Report a Safety Concern
Search

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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

NUREG-1242, Vol. 2, Pt. 2, "NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document, Evolutionary Plant Designs, Chapters 2-13."

NUREG-1242Vol. 2, Pt. 2NRC Review ofElectric Power Research Institute'sAdvanced Light Water ReactorUtility Requirements DocumentEvolutionary Plant DesignsChapters 2-13Project Number 669U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationAVAILABILITY NOTICEAva...

2008/12/16 Areva EPR DC - Feedback Re: AREVA's Approach to RLBLOCA Topical Report RAI (ANP-10278P)

1ArevaEPRDCPEm ResourceFrom: Getachew TesfayeSent: Tuesday, December 16, 2008 4:04 PMTo: 'Pederson Ronda M (AREVA NP INC)'Cc: Jason Carneal; Prosanta Chowdhury; Fred Forsaty; Shanlai Lu; Joseph Donoghue; Joseph Colaccino; John Rycyna; ArevaEPRDCPEm Resource; 'DUNCAN Leslie E (...

Watts Bar Nuclear Plant, Unit 2, Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 11 (CAC NO. MF8869).

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-020 February 16, 2017 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Facility Operating Lic...

Watts Bar, Unit 2, Final Safety Analysis Report, Amendment 106, Section 3.8, Design of Category I Structures through Figure 3.8.4-80.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-106m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornad...

September 4, 2012, Applications and Amendments to Facility Operating Licenses, etc: BI-weekly Notice.

53923 Federal Register/Vol. 77, No. 171/Tuesday, September 4, 2012/Notices temporary items). Master files of an electronic information system containing information on explosive devices used for reference purposes by the Explosive Ordnance Disposal community of the Armed Servi...

2012/09/19 Fermi COL - FW: Courtesy Copies of Fermi 3 RAI Letters

1PMFermiCOLPEm ResourceFrom: FermiCOL ResourceSent: Wednesday, September 19, 2012 3:06 PMTo: PMFermiCOLPEm ResourceSubject: FW: Courtesy Copies of Fermi 3 RAI LettersAttachments: NRC3-12-0024.pdf; NRC3-12-0025.pdf; NRC_Data_Request_1.pdf; NRC_Data_Request_2.pdf; NRC_Data_Reque...

RG-1.079, Rev. 2, "Preoperational Testing of Emergency Core Cooling Systems for Pressurized-Water Reactors".

U.S. NUCLEAR REGULATORY COMMISSION October 2013 Revision 2REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH Technical Lead F. X. Talbot Written suggestions regarding this guide or development of new guides may be submitted through the NRC’s public Web site under the Reg...

RTM 118 Issue 2 - Test Plan for the R7021 Transport Container.

Author Name Signature Date REVISS SERVICES Man facturing and Technical Group Te t Plan for the R7021 ransport Container Reviewer -DWRogers. Name M A Shepperson D:J Signature t1.S~O\'\ Date r \t /I 0/ zoo8 RTM 118 issue 2 page 1 of 24 RTM 118 issue 2 page 2 of 24 1. PURPOSE AN...

Proposed Tech Spec changes as result of mods to satisfy requirements of NUREG-0737,Items II.B.1,II.F.1.1,II.F.1.3, II.F.1.4 & II.F.2 & diesel generator testing.

- - - - _--. ...*..ENCLOSURE 1~,..PROPOSED TECHNICAL SPECIFICATIONSSEQUOYAH NUCLEAR PLANTUNITS 1 AND 2..1i'a,h||-,I|!8401310425 840125PDR ADOCK 05000327P PDR. .. . . . ____ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ __. - -. . _ . . . . . . _ - -. - . - - -';.'TABLE 3...

Public version of revised emergency plan implementing procedures,including Procedures EPIP-OSC-10 re assessment of plant parameters,EPIP-OSC-15 re control room communicator & EPIP-TSC-7 re response assistance.

