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2009 Fermi Initial License Examination Administered Written Examination.

2009 Fermi 2 NRC SRO License Exam QUESTION 1 With the plant operating at 100% power, the following indications exist: • 7D14, GEN SERV H2O HEADER PRESSURE HIGH/LOW alarms • 4D64 GENERATOR H2 COOLERS INLET/OUTLET GAS TEMP HIGH / LOW TEMP HIGH alarms. • Main Generator H2 Coole...

2010/05/19 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 276, FSARCh. 11, Supplement 4

1ArevaEPRDCPEm ResourceFrom: BRYAN Martin (EXT) [Martin.Bryan.ext@areva.com]Sent: Wednesday, May 19, 2010 3:16 PMTo: Tesfaye, GetachewCc: DELANO Karen V (AREVA NP INC); ROMINE Judy (AREVA NP INC); BENNETT Kathy A (OFR) (AREVA NP INC); NOXON David B (AREVA NP INC)Subject: Respo...

St. Lucie Plant, Units 1 and 2 - Issuance of Amendments Regarding Deletion of the Structural Integrity Technical Specification Update of Accident Monitoring Instrumentation Requirements and Various Administrative Changes.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 28,2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 SUB~IECT: S1. LUCIE PLANT, UNITS 1 ...

V. C. Summer June 2007 Exam Nos. 05000395/2007301 Final SRO AS Given Written Exam.

Final Submittal(Blue Paper)V t,. S)()()1/f)l?r2(07- ~O/.~f)e. /3/ 2,{)o7AS GivwSenior Operator Written Examinationv. C. SUMMER JUNE 2007 EXAMEXAM NO. 05000395/2007301JUNE 4 - 8, 2007 (OP TEST)JUNE 13,2007 (WRITTEN EXAM)u.s. Nuclear Regulatory CommissionSite-Specific SRO Writte...

Wolf Creek, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls.

WOLF CREEKNUCLEAR OPERATING CORPORATIONTerry J. GarrettVice President, EngineeringSeptember 12, 2007ET 07-0040U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Reference: Letter ET 07-0004, dated March 14, 2007, from T. J. Garrett,WCNOC, to USNR...

Rev 3 to 26A6642AY, "ESBWR Design Control Document - Tier 2," Chapter 9, Changes from Revision 2 to Revision 3.

Page 1 of 36363636 Chapter 9 From Revision 2 to Revision 3 Change List Item Location Description of Change 1. S9.1, 1-4 para. Revised for clarity and Additional information provided 2. S9.1 5th para. 2nd sent. from last Revised for clarity to state reactor building storag...

Response to Portion of NRC Request for Additional Information Letter No. 69 Related to ESBWR Design Certification Application - Safety Analyses - RAI Number 15.4-1S01.

GE-Hitachi Nuclear Energy Americas LLCJames C. KinseyProject Manager, ESBWR LicensingPO Box 780 M/C A-55Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 07-017, Supplement 1 Docket No. 52-010August 22, 2007U.S. Nuclear Regulatory CommissionDocument ...

San Onofre, Units 2 & 3, Response to GL-04-002.

7IJISOUTHERN CALIFORNIA Ross T. RidenoureL~I nIC~rVVP and Site ManagerF 1E u IS LJ ON~I San Onofre Nuclear Generating StationAn EDISON INTERNA TIONAL®K CompanyFebruary 27, 2008U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Subject: Docke...

Final - Outlines (Change Summaries - Optional)

ES401 Written Examination Form ES-401-9 Review Worksheet 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other Y LOK LOD (FIH) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Focus Dist. Link units ward WA Only 1 2 3 X 4 X 5 6 X 7 8 9 10 6. 7. U/E/S Explanat...

Enclosure 9: Draft RAI Responses Concerning AMPs.

DRAFTReceived 8/26/02L-2002-16610 CFR 54U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555Re: St. Lucie Units 1 and 2Docket Nos. 50-335 and 50-389Response to NRC Request for Additional Information for Review of theSt. Lucie Units 1 and 2 Lice...

Seabrook Station - Draft Written Exam (Folder 2).

-----Seabrook Station 2009 Licensed Operator Remediation Written Exam ES-40I-5 Written Examination Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Question 1 Group # 1 KIA # 007 Reactor Trip­Stabilization EKI Knowledge of the operational implicat...

NUREG-1426, Vol. 3, Compilation of Reports from Research Supported by the Electrical, Materials, and Mechanical Engineering Branch, Division of Engineering, 1994-1998.

Compilation of Reports From Research Supported by the NUREG-1426 Vol. 3 Electrical, Materials, and Mechanical Engineering Branch, Division of Engineering 1994 - 1998 u.s. Nuclear Regulatory Commission Office of Nuclear Regulatory Research AVAILABILITY NOTICE Availability of Re...

Enclosure 3: Safety Evaluation Report (Non-Proprietary) (R. Grubb Letter re: Model No. TN-40 Package Approval).

