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Ltr S E Sisley, EnergySolutions Products and Technology Group, Certificate of Compliance No. 9204, Revision No. 21 for the Model No. 10-160B Package (Docket 71-9204) (TAC L24770) w/ Encl 2 (SER).

OFFICIAL USE ONLY – SECURITY RELATED INFORMATION OFFICIAL USE ONLY – SECURITY RELATED INFORMATION December 27, 2013 Mr. Steven E. Sisley Cask Licensing Manager EnergySolutions Products and Technology Group Suite 100, Center Point II 100 Center Point Circle Columb...

Oyster Creek Nuclear Generating Station - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC No. MF0824).

Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 19, 2014 SUBJECT: OYSTER CREEK NUCLEAR GENERATING STATION -INTERIM STAFF EVALUATI...

South Texas Project, Units 1 and 2- Licensee Documents for December 12, 2012 Public Meeting (TAC Nos. ME7735 and ME7736).

PROJECT DOCUMENTATION COVER PAGE Document No: CHLE-015 Revision: 2 Page 1 of 42 Title: Volume 3.6 – GSI-191 License Submittal Documentation for Chemical Effects at STP Project: Corrosion/Head Loss Experiment (CHLE) Program Date: 26 Nov 2012 Client: South Texas Project Nuclea...

Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 24, Chapter 4 - Reactor Coolant System.

IP2 FSAR UPDATE Chapter 4, Page 1 of 85 Revision 24, 2013 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 ...

Indian Point Unit 2 - Revision 27 to Updated Final Safety Analysis Report, Appendix A for License Renewal.

IP2 FSAR UPDATE Page 1 of 33 Appendix A for License Renewal Revision 27, 2018 A.1 INTRODUCTION This appendix provides the information submitted in an Updated Final Safety Analysis Report Supplement as required by 10 CFR 54.21(d) for the Indian Point Energy Center (IPEC) ...

Proposed Tech Specs re inservice insp testing.

-_ _ s wam, ,0O|- -.., ,,EX11IDIT B,LICEICE AMENIEENT RIQUEST DATED AUGUST 30, 1977Exhibit B, attached, consists of revised and newly prepa nd pages ofthe Appendix A Technical Specifications as listed below. Ibese pagesincorporate the proposed changec.Pages11iiigVv11ix88899094...

Central Files version of "Accident Radiological Dose Assessment - Manual Method for Enrico Fermi Atomic Power Plant - Unit 2."

_ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . . ___ _ _ _ .CARCENTO LUNDYENOlNEERCcMicAeo..4>t4ACCIDENT RADIOLOGICAL DOSE ASSESSMENT -MANUAL METHOD FOR THE ENRICO FERMIATOMIC POWER PLANT - UNIT 2I;'THE DETROIT EDISON COMPANYENRICO FERMI ATOMIC POWER PLANT - UNIT 2Prepared by...

Forwards procedure changes,tests & experiments requiring SE completed during March 1993 for Quad-Cities Units 1 & 2. Summary of SE reported in compliance w/10CFR50.59 & 10CFR50.71(e).

u1eO 22710206 AvenueNorthCommonwealth Edisonound Cities Nuclear Power Station;Corcova, Illinois 61242Telephone 309/654-2241,!RJW-93-14!April 12, 1993 i:iU. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555SUBJECT:Quad Cities Nuclear Station Unit...

Documents info obtained at 820223 meeting w/NRC re environ qualification of safety-related electrical equipment.Info on equipment identified as requiring replacement,future testing or addl research encl.

r4,- 1398L-Carolina Power & Liget CompanyNAR 031932EOI.(MAR 09 N$'Of fice of Nuclear Reactor Regulation g g p quaseATTN:Mr. D. B. Vassallo, ChiefMEB f MOperating Reactors Branch No. 2United States Nuclear Regulatory Commission~Washington, D.C. 20555BRUNSWICK STEAM ELECTRIC PLA...

"Perry Stainless Steel Cladding Evaluation Rept."

March, 1982GAI Rsport No. 2388...PE12Y STAINLESS STEELCLADDING EVALUATION REPORT.Perry Nuclear Power PlantUnits 1 and 2-The Cleveland Electric Illuminating CompanyPrepared by:-,Gilbert Associates, Inc.P. O. Box 1498Reading, Pennsylvania 196038203250337 820315PDR ADOCK 05000440...

Hope Creek, Revision 24 to Updated Final Safety Analysis Report, Section 1, Introduction & General Description of Plant

SECTION 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS Section Title Page 1.1 INTRODUCTION 1.1-1 1.2 GENERAL PLANT DESCRIPTION 1.2-1 1.2.1 Site Characteristics 1.2-1 1.2.1.1 Location 1.2-1 1.2.1.2 Meteorology 1.2-1 1.2.1.3 Site Environs and Ac...

Partially withheld Insp Repts 50-445/83-34 & 50-446/83-18 on 830812-19.No violations or deviations noted.Major areas inspected:nonconformance repts for 811012-821012 & reactor vessel outer wall.

. .*% ' . .-'* _ , _-.. - . . . . . ,.we. .,-.* .APPENDIXU. S. NUCLEAR REGULATORY COMMISSIONREGION IV.:NRC Inspection Report: 50-445/83-3450-446/83-18.Dockets: 50-445; 50-446 Construction Permits: CPPR-126CPPR-127 -Licensee: Texas Utilities Generating Company (TUGCO)2001 Bryan...

