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Watts Bar Nuclear Plant (Wbn) - Unit 1 - Technical Specification (Ts) Change Ts-03-16, "Revision of Ultimate Heat Sink (Uhs) Temperature"
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 William R. Lagergren, Jr. Site Vice President, Watts Bar Nuclear Plant APR 0 7 2004 TVA-WBN-TS-03-16 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen: In the Matter of ) Docket No. 50-390 Tennessee Valley Authority ) WATTS BAR NUCLEAR PLANT (WBN) - UNIT 1 - TECHNICAL SPECIFICATION (TS) CHANGE TS-03-16, "REVISION OF ULTIMATE HEAT SINK (UHS) TEMPERATURE" Pursuant to 10 CFR 50.90, TVA is submitting a request for an amendment to WBN's License NPF-90 to change the Technical Specifications for Unit 1. The proposed TS change (TS 03-16) will revise the limiting condition for operation for TS Section 3.7.9, "Ultimate Heat Sink." The maximum essential raw cooling water (ERCW) temperature limit associated with Surveillance Requirement (SR) 3.7.9.1 will be annotated with a note allowing an occasional increase from 85 degrees Fahrenheit (0F) to 880F. This proposed change is based on recent evaluations of the ERCW system and the UHS functions and maximum temperatures that will satisfy the associated safety functions. In addition, an administrative change is proposed to clarify the maximum allowable internal containment pressure. Corresponding TS Bases changes are also included for the temperature increase for UHS and the containment pressure clarification including a minor change in the maximum calculated containment pressure resulting from the increased UHS temperature. 1--~56 Pa0ted.]n ,Ededpa U.S. Nuclear Regulatory Commission Page 2 APR 0 7 2004 TVA discussed its plans for this proposal in a meeting with NRC staff in August 2003. -
Analyzing the Energy Industry in United States
+44 20 8123 2220 [email protected] Analyzing the Energy Industry in United States https://marketpublishers.com/r/AC4983D1366EN.html Date: June 2012 Pages: 700 Price: US$ 450.00 (Single User License) ID: AC4983D1366EN Abstracts The global energy industry has explored many options to meet the growing energy needs of industrialized economies wherein production demands are to be met with supply of power from varied energy resources worldwide. There has been a clearer realization of the finite nature of oil resources and the ever higher pushing demand for energy. The world has yet to stabilize on the complex geopolitical undercurrents which influence the oil and gas production as well as supply strategies globally. Aruvian's R'search’s report – Analyzing the Energy Industry in United States - analyzes the scope of American energy production from varied traditional sources as well as the developing renewable energy sources. In view of understanding energy transactions, the report also studies the revenue returns for investors in various energy channels which manifest themselves in American energy demand and supply dynamics. In depth view has been provided in this report of US oil, electricity, natural gas, nuclear power, coal, wind, and hydroelectric sectors. The various geopolitical interests and intentions governing the exploitation, production, trade and supply of these resources for energy production has also been analyzed by this report in a non-partisan manner. The report starts with a descriptive base analysis of the characteristics of the global energy industry in terms of economic quantity of demand. The drivers of demand and the traditional resources which are used to fulfill this demand are explained along with the emerging mandate of nuclear energy. -
Sequoyah Nuclear Plant
i Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 JUL 2 72004 10 CFR 50.54(f) U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen: In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 50-328 50-390 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 AND WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - SIXTY-DAY RESPONSE TO NRC BULLETIN 2004-01, "INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS," DATED MAY 28, 2004 The purpose of this letter is to submit TVA's 60-day response to the subject bulletin for SQN and WBN, with the exception of that portion of the response identified by TVA in it.s extension request dated June 14, 2004. Specifically, as stated in the June 14 letter, TVA committed to sending a response within 60 days addressing Items (1)(a) through (1)(d) for SQN and WBN. TVA's response to Item (1)(a) would include the available information (e.g., Alloy 600/82/182 locations, joint configuration and design, etc.,) retrieved from plant records. The balance of the requested information would be obtained from the original equipment manufacturer (Westinghouse Electric Company [Westinghouse]). Westinghouse has projected that a comprehensive report would be provided to TVA by November 24, 2004. Accordingly, as committed to in the June 14 letter, TVA will submit a supplemental response within two weeks following receipt and subsequent confirmation of the information received from Westinghouse. -
