Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Application for amend to license NPF-7,revising sections of TSs to delete reference to Rod Sequence Control Sys & reduce Rod Worth Minimizer low power setpoint from 20% to 10%.

. .- .~ -- -4.V 'L'1 :**Pubhc ServiceDectnc and GasCompanyLouis F. StorzPubkc Service Electric and Gas CompanyP.O. Box 236. Hmcocks Bridge, NJ 08038609-339-5700Sen

Forwards final plan for NRC response to incidents involving nuclear matl in unauthorized places.

*f same Q, ' .E ,ygg.,j,'(oUNITED STnTFS vgg NUCLEAR REGULATORY COMMISSION,,y g ,j wasmNGTON D.Cg518 BBS-,g w.O 5. /,+....MEMORANDUM FOR: Thomas E. Murley, Regional Administrator, Region 1J. Nelson Grace, Regional Administrator, Region IIJames G. Keppler, Regional Administrato...

Application for renewal of License SNM-1266,authorizing JE Smedley to use &/or supervise use of listed licensed matl.

,. .. . - - . . .. .. .. . - -. --o o1--. .. .|*."'.>Department of PhysicsBates CollegeiLewiston, ME 04240 ;February 26, 1987U.-S. Nuclear. Regulatory Commission INuclear Material Section B,631 Park Avenue.|King of Prussia, PA 19406'.Dear Sirs: !Here is our ranewal applicaticn...

Applicant Exhibit A-5,consisting of 860831 Rev 2 to Vol 24 of "Radiological Emergency Response Plan,Town of Stratham,NH." W/four oversize maps.

ZNSTRUCT10flS FOR 2NSERTIONNEW HA*1PSHIRE RERPRevision tJumber: 2Date of Revision:August, 198S1To facilitate the incorporation of Revision 2 into the NHRERA, the voltresthat pertain to the Seabrook Station (Volumes 1, 2, 4, 4A, 48, 5, 6,16,17,18,18A,19, 20, 21, 21A, 22, 23, 24...

"Millstone Nuclear Power Station,Unit 2,Independent Review Team Rept."

_ _ _ , .. _ _ _ . .- _ .^|;^t: l'iRocket No. 50-336B14611|1i,t;;|i:I|tAttachment 1!fiillstone Nuclear Power Station, Unit No. 2Independent Review Team Report*!i,t,;ah!,||,,'September 1993i|!)>!)9309200081 930910ID|PDRADDCK 05000336gy"j'ES ppg_ _ __oIlIINDEPENDENT REVIEW TEAM ...

Applicant Exhibit A-5,consisting of 860831 Rev 2 to Vol 27 of "Radiological Emergency Response Plan Town of Brentwood,NH." W/four oversize maps.

.INSTRUCTIONS FOR INSERTIONNEW HN1PSHIRE RERPvRevision Number: 2Date of Revision: August, 1986'To facilitate *the incorporation of Revision 2 into the NHRERP, the volumesthat pertain to the Seabrook Station (Volumes 1, 2, 4, 4A, 48, 5, 6,16,17,18,18A, 19, 20, 21, 21A, 22, 23, ...

Applicant Exhibit A-5,consisting of 860831 Rev 2 to Vol 26 of "Radiological Emergency Response Plan,Town of Exeter,NH."

.INSTRUCTIONS FOR INSERTIONNEW HAMPSHIRE RERPRevision Number: 2Date of Revision: Augus t, 1986To facilitate the incorperation of Revision 2 into the NHRERP, the volumesthat pertain to the Seabrook Station (Volumes 1, 2, 4, 4A, 48, 5, 6,16,17,18,1SA,19, 20, 21, 21A, 22, 23, 24,...

"EI Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14."

- . ,, . . ~. -.. -- . . - -.- . ..,:, y --....4''Enclosure .s,?: Edwin I. Hatch Nuclear Plant - Unit 2 J'Power Uprate Startup Test Report;-for |Cycle 14|",J,J!>110;INTRODUCTION 'i:;#;.j i!! |1.1 Eurpose andJtunmgIy .''The Plant Edwin I. Hatch Unit 2 Startup Test Report is sub...

LER 88-023-01:on 880519,reactor trip occurred due to steam/ feedwater flow mismatch coincident w/low steam generator level.Caused by plugged sight glass.Valve repaired & sight glass cleaned & controllers recalibr.W/880707 ltr.

