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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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HB Robinson Unit 2, Issuance of Bases to ITS and Corrections to License Amendment 176 Regarding Conversion to ITS.

"UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2555-0001 November 7, 1997 Mr. J. S. Keenan, Vice President _ 4A Carolina Power & Light Company H. B. Robinson Steam Electric Plant Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550 SUBJECT: ISSUA...

IR 05000219/2001006, on 05/13 - 06/30/2001, AmerGen, Oyster Creek Generating Station. Emergent Work.

July 27, 2001EA-01-197Mr. Ron J. DeGregorioVice President Oyster CreekAmerGen Energy Company, LLCP.O. Box 388Forked River, New Jersey 08731SUBJECT: OYSTER CREEK GENERATING STATION - NRC INTEGRATED INSPECTIONREPORT 50-219/01-06Dear Mr. DeGregorio:On June 30, 2001, the NRC comp...

NUREG-1433 Vol. 2, Rev. 2, [1:3] Bases, "Standard Technical Specifications General Electric Plants, BWR/4."

NUREG-1433 Vol. 2, Rev. 2Standard Technical Specifications General Electric Plants, BWR/4 Bases U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555-0001NUREG-1433 Vol. 2, Rev. 2Standard Technical Specifications General Electric Plants, ...

Revision 7 to Seabrook Station Updated Final Safety Analysis Report, Table 5.2-1 - page 7.5-10.

SEABROOK UPDATED FSAR TABLE 5.2-1 APPLICABLE CODE ADDENDA FOR REACTOR COOLANT SYSTEM COMPONENTSReactor Vessel Steam Generator Pressurizer CRDM Housing Full Length CRDM Head Adapter Reactor Coolant Pump Reactor Coolant Pipe Class 1 Interconnecting Piping to the RCS* Surge Line ...

Transmittal of Responses to AP1000 DSER Open Items.

SWWestinghouseU.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Westinghouse Electric CompanyNuclear Power PlantsP.O.Box355Pittsburgh, Pennsylvania 1 5230-0355USADirecttel:Directfax:e-mail:412-374-4728412-374-5005vijukrp@westinghouse.comYour ref Dock...

"Aging Analysis of Nordel Seat Matl for TRW Check Valves." W/one oversize drawing & related documentation.

. . - . _N NN5ENGINEERING576e3Wyle Report No. SCitNtiric stavicts a systems ceOur/ wtsf ERN OPitATIONs. NORCO FACILITY-57683k1841 hills!Of AVINUI, NOeCO. CALIFotNIA 91760Wyle Job No.AttA CODE 714 7374871C sfr P.O. Ny4926-EQOlEQTWX 914332-1204 TELECOPY (714) 7374871Total Pages ...

COMANCHE PEAK - TRANSMITTAL OF REVISED EMERGENCY PLAN PROCEDUkES

TXU Electric Comanche Peak Steam Electric Station P.O. Box 1002 Glen RoseTX 76043 Tel: 254 897 8920 Fax: 254 897 6652 Iterryl@txu.comC. Lance Terry Senior Vice President & Principal Nuclear OfficerLog # TXX-00063 File # 10013 w/o enc. Ref. # 10CFR50.54(q) 1OCFR50 App. E March...

Letter forwarding Revision 9 to the Vogtle Electric Generating Plant Updated Final Safety Analysis Report (UFSAR), per 10CFR50.4(b) and 50.71(e).

J. Barnie Beasley. Jr., P.E. Southern Nuclear Vice President Operating Company, Inc. Vogtle Project 40 Inverness Center Parkway P.O. Box 1295 Birmingham, Alabama 35201 Tel 205.992.7110 Fax 205.992.0403 SOUTHERN A COMPANY Energy to Serve Your World May 5, 2000 LCV-1365-D Dock...

Press Release-92-085, Informing that Nuclear Regulatory Commission has received two letter-type reports from its Advisory Committee.

No. 92-85 FOR IMMEDIATE RELEASETel. 301/504-2240 (Thursday, May 28, 1992)NOTE TO EDITORS:The Nuclear Regulatory Commission has received two letter-type reports from its Advisory Committee on Reactor Safeguards.They provide comments on the reliability of emergency AC power atnu...

Calvert Cliffs, Units 1 & 2 - Supplemental Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized Water Reactors".

James A. Spina Calvert Cliffs Nuclear Power Plant, Inc.Vice President 1650 Calvert Cliffs ParkwayLusby, Maryland 20657410.495.5200410.495-3500 Fax0 Costellation En~yNuclear Generation GroupFebruary 29, 2008U. S. Nuclear Regulatory CommissionWashington, DC 20555ATTENTION: Docum...

Diablo Canyon, Response to Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors".

Pacific Gas andElectric Company-Diablo Canyon Power PlantP. 0. Box 56Avila Beach, CA 93424November 3, 2008PG&E Letter DCL-08-094U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Docket No. 50-275, OL-DPR-80Docket No. 50-323, OL-DPR-82Diablo ...

Emergency preparedness exercise scenario timeline,including control room data sheets & contingency messages.

4\Go- 95 l.SCENARIO TIMELINE.O%e.000$e8501160328 841022PDR ADOCK 05000250FPDR..ress 4,-.. . . - - _ . - - - - .= _~. - . . . - - - _ - - - . . . - . _ _ _ - _ . _ - . . . - - _:y IliON-SITE CONTROLLER PHONE NUMBERS.i.'NAME LOCATION PHONE NUMBERjt1 . .-l__._~__h7)Henry Wong Con...

"LOCA Aspects of C-E Advanced LWR - Sys 80+."

