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Quad Cities Nuclear Power Station Unit 1, 90-Day Post Outage ISI Letter.

Exekln.Exelon Generation Company. LLC wwwexeloncorp.com NucleaTQuad Cities Nuclear Power Station22710 206'" Avenue NorthCordova, IL 61242-97401 OCFR50.55aSVP-05-049July 18, 2005U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001Quad Cities...

Point Beach, Plan-of-the-Day Meeting for 05/26/2004.

-Pn Bc N-u~Point Beach Nuclear PlantFS-2,,- ,I j -II.,ICCSa'I I* cct* (rID Ert At~t * reSMdbRue - [>se Free _ Sdile - Trzi. *Event Response Team Plan-of-the-Day Meeting U1R28: Day 53On Call: I8n5L084a Days to U2R27: 311Team D'-'0815-0845Team "D" Front Office Conference Room Da...

Calculation No. 050-PSA-WH00-00200-000-00B, "Wet Handling Facility Reliability and Event Sequence Categorization Analysis," Attachment F, Page F-70 through Page F-119.

Wet Handling Facility Reliability 050-PSA-WHOO-00200-000-00B and Event Sequence Categorization Analysis INTENTIONALLY LEFT BLANK F-70 November 2008 I Wet Handling Facility Reliability and Event Sequence Categorization Analysis 050-PSA-WHOO-00200-000-00B I~ource Room Number Ele...

Comanche Peak, Units 1 and 2 - FSAR Amendment 108, Figures - Chapter 09 thru 11.

• I 1.0 m I 0 m lli IF . I . ... ,. : - 4. 4 ;l:~. D D D--B D-B -+---4--i~--- -8----B-D--B--B -8--B- D-B--8--D -0 D Or--+-+ ~W FUEL STORNM: RACKS U32 ~SS' "'f} PARTIAL PLAl-J A. I T I Ff I I I I I I I E1l T c E:±1 1-l ti "' I ·~ ::l I I I C :::1 ::l t t ~J I C r ? c I :J J I I...

Forwards revised draft FSAR pages for solid radwaste sys. Pages will be incorporated into FSAR Amend 18,dtd Sept 1981.

. fTP~ACCESSION NBRF AC ILi;50 397AUTH' N AiREBOUCHEYPG.D,REC IP ~ NAMKISCHNENCERBA,REGULATORY VFORMATION DISTRIBUTION S EM (RIDS);8108140275 DOC ~ DATE: 81/08/06 NOTARIZED: NO DOCKETNPPSS Nucle'ar Projects Unit 2P Washington Public Powe. 05000397AUTHOR AFFILIATIONWashington P...

Confirms 871014 meeting w/NRC in Silver Spring,MD to discuss current UMTRAP status & issues,including Title I & II areas, demolition criteria & UMTRAP schedules,per discussion. Related info encl.

_ - -w,., .er -Dsp rtm:nt cf En:rgy,"is'iAlbuquerque Operations Office,P.O.' Box 5400Albuquerque, New Mexico 87115007 2 - EEdMr. Paul LohausU.S. Nuclear Regulatory Commission7915 Eastern AvenueSilver Springs, MD 20910Dear Mr. Lohaus:Per our recent discussion, DOE 1rL11 meet wi...

Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Reference Drawings, Part 6 of 11, Redacted.

0 ----c ---B --A ~I- .133HS L00£17ZL-4 SAFE1Y INJECT I ttl SIGNAL (SHEET 8) BY I @ .!;_E.S. BY Oll-IERS -----I--------- -IILAO<-OUT ---, SI~Al. t ("--OTE 12) ~ ~ START. romn. 110()4 --------------. MANUAL START, LOCAL (I()TES 2,3 & 8)------------~ MANUAL STOP, ~TID.. ltXJ4 (NO...

CR3 Outage Containment Repair Project - Level 3 Schedule.

CR3 Outage Containment Repair Project - Level 3 ScheduleRow Activity Lecripi .iySts Eal4 ROWes Doc Jan FebF~~P inish Dur 28 04 11 18 25 01 08 15 22 01Apr22 29 05Mar-2-I ij2 DELACT010-Issue Level 2 Schedule ThatIncludes Input from Engineering & 11/171090701/07/1012 34 C13300EPC...

