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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Surry, Units 1 and 2, License Amendment, Revises Technical Specification Section 3.4.A.4.

November 1, 1999 Mr. J. P. O'Hanlon Senior Vice President - N._Iear Virginia Electric and Power Company * 5000 Dominion Blvd. Glen Allen, Virginia 23060SUBJECT:Distribution: See next page,SURRY UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: MINIMUM VOLUME OF SODIUM HYDROXIDE SOL...

Sections 7-8 - 10CFR50.59 Report & Safety Analysis Report (USAR) Revision for Fort Calhoun Station.

SECTION 7 INSTRUMENTATION AND CONTROLFORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORTSECTION 7 PAGE 1 OF 6Table of Contents7. INSTRUMENTATION AND CONTROL ................ 7.1 INTRODUCTION ............................ 7.2 REACTOR PROTECTIVE SYSTEM ............. 7.2.1 Gene...

Enclosure 1 (Coc 9226, Rev 1) to07/17/03 - Ltr K Asmussen, General Atomics, Certificate of Compliance No. 9226 (Rev No. 1) for the Model No. GA-4 Package. (71-9226) (L23619).

NRC FORM 618(8-2000)10 CFR 71U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCEFOR RADIOACTIVE MATERIAL PACKAGES1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9226 1 71-9226 USA/9226/...

GALL Report, Vol. 2, Section X

CHAPTER X(August 2000)TIME-LIMITED AGING ANALYSESEVALUATION OF AGING MANAGEMENTPROGRAMS UNDER 10 CFR 54.21(c)(1)(iii)X-1 DRAFT - August 2000Time-Limited Aging Analyses: Evaluation of Aging Management Programs Under10 CFR 54.21(c)(1)(iii) X.M1 Metal Fatigue of Reactor Coolant ...

Robinson Aug/Sept 2004-301 Exam 50-261/2004-301 FINAL Written Outlines.

Final SubmittalROBINSON AUG/SEPT 2004EXAM NO. 05000261/2004-301AUG. 27 - SEPT. 3, 2004FINAL SAMPLE PLANS / OUTLINESES-401 PWR Examination Outline Form ES-401-2FinalFacility: HB Robinson Date of Exam: 8/27/2004RO K/A Category Points I ITier Group K K K K K K A A 7 A G Total1 2 ...

Peach Bottom, Units 2 and 3, License Amendment, Elimination of Requirements for Post Accident Sampling System.

May 22, 2003Mr. John L. Skolds, President and Chief Nuclear OfficerExelon NuclearExelon Generation Company, LLC200 Exelon Way, KSA 3-EKennett Square, PA 19348SUBJECT: PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCEOF AMENDMENT RE: ELIMINATION OF REQUIREMENTS FOR...

Fermi Unit 2, License Amendment 46, Revises TS to Reflect Deletion of Special Test Exceptions-Oxygen Concentration 3/4.10.5.

November 28, 1989Docket No. 50-341 Mr. B. Ralph Sylvia Senior Vice President - Nuclear Operations Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166 Dear Mr. Sylvia:DISTRIBUTION Docket File NRC & Local PDRs PD31 Plant Gray EButcher MVirgilio PShuttleworth ...

License Renewal USA - Moscow - August 25 2010.

License Renewal in the United States License Renewal in the United States1Allen Hiser, Jr. Allen Hiser, Jr.Senior Technical Advisor Senior Technical AdvisorDivision of License Renewal Division of License RenewalOffice of Nuclear Reactor Regulation Office of Nuclear Reactor Reg...

Susquehanna, Unit 2 - Technical Requirements Manual.

Jan. 17, 2011HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2011-2403USER INFORMATION:Name: GERLACH*ROSE M EMPL#:028401 CA#:0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSE M 01/14/2011LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2...

Revision 0 to WCAP-16157-NP, "Stretch Power Uprate NSSS and BOP Licensing Report," Cover Page through Page 6.3-160.

Westinghouse Non-Proprietary Class 3WCAP-16157-NP January 2004Indian Point Nuclear GeneratingUnit No. 2Stretch Power U prateNSSS and BOP Licensing ReportWestinghouse Nonproprietary Class 3WCAP-1 6157-NPIndian Point Nuclear GeneratingUnit No. 2Stretch Power UprateNSSS and BOP L...

