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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.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

NRC Information Notice 1998-026: Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations.

. -2v?UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001July 24, 1998NRC INFORMATION NOTICE 98-26: SETTLEMENT MONITORING AND INSPECTION OFPLANT STRUCTURES AFFECTED BYDEGRADATION OF POROUS CONCRETESUBFOUNDATIONSAddresseesAl...

Telecommunication with Duke Energy Corporation to Discuss Information in their License Renewal Application on Aging Management of Containments, Structures and Structural Supports.

November 30, 2001LICENSEE : Duke Energy CorporationFACILITIES: McGuire (MNS), Units 1 and 2, and Catawba (CNS), Units 1 and 2SUBJECT: TELECOMMUNICATION WITH DUKE ENERGY CORPORATION TO DISCUSSINFORMATION IN THEIR LICENSE RENEWAL APPLICATION ON AGINGMANAGEMENT OF CONTAINMENTS, S...

SUMMARY OF MAY 24,2000, MEETING TO DISCUSS STEAM GENERATOR REPLACEMENT & POWER UPRATE ISSUES.

LICENSEE: Arizona Pubfd S €8rkpanyPalo Verde Nuclear Generating Station, Unit 2 SUMMARY OF THE MAY 24,2000, MEETING TO DISCUSS STEAM GENERATOR REPLACEMENT AND POWER UPRATE ISSUESOn May 24, 2000, the U.S. Nuclear Regulatory Commission's (NRC's) staff, and the Palo Verde Nuclear...

Peach Bottom Atomic Power Station IMPROVED TECHNICAL SPECIFICATIONS (UNIT #3 BASES)

PECO ENERGY Peach Bottom Atomic Power Station IMPROVED TECHNICAL SPECIFICATIONS (UNIT #3 BASES)PAGE REVISION LISTING B TABLE OF CONTENTS page(s) . .............................................................................................................. Rev 28 page(s) ii -...

Part A - Submittal of all Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40.

Exel . sm Exelon Nuclear www-exeloncorp.com Nuclear 2o0 Exelon Way Kennett Square, PA 19348 TS 5.5.10.d April 19, 2002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Peach Bottom Atomic Power Station, Units 2 and 3 Facility Operating Licen...

Davis-Besse Station, License Amendment 159, Amendment Removes Operability Requirements For Decay Heat Isolation Valve Interlock Channels & Pressurizer Heater Interlock Channels In Mode 4 & 5.

August 14, 1991Docket No. 50-346 Mr. Donald C. Shelton, Vice President Nuclear - Davis-Besse c/o Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 Dear Mr. Shelton: SUBJECT: AMENDMENT NO.159 TO FACILITY (TAC NO. 80329) The Commission has issued Amendment No. NPF-3 f...

Brunswick, Units 1 & 2 - Non-proprietary Safety Evaluation for Extended Power Uprate.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 222 TO FACILITY OPERATING LICENSE NO. DPR-71AND AMENDMENT NO. 247 TO FACILITY OPERATING LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANYBRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2DOCKET N...

Forwards response to questions raised on 860321 application for amend to License DPR-40 re testing of emergency diesel generators to complete Generic Ltr 84-15 actions.

'.Omaha Public Power District1623 Harney Omaha, Nebraska 68102-2247402/536-4000March 13, 1987LIC-87-126U. S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555Reference: 1. Docket No. 50-2852.OPPD Application for Amendment of Operating Licensedated March 21...

05/20/2004 Public Meeting Handouts re Power Uprate License Amendment Request for Seabrook Station Unit No. 1.

DRAFT SUPPLEMENTAL INFORMATIONATTACHMENT 1RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATIONFOR LAR 04-03APPLICATION FOR STRETCH POWER UPRATEDRAFT SUPPLEMENTAL INFORMATIONDRAFT REQUEST FOR ADDITIONAL INFORMATIONRELATED TO POWER UPRATE LICENSE AMENDMENT REQUESTSEABROOK STATIONDOC...

Three Mile Island, Unit 1 - 2003 Annual Report.

AmerGen SMAmerGen Energy Company, LLC200 Exelon WayKennett Square, PA 19348www.exeloncorp.comAn Exelon Company1 OCFR50.46June 1, 20045928-04-20128U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Three Mile Island, Unit 1 (TMI Unit 1)Operati...

"Diablo Canyon Design Verification Program,Semimonthly Status Rept 45."

TABLE OF CONTENTSSummaryStatus of Independent ProgramStatus of Internal Technical ProgramAddendum-l

Browns Ferry, Units 1, 2 and 3, License Renewal Application, Heating, Ventilation and Cooling (HVAC) Systems Sections 2.3.2 and 2.3.3, Request for Additional Information (RAI).

November 3, 2004 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen: In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 ...

Transcript of ACRS Thermal Hydraulic Phenomena Subcommittee Meeting on Waterford 3 Extended Power Uprate Project, January 26, 2005.

Waterford 3Extended Power UprateACRS Thermal HydraulicPhenomena SubcommitteeJanuary 26, 2005- EntffgyC.-z=-En tergyCWaterford 3 Extended Power Uprate ProjectACRS Thermal HydraulicPhenomena SubcommitteeJanuary 26, 2005IC-,A-En tergyTim MitchellEngineering Director2AdEn tergyAge...

Vogtle, Units 1 & 2, Initial Exam 2015-301 Final SRO Written Exam.

