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Forwards response to Matls & Chemical Engineering Branch 910808,Structural & Geosciences Branch 910926 & Plant Sys Branch 911010 requests for addl info re SSAR - design certification.

. _ _ . - - . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ - _ _ _ _ _ _ _ - - - - _ _ _ _ - _i''4 ,Anrumou now m.iJanuary 24,1992LD 924)07,eDocket No. 524)02'tU. S. Nuclear Regulatory Commission,.Attn: Document Control DeskWashington, DC 20555Subject: Response to NRC Requ...

Forwards NRC Approved Operator Licensing Exam (facility outline & initial exam submittal) for tests administered on 970324-28.

' - -,1. $m ukUNITED STATEStNUCLEAR REGULATORY COMMISSIONREGION IV(+9611 RYAN PLAZA DRIVE, SulTE 400't, ARLINGTON, TEXAS 76011-8064May 6, 1997lNOTE T0;NRC Document Control DeskMail Stop 0 5 D 24FR0h: Laura Hurley, Licensing AssistrntOperations Branch, Region IVSUBJECT:OPERATOR...

Insp Repts 50-454/85-22 & 50-455/85-20 on 850506-0722. Violations noted:failure to follow radiation protection procedures,inadequate instructions to workers,inadequate high radiation area controls & lack of adequate procedures.

;- :U.S. NUCLEAR REGULATORY COMMISSIONREGION IIIReports No. 50-454/85022(DRSS); 50-455/85020(DRSS)Docket Nos. 50-454; 50-455 Licenses No. NPF-37; CPPR-131Licensee:Commonwealth Edison CompanyPost Office Box 767Chicago, Illinois 60690Facility Name: Byron Nuclear Power Station, U...

Appendix A and B of Harris IPEEE submittal

52214-R-001 Rev. 0 Appendix A Page A-1 APPENDIX A SEISMIC REVIEW TEAM QUALIFICATIONSP:\52214\SHNPrpt~irv52214-R-001 Rev. 0 Appendix A Page A-2 JEFFREY H. BOND Jeffrey H. Bond has over seventeen years of experience in the design, analysis, testing, and qualification of industri...

Dresden Table LA - Removal of Details Matrix and Specification Requirements.

TABLE LA - REMOVAL OF DETAILS MATRIX AND SPECIFICATION REQUIREMENTSCHAPTER 1.0 - USE AND APPLICATIONPage 1 of 39 Dresden 2 and 3ITS SECTIONAND DOC #CTSSECTIONSUMMARY LOCATION CHANGE CONTROLPROCESSCHANGETYPE1.0-LA.1 1.0 Moves the definition of FRACTION OF RATED POWER(FRTP) and ...

Revision 35 to EPIP-El-1 "Emergency Classification & Actions"

Date Entered: Jan 17, 2001TO: USNRCIWASHINGTON JMCKNIGHTCopy Number: 145HTRANSMITAL NUMBER: 173831 PROCEDURE NUMBER: El-1 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM ...

Indian Point, Units 2 & 3 - Submittal of 60-Day Response to NRC Bulletin 2002-01.

Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 271 7060 Fax 914 271 7181 jherron@entergy.comJohn T. Herron Senior Vice President May 15, 2002 N L-02-074 I PN-02-039U.S. Nuclear Regulatory Commission ATTN:...

Westinghouse, Transmittal of AP1000 Fire Risk Assessment.

*Westinghouse U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555Westinghouse Electric Company Nuclear Plant Projects P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA Direct tel: 412-374-5355 Direct fax: 412-374-5456 e-mail: corletmm@...

Davis-Besse Oversight Panel Restart Action Matrix Closures - Non-Cited Violation Items.

March 22, 20041RAM Item No. - NCV-01 Closed: Y Description of Issue - Failure to have procedural guidance to control the construction ofscaffolding in a manner that would assure proper operation of ventilation of safety equipment. During a run of EDG 2, scaffolding restri...

Supplement to Oyster Creek Implementation of Emergency Action Levels Developed from NUMARC/NESP-007 Methodology.

AmerGenSMAmerGen Energy Company, LLC www.exeloncorp.com An Exelon/British Energy Company200 Exelon WayKennett Square, PA 1934810CFR50 Appendix E.IV.B2130-03-20311December 12, 2003U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Oyster Cree...

Minutes of the 74th ACNW Meeting, May 10-11, 1995.

MINUTES OF THE 74TH ACNW MEETINGMay 10-11, 1995- TABLE OF CONTENTS -PageI. Chairman's Report (Open) . . . . . . . . . . . . . . . .II. NRC Staff Position on Substantially Complete Containment(Open) . . . . . . . . . . . . . . . . . . . . . . . ..III. Meeting with the Director,...

Pilgrim Nuclear Power Station Fourth Ten-Year Inservice Inspection Program Plan and the Associated Relief Requests for NRC Approval.

E- t1 ~ Entergy Nuclear Operations, Inc.-= 7oEnte g y Pilgrim Station> tJ 600 Rocky Hill RoadPlymouth, MA 02360Stephen J. BethayDirector. Nuclear AssessmentJune 29, 2005U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001SUBJECT: Entergy Nucle...

