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
To:
References
NUREG-0847 S6
Download: ML090570741 (52)

Text

• U.S.NRC United States Nuclear Regulatory Commission NUREG-0847 Supplement 21 ProtectingPeople andthe Environment 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 Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at libraries include all open literature items, such as NRC'S Public Electronic Reading Room at books, journal articles, and transactions, Federal http://www. nrc.qov/readinr-rm.html. Register notices, Federal and State legislation, and Publicly released records include, to name a few, congressional reports. Such documents as theses, NUREG-series publications; FederalRegister notices; dissertations, foreign reports and translations, and applicant, licensee, and vendor documents and non-NRC conference proceedings may be purchased correspondence; NRC correspondence and internal from their sponsoring organization.

memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their Copies of industry codes and standards used in a attachments. substantive manner in the NRC regulatory process are maintained at-NRC publications in the NUREG series, NRC The NRC Technical Library regulations,' and Title 10, Energy, in the Code of Two White Flint North FederalRegulations may also be purchased from one 11545 Rockville Pike of these two sources. Rockville, MD 20852-2738

1. The Superintendent of Documents

-U.S. Government Printing Office Mail Stop SSOP These standards are available in the library for Washington, DC 20402-0001 reference use by the public. Codes and standards are Internet: bookstore.gpo.gov usually copyrighted and may be purchased from the

• Telephone: 202-512-1800 originating organization or, if they are American Fax: 202-512-2250 National Standards, from-

2. The National Technical Information Service American National Standards Institute Springfield, VA 22161-0002 11 West 42nd Street www.ntis.gov New York, NY 10036-8002 1-800-553-6847 or, locally, 703-605-6000 www.ansi.org 212-642-4900 A single copy of each NRC draft report for comment is available free, to the extent of supply, upon written request as follows: Legally binding regulatory requirements are stated only Address: U.S. Nuclear Regulatory Commission in laws; NRC regulations; licenses, including technical S ".Office of Administration specifications; or orders, not in Mail, Distribution and Messenger Team NUREG-series publications. The views expressed in Washington, DC 20555-0001 contractor-prepared publications in this series are not E-mail: DISTRIBUTION anrc.qov necessarily those of the NRC.

Facsimile: 301-415-2289 The NUREG series comprises (1) technical and Some publications in the NUREG series that are administrative reports and books prepared by the staff posted at NRC's Web site address (NUREG-XXXX) or agency contractors http:!/www.nrc.ciov/readinq-rm/doc-collections!nurecis (NUREG/CR-XXXX), (2) proceedings of conferences are updated periodically and may differ from the last (NUREG/CP-XXXX), (3) reports resulting from printed version. Although references to material found international agreements (NUREG/IA-XXXX), (4) on a Web site bear the date the material was brochures (NUREG/BR-XXXX), and (5) compilations accessed, the material available on the date cited may of legal decisions and orders of the Commission and subsequently be removed from the site. Atomic and Safety Licensing Boards and of Directors' decisions under Section 2.206 of NRC's regulations (NUREG-0750).

• U.S.NRC United States Nuclear Regulatory Commission NUREG-0847 Supplement 21 ProtectingPeople and the Environment 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 ........ ............. . ....... .............. ... vii 1 INTRODUCTION AND DISCUSSION ........ ................. ... 1-1 1.1 Introduction ............... ......................... .... 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 ......... ............... . .. 1-21 1.13.2 Special Programs .......... ..................... ... 1-22 1.14 Implementation of Applicable Bulletin and Generic Letter Requirements 1-22 17 QUALITY ASSURANCE ............... ....................... ... 17-1 17.3 Quality Assurance Program .......... ................... ... 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 Section (8) Transportation Routes Open (NRR) (SER) 2.2.1 (9) Nearby Facilities Open (NRR) (SER) 2.2.2 (10) Conclusions Open (NRR) (SER) 2.2.3 (11) Meteorology 2.3.0 (12) Regional Climatology Resolved (SER) 2.3.1 (13) Local Meteorology Resolved (SER) 2.3.2 (14) Onsite Meteorological Measurements Resolved (SER) 2.3.3 Program (15) Short-Term (Accident) Atmospheric Resolved (SER) 2.3.4 Diffusion Estimates (SSER 14)

(16) Long-Term (Routine) Diffusion Estimates Resolved (SER) 2.3.5 (SSER 14)

(17) Hydrologic Engineering 2.4.0 (18) Introduction Resolved (SER) 2.4.1 (19) Hydrologic Description Resolved (SER) 2.4.2 (20) Flood Potential Resolved (SER) 2.4.3 (21) Local Intense Precipitation in Plant Area Resolved (SER) 2.4.4 (22) Roof Drainage Resolved (SER) 2.4.5 (23) Ultimate Heat Sink Resolved (SER) 2.4.6 (24) Groundwater Resolved (SER) 2.4.7 (25) Design Basis for Subsurface Hydrostatic Open (NRR) (SER) 2.4.8 Loading (SSER 3)

(26) Transport of Liquid Releases Open (NRR) (SER) 2.4.9 (27) Flooding Protection Requirements Open (SER) 2.4.10 (Inspection)

(28) Geological, Seismological, and Resolved (SER) 2.5.0 Geotechnical Engineering (29) Geology Resolved (SER) 2.5.1 (30) Seismology Resolved (SER) 2.5.2 (31) Surface Faulting Resolved (SER) 2.5.3 (32) Stability of Subsurface Materials and Resolved (SER) 2.5.4 Foundations (SSER 3)

(SSER 9)

(SSER 11)

(33) Stability of Slopes Resolved (SER) 2.5.5 (34) Embankments and Dams Resolved (SER) 2.5.6 (35) References 2.6.0 (36) Design of Structures, Components, 3.0.0 Equipment, and Systems (37) Introduction (SER) 3.1.0 Resolved (38) Conformance With General Design Criteria 3.1.1 (39) Conformance With Industry Codes and Resolved (SER) 3.1.2 Standards (40) Classification of Structures, Systems and Resolved (SSER 14) 3.2.0 Components 1-4

