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SEQUOYAH NUCLEAR PLANT - REVISION TO THE TECHNICAL REQUIREMENTS MANUAL (TRM) (REVISIONS 8, 9, 10, 11, 12, AND 13).

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 April 5, 2001 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH...

Limerick Generating Station, Units 1 & 2 Emergency Response Procedure Revision 12 to ERP-101, "Classification of Emergencies."

Exekon,.Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348www.exeloncorp.comNuclear1 OCFR50, Appendix EJune 8, 2001Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555Subject: Limerick Gener...

Kewaunee Power Station License Amendment Request 211, "Radiological Accident Analysis and Associated Technical Specifications Change."

IA

Columbia Generating Station, Calculation, "Dose Calculation Database".

Page No.ENERGY 1.000a, NORTHWEST CALCULATION COVER SHEET Calculation No. NE-02-04-1People * Vision- SolutionsRevision No. 2Equipment Piece No. Project: Columbia I Quality Class: IDiscipline: NUCLEARRemarksTITLE/SUBJECT/PURPOSEDOSE CALCULATION DATABASEPurposeThe purpose of this...

Response to Request for Additional Information Regarding the Point Beach Nuclear Plant License Renewal Application (TAC Nos. MC2099 and MC2100).

Committed to NucleaExcellen Point Beach Nuclear PlantOperated by Nuclear Management Company, LLCAugust 31, 2004 NRC 2004-008410 CFR 54U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Point Beach Nuclear Plant, Units 1 and 2Dockets 50-266 and 50-...

Enclosure 2 - Revised DCD Section 1.C, Industry Operating Experience.

MFN 05-117 Enclosure 2 General Electric Company ENCLOSURE 2 MFN 05-117 Revised DCD Section 1.C, “Industry Operating Experience” Conditional Release – pending closure of design verifications 1C-1 APPENDIX 1C INDUSTRY OPERATING EXPERIENCE 1C.1...

Rev 0 to 26A6642AW, "ESBWR Design Control Document - Tier 2, Chapter 7, Instrumentation And Control Systems."

g GE Nuclear Energy ESBWR Design Control Document Tier 2 Chapter 7 Instrumentation And Control Systems (Conditional Release - pending closure of design verifications) 26A6642AWRevision 0August 200526A6642AW Rev. 00 ESBWR Design Control Document/Tier 2 7-i Contents 7. I...

Revised Subsection 1.2 of the Proposed SAR (rev.12b Draft).

HI-STAR SAR Proposed Rev. 12b (DRAFT) REPORT HI-951251 1.2-1 1.2 PACKAGE DESCRIPTION 1.2.1 Packaging The HI-STAR 100 System consists of an MPC designed for BWR or PWR spent nuclear fuel, an overpack that provides the containment boundary and a set of impact limiters that ...

Non-Proprietary version of NEDO-33080, Revision 1, "TRACG Qualification for ESBWR," January 2006.

GE EnergyDavid H. HindsManager, ES6WRPO Box 780 M/C L60Wilmington, NC 28402-0780USAT 910 675 6363F 910 362 6363david.hinds@ge.comMFN 06-004 Docket No. 52-010January 6, 2006U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555-0001Subject: NEDO-33080, Re...

Responds to 820430 request for addl info.Encl responses to NRC questions will be incorporated into PSAR,Amend 69, scheduled for submittal later in Jul 1982.

- - -v;?$o .ptamDepartment of EnergyWashington, D.C. 20545Docket No. 50-537HQ:S:82:065JUL 07 NMr. Paul S. Check, DirectorCRBR Program OfficeOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C. 20555Dear Mr. Check:RESPONSES TO REQUEST FOR ADDIT...

Proposed tech specs,revising 24-month fuel cycle.

f.t..Docket No. 50-423'B15162|t4!Attachment 1iMillstone Nuclear Power Station, Unit No. 3{,Proposed Revision to Technical Specifications e24-Month Fuel CycleMarked-Up Pages?!Li,May 1995#9505050185 950501PDRADOCK 05000423PDRpr: -.,!.Millstone Unit No. 3,Proposed Revision to Tec...

Surry Power Station Units 1 & 2, North Anna Power Station Units 1 & 2, Request to use Portion of Later Edition and Addenda of ASME Section XI.

October 9, 2006 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.: 06-856 N L&OSlETS : RO Docket Nos. : 50-2801281 50-3381339 License Nos.: DPR-32/37 N PF-417 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) SURRY POW...

NEDO-33201, Revision 4, "ESBWR Certification Probabilistic Risk Assessment," Section 21A, Verification of the Transient CLCH Model.

NEDO-33201 Rev 4 21A-1 21A VERIFICATION OF THE TRANSIENT CLCH MODEL In this Appendix, the transient CLCH model is verified with a sample of three experiments from the Integral Effects Tests (IET) series. This adds to the previous extensive validation of the original CLCH mo...

