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Davis-Besse, Unit 1, License Amendment 93, Revises Immediate Reporting Requirements and Incorporates New Reporting System for Significant Events at Nuclear Power Plants.

Docket No. 50-346 Mr. Joe Williams, Jr. Vice President, Nuclear Toledo Edison Company Edison Plaza - Stop 712 300 Madison Avenue Toledo, Ohio 43652 Dear Mr. Williams:April 8, 1986 DJ S N tR DR L PDR PBD-6 FMi ragl i a OELD OPA LHarmon ACRS-10 JPartlow1h3WJones FOB, PWR-B RDig...

Proposed findings of fact & conclusions of law in form of partial initial decision (hydrogen control).Certificate of Svc encl.

,15-DOCKETEDJune 3,Ul %UNITED STATES OF AMERICA WN -5 All :00NUCLEAR REGULATORY. COMMISSION- GFFICE cr SECRr:ThR>00CMEilNG & SEPVM,F'BEFORE THE ATOMIC SAFETY AND LICENSING BOARD. BRANCHIn the Matter of)bTHE CLEVELAND ELECTRIC Docket Nos. 50-440ILLUMINATING COMPANY, ET AL.)50-4...

IR 05000338/2002-006, IR 05000339/2002-006, 05000280/2002-006 & 05000281/2002-006, Virginia Electric & Power Co., Glen Allen, VA. Inspection on 02/08/2002 related to application for renewal. No violations noted.

1VEPCOMarch 25, 2002Virginia Electric and Power CompanyATTN: Mr. David A. ChristianSenior Vice President and Chief Nuclear OfficerInnsbrook Technical Center5000 Dominion BoulevardGlen Allen, VA 23060-6711SUBJECT: NORTH ANNA AND SURRY POWER STATIONS - NRC INSPECTIONREPORT 50-3...

CLOSEOUT OF IE BULLETIN 86-01:MINIMUM FLOW LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT REMOVAL PUMPS.

,-.NUREG/CR-5293Closeout of IE Bulletin 86-01:Minimum Flow Logic ProblemsThat Could DisableResidual Heat Removal PumpsPrepared by W.J. Foley, R.S. Dean, A. HennickPARAM ETER, Inc.U Nuclear Regulatory*in' E8E8'PDRCR-5293 R_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. -...

Virgil C. Summer Unit 1 Updated Final Safety Analysis Report, Chapter 15, Accident Analyses.

15-i Reset February 2018 TABLE OF CONTENTS Section Title Page 15.0 ACCIDENT ANALYSES 15.0-1 15.1 CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1-1 15.1.1 OPTIMIZATION OF CONTROL SYSTEMS 15.1-215.1.2 INITIAL POWER CONDITIONS ASSUMED IN ACCIDENT ANALYSES 15.1...

Revision 0 to Calculation NEDC 99-032, "Review of Scientech Calculation 17080-M-02, Control Room Habitability and Offsite Dose for a Fuel Handling Accident."

ATTACHMENT 1 DESIGN CALCULATION COVER SHEET Title: Review of Scientech Calculation 17080-M-02, Calculation No: NEDC 99-032 Control Room Habitability and Offsite Dose for a Fuel Handling Task Identification No: N/A Accident Design Change No: N/A System/Structure: HVAC, SGT, SC ...

Prairie Island, Units 1 & 2, License Amendments 61 & 55, Revises TSs Concerned with Steam Generator Tube Surveillance, Steam Exclusion System, Auxiliary Feedwater System Reporting Requirements, Administrative Controls, & Correct Typographical Errors.

L[CL.d r A O'A "Y-! , Y0, r,, `. LI,.- i Ia,, i L L- CO P YUNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555February 2, 1983Docket Nos. and 5Th3U6 Mr. D. M. Musolf Nuclear Support Services Department Northern States Power Company 414 Nicollet Mall - 8th Flo...

Application of the EPRI Risk-Informed ISI Methodology To: VC Summer (Class 1 and 2), Table of Contents - Figure 1-7.

