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"Electrical Load Analysis for 480 Volt Emergency Power Sys."

• ELECTRICAL LOAD ANALYSIS FOR 480 VOLT EHERGENCY POWER SYSTEH SURRY Pm .. 'ER STATION UNITS 1 AND 2 DOCKET NOS. 50-280 50-281 LICENSE NOS. DPR-32 DPR-37 ISSUED: Hay 17, 1979 , 79062102llo VIRGINIA ELECTRIC AND POWER COMPANY 1 ! I - ' ! I ! i I , e 1.0 System Description 2.0 L...

Forwards documentation concerning 10CFR50.55(e) Investigation 84-18 re ASTM A36 plate matl,per request.Tests conducted by St Louis Testing Labs,Inc.

]) r>1*> *,%-iILLIN0/8 POWER COMPANYjfygg,329CLINTON POWER STATION. P.O. BOX 678. CLINTON. ILLINOls 61727|U-10270April 24, 1985/RICUTY ROUTI' 2y $.Q-,! a aMr. Paul Cortlandm,U. S. Nuclear Regulatory Commission , -359 E/W-W@gWashington, DC 20555/ NC[/ FILE\Subject:10CFR50.55(e)...

2011/09/20 Levy County COL - Progress Energy Response #1 to 6/23/11 USACE Letter

1PMLevyCOLPEm ResourceFrom: Wilkins, Tillie [tillie.wilkins@pgnmail.com]Sent: Tuesday, September 20, 2011 1:46 PMTo: 'osvaldo.collazo@usace.army.mil'; 'gordon.a.hambrick@usace.army.mil'; Bruner, Douglas; 'gagliano.paul@epa.gov'; 'DavidA Pritchett'Cc: Snead, PaulSubject: Progre...

2012/01/25 Levy County COL - Draft meeting notes with attachments for PEF/LNP Meeting on 01/19/2012 (UNCLASSIFIED)

1PMLevyCOLPEm ResourceFrom: Hambrick, Gordon A SAJ [Gordon.A.Hambrick@usace.army.mil]Sent: Wednesday, January 25, 2012 12:55 PMTo: Snead, Paul; Bruner, Douglas; DavidA Pritchett; Gagliano.Paul@epamail.epa.gov; Dierolf, Amy C.; Kitchen, Robert; Hunter, John J (Jamie); Kitchen, ...

Clinton Power Station, Unit 1, Revision 19 to Updated Safety Analysis Report, Appendix D, Requirements Resulting from TMI-2 Accident (Redacted).

CPS/USAR APPENDIX D D-i REV. 11, JANUARY 2005 APPENDIX D REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT TABLE OF CONTENTS ITEM PAGE TMI ACTION PLAN REQUIREMENTS FOR APPLICANTS FOR AN OPERATING LICENSE (NUREG-0737 ENCLOSURE 2) Introduction D-1 I.A.1.1 Shift Technical Advisor ...

Response to NRC Request for Additional Information, dated May 15, 2019 related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application.

Exelon Generation _ , 2lXJ E\ch>11 \\ .1y k.cnm.~ll 'iqu.uc I'\ It} \4X \.\\\\\.1..'xdon .._ orp om June 6, 2019 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Ope...

"Comments on Cost Estimates in Regulatory Analysis Supporting Proposed Station Blackout Rule."

e.NUGSBO 86-001JULY 1986eeCOMMENTS ONCOST ESTIMATES IN THEREGULATORY ANALYSISgSUPPORTING THEPROPOSED STATION BLACKOUT RULEO3OO,NUCLEAR UTILITY GROUP"ON STATION BLACKOUT1200 Seventeenth Street, NWSuite 700Washington, D.C. 20036372 134 86072150 51FR9829 "DR_. .:oNUGSBO 86-001JUL...

Final - Section B Operating (Folder 3), Indian Point 2.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Indian Point 2 Task No: 0140040401 Task Title: Perform the required actions for a malfunction of rod position indicator 01 4A2.06 (2.6/3.0) K/A Reference: 01 4A4.03 (2H2.7) Job Performance Measure No: Sim-A Exa...

Modeling Junction Box Scenarios in a Fire PRA.

March 31, 2013 1 Modeling Junction Box Scenarios in a Fire PRA 1 Background Chapter 6 of NUREG/CR-6850 includes a generic fire ignition frequency for junction boxes. This classification of junction boxes as an individual ignition source was also previously included in the E...

Inspection Procedure 80522, "Part 52, Radiological Environmental Monitoring Program (REMP)."

Issue Date: 07/01/08 1 80522 NRC INSPECTION MANUAL CHPB INSPECTION PROCEDURE 80522 PART 52, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) PROGRAM APPLICABILITY: 2504 80522 - 01 INSPECTION OBJECTIVE 01.01 To inspect for compliance with 10 CFR 20.1301 and 20.13...

HPSmidyear2020_NUREG1757V2R2 no notes.

NUREG-1757, Volume 2, Revision 2Consolidated Decommissioning Guidance:Characterization, Survey, and Determination of Radiological CriteriaCynthia Barr, Christepher McKenney, Adam Schwartzman,John Clements, CHP, Bruce Watson, CHPU.S. Nuclear Regulatory CommissionHealth Physics ...

PRA Quality Expectations: Treatment of Uncertainties.

1 PRA Quality Expectations: Treatment of Uncertainties To support risk-informed regulatory activities, the expectations for PRA quality need to be provided. These expectations are provided in Regulatory Guide (RG 1.200) which provides the staff endorsement of the standards...

