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Final As-Administered SRO Written Examination for the Duane Arnold Initial Examination - Jan/Feb 2005.

QF-1030-03 Rev. 3 (FP-T-SAT-30) WRITTEN EXAMINATION COVERSHEET Trainee Name: Employee Number: Site: DAEC Examination Number/Title: 57_05-ILC-SRO NRC-Written Training Program: Operations Course/Lesson Plan Number(s): Senior Reactor Operator, 60006 GRA...

IR 05000266-05-004, IR 05000301-05-004 on 04/01/2005 - 06/30/2005 for Point Beach Nuclear Plant, Units 1 and 2; Non-Routine Evolutions, Operability Evaluations, Refueling and Outage Activities, Surveillance Testing, and Other Activities.

August 10, 2005Mr. Dennis L. KoehlSite Vice PresidentPoint Beach Nuclear PlantNuclear Management Company, LLC6590 Nuclear RoadTwo Rivers, WI 54241-9516SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000266/2005004; 05000301/2005004 Dear Mr...

Susquehanna Steam Electric Station Unit 1, Technical Requirements Manual, Revision 2.

Aug. 19, 2005Page 1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2005-34581g R. {ORATION:GE H*ROSE M EMPL#:028401 CA#: 0363Add SA2P ne#: 254-TRANSMITTAL INFORMATION:TO: o 08/19/2005LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHA...

NUREG-0800, (50:237) Chpt 3, Section 3.7.4 Draft Rev. 2, Seismic Instrumentation, of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants. LWR Edition, Draft Report for Comment.

NUREG-0800(Formerly NUREG-75/087)U.S. NUCLEAR REGULATORY COMMISSIONSTANDARD REVIEW PLANOFFICE OF NUCLEAR REACTOR REGULATIONDRAFT Rev. 2 - April 1996USNRC STANDARD REVIEW PLANStandard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff r...

Waterford 3 - November 2004 - Final RO/SRO Written Examination.

Page 1 of 100 Waterford 3 Examination Question Examination Bank Examination Question Number 1 QUESTION ID: 6090 - A DESCRIPTION: Knowledge of the interrelations between a reactor trip and the following: Reactor Trip Status Panel AUTHOR: avest REVISION 1 REVISION DATE 9...

Correction to License and Technical Specification Pages for Susquehanna Steam Electric Station, Units 1 & 2.

May 29, 2003Mr. Bryce L. ShriverSenior Vice Presidentand Chief Nuclear OfficerPPL Susquehanna, LLC769 Salem BoulevardBerwick, PA 18603-0467SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - MAINTURBINE BYPASS SYSTEM OPERABILITY REQUIREMENTS (TAC NOS.MB6671 AND MB6672...

Monticello, License of Amendment, Adopts Proposed Requirements in TSTF-448, Revision 3 Regarding Control Room Envelope Habitability.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 17, 2009 Mr. Timothy J. O'Connor Site Vice President Monticello Nuclear Generating Plant Northern States Power Company 2807 West County Road 75 Monticello, MN 55362-9637 SUBJECT: MONTICELLO NUCLEA...

AREVA Design Control Document Rev. 1 - Tier 2 Chapter 10 - Steam and Power Conversion System - Section 10.4.9 Emergency Feedwater System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 1 Page 10.4-7510.4.9 Emergency Feedwater SystemThe emergency feedwater system (EFWS) supplies water to the steam generators (SG) to restore and maintain water level and to remove decay heat following the loss of normal fe...

Watts Bar, Unit 2 - Final Safety Analysis Report, Amendment 94, Section 9, Auxiliary Systems, Table of Contents through Figure 9.3-21.

Table of Contents 9-iWATTS BAR WBNP-76TABLE OF CONTENTSSection Title Page9.0 AUXILIARY SYSTEMS9.1 FUEL STORAGE AND HANDLING 9.1-19.1.1 New Fuel Storage 9.1-19.1.1.1 Design Bases 9.1-19.1.1.2 Facilities Description 9.1-19.1.1.3 Safety Evaluation 9.1-19.1.2 SPENT FUEL STORAGE 9....

Mitsubishi Heavy Industries, LTD.'s Responses to US-APWR DCD RAI No. 422-2823, Revision 0.

AkMITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANJanuary 21, 2010Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-10013Subject: MHI's Responses to US-APW...

06/04/2009 Technical Specification Task Force Presentation for Meeting to Discuss Status of Current and Planned TSTF Travelers, and Process and Administrative Issues of Mutual Interest.

6/4/20091Technical Specifications Task ForceA Joint Owners Group Activity TSTFTSTF/NRC MeetingJune 4, 20091Technical Specifications Task ForceA Joint Owners Group Activity TSTFAdministrative Issues26/4/20092Technical Specifications Task ForceA Joint Owners Group Activity TSTFT...

Task Order No. 004 Under Delivery Order No. NRC-42-07-481.

* . .ORDER FOR SUPPLIES OR SERVICES PAGE OF PAGESIMPORTANT: Mark all packages and papers with contract and/or order numbers, BPA NO. 1 21. DATE OF ORDER 2. CONTRACT NO. (If any) 6. SHIP TO.NRC-42-07-4813 a. NAME OF CONSIGNEE3. ORDER NO. MODIFICATION NO, 4. REQUISITIONIREFERENC...

Fort Calhoun, Technical Specifications Change, CH-AD-0003 Rev 62 and 63 are Being Issue.

