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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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OFFICIAL EXHIBIT - MANDATORY HEARING - NRC000040-MA-BD01 - Request for Exemption from 10 CFR 21.3, Definitions, for "Commercial Grade Item, Basic Component, Critical Characteristic, Dedication, and Dedicating Entity".

AREVA10 CFR 21.7January 29, 2010AES-O-NRC-10-00081-0ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001AREVA Enrichment Services LLCEagle Rock Enrichment FacilityNRC Docket No: 70-7015Subject: Request for Exemption from 10 CFR 21.3, Definiton...

NUREG-0800, Rev . 0, Section 17.3, " Quality Assurance Program Description."

NUREG-0800(Formerly NUREG-75/087)ENCLOSURE 1%4 . U.S. NUCLEAR REGULATORY COMMISSION(iJ STANDARD REVIEW PLA-N/ OFFICE OF NUCLEAR REACTOR REGULATION17.3 QUALITY ASSURANCE PROGRAM DESCRIPTIONREVIEW RESPONSIBILITIESPrimary - Performance and Quality Evaluation Branch (LPEB)Secondar...

AREVA Design Control Document Rev. 2 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.8.6 Main Feedwater System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Tier 1 Revision 2 Page 2.8-30 2.8.6 Main Feedwater System 1.0 Description The main feedwater system (MFWS) is a non-safety-related system with portions that are safety related. It transports and controls feedwater from the deaerator/fee...

AREVA Design Control Document Rev. 2 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.6.4 Fuel Building Ventilation System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Tier 1 Revision 2 Page 2.6-36 2.6.4 Fuel Building Ventilation System 1.0 Description The fuel building ventilation system (FBVS) receives the conditioned air supply from the nuclear auxiliary building ventilation system (NABVS). The exh...

Submittal of Final Status Survey Report, Amendment 4, Pentolite Ditch, for Plum Brook Reactor Facility.

Space AdministrationJohn H. Glenn Research Center,"Lewis FieldPlum Brook Station 7'Sandusky, OH, 44870 /August 26, 4i11foiReply to Attn of: QDU.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555Subject: Final Status Survey Report, Attachment 4, P...

Arkansas Nuclear One, Unit 1 - Relief, ANO1-R&R-016, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval. ME6107.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 10, 2011 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 SUBJECT: ARKANSAS NUCLEAR ONE, UNIT NO.1 - REQUEST FOR USE OF NON­ASME CODE ...

DRAFT NRC Regulatory Issue Summary 2011-## Follow Up To Response For Generic Letter 96-05 Guidance For The Evaluation Of Class D Valves In The Joint Owners Group Motor-Operated Valve Periodic Verification Program.

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS WASHINGTON, DC 20555-0001 Month XX, 2011 NRC REGULATORY ISSUE SUMMARY 2011-XX FOLLOW UP TO RESPONSE FOR GENERIC LETTER 96-05 GUIDANCE FOR THE EVALUATION OF CLASS D VALVE...

Forwards addl info in response to IE Bulletin 80-11 re seismic qualification of masonry walls.W/23 aperture cards. Aperture cards are available in PDR.

REGULeRY INFORMATION DISTRIBUTICSYSTEM CRIDS)ACCESSION NBR:8305030314 DOC.DATE: 83/04/29 NOTARIZED: NO FACILtS0-305-Kewaunee Nuclear Power Plant, Wfsconsin Public Servic AUTH.NAME AUTHOR AFFILIATION GIESLERt,C . WsconsiaPublic Service Corp. RECIP.NAME RECIPIENT AFFILIATION VA...

OFFICIAL EXHIBIT - MANDATORY HEARING - NRC000085-MA-BD01 - Request for Exemption from 10 CFR 21.3, Definitions, for "Commercial Grade Item, Basic Component, Critical Characteristic, Dedication, and Dedicating Entity."

AREVA10 CFR 21.7January 29, 2010AES-O-NRC-10-00081-0ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001AREVA Enrichment Services LLCEagle Rock Enrichment FacilityNRC Docket No: 70-7015Subject: Request for Exemption from 10 CFR 21.3, Definiton...

Regulatory Guide 1.206 - Section C.I.1 Introduction and General Description of the Plant.

Issued for Preliminary Use110 CFR 52.8, “Combining licenses; elimination of repetition,” allows an applicant to combine several applications fordifferent kinds of licenses (e.g., power reactor and an independent spent fuel storage installation) and allows the agencyto combine ...

Three Mile Island Unit 1, Request for Relief to Utilize Code Case N-659, "Use of Ultrasonic Examination in Lieu of Radiography for Weld Examination Section III, Division 1."

ArnerCen Energy Company, 1.LC WVL‘V~,.I-XelOric.;.a.C/3.T* 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.55a 5928-06-20560 September 28, 2006 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Three Mile Island, Unit 1 Facility Operating L...

2008/02/07-Shaw AREVA MOX Services LLC's Response to Petitioners' Contention 4 as Reformulated by the Board.

fLA4-5 / S -a 19-,A'DOCKETEDUSNRCFebruary 8, 2008 (:8:15am)OFFICE OF SECRETARYRULEMAKINGS ANDADJUDICATIONS STAFFUNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONATOMIC SAFETY AND LICENSING BOARD)In the Matter of: ))Shaw AREVA MOX Services, LLC ))(Mixed Oxide Fuel Fabricati...

12/02/2009 Summary of Meeting with the Industry Focus Group on New Reactor Operator Licensing.

December 30, 2009 MEMORANDUM TO: Michael Junge, Chief Operator Licensing and Human Performance Branch Division of Construction and Operational Programs Office of New Reactors FROM: Richard Pelton /RA/ Operator Licensing and Human Performance Branch Division of C...