Issue Status Section (41) Seismic Classifications Resolved (SER) 3.2.1 (SSER 3)

(SSER 5)

(SSER 6)

(SSER 8)

(42) System Quality Group Classification Open (NRR) (SER) 3.2.2 (SSER 3)

(SSER 7)

(SSER 9)

(43) Wind and Tornado Loadings 3.3.0 (SER) 3.3.1 (44) Wind Loading Resolved (45) Tornado Loading Resolved (SER) 3.3.2 (46) Flood Level (Flood) Design 3.4.0 (47) Flood Protection Resolved (SER) 3.4.1 (48) Missile Protection 3.5.0 (49) Missile Selection and Description Resolved (SER) 3.5.1 (SSER 9)

(SSER 14)

(50) Structures, Systems, and Components to Resolved (SER) 3.5.2 be Protected from Externally Generated (SSER 2)

Missiles (51) Barrier Design Procedures Resolved (SER) 3.5.3 (52) Protection Against the Dynamic Effects Open (NRR) (SER) 3.6.0 Associated with the Postulated Rupture of (SSER 6)

Piping (SSER 11)

(53) Plant Design for Protection Against Open (NRR) (SER) 3.6.1 Postulated Piping Failures in Fluid System (SSER 14)

Outside Containment (54) Determination of Break Locations and Resolved (SER) 3.6.2 Dynamic Effects Associated with the (SSER 14)

Postulated Rupture of Piping (55) Leak-Before-Break Evaluation Procedures Resolved (SSER 5) 3.6.3 (SSER 12).

(56) Seismic Design Open (NRR) (SER) 3.7.0 (SSER 6)

(57) Seismic Input Open (NRR) (SER) 3.7.1 (SSER 6)

(SSER 9)

(SSER 16)

(58) Seismic Analysis Open (NRR) (SER) 3.7.2 (SSER 6)

(SSER 8)

(SSER 11)

(SSER 16) 1-5

Issue Status Section (59) Seismic Subsystem Analysis Open (NRR) (SER) 3.7.3 (SSER 6)

(SSER 7)

(SSER 8)

(SSER 9)

(SSER 12)

(60) Seismic Instrumentation Resolved (SER) 3.7.4 (61) Design of Seismic Category I Structures Open (NRR) (SER) 3.8.0 (SSER 9)

(62) Steel Containment Resolved (SER) 3.8.1 (SSER 3)

(63) Concrete and Structural Steel Internal Resolved (SER) 3.8.2 Structures (SSER 7)

(64) Other Seismic Category I Structures Open (NRR) (SER) 3.8.3 (SSER 14)

(SSER 16)

(65) Foundations Resolved (SER) 3.8.4 (66) Mechanical Systems and Components 3.9.0 (67) Special Topics for Mechanical Components Open (NRR) (SER) 3.9.1 (SSER 6)

(SSER 13)

(68) Dynamic Testing and Analysis of Systems, Resolved (SER) 3.9.2 Components, and Equipment (SSER 14)

(69) ASME Code Class 1, 2, and 3 Components, Open (NRR) (SER) 3.9.3 Component Structures, and Core Support (SSER 3)

Structures (SSER 4)

(SSER 6)

(SSER 7)

(SSER 8)

(SSER 15)

(70) Control Rod Drive Systems Resolved (SER) 3.9.4 (71) Reactor Pressure Vessel Internals Resolved (SER) 3.9.5 (72) Inservice Testing of Pumps and Valves Open (NRR) (SER) 3.9.6 (SSER 5)

(SSER 12)

(SSER 14)

(SSER 18)

(SSER 20)

(73) Seismic and Dynamic Qualification of Open (NRR) (SER) 2 3.10.0 Seismic Category I Mechanical and (SSER 1)

Electrical Equipment. (SSER 3)

(SSER 4)

(SSER 5)

(SSER 6)

(SSER 8)

(SSER 9)

(74) Environmental Qualification of Mechanical Open (NRR) (SSER 15) 3.11.0 and Electrical Equipment 1-6

Issue Status Section 3.13.0 (75) Threaded Fasteners - ASME Code Class 1, 2, and 3 (76) Reactor 4.0.0 4.1.0 (77) Introduction 4.2.0 (78) Fuel System Design Open (NRR) (SER) 4.2.1 (79) Description (SSER 13)

Open (NRR) (SER) 4.2.2 (80) Thermal Performance (SSER 2)

Open (NRR) (SER) 4.2.3 (81) Mechanical Performance (SSER 2)

(SSER 10)

(SSER 13)

Resolved (SER) 4.2.4 (82) Surveillance (SSER 2)

Open (NRR) (SER) 4.2.5 (83) Fuel Design Considerations 4.3.0 (84) Nuclear Design Open (NRR) (SER) 4.3.1 (85) Design Basis (SSER 13)

Open (NRR) (SER) 4.3.2 (86) Design Description (SSER 13)

(SSER 15)

Open (NRR) (SER) 4.3.3 (87) Analytical Methods (SSER 13)

Open (NRR) (SER) 4.3.4 (88) Summary of Evaluation Findings (SSER 13) 4.4.0 (89) Thermal-Hydraulic Design Resolved (SER) 4.4.1 (90) Performance in Safety Criteria Open (NRR) (SER) 4.4.2 (91) Design Bases (SSER 12)

Open (NRR) (SER) 4.4.3 (92) Thermal-Hydraulic Design Methodology (SSER 6)

(SSER 8)

(SSER 12)

(SSER 13)

(SSER 16)

SER dated 6/13/89 Open (NRR) (SER) 4.4.4 (93) Operating Abnormalities (SSER 13)

Open (NRR) (SER) 4.4.5 (94) Loose Parts Monitoring System (SSER 3)

(SSER 5)

(SSER 16)

(SER) 4.4.6 (95) Thermal-Hydraulic Comparison Resolved Open (SER) 4.4.7 (96) N-1 Loop Operation (Inspection)

