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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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Motion for leave to file new contentions re LILCO offsite emergency preparedness training program.Proposed contentions & Certificate of Svc encl.

. ._-.t.% 4DOCKETEDU 2.CUNITED STATES OF AMERICAr,q7 gge . ,r, , i - ,.NUCLEAR REGULATORY COMMISSION_Before the Atomic Safety and Licensing Board.|)In the Matter of ))LONG ISLAND LIGHTING COMPANY )Docket No. 50-322-OL-3)(Shoreham Nuclear Power Station, )(Emergency Planning)Uni...

Discusses requalification program evaluation & senior operator license exam scheduled for wk of 930308.Encl ref info should be furnished prior to exam.

f#5 ,4)d(|Df.C2 1932|iDocket Nos. 50-277!50-278hir. D. hi. Smith|Senior Vice President-Nuclear'|Philadelphia Electric Company,jNuclear Group Headquarters ,!Correspondence Control Desk'||P. O. Box 195)Wayne, Pennsylvania 19087-0195:Dear hir. Smith:)SU10ECT:REQUALIFICATION PROGR...

Summary of NRC/IDCOR 851210 meeting re preliminary results & differences of risk analysis for facilities.Viewgraphs encl.

.- .- - . - _ - _ . - - . - - . - .. - - - - __ . - - _ -- -..}, bt .(m 9 ~ '.: .2MAR 0.i1E: .|MENDRANDUM FOR: Themis P. Speis, Director-Division of Safety Review and Oversight-FROM: Zoltan R. Rosztoczy, ChiefRegulatory Improvements Branch,Division of Safety Review and Oversig...

OFFICIAL EXHIBIT - NRC009-MA-BD01 - NRC Staff Pre-Filed Testimony on SER Topic 4: Consideration of Climate Change Induced Increases in the Power and Frequency of Hurricanes.

- 1 - UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of ) ) Docket No. 52-043-ESP PSEG POWER, LLC AND PSEG ) NUCLEAR, LLC ) ASLBP No. 15-943-01-ESP-BC01 ) (Early Site Permit Application) ) February 25, 2016 NRC...

Safety Evaluation Report for Exemption Request for Entergy Nuclear Operations, Inc.'s Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT DOCKET NOS. 51-271, 72-59, 72-1014 EXEMPTION REQUEST FOR ENTERGY NUCLEAR OPERATIONS, INC.’S VERMONT YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION ...

LER 17-01-00 for Nine Mile Point Unit 1 RE: Manual Reactor Scram Due to High Turbine Vibration.

p:i: .. 7 r+7 Exelon Generation® NMP1L3129 February 8, 2017 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 Docket No. 50-220 10 CFR 50.73 Subject: N...

Enclosure 3: Presentation Handouts [Memorandum to A. Hsia re: Summary of April 21, 2015, Public Meeting With The Nuclear Energy Institute On The Chloride Induced Stress Corrosion Cracking Regulatory Issues Resolution Protocol].

© 2015 Electric Power Research Institute, Inc. All rights reserved. John Broussard Dominion Engineering, Inc. Shannon Chu EPRI Susceptibility Assessment Criteria for Chloride-Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters for Dry Cask Storage Sys...

Attachment 1, NMSS Policy and Procedures Letter 1-82, "10 CFR Part 70 Backfit Guidance"

P&P 1-82 1This NMSS Policy and Procedures Letter (PPL) was written to be that “staff guidance.” 2A fuel cycle licensee’s commitment is a regulatory requirement if it appears in anenforceable document. Consult with OGC regarding whether a licensee’s commitment is aregu...

2003/12/12-Applications for Material License Under 10CFR70, "Domestic Licensing of Special Nuclear Material," 10CFR40, "Domestic Licensing of Source Material," and 10CFR30, "Rules of General Applicability to Domestic Licensing of Byproduct Material."

10 CFR 30.6, NNATIONAL 10 CFR 40.5ENRICHMENT 10 CFR 70.5FAACILITY 10 CFR 95.9December 12, 2003NEF#03-003DirectorsOffice of Nuclear Material Safety and Safeguardsand the Division of Facilities and SecurityU.S. Nuclear Regulatory CommissionWashington, DC 20555Louisiana Energy Se...

Three Mile Island, Unit 1 Biennial 10 CFR 50.59 and Commitment Revision Report for 2002 and 2003.

AmerGenSMAmerGen Energy Company. LLCThree Mile Island Unit 1Route 441 South, PO. Box 480Middletown, PA 17057Telephone: 717-948-8000An Exelon CompanyApril 15, 20045928-04-20105U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555THREE MILE ISLAND ...

12/22/04 Ltr to J. Ellis ( Seqyoyah Fuels Corporation) frm M. Fliegel - Sequoyah Fuels Corporation - Materials License No. SUB-1010 Request for Additional Information - Reclamation Plan Radiation Protection and Erosion Protection (TAC L52511).

December 22, 2004Mr. John H. EllisPresidentSequoyah Fuels CorporationP.O. Box 610Gore, OK 74435SUBJECT: SEQUOYAH FUELS CORPORATION - MATERIALS LICENSE NO. SUB-1010 -REQUEST FOR ADDITIONAL INFORMATION - RECLAMATION PLAN -RADIATION PROTECTION AND EROSION PROTECTION (TAC L52511)D...

Braidwood and Byron Technical Specification Changes of Pressurizer Safety Valve Setpoint Lift Settings (TAC Nos. MB9760, MB9761, MB9762 and MB9763).

July 15, 2004MEMORANDUM TO: G. Dick, Project ManagerProject Directorate IIIDivision of Licensing Project ManagementFROM: J. Uhle, Chief /RA/PWR Systems Section Reactor Systems BranchDivision of Systems Safety and AnalysisSUBJECT: BRAIDWOOD AND BYRON TECHNICAL SPECIFICATION C...