Nuclear Energy Institute's Proposals for Determining Limiting Pipe Break Size Used in Assessing Debris Generation Following a Design Basis LOCA (Tac No. MC1154).

March 4, 2004Mr. Antony PietrangeloNuclear Energy Institute1776 I Street, NWSuite 400Washington, DC 20006-3708SUBJECT: NUCLEAR ENERGY INSTITUTE’S PROPOSALS FOR DETERMINING LIMITINGPIPE BREAK SIZE USED IN ASSESSING DEBRIS GENERATION FOLLOWING ADESIGN BASIS LOCA (TAC NO. MC1154...

AP1000 Targeted ITAAC List 20091022.

NRO/CTSB/ITAACAP1000 Targeted ITAACRev. 15 Cerified Design233 Targeted ITAACTargeted ITAAC NumberDescription ITAAC Family2.1.2.1 Inspection: As-built RCS System functional arrangement 14A2.1.2.2a Inspection: RCS components (table) designed and constructed IAW ASME 6F2.1.2.2b I...

Updated Checklists - Administered Examination for the Prairie Island Nuclear Generating Plant Initial Examination - July 2007.

UPDATED CHECKLISTS - ADMINISTERED EXAMINATION FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT INITIAL EXAMINATION - JULY 2007 Chanqes on ES-301-2 Forms since 75 Day Submittal 1. 2. 3. 4. Replaced In-Plant JPM “k” Added the code “L” to Control Room JPM “f” Replaced Control Room...

IR 05000336-07-002 & 05000423-07-002, on 01/01/2007 - 03/31/2007; Millstone Power Station, Unit 2 and Unit 3; Surveillance Testing, Problem Identification and Resolution - NRC Integrated Inspection Report.

May 14, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear OfficerDominion Resources5000 Dominion BoulevardGlenn Allen, VA 23060-6711SUBJECT: MILLSTONE POWER STATION - NRC INTEGRATED INSPECTIONREPORT 05000336/2007002 AND 05000423/2007002Dear Mr. Christian:On March...

Regulatory Guide 1.206, Section C.IV.9, Regulatory Treatment of Non-Safety Systems (Document Comparison), Combined License Applications for Nuclear Power Plants (LWR Edition) (Preliminary Use).

WordPerfect Document Compare SummaryOriginal document: P:\RG 1.206 draft\C.IV.10.wpdRevised document: @PFDesktop\:MyComputer\C:\ADAMS\Cache\ML0625000130.wpdDeletions are shown with the following attributes and color: Strikeout, Blue RGB(0,0,255). Deleted text is sho...

2009/07/28 STP COL - RAI Response on 06.02.01.01.C-6

1PMSTPCOL PEmailsFrom: Tomkins, James [jetomkins@STPEGS.COM]Sent: Tuesday, July 28, 2009 7:41 PMTo: Muniz, Adrian; Sosa, Belkys; Dyer, Linda; Wunder, George; Eudy, Michael; Plisco, Loren; Anand, Raj; Foster, Rocky; Joseph, Stacy; Govan, Tekia; Tai, TomSubject: RAI Response on ...

2008/12/31-Vogtle ESP SNC Pre-Filed Hearing Exhibit SNC00080G, Vogtle Early Site Permit Application, Part 2 - Site Safety Analysis Report Appendix 2.5E.

Southern Nuclear Operating CompanyVogtle Early Site Permit ApplicationPart 2 – Site Safety Analysis Report2.5E -1 Revision 5December 2008Appendix 2.5E—AP1000 Vogtle Site Specific Seismic Evaluation ReportPrepared byWestinghouse Electric Company LLCOctober 2008 SNC00080GSouther...

Comanche Peak Supplement Response to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors."

Rafael FloresSenior Vice President& Chief Nuclear Officerrafaelflores @ Luminant.comLuminant PowerP 0 Box 10026322 North FM 56Glen Rose, TX 76043ý71m D, - S, "1T 254 897 5550C 817 559 0403F 254 897 6652CP-200901307TXX-09114Ref. # GL 2004-02September 10, 2009U. S. Nuclear Regu...