Open (NRR) (SER) 4.4.8 (97) Instrumentation for Inadequate Core (SSER 10)

Cooling Detection (TMI Action Item II.F.2) 1-7

Issue Status Section (98) Summary and Conclusion Open (NRR) (SER) 4.4.9 (99) Reactor Materials 4.5.0 (100) Control Rod Drive Structural Materials Resolved (SER) 4.5.1 (101) Reactor Internals and Core Support Resolved (SER) 4.5.2 Materials (102) Functional Design of Reactivity Control Resolved (SER) 4.6.0 Systems (103) Reactor Coolant System and Connected 5.0.0 Systems (104) Summary Description Open (NRR) (SER) 5.1.0 (SSER 5)

(SSER 6)

(105) Integrity of Reactor Coolant Pressure 5.2.0 Boundary (106) Compliance with Codes and Code Cases Resolved (SER) 5.2.1 (107) Overpressurization Protection Resolved (SER) 5.2.2 (SSER 2)

(SSER 15)

(108) Reactor Coolant Pressure Boundary Resolved (SER) 5.2.3 Materials (109) Reactor Coolant System Pressure Open (NRR) (SER) 5.2.4 Boundary Inservice Inspection and Testing (SSER 10)

(SSER 12)

(SSER 16)

(110) Reactor Coolant Pressure Boundary Open (NRR) (SER) 5.2.5 Leakage Detection (SSER 9)

(SSER 11)

(SSER 12)

(111) Reactor Vessel and Internals Modeling 5.2.6 (112) Reactor Vessel 5.3.0 (113) Reactor Vessel Materials Open (NRR) (SER) 5.3.1 (SSER 11)

(SSER 14)

(114) Pressure-Temperature Limits Open (NRR) (SER) 5.3.2 (SSER 16)

(115) Reactor Vessel Integrity Open (NRR) (SER) 5.3.3 (116) Component and Subsystem Design 5.4.0 (117) Reactor Coolant Pumps Resolved (SER) 5.4.1 (118) Steam Generators Resolved (SER) 5.4.2 (SSER 1)

(SSER 4)

(119) Residual Heat Removal System Open (NRR) (SER) 5.4.3 (SSER 2)

(SSER 5)

(SSER 10)

(SSER 11)

(120) Pressurizer Relief Tank Resolved (SER) 5.4.4 1-8

Issue Status Section (121) Reactor Coolant System Vents (TMI Action Open (SER) 5.4.5 Item II.B.1) (Inspection) (SSER 2)

(SSER 12)

(122) Engineered Safety Features 6.0.0 (123) Engineered Safety Feature Materials 6.1.0 (124) Metallic Materials Resolved (SER) 6.1.1 (125) Organic Materials Resolved (SER) 6.1.2 (126) Postaccident Emergency Cooling Water Resolved (SER) 6.1.3 Chemistry (127) Containment Systems 6.2.0 (128) Containment Functional Design Open (NRR) (SER) 6.2.1 (SSER 3)

(SSER 5)

(SSER 7)

(SSER 12)

(SSER 14)

(SSER 15)

(129) Containment Heat Removal Systems Open (NRR) (SER) 6.2.2 (SSER 7)

(130) Secondary Containment Functional Design Resolved (SER) 6.2.3 (SSER 16)

(131) Containment Isolation Systems Open (SER) 6.2.4 (Inspection) (SSER 3)

(SSER 5)

(SSER 7)

(SSER 12)

(132) Combustible Gas Control Systems Open (NRR) (SER) 6.2.5 (SSER 4)

(SSER 5)

(SSER 8)

(133) Containment Leakage Testing Open (NRR) (SER) 6.2.6 (SSER 4)

(SSER 5)

(SSER 19)

(134) Fracture Prevention of Containment Resolved (SER) 6.2.7 Pressure Boundary (SSER 4)

(135) Emergency Core Cooling System Resolved (SER) 6.3.0 (136) System Design Open (NRR) (SER) 6.3.1 (SSER 6)

(SSER 7)

(SSER 11)

(137) Evaluation Open (NRR) (SER) 6.3.2 (SSER 5)

(138) Testing Open (NRR) (SER) 6.3.3 (SSER 2)

(SSER 9)

(139) Performance Evaluation Resolved (SER) 6.3.4 (140) Conclusions Open (NRR) (SER) 6.3.5 1-9

Issue Status Section (141) Control Room Habitability Open (NRR) (SER) 6.4.0 (SSER 5)

(SSER 11)

(SSER 16)

(SSER 18)

(142) Engineered Safety Feature (ESF) Filter 6.5.0 Systems (143) ESF Atmosphere Cleanup Systems Open (NRR) (SER) 6.5.1 (SSER 5)

(144) Fission Product Cleanup System Resolved (SER) 6.5.2 (145) Fission Product Control System Resolved (SER) 6.5.3 (146) Ice Condenser as a Fission Product Resolved (SER) 6.5.4 Cleanup System (147) Inservice Inspection of Class 2 and 3 Open (NRR) (SER) 6.6.0 Components (SSER 10)

(SSER 15)

(148) Instrumentation and Controls 7.0.0 (149) Introduction 7.1.0 (150) General Open (NRR) (SER) 7.1.1 (SSER 13)

(SSER 16)

(151) Comparison with Other Plants Resolved (SER) 7.1.2 (152) Design Criteria Open (NRR) (SER) 7.1.3 (SSER 4)

(SSER 15)

(153) Reactor Trip System Resolved (SER) 7.2.0 (154) System Description Open (NRR) (SER) 7.2.1 (SSER 13)

(SSER 15)

(155) Manual Trip Switches Resolved (SER) 7.2.2 (156) Testing of Reactor Trip Breaker Shunt Coils Resolved (SER) 7.2.3 (157) Anticipatory Trips Resolved (SER) 7.2.4 (158) Steam Generator Water Level Trip Open (NRR) (SER) 7.2.5 (SSER 2)

(SSER 14)

(159) Conclusions Open (NRR) (SER) 7.2.6 (SSER 13)

(160) Engineered Safety Features System Open (NRR) (SER) 7.3.0 (SSER 13)

(161) System Description Open (NRR) (SER) 7.3.1 (SSER 13)

(SSER 14)

(162) Containment Sump Level Measurement Resolved (SER) 7.3.2 (SSER 2)

(163) Auxiliary Feedwater Initiation and Control Resolved (SER) 7.3.3.