2011/08/30 Turkey Point COL Hearing - FW: L-2011-340 RAI Ltr 22 eRAI 5403 Response_rev 1

1PMTurkeyCOLPEm ResourceFrom: Comar, MannySent: Tuesday, August 30, 2011 9:27 AMTo: TurkeyCOL ResourceSubject: FW: L-2011-340 RAI Ltr 22 eRAI 5403 Response_rev 1Attachments: L-2011-340 Signed 08-29-2011 RAI Ltr 22 eRAI 5403 Response_rev 1.pdf From: CHILDRESS, ELWOOD [mailto:E...

Byron Station Units 1 & 2, Inservice Testing Program for the Third Ten Year Interval. Attachment 7 to Attachment 14.

1ST Program PlanByron Station Units I & 2, Third IntervalATTACHMENT 7REFUEL OUTAGE JUSTIFICATION INDEX(Page! of!)Designator Description DateRJ-! (!/2S18811A/B) Stroke Time Tested (SO/SC) July 1,2006during RefuelingRJ-2 (1/21A065; 1/21A066) Stroke Time Test (SC) July 1, 2006and...

South Texas Project Units 3 & 4 COLA (Emergency Plan), Rev. 0 - Chapter 03 - Emergency Action Level Bases

Page 1 of 93 South Texas Project Units 3 and 4 Threshold Value Technical Basis Page 2 of 93 Reference The technical basis for the Threshold Value scheme presented in this document is Revision 5 to NEI 99-01, Methodology for the Development of Threshold Values. ...

Oyster Creek Exam Oct. 2006 - Draft Outlines (Folder 2).

Form ES-40 1-1 ES-401 BWR Examination Outline Facilitv: Oyster Creek Nuclear Station Printed: 03/22/2006 8 Note: 1. 2. 3. 4. 5. 6. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (Le,, except for one category ...

Columbia - Issuance of License Amendment 199 Re: Changes to Technical Specifications to Replace the Current Accident Source Term Used in Design Basis Radiological Analyses.

November 27, 2006Mr. J. V. Parrish Chief Executive OfficerEnergy NorthwestP.O. Box 968 (Mail Drop 1023)Richland, WA 99352-0968 SUBJECT: COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT RE:ALTERNATIVE SOURCE TERM (TAC NO. MC4570)Dear Mr. Parrish:The U.S. ...

Response to Portion of NRC Request for Additional Information Letter No. 85 - Engineered Safety Features - RAI Numbers 6.2-151, 6.3-64, 6.3-65, 6.3-69, 6.3-71, 6.3-73, 6.3-74 and 6.3-75.

GE EnergyJames C. KinseyProject Manager, ESBWR LicensingPO Box 780 M/C J-70Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 07-269 Docket No. 52-010May 14, 2007U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555-0001Subject...

Oconee - Technical Specification Bases (TSB) Change.

U ukeBRUCE H HAMILTONVice PresidentWnergy. Oconee Nuclear StationDuke Energy CorporationON01 VP / 7800 Rochester HighwaySeneca, SC 29672864 885 3487December 3, 2007 864 885 4208 faxbhhamilton@duke-energy. cornU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Attention:...

26A6642AF, Rev. 1, "ESBWR Design Control Document" Tier 2, Chapter 1 - Introduction and General Description of Plant, Appendices 1A-1D.

g GE Nuclear Energy ESBWR Design Control Document Tier 2 Chapter 1 Introduction and General Description of Plant Appendices 1A-1D 26A6642AFRevision 1January 200626A6642AF Rev. 01 ESBWR Design Control Document/Tier 2 ii Contents Appendix 1A Response to TMI Related Matte...

Nine Mile Point, Unit 1, Non-Proprietary Calculations for Alternative Source Term, H21C092, "Unit 1 LOCA w/Loop, AST Methodology," Attachment 8.

ATTACHMENT (8)ENCLOSED CALCULATIONS FOR ALTERNATIVE SOURCE TERMNon-Proprietary VersionsThe following calculations are provided in this attachment:1. H21C092, "U1 LOCA w/LOOP, AST Methodology" [Non-proprietary]*2. H21C087, "Unit 1 LOCA Secondary Containment Bypass Piping Data"3...

Nine Mile Point, Unit 1 - Calculation for Alternative Source Term, H21C084, "Post-LOCA Suppression Chamber (Torus) Water pH Analysis".

Nine Mile Point Unit 1Alternative Source TermCalculation H21C084"Post-LOCA Suppression Chamber (Torus)Water pH Analysis"Last 7-1Project: NINE MILE POINT NUCLEAR STATION Unit (1,2 oi'O=Both).: 1 Discipline: MECHANICALTitle Calculation No. ,I/POST-LOCA SUPPRESSION CHAMBER (TORUS...

License Renewal Electronic Correspondence for Hearing File, Response to NRC Request for Additional Information.

McGuire/Catawba Application for Renewed Operating Licenses NRC Requests for Additional Information (RAI) The applicant for McGuire/Catawba NPPs described its aging management review (AMR) of the Auxiliary Systems in the following sections of its license renewal application (LR...

Transmittal of Westinghouse Proprietary and Non-Proprietary Responses to U.S. Nuclear Regulatory Commission Requests for Additional Information on AP1000.

~) WestinghouseU.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Westinghouse Electric CompanyNuclear Plant ProjectsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USADirect tel:Direct fax:e-mail:412-374-5355412-374-5456corletmm@westinghouse.comYour r...

Peach Bottom, Units 2 & 3, and Limerick, Units 1 & 2, EP-MA-110-200, Revision 1, "Dose Assessment."

NExelkni,Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348www exeloncorp cornNuclear1 OCFR50, Appendix ENovember 21, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001Subject: Peach Bottom Atomic Power Station, Units 2 & 3 Facil...