. . . ~ .. _. __ii* *. ...|,VOLUME IIIOMAHA PUBLIC POWER DISTRICT - FORT CALHOUN STATIONEMERGENCY PLAN IMPLEMENTING PROCEDURESTABLE OF CONTENTS,?1. OPERATION SUPPORT CENTERRevision Last ReviewProcedure No.Title No./DateDateEPIP-OSC-1Emergency ClassificationR4 11-18-83 11-18-83...

Proposed Tech Spec Change Request 118 for clarity & format purposes only.

.. _ _ _ _ ._ . . _ _ _ ._TABLE OF CONTDITSPAGE'/Section 1 Definitions,1.1 Operable1-11.2 Operating _1-1i1.3 Power Operation1-11.4 Startup Mode1-11.5 Run Mode1-1,1.6 Shutdown Condition1-11.7 Cold Shutdown~1-21.t Place in Shutdown Condition1-21.9 Place in Cold Shutdown Conditio...

Proposed tech specs for conformance of Administrative Controls Section 6 to guidance of STS.

~. - _ . . - _ _ . . ._ ._LICENSE AMENDMENT REQUEST DATED December 14, 1995Conformance of Administrative Controls Section 6-to the Guidance of Standard Technical SoecificationsEXHIBIT BAppendix A, Technical Specification PagesMarked Up PagesTS-ilTS-vTS-viii through TS-xiiiTS.3...

Proposed Tech Specs incorporating miscellaneous administrative changes,including changes to administrative control section.

' *;(i .,,,: .PY-CE1/NRR-1214 L *Attachm2nt 3,Page 1 of 26',. ADMINISTRATIVE CONTROLSSECTIONPAGE6.1 RESPONSIBILITY...............................................6-16.2 0RGANIZ'TION.................................................6-1A6.2.1Corporate.................................

Requests one-time exemption from schedular requirements of 10CFR50,App J Sections II.D.2(a) & III.D.3 re as-left local leak rate testing of water-sealed isolation valves,closed loop seismic Class 1 isolation valves & new components.

m.a. ..Awew wy vo.n n.u naorv.mnouE d ma^December 20, 1991O J %e'7enngueva mnunswuecer,op w nU.S. Nuclear Regulatory CommissionATTN Document Control DeskWashington, D.C. 20555Centlementin the Matter of) Docket No. 50-260Tenneuce Vality Authority)BROWNS PERRY NUCLEAR PLANT (BFN...

LER 94-005-01:on 940829,automatic scram resulting from load rejection at 100 percent power occurred.Caused by blockage of cooling water through one of generator stator bars.Main generator station was completely rewound.W/960911 ltr.

. _ _ _ _ _ _ .. _8.,..GBoston Edison 10 CFR 50.73'''Pdgrrn Nuclear Power statenRocky Hill RoadPlytnouth. Massachusetts 02360E. T. Bouletta, PhDsenior Vice President-NuclearSeptember 11,1996BECo Ltr. #96t82U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington...

Safety evaluation supporting relief from ASME Code Section XI inservice testing program requirements w/listed exceptions.

. . . -, ..['o,, UNITED STATESj? g NUCLEAR REGULATORY COMMISSION{-G j. ASHINGTON, D. C. 20555 W\...../SAFETY EVALUATIONBY THE OFFICE OF NUCLEAR REACTOR REGULATIONCONCERNINGINSERVICE TESTING PROGRAM#FOR~ARKANSAS NUCLEAR ONE, UNIT 2DOCKET N0. 50-368ARKANSAS POWER & LIGHT COMPANY...

SUMMARY OF MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND NE ON GENERIC LICENSE RENEWAL ISSUES

UNITED STATES 0 NUCLEAR REGULATORY COMMISSION SWASHINGTON, D.C. 20555-0001 November 18, 1999 ORGANIZATION: Nuclear Energy Institute (NEI) SUBJECT: SUMMARY OF MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND NEI ON GENERIC LICENSE RENEWAL ISSUES The U.S. N...

Insp Repts 50-317/89-03 & 50-318/89-03 on 890110-0220. Violation noted.Major areas inspected:facility activities, routine insps,operational events,maint,surveillance,physical security,LERs & repts to NRC.