Transcript of 565th ACRS Meeting, September 11, 2009, Pages 1-94.

DISCLAIMER UNITED STATES NUCLEAR REGULATORY COMMISSION’S ADVISORY COMMITTEE ON REACTOR SAFEGUARDS The contents of this transcript of the proceeding of the United States Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards, as reported herein, is a record...

North Anna Initial Written Retake Examination, 2009-301 Final RO Written Exam.

ES-401Name:Site-Specific RO Written ExaminationCover Sheetu.s. Nuclear Regulatory CommissionSite-Specific RO Written ExaminationApplicant InformationForm ES-401-7Date: February 10, 2009 Facility/Unit: North Anna Units 1 &2Region:Start Time:I D II- [8J III D IV D Reactor Type: ...

Dresden, Units 2 and 3, Updated Final Safety Analysis Report (UFSAR), Revision 9, Chapter 7.0, Instrumentation and Controls.

DRESDEN — UFSAR Rev. 8June 20097.0 INSTRUMENTATION AND CONTROLSTABLE OF CONTENTSPage7-i7.0 INSTRUMENTATION AND CONTROLS7.1 INTRODUCTION 7.1-17.1.1 Identification of Systems 7.1-1a7.1.1.1 Protective Systems 7.1-1a7.1.1.2 Safe Shutdown 7.1-27.1.1.3 Display Instrumentation ...

Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report (FSAR), Amendment 103. Section 3.8 Design of Category I Structures through 3.8.4-182 Other Category I Structures.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-103m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornad...

Oconee Nuclear Station - Technical Specification Bases (TSB) Change.

Duke DAVE BAXTERVice PresidentOconee Nuclear StationDuke Energy CorporationONO0 VP17800 Rochester HighwaySeneca, SC 29672864-885-4460December 10, 2008 864-885-4208 faxdabaxter@dukeenergy.comU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Attention: Document Control D...

Revised "Offsite Dose Calculation Manual."

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. 0. BOX 215 BUCHANAN. N. Y. 10511 TELEPHONE: 914.739.8200INDIAN POINT 3 OFF SITE DOSE CALCULATION MANUAL 8.102020 7Offsite Dose Calculation ManaualTable of Contents Page Chapter 1 Set Points 1 1....

Application for withholding proprietary summary rept "Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling." Affidavit,response to 810710 confirmatory order & nonproprietary summary rept encl.

0Westinghouse Electric CorporationWater Reactor DivisionsNuclear Technology Division Box 355 Pittsburgh Pennsylvania 15230 July 21, 1981 CAW-81-43 Docket 50-247 DPR-26Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Phillips Building ...

Safety evaluation re proposed radwaste sys.Discharge of radioactivity to unrestricted areas will not satisfy ALARA guidelines.

jeINDIAN POINT NUCLEAR GENERATING PLANT UNIT 3 SAFETY EVALUATION5/13/73i(1124017875021 of ADOCK 0500028611.0 RADIOACTIVE WASTE MANAGEMENT 11.1 Design Objective and Criteria The radioactive waste management systems are designed to provide for the controlled handling and disposa...

Advises that AEC review of CP application is completed.Matl submitted is inadequate.Reply,in form of application amend, should address questions raised.

EORUAL : UNITED STATES _ . ATOMIC ENERGY COMMISSION WASHINGTON, D.C. 20545 ~~tES c IN REPLY REFER TO: Fcbrueiry 19, 1968 ,pcket No. 50-286 Consolidated Edison Company of New York, Inc. 4 Irving Place New York, New York 10003 Attention: Mr. Donham Crawford Administrative Vice...

Fire Protection Safety Evaluation Input for Wolf Creek Generating Station Regarding License Amendment request for Deviation from the Fire Protection Program Requirements (TAC ME3766).

February 7, 2011 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Alexander R. Klein, Chief /RA/ Fire Protection Branch Division of Risk Assessment Of...

Indian Point Nuclear Generating Unit No. 3 - Issuance of Amendment Re: Main Feedwater Isolation Valve Modifications (Tac No. MB0179)

Mr. Michael Kansler April 18, 2001Vice President andChief Operating OfficerEntergy Nuclear Operations, Inc.440 Hamilton AvenueWhite Plains, NY 10601SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OFAMENDMENT RE: MAIN FEEDWATER ISOLATION VALVE MODIFICATIONS(TAC N...

James A. Fitzpatrick Nuclear Power Plant, License Amendment, Elimination of Requirements for Post Accident Sampling.

May 16, 2003Mr. Michael KanslerSr. Vice President and Chief Operating OfficerEntergy Nuclear Operations, Inc.440 Hamilton AvenueWhite Plains, NY 10601SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - AMENDMENT RE:ELIMINATION OF REQUIREMENTS FOR POST ACCIDENT SAMPLING(TAC NO...