(164) Failure Modes and Effects Analysis Resolved (SER) 7.3.4 (165) IE Bulletin 80-06 Open (SER) 7.3.5 (Inspection) (SSER 3) 1-10

Issue Status Section (166) Conclusions Open (NRR) (SER) 7.3.6 (SSER 13)

(167) Systems Required for Safe Shutdown 7.4.0 (168) System Description Resolved (SER) 7.4.1 (169) Safe Shutdown from Auxiliary Control Room Open (NRR) (SER) 7.4.2 (SSER 7)

(170) Conclusions Resolved (SER) 7.4.3 (171) Safety-Related Display Instrumentation 7.5.0 (172) System Description Resolved (SER) 7.5.1 (173) Post-accident Monitoring System Open (NRR) (SER) 7.5.2 (SSER 7)

(SSER 9)

(SSER 14)

(SSER 15)

(174) IE Bulletin 79-27 Open (SER) 7.5.3 (Inspection)

(175) Conclusions Open (SER) 7.5.4 (Inspection)

(176) All Other Systems Required for Safety 7.6.0 (177) System Description Resolved (SER) 7.6.1 (178) Residual Heat Removal System Bypass Resolved (SER) 7.6.2 Valves Resolved 7.6.3 (179) Upper Head Injection Manual Control (SER)

(180) Protection Against Spurious Actuation of Resolved (SER) 7.6.4 Motor-Operated Valves (181) Overpressure Protection during Low Resolved (SER) 7.6.5 Temperature Operation (SSER 4)

(182) Valve Power Lockout Resolved (SER) 7.6.6 (183) Cold Leg Accumulator Valve Interlocks and Resolved (SER) 7.6.7 Position Indication (184) Automatic Switchover From Injection to Resolved (SER) 7.6.8 Recirculation Mode (185) Conclusions Resolved (SER) 7.6.9 (SSER 4)

(186) Control Systems Not Required for Safety 7.7.0 (187) System Description Resolved (SER) 7.7.1 (188) Safety System Status Monitoring System Resolved (SER) 7.7.2 (SSER 7)

(SSER 13)

(189) Volume Control Tank Level Control System Resolved (SER) 7.7.3 (190) Pressurizer and Steam Generator Overfill Resolved (SER) 7.7.4 (191) IE Information Notice 79-22 Resolved (SER) 7.7.5 (192) Multiple Control System Failures Resolved (SER) 7.7.6 (193) Conclusions Resolved (SER) 7.7.7 (194) Anticipated Transient Without Scram Open (NRR) (SSER 9) 7.7.8 Mitigation System Actuation Circuitry (SSER 14)

(AMSAC)

(195) NUREG-0737 Items Resolved (SER) 7.8.0 1-11

Issue Status Section (196) Relief and Safety Valve Position Indication Open (NRR) (SER) 7.8.1 (TMI Action Item ll.D.3) (SSER 5)

(SSER 14)

(197) Auxiliary Feedwater System Initiation and Open (SER) 7.8.2 Flow Indication (TMI Action Item II.E.1.2) (Inspection)

(198) Proportional Integral Derivative Control Open (SER) 7.8.3 Modification (TMI Action Item II.K.3.9) (Inspection)

(199) Proposed Anticipatory Trip Modification Open (SER) 7.8.4 (TMI Action Item II.K.3.10) (Inspection) (SSER 4)

(200) Confirm Existence of Anticipatory Reactor Resolved (SER) 7.8.5 Trip Upon Turbine Trip (TMI Action Item II.K.3.12)

(201) Data Communication Systems 7.9.0 (202) Electric Power Systems. 8.0.0 (203) General Resolved (SER) 8.1.0 (204) Offsite Power System 8.2.0 (205) Compliance with GDC 5 Resolved (SER) 8.2.1 (SSER 13)

(206) Compliance with GDC 17 Open (NRR) (SER) 8.2.2 (SSER 2)

(SSER 3)

(SSER 13)

(SSER 14)

(SSER 15)

(207) Compliance with GDC 18 Resolved (SER) 8.2.3 (208) Evaluation Findings Resolved (SER) 8.2.4 (209) Onsite Power Systems Resolved (SER) 8.3.0 (210) Onsite AC Power System Compliance with Open (NRR) (SER) 8.3.1 GDC 17 (SSER 2)

(SSER 7)

(SSER 9)

(SSER 10)

(SSER 13)

(SSER 14)

(SSER 18)

(SSER 20)

(211) Onsite DC System Compliance with Resolved (SER) 8.3.2 GDC 17 (SSER 2)

(SSER 3)

(SSER 13)

(SSER 14)

(212) Evaluation Findings Open (NRR) (SER) 8.3.3 (SSER 2)

(SSER 3)

(SSER 7)

(SSER 13)

(SSER 14)

(SSER 15)

(SSER 16) 1-12

Issue Status Section (213) Station Blackout 8.4.0 (214) Auxiliary Systems Resolved (SER) 9.0.0 (SSER 10)

(215) Fuel Storage Facility 9.1.0 (216) New-Fuel Storage Resolved (SER) 9.1.1 (217) Spent-Fuel Storage Open (NRR) (SER) 9.1.2 (SSER 5)

(SSER 15)

(SSER 16)

(218) Spent Fuel Pool Cooling and Cleanup Open (NRR) (SER) 9.1.3 System (SSER 11)

(SSER 15)

(219) Fuel-Handling System Open (NRR) (SER) 9.1.4 (SSER 3)

(SSER 13)

(220) Water Systems 9.2.0 (221) Essential Raw Cooling Water and Raw Open (NRR) (SER) 9.2.1 Cooling Water System (SSER 9)