Humboldt Bay Power Plant, Unit 3 - Responses to NRC Requests for Additional Information on the Final Status Survey Reports for the Humboldt Bay Power Plant

James M. Welsch Senior Vice President Generation and Chief Nuclear Officer Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 805.545.3242 E-Mail: James.Welsch@pge.com September 3, 2020 PG&E Letter HBL-20-012 ATTN: Document Control Desk U.S. Nuclear Regulatory...

Rev 0 to Calculation BYR97-023, "Determination of RCS Dose Equivalent I-131 Release Rate & Spike Factor Based on Plant Trip Data."

- - . . . . . . -,Exhibit Cs'NEP 12-02Revision 4COMMONWEALTH EDISON COMPANYCALCULATION TITLE PAGECALCULATION NO. BYR97-023PAGE NO.: 1XSAFETY RELATEDREGULATORY RELATEDNON-SAFETY RELATEDCALCULATION TITLE:Datermination of RCS Dose Equivalent Iodine-131 Release Rate and SpikeFacto...

Oconee Nuclear Station, Units 1, 2, and 3 - Independent Spent Fuel Storage Installation Updated Final Safety Analysis Report, Revision 23, Appendix A. Tables - Table A-23 (Page 1 of 1).

Oconee ISFSI UFSAR Appendix A. Tables Appendix A. Tables Oconee ISFSI UFSAR Table A-1 (Page 1 of 1) (31 DEC 2007) Table A-1. Design Parameters for the Oconee ISFSI GENERAL DESIGN REQUIREMENTS Maximum weight on crane hook 100 tons Capacity (Casks/Canister) 24 PWR Assys M...

Matls licensing package for amend 51 to license 21-00159-04 for Dept of Veterans Affairs Medical Ctr.Control:305071.

$\petC Poltte 374{PAGE 1 oF 6 PAGEsy,3, pduCLEAft ftEOuLATORY cot 4W888Amendment No. 51|}MATERIALS LICENSEIPursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Pubhc Law 93-438), and Title 10, Codefof Federal Regulations, Chapter I, Par...

Matls licensing package for amend 13 to license 34-12356-02 for Dow Chemical Co USA.Control:305224.

*u.a. LEAR CEGU tor CoMMISSloNAmendmsnt No.13MATERIALS LICENSEPursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Codeof Federal Regulations, Chapter 1. Parts 30,31,32,33,34,35,36,39,40, and 70, and in...

Rev 8 to Procedure 1302.025, "Spent Fuel Removal & Dry Storage Operations."

i"/e. . .PROCJWORK PLAN NO.' PROCEDUREMIORK PLAN TITLE: PAGE: 43 Cf 74 .ir 1302.025 SPENT FUEL REMOVAL AND DRY STORAGE OPERATIONSREV: 8;CHANGE:'NDE HOLDB. PT of inner valve cover plate acceptable.NDE9.7.19 Weld the outer valve cover plate per weld package.9.7.20 Determine acce...

"DC Cook Nuclear Plant Annual Operating Rept,1987." W/880225 ltr.

_ - _ _ _ _ _ _ - _ _ _ _eaD 0 N.A L D C.- COOK NUCLEAR P L A N'Tt..eANNUAL OPERATING REPORT1987;-a M r[FP COMPILED BY:m ,@w~'B.A. SvenssonLicensing Activities CoordinatorREVIEWED BY: N h/ mot n [2r fseA.A. B;.ind''Assistag. Plant ManagerAPPROVED BY: [Lu.ygd2 ?f ff4/W.G.Smith,...

HSA Historical Site Assessment, MYAPC.

Historical Site AssessmentMYAPC(KID# DATE IDENTIFIER LOCATION DESCRIPTION TYPE 1 23-Mar-90 UOR 90-030 I&C Hotshop Mercury spill. 2 teaspoons of mercury from transmitters. HAZ 2 29-Nov-94 UOR 94-105 Turbine Hall roof, and outside Oil spill from P-2C blew onto Turbine Hall roof,...

McGuire Nuclear Station, Units 1 and 2 - Updated Final Safety Analysis Report, Chapter 11 Tables

McGuire Nuclear Station UFSAR Appendix 11A. Tables Appendix 11A. Tables McGuire Nuclear Station UFSAR Table 11-1 (Page 1 of 2) (14 APR 2005) Table 11-1. Parameters Used in the Calculation of Reactor Coolant Fission Product Activities During Normal Operation 1. Ultimate co...

