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"TER on Individual Plant Exam Front End Analysis."

l. .ISEA-92-553-029 A:3August 31,1995 ||-.,North Anna 1 and 2Technical Evaluation Reporton the Individual Plant ExaminationFront End Analysis|NRC-04 91-066, Task 29.!-John Darby, Technical AnalystWillard Thomas, Technical EditorFrank W. Sciacca, Technical EditoriII|Science and...

Browns Ferry Units 1, 2 & 3, License Amendments 67, 63 & 39, Changing Technical Specifications to Modify Bases for Scram Insertion Times.

FEB 24 1981 Docket No. 50-259 5QI-2w6 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401Di stri butsn Docket ORB 42 Local PDR NRC PDR DEisenhut RPurpl e TNovak RTedesco GLainas SNorri s RClark TIppol Ito OE...

Waterford 3, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003.

Entergy Operations, Inc.17265 River RoadTel 504 739 6650W3F11-2003-0055A4.05PRJuly 24, 2003U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555Subject: Waterford 3 SESDocket No. 50-382License No. NPF-38Technical Specification Bases Update to the ...

Brunswick Units 1 and 2, License Amendments 133 and 163, Revise Titles in TS for Consistency Between Index and Text.

4 June 13, 1989 Docket Nos. 50-325 DISTRIBUTION and 50-324 See attached list Mr. Lynn W. Eury Executive Vice President Power Supply Carolina Power & Light Company Post Office Box 1551 Raleigh, North Carolina 21602 Dear Mr. Eury: SUBJECT: ISSUANCE OF AMENDMENT NO. 133 TO FACILI...

Comanche Peak-03-2005-Final-Written Outline.

ES-401 PWR Examination Outline Form ES-401-2 Facility: CPSES Date of Exam: March 24, 2005 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 2 4 4 2 2 18 5 ...

Catawba, Initial Exam 2009-301 Final Sim/In-Plant JPMs.

CANDIDATE EXAMINER JPM09A CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09A Pressurize Cold Leg Accumulator 1A Page 1 of 9 CANDIDATE EXAMINER JPM09 A CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 A Pressurize...

Reactor Technology Memo RTM-4, "ECCS Evaluation Guidelines."

-.'s';.'.... .RTM-40FFICIAL USE ONLY..|| DiERGENCY CORE COOLING SYSTD(l'EVALUATION GUIDELINESJanuary 1968.9|i||||48803210147 000311PDR FOIACONNER 88-17PDRr..OFFICI AL USE ONLY'RTM-4 January 1968LIST OF GUIDELINESEmergency Core Cooling Definitions1. ECCS Functional Requirements...

Revised Response to a Portion of NRC RAI Letter No. 368 Related to ESBWR Design Certification Application - Piping Design; RAI Number 3.12-3 S05.

GE Hitachi Nuclear Energy Richard E. Kingston Vice President, ESBWR Licensing P.O. Box 780 3901 Castle Hayne Road, M/C A-65 Wilmington, NC 28402 USA T 910.819.6192 F 910.362.6192 rick.kingston@ge.com MFN 09-670 Revision 1 Docket No. 52-010 January 12, 2010 ...

Oconee Nuclear Station - Technical Specification Bases (TSB) Change.

hDue BRUCE H HAMILTONVice President6 oEnergy® Oconee Nuclear StationDuke Energy CorporationON01 VP / 7800 Rochester HighwaySeneca, SC 29672864 885 3487December 6, 2006 864 885 4208 faxbhhamilton@duke-energy. cornU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Attenti...

Safety Analysis Report for Certificate of Compliance No. 9216, Model No. CNS 1-13G, Revision No. 0.

'7/- 2/SAFETY ANALYSIS REPORT FOR CNS MODEL 1-13G SHIPPING CONTAINERRevision 0 December 1987 Submitted By: CHEM-NUCLEAR SYSTEMS, INC. 220 Stonerldge Drive Columbia, SC 29210/ / A I 14 1-8712150255 871124 PDR ADOCK 07109216 C PDRC P79 7TABLE OF CONTENTSPage1.0 GENERAL INFORMAT...

Palo Verde, Units 1, 2, & 3, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process.

10 CFR 5O.90A M A subsidiary of Pinnacle West Capital CorporationDwight C. Mims Mail Station 7605Palo Verde Nuclear Vice President Tel. 623-393-5403 P. 0. Box 52034Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034102-05801...

Proposed Revision 2 to Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Draft 1.

3Draft 1October 15, 1979PROPOSED REVISION 2 TO REGULATORY GUIDE 1.97INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTSTO ASSESS PLANT AND ENVIRONS CONDITIONS DURING AND FOLLOWING AN ACCIDENTA. INTRODUCTIONCriterion 13, "Instrumentation and Control," of Appendix A, "Ge...

NEDO-33201, Revision 3, "ESBWR Certification Probabilistic Risk Assessment," Section 21A, Verification of the Transient CLCH Model.

