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LER 06-003-00 for Catawba Nuclear Station, Unit 1, re Technical Specification Violations Associated with Hydrogen Ignition System.

JAMES R. MORRISEner Vice PresidentCatawba Nuclear Station4800 Concord Rd. / CN01 VPYork, SC 29745-9635803 831 4251803 831 3221 faxFebruary 12, 2007U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555Subject: Duke Power Company LLC d/b/a Duke...

Response to Portion of NRC RAI Letter No. 69 Related to ESBWR Design Certification Application Safety Analysis - RAI Number 15.4-4.

GE EnergyProprietary NoticeThis letter forwards proprietaryinformation in accordance with1 OCFR2.390. Upon the removalof Enclosure 1, the balance of thisletter may be considered non-proprietary.James C. KinseyProject Manager, ESBWR LicensingPO Box 780 M/C J-70Wilmington, NC 28...

BEA Research Reactor Package (BRR) Safety Analysis Report, Revision 0, March 2009 AREVA Federal Services, LLC.

/".'--- vF!ADOCKET 71-9341R EVAL"IB EA Re searchPackageReactorIISafety Analysis ReportRevision 0.,-.AREVA Federal Servi.ces: LLCMarch 2009I-iaccoidaflas w .the Freedom of IfomiWI*Exem.tIons 4.POWPAiDocket No. 71-9341BRR Package Safety Analysis Report Rev. 0, March 2009TABLE ...

Draft "Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28...Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Kewaunee Nuclear Power Plant," technical evaluation rept.

SAIC-85/1524-9 REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2 "POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR KEWAUNEE NUCLEAR POWER PLANT (50-305) Technical Evalu...

Forwards response to request for clarification re App R exemption on HVAC exhaust fans,discussed w/NRC on 850906.

John D. O'Toole Vice President0Consolidated Edison Company of New York, Inc. 4 Irving Place, New York, NY 10003 Telephone (212) 460-2533January 10, 1986Indian Point Unit No. 2 Docket No. 50-247Mr. Hugh L. Thompson, Jr., Director Division of PWR Licensing - A Nuclear Reactor R...

"Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Indian Point Station,Unit 3 (50-286)."

0 0 SAIC-85/1518-2 REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2 "POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR INDIAN POINT STATION, UNIT 3 (50-286) Technical E...

Summary Report - 573rd Meeting of the Advisory Committee on Reactor Safeguards, June 9-11, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 July 12, 2010 The Honorable Gregory B. Jaczko Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: SUMMARY REPORT – 573rd MEETING OF T...

IMC 2515 Appendix D, Plant Status

Issue Date: 04/27/16 1 2515 Appendix D Effective Date: 07/01/16 NRC INSPECTION MANUAL IRIB INSPECTION MANUAL CHAPTER 2515 APPENDIX D PLANT STATUS 2515D-01 OBJECTIVES AND PHILOSOPHY OF PLANT STATUS ACTIVITIES The Reactor Oversight Process recognizes that resident insp...

Catawba and McGuire Nuclear Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task....

MNS-16-075 CNS-16-066 October 20, 2016 Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Renewed License Numbers NPF-35 and NPF-52 McGuire Nuclear Station, Un...

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75.

• • • 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY The Reactor Coolant System (RCS) is of primary importance with respect to its safety function in protecting the health and safety of the public. Quality standards of material selection, design, fabrication, and inspectio...

Nonproprietary "Summary Rept,Eagle 21 Process Protection Sys Upgrade for Diablo Canyon Power Plant Units 1 & 2."

WCAP-13615-R1ISUMMARYREPORTEAGLE 21PROCESS PROTECTION SYSTEM UPGRADEFOR DIABLOCANYON POWER PLANTUNITS 1 AND 2Revision 1January 1993Prepared by: Westinghouse Electric CorporationNuclear and Advanced Technology Division9302ii0025 930202PDR ADQCK 05000275P"PDRWestinghouse Electri...

Arkansas Nuclear One, Unit 2-2015-09-DRAFT-OUTLINES.

ES-401 PWR Examination Outline (RO) Form ES-401-2 Facility: Arkansas Nuclear One, Unit 2 Date of Exam: August 21, 2015 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G * Total A2 G* Total 1. Emergency & ...

NuScale Power, LLC Supplemental Response to NRC Request for Additional Information No. 9466 (eRAI No. 9466) on the NuScale Topical Report, "Non-Loss of Coolant Accident Analysis Methodology," TR-0516-49416, Revision 1.

RAIO-0719-66521July 31, 2019 Docket: PROJ0769U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockville PikeRockville, MD 20852-2738SUBJECT: NuScale Power, LLC Supplemental Response to NRC Request for AdditionalInformation No. 9466 (eRAI ...

Discusses submittal schedule for responses to Reactor Sys Branch open items on NUREG-0737 re reactor vessel vent, thermal mechanical rept,revised small break LOCA model & plant specific calculation per 10CFR50.46.

