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Oconee Nuclear Station, Units 1, 2, and 3, Technical Specifications, Issuance of Amendments Regarding Steam Generator Tube Integrity (TAC Nos. MD2038, MD2039, MD2040, MD2043, MD2044, and MD2045).

-3-Part 70; Is subject to all applicable provisions of the Act and to the rules, regulations, andorders of the Commission now or hereafter in effect; and is subject to the additionalconditions specified or Incorporated below.A. Maximum Power LevelThe licensee Is authorized to ...

Point Beach Nuclear Plant, Unit 1 - Technical Specification Pages re: Steam Generator Tube Repair in the Tubesheet Amendment (TAC No. MD2583).

-3-D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NMC to receive, possess anduse in amounts as required any byproduct, source or special nuclear materialwithout restriction to chemical or physical form, for sample analysis or instrumentcalibration or associated with ra...

NUREG-0800, (64:234) Chpt 3, Section 3.11, Rev. 2, Environmental Qualification of Mechanical and Electrical Equipment, of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants. LWR Edition.

NIUREG -'CI',ornsarlv NL.'. - .tst RtEvU.S. NUCLEAR REGULATORY COMMISSIONSTANDARD REVIEW PLANOFFICE OF NUCLEAR REACTOR REGULATION3.11 ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENTREVIEW RESPONSIBILITIESPrimary - Equipment Qualification Branch (EQB)Secondar...

Vogtle, Unit 2 - Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01.

Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERNA.. COMPANY January 21, 2009 Energy to Serve }'OurWorldSM Docket No.: 50-425 NL-08-1921 U. S. Nuclear Regulatory Commission ...

2006/09/18-Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 17, E-mail from S. Hutchins to J. Hufnagel, J. O'Rourke, re DW White Papers.

U"MILEARFRAUKYt C0Mmg=gCitizens Exhibits 17 bMatmer Af 'lCrA&-rp, (t,.LL(Doaft N& -50- o.)lq -/.iL.Official Exhdibt No. 7LOFFERED by: ApplicantILicon- rvnoNNRC StaffIDEPMFIED on4/-Fromn: Hutchins, Steven P on: ....Sent: Monday, September 18, 2006 4:51 PM A Taken: wI iECTED W...

SECY-R 143, Amendment to 10 CFR Part 50 - General Design Criteria for Nuclear Power Plants.

71aA=jMr.'A0Z2Q=ytUSI eSECY-R 143 f,-January 28, 1971AMENDMENT TO 10 CFR 50 - GENERAL DESIGNCRITERIA FOR NUCLEAR POWER PLANTSNote by the SecretaryThe Director of Regulation has requested that the attachedreport by the Director of Reactor Standards be circulated forconsideratio...

Indian Point, Unit 2 - License Amendment Request Regarding Surveillance Requirements For ECCS Valves Required to be in Position with Power to the Valve Operator Removed.

Entergy Nuclear NortheastIndian Point Energy CenterS_.450 Broadway, GSBTP.O. Box 249Buchanan, N.Y. 10511-0249Tel (914) 734-6700J.E. PollockSite Vice PresidentAdministrationMarch 25, 2009Indian Point Unit 2Docket No. 50-247NL-09-004U.S. Nuclear Regulatory CommissionATTN: Docume...

2008/12/31-OFFICIAL EXHIBIT - MANDATORY HEARING - SNC00080G-MA-BD01 - Vogtle Early Site Permit Application, Part 2 - Site Safety Analysis Report Appendix 2.5E.

Southern Nuclear Operating CompanyVogtle Early Site Permit ApplicationPart 2 – Site Safety Analysis Report2.5E -1 Revision 5December 2008Appendix 2.5E—AP1000 Vogtle Site Specific Seismic Evaluation ReportPrepared byWestinghouse Electric Company LLCOctober 2008 SNC00080GNuclear...

UniStar Nuclear Calvert Cliffs Unit 3 COLA (Final Safety Analysis Report), Rev. 2 - P FSAR Chapter 03.0

CCNPP Unit 3 3–1 Rev. 2© 2007 UniStar Nuclear Development, LLC. All rights reserved.COPYRIGHT PROTECTEDTable Of Contents3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS . . . . . . . . . . .3–73.1 COMPLIANCE WITH NUCLEAR REGULATORY COMMISSION GENERAL DESIGN CRITERIA...

LaSalle County Station Units 1 & 2 - Additional Information Supporting Request for License Amendment re Measurement Uncertainty Recapture Power Uprate.

Exelon Generation 4300 Winfield Road Warrenville, IL 60555 RS-10-090 May 13, 2010 www.exeloncorp.com U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-...

Browns Ferry Unit 1 Restart Inspection Plan and Schedule (IP&S) Report - Enclosure 2.

Browns Ferry Unit 1 RestartInspection Plan and Schedule (IP&S) Report In accordance with MC 2509, the NRC staff has developed IP&S which collects and provides inspection requirements for areas that comprise the BF1 Restart Project Inspection Program. This IP&S tracking tool ...

Waterford 3-2007-11-FINAL Outline, PWR Examination Outline.

ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021 1Facility: Waterford 3 2007 NRC Retake Date of Exam: 11/8/2007 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G* Total 1 3 3 3 3 3 3 18 6 2 1 1 2 2 1 2 9 ...