Susquehanna Steam Electric Station Proposed Amendment No. 266 to License NPF-14 and Proposed Amendment No. 231 to License NPF-22: Incorporation of TSTF-16 and Editorial Changes.

Britt T. McKlnnoyVice President-Nuclear Site OperationsPPL Susquehanna, LLC769 Salem BoulevardBerwick, PA 18603Tel. 570.542.3149 Fax 570.542.1504btmckinney@ pplweb.comPPtM.SEP 0 8 2004U.S. Nuclear Regulatory CommissionAttn: Document Control DeskMail Station OP1-17Washington, D...

Turkey Point, Unit 3 and 4, Issuance of License Amendment, Approves the steam generator repair program and provide license conditions related to the repair operation.

UOCI U L r i i 11;m V u.... LO a; r --: ORB I F1 e D. Eisenhut ___ us..M. C-rote'-h; 61 QEL Le bei.-OELD OI&E(5 G. Deegan f8) B. Scharf Dr. Robert E. Uhrig, Vice President B. Wetmore. Advanced Systems & Technology ACRS (10) LTC2ZSZAU C'AJ* Y-ITUEC CC Florida Power & Light Co...

SECY-00-0037 - "Status of Potassium Iodide Activities"

February 11, 2000 SECY-00-0037FOR: The CommissionersFROM: William D. Travers /RA/Executive Director for OperationsSUBJECT: STATUS OF POTASSIUM IODIDE ACTIVITIESPURPOSE:To inform the Commission of the status of NRC activities related to the use of potassium iodide(KI) as a su...

Part 1, "Safety Evaluation Report with Open Items Related to the License Renewal of Turkey Point Nuclear Plant, Units 3 & 4." Table of Contents to Page 3-82.

Safety Evaluation Report with Open Items Related to the License Renewal of Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 Florida Power & Light CompanyU.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation August 20010 4 ,ABSTRACTThis ...

North Anna, Units 1 & 2, License Amendments 104 & 91, Adding In-Core Thermocouples to Accident Monitoring Instrumentation, Technical Specification Tables 3.3-10 & 4.3-7.

June 20, 1988Docket Nos. 50-338 and 50-339 Mr. D. S. Cruden Vice President - Nuclear Virginia Electric and Power Company Post Office Box 26666Richmond, Virginia Dear Mr. Cruden:23261DISTRIBUTION Docket FileNRC & Local PDRs PDII-2 Rdg. SVarga, 14/E/4 GLainas, 14/H/3 DMiller LE...

Minutes of the 606th ACRS Meeting, July 9-12, 2013 [OPEN].

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 January 14, 2013 NOTE TO: FILE FROM: Sherry Meador, Technical Secretary /RA/ Advisory Committee on Reactor Safeguards The minutes of the subject ...

HI-STORM UMAX Canister Storage System (MPC-37, MPC-89), Preliminary SER, Certificate of Compliance No. 1040, Proposed Rule Supporting Information (CoC, Tech Specs, SER) (72-1040) (TAC No. L24664).

PRELIMINARY SAFETY EVALUATION REPORT Docket No. 72-1040 HI-STORM UMAX Canister Storage System Holtec International, Inc. Certificate of Compliance No. 1040 i Table of Contents 1 SUMMARY ........................................................................

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 09 Auxiliary Systems - Sections 09.01 - 09.05, Appendix 9A

William States Lee III Nuclear Station FSAR, Chapter 9Revision: 9 9-iCHAPTER 9AUXILIARY SYSTEMSTABLE OF CONTENTSSection Title Page9.1 FUEL STORAGE AND HANDLING..................................................... 9.1-19.1.3.7 Instrumentation Requirements..........................

FOIA/PA-2014-0348 - Resp 1 - Final. Group C (Records Being Released in Part), Part 3 of 3.

I BEST COPY AVAILABLEElements of the Screening AnalysisBackground on Fort Calhoun Station and Oconee Nuclear StationBEST COPY AVAILABLEGiven catastrophic dam failure, containment failure appeared likely- LOOP- SSF Failure- Failure of Keowee DamT - Degradation TimelineI BEST CO...

Browns Ferry Nuclear Plant, Unit 1 - Alternative Relief Request 1-ISI-27 for Relief from the Reactor Vessel Circumferential Weld Examination Requirements of the ASME Code (CAC No. MF6401).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 February 17, 2016 SUBJECT: BROWNS FERRY NUCLEAR PLANT, UNIT 1 -ALTERNA...

Salem, Unit 2 - Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel.

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 LR-N16-0044 LAR S16-02 February 11, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-7...

"Improved Design Control Documentation for Crystal River Unit 3 Design Basis for Post-Accident Monitoring Instrumentation."

-___|IMPROVED DESIGN CONTROL L'0CUMENTATIONFORCRYSTAL RIVER UNIT 3DESIGN BASISFORPOST- ACCIDENT MONITORING INSTRUMENTAT10NThe following contains design basis information pertainingto the Plant as of September 28,1990(DateofRecord).J A,,//d M m/ +/9 o ,(/||0 9 $0.,'<,,,L bOC OO...

Final rept, "Technical Evaluation Rept on IPE Submittal Human Reliability Analysis," Rev 1.

__ . _ . _ _ _ . _ . _ . . . _ . . _ . .._ ._ _ . . . _ _ _ . _. .4,sCA/TR-95-019-20DRESDEN STATION UNITS 2 & 3TECHNICAL EVALUATION REPORTON THE IPE SUBMITTALHUMAN RELIABILITY ANALYSISFINAL REPORT!-1byP. J. SwansonPrepared forU.S. Nuclear Regulatory ConunissionOffice of Nuclea...