Byron, Units 1 & 2, Dresden, Units 2 & 3, James A. Fitzpatrick, Lasalle
200 Exelon Way Exelon Generation ® Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a RS-19-089 JAFP-19-0084 August 27, 2019 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 N RC Docket Nos. 50-373 and 50-37 4 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 N RC Docket Nos. 50-352 and 50-353 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 Subject: Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI Reference: NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," dated July 28, 2004 U.S. Nuclear Regulatory Commission Request to Use a Provision of a Later Addenda of the ASME B&PV Code, Section XI August 27, 2019 Page 2 In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv), and the guidance provided in the referenced document, Exelon Generation Company, LLC (Exelon) requests NRC approval to use a specific provision of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, for the units identified above. -
Nrc Liaison Report
SC-2Mtg07-2_Att#10 NRC LIAISON REPORT • STP first company to step forward in decades seeking new reactor license The application, a 200,000-page document submitted on a single DVD, was filed on September 24. The staff and STP officials met October 11 for the first public meeting since the application was filed. NRC staffers outlined several issues during the meeting, including a lack of supporting documents for at least two sections, outdated data for one section, missing figures for another and, in one instance, the absence of state emergency preparedness plans that were cross-referenced in the application. • TVA Opts For AP1000 Design Instead Of Completing Partially Finished Existing Reactors. TVA is submitting the combined operating license request nearly two decades after work stopped in 1988 toward building two similar-sized reactors at Bellefonte. TVA officials determined that finishing those reactors, which the agency started building in 1973, would be too costly." Application will be the first involving construction of a Westinghouse AP1000 advanced reactor, made by Westinghouse Electric Co., which is owned by Japan's Toshiba Corp. • Grid Security A video released last month by CNN illustrates the potential danger to the power grid, experts say. While in the past, most had imagined a cyberattack might shut down patches of the US grid for a few days at worst, But the video shows a demonstration by the Idaho National Laboratory that a large electric generator shaking violently, spraying metal parts, and spewing smoke before grinding to a stop. The method of attack used in that demonstration could be replicated to destroy more and larger equipment, several experts say. -
Nuclear Power Summary – Licensing Actions August 2020
NUCLEAR POWER SUMMARY – LICENSING ACTIONS AUGUST 2020 Congressional Legislative Action: o August 2020: • The American Nuclear Infrastructure Act of 2020, which was heard by the Senate’s Committee on Environment and Public Works on August 5, 2020, will enable U.S. international leadership, preserve America’s uranium supply chain, reduce carbon emissions, and strengthen our economic, energy, and national security. • The Nuclear Energy Leadership Act (NELA), included in the National Defense Authorization Act (NDAA) for fiscal year 2021, was passed by the Senate on July 23, 2020. NELA will help facilitate the path to market for advanced reactors by allowing the federal government to be an early adopter of commercialized technologies; providing for needed scientific research facilities; demonstrating advanced reactor concepts; breaking down fuel availability barriers when the market cannot; and training the next generation of nuclear scientists. • The Nuclear Energy for the Future Act (HR 6796), which was introduced to the House on May 8, 2020, builds on the Nuclear Energy Innovation Capabilities Act (NEICA) to provide full authorization for the Versatile Test Reactor. • The Nuclear Energy Research and Development Act (HR 6097) was passed by the House Science, Space, and Technology Subcommittee on Energy on March 12, 2020 and forwarded to the full Committee. This act would authorize many programs within the Office of Nuclear Energy, including further research and development on the existing fleet of reactors, advanced reactors, hybrid energy systems, and advanced fuels. • The Integrated Energy Systems Act of 2019 (S 2702), which was heard by the Senate Committee on Energy and Natural Resources on December 17, 2019, would direct the Department of Energy to establish an integrated energy systems research, development, and demonstration program. -