(SSER 10)

(SSER 18)

(222) Component Cooling System (Reactor Open (NRR) (SER) 9.2.2 Auxiliaries Cooling Water System) (SSER 5)

(223) Demineralized Water Makeup System Resolved (SER) 9.2.3 (224) Potable and Sanitary Water Systems Resolved (SER) 9.2.4 (SSER 9)

(225) Ultimate Heat Sink Resolved (SER) 9.2.5 (226) Condensate Storage Facilities Resolved (SER) 9.2.6 (SSER 12)

(227) Process Auxiliaries 9.3.0 (228) Compressed Air System Resolved (SER) 9.3.1 (229) Process Sampling System Open (NRR) (SER) 9.3.2 (SSER 3)

(SSER 5)

(SSER 14)

(SSER 16)

(230) Equipment and Floor Drainage System Resolved (SER) 9.3.3 (231) Chemical and Volume Control System Resolved (SER) 9.3.4 (232) Heating, Ventilation, and Air Conditioning 9.4.0 Systems (233) Control Room Area Ventilation System Resolved (SER) 9.4.1 (SSER 9)

(234) Fuel-Handling Area Ventilation System Resolved (SER) 9.4.2 (235) Auxiliary Building and Radwaste Area Resolved (SER) 9.4.3 Ventilation System (236) Turbine Building Area Ventilation System Resolved (SER) 9.4.4 1-13

Issue Status Section (237) Engineered Safety Features Ventilation Open (NRR) (SER) 9.4.5 System (SSER 9)

(SSER 10)

(SSER 11)

(SSER 14)

(SSER 16)

(SSER 19)

(238) Other Auxiliary Systems 9.5.0 (239) Fire Protection Resolved (SER) 9.5.1 (SSER 10)

(SSER 18)

(SSER 19)

(240) Communications System Open (NRR) (SER) 9.5.2 (SSER 5)

(241) Lighting System Resolved (SER) 9.5.3 (242) Emergency Diesel Engine Fuel Oil Storage Open (NRR) (SER) 9.5.4 and Transfer System (SSER 5)

(SSER 9)

(SSER 10)

(SSER 11)

(SSER 12)

(243) Emergency Diesel Engine Cooling Water Resolved (SER) 9.5.5 System (SSER 5)

(SSER 11)

(244) Emergency Diesel Engine Starting Systems Open (NRR) (SER) 9.5.6 (SSER 5)

(SSER 10)

(245) Emergency Diesel Engine Lubricating Oil Open (NRR) (SER) 9.5.7 System (SSER 3)

(SSER 5)

(SSER 10)

(246) Emergency Diesel Engine Combustion Air Open (NRR) (SER) 9.5.8 Intake and Exhaust System (SSER 5)

(SSER 10)

(247) Steam and Power Conversion System 10.0.0 (248) Summary Description Resolved (SER) 10.1.0 (249) Turbine Generator Open (NRR) (SER) 10.2.0 (SSER 5)

(250) Turbine Generator Design Resolved (SER) 10.2.1 (SSER 12)

(251) Turbine Disc Integrity Resolved (SER) 10.2.2 (252) Main Steam Supply System Resolved (SER) 10.3.0 (253) Main Steam Supply System (Up to and Open (NRR) (SER) 10.3.1 Including the Main Steam Isolation Valves) (SSER 19)

(254) Main Steam Supply System Resolved (SER) 10.3.2 (255) Steam and Feedwater System Materials Resolved (SER) 10.3.3 (256) Secondary Water Chemistry Open (NRR) (SER) 10.3.4 (SSER 5)

(257) Other Features 10.4.0 1-14

Issue Status Section (258) Main Condenser Resolved (SER) 10.4.1 (SSER 9)

(259) Main Condenser Evacuation System Resolved (SER) 10.4.2 (260) Turbine Gland Sealing System Resolved (SER) 10.4.3 (261) Turbine Bypass System Open (NRR) (SER) 10.4.4 (SSER 5)

(262) Condenser Circulating Water System Resolved (SER) 10.4.5 (263) Condensate Cleanup System Resolved (SER) 10.4.6 (264) Condensate and Feedwater Systems Resolved (SER) 10.4.7 (SSER 14)

(265) Steam Generator Blowdown System Resolved (SER) 10.4.8 (266) Auxiliary Feedwater System Resolved (SER) 10.4.9 (SSER 14)

(267) Radioactive Waste Management 11.0.0 (268) Summary Description Open (NRR) (SER) 11.1.0 (SSER 16)

(269) Liquid Waste Management Resolved (SER) 11.2.0 (SSER 4)

(SSER 16)

(270) Gaseous Waste Management Resolved (SER) 11.3.0 (SSER 8)

(SSER 16)

(271) Solid Waste Management System Open (NRR) (SER) 11.4.0 (SSER 16)

(272) Process and Effluent Radiological Open (NRR) (SER) 11.5.0 Monitoring and Sampling Systems (SSER 16)

(SSER 20)

(273) Evaluation Findings Open (NRR) (SER) 11.6.0 (SSER 8)

(SSER 16)

(274) NUREG-0737 Items Open (NRR) (SER) 11.7.0 (275) Wide-Range Noble Gas, Iodine, and Open (SER) 11.7.1 Particulate Effluent Monitors (TMI Action (Inspection) (SSER 5)

Items II.F.1(1) and II.F.1(2)) (SSER 6)

(276) Primary Coolant Outside Containment Open (NRR) (SER) 11.7.2 (TMI Action item III.D.1.1) (SSER 5)

(SSER 6)

(SSER 10)

(SSER 16)

(277) Radiation Protection 12.0.0 (278) General Open (NRR) (SER) 12.1.0 (SSER 10)

(SSER 14)

(279) Ensuring that Occupational Radiation Open (NRR) (SER) 12.2.0 Doses Are As Low As Reasonably (SSER 14)

Achievable (ALARA)

