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Revision 0 to Oyster Creek Nuclear Generating Station - Saphire 5.0 Probabilistic Risk Assessment Database for Internally Generated Events IRRAS-Level Load.

OYSTER CREEK "SAPHIRE 5-0 DATABASE IARPAS-LEFVEL LOAD March 20, 1995 OYSTER CREEK NUCLEAR GENERATING -STATION. SAPHIRE 5-. 0: "PROBABILISTIC RISK ASSESSMENT DATABASEFOR INTERNALLY GENERATED EVENTS-. I.RRAS-LEVEL LOAD Revision 0 Ri cha rd' D. Fowler, Richard S. Gregg. March2...

Final - RO & SRO Written

Susquehanna ILO NRC Exam - Question Repetition Analysis Region I examiners verified that the 2003 ILO exam to be administered in August 2003 did not contain an inappropriate number of questions repeated from the licensee’s two previous ILO exams (administered in August 2002 an...

Letter from Dennis L. Ziemann to I. R. Finfrock , the Commission issued the Amendment 44 to Provisional Operating Licnese DPR-16 for the Oyster Creek Nuclear Generating Station, TS modifies the definitions of shutdown and refueling conditions in Section

Docket No. 50-219 Mr. I. R. Finfrock, Jr. Vice President - Generation Jersey Central-Power & Light Company Madison Avenue At Punch Bowl Road Morristown, New Jersey 07960 Dear Mr. Finfrock:DISTRIBUTION Local PDR ORB #2 Reading NRR Reading, DEisenhut RHVollmer HSmith DLZiemann ...

St. Lucie Units 1 and 2 Revised Emergency Plan Implementing Procedures.

Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 a April 9, 2001 L-2001-082 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emerg...

Submittal of Fourth 10-year testing interval IST program, Revision 0, beginning February 22, 2004 for Turkey Point Unit 3 and April 15, 2004 for Turkey Point Unit 4.

esa~, , A -l I y BawFPL L-2004-04310 CFR 50.55a(f)U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D. C. 20555Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251Fourth-10 Year IntervalInservice Testing ProgramThe Turkey Point Units 3 and 4 Inse...

INITIAL SUBMITTAL OF THE SCENARIOS FOR THE D.C. COOK EXAMINATION - NOV/ DEC 2002.

INITIAL SUBMITTAL OF THE SCENARIOS FOR THE D. C. COOK EXAMINATION - NOV/DEC 2002Appendix D Scenario Outline Form ES-D-1Facility: Cook Plant Unit 1 & Unit 2Scenario No.: COOK02-02Examiners:Op-Test No.: Set IOperators:Initial Conditions: IC 36, 81% power Xenon Equilibrium, Tave ...

Draft - RO Written Exam (Folder 2)

Origin: R 0 SRO 0 Student Handout? Lower Order? Question ID: New Selected for Exam 0 Past NRC Exam? 6000023 #I The plant has been tripped from 30% power per AOP-2575, Rapid Downpower. The Crew has since transitioned to EOP 2526, Reactor Trip Recovery and is performing applicab...

Peach Bottom, Units 2 & 3, License Amendment Request 02-00049 re Revision of Normal Heat Sink Technical Specification Temperature Limit.

Exel 1l n Exelon Nuclear www.exeloncorp.com N ucl e ar 20o Exelon Way Kennett Square, PA 19348 10 CFR 50.90 March 19, 2002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Peach Bottom Atomic Power Station, Units 2 and 3 Facility Operating Li...

Dresden Station & Quad Cities, License Amendments 70, 62, 76, 70, Amendments Regards Changes to Modify TS to Provide Additional Surveillance Requirements for Safety-Related Hydraulic & Mechanical Snubbers.

Distribution: Local PDR L. Schneider Gray R. BevanD. Eisenhut ORB#2 Rdg J. Wetmore Extra L. EngleT. Barnhart-16 S. Norris ACRS-1O POConnorR. Diggs J. Hegner OPA HShawDocket File OELD NSIC DCrutchfield ORB#5 GrayDocket Nos. 50-237 50-249 50-254 50-2652 8 1982Mr. L. DelGeorge Di...

NUREG-1753, [1:2] Cover - Appendix C, Risk-Based Performance Indicators: Results of Phase 1 Development.

NUREG-1753Risk-Based Performance Indicators: Results of Phase 1 Development U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Washington, DC 20555-0001AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONSNRC Reference Material As of November 1999, you ...

Dresden, Units 2 & 3, License Amendments 120 & 116, Restructures Section 3/4.9 as Part of TS Improvement Program.

Docket Nos. 50-237 and 50-249 Mr. Thomas J. Kovach Nuclear Licensing Manager Commonwealth Edison Company-Suite 300 OPUS West III 1400 OPUS Place Downers Grove, Illinois 60515 Dear Mr. Kovach:October 29, 19:-, DISTRIBUTION: Docket Files J. Roe R. Barrett C. Moore PDIII-2 p/f D....

Draft - Section A Operating.