TVA Labor Relation Supplements
Revised 01-31-2013 PROJECT AGREEMENT LABOR RELATIONS SUPPLEMENTS (LRSs not listed have been deleted) Number Subject Page LRS-2 Arbitrator Limitation Relative to Jurisdictional Issues ................................................................ 1 LRS-3 Call-By-Name ............................................................................................................................. 2 LRS-4 Staffing - Contractor vs. TVA ..................................................................................................... 3 LRS-5 Wage Determination .................................................................................................................. 4 LRS-16 Apprenticeship Programs ........................................................................................................... 5 LRS-17 Defined Incidental Work, Maintenance, & Office Work .............................................................. 8 LRS-21 Certified Apprenticeship Programs Approved to Receive Contributions From Contractors .... 11 LRS-24 Project Agreement Rates of Pay .............................................................................................. 13 LRS-25 Foremen Rates of Pay (Supervising Other Crafts) .................................................................. 14 LRS-26 Definition of First, Second, and Third Shifts (replaced 8/3/99 with Interpretation No. 21) ....... 15 LRS-27 Payroll Deductions for Political Action Committees ................................................................. 16 LRS-32 Injury - Pay -
Savannah River Site, 700/A Area, Site Administration, Safety, Security, And
SAVANNAH RIVER SITE COLD WAR HISTORIC PROPERTY DOCUMENTATION 700/A AREA SITE ADMINISTRATION, SAFETY, SECURITY, AND SUPPORT Aiken County, South Carolina NEW SOUTH ASSOCIATES 6150 East Ponce de Leon Avenue Stone Mountain, Georgia 30083 SAVANNAH RIVER SITE COLD WAR HISTORIC PROPERTY DOCUMENTATION NARRATIVE AND PHOTOGRAPHY 700/A AREA – SITE ADMINISTRATION, SAFETY, SECURITY, AND SUPPORT Aiken County, South Carolina Report submitted to: Washington Savannah River Company • Aiken, SC Report prepared by: New South Associates • 6150 East Ponce de Leon Avenue • Stone Mountain, Georgia 30083 Terri Gillett Mary Beth Reed Mark T. Swanson Steven Gaither May 25, 2007 • Final Report New South Associates Technical Report 1433 ii ABSTRACT ABSTRACT This documentation was prepared in accordance with a Memorandum of Agreement (MOA) signed by the Department of Energy–Savannah River (DOE-SR) and the South Carolina Historic Preservation Office (SHPO) dated February 17, 2004, as well as the Consolidated MOA of August 2004. The MOA stipulated that a thematic study and photographic documentation be undertaken on A Area historic properties 703-A and 708-A. In addition, a Cultural Resource Management Plan was accepted and signed by DOE-SR and the SHPO on December 9, 2004 calling for documentation of the remainder of the A Area buildings that were deemed eligible for listing in the National Register of Historic Places (NRHP) as contributing resources to a Savannah River Site (SRS) Cold War Historic District. The impetus for the study was the imminent decommissioning and/or dismantling of the majority of NRHP eligible buildings in A Area. The resulting narrative is based on field analysis, oral history, primary documentation and research. -
Electric Power Monthly December 1997
DOE/EIA-0226(97/12) Distribution Category UC-950 Electric Power Monthly December 1997 With Data for September 1997 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 mmwm OF m$ mumr is mmm This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. Contacts The Electric Power Monthly is prepared by the U.S. Department of Energy's Energy Information Administration. Questions and comments concerning the contents of the Electric Power Monthly may be directed to: Ms. Sandra Smith, Project Leader Energy Information Administration, EI-524 U.S. Department of Energy Washington, DC, 20585 Telephone number: (202)426-1173 Internet E-Mail number: [email protected] or the following subject specialists: Subject Contact Phone Number Internet E-Mail Electricity Supply and Demand Forecast.. Rebecca McNerney 202-426-1251 [email protected] Industry Developments Kenneth McClevey 202-426-1144 [email protected] New Electric Generating Units Karen McDaniel 202-426-1234 [email protected] U.S. Electric Utility Net Generation Melvin E. Johnson 202-426-1172 [email protected] U.S. Electric Utility Consumption of Fuels . Melvin E. Johnson 202-426-1172 [email protected] U.S. Electric Utility Stocks of Fuels Melvin E. Johnson 202-426-1172 [email protected] U.S. -
