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North Anna Nuclear Plant, Unit 2, Request For Additional Information Regarding Proposed License Amendment Request For A One-Time Five-Year Extension of the Type A Test Interval (TAC MD7478).

March 24, 2008 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SUBJECT: NORTH ANNA POWER STATION, UNIT NO. 2, REQUEST FOR ADDITIONAL INFORMATION (RA...

Oconee, Units 1, 2 and 3 - Application For Technical Specification Improvement To Eliminate Requirements For Post- Accident Sampling Systems (PASS) for Babcock and Wilcox Reactors Using the Consolidated Line Item Improvement Process, TS Change 2003-10.

k DukeW Power.A Duke Energy CompanyRON A. JONESVice PresidentOconee Nuclear SiteDuke PowerON01 VP/ 7800 Rochester HighwaySeneca, SC 29672864 885 3158864 885 3564 faxMarch 14, 2005U. S. Nuclear Regulatory CommissionWashington, DC 20555-0001ATTENTION:SUBJECT:Document Control Des...

AP1000 Response to Request for Additional Information (SRP 12).

B )WestinghouseU.S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, D.C. 20555Westinghouse Electric CompanyNuclear Power PlantsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USA412-374-6206412-374-5005siskl rb@westinghouse.comDirect tel:Direct fax:e-ma...

LER 99-013-02 James A Fitzpatrick Nuclear Power Plant, Steam Leakage Detection System Outside Design Bases.

- EntergyEntergy Nuclear NortheastEntergy Nuclear Operations, Inc.James A. FitzPatrick NPPP.O. Box 110Lycoming, NY 13093Tel 315 349 6024 Fax 315 349 6480T. A. SullivanVice President, Operations-JAFAugust 17, 2001JAFP-01 -0182United States Nuclear Regulatory CommissionAttn: Doc...

Fermi-2, License Amendment 18, Revises TS 4.6.1.2.b to Provide a One-Time Extension of 24-Month Surveillance Interval for Type C Local Leak Rate Tests of Three Residual Heat Removal Shutdown Cooling Isolation Valves.

April 15, 1988"Docket No. 50-341 Mr. B. Ralph Sylvia Group Vice President - Nuclear Operations Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166 Dear Mr. Sylvia:DISTRIBUTION Docket File NRC & Local PDRs PD31 Plant Gray GHolahan TQuay Rlngram OGC DHaganJPa...

LER 09-003-00, for Braidwood, Unit 2, Regarding Drain Procedure for ECCS Suction Line Creates an Unanalyzed Condition Due to Inadequate Configuration Requirements.

ExelN10 CFR 50.73January 11, 2010BW100002U. S. Nuclear Regulatory CommissionATIN: Document Control DeskWashington, DC 20555-0001Braidwood Station, Unit 2Facility Operating License No. NPF-77NRC Docket No. STN 50-457SUbject: Licensee Event Report 2009-003-00 - Drain Procedure f...

Briefing Package for Meeting with the Nuclear Energy Institute (NEI) to Discuss Requests for Additional Information (RAIS) Associated with Review of NEI 94-01, Revision 1 (Draft) and EPRI Report, Product No. (TAC No. MC4235).

LIST OF ATTENDEESMEETING REGARDING REQUESTS FOR ADDITIONAL INFORMATION (RAls) ASSOCIATEDWITHREVIEW OF NEI 94-01. REVISION 1 (DRAFT) AND EPRI REPORT. PRODUCT NO. 1009325FRIDAY. JUNE 17. 2005NAME ORGANIZATION PHONE / E-MAILJohn GisclonTony HarrisBiff BradleyKen CanavanGreg Krueg...

Responds to NRC 860924 ltr re violations noted in Insp Rept 50-247/86-19.Corrective actions:personnel training conducted in areas of safety issues program,backfitting controls & plant failure analysis.

S 2*Murray Selman Vice President Consolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8 116 October 24, 1986 Re: Indian Point Unit No. 2 Docket No. 50-247 Mr. Stewart D. Ebneter, Director Division...

Updated/Expanded Matrix of enclosed WordPerfect document containing programs/activities amd commodity groups with a system column added.