(280) Radiation Sources Open (NRR) (SER) 12.3.0 (SSER 14) 1-15

Issue Status Section (281) Radiation Protection Design Features Open (NRR) (SER) 12.4.0 (SSER 10)

(SSER 14)

(SSER 18)

(282) Dose Assessment Open (NRR) (SER) 12.5.0 (SSER 14)

(283) Health Physics Program Open (NRR) (SER) 12.6.0 (SSER 10)

(SSER 14)

(284) NUREG-0737 Items 12.7.0 (285) Plant Shielding Open (NRR) (SER) 12.7.1 (SSER 14)

(SSER 16)

(286) High Range In-Containment Monitor Open (NRR) (SER) 12.7.2 (TMI Action Item II.F.1.(3)) (SSER 5)

(287) In-Plant Radioiodine Monitor (TMI Action Open (NRR) (SER) 12.7.3 Item II.D.3.3) (SSER 16)

(288) Conduct of Operations 13.0.0 (289) Organization Structure of the Applicant Resolved (SER) 13.1.0 (SSER 16)

(290) Management and Technical Organization Resolved (SER) 13.1.1 (291) Corporate Organization and Technical Resolved (SER) 13.1.2 Support (292) Plant Staff Organization Open (NRR) (SER) 13.1.3 (SSER 8)

(293) Training 13.2.0 (294) Licensed Operator Training Program Resolved (SER) 13.2.1 (SSER 9)

(SSER 10)

(295) Training for Nonlicensed Personnel Resolved (SER) 13.2.2 (296) Emergency Preparedness Evaluation 13.3.0 (297) Introduction Open (NRR) (SER) 13.3.1 (SSER 13)

(SSER 20)

(298) Evaluations of the Emergency Plan Open (NRR) (SER) 13.3.2 (SSER 13)

(SSER 20)

(299) Conclusions Open (NRR) (SER) 13.3.3 (SSER 13)

(SSER 20)

(300) Review and Audit Open (NRR) (SER) 13.4.0 (SSER 8)

(301) Plant Procedures 13.5.0 (302) Administrative Procedures Open (NRR) (SER) 13.5.1 (303) Operating and Maintenance Procedures Open (SER) 13.5.2 (Inspection) (SSER 9)

(SSER 10) 1-16

Issue Status Section (304) NUREG-0737 Items Open (SER) 13.5.3 (Inspection) (SSER 3)

(SSER 16)

(305) Physical Security Plan Open (NRR) (SER) 13.6.0 (SSER 1)

(SSER 10)

(SSER 15)

(SSER 20)

(306) Physical Security Organization 13.6.1 (307) Physical Barriers 13.6.2 (308) Access Requirements 13.6.3 (30Q9) Detection Aids 13.6.4 (310) Communications 13.6.5 (311) Test and Maintenance Requirements 13.6.6 (312) Response Requirements 13.6.7 (313) Personnel Reliability 13.6.8 (314) Land Vehicle Bomb Control Program 13.6.9 (315) Initial Test Program Open (SER) 14.0.0 (Inspection) (SSER 3)

(SSER 5)

(SSER 7)

(SSER 9)

(SSER 10)

(SSER 12)

(SSER 14)

(SSER 16)

(SSER 18)

(SSER 19)

(316) Accident Analyses 15.0.0 (317) General Discussion Resolved (SER) 15.1.0 (318) Normal Operation and Anticipated Open (NRR) (SER) 15.2.0 Transients (319) Loss-of-Cooling Transients Open (NRR) (SER) 15.2.1 (SSER 13)

(SSER 14)

(320) Increased Cooling Inventory Transients Resolved (SER) 15.2.2 (321) Change in Inventory Transients Open (NRR) (SER) 15.2.3 (SSER 18)

(322) Reactivity and Power Distribution Open (NRR) (SER) 15.2.4 Anomalies (SSER 4)

(SSER 7)

(SSER 13)

(SSER 14)

(323) Conclusions Resolved (SER) 15.2.5 (SSER 4)

(324) Limiting Accidents Resolved (SER) 15.3.0 (325) Loss-of-Coolant Accident (LOCA) Open (NRR) (SER) 15.3.1 (SSER 12)

(SSER 15) 1-17

Issue Status Section (326) Steamline Break Open (NRR) (SER) 15.3.2 (SSER 3)

(SSER 14)

(327) Feedwater System Pipe Break Open (NRR) (SER) 15.3.3 (SSER 14)

(328) Reactor Coolant Pump Rotor Seizure Open (NRR) (SER) 15.3.4 (SSER 14)

(329) Reactor Coolant Pump Shaft Break Open (NRR) (SER) 15.3.5 (SSER 14)

(330) Anticipated Transients Without Scram Open (SER) 15.3.6 (Inspection) (SSER 3)

(SSER 5)

(SSER 6)

(SSER 10)

(SSER 11)

(SSER 12)

(331) Conclusions Resolved (SER) 15.3.7 (332) Radiological Consequences of Accidents Resolved (SER) 15.4.0 (333) Loss-of-Coolant Accident Open (NRR) (SER) 15.4.1 (SSER 5)

(SSER 9)

(SSER 15)

(SSER 18)

(334) Main Steamline Break Outside of Open (NRR) (SER) 15.4.2 Containment (SSER 15)

(335) Steam Generator Tube Rupture Open (NRR) (SER) 15.4.3 (SSER 2)

(SSER 5)

(SSER 12)

(SSER 14)

(SSER 15)

(336) Control Rod Ejection Accident Open (NRR) (SER) 15.4.4 (SSER 15)

(337) Fuel-Handling Accident Open (NRR) (SER) 15.4.5 (SSER 4)

(SSER 15)

(338) Failure of Small Line Carrying Coolant Open (NRR) (SER) 15.4.6 Outside Containment (339) Postulated Radioactive Releases as a Open (NRR) (SER) 15.4.7 Result of Liquid Tank Failures (340) NUREG-0737 Items 15.5.0 (341) Thermal Mechanical Report (TMI Action Resolved (SER) 15.5.1 Item II.K.2.13) (SSER 4)