20071204-Ucs-Brief-Got-Water
GOT WATER? Nuclear power plants are usually built next to lakes, rivers, and oceans.1 Not for the scenic views that such locales provide, but because water can absorb the waste heat produced by the plants. Nuclear power plants consume vast amounts of water during normal operation to absorb the waste heat left over after making electricity and also to cool the equipment and buildings used in generating that electricity. In event of an accident, nuclear power plants need water to remove the decay heat produced by the reactor core and also to cool the equipment and buildings used to provide the core’s heat removal. This issue brief describes the reliance of nuclear power plants on nearby bodies of water during normal operation and under accident conditions. All of the 104 nuclear reactors currently licensed to operate in the United States are light2 water reactors. Sixty-nine (69) are pressurized water reactors (PWRs) and 35 are boiling water reactors (BWRs). In a PWR, water flowing through the reactor core is In a BWR, water flowing through the reactor core is heated by its thermal energy. Because this water is heated by its thermal energy and boils. The steam flows maintained under high pressure (over 2,000 pounds per from the reactor vessel to the turbine. The steam spins the square inch), it does not boil even when heated to over turbine, which is connected to a generator that produces 500ºF. The hot water flows from the reactor vessel and electricity. The steam exits the turbine into the condenser. enters thousands of metal tubes within the steam Water from the nearby lake, river, or ocean flows through generator. -
Dresden Nuclear Power Station, Units 2 & 3
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 July 19, 2017 Mr. Bryan C. Hanson Senior VP, Exelon Generation Co., LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3—NRC INTEGRATED INSPECTION REPORT 05000237/2017002 AND 05000249/2017002 Dear Mr. Hanson: On June 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Dresden Nuclear Power Station, Units 2 and 3. On June 30, 2017, the NRC inspectors discussed the results of this inspection with Mr. J. Washko and other members of your staff. The results of this inspection are documented in the enclosed report. Based on the results of this inspection, one issue was self-revealed and was evaluated under the risk significance determination process as having very low safety significance (Green). The NRC has also determined a violation is associated with this issue. Because the licensee initiated a condition report to address this issue, the violation is being treated as a Non-Cited Violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy. This NCV is described in the subject inspection report. If you contest the violations or significance of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555–0001, with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at the Dresden Nuclear Power Station. -
Ornl/Nsic-176
4 ggcBvePBtnc APR 291980 ORNL/NSIC-176 MASTER Descriptions of Selected Accidents that Have Occurred at Nuclear Reactor Facilities H. W. Bertini and Members of the Staff of the Nuclear Safety Information Center NUCLFAR SAFETY INFORMATION CENTER DIEmu'lhj \i 'uNLIMIlt.il c ORNL/NSIC-176 Contract No. W-7405-eng-26 Engineering Technology Division DESCRIPTIONS OF SFLEuTED ACCIDENTS THAT HAVE OCCURRED AT NUCLEAR REACTOR FACILITIES H. W. Bertini and Members of the Staff of the Nuclear Safety Information Center Date Published: April 1980 Prepared by the OAK RIDGE NATIONAL LABORArORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the DEPARTMENT OP ENERGY tP MTOWiOtl Cf THIS MCU«»T It IHWWTW iii CONTENTS (7 Page FOREWORD ...» v PREFACE . vli 1. INTRODUCTION 1 2. NUCLEAR REACTORS: FUNDAMENTALS .' 3 2.1 Basic Theory 3 2.2 The Components of a Nuclear Reactor 8 2.3 Radioactivity , 11 2.4 Electric Power Plants .... 16 2.5 Classification of Reactors 17 2.6 Light-Water Reactors for the Production of Electricity ..... 19 3. CENTRAL STATION POWER PLANTS. 32 3.1 Fuel Melting Incideat at the Fermi Reactor (1966) 32 3.2 Electrical Cable Fires at San Onofre 1 (1968) 33 3.3 Fuel Meltdown at St. Laurent (1969) 35 3.4 Uncovering of the Core at La Crosse (1970) 38 3.5 Seven Injured When Steam Nozzle Breaks at Robinson 2 (1970) 39 3.6 Discharge of Primary System into Drywell at Did 'en 2 (1970) 42 3.7 Turbine Damage Caused by Human Error at Robinson 2 (1970) 45 3.8 Construction Fire at Indian Point 2 (1971) 46 3.9 Valve Separations at Turkey Point 3 (1971) 47 3.10 Turbine Basement Flooded at Quad Cities V?I2) 48 3.11 Steam Generator Damaged in Hot Tests at Oconee 1 (1972) 49 3.12 Two Fatalities in Steam Line Accident at Surry 1 (1972) 50 3.13 Seawater Intrusion into Primary System at Millstone 1 (1972) ..