SAFETY EVALUATION REPORT (NON-PROPRIETARY) Docket No. 71-9313 Model No. TN-40 Package Certificate of Compliance No. 9313 Revision No. 0 i TABLE OF CONTENTS SUMMARY ....................................................................................................

Response to Portion of NRC Request for Additional Information Letter No. 293 - Related to ESBWR Design Certification Application - RAI Number 21.6-96 Supplement 2.

HITACHI GE Hitachi Nuclear EnergyRichard E. KingstonVice President, ESBWR LicensingPO Box 780 M/C A-65Proprietary Notice Wilmington, NC 28402-0780This letter forwards proprietary information in USAaccordance with 1OCFR2.390. Upon theremoval of Enclosure 1, the balance of this ...

Browns Ferry Nuclear Plant (BFN) - Response for Additional Information Regarding Units 1, 2, and 3 - Technical Specifications (TS) Change 444 - Adoption of Changes to Standard Technical Specifications Under Technical Specification Task Force (TSTF) .....

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000April 24, 2009TVA-BFN-TS-44410 CFR 50.90U.S. Nuclear Regulatory CommissionATTN: Document Control DeskMail Stop: OWFN P1-35Washington, D.C. 20555-0001In the Matter of ) Docket Nos. 50-259Tennessee Vall...

US-APWR Design Certification: SRP Section: 09.02.02 - Reactor Auxiliary Cooling Water Systems Application Section: 9.2.2.

REQUEST FOR ADDITIONAL INFORMATION 362-2278 REVISION 0 15/13/2009 US-APWR Design Certification Mitsubishi Heavy Industries Docket No. 52-021 SRP Section: 09.02.02 - Reactor Auxiliary Cooling Water Systems Application Section: 9.2.2 QUESTIONS for Balance of Plant Branch...

"1987 Annual Evaluation of Term DOE Waste Package Programs: Generic Problems with the DOE Compliance Strategies."

DRAT BNL-521111987 ANNUAL EVALUATION OF TEM DOE WASTE PACKAGE PROGRAMS:GENERIC PROBLEMS WITH THE DOE COMPLIANCE STRATEGIESD. C. Schweitzer and C. SastreOctober 1987DOE RADIOACTIVE WASTE MANAGEMENT DIVISIONDONALD G. SCWITZER, EAmD UPARTW OF NUCLAd EIRYBROOKHAVEN NATIONAL LABORA...

Braidwood and Byron Stations, Units 1 and 2 - Request for License Amendment Related to Application of Alternative Source Term.

' ExekrnSMExelon Generation www.exeloncorp.com Nuclear4300 Winfield RoadWarrenville, IL 6055510 CFR 50.90RS-05-001February 15, 2005U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Braidwood Station, Units 1 and 2Facility Operating License ...

Edwin I. Hatch Units 1 & 2 Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling Systems Using the Consolidated Line Item Improvement Process.

Lewis Sumner Southern Nuclear Vice President Operating Company, Inc. Hatch Project Support 40 Inverness Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7279 Fax 205.992.0341 SOUTHERN COMPANY Energy to Serve Your WorldSM June 24, 2002 Docket Nos. 50-321 HL-6...

Initial Submittal of Scenarios for Braidwood Initial Examinationn - July 2004.

Braidwood NRC 04-1 Page 1 Simulation Facility Braidwood Scenario No.: NRC 04-1 Operating Test No.: 2004301 Examiners: _______________________ Applicant: ______________________ SRO _______________________ ______________________ RO _______________________ __Surrog...

Fermi Sept 2004 SRO Initial Exam.

Question #1 Details EQ-OP-802-2001-000-S001-001 2004 SRO NRC Exam Question Text The reactor is operating at 100% power when a Loss of Power Event occurs. The CRNSO reports the following: 345KV mat power indicating lights........................off EDG 13................

Byron, Units 1 and 2, License Amendment Request Regarding Ultimate Heat Sink.

Exelon Nuclear www.exeloncorp.com 4300 Winfiield Road War renville, I L 60555 RS-09-054 10 CFR 50.90 June 30, 2009 U . S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 ...

Calculation No. 060-PSA-CR00-00200-000-00B, "Canister Receipt and Closure Facility Receipt Facility Reliability and Event Sequence Categorization Analysis," Attachment D, Page D-22 Through D-71.

Canister Receipt and Closure Facility Reliability 060-PSA-CROO-00200-000-00B and Event Sequence Categorization Analysis Table 01.2-6. Strains at Various Canister Locations Due to Drops Maximum PEEQ Strains (%) Load Casel Canister Component ConditionsOutside Mid- Inside Surface...

Susquehanna, Unit 2 - Revision 2 to Technical Specification Bases Manual TSB2 3.8.4, Revision 1 of TSB2 3.8.5, Revision 1 of TSB2 3.8.6 and Revision 79 to TSB2 Text LOES.

Dec. 15, 2006Page 1 of 1MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2006-52298USER INFORMATION:Name:GERLACH*ROSE MEMPL#:028401 CA#:0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSE M 12/15/2006LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTRO...

Unistar Nuclear - Calvert Cliffs Power Plant Unit 3 COLA 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...