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Watts Bar, Unit 2, Final Safety Analysis Report, Amendment 107 - Section 3.8 - Design of Category I Structures through Figure 3.8.4-80.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-107m3.8 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 tornad...

E-mail 01/03/2012 Re: Oyster Creek 2.206 Petition - PRB Immediate Action Decision.

From: Richard WebsterTo: Lamb, JohnCc: Janet TauroSubject: FW: Oyster Creek 2.206 Petition - PRB Immediate Action DecisionDate: Thursday, January 03, 2013 5:24:44 PMAttachments: 19890900-oc-sourcebook.pdfJohn: Please see e-mail below from a nuclear expert.  Could you clarify w...

Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems.

CPS/USAR CHAPTER 05 5-i REV. 13, JANUARY 2009 CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS PAGE 5.1 SUMMARY DESCRIPTION 5.1-1 5.1.1 Schematic Flow Diagram 5.1-2 5.1.2 Piping and Instrumentation Diagram 5.1-3 5.1.3 Elevation Drawings 5.1 3 5.2...

South Texas Project, Units 1 and 2, Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191.

VSMmIFARDNuclear Operating CompanySouth Texas Pro/ed Ekctric Generating Station PO Bax 289 Wadsworth. Texas 77483 -January 31, 2013NOC-AE-1300295410 CFR 50.1210 CFR 50.46Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001South Texas ProjectUnits 1...

2013/01/28 Fermi COL - FW: 1/25/13 Fermi 3 Submittals

1PMFermiCOLPEm ResourceFrom: FermiCOL ResourceSent: Monday, January 28, 2013 2:56 PMTo: PMFermiCOLPEm ResourceSubject: FW: 1/25/13 Fermi 3 SubmittalsAttachments: NRC3-13-0002.pdf; NRC3-13-0003.pdf; NRC3-13-0004.pdf; FERMI3_CEUS_SSC_NRC_Data_Request_1.pdf; FERMI3_CEUS_SSC_NRC_D...

U.S. Nuclear Regulatory Commission Individual Examination Report, Form ES-303-1, Reactor Operator, Redacted. Part 1 of 3.

Individual Examination RenoñES-303. Rev. 9Form ES-03-1U.S. Nuclear Regulatory CommissionIndividual Examination ReportExamination Type (Initial or Retake)Reactor OperatorSenior Reactor Operator (SRO) InstantSRO UpgradeSRO Limited to Fuel HandlingFacilityDescriptionPage 1 of 12x...

Forwards application for proposed Amend 97 to License NPF-14.Amend revises Tech Specs to allow operation of facility until third refueling & insp outage w/o availability of HPCI sys.Fee paid.

REQUL RY INFORNATION DIBTRIBUT SYBTEN ( R IDB >ACCESSION NBR: 8705260070 DOC. DATE: 87/05/14 NOTARIZED: NO DOCKET ¹PAD IL: 50-887 Susquehanna Steam Electric Station, Unit I Pennstlva 05000887AUTH. NANE'UTHOR AFFILIATIONKENYON> 9. D. Pennsylvania Potoer 5 Light Co.RECIP. NANE R...

Peach Bottom Atomic Power Station, Unit 1 - Decommissioning Plan and Safety Analysis Report.

.. , ,• ·:•·''" .... I •,·.. • ' -~.' l-,~ ..•.• '· •• ~-..• ·•• , • ., ~, .• • .• '· ·•:')"'''' "'1,. , •.• •·'<-·: .. -:'',,;. ' ' ~ ,. PHILADELPHIA ELECTRIC COMPANY , _. , r!/ . itlt1{ ;'!Ci . .!J fJ 171- -· I 1, E:CWARD G. BAUER. JR. 2301 MARKC:T STREET VICE PRESIDENT AND ...

River Bend Station Spill Prevention Control Countermeasure Plan_R17.

ENTERGY OPERATIONS RIVER BEND STATION SPILL PREVENTION, CONTROL AND COUNTERMEASURE PLAN (SPCC) Revision 17 Prepared by: {AJ,.d~ William H. Spell, J r Reviewed by: 4:2 ~ ~ Adrainne J. Wilson Senior Management Certification [40CFRI12.7] Date Date This SPCC Plan has the full appr...

EA-17-101 - Qal-Tek Associates, LLC - Notice of Violation and Proposed Imposition of Civil Penalty - $22,400, NRC Special Inspection Report 030-34866/2017-001.

December 12, 2017 EA-17-101 Mr. Travis Snowder President/Chief Executive Officer Qal-Tek Associates, LLC 3998 Commerce Circle Idaho Falls, ID 83401 SUBJECT: NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY - $22,400, NRC SPECIAL INSPECTION REPORT 030-348...

Beaver Valley Unit 1 - Final Written Examination with Answer Key (401-5 Format) (Folder 3).

Beaver Valley Unit 1 NRC Written Exam (1LOT18) 1. As power decays after a reactor trip, which of the following describes (1) the MINIMUM time that it takes for the Source Range instruments to energize, and (2) the condition that would prevent the Source Range instruments from ...

Millstone Power Station - Integrated Inspection Report 05000336/2018004 and 05000423/2018004.

D. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 February 5, 2019 EA-16-090 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Dominion Energy, Inc. Innsbrook Technical Cent...

Monthly operating repts for Nov 1994 for Surry Power Station Units 1 & 2.

' l - - -VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-11 Approved: ~ ~C..G.___ n- 11--'i:1, Station Manager Date 9412190221 941212 1 PDR ADOCK 05000280 / - 8- - - -- - - ---- _ l:QfL ____ __ J \ 1 e Section TABLE OF CONTENTS e ...