(342) Voiding in the Reactor Coolant System Resolved (SER) 15.5.2 during Transients (TMI Action (SSER 4)

Item II.K.2.17) 1-18

Issue Status Section (343) Installation and Testing of Automatic Resolved (SER) 15.5.3 Power-Operated Relief Valve Isolation (SSER 5)

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 Open (SER) 15.5.4 (TMI Action Item II.K.3.5) (Inspection) (SSER 4)

(SSER 16)

(345) Small-Break LOCA Methods (l1.K.3.30) and Open (SER) 15.5.5 Plant-Specific Calculations (I1.K.3.31) (Inspection) (SSER 4)

(SSER 5)

(SSER 16)

(346) Relative Risk of Low-Power Operation Resolved (SER) 15.6.0 (347) Technical Specification Open (NRR) 16.0.0 (348) Quality Assurance 17.0.0 (349) General Resolved (SER) 17.1.0 (350) Organization Resolved (SER) 17.2.0 (351) Quality Assurance Program Resolved (SER) 17.3.0 (SSER 2)

(SSER 5)

(SSER 10)

(SSER 13)

(SSER 15)

(352) Conclusions Resolved (SER) 17.4.0 (353) Maintenance Rule 17.6.0 (354) Control Room Design Review 18.0.0 (355) General Open (NRR) (SER) 18.1.0 (SSER 5)

(SSER 6)

(SSER 15)

(SSER 16)

(356) Conclusions Open (NRR) (SER) 18.2.0 (SSER 16) 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 Open (NRR)

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 Resolved (3) Design Baseline and Verification Program Resolved (4) Electrical Conduit and Conduit Support Resolved (5) Electrical Issues

a. Flexible Conduit Installations Open (NRR)

b. Physical Cable Separation and Electrical Isolation Open (NRR)

c. Contact and Coil Rating of Electrical Devices Resolved

d. Torque Switch and Overload Relay Bypass Capability Open (NRR) for Active Safety-Related Valves

e. Adhesive-Backed Cable Support Mount Resolved (6) Equipment Seismic Qualification Resolved (7) Fire protection Resolved (8) Hanger and Analysis Update Program Resolved (9) Heat Code Traceability Resolved (10) Heating, Ventilation, and Air-Conditioning Duct and Resolved Duct Supports (11) Instrument Lines Resolved (12) Prestart Test Program Plan 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 Light-Water Reactor Primary Coolant System Pressure Isolation Valves TVA Action: Submit Technical Specifications for NRC Review.

NRC Action: Review Technical Specifications (2) GL 80-77 Refueling Water Level - Technical Specifications Changes TVA Action: Submit Technical Specifications for NRC Review.

NRC Action: Review Technical Specifications (3) GL 82-28 Inadequate Core Cooling Instrumentation System TVA Action: Open NRC Action: Open (4) GL 83-28 Required Actions Based on Generic Implications of Salem Anticipated Transient without Scram Events (Screened into the Items 4 through 7)

(4.a) GL 83-28 (item 3.1) Post-Maintenance Testing (reactor trip system components)

TVA Action: Submit Technical Specifications for NRC Review NRC Action: Review Technical Specifications 1-23

Correspondence No. Title (4.b) GL 83-28 (3.2) Post-Maintenance Testing (All Surveillance Requirement Components)

TVA Action Submit Technical Specifications and NRC Review NRC Action Review Technical Specifications (4.c) GL 83-28 (4.2) Reactor Trip System Reliability (Preventive Maintenance and Surveillance Program for Reactor Trip Breakers)

TVA Action Submit Technical Specifications and NRC Review NRC Action Review Technical Specifications (4.d) GL 83-28 (4.5) Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment)

TVA Action Submit Technical Specifications and NRC Review NRC Action Review Technical Specifications (8) GL 86-09 Technical Resolution of Generic Issue B-59, (N-i) Loop Operation in BWRs and PWRs TVA Action Submit Technical Specifications for NRC Review.

NRC Action Review Technical Specifications (9) GL 88-20 Individual Plant Examination for Severe Accident Vulnerability TVA Action Open NRC Action Open (10) GL 88-20sl Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54 TVA Action Open NRC Action Open (11) GL 88-20s2 Individual Plant Examination for Severe Accident Vulnerability. Accident Management Strategies for Consideration in the Individual Plant Examination Process TVA Action Open NRC Action 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 Open NRC Action Open (13) GL 88-20s4 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities TVA Action Open NRC Action Open (14) GL 88-20s5 Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - 10 CFR 50.54(f)

TVA Action Open NRC Action Open (15) GL 89-04 Guidelines on Developing Acceptable In-service Testing Programs TVA 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.

NRC Action Open (16) GL 89-21 Request for Information Concerning Status of Implementation of Unresolved Safety Issue Requirements TVA Action TVA provided status of unresolved safety issues on September 26, 2008.

NRC Action Open (17) GL 90-06 Resolution of Generic Issues 70, "PORV [power-operated relief valve] and Block Valve Reliability," and 94, "Additional LTOP [low-temperature overpressure] Protection for PWRs" TVA Action Submit Technical Specifications for NRC Review NRC Action Review Technical Specifications 1-25

Correspondence No. Title (18) GL 92-08 Thermo-Lag 330-1 Fire Barriers TVA 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 NRC Action Open (19) GL 95-03 Circumferential cracking of Steam Generator (SG) Tubes TVA 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 NRC Action Open (20) GL 96-06 Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions TVA 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 NRC Action Open (21) GL 97-01 Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations TVA 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 NRC Action Open (22) GL 97-04 Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps Integrity During Design-Basis Accident Conditions TVA 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.

NRC Action Open 1-26

Correspondence No. Title (23) GL 97-05 SG Tube Inspection Techniques TVA 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 NRC Action Open (24) GL 97-06 Degradation of SG Internals TVA 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.

NRC Action Open (25) GL 98-02 Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition TVA 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.

NRC Action Open (26) GL 98-04 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; TVA Action the same approach will be proposed for use on WBN Unit 2 without change.

