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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.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

LER 95-006-00:on 950818,pressure boundary leakage resulted in plant shutdown.Contained leakage in plant collection & completed repairs to leaking weld on 950821.W/950915 ltr.

.i*'}Vs-7TAbTelephone (412) 393-6000O. x4Shippingport, PA 15077-0004September 15,1995ND3MNO:3715Beaver Valley Power Station, Unit No.1Docket No. 50-334, Licensee No. DPR-66LER 95-006-00United States Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555In accor...

Responds to request for addl info re Rev 3 to Reg Guide 1.97, "Emergency Response Capability." Instrumentation used to monitor status of standby power sys & energy sources important to safety listed.

. _- _ __-- ._ _ . ._ . . . ._7.. c- -Generic Letter 82-33-lj:-. .,*I gosygygotSONPilgrim Nuclear Power StationRocky Hill RoadPlyrnouth, Massachusetts 02360Ralph G. BirdBECo 89-053senior Vice President - NuclearU.S. Nuclear Regulatory CommissionDocument Control DeskWashington,...

TS Change Request 98-09-0 for licenses NPF-39 & NPF-85, revising TS Section 3/4.4.3, "RCS Leakage,Leakage Detection Systems," by clarifying action statement re inoperative reactor coolant leakage detection systems.

,. ...A10 CFR 50.90PECO NUCLEAR es w eoe,9v comnen,Nuclear Group HeadquartersA UMr of PECO ENERCy965 Chesterbrook BoulevardWayne, PA 19087-5691,lJune 7,1999Docket Nos. 50-35250-353License Nos. NPF-39NPF-851U.S. Nuclear Regulatory Commission!Attention: Document Control DeskWash...

Forwards request for addl info re util 850411 procedures generation package submitted in accordance w/Generic Ltr 82-33.Response requested by 860715.

*,..W IF %Docket No. 50-416, DISTRIBUTIONJDocket FfTe,g ,BrienNRC PORACRS(10)LPDR RAnandMr. Oliver D. Kingsley, Jr. PD#4 Rdg. ISchoenfeldVice President, Nuclear Operations RBerneroMississippi Power & Light CompanyYoung, OELDP.O. Box 23054EJordanJackson, Mississippi 39205 BGrim...

Proposed Tech Specs re RCS emergency vent sys.

-.MAINE YANKEE ATOMIC POWER COMPANYD. Reactor Coolant System Emergency Vent System]]1.At least one reactor coolant system emergency vent path, consisting]]of at least two valves in series capable of being powered from]emergency busses shall be operable * and closed during tran...

Concurs w/Chapter 7 of 820310 SER upon incorporation of encl changes per 820216 SER & 820311 discussions.

p_!.fr/m,hchekeJ-..~'. . ? . . .,, -/''-i-/c., , ,1 i i33") *h'%;'IMAR 12 W62' co sd :en:./ %s J/ n... ./ t...u _ , . .,T;sr.:i" - 4f, ^,MEMORANDUM FOR: Albert Schwencer, Chief, Licensing ranch #2Division of Licensing1FROM:Faust Rosa, Chief, Instrumentation & Control Systems B...

Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, Emergency Plan Implementing Procedure (EPIP) Revisions

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609 June 14, 200010 CFR Part 50, APP.EU.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentleman:In the Matter of Tennessee Valley AuthorityDocket Nos. 50-259 50-260 50-29...

Request to Use an Alternative to the ASME Boiler and Pressure Vessel Code, Section XI, in Accordance With 10 CFR 50.55a (a)(3)(i), Duke Energy Corporation Serial Number 01-GO-003.

Duke Duke Power 526 South Church St. EC07H *PowVer@ Charlotte, NC 28202 A Duke Energy Company P.O. Box 1006 EC07H Charlotte, NC 28201-1006 M. S. Tuckman (704) 382-2200 OFFICE Executive Vice President (704) 382-4360 FAX Nuclear Generation September 25, 2001 U.S. Nuclear Regulat...

Application for amend to License DPR-20,changing Tech Specs to allow surveillance tests that require cold shutdown conditions to be performed on refueling cycle rather than current 18-month cycle.