I i-,*.,NR Feras 384 U S. NUCLE AA 5.ELULATWY COMMISSIONAPPROVED OMB NO. 3150 4104LICENSEE EVENT REPORT (LER)" a a ' * * *' *F ACILITY NAME til DOCK $f NUMSER (2)PAGE13,Sequoyah, Unit 20151 o |0 | o |3 |2 | 8 1 |OF| 0 ]6tiReactor Trip On Steam /Feedwater Flow Mismatch Coincide...

Forwards IE Bulletin#78-13 to Stearns Roger,Inc.(See ANO:7811060166

,O f 2,,. . . .. ..., ,bp8 880 ( . - UNITED STATES0ck#g NUCLEAR ~ REGULATORY COMMtsSION; { }. $REGION I5'\/.E- 631 P ARK AVENUEo,(/KWG OF PRUSSI A, PENNSYLV AM A 1906October 27, 1978.....Stearns-Roger, Inc.Mike Wida Industrial ParkGlen RoadHomer City, Pennsylvania 15748Gentlem...

Amend 6 to License 29-20512-01 for Sentex Sensing Technology Inc,amending license in entirety.

jaKT%------ ----.-----.---1_mmm.mmmm,m_ mmmmm_ _ _ _ _iW F*"F m1 2]O 34 'U.S.NdCLEAR REGULATORY COMMISSIONPAoE oFPAGES| MATERIALS LICENSEAmendment No. 06|'|Pursuant to the Atomic Eriergy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Ti...

Responds to Generic Ltr 89-19 re resolution of USI A-47, "Safety Implications of Control Sys in LWR Nuclear Power Plants." Concerns of Generic Ltr 89-19 will be addressed in util individual plant exam submittal.

y,h-~s,%. -()f38 s Po & UghtCompany>g'-;Route 3. Box 137 a. Au%ende. AR 72801,'.! ' Tel 501964 3100..!iMarch 19, 1990,,2CAN039001'U. S. Nuclear Regulatory CommissionDocuhent Control DeskMail. Station P1-137Washington, DC 20555' Subject: Arkansas Nuclear One - Unit 2'Docket No....

LER 90-003-01:on 900316,main steam & safety injection piping supports determined to be outside plant design basis & on 900328,steam generator blowdown piping also outside plant design basis.Caused by analysis deficiencies.W/900416 ltr.

_ - . - - .. - - - - - . .- - - - - - - - - ' -;fJ.-.,Omaha Public Power District1623 Harney Omaha, Nebraska 68102 2247402/536 4000;!April 16, 1990'LIC-90-0303>.i,'(| U. S. Nuclear Regulatory Commission..}';Attn: Document Control Desk' Mail Station P1-137(; Washington, DC 2055...

Rev 2 to "COLR."

-,Attachment to NSD930476.,Cooper Nuclear Station*NRC Docket No. 50-298.-f, :CORE OPERATING LIMITS REPORT ,!LIST OF EFFECTIVE PAGESi'Page(s) RevisionDatai through iv 203/26/931 through 20 203/26/93,t1.II'.i.,'03/26/93~9305110253 930503PDRADOCK 05000298P' PDR..y:..-.,*'! .,CORE...

Proposed Tech Specs concerning EOL moderator temp coefficient.

. .- - . ... .- - - - . .-... - _ -.. . - ._--__ -._-.'L. . t!1 ,| .i!'|i:'!iATsageNr i:!!PrW Omnged Pages{i|!Unit 1 RevisioniPage 3/4 1-4 Replace!Page 3/4 1-5 . Replace-Page B 3/4 1-1 Replace jPage B 3/4 1-2 Replace!!!Unit 2 RevisionitPage 3/4 1-4 Replace!Page 3/4 1-5 Replace...

Application for amends to licenses DPR-53 & DPR-69,revising TS associated w/content of design features.

Y9?=BALTIMORElGAS ANDELECTRIC1650 CALVERT CLIFFS PARKWAY . LUSBY. MARYLAND 20657-4702|.70BERT E. DENTONVict PRESIDENTDecember 8,1993i NUCLEAR ENERGY(4io) aso-44ssU. S. Nuclear Regul . tory CommissionjWashington,DC 20555A'ITENTION: Document Control DeskSUBJECT:Calvert Cliffs Nu...

Responds to NRC ltr re violations noted in insp rept 50-331/93-15.C/A:skimmer surge tank,1T-61B,will be recoated by 941231.

cw...Iowa Electric Light and Power CompanyDecember 6, 1993$"Edie$"N ]",;NG-93-5025Dr. Thomas E. Murley, DirectorOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionAttn: Document Control DeskMail Station P1-137Washington, DC 20555Subject: Duane Arnold Energy...