-Open NRC Action (27) GL 2003-01 Control Room Habitability TVA Action 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.

NRC Action Open 1-27

Correspondence No. Title (28) GL 2004-01 Requirements for SG Tube Inspection TVA 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.

NRC Action Open (29) GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation during Design-Basis Accidents at PWRs TVA 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.

NRC Action Open (30) GL 2006-01 SG Tube Integrity and Associated Technical Specifications TVA Action 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.

NRC Action Open (31) GL 2006-02 Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power TVA 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.

NRC Action Open (32) GL 2006-03 Potentially Nonconforming Hemyc and MT Fire Barrier Configurations TVA 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.

NRC Action Open 1-28

Correspondence No. Title (34) G L 2007-01 Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients TVA Action Open; Complete testing of four additional cables NRC Action Open (35) GL 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems TVA Action Open NRC Action Open (36) BL 92-01 and Failure of Thermo-Lag 330 Fire Barrier System to Perform its Supplement 1 Specified Fire Endurance Function TVA 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.

NRC Action Open (37) BL 96-01 Control Rod Insertion Problems (PWR)

TVA 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.

NRC Action Open (38) BL 01-01 Circumferential Cracking of Reactor Pressure Vessel (RPV)

Head Penetration Nozzles TVA 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.

NRC Action Open (39) BL 02-01 RPV Head Degradation and Reactor Coolant Pressure Boundary Integrity TVA 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.

NRC Action Open 1-29

1 1.

Correspondence No. Title (40) BL 02-02 RPV Head and Vessel Head Penetration Nozzle Inspection Program TVA 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.

NRC Action Open (41) BL 03-02 Leakage from RPV Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity TVA 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.

NRC Action Open (42) BL 04-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at PWRs TVA 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.

NRC Action Open (43) BL 07-01 Security Officer Attentiveness TVA 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.

NRC Action Open NUREG 0737 TMI Action Items (TVA letter dated September 14, 1981 applies to all of the following NUREG 0737 issues)

(44) NUREG 0737 Independent Safety Engineering Group Item I.B.1.2 TVA 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.

NRC Action Open 1-30

Correspondence No. Title (45) NUREG 0737 Control Room Design Review (CRDR)

Item I.D.1 TVA 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.

NIRC Action Open (46) NUREG 0737 Post-accident Sampling Item lI.B.3 TVA Action Submit. Technical Specifications for NRC Review NRC Action Review Technical Specifications (47) NUREG 0737 Containment Isolation Dependability Item II.E.4.2 TVA Action Submit Technical Specifications for NRC Review NRC Action Review Technical Specifications (48) NUREG 0737 Instrumentation for Detection of Inadequate Core-Cooling Item II.F.2 TVA Action Open N RC Action Open (49) NUREG 0737 Reporting SV/RV Failures/Challenges Item II.K.3.3 TVA Action Submit Technical Specifications for NRC Review NRC Action Review Technical Specifications (50) NUREG 0737 Anticipatory Trip at High Power Item II.K.3.10 TVA Action Submit Technical Specifications for NRC Review NRC Action Review Technical Specifications 1-31

Correspondence No. Title (51) NUREG 0737 Primary Coolant Outside Containment Item ll.0.1.1 TVA Action 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.

NRC Action Open (52) NUREG 0737 Control-Room Habitability Item III.D.3.4 TVA 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.

NRC Action Open (53) IEB 75-08 PWR Pressure Instrumentation TVA Action 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.

NRC Action *Review Technical Specifications (54) IEB 77-04 Calculation Error Affecting Performance of a System for Controlling pH of Containment Sump Water Following a LOCA TVA Action 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 NRC Action 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 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)

October 23, 2007 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)

May 8, 2008 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)

June 3, 2008 Letter, J. Williams to A. Bhatnagar (TVA), requesting supplemental information to support acceptance review for the Supplemental Environmental Statement. (ADAMS Accession No. ML081210270)

May 28, 2008 Letter, P. Milano to A. Bhatnagar (TVA), providing results of the staff's assessment of all generic communications items. (ADAMS Accession No. ML081490110)

June 20, 2008 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)

July 7, 2008 Letter, J. Williams to A. Bhatnagar (TVA), forwarding Order extending construction completion date of construction permit. (ADAMS Accession No. ML081500115)

August 25, 2008 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)

October 2, 2008 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 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)

February 11, 2009 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 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)

September 7, 2007 Letter, M. Bajestani to NRC, providing response to certain NRC bulletins and generic letters for Watts Bar Unit 2 (ADAMS Accession No. ML072570676)

September 7, 2007 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)

October 11, 2007 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 December 5, 2007 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)

January 29, 2008 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 February 1, 2008 Letter, M. Bajestani to NRC, requesting authorization to use ASME Code Case N-520-2 for expired N-type Certificates. (ADAMS Accession No. ML080370185)

February 15, 2008 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)

March 6, 2008 Letter, M. Bajestani to NRC, requests further extension of the construction permit to March 31, 2013. (ADAMS Accession No. ML080710489)

March 13, 2008 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)

March 20, 2008 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)

May 8, 2008 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 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)

June 16, 2008 Letter, M. Bajestani to NRC, submitting additional information on regulatory framework for completion of construction and licensing activities. (ADAMS Accession No. ML081700293)

September 26, 2008 Letter, M. Bajestani to NRC, submitting regulatory framework for corrective action programs and special programs. (ADAMS Accession No. ML082750019)

October 30, 2008 Letter, M. Bajestani to NRC, submitting preservice inspection program plan. (ADAMS Accession No. ML083090046)

December 9, 2008 Letter, M. Bajestani to NRC, submits licensing basis preservation and construction refurbishment program plan. (ADAMS Accession No. ML083460177)

January 14, 2009 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 instructionson 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 mailingaddress; 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 researchersin 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, Suipplement 21 Safety Evaluation Report: Related to the Operation of Watts Bar Nuclear Plant, Unit 2 February 2009 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 OFFICIAL BUSINESS

(