APPLICATION OF THE EPRI RISK-INFORMED ISI METHODOLOGY TO: VC SUMMER (Class 1 and 2)Binder I of 2APPLICATION OF THE EPRI RISKINFORMED ISI METHODOLOGY TO VC SUMMER (Class 1 and 2)APPLICATION OF THE EPRI RISKINFORMED ISI METHODOLOGY TO VC SUMMER (Class 1 and 2)INTRODUCTION The en...

Diablo Canyon, Units 1 & 2, License Amendments 72 & 71, Amendments Revise Combined TSs by Removing Cycle Specific Information That is No Longer Applicable.

Docket Nos. 50-275 and 50-323August 6, 1992Mr. Gregory M. Rueger Senior Vice President and General Manager Nuclear Power Generation Business Unit Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Dear Mr. Rueger: SUBJECT: ISSUANCE OF A...

Reactors Safety Hydrogen Research in Canada - An Overview.

IAEA -IHMTFCV Cologne, 18-22 June 2001 15 April 2003 Hydrogen research Cologne June 2001r3.doc REACTOR SAFETY HYDROGEN RESEARCH IN CANADA – AN OVERVIEW C.K. CHAN, J. LOESEL SITAR AND G.W. KOROLL AECL Whiteshell Laboratories Pinawa, Manitoba Canada 1. Introduction A sci...

NRC Generic Letter 1980-082: Transmittal of Supplement No. 2 to IE Bulletin No. 1979-01B, "Environmental Qualification of Class 1E Equipment."

C'154k IW4 -/F\cUNITED STATESNUCLEAR REGULATORY COMMISSIONREGION I631 PARK AVENUEKING OF PRUSSIA, PENNSYLVANIA 19406September 30, 1980Docket Nos. 50-036&-S4200Consolidated Edison Company ofNew York, Inc.ATTN: Mr. Peter ZarakasVice President4 Irving PlaceNew York, New York 100...

Sequoyah, Units 1 & 2, Technical Specification Pages for Amendment Nos. 281 & 272, Deleting One Definition & Modify Several Subsections Contained in TS Section 6.0, Administrative Controls.

INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 ACTION ......................................................................................................................................... 1-1 1.2 AXIAL FLUX DIFFERENCE ......................................................

Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term.

Exeltnm.Exelon Generation wwwexeloncorp corn Nuclear4300 Winfield RoadWarrenville, IL 60555RS-03-053March 28, 2003U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Dresden Nuclear Power Station, Units 2 and 3Facility Operating License Nos. ...

Davis-Besse, RAI, Amendment Request Re Allowing Entry Into Mode 3 Operation During the Current Outage.

July 31, 2003Mr. Lew W. MyersChief Operating OfficerFirstEnergy Nuclear Operating CompanyDavis-Besse Nuclear Power Station5501 North State Route 2Oak Harbor, OH 43449-9760SUBJECT: REQUEST FOR ADDITIONAL INFORMATION - DAVIS-BESSE NUCLEARPOWER STATION (TAC NO. MB8953)Dear Mr. M...

Transfer to Cold Leg Recirculation During LOCA when RCS Temperature at least 200F and less than 350 F.

TRANSFER TO COLD LEG RECIRCULATION DURING LOCA WHEN RCS AOl 4.2.3TEMPERATURE AT LEAST 200 0F AND LESS THAN 350 *F REV. 5TABLE OF CONTENTSSTEP NO DESCRIPTION PAGE NO1.OPURPOSE ....................................................... 12.0SYMPTOMS/ENTRY CONDITIONS ...................

Forwards response to IE Bulletin 79-01B re environ qualification of Class IE equipment.Provides master list of electrical components.Will submit qualification data within 45 days after master list submitted.

_ . _ _ - _ _ - -Wc',Metropolitan Edison Company . , -j{Q' ('Middletown, Pennsylvan,a 17057f Post Office Box 480i717 944-4041Writer's Direct Dial NumberMarch 11, 1980TLL 111Office of Inspection and EnforcementAttn: Boyce H. Grier, DirectorRegion IU. S. Nuclear Regulatory Commi...