Donald C. Cook, Units 1 and 2 - NRC Integrated Inspection Report 05000315/2019001 and 05000316/2019001.

May 7, 2019 Mr. Joel P. Gebbie Senior VP and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUBJECT: DONALD C. COOK NUCLEAR GENERATING PLANT, UNITS 1 AND 2—NRC INTEGRATED INSPECTION REPORT 05000315/2019001 AND 0...

Palisades Nuclear Plant, Revision 34 to Updated Final Safety Analysis Report, Chapter 5, Design of Structures, Systems, and Components.

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 32 SECTION 5.1 Page 5.1-1 of 5.1-43 5.1 GENERAL DESIGN CRITERIA 5.1.1 INTRODUCTION Appendix I to the original FSAR contained a comparison to 70 General Design Criteria (GDC) for Nuclear Power Plant Con...

Catawba Nuclear Station, Units 1 & 2, Revision 19 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection.

Catawba Nuclear Station UFSAR Chapter 12 (09 OCT 2016) 12 - i Table of Contents 12.0 Radiation Protection 12.1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 12.1.1 Policy Considerations 12.1.2 Design Considerations 12.1.3 ALA...

Forwards response to NUREG-0578 recommendations.Reactor vessel power operated safety relief valves are air operated & provided w/accumulators for operation despite temporary loss of plant air supply.

iVERMONT Y AN KEE NUCLEAR POWER CORI* ORATION,nSEv=NTY SEVEN GROVE STREET3 2.1RUTL AND. VERMONT 05701WVY 80-7RE PLY TO -ENGINEERING OFFICEJanuary 8, 1980 vuRNeixE RO AoWESTBORO M ASS ACHUSETTS 015 81TELEPHONE 417 366 9019Mr. Harold R. Denton, DirectorOf fice of Nuclear Reactor...

Cooper Nuclear Station - Issuance of Amendment No. 263 RE: Adoption of TSTF-514, Revision 3, "Revise BWR Operability Requirements And Actions For RCS Leakage Instrumentation" (EPID L-2019-LLA-0050)

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. John Dent, Jr. Vice President and CNO Nebraska Public Power District Cooper Nuclear Station 72676 648A Avenue Brownville, NE 68321 October 30, 2019 SUBJECT: COOPER NUCLEAR STATION - ISSUANCE OF AMENDME...

Hybrid Combined Email & Comments on Advanced Non-LWR Design Criteria Table.

From: Michael KellerTo: AdvancedRxDCComments ResourceSubject: [External_Sender] Comment - Advanced Reactor Design Criteria (ARDC)Date: Wednesday, June 01, 2016 12:35:39 PMAttachments: Hybrid Comments ARDC r2.pdfAs a developer of an advanced reactor, Hybrid Power Technologies i...

Proposed Tech Specs re operability of ATWS & recirculation pump trip sys.

ENCLOSURE 1PROPOSED TECHNICAL SPECIFICATIONS REVISIONSBROGANS FERRY NUCLEAR PLANTUNITS 1, .2, AND 3(TVA BFN TS 252)8808120267880804. PDRADOCK05000259'PrTABLE OF CONTENTS~Seotfo1.0 Definitions.~Pe e No1.0-1SAFETY LIMITS AND LIMITING SA TY SYSTEM~SETT NGS1.1/2.11.2/2.2Fuel Cladd...

Proposed Tech Specs deleting footnotes re surveillance interval extensions.

3/4 ' APPLICABILITYSURVEILLANCE REQUIREMENTSb. Surveillance intervals specified in Section Xl of theASME Boiler and Pressure Vessel Code and applicable Addenda forthe inservice inspection and testing activities requiredbytheASME Boiler and Pressure Vessel Code and applicable A...

"IPE of External Events (IPEEE)."

:···,·:: (. . INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) JUNE 1995 9507060372 950630 I PDR ADDCK 050002~5 : : . p PDR ' - -;,_..,,. .: .. • TABLE,OF CONTENTS SECTION 1.0 EXECUTIVE SUMMARY 1.1 Background and Objectives 1-1 1.2 Plant Familiarization 1-2 1.3 Overall ...

Forwards responses addressing 10 of 11 criteria from NUREG-0737,Item II.B.3 for redesigned post-accident sampling sys.Response to Criterion 6 currently being developed & will be submitted by 870331.

ACCESSION NBR:FAC IL: 50-25950-26050-296AUTH. NAMEQRIDLEY> R. L.RECXr . NAMEMULLER> D. R.REGULATORY ORMATION DISTRIBUTION SYS M (RIDS)8612300292 DOC. DATE: 86/12/19 NOTARIZED: NO DOCKET 0Brogans Fev rgNuclear Pouer Station> Unit 1> Tennessee 05000259Brogans Ferry Nuclear Power...

Virgil C. Summer Nuclear Station, Unit 1, Final Safety Analysis Report Updated Through April 30, 2017, Chapter 15, Table of Contents, Accident Analyses.

15-i Reset January 2017 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 15.1-2 15.1.2 INITIAL POWER CONDITIONS ASSUMED IN ACCIDENT ANALYSE...

Three Mile Island Nuclear Station, Unit 1, Revision 24 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.0-1 thru 5.8-5

TMI-1 UFSAR CHAPTER 05 5.0-1 REV. 18, APRIL 2006 5.0 CONTAINMENT SYSTEM AND OTHER SPECIAL STRUCTURES Containment for this unit is provided by the Reactor Building including its steel liner and the Reactor Building isolation systems. The concrete structure also provides sh...