._. _- .- . - . - . . . . -_ - - .s...s'SOUTH CAROLINA ELECTRIC a gas COMPANYPOST OF FICE BC A 764CotuweiA. SOUTH CAROLINA 29218^we ,.Id.".$$Nc"cc- -February 19, 1981a u on. ~ .sMr. Harold R. Denton, DirectorOffice of Nuclear Reactor Regulation'U. S. Nuclear Regulatory Commiss...

Rev 1.0 to Chapters 10,11,12 & App F to "ODCM,Braidwood Station."

r-]8;i- .1-ERAIDWOODRevision 1.0- .*--January 1994.;_ j-:y .-1~[''BRAIDWOOD ANNEX INDEX ;IiPAGE RT:' VISION;CHAPTER 10',10-i1.010-11 1.010-iii.010-iv1.010-v 1.0[i10-1 1.010-2 1.010-3 1.010-4 1.0l ') - 5 1.O I10-6 1.010-71.0'10-8 1.0 '10-9 1.010-10 1.0!10-11 1.0t10-12 1.010-13 ...

Hope Creek - Draft - Outlines (Folder 2).

ES-401 Written Examination Outline Form ES-401-1 II Facility: Hope Creek Station Date of Exam: 03/05/2012 SRO-Only Points Tier Group K 1 K 2 K 3 ~j A2 G* Total ~=:::==*==~ 1. 1 3 3 4 3 4 3 20 4 3 7 Emergency & 1-------1-+--+---1 Abnormal Plant Evolutions 2 1 2 N/A 1 1 N/A 1 7 ...

Fermi, Unit 2 - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies (TAC NO. MF0770).

Mr. Joseph H. Plona UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 25, 2013 Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2-210 NOC 6400 North Dixie Highway Newport, Ml 48166 SUBJECT: FERMI, UNIT 2 -INTERIM STAFF...

IR 05000285-13-015; 08/11/2013 - 09/30/2013; on Fort Calhoun Station, Integrated Resident and Regional Report; Emergency Action Level and Emergency Plan Changes.

November 8, 2013 Louis P. Cortopassi, Site Vice President Omaha Public Power District Fort Calhoun Station FC-2-4 P.O. Box 550 Fort Calhoun, NE 68023-0550 Subject: FORT CALHOUN - NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/2013015 Dear Mr. Cortopas...

Indian Point Station, Unit 2 - Draft-Outlines (Folder 2).

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: Indian Point Unit 2 Printed: 12/1 0/2013 Date Of Exam: 02/10/2014 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* Total A2 G* 1. 1 3 3 3 3 3 3 18 3 3 Emergency 2 2 2 1 1 2 1 9 2 2 & N/A N...

Generic Issue Management Control System Report (FY 2013, Q2).

Enclosure GENERIC ISSUE MANAGEMENT CONTROL SYSTEM REPORT FOR FISCAL YEAR 2013 2nd QUARTER OFFICE OF NUCLEAR REGULATORY RESEARCH Generic Issue Management Control System ii TABLE OF CONTENTS Description …..................................................

Browns Ferry Nuclear Plant - Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-210 December 22, 2014 10 CFR 50.4 10 CFR 50.54(f) Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001   Browns Ferry Nuclear Plant, Units 1, 2, a...

Michael Meeks Examiner Notes for C Smith Scenario 6 [redacted].

/IlONMY Appendix 0 Scenario Outline Form ES-O-1 ~----------------~. Facility: Vogtle Scenario No.: _ ..... 6 __ Op-Test No.: 2012-301 Examiners: !!lilt/( titlES 11t-HJ1~ liP-Operators: a Initial Conditions: The plant is at 100% power, BOl, steady state operations, control rod...

Supplemental Information to the Final Notification of Full Compliance with Order EA-12-049,Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, et al

e,(~DUKE ~ ENERGY® CNS-16-022 March 31, 2016 Attention: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555-001 Duke Energy Carolinas, LLC (Duke Energy) Catawba Nuclear Station (CNS), Units 1 and 2 Docket Number(s) 50-413 and 50-414 Renewed Licens...

Insp repts 50-369/99-03 & 50-370/99-03 on 990328-0508. Non-cited violations noted.Major areas inspected:operations, maintenance,engineering & plant support.

r*..;l';U.S. NUCLEAR REGULATORY COMMISSIONREGION 11Docket Nos: 50-369,50-370License Nos: NPF-9, NPF-17Report No: 50-369/99-03,50-370/99-03Licensee: Duke Energy CorporationFacility: McGuire Nuclear Station, Units 1 and 2)Location: 12700 Hagers Ferry RoadHuntersville, NC 28078Da...

Insp repts 50-282/97-21 & 50-306/97-21 on 971022-1202.No violations noted.Major areas inspected:operations,maint, engineering & plant support.

. . -. . . . . .r'U.S. NUCLEAR REGULATORY COMMISSIONREGIONlli ;IDocket Nas:50 282; 50-306License Nos:DPR-42; DPR-60>.Report No: 50 282/97021(DRP); 50 306/97021(DRP)- Licensee:Northem States Power Company.Facility:Prairie Island Nuclear Generating Plant- -'Location: 1717 Wakona...