[ Burton - Updated/Expanded Matrix Page 1 From: "Baker, Ray D." To: "William F. Burton (E-mail)" Date: Tue, Apr 4, 2000 2:49 PM Subject: Updated/Expanded Matrix Butch, As you requested last week, please find attached a WordPerfect document containing the previously provided ...

Forwards partially marked-up plant-specific list re implementation of approved regulatory improvements w/estimates of completion dates for items.Complete list will be provided in Sept 1986.

REQULATO INFORN*TION DISTRIBUTION TEN {R IDS)ACCESSION NBR: 8606030043 DOC. DATE: 86/05/30 NOTARIZED: NODOCKET 0FACIL: 50-220 Nine Nile Point Nuclear Station> Unit i. Niagara Pave 05000220AUTH. NAME AUTHOR AFFILIATIONNANQAN> C. V. Niagav a Nohaek Poeer Corp.RECIP. NANE~RECIPIE...

Sequoyah Nuclear Plant - NRC Evaluation Of Changes, Tests, And Experiments Report Number 05000327/2018010 And 05000328/2018010.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 June 19, 2018 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP ...

Proposed Tech Specs 3/4.3.3.3 re seismic monitoring requirements.

1| ..|-ATTACIIMENT (1)UNIT 1|MARKED-UP TECIINICAL SPECIFICATIONPAGESIV3/4 3-303/4 3-313/4 3-32B 3/4 3-26-26||9400090330 940804PDRADOCK 05000317PDR. ___ _ . _ . , _ - , . _._. _!|'.TABLE OF CONTENTSLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSSECTIONPAGE3/4.3 ...

Responds to NRC bulletin 93-002,suppl 1, "Debris Plugging of Emergency Core Cooling Suction Strainers."

-!,k#!?! aamwwwnnnCarolino Power & Ught CompanyRoy A. AndersonPO Box 10429Vice PresidentSouthport NC 28461Brunswick Nuclear Plant919 457 2496April 19,1994SERIAL: BSEP 94-0143U. S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, DC 20555BRUNSWICK STEAM ...

Forwards advance matl re NUREG-0737,Item II.K.3.18, "Automatic Pressurization Sys Logic Mod & ATWS." Matl will be incorporated in Amend 61 to FSAR.

,C[N Commonwealth ECson,*./ one rirst National Plan. Chicigo. lilino S,7 Address R: ply to' Post bfide Bo7767--(Oichicago. tihnois 60690*March 9, 1982 (1,s//12Ecap,TD3 ,%k'AR.io:Mr. A. Schwencer, Chie fa # AVJLicensing Branch #26Division of LicensinggU. S. Nuclear Regulatory C...

Discusses re-evaluation of ECCS cooling performance to conform w/acceptable evaluation model under provisions of 10CFR50.46,break spectrum & partial loop operation boron precipitation,single failure & submerged valves.

.S'. .NRC DdTRIBUTION FOR PART 50 DOCKE1 MATERIAL!(TEMPORARY FO3M).,FILE:,t]EDATE OF DOC DATE REC'D LTR TWX RPT OTHER*FROMP nnaR.C. Arnold7-9-757-12-75XXX^A'"TO:ORIG CC OTHER SENT URC PDR8"SENT LOCAL PDRCLASS UNCLASS PROP |NFO INPUT NO CYS REC'D DOCKET NO:XXXX150-289DESCRIPTIO...

LER 86-034-00:on 860826,design deficiency noted re postulated bus failure resulting in inoperable electronic switching sys.Design error corrected prior to start-up by modifying recirculation actuation sys.W/860918 ltr.

1.meC Fwe age u 3. seuCLEAM E.E tuLAtOe? Comessose9 433 Apr#0VED Dast eso 3tgo etoa" * " " ' ' ' ' "LICENSEE EVENT REPORT (LER)*~,Ac u n =Asse m cocas 7 mummen us'asu mPalisades Nuclear Plant0 |5 | 010 | 0 | 2| 515 1 |oF| 0 |5ftTLt seePostulated DC Eus Failure Results in Inope...

LER 97-007-00:on 971118,pneumatic leak resulted in closure of PCIV.Caused by N leak from pneumatic manifold on MSIV 1B21-F022B.Repaired leak & confirmed that no similar leaks exist on any other MSIVs.

