section Il, Subsection NCA-8100.

Thus, the NRC staff authorized the use of the proposed alternative at WBN Unit 2.17-2 APPENDIX A CHRONOLOGY OF RADIOLOGICAL REVIEW OF WATTS BAR NUCLEAR PLANT, UNIT 2, OPERATING LICENSE REVIEW In Supplement No. 20 to this safety evaluation report (SER), the staff of the U.S. Nuclear Regulatory Commission (NRC) provided a summary of the more significant correspondence exchanged between the NRC and the Tennessee Valley Authority (TVA or the applicant) during the review of the operating license application for Watts Bar Nuclear (WBN) Plant, Units 1 and 2.The NRC has made these documents available through its Agencywide Documents Access and Management System (ADAMS) or the Public Document Room.The following list of documents presents the correspondence that has occurred subsequent to the applicant's letter notifying the NRC of its decision to reactivate construction of WBN Unit 2, which had been in a deferred status under the Commission's Policy Statement on Deferred Plants. This appendix contains most of the documents that are referenced in this supplement.

However, it is not a complete listing of all correspondence.

The reader may obtain the complete list, along with these documents, through ADAMS.NRC Letters and Summaries October 22, 2007 October 23, 2007 May 8, 2008 June 3, 2008 May 28, 2008 June 20, 2008 July 7, 2008 August 25, 2008 October 2, 2008 Letter, J.E. Dyer to W.R. McCollum (TVA), regarding the NRC staff action related to resumption of plant construction and continuation of operating license application reviews. (ADAMS Accession No. ML072570319)

Letter, J. Williams to W. Campbell (TVA), requesting information the NRC staff will need for its own assessment of the status of the licensing review. (ADAMS Accession No. ML072840337)

Letter, L. Raghavan to A. Bhatnagar (TVA), providing the NRC's initial assessment of the remaining operating license review scope for WBN Unit 2. (ADAMS Accession No. ML080860026)

Letter, J. Williams to A. Bhatnagar (TVA), requesting supplemental information to support acceptance review for the Supplemental Environmental Statement. (ADAMS Accession No. ML081210270)

Letter, P. Milano to A. Bhatnagar (TVA), providing results of the staff's assessment of all generic communications items. (ADAMS Accession No. ML081490110)

Letter, J. Williams to A. Bhatnagar (TVA), forwarding environmental assessment and finding of no significant impact related to request for extension of latest construction completion date. (ADAMS Accession No. ML081500030)

Letter, J. Williams to A. Bhatnagar (TVA), forwarding Order extending construction completion date of construction permit. (ADAMS Accession No. ML081500115)

Letter, P. Milano to A. Bhatnagar (TVA), providing staff's assessment of status of TVA responses to the NRC generic communications issued before 1995. (ADAMS Accession No. ML082330421)

Letter, L. Raghavan to A. Bhatnagar (TVA), forwarding relief request authorizing use of ASME Code Case N-520. (ADAMS Accession No. ML082560373)

A-1 October 10, 2008 February 11, 2009 Letter, P. Milano to A. Bhatnagar (TVA), providing staff's assessment of status of regulatory framework for completion of construction and licensing activities. (ADAMS Accession No. ML082840361)

Letter, P. Milano to A. Bhatnagar (TVA), providing staff's assessment of regulatory framework for completion of corrective action and special programs. (ADAMS Accession No. ML090210107)

TVA Letters August 3, 2007 September 7, 2007 September 7, 2007 October 11, 2007 December 5, 2007 January 29, 2008 February 1, 2008 February 15, 2008 March 6, 2008 March 13, 2008 March 20, 2008 May 8, 2008 Letter, W.R. McCollum, Jr., informing NRC staff of TVA's intention to reactivate and complete construction activities at WBN Unit 2. (ADAMS Accession No. ML072190047)

Letter, M. Bajestani to NRC, providing response to certain NRC bulletins and generic letters for Watts Bar Unit 2 (ADAMS Accession No. ML072570676)

Letter, M. Bajestani to NRC, providing a summary of generic communications with supplemental information on references to closure documentation where applicable. (ADAMS Accession No. ML072570678)

Letter, M. Bajestani to NRC, informing the NRC that TVA does not see the need for additional exemptions or relief, other than those discussed in the attachment to this letter and those associated with preservice and inservice inspection programs. (ADAMS Accession No. ML072910331 Letter, M. Bajestani to NRC, notifying NRC that TVA will use the Westinghouse Eagle-21 process protection system on WBN Unit 2.(ADAMS Accession No. ML073440022)

