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McGuire Initial Exam 2010-301 Final Administrative Documents

ES-201 Examination Preparation Checklist Form ES-201-1Facility: McGuire Nuclear Station Date of Examination: 81212010Developed by: Written - FacilityElNRC El II Operating - Facility El NRC ElTarget ChiefDate*Task Description (Reference) Examiner’sInitials-180 1. Examination ad...

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

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 September 27, 2010 MEMORANDUM TO: ACRS Members FROM: Sherry Meador /RA/ Technical Secretary, ACRS SUBJECT: CERTIFICATION OF THE MEETING...

Vermont Yankee, Nine-Month Response to Generic Letter 2008-01.

S' EntergyEntergy Nuclear Operations, Inc,Vermont YankeeP.O. Box 250Governor Hunt Road rVernon, VT 05354Tel 802 257 7711October 14, 2008BVY 08-071ATTN: Document Control DeskU.S. Nuclear Regulatory Commission11555 Rockville PikeRockville, MD 20852References:Subject:(a) NRC Gene...

Draft - Outlines (Folder 2) (Facility Ltrs. Dtd- 10/02/2006 and 09/22/2006).

Oct 2,2006 NMP Outline Review Comments e e e m e e e e e e e RO Admin 1 - this task is overly leading and is effectively cuing the applicants that there is something wrong with this particular instrumentation. A more appropriate task would be to have the applicants take multip...

WAT - INIT EXAM - 11/2006 - Draft Written Exam.

Waterford III 2006 SRO/RO Initial License ExaminationJustifications for changes from Initial Approved Outlines.Written ExaminationRO Written:1. Question 14; Tier 1/1 4.1-055-G 2.4.20 Knowledge of operational implications of EOPwarnings, cautions and notes.No credible discrimin...

Unistar Nuclear - Calvert Cliffs Power Plant Unit 3 COLA (Tech Specs), Rev. 3 - Technical Specifications - Section 3.3 - Instrumentation

PS 3.3.1 CCNPP Unit 3 3.3.1-1 Amendment No. 0 COLA Revision 3 3.3 INSTRUMENTATION 3.3.1 Protection System (PS) LCO 3.3.1 The PS sensors, manual actuation switches, signal processors, and actuation devices specified in Table 3.3.1-1 shall be OPERABLE. APPLICA...

2008/12/05 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 25, Supplement 1, FSAR Ch 9

1ArevaEPRDCPEm ResourceFrom: DUNCAN Leslie E (AREVA NP INC) [Leslie.Duncan@areva.com]Sent: Friday, December 05, 2008 4:24 PMTo: Getachew TesfayeCc: John Rycyna; Pederson Ronda M (AREVA NP INC); BENNETT Kathy A (OFR) (AREVA NP INC); DELANO Karen V (AREVA NP INC)Subject: Respons...

Nuclear Energy Institute Letter Concerning the Electric Power Research Institute Paper Entitled, "Safety Benefits of Risk Assessment at U.S. Nuclear Power Plants".

e e UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555-0001 August 14, 2001 MEMORANDUM TO: FROM: ACRS MembeI.s ~~4~~ Michael T. Markley, Senior Staff Engineer SUB..IECT: NUCLEAR ENERGY INSTITUTE LETTER CONCERNING THE EL...

Susquehanna - Draft - Section C Operating (Folder 2)

Susquehanna Learning Center 707 Salem Boulevard P.O. Box 467 Berwick, PA 18603-0467 570-542-3353 December 17,2004 Mr. John Caruso USNRC Chief Examiner USNRC Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Susquehanna Learning Center Proposed Examination Materials PL...

Point Beach Plant, License Amendment 110 & 113, Amendments Modify TS 15.6.10, Plant Operating Records, & Modify Other TS To Correct Minor Administrative Errors.

January 5, 1988Docket Nos. 50-266 and 50-301 Mr. C. W. Fay, Vice President Nuclear Power Department Wisconsin Electric Power Company 231 West Michigan Street, Room 308 Milwaukee, Wisconsin 53201 Dear Mr. Fay:DISTRIBUTION: Docket Pi NRC PDR Local PDR PDIII-3 r/f PDIII-3 s/f GHo...

26A6642AW, Rev. 1, "ESBWR Design Control Document" Tier 2, Chapter 7 - Instrumentation And Control Systems.

g GE Nuclear Energy ESBWR Design Control Document Tier 2 Chapter 7 Instrumentation And Control Systems 26A6642AWRevision 1January 200626A6642AW Rev. 01 ESBWR Design Control Document/Tier 2 7-ii Contents 7. Instrumentation And Control Systems 7.1-1 7.1 Introduction 7.1-1...

SONGS - 10-2005 - Final Reference Written Exam.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 A4.08 Importance Rating 3.2 Ability to manually operate and/or monitor in the control room: RCP Cooling Water Supply ...

SONGS-10-2005-DRAFT EXAM.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003 A4.08 Importance Rating 3.2 Ability to manually operate and/or monitor in the control room: RCP Cooling Water Supply ...

Transmittal of Entire EAL Basis Document (Table of Contents Rev).

Committed to Nuclear ExceDAEC EMERGENCY PLANNING DEPARTMENT PROCEDURETRANSMITTAL ACKNOWLEDGEMENT MEMO (TAM-79)To: NRC-NRR Document Control DeskUS NRCWashington DC 20555Re: Entire EAL Basis Document (Table of Contents Rev) (Copy 91)PSM Title: n/aDistribution Date:Effective Date...