River Bend-2008-12-Draft Written Exams.

2008 River Bend Station Initial NRC License Examination Reactor Operator 1 QUESTION 1 Rev 0 Examination Outline Cross-Reference: Level RO SRO Tier # 1 Group # 1 K/A # 295001 AK3.04 Importance Rating 3.4 Knowledge of the reason for a reactor scram as it a...

RO/SRO Initial Examination - Davis-Besse July 2009.

U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: July 20, 2009 Facility/Unit: Davis Besse U1 Region: I II III IV Reactor Type: W CE BW GE Start Time: 0800 Finish Time: Instructions U...

AREVA Federal Services LLC - Request for Additional Information on TRUPACT-IH, Docket No. 71-9305.

AAREVARef AFS-1O-0020Document No. TP3(51199)GLCO12610January 26, 2010ATTN: Document Control DeskDirector, Spent Fuel Project OfficeOffice of Nuclear Material Safety and SafeguardsU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001SUBJECT: Request for Additional Inform...

Transcript of 701218 hearing in Peekskill,NY. Pp 363-452.Prof qualifications,testimonies & safety evaluation encl.

Dae- Pages,DUPLICATION OR COPYING OF THIS TRANSCRIPT BY PHOTOGRAPHIC, ELECTROSTATIC OR OTHER FACSIMILE MEANS IS PROHIBITED BY THE ORDER FORM AGREEMENTTelephone: (Code 202) 547-6222ACE - FEDERAL REPORTERS, INC. Official Reporters 415 Second Street, N.E. Washington, D. C. 2000...

Calculation No. 000-PSA-MGR0-00500-000-00B, "Subsurface Operations Reliability and Event Sequence Categorization Analysis," Attachment D, Page D-23 through D-72.

I Subsurface Operations Reliability 000-PSA-MGRO-00500-000-00B and Event Sequence Categorization Analysis Table 01.2-7. Failure Probabilities for the DOE Spent Nuclear Fuel (DSNF) Canisters and Multicanister Overpack (MCO) Probabilit~ of Failure Peak Equivalent Plastic CDF adj...

ANP-10290, Revision 0, "AREVA NP Environmental Report, Standard Design Certification."

ANP-10290 Revision 0 AREVA NP Environmental Report Standard Design Certification November 2007 AREVA NP Inc. (c) 2007 AREVA NP Inc. Copyright © 2007 AREVA NP Inc. All Rights Reserved AREVA NP Inc. ANP-10290 Revision 0 Applicant...

AREVA Design Control Document Rev. 0 - Tier 2 Chapter 10 - Steam and Power Conversion System - Section 10.3 Main Steam Supply System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 0 Page 10.3-110.3 Main Steam Supply SystemThe main steam supply system (MSSS) conveys steam from the steam generators (SG) to the high pressure (HP) turbine. The MSSS also provides steam to the second stage reheaters, de...

2005/01/01-Attachment 3 - North Anna ESP Application Engineering Calculation.

iWoDominion-Calculation Cover Sheet= A -1.Type 2. Sub 3. Station 4. Unit 5. Status 6. System Code(s)CALCNFL 03 AC N/A7. Calculation Number | 8. Rev. 9. AddendumSM-1 526 1 0 N/A10. QA Cat a SR | NSQ LI NS 11. Critical Calculation E] Yes A No12. Calculation Title (Subject):North...

South Texas, Units 3 & 4 Response to Request for Additional Information Relates to Combined License Application Part 2, Tier 2 Chapter 19.

Nuclear Operating CompanySouth Texas Project Electric Generating Station 4000 Avenue F- Suite A Bay City, Texas 77414December 3, 2009U7-C-STP-NRC-090216U. S. Nuclear Regulatory CommissionAttention: Document Control Desk.One White Flint North11555 Rockville PikeRockville MD 208...

Watts Bar, Unit 2 - Final Safety Analysis Report, Amendment 97, Section 3 - Design of Structures, Components, Equipment, and Systems, Page 3.8-1 through Figure 3.8.4-80, Page 3.8.4-182.

DESIGN OF CATEGORY I STRUCTURES 3.8-1WATTS BAR WBNP-97m3.8 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 to...

Response to NRC Request for Status of Corrective Actions Contained in the Omaha Public Power District (OPPD) Response to Generic Letter 2008-01.

Employment with Equal Opportunity 444 South 16th Street Mall Omaha, NE 68102-2247 LIC-10-0062 August 10, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 REFERENCES: 1. Docket No. 50-285 2. NRC Generic Letter 2008-01, ...

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

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 August 25, 2010 MEMORANDUM TO: ACRS Members FROM: Sherry Meador /RA/ Technical Secretary, ACRS SUBJECT: CERTIFICATION OF THE MEETING MIN...

Sequoyah Initial Exam 2010-301 Draft SRO Written Exam.

QUESTIONS REPORTfor 2010 Feb SRO exam007 EA2.04 076Given the following:- Unit 2 in seniice at 100% power with the TD AFW pump tagged.- The reactor failed to trip after a valid trip signal was received and attemptsto manually trip from the MCR were unsuccessful.- The crew enter...