Letter, M. Bajestani to NRC, describing the regulatory framework for the completion of construction and licensing activities for WBN Unit 2 as committed to in TVA's August 3, 2007, letter. (ADAMS Accession No. ML080320443 Letter, M. Bajestani to NRC, requesting authorization to use ASME Code Case N-520-2 for expired N-type Certificates. (ADAMS Accession No. ML080370185)

Letter, M. Bajestani to NRC, providing Final Supplemental Environmental Impact Statement for completion and operation of WBN Unit 2, as committed to in TVA's January 29, 2008, letter. (ADAMS Accession No. ML080510469)

Letter, M. Bajestani to NRC, requests further extension of the construction permit to March 31, 2013. (ADAMS Accession No. ML080710489)

Letter, M. Bajestani to NRC, supplementing the January 29, 2008, letter on the regulatory framework tables for the SER and its supplements to allow ease of review and provide additional definitions for section status.(ADAMS Accession No. ML080770237)

Letter, M. Bajestani to NRC, providing a comprehensive list of generic communications for WBN Unit 2, reviewed and categorized by status.(ADAMS Accession No. ML080850253)

Letter, M. Bajestani to NRC, providing additional information and supersedes in its entirety TVA's March 6, 2008, request to extend the expiration date for the WBN Unit 2 Construction Permit. (ADAMS Accession No. ML081340309)

A-2 May 29, 2008 June 16, 2008 September 26, 2008 October 30, 2008 December 9, 2008 January 14, 2009 Letter, M. Bajestani to NRC, providing proposed program methods to resolve those subissues of the cable issues corrective action program that are different from those used for WBN Unit 1. (ADAMS Accession No ML081560183)

Letter, M. Bajestani to NRC, submitting additional information on regulatory framework for completion of construction and licensing activities. (ADAMS Accession No. ML081700293)

Letter, M. Bajestani to NRC, submitting regulatory framework for corrective action programs and special programs. (ADAMS Accession No. ML082750019)

Letter, M. Bajestani to NRC, submitting preservice inspection program plan. (ADAMS Accession No. ML083090046)

Letter, M. Bajestani to NRC, submits licensing basis preservation and construction refurbishment program plan. (ADAMS Accession No. ML083460177)

Letter, M. Bajestani to NRC, providing additional information regarding the cable issues corrective action program. (ADAMS Accession No. ML090210473)

A-3

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION

1. REPORT NUMBER (9-2004) (Assigned by NRC, Add Vol., Supp., Rev., NRCMD 3.7 and Addendum Numbers, if any.)BIBLIOGRAPHIC DATA SHEET NUREG-0847 (See instructions on the reverse) SUpplement No. 21 2. TITLE AND SUBTITLE 3. DATE REPORT PUBLISHED Safety Evaluation Report MONTH YEAR related to the operation of Watts Bar Nuclear Plant Unit 2 February 2009 Docket No. 50-391 4. FIN OR GRANT NUMBER 5. AUTHOR(S)

6. TYPE OF REPORT L. Raghavan P. D. Milano Technical 7. PERIOD COVERED (Inclusive Dates)8. PERFORMING ORGANIZATION

-NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor, provide name and mailing address.)U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Washington, DC 20555-0001

9. SPONSORING ORGANIZATION

-NAME AND ADDRESS (If NRC, type "Same as above"; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address.)Same as above.10. SUPPLEMENTARY NOTES Docket No. 50-391 11. ABSTRACT (200 words or less)Supplement No. 21 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for the license to operate Watts Bar Nuclear Plant Unit 2, Docket No. 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission (NRC). In Supplement No. 20, the NRC concluded that all applicable regulations and guidance as stated in the Safety Evaluation report and its Supplements were met for Watts Bar Nuclear Plant Unit 1. The purpose of this supplement is to provide information specific to the review for Watts Bar Nuclear Plant Unit 2 regarding the status of the matters remaining for resolution, which were outstanding at the time that the applicant deferred construction of Unit 2 and were not evaluated and resolved as part of the evaluation of Unit 1.12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.) 13. AVAILABILITY STATEMENT Safety Evaluation Report (SER) unlimited Watts Bar Nuclear Plant 14. SECURITY CLASSIFICATION Docket No. 50-391 (This Page)unclassified (This Report)unclassified

15. NUMBER OF PAGES 16. PRICE NRC FORM 335 (9-2004)PRINTED ON RECYCLED PAPER Fedal Recycling Program

NUREG-0847, Su ipplement 21 Safety Evaluation Report: Related to the Operation of Watts Bar Nuclear Plant, Unit 2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 OFFICIAL BUSINESS February 2009 (