_ _',C QRM $4.W b. WVGLLAR hEQWLAIQRY 6,QaptA4bbf006 APPMQVLD $ .4 D&e194iT *A'"e"itac",,*RY :'t 'e:W ia' d#LICENSEE EVENT REPORT (LER)g**,, "5%"57, coy",g5,,, foJ'" 4 "1T i J" ! J" R 2 "A=*,".2,.M x021 t cucE cv uAuActuLm Ano*xet miomRcouctoN e e,4370N DC 30fc3leuDG67, vv ASH...

Final Significance Determination of White Finding and Notice of Violation Inspection Report 05000424-2020090.

March 31, 2020 EA -19-112 Ms. Cheryl Gayheart Regulatory Affairs Director Southern Nuclear Operating Company, Inc. 3535 Colonnade Parkway Birmingham, AL 35243 SUBJECT: VOGTLE ELECTRIC GENERATING PLANT - FINAL SIGNIFICANCE DETERMINATION OF A WHITE FINDING AND NOTICE OF ...

Forwards request for addl info to clarify or commit to dose assessment methodology described in radiological emergency plan,Sections 9 & 10.Emergency action levels conform to NUREG-0654.Response requested within 60 days.

eR .?. Docket No. 50-354Mr. R. L..Mitti, General Manager.' Nuclear Assurance and RegulationPublic Service Electric & Gas Company-P. 0. Box 570, T22ANewark, New Jersey 07101-Dear Mr. ' Mittl:-SUBJECT: REQUEST FOR ADDITIONAL INFORMATION - EMERGENCY ACTION LEVELSAND DOSE ASSESSME...

Proposed Tech Spec Tables 3.3-6 & 4.3-3 to allow control room ventilation sys to remain in operation provided that two radiation monitors operable on ventilation train that is operating.

g,_ ._- .- - .- __. - - _ - _ - - _ _ _ -_ - __--______ - - _ _ _ _^ ^^'~,.j? t_<- Q ). .g ,;4 ,,,.!-. , ..;;,,ATTACHMENT A..-,.PROPOSED CHANGES-TO APPENDIX A,TECHNICAL SPECIFICATIONS OF FACILITY ~-OPERATING LICENSES NPF-37, NPF-66 and NPF-72...Hyron Station'Braidwood Station....

LER 88-001-00:on 880118,contrary to Tech Spec Surveillance Requirement 4.11.2.1.2,Table 4.11-2,required purge samples not collected within specified time.Caused by technician error.All chemistry technicians reinstructed.W/880217 ltr.

0 0 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:8802230026 DOC.DATE: 88/02/17 NOTARIZED: NO DOCKET # FACIL:50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUTH NAME AUTHOR AFFILIATION MORGANH.E. Southern California Edison Co. RECIP.NA...

Byron Station, Unit 2 - 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R18).

Byron Generating StationExeton Generation®January21, 2015LTR: BYRON 201 5-0009FILE: 1.10.0101 (1D.101)United States Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Byron Station, Unit 2Facility Operating License No. NPF-66NRC Docket No. STN5O-4...

Regulatory Analysis - Incorporation by Reference of American Society of Mechanical Engineers Codes and Code Cases (TAC No. MF3530)

Regulatory Analysis for Proposed Rule: Incorporation by Reference of American Society of Mechanical Engineers Codes and Code Cases NRC-2011-0088; RIN 3150-AI97 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation i Table...

SECY-14-0114: Enclosure 5 - Overview of Fukushima-Related Recommendations and Related Activities

Enclosure 5 Overview of Fukushima-Related Recommendations and Related Activities The Near Term Task Force (NTTF) Report, “Recommendations for Enhancing Reactor Safety in the 21st Century” (Agencywide Document Access and Management System Accession No. ML112510271), provide...

SECY-15-0059: Enclosure 5 - Overview of Fukushima-Related Recommendations and Related Activities

Enclosure 5 Overview of Fukushima-Related Recommendations and Related Activities The Near-Term Task Force (NTTF) Report, “Recommendations for Enhancing Reactor Safety in the 21st Century” (Agencywide Document Access and Management System Accession No. ML112510271), offered...