__, ,-.|.U.S. NUCLEAR REGULATORY COMMISSION.Region I50-317 DPR-53Docket Nos.: 50-318 License Nos.: DPR-6950-317/89-03Report Nos.:50-318/89-03Licensee: Baltimore Gas and Electric CompanyPost Office Box 1475Baltimore, Maryland 21203Facility:Calvert Cliffs Nuclear Power Plant, Un...

"Detailed Modeling & Analysis of Zion Plant for Phase II of Revised (NUREG-1465) Source Term Rebaselining for Operating Reactors."

._ . . - - .. - . --. . . . . . . -. - . .AEB-98-02.\Detailed Modeling and Analysis of the ZionPlant for Phase || of the Revised(NUREG-1465) Source Term Rebase'iningfor Operating ReactorsAuthors: Chester GingrichJason SchaperowAccident Evaluation BranchDivision of Systems Tech...

Forwards evaluation of large break LOCA analysis for increased steam generator tube plugging,per 10CFR50.59. Plant operation w/steam generator tube plugging levels up to 12% does not involve any unreviewed safety questions.

-VINGINIA ELucrnic Axn Powen CoxiwxyRicitwoxn,Vinoxx A eilentW.L. STEWARTVaca PassinawrNucs. sam oramarnowsMarch 16, 1987U.S. Nuclear Regulatory Commission Serial No. 87-121Attn: Document Control Desk E&C/J0E/cdkWashington, D.C. 20555 Docket No. 50-33850-339License Nos. NPF-4N...

Catawba Nuclear Station, Units 1 and 2 - Revision 43 to "Offsite Dose Calculation Manual (ODCM)."

Catawba Nuclear Station Units 1 and 2S Duke rSPower® A Duke Energy CompanySilP.r iT !,. -.P Duke rPowersm A Duke Energy Company Catawba Nuclear Station Units l and 2 OFFSITE DOSE CALCULATION MANUAL (ODCM)Revision 43Catawba Nuclear Station January, 2001 Offsite Dose Calculati...

Surry Retake Exam 50-280, 281/2001-301 4/2 & 16-17/01 - Final RO Written Exam And Reference Material.

o :.; . .%, w.s-, , r  7" . . I  FINAL SUBMITTAL. i,... . ..| . . .SURRY RETAKE EXAM50-280, 281/2001-301APRIL 2, 2001 (WRITTEN) &APRIL 16-17, 2001 (ADMIN)FINAL RO WRITTEN EXAMINATION------1.The following conditions exist:* Unit 1 is at 100%* Charging pump, I-CH-P-lA, is run...

Catawba, Units 1 & 2, Issuance of amendments 108 and 102, revising TS 3.7.5b for Standby Nuclear Service Water Pond to require an average water temperature less than or equal to 91.5 degrees at 568 feet elevation.

March 30, 1993Docket Nos. 50-413 Distribution and 50-414 See next page Mr. M. S. Tuckman Vice President, Catawba Site Duke Power Company 4800 Concord Road York, South Carolina 29745 Dear Mr. Tuckman: SUBJECT: ISSUANCE OF AMENDMENTS - CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (TAC...

Millstone, Units 1, 2, and 3 - Revised Emergency Plan Implementing Procedures.

SNortheast Rope Ferry Rd. (Route 156), Waterford, CT 06385 Nuclear Energy Millstone Nuclear Power Station Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utilities System WR 2 3 2001 Docket Nos. 50-245 50-3...

Monticello, License Amendment 8, Specifies New In-Service Inspection, Surveillance and Testing Requirements for the Torus-to-Drywell Vacuum Breakers to Increase Performance Reliability and Provides Added Assurance That Breakers Will Operate as Required.

FEB 2 e, 1975 DISTRIBUTION Docket MRC-A46 PDR Local PDR ORB #2 Reading Docket No. 56-263 4 Attorney, OGC OS!QA (3) NDube BJones (4) Northern States Power Company ________ ATTN: Mr. L. 0. Mayer JSaltzman Director of Nuclear RMDiggs Support Services BBucklqy 414 Nicollet Mall DL...