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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Proposed Tech Specs,correcting typos & clarifying statements re ventilation exhaust treatment sys,reactor trip sys instrumentation setpoints,movable control assemblies, operational leakage & chemical treatment ponds.

- - - . .- -- -- . - - .-..*. ,:IDEFINITIONSt{SOURCE CHECK!i1.33 A SOURCE CHECK shall be the qualitative assessment of channel responseiwhen the channel sensor is exposed to a source of increased radioactivity.,STAGGERED TEST BASIS1.34 A STAGGERED TEST BASIS shall consist of:A...

Insp rept 50-155/96-12 on 961130-970117.Violations noted. Major areas inspected:operations,engineering,maintenance & plant support.

- - . . -. .. -. _ _ _ - - .- . - . - . .. . . . _.-U.S. NUCLEAR REGULATORY COMMISSION !|-REGION lli!Docket No: 50-155License No: DPR-06i|Report No:50-155/96012(DRP)Licensee: Consumers Power CompanyFocility: Big Rock Point Nuclear Power Plant!Location: 10269 U.S. 31 North'Char...

Proposed tech specs re part of overall effort to improve outage performance at plant.

ii*|.!1.0DEFINITIO.NR'The succeeding frequently used terms are explicitly defined so that a uniform interpretation of thespecifications may be achieved.A. Safety Limit - The safety limits are limits below which the reasonable maintenance o' thecladding and primary systems are ...

Forwards draft NUREG-0785, "Safety Concerns Associated W/Pipe Breaks in BWR Scram Sys." Requests rept re applicability to facility & determination of remedial measures.

.>, , . . ,,.'73..(* -T_+ .DISTRIBUTION:*w/ enc 1.gusteem6mbe*LB#1 Rdg bec:DEisenhut TERAAfAY5 G81JYoungblood PDR*Docket No.: 50-341LKintner LPDR*MRushbrook NSICRTedesco TICMr. Harry TauberSHanauerACRS (16)Vice PresidentRVollmerEngineering & ConstructionTMurleyDetroit Edison C...

Southern Nuclear Operating Co, Inc - Exemption Request and License Amendment Request for a Risk-Informed Resolution to GSI-191

Cheryl A. GayheartRegulatory Affairs Director3535 Colonnade ParkwayBirmingham, AL 35243205 992 5316cagayhea@southernco.comNL-20-059710 CFR 50.9010 CFR 50.12ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, D. C. 20555-0001Vogtle Electric Generating Pl...

"Changes,Tests & Experiments Made W/o Prior Commission Approval for Period Jul 1985 - June 1986."

1|||TURKEY POINT PLANT UNITS 3 AND 4|DCCKET NUMBERS 50-250 AND 50-251CHANGES, TESTS, AND EXPERIMENTSMADE WITHOUT PRIOR COMMISSION APPROVALFOR PERIODJULY 1, 1985 THROUGH JUNE 30, 1986IN COMPLIANCE WITHTITLE 10, SECTION 50.59(b)CODE OF FEDERAL REGULATIONS!BQOhSOPR_ - _ _ _ _ . -...

Insp rept 50-482/98-04 on 980125-0307.Violations noted.Major areas inspected:operations,maint,engineering & plant support.

. .9ENCLOSURE 2U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDocket No.: 50-482NPF-42 -Report No.: 50-482/98-04Licensee: Wolf Creek Nuclear Operating CorporationFacility: Wolf Creek Generating Station -Location: 1550 Oxen Lane, NEBurlington, KansasDates: January 25 through March ...

ANO-Init Exam-2/2001-Draft Outline and Written Exam.

ANO Unit One PWR RO Examination OutlineBased on NUREG-1021 Form ES-401-4 Pg 33 of 45 Rev.8K/A Category PointsTier GroupK1 K2 K3 K4 K5 K6 A1 A2 A3 A4 GPoint TotalTemp TotalAverageStd. Dev.Tier 111 2 3 2 3 516 16Plant22 3 5 3 3 117 17E...

Arkansas Nuclear One, Unit 1 - August 2002 - Draft outline.

ES-301 Administrative Topics Outline Form ES-301-1June 2000 21 of 26 NUREG-1021, Revision 8Facility: ANO Unit 1 Date of Examination: 8-19-02 Examination Level (circle one): RO / SRO Operating Test Number: ...

Arkansas Nuclear One, Units 1 and 2 - Proposed Upgraded Emergency Action Levels.

Entergy Operations, Inc.Entergy 1448 S.R. 333Ene gy JRussellville, AR 72802Tel 501 858 5000OCAN020407February 27, 2004U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Subject: Proposed Upgraded Emergency Action LevelsArkansas Nuclear One - ...

Submittal of Supplement to 15-day Response for NRC Bulletin 2002-01 from Entergy Nuclear Northeast.

'EntergyEntergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 PO. Box 249 Buchanan, NY 10511-0249 Tel 914 271 7060 Fax 914 271 7181 jherron@entergy.comJohn T. Herron Senior Vice President July 11, 2002 NL-02-099 IPN-02-060U.S. Nuclear Regulatory Commission...

Final - Section C Operating.

PP&L-SUSQUEHANNATRAINING CENTERSIMULATOR SCENARIOScenario Title: NRC INITIAL LICENSE OPERATOR EXAMINATIONScenario Duration: 2 HoursScenario Number: NRC0201Revision/Date: Rev 0, 411/2002Course: PCO17, NRC Initial License Operator ExaminationOperational Activities: 6. Power redu...