NEDO-33201 Rev 3 21A-121A VERIFICATION OF THE TRANSIENT CLCH MODEL In this Appendix, the transient CLCH model is verified with a sample of three experiments from the Integral Effects Tests (IET) series. This adds to the previous extensive validation of the original CLCH mod...

Mitsubishi Heavy Industries LTD, Responses to US-APWR DCD RAI No. 490-3732.

A,MITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANFebruary 4, 2010Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. JefferyA. CioccoDocket No. 52-021MHI Ref: UAP-HF-10033Subject: MHI's Responses to US-APWR...

Licensing Topical Report, NEDO-33201, Rev. 5, "ESBWR Certification Probabilistic Risk Assessment," Chapter 21.A - Verification of the Transient CLCH Model.

NEDO-33201 Rev 5 21A-1 21A VERIFICATION OF THE TRANSIENT CLCH MODEL In this Appendix, the transient CLCH model is verified with a sample of three experiments from the Integral Effects Tests (IET) series. This adds to the previous extensive validation of the original CLCH mo...

List of all Questions.

2009 NRC Special Inspection - RB Concrete Separation20-Jan-10 11:21:08 ARequest Number: 1Individual Contacted: Sid PowellRequestor/Inspector: lAnthony Masters1 Date Contacted: 10/15/2009Category: QuestionRequest: There is an area on the containment dome on the south, approxima...

2005 ILRT.pdf.

ENCLOSURE1[NOCS 002542. 0018581Procedure ApproVal and Transmittal SheetProcedure # Revision # Title  L.AAe fes$- "T7I".'I I atoftw trA U- 1 y"Reason Performed (Schedule, WO#, Testing, etc.) Work Order Task #Comments:TECHNICAL SPECIFICATION OTHER (NON-TECHNICAL SPECIFICATION)A...

Watts Bar Nuclear Plant, Unit 2 - Amendment 99 to Final Safety Analysis Report (FSAR), Section 3 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.1-1 through 3.8.4-182.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-99m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornado...

Meeting Minutes of the 564th ACRS Meeting on July 8th thru 10th, 2009.

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 October 23, 2009 MEMORANDUM TO: ACRS Members FROM: Sherry Meador /RA/ Technical Secretary, ACRS SUBJECT: CERTIFICATION OF THE MEETING MI...

Calculation No. C-1101-900-E000-083 Revision 2, "EAB, LPZ, and CR Doses Due to Fuel Handling Accident in Reactor Building With Hatch Doors Opened."

ENCLOSURE 2TMI Unit 1 Calculation No. C-1101-900-EOOO-083Revision 2"EAB, LPZ, and CR Doses Due to Fuel Handling Accident In Reactor BuildingWith Hatch Doors Opened"Exelon.NuclearCC-AA-309-1001Revision 2ATTACHMENT 1Design Analysis Cover SheetDesign Analysis (Major Revision) I L...

Outline Submittal For The Monticello Initial Examination - May 2005.

OUTLINE SUBMITTAL FOR THE MONTICELLO INITIAL EXAMINATION - MAY 2005 Monticello Outline Submittal Contains the following: Station Cover Letter transmitting the outline ES-201-2 Examination Outline Quality Checklist ES-301-1 ES-301-2 ES-301-5 Transient and Event Checklist ES-401...

Wolf Creek, Submittal of Changes to Technical Specification Bases - Revisions 36 through 40.

W F CREEKNUCLEAR OPERATING CORPORATIONRichard D. FlanniganManager Regulatory Affairs March 11, 2009RA 09-0053U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Subject: Docket No. 50-482: Wolf Creek Generating Station Changes toTechnical Specific...

River Bend RB-2008-12 - Final Written Exams.

RB-2008-12 Written Exam Answer Key 1. B 2. B 3. B 4. A 5. A 6. D 7. C 8. D 9. D 10. C 11. A 12. B 13. A 14. B 15. B 16. A 17. C 18. B 19. B 20. C 21. D 22. A 23. D 24. C 25. D 26. C 27. C 28. B 29. A 30. D 31. B 32. B 33. D 34. A 35. B 36. B 37. A 38. D 39. D 40. C 41. C 4...

R. E. Ginna Final Examinations Outlines (Folder 3).

\ f%Lf#[ 0LK4AIc ----- -- ES-401 Form ES-401-2 RO WA Category Points SRO-Only Points Systems 2 20111110111 10 011 2 3 Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e.. except for one category i...

2006/12/03-Oyster Creek September 2007 Evidentiary Hearing - Intervenors Exhibit 35, Letter from AmerGen to the NRC (2103-06-20426) (Excerpted pages: pp. 1-3, pp. 9-15, pp. 17-24

Citizens Exhibits 3577,45 1f/3 5 /AmerGen.Michael.P. Gallagher, PEVice PresidentLicense Renewal ProjectsAmerGen2oo Exelon WayKSA/2-EKennett Square, PA 193482130-06-20426Telephone 61o.765.5958www.exeloncovp.commichaelp.gallagher@exeloncorp.comnDOCKETEDUSNRCOctober 1, 2007 (10:4...