CO Insp Rept 50-286/69-06 on 690625-26.Major areas inspected:review status of deficiencies found in last insp, concrete batch plant & control of aggreggates & status of written procedures listed in App E of QA suppl to PSAR.

U. SATOMIC EERGY COMMISSION. REGION I DIVISION OF COMPLIANCE Report of Inspection CO Report No. 286/69-6 Licensee: Consolidated Edison Company Indian Point No. 3 Category A Date of Inspection: June 25-26, 1969 Date of Previo :ngn on. April 30 and May 1, 1969 inspected By: .b...

2010/03/15-Petitioners' Response to Licensing Board Memorandum and Order Regarding Prehearing Conference Transcript Corrections.

1UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARD___________________________________In the Matter of Tennessee Valley Authority Docket Nos. 50-438 and 50-439 Bellefonte Nuclear Power Plant Units 1 and 2 ...

QSA Responses to RAIs and SAR Revision No. 10 for the 741-OP package, dated April 15, 2010.

15 April 2010 Pierre Saverot, Project Manager Licensing Branch Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission 11555 Rockville Pike One White Flint Rockville, MD 20852 Docket No. 71-9027 (Mod...

Trip Report - July 9-10, 2008, Readiness Assessment (T-2) Visit for a Combined License Applications at the Fermi, Unit 3, Site.

September 16, 2008 MEMORANDUM TO: Andrew Kugler, Acting Chief Environmental Projects Branch 2 Division of Site and Environmental Reviews Office of New Reactors FROM: H. Brent Clayton, Chief /RA/ Environmental Technical Support Branch Division of Site and Environment...

AmerenUE Callaway Plant Unit 2 COLA Rev. 0 - Chapter 03 - Plant Description

ER Chapter 3.0Callaway Plant Unit 2 3–1 Rev. 0© 2007-2008 UniStar Nuclear Services, LLC in and to the Reference COLA, namely all text not in brackets© 2007-2008 Union Electric Company d/b/a AmerenUE in and to all Callaway site specific and AmerenUE specific COLA material, nam...

Matls licensing package for amend 5 to license 24-24660-01 for Lee Summit Hosp.Control:393886.

- -- - - - - - .9e*,y______ q _______________ ,-__ - %PAGU.S. NUCLE AR ftEGULATOTW COMM!S$10N- PAGESsoI, hMATERIALS LICENSEr[f Code of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35, 39,40 and 70. and in f nuclear material designated below; to use such ruterial fer th...

Palo Verde, Unit 1, and Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canister Identification No. AMZDFX127.

10 CFR 72.212(b)(2)SapsPalo VerdeNuclear Generating Station5801 S. Wintersburg Road102-07051-TNW/CJS Tonopah, AZ 85354May 15, 2015ATTN: Document Control DeskDirector, Division of Spent Fuel Storage and TransportationOffice of Nuclear Material Safety and SafeguardsU.S. Nuclear ...

Forwards deficiency rept on 780413 re defective solder connections on electrical penetrations X100,A,B,C & D.

REGULATORY ? RMATION DISTRIBUTION SYS.(RIDS)ACCESSION NBR:7906080312 DOC~DATE'9/05/31 NOTARIZED'O DOCKETFAC?Li50 397'IIPPSS Nuclear Pr oJecti Unit 2i Washington Public Powe'5000397AUTHBYNAMEAUTHORAFFILIATIONRENBERGERiD,L, Nashington Public Power Supply SystemREC IP~NAME RECIP?...

E-mail from ODOT- Traffic Count Data-Cimarron Site NE of SH 74 and SH 33.

From: Daryl JohnsonTo: Bjornsen, AlanCc: Ron Maxwell; Matthew BlakesleeSubject: [External_Sender] RE: Cimarron Site, NE of SH 74 and SH 33Date: Thursday, October 27, 2016 11:06:15 AMAttachments: image2016-10-27-103302.pdf2015 42-Logan.pdfMr. Bjornsen,I have attached a 2015 AAD...

Expresses appreciation & urges continued effort to ensure safety of residents by requiring util to abide by all federal regulations.Util should complete successful testing of plant before license granted.

ACCESSION NBR:FACIL: 50-400AUTH. NAI'fEFLATHATC. A.REC IP. NANFDENTON> H.REGU ORY INFORMATION DISTRIBUT N SYSTEN (R IDS>8701070301 DOC. DATE: B7/01/02 NOTARIZED: NO DOCKET 4Shearon Harv is Nucleav Power Planti Unit ii Carolina 05000400AUTHOR AFFILIATIONAFFiliation Not Assigned...

Final Part 21 rept re potential failure of anchor bolts supplied by Hilti Fastening Sys,Inc initially reported on 800814.Condition determined not reportable per 10CFR50.55(e) or 10CFR21.

-- - _ _ _ _ _ - _ _ _ _ _ _ _ - - - _ _ - ._ ._ _ _ - _ _ _ _ ,| * * ^-D *\'*3'/NilSSISSIPPI POWER & LIGHT COMPANY'.Helping Build MississippiP. O. B O X 1640, J A C K S O N, MIS SIS SIP PI 3 9 2 0 5" " ' ' " "33'dOO#JAME$ P. McGAUGHY.JR.awstw vca m we.nOffice of Inspection & ...

Interim deficiency rept re embed plate load capacity tables. Pipe supports currently undergoing review & design drawings will be revised.Final rept will be submitted by 800715.

3. 8005130'/.5.2.SGeorgia Power CompanyPost Office Box 4545LAtlanta, Georgia 30302Vogtle ProjectTelephone 404 522-606oSouthem Company Services, Inc.!Post Office Box 2625May 8, 1980|Birmingham, Alabama 35202Telephone 205 87o-60t1.|United States fluclear Regulatory Commission Fi...