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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Peach Bottom Station, License Amendments 65 & 64, Revising TS Relating To Core Monitoring, Core Flooding & Cooling System Operability Requirements & Are In Response To Your Application Dated 1/14/80.

MARCH2 6 maDocket Nos. 5O L Mr. Edward G. Bauer, Jr. Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Dear Mr. Bauer:LA// ".. .. 'C i stributi on ,-Docket ORB #3 NRR Reading Local PDR NRC PDR HDenton DEisenh...

Turkey Point Units 3 and 4 Proposed License Amendments Risk-Informed Residual Heat Removal Pump Allowed Outage Time Extension

0 FPL OCT 3 0 2000 L-2000-124 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed License Amendments Risk-Informed Residual Heat Removal Pump Allowed Outage T...

Quad Cities Nuclear Power Station Unit 1 and 2 - Issurance of amendments (TAC MA7865 and TAC MA7886) for facility operating licenses

October 13, 2000Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West IlI 1400 Opus Place, Suite 500 Downers Grove, IL 60515 SUBJECT: QUAD CITIES - ISSUANCE OF AMENDMENTS (TAC NOS. MA7865 AND MA7866) Dear Mr. Kingsley: The...

Duane Arnold Energy Center, Changes to Emergency Action Level Basis Document, Index, Rev. 5 and EBD-H Rev. 2

jALLIANT ENERGY DUANE ARNOLD ENERGY CENTER TRANSMITTAL/ACKNOWLEDGMENT MEMORANDUMManual #92 NRC-NRRlDocument Control Desk Washington, DCEmergency Action Level Please make the following changes to your Emergency Action Level Basis Document.MANUAL CONTENTS Remove Insert Index, R...

Draft - Section C Operating.

Appendix D Scenario Outline Form ES-D-1Facility: IP2 Scenario No.: 1 Op Test No.: 1Examiners: Candidates: CRSROPOInitial Conditions: 100% power MOL21 Charging Pump OOS21 CCW Pump OOSSmall SG Tube Leak < 5 GPDTurnover: Reduce load to 900 MWe to remove 23 Condensate Pump from se...

Final - RO & SRO Written.

U. S. Nuclear Regulatory CommissionSite-SpecificWritten ExaminationApplicant InformationName: Region: IDate: Facility/Unit: Indian Point Unit 3License Level: SRO Reactor Type: Westinghouse PWRStart Time: Finish Time:InstructionsUse the answer sheets provided to document your a...

Fort Calhoun, Unit 1 - License Renewal Application Review Staff requests for additional information (RAIs).

FORT CALHOUN STATION, UNIT 1LICENSE RENEWAL APPLICATION REVIEWSTAFF REQUESTS FOR ADDITIONAL INFORMATION (RAIs)2.1 Scoping and Screening Methodology2.1-1 10 CFR 54.4(a)(2) Scoping Criteria for Non-Safety-related SSCs By letters dated December 3, 2001, and March 15, 2002, respec...

Duane Arnold RO Initial License Examination November 2002.

QF-1030-03 Rev. 0 (FP-T-SAT-30)Retention: Life of plant insurance policy + 10 yr. Disposition: Instructor, Training Supervisor, and TACRetain in: Training RecordsDuane Arnold RO Exam.doc Rev. 0DUANE ARNOLD RO INITIAL LICENSE EXAMINATIONNOVEMBER 2002Docket No. 50-331License N...

Sequoyah, Units 1 & 2 & Watts Bar, Unit1 60-Day Response RAI to NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity."

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 January 24, 2003 10 CFR 50.54(f) U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20005-0001 Gentlemen: In the Matter of ) Docket No. 50-327 Tennessee Valley Author...

Point Beach October 2000 - NRC Comments on Written Examination.

POINT BEACIIOCTOBI!R 2000NRC COM*IFNTSWRITTTEN[XA1 I NATIONONPoint Beach October 2000 ExamES-401 Written Examination Form ES-401-9Review Worksheet1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 56. * 67.(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0 -...

River Bend, Unit 1, Supplement to License Amendment Request, (LAR) 2001-43, "High Energy Line Break Analysis Method."

~EntergyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61P. 0. Box 220St. Francisville, LA 70775Tel 225 336 6225Fax 225 635 5068Rick J. KingDirectorNuclear Safety AssuranceRBG-46124July 9, 2003U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington...

Insp Repts 50-361/88-18 & 50-362/88-19 on 880627-0701. Violation noted.Major areas inspected:representative subsystems of post-accident monitoring sys at facility, plant conformance w/Rev 2 to Reg Guide 1.97.

.',.U. S. NUCLEAR REGULATORY COMMISSIONREGION VReports Nos:50-361/88-18,50-362/88-19Docket Nos.50-361, 50-362License Nos.NPF-10, NPF-15Licensee:Southern California Edison CompanyP. O. Box 8002244 Walnut Grove Avenue.Rosemead, California, 91770Facility Name: San Onofre Units 2 ...

Provides corrections to Attachment 4 of 810204 ltr re AFW design info.Background discussion of errors found along w/description of each of specific correction provided.

Northein States Power CompanyPrairie Island Nuclear Generating Plant1717 Wakonade Dr. EastWelch, Minresota 55089August 29,1997U S Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555PRAIRIE ISLAND NUCLEAR GENERATING PLANTDocket Nos. 50-282 License Nos. ...

Responds to 921216 ltr,providing AECL Technologies w/NRC staff papers re preapplication review of CANDU 3 design.

