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Motion for Admission of Contention No. 5 on Shield Building Cracking.

-1-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of First Energy Nuclear Operating Company (Davis-Besse Nuclear Power Station, Unit 1) Regarding the Renewal of Facility Operating License NPF-003 for a 20-...

SECY-11-0124 - Enclosure 1 Recommended Actions To Be Taken Without Delay From The Near-Term Task Force Report.

Staff Assessment of Near-Term Task Force Recommendations As directed by SRM-SECY-11-0093, U. S. Nuclear Regulatory Commission (NRC) staff reviewed the Near-Term Task Force (NTTF or Task Force) recommendations within the context of the NRC’s existing framework and gave consid...

Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report (FSAR), Amendment 105, 3.8 Design of Category I Structures.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-105m3.8 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...

Arkansas Nuclear One, Unit 1 - Issuance of Amendment No. 246, Adoption of Technical Specification Task Force (TSTF)…513, Revision 3, "Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation" (TAC No. ME6125).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 16, 2011 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 SUBJECT: ARKANSAS NUCLEAR ONE, UNIT NO.1 - ISSUANCE OF AMENDMENT RE: ADOPT...

Letter re Case Nos. R3-20110124-27, R3-20110124-27-NRD, R3-20110124-27-2 and R3-20110124-27-3.

Indian Point Energy Center450 Broadway, GSBP.O. Box 249n er y Buchanan, N.Y. 10511-0249Tel (914) 254-6700John A VentosaSite Vice PresidentAdministrationMarch 16, 2012[PEC-ADM- 12-009Edward Moore, P.E.Regional Spills EngineerDepartment of Environmental Conservation, Region Thre...

OFFICIAL EXHIBIT - CCS-050-00-BD01 - Appendix D - Scenario Outline - Form ES-D-1, Op-Test No: 2012-301 for Scenario 6.

United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Charlissa C. Smith (Denial of Senior Reactor Operator License) ASLBP #: 13-925-01-SP-BD01 Docket #: 05523694 Exhibit #: Identified: Admitted: Withdrawn: Rejected: Stricken: Other: CCS-...

Arkansas Nuclear One, Unit 2 - 2014-02 - Draft Written Exam.

• • Data for 2014 NRC RO/SRO Exam 21-Dec-13 Bank: 1 1925 I Rev: [QJ Rev Date: 1 9/26/2013 3:30:49 1 QID #: Author: foster Lie Level: [}] Difficulty:[]] Taxonomy:[EJ Source: I NEW Search looCE02K103 I t0CFR55: 1 41.8 I 41.10 I 45.3 \ Safety Function \ \ System Title: \Reactor T...

Proposed tech specs,supporting operation of facility at increased core rated thermal power of 3,588 MWt.

PROPOSED CHANGES TO THECOOK NUCLEAR PLANT UNIT NO. 1TECHNICAL SPECIFICATIONSVSO7i50009 9SO7iaPDR ADOCK 050003i5PPDR)f'3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS3/4.4 REACTOR COOLANT SYSTEMSAFETY VALVES-SHUTDOWNUMITINGCONDITION FOR OPERATION3.4.2 A mini...

Forwards "Rept of ISIs From 921029-940529," summarizing ISI activities performed at Cook Nuclear Plant Unit 1.

PR.IC)R.IMV*1ACCELERATED RIDS PROCESSING)~4REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9409010255 DOC.DATE: 94/08/24 NOTARIZED: NO DOCKETgFACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 050003+6AUTH.NAME AUTHOR AFFILIATIONpl~GXBSON,L.S. Xn...

"Steam Generator Repair Rept,Revision 6." Provides detailed description of onsite storage facility for replaced steam generator lower assemblies.

U.S. NUCLEAR REGULATORYCOMMISSIONDOCKET NOS.50-25050-251STEAM GENERATORREPAIR REPORTREVISION 6January 1929TURKEYPOINT UNITS 3&49013OOiZ1-U.S. NUCLEAR REGULATORYCOMMISSIONDOCKET NOS.50-25050-251STEAM GENERATORREPAIR REPORTREVISION 5Auguat 1978TURKEYPOINT UNITS 3&4U.S. NUCLEAR R...

Rev 1 to "Plant-Specific Technical Guidelines."

}HOPE CREEK GENERATING STATION9PLANT SPECIFIC TECHNICAL GUIDELINESJanuary 8, 1986Revision 18601310174 860128DR ADOCK 05004OPERATOR PRECAUTIONSGENERALThis section lists " Cautions which are generally applicable atall times.CAUTION #1Monitor the general state of the plant.If an ...

LER 98-011-00:on 981014,manual RT due to CCWS leak was noted.Caused by failure of one letdown cooler rupture disk. All letdown cooler rupture disks were replaced prior to plant restart.With 981113 ltr.

. _ - . . . _ .a 4I.''w_mDavis-Besse Nuclear Pdwer Stationy y 'M r=5S01 North State Route 2Oak Harbor, Ohio 43449-9760m,INP-33-98-011-00Docket No. 50-346License No. NPF-3November 13, 1998United States Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Ladi...

Clinton Power Station, Unit 1, Additional Information Supporting the Request for License Amendment Related to Application of the Alternative Source Term.

RS-05-033 10 CFR 50.90 March 30, 2005 U . S . Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 References : Clinton Power Station, Unit 1 Facility Operating License No . NPF-62 NRC Docket No . 50-461 Subject : Additional Information Suppor...