Fax to Engineering Services to License No. 21-26742-01.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, ILLINOIS 60532-4352 TELEFAX TRANSMITTAL DATE July 7, 2011 NUMBER OF PAGES 8 SEND TO Miraj Mehta, Radiation Safety Officer LOCATION Engineering Services, Inc. - NRC license 21-2674...

Letter forwarding Industry's Seismic Methodology Description, per NRC request at the 04/13/99 presentation by NEI on methodology for updating NRC's seismic analysis for examining beyond design accidents in spent fuel pools.

NUCLEAR ENERGY INSTITUTE Lynnette Hendricks DIRECTOR PLANT SUPPORT NUCLEAR GENERATION OMSION April 28, 1999 Mr. John Zwolinski Director, Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 D...

Forwards GDC 51 compliance review re RCPB components & certified matl test repts for components.Info should resolve SER Outstanding Item 4.

- __ - __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _'} One First N;tional Plazt, Chictgo. IllinoisCommonwealth Edisonf'*..( O"'7 Addrzss R; ply to: Post Off'ca Box 767,sy' Chicago Illinois 60690 .February 22, 1984Mr. Harold R. Denton, Dire...

Redacted_Clinton Power Station, Revision 21 to Updated Safety Analysis Report, Appendix D, Requirements Resulting from TMI-2 Accident.

CPS/USAR APPENDIX D D-i REV. 11, JANUARY 2005 APPENDIX D REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT TABLE OF CONTENTS ITEM PAGE TMI ACTION PLAN REQUIREMENTS FOR APPLICANTS FOR AN OPERATING LICENSE (NUREG-0737 ENCLOSURE 2) Introduction D-1 I.A.1.1 Shift Technical Advisor ...

SUPPLEMENT 1 TO APPLICATION FOR AMENDMEMT TO FACILITY OPERATING LICENSE APPENDIX A TECHNICAL SPECIFICATIONS IMPROVEMENT PROJECT POINT BEACH NUCLEAR PLANT UNITS 1 AND 2

MARK E. REDDEMANN Wisconsin Electric Site Vice President A WISCONSIN ENERGY COMPANY Point Beach Nuclear Plant 6610 Nuclear Rd. Two Rivers, Wl 54241 Phone 920-755-7627 NPL 2000-0142 March 15, 2000 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P 1-137 Wa...

08/08/2007 Digital I&C HICR-Human Factors TWG Draft Interim Staff Guidance on Computer-Based Procedures and Soft Controls.

Page 1 of 12 8/5/2007 Interim Staff Guidance Human Factors TWG 5 Computerized-Based Procedures and Soft Controls NUREG-0700, Section 8 currently contains guidance regarding the review of Computer-based procedures (CBP). NUREG-0899, Guidelines for the Preparation of Emerge...

Draft - U.S. EPR Design Certification Application RAI No. 32, FSAR Ch 6.

1 DRAFT Request for Additional Information No. 32, Revision 0 7/15/2008 U. S. EPR Standard Design Certification AREVA NP Inc. Docket No. 52-020 SRP Section: 06.03 - Emergency Core Cooling System Application Section: 6.3 QUESTIONS 06.03-1 One valve was identified from the ...

Urban Engineers of Erie, Inc., Additional New License Application Information dtd 2/18/2009.

&muman UI.MICUW~~~MIM)~ ACMOMDDYOM: wo.wwa ma tz?ms24 84,S.*,lndW, < l&TRUCTION$: SEE THE APPROPRIATE LICENSE APPLICATION GUIDE FOR DETAILED INSTRUCVONS FOR COMPLETING APPLIC 4% SEND ENTIRE COMPLETED APPUCATION THE NRC OFFICE SPECIFIED BELOW. - AM#AT#WCOll#n#nwrw##nnowon~uruc...

SMAC Testing, Inc.- Additional Information, License No. 21-32606-01.

r-----------------------------------------------------------------------------------------,'· '· , . ~ . : . ~ •' -.::. . : ~ .:.· ,· ', ',' '.· ·· .. ~~ · :·. .. . · . ... ·. ... .·.· .. , · .. ' ~ . '' "•• I SOii:s~MATBlUA.LS-ASPHAL 't -CONCRETE · · SMAC tEsriNd~ Inc.-. · .·...

South Texas Project Units 3 & 4 COLA (Environmental Report), Rev. 9 - Chapter 01 - Introduction - Section 01.03S Methodology

Methodology 1.3S-1STP 3 & 4 Environmental Report1.3S MethodologyFor COL applications that do not refer to an early site permit, NRC regulations under 10 CFR 52.79(a)(2) require an Environmental Report (ER) be prepared in accordance with the provisions of Subpart A of 10 CFR P...

FPRA FAQ 18-0014 - Time to Detection is Zero for Manual Non Suppression Probability Calculations - Version 0-V6.

FAQ Number 18-0014 FAQ Revision 0 (Draft V6) FAQ Title The time to Detection is Zero for Manual Non-Suppression Probability (NSP) Calculations Page 1 of 3 Plant: Various Date: Contact: Robert Cavedo Ashley Lindeman Patricia Pringle Phone: (301) 938-0397 (704) 595-2538 (41...

OFFICIAL EXHIBIT - ENT000551-00-BD01 - Letter from B. Harris, NRC Project Manager, to B. Allen, FENOC, "Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 3" (May 2, 2011).

ENT000551 Submitted: August 20, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Ide...

Department of Health & Human Services, Letter rec'd 11/19/2012, Subj: Financial Assurance Action.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 June 22, 2012 Docket No. 03004001 License No. 10-06772-01 Control No. 577684 lrCoPaul D. Simpson CDC Radiation Safety Officer () 300'-+00 IU.S...