RO. Box 63Lycoming, New York 13093Constellation NMP-97924NuclearNine Mile PointNuclear StationA Member of theConstellation Energy GroupMr. Hubert J. MillerRegional AdministratorUSNRC Region I475 Allendale RoadKing of Prussia, PA 19406ATTENTION: Mr. John CarusoSUBJECT: NINE MIL...

CTR 2008/10, Rev. 2, "Safety Analysis Report for Packaging Safkeg-LS Design No. 3979A, Package Docket No. 71-9337." Part 1 of 4.

Safkeg-LS 3979A CTR 2008/10, Revision 2Docket No. 71-9337 September 2010Safety Analysis Report for PackagingSafkeg-LS Design No. 3979APackage Docket No. 71-9337Safkeg-LS 3979A CTR 2008/10, Revision 2Docket No. 71-9337 September 2010Safety Analysis Report for PackagingSafkeg-LS...

Delivery Order No. NRC-DR-03-10-072.

SOUCITATIONICONTRACTIORDER FOR COMMERCIAL ITEMS 1. REQUISTION NO. PAGE 1 OFOFFEROR TO COMPLETE BLOCKS 12,17, 23, 24, & 30 03-10-072 112. CONTRACT NO. 3. AWA "CTIVE DATE 4. ORDER NO. 5. SOLICITATION NUMBER 6. SOUCITATION ISSUE DATE.jftj D .. RC-DR-03-10-0727. FOR SOLICITATION ...

Robinson Initial Exam 2008-301 Draft Administrative Documents.

ES-401 Written Examination Quality ChecklistD -a)4 Form ES-401-6Facility: H. B. Robinson Date of Exam: 8/15/2008 Exam Level: RO SRO EiInitialItem Description b”c#1. Questions and answers are technically accurate and applicable to the facility. “2. a. NRC K/As are referenced fo...

Information on Proposed Changes for the AP1000 Design Control Document Rev. 18.

Westinghouse Westinghouse Electric CompanyNuclear Power PlantsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USAU.S. Nuclear Regulatory Commission Direct tel: 412-374-6206ATTENTION: Document Control Desk Direct fax: 724-940-8505Washington, D.C. 20555 e-mail: sisklrb@westinghou...

Point Beach, Units 1 & 2 - License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated With Extended Power Uprate.

February 25,201 0 POINT BEACH NRC 201 0-0022 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Recluest 26...

Vogtle Units 1 & 2 - Page Numbering Scheme Clarification for License Amendment Request for Adoption of TSTF-425-A, Rev. 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program.

Mark J. Ajluni, P.E. Southern Nuclear Nuclear Director Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 January 7, 2011 SOUTHERN'\ COMPANY Docket Nos.: 50-424 NL-10-2375 50-425 U. S. Nucle...

South Texas Project Units 3 & 4 COLA (FSAR), Rev. 2 - Chapter 19 - Final Safety Analysis Report- Tier 2 - Introduction- Section 19.2- Pages 1-38

Introduction 19.2-1STP 3 & 4 Final Safety Analysis Report 19.2 IntroductionThe information in this section of the reference ABWR DCD, including all subsections, and tables, is incorporated by reference with the following departure and supplements.STD DEP Admin (Table 19.2-1)1...

LaSalle, Units 1 & 2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation."

n® Nuclear RS-11-036 April 4, 2011 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 10 CFR 50.90 Subject: License ...

San Onofre Station, License Amendments, Revise TS 3/4.3.2, Engineered Safety Features Actuation System Instrumentation, Table 3.3-3.

_. November 2, IK Mr. Harold B. Ray Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P. 0. Box 128 San Clemente, California 92674-0128 SUBJECT: ISSUANCE OF AMENDMENT FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 (TAC NO...

Applicant's Answers to the ASLB Questions of 11/06/72, Watts Bar, Units 1 & 2.

-- 4-'APPLICANT' S ANSWERS TO THE ASLB QUESTIONSOF NOVEMBER 6, 1972In the Matter of TheTENNESSEE VALLEY AUTHORITY(Watts Bar Nuclear Plant Units 1 and 2)DOCKET NOS. 50-390, 50-3911 Environmental Question No. 12 "The first question is on page 3-5 of the environmental statementsu...

Watts Bar, Unit 2 - Amendment 98 to Final Safety Analysis Report, Section 3C - Pages 3.8.1-1 thur 3.8.4-182.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-97m3.8 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 tornado...

Versa-Pac SARP Section 1 R 4 August, 2010.

Century Versa-Pac Rev. 4 Page 1-i August 9, 2010 SECTION ONE GENERAL INFORMATION Table of Contents 1 GENERAL INFORMATION .....................................................1-1 1.1 Introduction...................................................................................

Part 2 of 4, 910013 B, GADR 55, Volume 1, "Consolidated Design Report for the Model FSV-1 Shipping Cask." Configurations A, B, C, D, and Volume 2, Configurations E, F and G

910013GADR 55 Volume ISECTION 4.0 CONTAINMENT4-1INc910013 NC GADR 55 Volume I 4.0 CONTAINMENT 4.1 CONTAINMENT BOUNDARY The following components of Model FSV-1 in Configurations A, B, C and D form the containment boundary as described in Section 1.0: Cask body Cask closure with...