Callaway Plant, Unit 1 - Final Safety Analysis Report, Revision OL-22, Chapter 11 Figures, Radioactive Waste Management.

::~I::~~~v( 1--------+-t-' (O~>•) llli~!O. R.A.OIUST~ SYSTEM "_8'" _TAAIN tH6l t ::H:~~~~:( 1--lf--.-r---1 tOitW) h_AUNOR'f ANO HJT SHJWER lHSJ ~ TIH(lHlM.ll + ~:=~~:~r!:~ut>~li /----'"--{ flj)QI! tU.tM1 (I.IIW) COIIDENUT[ rol tSM~~ J!L L----------l&HS Tank A Filter L&HS Tank ...

Point Beach Nuclear Plant, Plan-of-the Day Meeting for 05/25/2004.

. --- -1.- -1WC Point Beach Nuclear PlantLmnex kw_ _IN IEvent Response TeamOn Call:Team "D"Plan-of-the-Day Meeting0815-0845Front Office Conference RoomWork Week: B1OBIDate: Tuesday, May 25, 2004UIR28: Day 52Days to U2R27: 312Days to U1 R29: 487Safety Event: Days Since Last HPC...

Email - From: Williams, Charles R. [Charles.Williams@pgnmail.com] To: Lake, Louis; Thomas, George dated Thursday, January 14, 2010 7:16 AM Subject: FW: 01-14-10 Containment Repair Project Level 3 Schedule.

Sengupta, AbhijitFrom: Williams, Charles R. [Charles.Williams@pgnmail.com]Sent: Thursday, January 14, 2010 7:16 AMTo: Lake, Louis; Thomas, GeorgeSubject: FW: 01-14-10 Containment Repair Project Level 3 scheduleAttachments: 01-14-10Level,3RevD-11x17.pdf,- 0.1JFYIFrom: Goering,...

Voided matls licensing action for Wisconsin-Madison Univ. Control:300230.

oOV010 SHEET,To:License Fee Management Branch.FROM:RIII_ kEtruv 6;, Ah(LL-'''SUBJECT:VOIDED APPLICATION!Control Number:_300930>Applicant:ld.. M E //,4,eJM>l'License Number:_ WP-09797-/8e oDocket Number:0 '70 - Of4 W.'Date Voided:_ 7N/97 i~ /'IReason for Void:%' (k$,2 m tid

Forwards Revision 3 to steam generator repair rept.

. .! / ,. ~· .~ .. consumers Power company ·• General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 • Area Code 517 788-0550 August 3, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Brandi No 2 US Nuclear Regulatory Com...

ISFSI Safety Analysis Report for Oconee Nuclear Station, Units 1, 2, and 3. Appendix A. Tables - Design Parameters.

Oconee ISFSI UFSAR Appendix A. Tables Appendix A. Tables Oconee ISFSI UFSAR Table A-1 (Page 1 of 1) (31 DEC 2007) Table A-1. Design Parameters for the Oconee ISFSI GENERAL DESIGN REQUIREMENTS Maximum weight on crane hook 100 tons Capacity (Casks/Canister) 24 PWR Assys M...

Oconee Nuclear Station Independent Spent Fuel Storage Facility Updated Safety Analysis Report, Revision 19, Appendix A. Tables.

Oconee ISFSI UFSAR Appendix A. Tables Appendix A. Tables Oconee ISFSI UFSAR Table A-1 (Page 1 of 1) (31 DEC 2007) Table A-1. Design Parameters for the Oconee ISFSI GENERAL DESIGN REQUIREMENTS Maximum weight on crane hook 100 tons Capacity (Casks/Canister) 24 PWR Assys M...

IE Info Notice 86-051, "Excessive Pneumatic Leakage in Automatic Depressurization Sys." Svc list encl.

SSINS No.: 6835 IN 86-51 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 June 18, 1986 IE INFORMATION NOTICE NO. 86-51: EXCESSIVE PNEUMATIC LEAKAGE IN THE AUTOMATIC DEPRESSURIZATION SYSTEM Addressees: All boiling water re...