NRC Generic Letter 1989-010, Supplement 3: Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves.

;A REG11t~ 4UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555October 25, 1990TO: ALL LICENSEES OF OPERATING NUCLEAR POWER PLANTS AND HOLDERS OFCONSTRUCTION PERMITS FOR NUCLEAR POWER PLANTSSUBJECT: GENERIC LETTER 89-10, SUPPLEMENT 3, "CONSIDERATION OF THE RESULT...

Notice of Opportunity for Public Comment on the Proposed Model SE of TSTF Traveler-513, Revision 2, "Revise PWR Operability Requirements And Actions For RCS Leakage Instrumentation".

[7590-01-P] Nuclear Regulatory Commission Notice of Opportunity for Public Comment on the Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specification Task Force Traveler-513, Revision 2, “Revise PWR Operability Requirements And Actions For RCS Lea...

Evaluation Of Hydrogen Generation And Maximum Normal Operating Pressure For Waste Transportation Packages (WM2011 Conference, February 27-March 3, 2011).

WM2011 Conference, February 27 – March 3, 2011, Phoenix, AZ Evaluation of Hydrogen Generation and Maximum Normal Operating Pressure for Waste Transportation Packages Jimmy F.C. Chang, Peter Lien, and Michael Waters U.S. Nuclear Regulatory Commission, Rockville, Maryland 20852...

HB Robinson Initial Exam 2011-301 Final RO Written Exam.

IES-401 Site-Specific RO Written Examination Form ES-401-7Cover SheetU.S. Nuclear Regulatory CommissionISite-Specific RO Written Examination______Applicant InformationName:Date:Facility/Unit:Region: I II Ill IV Reactor Type:WECEDBWEGEEStart Time: Finish Time:InstructionsUse th...

IMC 2515 Appendix D, "Plant Status."

Issue Date: 02/02/10 D-1 2515 APPENDIX D PLANT STATUS A. OBJECTIVES AND PHILOSOPHY OF PLANT STATUS ACTIVITIES The Reactor Oversight Process recognizes that resident inspectors have a specific responsibility, outside of inspection activities, to be aware of plant condit...

Application to amend License DPR-43,consisting of Proposed Amend 55,revising Tech Specs to resolve outstanding concerns raised by NRC.Description of changes,safety evaluation & significant hazards determination encl.

REGULATOR*NFORMATION DISTRIBUTION &rEM (RIDS) ACCESSION NBR;8308260003 DOC.DATE: 83/08/24 NOTARIZED: YES 0 FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 0 AUTH.NAME AUTHOR AFFILIATION GIESLERC.W. Wisconsin Public Service Corp. RECIP.NAME, RECIPIENT AFFILI...

Rev 1 to "Technical Evaluation Rept Pump & Valve Inservice Testing Program Kewaunee Nuclear Power Plant," final rept.

EGG-NTA-7166 Revision 1 February 1987 INFORMAL REPORT TECHNICAL EVALUATION REPORT PUMP AND VALVE INSERVICE TESTING PROGRAM KEWAUNEE NUCLEAR POWER PLANTIdaho National Engineering LaboratoryManaged by the U S. Department of EnergyD. I. Monnie C. B. Ransom H. C. RockholdEGrGIdah...

Forwards responses to NUREG-0737 re post-TMI requirements. Util will meet most implementation dates specified in NUREG-0737.Other dates cannot be committed to w/o evaluating full impact of proposed mods.

REGULATU INFORMATION DISTRIBUTION STEM (RIDS) ACCESSION NBR:8101090529 DUC.DATE: 81/01/05 NOTARIZED: YES D FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 0 AUTH.NAME AUTHOR AFFILIATION MATHEWSER, Wisconsin Public Service Corp. RECIP.NAME RECIPIENT AFFILIAT...

AREVA Design Control Document Rev. 1 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Sections 2.4 Instrumentation of Control Systems - 2.4.1 Protection System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Tier 1 Revision 1 Page 2.4-1 2.4 Instrumentation and Control Systems 2.4.1 Protection System 1.0 Description The protection system (PS) is provided to sense conditions requiring protective action and automatically initiate the safety sys...

AREVA Design Control Document Rev. 1 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.5 Other Auxiliary Systems - 9.5.1 Fire Protection System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 1 Page 9.5-19.5 Other Auxiliary Systems9.5.1 Fire Protection SystemThe purpose of the fire protection system (FPS) is to protect other plant systems and equipment which provide the capability to safely shut down the react...

Indian Point, Unit 3, Current Facility Operating License DPR-64, Technical Specifications, Revised 06/03/2020.

ENTERGY NUCLEAR INDIAN POINT 3, LLC AND ENTERGY NUCLEAR OPERATIONS, INC. DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 RENEWED FACILITY OPERATING LICENSE Renewed License No. DPR-64 1. The Nuclear Regulatory Commission (the Commission) has found t...

MHI's Response to US-APWR DCD RAI No. 634-4845, Revision 2.

ArMITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANOctorber 15, 2010Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-10278Subject: MHI's Response to US-APW...

Chapter 20 - Generic Issues.

20-1 20.0 GENERIC ISSUES TABLE OF CONTENTS 20.1 Introduction ............................................................................................................... 20-1 20.1.1 Compliance with 10 CFR 52.47(a)(21) .........................................................