___ -_ _ _ - -.....LOCA Aspects of the._,Combustion Engineering-,Advanced Light Water.Reactor -- System 80 + ..,.,e?n}W4S. RosenR. D. IvanyJ. KapinosS. SimNuclear Fuel EngineeringNuclear Power SystemsCombustion Engineering, Inc.Windsor, Connecticut.J &TIS-8328*- '''.),c..- . ,...

Response to TMI Alert first set of interrogatories & first request for production.Certificate of Svc encl.Related correspondence.

- ~....:'b~""lDEnc;5 September 4, 1984-UNITED STATES OF AMERICA. -NUCLEAR REGULATORY COMMISSION.p-Before the Atomic Safety and Licensing Board00CKETEDUSWCIn1the Matter.of!) '84 SEP -5 N154'. . )METROPOLITAN EDISON COMPANY) Docket No. 50-289 SP re- ,,.. . ) (Restart-Remand on M...

Forwards "Emergency Preparedness Exercise Scenario for Point Beach Nuclear Plant,Units 1 & 2." Scenario withheld.

_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - _ _ _ _ _ _ _ _ ...Wisconsin1 Electnc-POMR COMPANYnt w Mengan ro ban.wo Muuee w brmpulm 22V...

Forwards repts on experimental research projects on source term projects emphasizing aerosol science.List of rept authors & repts re aerosols from ejection of corium melt simulants encl.

..:y* DistributionConcurrence..Ktd Lentral rileAWU/ RESCHRON/ CIRCCPRyder:mir-ASTP0 Subject File08/SO/84CPRyder-*Dr. Simon L. Goren201 F GilmanDepartment of Chemical EngineeringUniversity of CaliforniaBerkeley, CA 95720Dear Dr. Goren:You wanted to know about experimental resea...

"Safety Review of Trojan Plant Restart:Steam Generator Deterioration & Interim Plugging Criteria."

=.qg,z.,.. . , , . .%d.,!''.-. ':7:(,,Ji;'I. -..!::... . ,',q.. ;(. .i-SAFETY REVIEW 0F TI.OJAN PLANT RESTART: . .-Steam Generr. tor Deterioration-'and Interim Plugging Criteria<.,Stephen H. Hanauer -.,',9January 18,1993'-','-+.a: Technical Analysis Corporation_6723 Whittier A...

Comment opposing issuance of proposed generic communication, "Augmented Inservice Insp Requirements for Mark I & Mark II Steel Containments,Refueling Cavities & Associated Drainage Sys."

gg g- - -g;, g f. ;%,-.5, rp g wp cmgmw +1 ..DW n OUJNEA5' GAOUP""'"* "25 kif.''s;BWROG 93027c o Southern Nuclear Operokdhh a hEOMob295. Bin 8052 * Birminohom, Al 35201--, . _ . - ,[February 19,1993iChief, Rules and Directives Review BranchU. S. Nuclear Regulatory CommissionWa...

Shearon Harris Nuclear Plant, Unit 1 - 2nd Correction to License Amendment No. 154 Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program (CAC No. MF6583).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ms. Tanya Hamilton Site Vice President Shearon Harris Nuclear Power Plant Duke Energy 5413 Shearon Harris Road New Hill, NC 27562-0165 March 28, 2017 SUBJECT: SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - 2...

DG-1285 Section 2-1 Revised Draft 7-26-16.

D R A F T D R A F T D R A F T Revised Draft of Section 2.1 from DG-1285 [7-27-16] 1 D R A F T D R A F T D R A F T 2.1 Evaluation of Defense-in-Depth Attributes and Safety Margins 1 One aspect of the engineering evaluation is to show that the proposed change does not 2 comp...

Proposed revised App A Tech Specs for License DPR-22,re loss of voltage protection.

09EXHIBIT A - 6 -8. Definition of Operability ,PROPOSED CHANGE Revise the definition of "operability" in Section 1 of the Technical Specifications to include the additional clarification contained in Enclosure (2) of a letter dated April 10, 1980 from D G Eisenhut, Acting Dire...

Prairie Island, Units 1 and 2, Submittal of 50.59 Evaluation Summary Report.

@ Xcel Energya L-PI-I 1-098 10 CFR 50.59 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 50.59 EVALUATION SUMMARY REPORT With ...

Enclosure 1 - Non-Prop - Final Safety Evaluation by The Office of New Reactors WCAP-17065 P, "Westinghouse ABWR Subcompartment Analysis Using Gothic" South Texas Project Nuclear Operating Company Units 3 and 4 Project Number 772.

Enclosure 1 FINAL SAEFTY EVAULATION BY THE OFFICE OF NEW REACTORS WCAP-17065-P, “WESTINGHOUSE ABWR SUBCOMPARTMENT ANALYSIS USING GOTHIC” SOUTH TEXAS PROJECT NUCLEAR OPERATING COMPANY UNITS 3 AND 4 PROJECT NUMBER 772 1.0 INTRODUCTION By letter dated April 29, 2010 (Agencyw...

Duane Arnold Technical Requirements Manual Revision 23.

TRM REVISION UPDATE INSTRUCTIONSManual Holder REGIONAL LIBRARYTRM Copy # 14 NRC REGION III TRM Revision # 023Responsible Licensing Engineer/Specialist Tony BrowningTRMCR-038 implements TS Amendment 282 (TSCR-129 - SRV Dry Lift Test) byremoving the references to Notes on the SR...

Farley Initial Exam 2012-301 Final SRO Written Exam.

ES-401-8 Site-Specific SRO Written Examination ILT-35 SRO NRC ExamCover SheetU.S. Nuclear Regulatory CommissionSite-Specific SRO Written ExaminationApplicant InformationName:Date: 6128/2012 Facility/Unit: FARLEY Units I & 2Region: I D II tEl Ill D IV D Reactor Type: W tEl CE D...