,. ' CONSUMERS POWER COMPANY . Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued ...

"Technical Assistance for Insp of Diablo Canyon Design Verification Program," progress rept for June 1984.

' '..:- - .+..'- 5c4.E I~"LAWRENCE UVE@MORE LABORATORY.La m e-1955 JA 25 FH 1: 18LJuly 19,1984WOW: 84-23-REGIO!!Vl&E'Mr. Phillip J. Morrill, Project ManagerU.S.- Nuclear Regulatory Agency, Region V1450 Maria Lane, Suite 210Walnut Creek,-California 94596PROGRESS REPORT, JUNE 19...

Insp Rept 50-155/85-05 on 850319-0429.No noncompliance or deviations noted.Major areas inspected:licensee actions on previous insp findings,operational safety,maint operation, surveillance operation & reactor trips.

_.,..U.S. NUCLEAR REGULATORY COMMISSIONREGION III. Report No. 50-155/85005(DRP)Docket No. 50-155License No. DPR-6Licensee: Consumers Power Company212 West Michigan AvenueJackson, MI 49201Facility Name: Big Rock Point Nuclear PlantInspection At: Charlevoix, MI 49720Inspection C...

Summary of operating reactors events 850515 meeting.Div directors or representatives briefed on events occurring since 850507 meeting.Assignment of followup review responsibilities discussed.Attendance list encl.

'-y_4MAY 2 21985'..MEMORANDUM FOR: Hugh L. Thompson, Jr., Director>Division.of LicensingFROM:Dennis M. Crutchfield, Assistant Directorfor Safety Assessment, DLSUBJECT: SUMMARY OF THE OPERATING REACTORS EVENTSMEETING ON MAY 15, 1985On May 15, 1985, an Operating Reactor Events m...

LER 96-008-00:on 960607,TS required pressure not met during local leak rate testing.Caused by procedural deficiency. Procedure changes submitted & check valves retested using appropriate vent paths.

.-. . .--. _- _ -. iLICENSEE EVENT REPORT (LER) Form Rev. 2.0||Facility Name (1) Docket Number G)Page (3)||0|5|0|0|0|2|5|4 1 | of | 0 | 4Quad Cities Unic Onei.i Title (4),i i. .Tha Technical Specification Required Pressure Was Not Met During Local Leak Rate Testing Due To A Pr...

LER 91-003-02:on 910118,found stresses at specific points in piping exceeded UFSAR allowable stresses.Caused by preservice error.No corrective action required since all lines operable.

(gmT nto1Revision 2 1'ATTACHMENT Fp1d., g t ,-. ,'REVISION TO DVR{75).DVR NO.,STA UNIT YEARNO*- . .04 01 91012 (Rev. 1)|PART 1 TITLE OF EVENTOCCURRED|Specific points in ACAD/ CAM lines exceed 01-18-91 1532IUFSAR allowable stresses DATE TIMEREASON FOR REVISED REPORT lWalkdowns ...

LER 96-008-00:on 960709,failed to perform quarterly backseat/closure test on five check valves.Caused by personnel error.Test procedure written & performed on subject check valves.W/960808 ltr.

. . _ _ __. . ..T~*.|'.*;.I'!Tennessee Valley Authority, Post Offce Box 2000, Soddy-Daisy, Tennessee 37379-2000R.J. AdneySite Vice PresidentSequoyah Ntclear PlantLAugust 8,1996-U.S. Nuclear Regulatory CommissionATTN: Document Control DeskiWashington, D.C 20555Gentlemen:TENNESS...

Forwards plant-specific response re util trip-two/leave-two procedures for small break LOCAs,per Generic Ltr 86-06, "Automatic Trip of Reactor Coolant Pumps."

_ _ _ _ _ _ _ _ _ _ _. .e. -.- -wes--)Omaha Public Power District1623 Harney Omaha. Nebraska 68102 2247402/536-4000September 30, 1987LIC-87-649)U. S. Nuclear Regulatory Commission|ATTN: Document Control DeskWashington, DC 20555References:(1)Docket No. 50-285(2)Resolution of TM...

PWR SRO Examination Outline (Form ES-401-3) for Point Beach Nuclear Plant.