To CHIEF PROJECT BRANCH EFacility FC Department :Address USNRC CHIEF PROJECT BRANCH E611 RYAN PLAZA DRIVE, SUITE 400ARLINGTON TX 76011-8064From : DOCCON Attention: Doc Management DistributionAddress : FC-2-3PASSPORT DOCUMENTTRANSMITTALPaqe: 1Hllllllllllllll 111tH H fU H1111111...

Responds to NRC 790929 request for addl info re fire protection program.W/23 oversize drawings.Drawings available in Central Files.

79 . POWER AUTHORITY OF THE 6TATE OF NEW YORK 10 COLUMBUS C0IIcLE NEW YORK, N. Y. 10019 (212) 397-6200TRUSTEES FREDERICK R. CLARK CHAIRMAN GEORGE L. INGALLS VICE CHAIRMAN RICHARD M. FLYNN ROBERT I. MILLONZI WILLIAM F. LUDOYOctober 23, 1978 IPO-163GEORGE T. BERRY GENERAL MANAG...

Watts Bar Initial Exam 2009-301 Draft Sim/In-Plant JPMs.

REV. 0 PAGE 1 0F 128 WATTS BAR NUCLEAR PLANT B.1.a B.1.a Withdraw Shutdown Banks REV. 0 PAGE 2 0F 128 WATTS BAR NUCLEAR PLANT B.1.a Task: Withdraw Shutdown Banks Alternate Path: Following failure of the group step counte...

St. Lucie Plant, Units 2, Draft Request for Additional Information on GL-2004-02.

From: Mozafari, Brenda Sent: Thursday, March 04, 2010 2:04 PM To: Frehafer, Ken; Eric.Katzman@fpl.com; john.laffrey@fpl.com Cc: Scott, Michael Subject: DRAFT - REQUEST FOR ADDITIONAL INFORMATION ON GL-2004-02 Eric and Ken, By two letters to the U.S. Nuclear Regulatory Commis...

AREVA Design Control Document Rev. 2 - Tier 2 Chapter 11 - Radioactive Waste Management - Section 11.3 Gaseous Waste Management Systems

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 2 Page 11.3-111.3 Gaseous Waste Management SystemsFission product gases and radiolytic decomposition gases (including xenon and krypton) are generated in the reactor, dissolve in the reactor coolant, and are transported t...

Attachment 1 Vol 10, Kewaunee Power Station Improved technical Specifications Conversion Section 3.5, Emergency Core Cooling System (ECCS), Rev. 1.

Summary of Changes ITS Section 3.5 Page 1 of 1 Change Description Affected Pages The changes described in the KPS response to question MEH-002 have been made. This change deletes ISTS SR 3.5.2.3 from the KPS ITS submittal. Pages 37, 41, 47, 50, 51, 61, and 65 Attachment 1, ...

AREVA Design Control Document Rev. 2 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.2.3 Safety Injection System and Residual Heat Removal System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Tier 1 Revision 2 Page 2.2-65 2.2.3 Safety Injection System and Residual Heat Removal System 1.0 Description The safety injection system and residual heat removal system (SIS/RHRS) is a safety-related system. The SIS/RHRS has four divi...

Mitsubishi Heavy Industries Responses to US-APWR DCD RAI No. 544-4267 Revision 0.

MIVTSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANApril 21, 2010Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-10114Subject: MHI's Responses to US-APWR D...

PPL - Bell Bend COLA, Rev. 1 - Part 04 - Technical Specifications and Bases

Bell Bend NuclearPower PlantCombined LicenseApplicationPart 4: TechnicalSpecifications and BasesRevision 1© 2008 UniStar Nuclear Services, LLC All rights reserved. COPYRIGHT PROTECTEDBBNPP © 2007 UniStar Nuclear Development, LLC. All rights reserved. Rev. 1COPYRIGHT PROTECTEDC...

Transmittal of ESBWR DCD Markups to Tier 1 and Chapters 2, 3, and 19 Related to GEH Internal Corrective Actions and Discussions with the NRC.

j %HITACHIGE Hitachi Nuclear EnergyRichard E. KingstonVice President, ESBWR LicensingPO Box 780 M/C A-65Wilmington, NC 28402-0780USAT 910 819 6192F 910 362 6192rick.kingston@ge.comMFN 10-253 Revision 1 Docket No. 52-010October 15, 2010U.S. Nuclear Regulatory CommissionDocument...

Toshiba Design Control Document Rev. 0 - Tier 1 - Chapter 02 - Certified Design Material for ABWR Systems - Section 02.04 - Core Cooling Systems

Core Cooling Systems 2.4-1RS-5146900 Rev. 0Design Control Document/Tier 1 ABWR2.4 Core Cooling Systems2.4.1 Residual Heat Removal SystemDesign DescriptionThe Residual Heat Removal (RHR) System has three separate divisions. The major functions of the RHR System are:(1) Contai...

Turkey Point, Units 3 and 4, Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel.

FPL,POWERING TODAY.EMPOWERING TOMORROW.*10 CFR 50.9010 CFR 50.91L-2009-093April 15, 2009U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D. C. 20555-0001Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251Emergency License Amendment Request No. ...

"Indian Point 3 Nuclear Power Plant Individual Plant Exam," Volume 2.

6ZX~=2f~aNew York Power AuthorityIndian Point 3 Nuclear Power Plaft Individual Plant ExaminationNEW YORK POWER AUTHORITY REACTOR ENGINEERING" NUCLEAR SYSTEM ANALYSIS GROUP JUNE, 1994VOLUME 2q f&xpXC7,Z:4,.P* e &p 16 .APPENDIX A REVIEW OF NRC COMMENTS ON THE INDIAN POINT PROBAB...