Waterford 3-2007-11-DRAFT Outline, 2007 NRC Initial License Written Examination, Written Examination Outline Methodology.

Waterford 2007 NRC Initial License Written Examination Written Examination Outline Methodology The written examination outline was developed using a proprietary electronic random outline generator developed by Western Technical Services, Inc. The software was designed to pro...

IR 05000282-98-022, 05000306-98-022 on 11/16/1998 - 11/20/1998 for Prairie Island Nuclear Generating Plant, Units 1 and 2.

December 1, 1998Mr. M. WadleyPresident, Nuclear GenerationNorthern States Power Company414 Nicollet MallMinneapolis, MN 55401SUBJECT: NRC RADIATION PROTECTION INSPECTION REPORTS 50-282/98022(DRS); 50-306/98022(DRS)Dear Mr. Wadley:On November 20, 1998, the NRC completed an ins...

LER 93-012-00:on 930910,identified condition which could have rendered weld channel & penetration pressurization sys nitrogen backup sys inoperable.Condition existed since original plan design.Temporary mod designed.W/931012 ltr.

Stephen B, 6mmr Vice PresidentConsolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116 October,12, 1993Re: Indian Point Unit No. 2 Docket No. 50-247 LER 93-12-00Document Control Desk US Nuclear R...

Submits response to request for addl info re implementation of station blackout rule 10CFR50.63 at facility.

123 Main Street 1 White Plains, NewYorl*1 914 681.6846OWb NewYork Power 4 Authority U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, DC 20555 ATTN: Document Control DeskSubject:Dear Sir: Enclosed is the Authority's response to the NRC staff's Request for Addi...

Improved Technical Specifications, LaSalle County Station, Volume 2: Sections 3.1 and 3.2.

Improved Technical SpecificationsLaSalle County StationVolume 2:Sections 3.1 and 3.2CoredSDM 3.1.13.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)LCO 3.1.1 SDM shall be:a. > 0.38% Ak/k, with the highest worth control rod analytically determined; or b. > 0.28% Ak/k, w...

Outline Submittal.

DUAN[ ARNOLD APRIL 2001. Outline ubmittalES-201 Examination Outline Form ES-201-2 Quality Checklist Facility: Date of Examination: Initials Item Task Description a b* c 1. a. Verify that the outline(s) fit(s) the appropriate model per ES-401. w R b. Assess whether the outlin...

Farley May 2003 Exam 50-348/2003-301 FINAL JPMs.

Final Submittal ~ FARLEY EXAM 50-348 & 50-364/2003-301 MAY 19 - 26,2003 1. Administrative QuestiondJPMs 2. In-plant JPMs 3. Control Room JPMs (simulator JPMs) ES-301 Administrative Topics Outline Form ES-301-1 Facility: Farlev Date of Examination: 5/19-27/2003 Examination Leve...

Part 5 of 8, Transmittal of Westinghouse Responses to US NRC Requests for Additional Information on the AP1000 Application for Design Certification as Related to Technical Specifications.

Boron Concentration 3.9.13.9 REFUELING OPERATIONS 3.9.1 Boron ConcentrationLCO 3.9.1 APPLICABILITY:Boron concentration of the Reactor Coolant System (RCS), the fuel transfer canal, and the refueling cavity shall be maintained within the limit specified in Core Operating Limits...

Evaluation of Davis Besse Modifications to the High Pressure Injection Pump and Associated Mock-Up Testing.

January 14, 2004MEMORANDUM TO: William H. Ruland, DirectorProject Directorate IIIDivision of Licensing and Project ManagementFROM John N. Hannon, Chief /RA/Plant Systems BranchDivision of Systems Safety and AnalysisEugene V. Imbro, Chief /RA/Mechanical and Civil Engineering Br...

IR-00-002 North Anna

May 1, 2000Virginia Electric and Power CompanyATTN: Mr. D. A. ChristianSenior Vice President - NuclearInnsbrook Technical Center5000 Dominion BoulevardGlen Allen, VA 23060SUBJECT: NRC INTEGRATED INSPECTION REPORT NOS. 50-338/00-02, 50-339/00-02Dear Mr. Christian:On April 1, 20...

DCC Meeting Summary 3/27/00

April 12, 2000MEMORANDUM TO: Donald C. Cook Nuclear Plant Manual Chapter 0350 PanelFROM: John A. Grobe, Director, DRS /s/John A. GrobeSUBJECT: MINUTES OF INTERNAL MEETING OF THE DONALD C. COOKNUCLEAR PLANT MANUAL CHAPTER 0350 PANELThe Donald C. Cook Nuclear Plant Manual Chapte...

Watts Bar Nuclear Plant, Response to Request for Additional Information re Radiological Impact.

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000HAY 2 3 200210 CFR 50.90U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:Docket No.50-390In the Matter of Tennessee Valley AuthorityWATTS BAR NUCL...

DCC Internal Meeting Summary - 2/28/00

April 7, 2000MEMORANDUM TO: Donald C. Cook Nuclear Plant Manual Chapter 0350 PanelFROM: John A. Grobe, Director, DRS /RA/SUBJECT: MINUTES OF INTERNAL MEETING OF THE DONALD C. COOKNUCLEAR PLANT MANUAL CHAPTER 0350 PANELThe Donald C. Cook Nuclear Plant Manual Chapter 0350 Panel ...