"10CFR50.59(b) Rept Changes,Tests & Experiments For 1992." W/930630 ltr.

Stephen B. Brain Vice President 49Consolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116June 30, 1993 Re: Indian Point Unit No. 2 Docket No. 50-247Document Control Desk US Nuclear Regulatory Co...

Fermi 2 RO & SRO Written Exam and Answer Key.

FERMI 2 REACTOR OPERATOR INITIAL LICENSE EXAM SEPTEMBER 2010 1. Thermal stratification of a non-isolated idle Recirculation loop may occur during steady-state Single Loop Operation if the operating Recirculation pump speed is (1) to the transition point where the d...

Forwards Rev 1 to "IST Program Summary for Interval 940701- 040630."

Stephen E. Quinnl Vice President 0Consolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 734-5340November 30, 1995 Re: Indian Point Unit No. 2 Docket No. 50-247Document Control Desk US Nuclear Regulator...

"Seismic Dynamic Analysis Comparison of Finite Boundaries Approach & Half-Space Approach."

F-.WASHINGTON PUBLIC POWER SUPPLY SYSTEMWASHINGTON NUCLEAR PROJECT N0. 3.SEISMIC DYNAMIC ANALYSISC0WARIS0NOFFINITE BOUNDARIES APPROACHANDHALF-SPACE APPROACH.OJUNE 1984.8407130171 840627-PDR ADOCK 05000508APDR.CONTENTSingPAGE ic-int.I. INTRODUCTION1lon1se31 . PURPOSE AND SCOPE3...

Proposed improved TS Section 3.7, "Plant Sys."

- .- _- - - _ _ ..-.._- -.- _ _ .-.- - - .- .-_.--- . - -.MSSVs .i.sB 3.7.1')B 3.7 PLANT SYSTEMSB 3.7.1 Main Steam Safety Valves (HSSVs)BASES(BACKGROUNDThe primary purpose of the HSSVs is to provide overpressure| protection for the secondary system. The MSSVs also provide!prot...

LER 97-020-01:on 971030,inadequate technical justification for proposed change to plant TS resulted in operation outside bounds of current analyses.Caused by inadequate assignment methods.Revised administrative controls.

.. 4 *VERMONT YANKEENUCLEAR POWER CORPORATIONA. '.'P.O. Box 157, Governor Hunt Road+ . --'/''Vernon, Vermont 05354 4 157s /(802) 257-7711x -,~.Feb.05,1998BVY 98-20U.S. Nuclear Regulatory Commission|ATTN: Document Control DeskWashington D.C. 20555Subject:Vermont Yankee Nuclear ...

Insp repts 50-266/97-22 & 50-301/97-22 on 971104-980203.No violations noted.Major areas inspected:review of 20 licensee event repts submitted between 960909 & 971215.

....U.S. NUCLEAR REGULATORY COMMISSIONREGION lliDocket Nos: 50-266,50-301License Nos: DPR 24, DPR 27EA Nos: 97 347 and 97-505Report No:50-266/97022(DRP); 50-301/97022(DRP)|;Licensee: Wisconsin Electric Power Company, WEPCO!Facility: Point Beach Nuclear Plant, Units 1 & 2Locati...

Proposed tech specs,adding new LCO to TS 2.15 pertaining to inoperable ESF logic subsystem.

. -- . - - . - - - . . . - .- - --_ - - -. .i. .4.DEFINITIONSI.;..PROTECTIVE SYSTEMS (Continued):!Ennineered Safety Feature Ircicm|wtputsJrorh9mdiv ualinstniqicnt channels to The system which utilizes conependerMf' initiate the itef6ation of incered safety'o logic subsystems, ...

Forwards HD Hukill 840330 ltr,840229 notice of violation, licensee 840402 revised response & GPU 840328 ltr & status rept re licensed operator experience.Related correspondence.

M (O.RaATED CORRESrwuclQ,') SHAW, PITTMAN, PoTTs & TROWBRIDGEA PARTNresMin or enortssioNAL componATioNsCCD._O.j, 'A 1800 M STREET, N. W.WASHINGTON, O. C. 20036maMsat o. .oTTs. pc JoMN ENGEL. p c. oE.o .. caessE m MamTMa .ooNE nowaN'w.E mg e:." = w::,r,=:"at: ara =e:eSi?.rfJat"...

"Preimplementation Audit of SPDS for Clinton Power Station."

, - .A,fEnclosure 2-..PRE-IMPLEMENTATION AUDIT OF THESAFETY PARAMETER DISPLAY SYSTEMFOR THECLINTON POWER STATIONJanuary 15, 1985Prepared for,U.S. Nuclear Regulatory CommissionWashington, D.C. 20555Prepared byScience Applications International Corporation1710 Goodridge DriveMcL...

Forwards proposed initial license exam w/two mods made to sample plan to be administered in Nov 1996 at PVNGS.

1__Palo Veroe NuclearTel SQ2092-053Q Mall Station ZQ2dGenerating Staten Fax 602f393-6164 P.o. Box 52034Phoenix, AZ 85072-2034054-02430-RAN/MDBSeptember 27,1996Nuclear Regulatory Commission - Region IV611 Ryan Plaza Drive, Suite 400Arlington, Texas 76011-8064ATTN: Steve McCrory...