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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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Indian Point Nucler Generating Unit 2, Table LA of Removed Details & Less Restrictive Administrative Changes to the CTS.

Indian Point - Unit 2 LA-1 Section 1.0Categories for LA-Table1 - Details of system design and system description including design limits2 - Description of system or plant operation3 - Procedural details for requirements and related reporting problems4 - Administrative requirem...

E-mail from Pat Lyman, Entergy, to Rick Ennis, NRC (and others), Re: VY News, Wednesday, April 14, 2004.

L.',s'a'. 8._Vl 9w? Ve!l~ds^1 _4 UV _.......v...................... ... _v ....... .. , _ wuIu y pi_i , e ~ u . _ _ Page 1From: "Lyman, Pat" To: "_Power Uprate" ', "Al Chesley", "Al Parker" , "Alan Haumann", "Alan Robertshaw" , "Art Wiese", "Audra Williams" , "B. Cosgrove", "B...

TECHNICAL SPECIFICATION CHANGES TO PERMIT TEMPORARY RELIEF FROM DIFFERENTIAL TEMPERATURE SYSTEM OPERABILITY REQUIREMENT (TAC NOS. 75116/75117).

December 6, 1989Docket Nos. 50-387/388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Liqht Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dear Mr. Keiser:DISTRIBUTION Docket File NRC PDR LPDR PDI-2 Rdg. SVarga BBoger WButler MThadani(2)...

Turkey Point, Unit 4, Amendment No. 9 to Facility Operating License No. DPR-41.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHTF COMPANTY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. DPR-41 1. The Nuclear Regulatory Commission (the C...

LER 92-002-01:on 920220,interruption of one train of residual heat removal during unit 2 RCS draining operation occurred.Procedure D2 did not provide adequate guidance. Procedure D2.3 written for one-time use.W/920916 ltr.

--7..*.-,_Northem States Power Oxnpany414 Nicohet MallMinneapohs, Minnesota 55401 1927Te8ephone (612) 3304500Sentember 16, 199210 CFR Parc 50Section 50,73U S Nuclear Regulatory ComrnisaloilAttn: Document Conttol DeskWashington, DC 20S55PRAIRIE ISLAND NUCLEAR CENERATINC PLANTDo...

Insp Rpt-Callaway IR-00-001 Resident

March 7, 2000Garry L. Randolph, Vice President andChief Nuclear OfficerUnion Electric CompanyP.O. Box 620Fulton, Missouri 65251SUBJECT: NRC INSPECTION REPORT NO. 50-483/00-01Dear Mr. Randolph:This refers to the inspection conducted on January 9 through February 19, 2000, at th...

Vermont Yankee Nuclear Power Station - Technical Specification Proposed Change No.243 LPCI Operability During Hot Shutdown

VERMONT YANKEE NUCLEAR POWER CORPORATION 185 OLD FERRY ROAD, PO BOX 7002, BRATTLEBORO, VT 05302-7002 (802) 257-5271 December 7, 2000 BVY 00-112 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Subject: Vermont Yankee Nuclear Power Station Lic...

Farley Nuclear Plant, Emergency Plan Implementing Procedure FNP-0-EIP-9.0, Revision 47

Southern Nuclear Operating Company, Inc. Post Office Drawer 470 Ashford, Alabama 363124A SOUTHERNNi COMPANY Energy to Serve Your World"' FNP-079-NRC-DCMARCH 26, 2001DIRECTOR, OFFICE OF NRC ATT: DOCUMENT CONTROL DESK C/O JIM MCKNIGHT US NUCLEAR REGULATORY COMMISSION WASHINGTON...

Brunswick July-August 2001 Exam 50-325/ 2001-30 FINAL SRO written Exam With Answers

Site-Specific Written Examination Cover SheetI -1UI III L.JJ I-s-iU.S. Nuclear Regulatory Commission Site-Specific Written ExaminationAnnlicant InformationName: Region: II Date: 07/27/01 Facility/Unit: Brunswick 1 & 2 License Level: SRO Reactor Type: GE BWR-4 Start Time: Fi...

Catawba Nuclear Station, Units 1 and 2, Issuance of amendments Nos. 86 and 80, revising TSs to reflect fuel reloading for Catawba Unit 1's Cycle 6 operation with fuel manufactured by B&W Fuel Co and continue to reflect previously existing TSs for Unit 2.

Docket Nos. andMay 31, 1991 Distribution See next page50-413 50-414Mr. M.S. Tuckman Vice President Nuclear Operations Duke Power Company P.O. Box 1007 Charlotte, North Carolina28201-1007Dear Mr. Tuckman:SUBJECT: ISSUANCE OF AMENDMENT AND AMENDMENT NO. 80 NUCLEAR STATION, UNIT...

Oconee Units 1, 2, & 3, Licenses DPR-38, DPR-47 & DPR-55, Issuance of Amendments 174, 174, & 171, Add TS in Response to NRC GL 83-37 Providing Guidance on the Scope of TS for NUREG-0737.

tIU'ENSE AU C>. 'Y FZLE COPY UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 6, 1989O0 NO- P[!1OVEDocket Nos.: 50-269, 50-270 and 50-287 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte...

Monticello Nuclear Generating Plant, Emergency Plan Implementing Procedures Revisions.