-..'f4 AECL._ _ . _ . _ _ - _- - _._._ _ _ __ -A.D. HinkNEP#W#vice Pres.deri swr. rW Manage Sude410Rockvtlie. Maryland20850 USAAECLT 93016|M^oo?Fax (301)417-0746* 3#2Project 679January 25,1993:Mr. Dennis M. CrutchfieldAssociate Director for AdvancedReactors and License Renewal...

Proposed Tech Spec changes re ASME Section XI & emergency svc water pump surveillance testing.

- . _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.ATTACHMENT I to JPN 910G4PROPOSED TECHNICAL SPECIFICATIOtt CH ANGESASME SECTION XI AND ESW PUMP SURVEILLANCE TESTitlG(JPTS 90023),|1_New York Power AuthorityJAMES A. FITZPATRICK NUCL...

Proposed tech specs,clarifying TS to allow switching of charging & low-head SI pumps during unit shutdown conditions.

iINDEX,, . . .LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSSECTIONPAGEI3/4.4.2 SAFETY VALVES - SIIUTDOWN... 3/44-61. . . .. . .. . . . . . . . . . . . . .3/4.4.3SAFETY AND RELIEF VALVES - OPERATING;Safety Valves.... ... . . .. .. ... 3/4 4-7 . . . . . . . . ....

Proposed revised radiological effluent Tech Specs.

\t $Attachment 1GPROPOSED RADIOLOGICAL EFFLUENTTECHNICAL SPECIFICATIONSForCooper Nuclear Station(Note: This cover sheet is not partof the proposed Technical Specifications)Revised August 20, 1983||.|8309160045 8309121PDR ADOCK 05000298PDRp9RADIOLOGICAL TECHNICAL SPECIFICATIONS...

"Calvert Cliffs Nuclear Power Plant Simulator Four-Yr Certification Rept."

- . . _ . _'.,,ENCLOSURE (1)+.CALVERT CLIFFS NUCLEAR POWER PLANT SIMULATORFOUR-YEAR CERTIFICATION REPORTL INTRODUCTION .He Calven Cliffs Nuclear Power Plant Simulator four-year Certification Repon is a supplementto the Simulation Certification form (NRC Fc. m-474), the Simulat...

Proposed tech specs,adding new LCO 3.0.6 that allows equipment removed from svc or declared inoperable to be returned to svc under administrative control to perform testing required to demonstrate operability.

Ue4s ,,w,.' g isN,*-;. ;;,.-,st,_'s.-. , , _, ,s_,ENCLOSURE 1!PROPOSED' TECHNICAL SPECIFICATION'(TS) CHANGE ~ i1:.SEQUOYAH NUCLEAR PLANT (SON) UNITS.1 AND 2.lDOCKET NOS. 50-327 AND 50-328.(TVA-SON-TS-95-02)-:.~ !- I:LIST OF AFFECTED PAGES ' i-Unit 1j13/4 0-13/4 3-22 iB 3/4 0-3...

"Risk-Based Evaluation of Tech Specs for Seabrook Station."

- .. _ _ _ _ - _ _ _ _ _ _ _ _ _ _ ___,-.PLG-0431RISK-BASED EVALUATION OFTECHNICAL SPECIFICATIONS FOR SEABROOK STATION (:-Prepared forNEW HAMPSHIRE YANKEE DIVISIONPUBLIC SERVICE OF NEW HAMPSHIRESeabrook, New HampshireAugust 1985w=t8hnBi8BihaAPickard,LOwe andGarrick,Inc.Applied...

Forwards schedule for providing info re NUREG-0737,Item II.B.3, "Post-Accident Sampling Capability," in response to NRC 820726 ltr.W/three oversize drawings.Aperture cards are available in PDR.

yn~c SVREGULATORY'-I RMATION DI'STRIBUTION 'SYS(RIDS)I'AOCESSION NBR:83010u07u3 DOc ~ DATE: 82/1'2/30 NQTARIZED: NO DOCKETFACIL:50-220 Nine Mile Point Nuclear "Station~ Unit ip Niagara Powe 05000220'AUTHINANEAUTHOR AFFILIATIONMANGAN W,4E'vW'I" Ih ~4II >»I>w"14'"w>,I>- h ~,I 'l...

Attachment 8: Salem Generating Station Event Classification Guide Emergency Action Level, Technical Bases, EP-SA-325-200 (Clean version).

LR-N17-0002 Attachment 8 SGS EAL Technical Bases (clean version) (331 Pages) SGS ECG – EAL Technical Bases EP-SA-325-200 SALEM EVENT CLASSIFICATION GUIDE (ECG) EMERGENCY ACTION LEVEL (EAL) TECHNICAL BASES TABLE OF CONTENTS Salem Page 1 of 4 Rev. 0 Salem Genera...

Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - May 26, 2015.

[7590-01-P] NUCLEAR REGULATORY COMMISSION [NRC-2015-0128] Biweekly Notice Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations AGENCY: Nuclear Regulatory Commission. ACTION: Biweekly notice. SUMMA...

Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 255-8285 for the Questions 03.08.05-9 and 03.08.05-13.

03.08.05-9_Rev.1 - 1 / 3 KEPCO/KHNP REVISED RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION APR1400 Design Certification Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., LTD Docket No. 52-046 RAI No.: 255-8285 SRP Section: 03.08.05 – Foundations Applicati...

Limerick Generating Station, Units 1 & 2, Revision 18 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems.

LGS UFSARCHAPTER 05 5-i REV. 16, SEPTEMBER 2012CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMSTABLE OF CONTENTS5.1 SUMMARY DESCRIPTION5.1.1 Schematic Flow Diagram5.1.2 Piping and Instrumentation Diagrams5.1.3 Arrangement Drawings5.2...