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Minutes of ACRS Subcommittee on Advanced Reactors 791129 meeting in Albuquerque,NM re NRC sponsored research on safety of advanced reactors.W/supporting documentation.

4~m 1 & >i: *,;hYsge/S , 4,9.5d ~. Fs-l''"{'gi' h' i- I THE ACRS SUBCOMMITTEE ON ADVANCED REACTORSDATE ISSUED: ..hg p My,1ALBUQUERQUE, N. M.M 4y ', .'b,.--4November 29-30, 1979W ,' g gLThe ACRS Subcommittee on Advanced Reactors held a meeting on November 29-30,1979 at Sandia L...

Forwards proposed changes to NRC second draft of Tech Specs. Brief description of proposed change,justification for change & marked-up pages from second draft also encl.

_ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _|GULF STATES UTILITIES COMPANYRIVER BEND STATION POST OFFICI som 220 ST FRANCISVILLE. LOUISIANA 70775AREA ...

Applicant exhibit A-52,consisting of response to EQ action items 18 & 67 concerning terminal blocks & loop accuracy.

-- _APCo Exhibit 52& ysja W g yg'Y#Y"'006 38'T2 RESemSE IoE.O. ACTIQ 4 ITEMS 018 AND 067, TERMit4AL DLOCKS/* *!**LOOP ACCUPACY AND IEC 78-08/IDI 84-47\72 MR 13 P4 20 -Westinghouse as documented in WCAP-11658 performed an evaluation of the ,impact of cable and terminal block le...

Comment (186) of Herschel Specter on PR- 50, 52- Emergency Preparedness for Small Modular Reactors and Other New Technologies

From: MH SpecterTo: RulemakingComments ResourceSubject: [External_Sender] Evacuation Time EstimatesDate: Thursday, September 03, 2020 1:33:32 AMAttachments: Comments on Emergency Preparedness for SMRs and ONTs.pdfRe: Public Protective Actions During a General EmergencyAttached...

"Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations."

r...,Attachment 1, ,10 CFR 50.46 Annual and 30-Day Report of theEmergency Core Cooling System Evaluation Model Changes and ErrorsAssessments as of March 22,1999);!'i9904290235 990421 7PDR ADOCK 05000454RPDR),r:-.* PLANT NAME: Braidwood Station Unit 1. ECCS EVALUATION MODEL:Sma...

Beaver Valley 1, 2000-2017 Q1-Q4 ROP Inspection Findings

Beaver Valley 1 Initiating Events Significance: Dec 29, 2001 Identified By: NRC Item Type: FIN Finding INADEQUATE WORK PLANNING AND HUMAN PERFORMANCE ERRORS CAUSE UNIT 1 LOSS OF INSTRUMENT AIR AND MANUAL REACTOR TRIP The inspectors determined that inadequate work planning and ...

Proposed tech spec 4.3.I to require inservice insp program for piping to be performed as identified in Generic Ltr 88-01 or per alternate measures approved by NRC.

_.. - - . . ~ . ~ . ~ . .. _ - . - - - - . - _ . - _ = . _ , . _ _ . ~ -.:37, ' . *G.Primary Coolant System Pressure Isolation Valves,Specificati2D8.-1.-Periodic leakage testing (a) on each valve listed inTable 4.3.1 shall be accomplished prior to exceeding -600 peig reactor p...

"Millstone Nuclear Power Station Emergency Response Exercise." W/two oversize tables.

-PMillstone NuclearPower Station.Emergency Response Exerciset.October 8,1987-_ =w_ _.-- _ = _, = m@ $ h hK ? * f [y p gk [N y gs g w [. 4 ,] y % ,If h' "'53y yg7 y4ypp y ag ;;- ---,m- .y -. m +..a., - . -... .i...,...: e- . .- . - e.v, . .s ..-4;.|.;;;g: .m.g;'-....y. .+TM. 1,...

NRC Operator Licensing Exam Rept 50-334/97-10OL (including completed & graded tests) for tests administered on 971215- 18.

- ..- .- . - . . . . . . . .. - . . . . - . _ ., , !!,:.j.U. S. NUCLEAR REGULATORY COMMISSIONREGION 1 !i!Docket No.: 50 334|' 'i'iReport No.1 97 10ILicense No.t - DPR 66|!l. Licensee: Duquesne Light Company: Facility:- Beaver Valley Unit 1 Nuclear Power Plant ari!Location:- Sh...

Proposed Tech Specs,adding requirements to Limiting Conditions for Operation 3.3.1.1 & 3.3.1 re operability of new shunt trip attachment to reactor trip breakers.

efENCLOSURE 1PROPOSED TECHNICAL SPECIFICATION CHANGESSEQUOYAH NUCLEAR PLANT UNITS 1 AND 2(TVA SQN TS 67)Proposed changes to add requirements to LCO 3.3.1.1 (unit 1) and LCO 3.3.1(unit 2) technical specifications for operability of the new shunt tripattachment. This changes als...

Forwards Westinghouse responses to NRC requests for addl info on AP600 from ltrs 940407,15,29,0505,11,16,23 & 0608. Listing of NRC requests for addl info responded to in ltr contained in Attachment A.

-.Westinghouse Energy Systemsb 32"" * * "'" * ^*" "#3U "Electric CorporationNTD-NRC-94-4249DCP/NRC0173Docket No.: sTN-52-003July 29,1994Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555A'ITENTION: R.W.BORCHARDTSUBJECT: WESTINGHOUSE RESPONSES TO NRC ...

Submits justification to extend completion of initial testing portion of GL 89-10 re motor operated valve program at plant.