NMC--I Committed to Nuclear ExcellenceMonticello Nuclear Generating Plant Operated by Nuclear Management Company, LLCAugust 27, 2001US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 2055510 CFR 50, Appendix E Section VMONTICELLO NUCLEAR GENERATING PLA...

Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2

October 28, 2020 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801 SUBJECT: WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 137 AN...

Forwards background info for Commissioner Carr visit to plant on 870522.

10(' ./%,UNITED STATES ,/'-NUCLEAR REGULATORY COMMISSIONo['$*REGION I|,o#[0,631 PARK AVENUE|%, KING OF PRUS$1A, PENNSYLVANIA 19406***.*j14 MAY 1987-1MEMORANDUM FOR: Thomas 0. Martin, Executive Coordinator for RegionalOperations, DEDROGRFROM: William F. Kane, Director| Division...

Rev 5 to CP&L-CED-M-01, "MLSB Analysis CR Dose Analysis to Support Power Uprate."

ENCLOSURE!BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62WITilDRAWAL OF REQUEST FOR LICENSE AMENDMENTREACTOR COOLANT SYSTEM SPECIFIC ACTIVITYiIOVA-0105, REVISION 5MAIN STEAM LINE BREAK ANALYSISCONTROL ROOM DOSE ANAL...

Fort Calhoun Station, Unit 1, License Amendment Request (LAR) 14-03, Proposed Change to Technical Specification 3.2, Table 3-5.

~~® jjiiiiu -- --Omaha Public Power District 444 South tffn Street Mall Omaha, NE 68102-2247 LlC-14-0041 April 30, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License ...

South Texas Project Units 3 & 4 COLA (FSAR), Rev. 12 - Tier 2 - Chapter 19 - Resp. to Severe Accident Policy Statement - Section 19.02 Introduction

Introduction 19.2-1STP 3 & 4 Final Safety Analysis Report19.2 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)19...

Peach Bottom, Unit 2 - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident.

RS-1 October 3 i , 4 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk 11 Rockville Pike Rockville, MD 20852 Peach Bottom Atomic Power Station, Unit 2 Renewed Facility Operating License No. DPR-44 NRG Docket No. 50-277 10 Subject: Supplemental Response to NRG Requ...

Non-proprietary "HB Robinson Unit 2 Extended Transfer to Cold Leg Recirculation Following Large Break LOCA."

SIEMENS EMF-94-157 H. B. Robinson Unit 2 Extended Transfer To Cold Leg Recirculation Following a Large Break LOCA September 1994 9710200119 971014 PDR ADOCK 05000261 P PDR Siemens Power Corporation Nuclear DivisionSiemens Power Corporation - Nuclear Division EMF-94-157 Issue D...

Summaries of facility design changes & special tests completed during 1980.

J .FACILITY DESIGN CHANGESNORTH ANNA POWER STATION UNITS 1 AND 2COMPLETED IN 1980DC 78-07 Feedwater Tilting Disc Check Valve Modification (Unit 1)Description: Three tilting disc check valves supplied by CraneManufacturing Company were reported by the supplier to be susceptible...

Proposed changes to STS re reactivity control sys.

A%%4me.J& /bo A W C #/- 74 // f/,-\Q-T "5 1. " "T?REACTIVITY CONTROL SYSTEMS, _'"'''''"'"]9?~)"dLIMITING CONDITION FOR OPERATION (Continued)ACTION (Continued)-2.-If the-inoperable control rod (s)-is-inserted;-within-cr,e-heur--disarm-the-associated-directional control-valvesaa...

Forwards responses to items requiring resolution resulting from NRC review of radiological emergency response preparedness plan published in Suppl 3 of NUREG-0798.Items reviewed w/F Kantor of NRC,in 840201 telcon.

O. yne H. JeroN cle atonsDetroitEdison EsEF5-February 23, 1984EF2 - 67,132Director of Nuclear Reactor RegulationAttention: Mr. B. J. Youngblood, ChiefLicensing Branch No. 1.Divicion of LicensingU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Dear Mr. Youngblood:Refer...

Proposed tech specs,removing main steam line high radiation monitor reactor scram & group isolation functions to improve availability of main condenser for removal of decay heat & to aid in minimizing inadvertent reactor scrams.

_ _ _ _ - _ _ _ _ _ _ _ _ - -ENCLOSURE 3PLAT 41 HATCH - UtilTS 1 AND 2NRC DOCKETS 50-321 AND 50-366OPERATING LICENSES DPR-57 AND NPF-5REQUEST TO REVISE TECHNICAL SPECIFICATIONSTO REMOVE THE MAIN STEAM LINE HIGH RADIATION MONITORREACJOR $3 RAM ANDl@UP ISOLATION FUNCTIONSREVISIO...

Amend 36 to Rev 8 to 23A6100, "ABWR SSAR."

-. . - - -@0GENuclear Energy23A6100 Rev. 8Mar.1996!Standardi|OSafety|AnalysisReportj:i!!:!!1j!O,ID DO 0520 1a,23A6100 Rev. 8ABWR standardsarery Analysis neportTable of Contents1.0 Introduction and General Description of Plant1.1 Introduction1.2General Plant Descripdon1.3Compar...

Issuance of Renewed Facility Operating License No. NPF-21 for Columbia Generating Station. Columbia LR Ltr to Applicant.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 22,2012 Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968 SUBJECT: ISSUANCE OF RENEWED FACILITY OPERATING LICENSE NO. NPF-21 FOR CO...