Forwards State of OH EPA approval for use of Betz biocide Clam Trol CT-1 at facility,per Section 3.2,App B to environ protection plan.

.___%..,,_6200 Dok Tree Boulevard Mail AddressIndependence 0H PO Box 94661116-447-310 0 Cleveland. 0H 44101-4661i-. July.20, 1990iPY-CEI/NRR-1202 L ,PiU.S. Nuclear Regulatory Commission;-Document Control DeskWashington, D. C. 20555Perry Nuclear Power Plant| Docket No. 50-440OE...

Forwards marked-up FSAR pages showing changes to be incorporated into Chapter 11 of Amend 32 re radwaste sys.

_f,N'/ |. .e,*'Very truly yours,7,dff's'4- . *$/..'T. C. Nichols, Jr.Senior Vice President* ~7 ~~Power Operations .,.-g-',T g8206020427 820324-"'PDR ADOCK 05000395i4 a~.q,APDRi g.,,-_*.eMr. Harold DentonMay 24, 1982Page 2NEC:'KN:lkbcc: V. C. Sumer (w/o attach.)G. H. Fischer (w...

Response in opposition to UCS 821228 petition to review ALAB-705 determination that EIS re Class 9 accident consequences not required.Further Commission review unwarranted.Certificate of Svc encl.

-, m*=l/7/83.COCKETEDU9iRCUNITED STATES OF AMERICANUCLEAR. REGULATORY COMMISSION'83 JAN 10 NO:I?' , ,r ;E c i!:wv~cc :i- iBEFORE THE COMMISSION4'In the Matter of ))METROPOLITAN EDISON COMPANY )Docket No. 50-289) (Restart)-(Three Mile Island Nuclear )Station, Unit No. 1))LICENS...

Enclosure 4 - SHINE Safety Analysis Methodology - Public Version

39 pages follow ENCLOSURE 4 SHINE MEDICAL TECHNOLOGIES, LLC MEETING SLIDES FOR THE MARCH 4 AND 5, 2020 PUBLIC MEETING BETWEEN SHINE MEDICAL TECHNOLOGIES, LLC AND THE NRC SHINE SAFETY ANALYSIS METHODOLOGY PUBLIC VERSION SHINE Safety Analysis MethodologyJohn Olvera, Saf...

Opposes const of facility.Miscellaneous newspaper articles & matl encl.

*- ....416 S. 17th StreetChesterton IndianaMay 12, 1951Nuclear Regulatory Commission -Washington Project ManagerUranium Fuel Licensing BranchWashington, D.C. 20555Gentlemen:Think of that salutation.Gentle men--I hope you will all be gentleand though.tful with our lives.Those w...

Application for amendment to license.Requests Tech Specs 3.7,4.6 & 6.9.2 be mod to establish limiting conditions for operation & surveillance requirements for a gas trubine generator.W/Tech Spec page revisions & safety evaluation.

*.. . ..UNITED S'IATES OF AMERICANUCLEAR REGUIA'IORY COMISSIONIn the Matter of ))CONSOLIDATED EDISCN COMPANY ) Docket No. 50-247OF NEW YORK, Itc.)(Indian Point Station,)Unit No. 2) )APPLIC.TTION FOR AMENrNENT'IO Or_MTING LICENSE _Pursuant to Section 50.90 of the Regulations of...

Responds to NRC 810914 ltr re violations noted in IE Performance Appraisal Insp Rept 50-293/81-20.Corrective actions:operations review committee charter will be reviewed,per ANSI N18-7-1976 & Reg Guide 1.33,by 811123.

,..e_L-'!tEOSTON EDISON COMPANYB00 SovLsTON STREETBOSTON. MASSACHUSETTS 02199ANDREW V. CORRYas=.co vcc eece.osatOctober 16, 1981BECo Ltr. #81-249NMr. Norman C. Moseley, DirectorDivision of Program Development and AppraisalOffice of Inspection and EnforcementU. S. Nuclear Regul...

Rev 7 to Engineering Operating Procedure EOP 40-7.00, "Design Reviews."

.'# #'O'GE Nuclear EnergyEngineenng Operating Procedure EOP 40-7.00SUBJECT: DESIGN REVIEWS1.0 PURPOSE1.1This E0P defines responsibilities and procedural requirements forconducting design reviews.2.0 GENERAL APPLICATIONI2.1 Design reviews are formal, design adequacy evaluations...