%<#"~--NEBRASKA PUBUC POWER DISTRICT. P. O. BOX 499WW Nebraska Public Power DistrictcOu%u's"S"AL, _ . - . . . _ - . - - _ - . - - - . - - . _ . . . _ . . - . . - - . . --_._ -- = = _ - , - . . _GUY R. HORNVice-President, Nuclear(402) 563-5518NLS950006January 8,1995U. S. Nuclea...

Forwards complete "Conformance to Reg Guide 1.97,Trojan Nuclear Plant," technical evaluation rept.Technical evaluation rept forwarded w/860929 ltr incomplete.

..October 17, 1986..Docket No. 50-344. DISTRIBUTION(Docket F.11e, T. ChanNRC PDR'C. Vogan~*Mr. Bart D. WithersLocal PDR ACRS(10)Vice President NuclearPD#3 Rdg. PAEIPortland General Electric CompanyT. NovakOGC121 S.W. Salmon StreetE. Jordan B. GrimesPortland, Oregon 97204J. Par...

Report on the Safety Aspects of the NuScale Small Modular Reactor

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 July 29, 2020 The Honorable Kristine L. Svinicki Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: REPORT ON THE SAFETY ASPECTS...

Insp Rept 50-285/91-03 on 910116-0226.No violations or deviations noted.Major areas inspected:onsite followup of events,operational safety verification,maint observations, safety-related sys walkdown & LER followup.

--. .. - - . . - . . . . - - - - - -, iAPPENDIXU.S. NUCLEAR REGULATORY COMMISSIONREGION IVNRC Inspection Report:50-285/91-03Operating License: DPR-40Docket: 50-285Licensee: OmahaPublicPowerDistrict(OPPD)444 South 16th Street Mall-Omaha, Nebraska - 68102-.2247Facility Name:Fort...

Rev 3 to "Emergency Operating Procedures," training course syllabus.

. . . . .v. i:'n:ATTACHMENT 4The Emergency Operating Procedure training course syllabus contained in'thisattachment is a part of our Control ~0perator training program. Our operations. training program received Institute of Nuclear Power Operations (INPO) accredi-tation in Aug...

Brunswick Steam Electric Plant, Units 1 & 2, Revision 26 to Updated Final Safety Analysis Report, Chapter 15A, Operational Safety Analysis, Figures.

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision: 26 Appendix: 15A Page: 1 of 2 LIST OF FIGURES FIGURE NUMBER TITLE FIGURE 15A-1 POSSIBLE INCONSISTENCIES IN THE SELECTION OF OPERATIONAL REQUIREMENTS FIGURE 15A-2 BLOCK DIAGRAM OF METHOD USED TO DERI...

Catawba Nuclear Station, Units 1 & 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection.

Catawba Nuclear Station UFSAR Chapter 12 (14 APR 2018) 12 - i Table of Contents 12.0 Radiation Protection 12.1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 12.1.1 Policy Considerations 12.1.2 Design Considerations 12.1.3 ALA...

Sequoyah Nuclear Plant 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report.

TennesseeValleyAuthority,SequoyahNuclearPlant, P.O. Box2000,SoddyDaisy,Tennessee37384June5, 2019U.S. NuclearRegulatoryCommissionATTN: DocumentControlDeskWashington, D.C. 20555-0001SequoyahNuclearPlant, Units1and2RenewedFacilityOperatingLicenseNos. DPR-77andDPR-79NRCDocketNos.5...

Forwards addl info re implementation of short-term Lessons Learned Task Force recommendations.

'N2P-NORTHERN STATES POWER COMPANYM I N N E A PO L.8 8, M 8 N N E SOTA 55409April 11, 1980Director of Nuclear Reactor RegulationU S Nuclear Regulatory CommissionWash ingt on , DC 20555PRAIRIE ISLAND NUCLEAR GENERATING PLANTDocke t No. 50-282 License Nos. DPR-4250-306 DPR-60Sup...

Duane Arnold Energy Center - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC No. MF1000).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Richard L. Anderson Site Vice President NextEra Energy Duane Arnold, LLC 3277 DAEC Road Palo, lA 52324-9785 February 21, 2014 SUBJECT: DUANE ARNOLD ENERGY CENTER -INTERIM STAFF EVALUATION RELATING TO O...

Encl 2: Applicability of TRACE/PARCS to MELLA+BWR ATWS Analyses - Revision 1.

ENCLOSURE 2 USNRC Office of Nuclear Regulatory Research Applicability of TRACE/PARCS to MELLLA+ BWR ATWS Analyses – Revision 1 Applicability of TRAC-RELAP Advanced Computational Engine (TRACE) and Purdue Advanced Reactor Core Simulator (PARCS) codes to Maximum ...

Shearon Harris Nuclear Power Plant, Unit 1 - Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment.

SERIAL: HNP-1 1-079Progress Energy 10 CFR 50.90AUG 3 1 2011U.S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, DC 20555SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63RESPONSE TO REQUEST FOR ADDITIONAL INFORMA...

FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 34 - Partial - Group KK/LL, Part 1 of 6.

_5riLJJSE-OLYEarthquake/Tsunami Status Update March 11,2011 1330 ESTUSNRC Emergency Operations Center Status UpdateMarch 11, 2011Earthquake / Tsunami Status UpdateCompiled by Executive Briefing TeamStatus of NRC and Agreement State Facilities (Region IV Update current as of 12...

AREVA Design Control Document Rev. 6 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.2.3 Safety Injection System and Residual Heat Removal System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 6 Page 2.2-642.2.3 Safety Injection System and Residual Heat Removal System Design Description1.0 System DescriptionThe safety injection system and residual heat removal system (SIS/RHRS) is a safety-related system. The ...