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Category:Final Safety Analysis Report (FSAR)
MONTHYEARWBL-23-053, Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version2023-11-0808 November 2023
Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version
ML23312A1462023-11-0808 November 2023
Updated Final Safety Analysis Report (UFSAR) Amendment 5 - Table of Contents
ML20323A3182020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Table of Contents
WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)2020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)
ML20323A3082020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program
ML20323A3142020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Table of Contents to Sec 3.7
ML20323A3192020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance
ML20323A3172020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Division of Responsibility (Dor), Abbreviations
ML20323A3112020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML20323A3222020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations
ML21123A2262020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.8 to 3.12 (Redacted)
ML20323A3152020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management
ML20323A3032020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System
ML20323A3052020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems
ML20323A3002020-10-29029 October 2020
Submittal of Amendment 3 to Updated Final Safety Analysis Report
ML20323A3202020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System
ML21123A2252020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Table of Contents to Sec 2.4 (Redacted)
ML20323A3012020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
ML20323A3092020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection
ML20323A3162020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses
ML20323A3102020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Sec 2.5, Geology, Seismology, and Geotechnical Engineering Summary of Foundation Conditions
ML20323A3062020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ML20323A3122020-10-29029 October 2020
Amendment 3 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications
ML20142A3892020-05-21021 May 2020
Wbnp PSAR, Chapter 12, Conduct of Operations
L-19-022, Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted2019-03-18018 March 2019
Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted
ML19060A1472019-02-19019 February 2019
Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 2 of 5
ML19060A1762019-02-18018 February 2019
Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 3 of 5
ML19060A1822019-02-18018 February 2019
Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 5 of 5
ML19039A1042019-02-0808 February 2019
Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 1 of 5
ML19060A1492019-02-0808 February 2019
Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 4 of 5
ML17334A1602017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 13, Conduct of Operations
ML17334A1732017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 8, Electric Power (Redacted)
ML17334A1622017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 14, Initial Test Program
ML17334A1692017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor
ML17334A1562017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted)
ML17334A1722017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls
ML17334A1582017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 11, Radioactive Waste Management
ML17334A1592017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 12, Radiation Protection (Redacted)
ML17334A1652017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 17, Quality Assurance
ML17334A1702017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System
ML17334A1632017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 15, Accident Analyses
ML17334A1572017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems
ML17334A1642017-11-0202 November 2017
Amendment 1 to Updated Safety Analysis Report, Chapter 16, Technical Specifications
ML15279A3042015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 1 of 2
ML15279A3072015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-556
ML15279A3182015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-579
ML15279A3192015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-583
ML15279A3082015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-571. Sheet 1 of 4
ML15279A3052015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 2 of 2
ML15279A3252015-09-11011 September 2015
Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-597
2023-11-08
[Table view] |
Text
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 027_TVA_WB_FSAR_Section_16.pdf 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1 16.2 PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1 16.3 RELOCATED SPECIFICATIONS 16.3-1 16.3.1 Discussion 16.3-1 16.3.2 Document Control 16.3-1 16.3.3 Changes to the Relocated Specifications 16.3-1 Table of Contents 16-i
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page THIS PAGE INTENTIONALLY BLANK Table of Contents 16-ii
WATTS BAR WBNP-76 LIST OF TABLES Section Title THIS PAGE INTENTIONALLY BLANK List of Tables 16-iii
WATTS BAR WBNP-76 LIST OF TABLES Section Title THIS PAGE INTENTIONALLY BLANK 16-iv List of Tables
WATTS BAR WBNP-91 LIST OF FIGURES Section Title THIS PAGE INTENTIONALLY BLANK List of Figures 16-v
WATTS BAR WBNP-91 LIST OF FIGURES Section Title THIS PAGE INTENTIONALLY BLANK List of Figures 16-vi
WATTS BAR WBNP-92 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)
PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1
WATTS BAR WBNP-69 THIS PAGE INTENTIONALLY BLANK PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-2
WATTS BAR WBNP-92 16.2 PROPOSED FINAL TECHNICAL SPECIFICATIONS This Section describes Watts Bars plan for implementation of the Restructured Standard Technical Specifications (RSTS) based on the Westinghouse Owners Group MERITS Program and NUREG-1431 in lieu of the previous Standard Technical Specification (STS) in NUREG-0452.
The RSTS (NUREG-1431) is structured for the broadest possible use on Westinghouse plants. Accordingly, the document contains specifications which may not be applicable to all plants. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. The values of parameters and variables which may vary because of plant design appear as either blanks or bracketed numbers throughout the RSTS for illustration purposes only.
During Technical Specification development for Watts Bar, specifications were removed as justified or added as required. The actual plant specific value for each parameter and variable was provided during the development process. A Proof and Review edition of the Watts Bar Technical Specifications was issued by NRC for review within NRC and Watts Bar. After resolution of the comments from this process, a Final Draft Technical Specification will be issued by NRC with a request for certification.
Watts Bar must certify the Technical Specifications prior to requesting an operating license. The Certified Technical Specification will be issued by the NRC as Appendix "A" of the Operating License.
Prior to issuance of the Final Draft Technical Specification, Watts Bar may maintain a controlled copy of the proposed Technical Specifications, based on the NRC approved changes from the Proof and Review version, for use in procedure development and training.
PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1
WATTS BAR WBNP-92 THIS PAGE INTENTIONALLY BLANK PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-2
WATTS BAR WBNP-94 16.3 RELOCATED SPECIFICATIONS 16.3.1 Discussion As part of the implementation of the improved Technical Specifications program, Watts Bar has relocated certain information from the previous Standard Technical Specifications (NUREG-0452) to separate controlled documents based on the Commission's Policy Statement for improvement of Technical Specifications for nuclear power plants.[1,2] The majority of relocated information is now contained in a separate document called the Technical Requirements Manual (TRM). Other information has been relocated into site procedures or other Technical Specification required programs such as the Offsite Dose Calculation Manual (ODCM), Fire Protection Report (FPR), and the Process Control Program (PCP) as permitted by generic guidance. These documents become effective upon receipt of the operating license. The following is a description of the administrative program for control and amending the relocated specification material. The requirements for changing the ODCM are specified in the Technical Specifications.
16.3.2 Document Control Overall control of the relocated material documents is in accordance with the procedures for control of documents. Changes to the TRM, ODCM, and FPR are issued on a replacement page basis to controlled document holders following approval of the change in accordance with TVA procedures.
16.3.3 Changes to the Relocated Specifications Activities at Watts Bar have the potential to affect the relocated specifications. These include design modifications, procedure changes, other licensing document changes, etc. Changes to the relocated material are controlled by procedures to ensure that appropriate reviews and approvals are obtained. The relocated material contained in the TRM may subsequently be relocated into other procedures and the TRM eliminated. Changes to the requirements of the relocated material are evaluated in accordance with 10CFR50.59.
Changes to the TRM are reported as required by TRM Section 5.0, Administrative Controls.
REFERENCES (1) "Interim Policy Statement on Technical Specification Improvements on Nuclear Power Reactors," Nuclear Regulatory Commission, 52 FR 3788, February 6, 1987.
(2) "Watts Bar Unit 1 Technical Specifications Criteria Application Report,"
WCAP-13470, August 1, 1992.
RELOCATED SPECIFICATIONS 16.3-1
WATTS BAR WBNP-92 THIS PAGE INTENTIONALLY BLANK 16.3-2 RELOCATED SPECIFICATIONS