Amend 64 to PSAR.

._ _ .. _ _ - _ _ - .|PAGE REPLACEMENT GUIDE FORAMENDMENT 64CLINCH RIVER BREEDER REACTOR PLANTPRELIMINARY SAFETY ANALYSIS REPORT'(DOCKET NO. 50-537)1,,|Transmitted herein is Amendment 64 to Clinch River -BreederOReactor Plant Preliminary Safety Analysis Report,-Docket 50-537.A...

ENT000634 - Entergy, IP2, FSAR Update, Revision 25 (2014) [Excerpts].

IP2 FSAR UPDATE Chapter 4, Page 1 of 85 Revision 25, 2014 CHAPTER 4 REACTOR COOLANT SYSTEM 4.0 GENERAL DESCRIPTION The reactor coolant system, shown in Plant Drawing 9321-2738 [Formerly UFSAR Figure 4.2-1], consists of four similar heat transfer loops connected in parallel ...

"Rept on Torus to Drywell Vacuum Breakers Tests & Mods for Monticello Nuclear Generating Plant."

- .c e3' ''11 Re~gulatory,,!@_U[;hff'Yh!fh .hci%ip-100ll06,.>-~ .au ..,a o s -i1-73INORTHERN STATES POWER COMPANYMinneapolis, MinnesotaREPORT ON TORUS TO DRYWELL|!VACUUM BREAKERSTESTS AND MODIFICATIONSFOR |MONTICELID NUCLEAR GENERATING PIANT||Prepared by:D W JamesMarch 12, 197...

Forwards proposed addition to SSAR Chapter 19 addressing issue of design certification matl rept contents,reflecting GE understanding of disposition of road map issues discussed during GE/NRC meetings 930727-29 in San Jose.

---. .- - .- . -- -- - - - _ _ .-_ -}GE Nuclear Energycews rwc : ccwn, a ce 7 4.e e sv: m u smsAugust 25, 1993 Docket No. STN 52-001Chet Poslusny, Senior Project ManagerStandardization Project DirectorateAssociate Directorate for Advanced Reactorsand License RenewalOffice of t...

Proposed TSs re control room emergency ventilation sys.

. .-.,fENCLOSURE 2BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2'NRC DOCKET NOS. 50-325 & 50-324OPERATING LICENSE NOS. DPR-71 & DPR-62CONTROL ROOM EMERGENCY VENTILATION SYSTEM(NRC TAC NOS. M85143 AND M85144),TECHNICAL SPECIFICATION PAGES - UNIT 1),y0;iIoLff9303110122 930301'DRA...

Generic Issue Management Control System Report (FY 2013, Q1).

Enclosure GENERIC ISSUE MANAGEMENT CONTROL SYSTEM REPORT FOR FISCAL YEAR 2013 1st QUARTER OFFICE OF NUCLEAR REGULATORY RESEARCH Generic Issue Management Control System ii TABLE OF CONTENTS Description …..................................................

Redacted - AOS-FM9054, Rev H "Radioactive Material Transport Packaging System - Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages." Part 12 of 12.

4 CONTAINMENTThis chapter identifies the AOS Transport Packaging System containment systems and describes how thePackages comply with the containment requirements of 10CFR71 [4.1], under Normal Accidentconditions of transport (NCT) and Hypothetical Accident conditions (HAC) of...

Virgil C. Summer, Units 2 and 3, LAR 13-05 Request for License Amendment: Structural Modules Shear Stud Size and Spacing.

Alfred M. PagliaManager, Nuclear LicensingNew Nuclear DeploymentA SCANA COMPANYFebruary 14, 2013NND-13-006710 CFR 50.90ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3Co...

AREVA Design Control Document Rev. 5 - Tier 2 Chapter 11 - Radioactive Waste Management - Section 11.5 Process and Effluent Radiological Monitoring and Sampling Systems

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 5 Page 11.5-111.5 Process and Effluent Radiological Monitoring and Sampling SystemsThe process and effluent radiological monitoring and sampling systems monitor, record, and (for certain subsystems) control the release of...