Unistar Nuclear - Calvert Cliffs Power Plant Unit 3 COLA (Tech Specs), Rev. 3 - Technical Specifications - Section 3.3 - Instrumentation

PS 3.3.1 CCNPP Unit 3 3.3.1-1 Amendment No. 0 COLA Revision 3 3.3 INSTRUMENTATION 3.3.1 Protection System (PS) LCO 3.3.1 The PS sensors, manual actuation switches, signal processors, and actuation devices specified in Table 3.3.1-1 shall be OPERABLE. APPLICA...

Forwards Tech Spec changes required for certification, changes representing further enhancement & optimization & list of SER sections which require updating.Remaining Tech Specs,except Section 6,accurately reflect as-built facility.

*9TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 37401400 Chestnut Street Tower IIApril 9, 1985Director of Nuclear Reactor RegulationAttention: Ms. E. Adensam, ChiefLicensing Branch No. 4Division of LicensingU.S. Nuclear Regulatory CommissionWashington, D.C. 20555Dear Ms. Ad...

Forwards proposed changes to Tech Specs & FSAR,including surveillance requirements & instrumentation trip setpoints. Changes will be reflected in Amend 56 to FSAR.

TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 37401400 Chestnut Street Tower IIMay 3, 1985Director of Nuclear Reactor RegulationAttention: Ms. E. Adensam, ChiefLicensing Branch No. 4Division of LicensingU.S. Nuclear Regulatory CommissionWashington, D.C. 20555Dear Ms. Adensa...

Response to Portion of NRC Request for Additional Information Letter No. 54 -Auxiliary Systems- RAI Numbers 9.1-9 S01, 9.1-10 S01, 9.1-11 S01, 9.1-17 S01, 9.1-18 S01, and 9.1-19 S01.

GE-Hitachi Nuclear Energy Americas LLCJames C. KinseyProject Manager, ESBWR LicensingPO Box 780 M/C J-70Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 06-309 Docket No. 52-0 10Supplement 2June 11, 2007U.S. Nuclear Regulatory CommissionDocument Con...

Oconee Nuclear Station, Technical Specification Bases (TSB) Change.

DAVE BAXTERVice President4Energy Oconee Nuclear StationDuke Energy CorporationON01 VP17800 Rochester HighwaySeneca, SC 29672864-885-4460May 14, 2008 864-885-4208 faxdabaxter@dukeenergy. comU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Attention: Document Control De...

2009/05/13 Indian Point LR Hearing - ACRS meeting summary

1IPRenewal NPEmailsFrom: Green, KimberlySent: Wednesday, May 13, 2009 4:22 PMTo: STROUD, MICHAEL DSubject: ACRS meeting summaryAttachments: ML091260359.pdfMike, Attached is the meeting summary that is publicly available in ADAMS (ML091260359). Kimberly Green Safety PM (301)...

2010/01/18 STP COL - Transmittal of Letter U7-C-STP-NRC-100015

1PMSTPCOL PEmailsFrom: Elton, Loree [leelton@STPEGS.COM]Sent: Monday, January 18, 2010 4:56 PMTo: Muniz, Adrian; Dyer, Linda; Wunder, George; Tonacci, Mark; Eudy, Michael; Plisco, Loren; Anand, Raj; Foster, Rocky; Joseph, Stacy; Govan, Tekia; Tai, TomSubject: Transmittal of Le...

Allied Technology Group, Inc., Consolidated Application for 10-142B Package.

ATG1~ 7/- yPOY ALLIED TECHNOLO GROUP May 31, 2002 Mr. E. William Brach, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards US Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Subject: Consolidated ...

Consolidated License Application for Framatome ANP, Inc. Model 51032-1 Shipping Container, EMF-52, Revision 7A.

Consolidated License Application forFramatome ANP, Inc. Model 51032-1Shipping ContainerMay 2003AtFRAMATOME ANPConsolidated License Applicationfor Framatome ANP, Inc.Model 51032-1 Shipping ContainerEMF-52Revision 7ACONSOLIDATED LICENSE APPLICATIONFORFRAMATOME ANP, INC.MODEL 510...

Transmittal of Big Rock Point Nuclear Power Plant Recordation, Historic American Engineering Record.

Consumers EnergyA CMS Energy Company Kurt M. HaasGeneral ManagerDecember 5, 2006Mr. Brian D. ConwayState Historic Preservation OfficerMichigan Historical CenterP.O. Box 30740Lansing, MI 48909-8240Dear Mr. Conway:In accordance with the Memorandum of Agreement (MOA) between the ...

2010/08/25 Areva EPR DC - FW: DRAFT RESPONSES FOR FSAR Chapter 9 Weekly NRC Telecon

1ArevaEPRDCPEm ResourceFrom: BRYAN Martin (EXTERNAL AREVA) [Martin.Bryan.ext@areva.com]Sent: Wednesday, August 25, 2010 3:20 PMTo: Tesfaye, GetachewCc: KOWALSKI David (AREVA)Subject: FW: DRAFT RESPONSES FOR FSAR Chapter 9 Weekly NRC TeleconAttachments: Blank Bkgrd.gif; DRAFT R...

Topical Report, NEDO-33201, Revision 6, "ESBWR Certification Probabilistic Risk Assessment," Chapter 21, Section 21A - Verification of the Transient CLCH Model through Section 21E.4 - Two-Phase Natural Circulation Flow in the BIMAC.

NEDO-33201 Revision 6 21A-1 21A VERIFICATION OF THE TRANSIENT CLCH MODEL In this Appendix, the transient CLCH model is verified with a sample of three experiments from the Integral Effects Tests (IET) series. This adds to the previous extensive validation of the original CL...