Si2oANSWER KEY REPORTfor Test Test Form: 0answers# ID Points Type 01 002G2.2.37 1 1.00 MCS B2 003AG2,2.25 1 1.00 MCS A3 004G2.1.23 1 1.00 MCS A4 006G2.1.7 1 1.00 MCS B5 007EA2.06 1 1.00 MCS A6 009EA2.38 1 1.00 MCS B7 011A2.02 1 1.00 MCS C8 013A2.03 1 1.00 MCS C9 027AA2.10 1 1....

Korea Hydro and Nuclear Power Co., Ltd - Response to RAI 297-8309 for Question 19.03-04.

19.03-4_Rev.1 - 1 / 2 KEPCO/KHNP REVISED RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONAPR1400 Design Certification Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., LTD Docket No. 52-046 RAI No.: 297-8309 SRP Section: 19.03 – Beyond Design Basis External Ev...

Forwards response to NRC 790913 ltr re followup actions resulting from NRC review of TMI.Requirements re emergency operations ctr insufficiently defined to designate dedicated primary & alternate locations.

REGULATORY Ii eORMATION DISTRIBUTION SYS (RIDS)ACCESSION, NBR: 7910250)33 DOC~DATE: 79/10/22'OTARIZED j NOFACIL:50 335 St, Lucia Planti Unit li Flor ida Power L Light Co.AUTH ~NAMg AUTHOR AFFILIATIONUHRIgiR ~ EDFlorida Power 8 Light Co~R E C I Py hf AME!, R E C I P I E NT A F ...

Vogtle, Units 3 & 4, Updated Final Safety Analysis Report, Revision 3, Chapter 2, Site Characteristics, Appendix 2.5E - AP1000 Vogtle Site Specific Seismic Evaluation Report.

2.5E-1 Revision 0VEGP 3&4 – UFSARAppendix 2.5E—AP1000 Vogtle Site Specific Seismic Evaluation ReportPrepared byWestinghouse Electric Company LLCOctober 2008 SV0-1000-S2R-802 October 2008 Revision 4 AP1000 Vogtle Site Specific Seismic Evaluation Report ...

Proposed tech specs,permitting refueling to continue beyond 7 days w/one emergency ventilation circuit inoperable provided remaining emergency ventilation circuit is operable & in operation.

ATTACHMENTANIAGARAMOHAWKPOWER CORPORATIONLICENSE NO. DPR-63DOCKET NO. 50-220PROPOSED CHANGE TO TECHNICALSPECIFICATIONSReplace existing page174 with the attached revisedpage174. Thispagehas been retyped in itsentirety with a marginal marking to indicate changes to the text.g+O>...

Forwards addl info re shift consultant program,per 840525 request.Shift consultant written & oral exams,written exam answer key & test results included.Individual who failed taking retraining program.

a. .KANSAS GAS AND ELECTRIC COMPANYTHei ELECT 54C COMPANYCLENN L MOESTERvice PatssotNT soucLeanOctober 8, 1984Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C. 20555FMLNRC 84-179Re: Docket No. STF 50-482Ref: 1)...

Proposed Tech Specs increasing surveillance test intervals & allowed outage times for RPS & ESFs actuation sys.

_ . _ . . .Docket No. 50 421B14018_Attachment 1.-H111 stone Nuclear Power Station, Unit No. 3Proposed Technical Specification ChangesReactor Protection System and Engineered Safetyfeatures Actuation System,-. . _March 19929203120333 920303DR ADOCK 0500 3.-_ _ _ _ _ _ _ _ . . ....

Application for amends to licenses NPF-9 & NPF-17,proposing rev related to replacment of steam generators.

_|| IDukeFowCompany M S Tutxas>p.0,gox1006Senior Mce PresidentCharlotte.NC2820H006 Nuclear Generation>(7003822200omce 1(7003824360 Fax@-:.September 30,1994,U.S. Nuclear Regulatory CommissionDocument Control Desk'Washington, D. C. 20555,Subject:McGuire Nuclear StationDocket Nos...

Revision 0 to "Suppression Pool Leakage Return." Response to NUREG-0737,Item II.B.3 re post-accident sampling encl.

bL,fJ~'<%mMC-1 --.. ~..=~f Chialttp< ; /lfp/ c - < >L//I--.,.(pp/., ./.c.,. 4/r' -~ ~ ** ''' /,1,pr ovcd :t' tan n.t,'cW-*x --*SP Number 23.702.f,4Revision 0-Date Eff.'12/307iilTPCTPCTPC,SUPIRESSION POOL LEAIM E PETURNO1.0 PURPOSETo provide detailed instructions to the Sectice...

Proposed tech specs for one time surveillance deferment.

ATTACHMENT I Consumers Power Company Pa 1 i sades Pl ant Docket 50-255 PROPOSED ONE TIME SURVEILLANCE DEFERMENT TECHNICAL SPECIFICATIONS REVISED PROPOSED PAGES 9503310313 950330 PDR ACOCK 05000255 P PDR 13 pages e 4:1 OVERPRESSURE PROTECTION SYSTEM TESTS Basis Surveillance Req...

Forwards rept re status of implementation of TMI action plan items,per 890414 request.

Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer APR 1 8 1009 NLR-N89079 United States Nuclear Regulatory Commission Document Con...

Rev 0 to EA-AIR-BRP-97-027, "RAI - Regarding Rerating of Portions of Post Incident Sys,A-BRP-97-027."

-. - - - . . - . . .. . - . - - . -EA-AIR-8RP 97-027. , ,BIO ROCK POINT NUCLEAR PLANT-*'ENOiNEERING ANALYSIS WORK SHEETTitk = RAI Regarding Rerating of Portions of the Post incident System, A BRP 97 027.AnalystReview Method (x)Tech RevRev# Description By Date Alt CalcDet Resie...