ES-401 PWR SRO Examination Outline ES-401-3 Facility: Point Beach Nuclear Plant Date of Exam: 16 Oct 2000 Exam Level: SRO K/A Category Points ATA Point Tier Group K K K A A A G Total 1 2 3 4 5 6 1 2 3 A 14 1 4 24 Emergency & 2 2 1 16 Abnormal Plant 3 0 1 , 3 Evolutions Tier To...

Pilgrim, License Amendment, Redefinition of High Radiation Area Criteria of Appendix A by Replacing Existing Wording With that Contained in BWR Standard Technical Specification.

Docket No. 50-293 DEC 1 0 i980 Mr. A. Victor Morisi .. Boston Edison Company M/C NUCLEAR 800 Boylston Street Boston, Massachusetts 02199 tt. Dear Mr. Morisi: The Commission has issued the enclosed Amendment No.LIto Facility License No. DPR-35 for the Pilgrim Nuclear Power St...

Fermi 2, Technical Specifications for License Amendment No. 149, Revision to Control Room Emergency Filtration System Requirements.

CREF System 3.7.33.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Filtration (CREF) SystemLCO 3.7.3The CREF System shall be OPERABLE.------------------------------------- NOTE ------------------------------------The control room boundary may be opened intermittently under admini...

North Anna and Surry, Units 1 & 2, Risk-Informed ISI Relief Requests R-1 Response to Request for Additional Information.

VIRGINIA ELECTRIC AND POWER COMPANYRICHMOND, VIRGINIA 23261April 2, 2003United States Nuclear Regulatory Commission Serial No.: 03-235Attention: Document Control Desk NL&OS/GDM R1Washington, D. C. 20555 Docket Nos. 50-338, 33950-280, 281License Nos.: NPF-4, 7DPR-32, 37Gentleme...

Waterford Steam Electric Station, Unit 3, Supplement to Amendment Request NPF-38-249, Extended Power Uprate.

5" EntergyEntergy Nuclear SouthEntergy Operations, Inc.17265 River RoadKillona. LA 70057Tel 504-739-6310Fax 504-739-698tmitchlentergy.comTimothy G. MitchellDirector, EngineeringWaterford 3W3F1-2004-0111November 4, 2004U.S. Nuclear Regulatory CommissionAttn: Document Control De...

GT-MHR Source Term Overview Presented on 01/28/2003.

2-1Presented toNuclear Regulatory Commission Staff28 January 2003 David L. HansonSenior Staff EngineerGeneral Atomics2-2• Radionuclide Containment System– Multiple release barriers– Defense-in-depth• Controlling Radionuclide Transport Phenomena• Methodology for Deriving Barrie...

GE-Hitachi (Design Control Document Tier 1), Rev. 6 - Tier 1

GE Hitachi Nuclear Energy 26A6641AB Revision 6 August 2009 ESBWR Design Control Document Tier 1 26A6641AB Rev. 06 ESBWR Design Control Document/Tier 1 ii NOTICE The design, engineering, and other information contained in this document is furnished by GE-Hitachi Nuc...

Transmittal Letter re: Amdt #7, change No. 9 to Tech Specs Consists of Revised & Addl pages to OL-DPR-43.

NRC DI&IBUTION FOR PART 50 DOCKET#TERIAL (TEMPORARY FORM) CONTROL NO: 12871AFILE:FROM: Wis. Public Service Corp. DATE OF DOC DATE REC'D LTR TWX RPT OTHER Green Bay, Wis. 54305 MF_ Stprn _11-7-75 11-10-75 XX TO: ORIG CC OTHER SENTNRC PDR XX Mr. E. Jo6dan1 SENT LOCAL PR 1 s-igne...

Proposed Tech Specs re fire protection requirements.

Section Title Page TS 3.3 Engineered Safety Features and Auxiliary Systems 3.3-1 3.3.a Accumulators 3.3-1 3.3.b Safety Injection and Residual Heat Removal Systems 3.3-2 3.3.c Containment Cooling Systems 3.3-4 3.3.d Component Cooling System 3.3-6 3.3.e Service Water System 3.3-...