Proposed Tech Spec 2.7 re availability of electric power.

._,..2.0 'LIMITING CONDITIONS FOR OPERATION*9'2.7Electrical SystemsApolicabilityApplies to the availability of electrical power for the operation of plant components.ObjectiveTo define those conditions of electrical pcwer availability necessary to provide for safereactor opera...

IE Insp Repts 50-266/83-11 & 50-301/83-19 on 830923-1120. Noncompliance noted:failure to provide specific written exclusive-use instructions to drivers of exclusive-use shipments.

.. .. .. .- _ - _ - _ - _ - _ _ _ _ - _ - - - _ - -L:..,.i .U.S. NUCLEAR REGULATORY COMMISSIONREGION IIIReports No. 50-266/83-11(DRMSP); 50-301/83-19(DRMSP)Docket Nos. 50-266; 50-301 Licenses No. DPR-24; DPR-27Licensee: Wisconsin Electric Power Company231 West MichiganMilwauke...

Informs NRC of submitted GL 89-10 scope expansions & suppls info provided in util 180-day response to GL 95-07,dtd 960212.

Georgia Power Company*333 Piedmont Avenue, . Atlanta. Georgf a 30308-,Telephone 404 526-3195Mailing Address40 inverness Center Parkway,Post Othce Box 1295iBirmingham. Alabama 35201 ITelephone 205 668-5086iJ. D. Woodard tN mut'+m eccre srstem iSenior Vice PresidentIOctober 21, ...

Response to Houston Lighting Power second set of interrogatories & request for production of documents. Alleges void testing program violates 10CFR50,Part B. Certificate of Svc & supporting documentation encl.

_ _ _ _ _ _ _ - - _ _ - ____,. _so4Mo 09 7', ,g'-~e,.p.occx m o .c,Us:coUNITED STATES OF AMERICA-NUCLEAR REGULATORY COMMISSION IAPR 41980 : n'D,.*[gN[ &BEFORE THE ATOMIC SAFETY AND LICENSING P.0ARD qtmc.In the Matter of$ gg4HOUSTON LIGHTING AND POWER Docket Nos. 50-498COMPANY,...

Proposed findings of fact & conclusions of law on radiological health & safety issues & environ issues in form of initial decisions.Certificate of process encl.

i..'".. . - . . . ....'., .4"(,f-~February 13, 1 82+ CO2;'t/-f-'; ,. ;--NUCIZAR REGULATORY COMMISSION' , ~M, > h UNITED STATES OF AMERICA,'f-. . , .g ,7 . f). ~jQ"BEFORE THE ATOMIC SAFETY AND LICENSING BOARDt-v ., / .'In the Matter of'i'1.iTTy\HOUSTON LIGHTING & POWER COMPANYD...

Forwards response to safety evaluation re environ qualification of safety-related electrical equipment,per 810522 request & revision of data previously transmitted in 801031 & 810201 ltrs.Summary of open items encl.

. ____ __ - ____. . . . _ _ _ _ _ _ -o ~ARKANSAS POWER & LIGHT COMPANY IPOST OFFICE BOX 551 UTTLE ROCK ARKANSAS 7P203 (501) 371-4000September 14, 1981hYf h(,.2CAN098105'&>N. ' 41Director of Nuclear Reactor Regulation#'ATTN: Mr. Robert A. Clark, ChiefM@'\0Operating Reactcrs Bra...

Forwards results of BART evaluation model large break LOCA 10CFR50.46 analysis,demonstrating acceptability of upper-head injection removal in support of license amend. Info re sys behavior w/ & w/o upper-head injection encl.

~' *.y jv.Westinghouse. Water ReactorBa 355Electric CorporationDliisions"'"5""''"""*#''''a 15230 cassMarch 17, 1986,NS-NRC-86-3112SED-SA-86-094Phone: (412)-374-4868, . . -Mr. Carl BerlingerReactor Systems BranchjUSNRC Division of IWR Licensing-AOffice of Nuclear Reactor Regula...