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Initial Submittal of the Written Exam for the Quad Cities Initial Examination - June 2007.

*QNUM 001*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2007/06/04*FAC 254*RTYP BWR-GE3*EXLEVEL B*EXMNR Walton*QVAL 1.00*SEC*SUBSORT*KA 295001K201*QUESTIONUnit 1 is at 80%. All condensate/booster pumps and feedwater pumps are in operation. TheUnit 1 NSO observes the followin...

Mitsubishi Heavy Industries, Ltd. - Responses to US-APWR DCD RAI No. 343-2208 Revision 0, SRP Section 09.02.02 - Reactor Auxiliary Cooling Water System.

AkMITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANJuly 17, 2009Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-09350Subject: MHI's Responses to US-APWR D...

Toshiba Design Control Document Rev. 0 - Tier 2 - Chapter 09 - Auxiliary Systems - Appendix 09B - Summary of Analysis Supporting Fire Protection Design Requirements

Summary of Analysis Supporting Fire Protection Design Requirements 9B-1RS-5146900 Rev. 0Design Control Document/Tier 2 ABWR9B Summary of Analysis Supporting Fire Protection Design Requirements9B.1 IntroductionThis appendix is included to discuss in detail some of the analysi...

Watts Bar Initial Exam 2009-301 Final Sim/In-Plant JPMs.

REV. 0 PAGE 1 0F 131 WATTS BAR NUCLEAR PLANT B.1.a ALTERNATE PATH. B.1.a Withdraw Shutdown Banks. REV. 0 PAGE 2 0F 131 WATTS BAR NUCLEAR PLANT B.1.a Task: Withdraw Shutdown Banks. Alternate Path: Following failure of th...

Wolf Creek Generating Station - Draft Request for Additional Information RE: Generic Letter 2004-02 (TAC MC4731).

- 1 - WOLF CREEK GENERATING STATION REQUEST FOR ADDITIONAL INFORMATION SUPPLEMENTAL RESPONSES TO GENERIC LETTER (GL) 2004-02 FEBRUARY 29 AND DECEMBER 22, 2008 A. Break selection 1. Please verify that the insulation types and amounts are distributed relatively symmetrica...

IP-1028/1, "Final Core Damage Assessment Procedure."

Attachment to IPN-84- 34 Final Core Damage Assessment Procedure New York Power Authority Indian Point 3 Nuclear Power Plant Docket No. 50-286 640,050072 814 3 0 PDR AbOCK 050 969f'86 P PD'RWCORE DAMAGE ASSESSMENT 1.0 PURPOSE To provide a methodology to determine the extent of ...

Draft - PWR Examination Outlines (Folder 2).

ES-401 PWR Examination Outline Form ES-401-2 RO KIA Category Points Group K K K K K K A A A A G Total Tier 1234561234* SRO-Only Points A2 G* Total 2 2. Plant Systems Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SR...

Duane Arnold, Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, "Use of TS 3.10.1 for Scram Time Testing Activities," Affected Technical Specifications: Section 3.10.1.

FPL Energy.Duane Arnold Energy CenterFPL Energy Duane Arnold, LLC3277 DAEC RoadPalo, Iowa 52324March 1, 2006NG-06-025010 CFR 50.90U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Duane Arnold Energy CenterDocket 50-331License No. DPR-49Tech...

Diablo Canyon, Units 1 and 2, Draft Response to Second Round Request for Additional Information Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors."

PG&E Letter DCL-10-0xx Enclosure Diablo Canyon Power Plant (DCPP) Units 1 and 2 Response to Second Round Request for Additional Information Generic Letter 2004-02, “Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized W...

Responds to violations noted in Insp Repts 50-286/86-10, 50-286/86-24,50-286/87-20 & 50-286/87-22 & proposed imposition of civil penalty in amount of $75,000.Maint program for equipment qualification developed.

123 Main Street White Plains, New York 10601 914 681.6240O NewYorkPower 4 AuthorilyJohn C. Brons Executive Vice President Nuclear GenerationOctober 21, 1988 IPN-88-047Director, Office of Enforcement U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1...

"Flame & Radiation Resistant Cables for Nuclear Power Plants."

BIW BOSTRAD CABLES FLAME AND RADIATION RESISTANT CABLES FOR NUCLEAR POWER PLANTS SEPTEMBER, 1969 Report No. B901BOSTON INSULATED WIRE & CABLE CO. 65 Bay Street Boston, Massachusetts 021258202090372 820204 PDR ADOCK 05000286 P PDR(f ik;]R TABLE OF CONTENTS Page I. INTRODUCTION...

2010/02/22 STP COL - Transmittal of Letter U7-C-STP-NRC-100044

1PMSTPCOL PEmailsFrom: Elton, Loree [leelton@STPEGS.COM]Sent: Monday, February 22, 2010 4:33 PMTo: Muniz, Adrian; Dyer, Linda; Wunder, George; Tonacci, Mark; Eudy, Michael; Kallan, Paul; Plisco, Loren; Anand, Raj; Foster, Rocky; Joseph, Stacy; Govan, Tekia; Tai, TomSubject: Tr...

SO-2009-10-DRAFT Outlines

ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Revision 9.1 Page 1 of 15 SONGS Oct 2009 NRC Rev 1 Facility: SONGS 2 & 3 NRC Date of Exam: 10/19/09 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1 4 3 2 2 5 2 ...

E-mail re: Handouts for the 5/20/2010 Kewaunee Public Meeting.

Collins, MichaelFrom: Tam, PeterSent: Wednesday, May 19, 2010 4:26 PMTo: Collins, Michael; Repetto, JohnSubject: Handouts for the 5/20/10 Kewaunee public meetingMike:I just brought to your office the complete set of handouts for the 5/20/10 Kewaunee public meeting. Pleasehave ...

Meeting Minutes of the 570th ACRS Meeting, on March 4-6, 2010

UNITED STATESNUCLEAR REGULATORY COMMISSIONADVISORY COMMITTEE ON REACTOR SAFEGUARDSWASHINGTON, DC 20555 - 0001 May 4, 2010 MEMORANDUM TO: Sherry Meador, Technical Secretary Advisory Committee on Reactor Safeguards FROM: Cayetano Santos, Chief /RA/ Reactor Safety Br...

South Texas Project Units 3 & 4 COLA (Emergency Plan), Rev. 2 - Chapter 03 - Emergency Plan - South Texas Project Units 3 and 4 Threshold Value Technical Basis- Pages 1-93

Page 1 of 93 5.3 Emergency Action Level South Texas Project Units 3 and 4 Emergency Action Level 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 D...

AP1000 Response to Request for Additional Information (SRP3.12) in Support of the Design Certification Amendment Application.

WestinghouseWestinghouse Electric CompanyNuclear Power PlantsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USA412-374-6206412-374-5005siskl rb@westinghouse.comU.S. Nuclear Regulatory CommissionATTENTION: Document.Control DeskWashington, D.C. 20555Direct tel:Direct fax:e-mail:...