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NRC Staff response to Yankee Atomic Electric Co motion to terminate proceeding.* For listed reasons,Licensing Board should grant motion to withdraw application & terminate proceedings.With Certificate of Svc.

-_. - - . - - . _.b'ko%$;/ #kJUL~7 %lum-g'iUNITED STA .NUCLEAR REGULA$tYC S*'q ..BEFORE THE ATOMIC SAFETY L!b . s GBOARDIn the Matter of)).YANKEE ATOMIC ELECTRIC COMPANY) Docket No. 50-029-LA)|(Yankee Nuclear Power Station)))NRC STAFF RESPONSE TO YANKEE ATOMIC ELECTRIC COMPANY...

"Vicinity Property Completion Rept at NT-067."

!DEPARTMENT OF ENERGYALBUQUERQUE OPERATIONS OFFICECONTRACT NO. DE-AC04-83AL18796Vicinity PropertyCompletion ReportRemedial Actions[ Contractor(ofortheC? Uranium Mill Tailingsl-Remedial ActionsZProjecth219,-- -5$.-E:n "";_|Isqju liIII.IIIIIIIIIIII91ws.tw % = hE n % .osIIIi;. . ...

Draft calculations for "Remedial Action Plan & Site Conceptual Design for Inactive U Mill Tailings Site at Spook,WY." W/one oversize drawing.

U MTR A-DOE / AL gg; _7pLUnited States Department of Energy ,''I,jfj/~* ;",,/s-Remedial Action Plan andSite Conceatua'Design forinactive Uranium Mill TailingsSite at Saook, WyomingODraft.'CalculationsON: August,1987m',Uranium MillTailings Remedial Action Project IUMTRAPIwx ciM...

The Oglala Sioux Tribe's Migrated, Renewed, and New Marsland Expansion Final Environmental Assessment Contentions.

1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of ) Docket No. 40-8943-MLA-2 ) CROW BUTTE RESOURCES INC. ) ASLBP No. 13-926-01-MLA-BD01 ) (Marsland Expansion Area) ) May 30, 2018 THE OGLAL...

Saint Lucie Unit 1 - Supplementary Startup Test Report.

FLORIDA POWER AND LIGHT COMPANYST. LUCIE NUCLEAR POWER PLANTUNIT 1gackot+ 04- -~~F00Qggtg)0 11 lOa(~5'f90cumen-hshow the fuel loading sequence. Figures2 0-2and2'-3show fuel assembly location and CEA location by theirrespective serial numbers. It should be noted that in the ori...

Forwards Rev 2 to updated FSAR for Nine Mile Point Unit 2 & annual safety evaluation summary rept.

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMt

Proposed Tech Spec 3.1.4 re max coolant activity.

Attachment A1. Replace Technical Specification pages3.1-21 and 3.1-24 withthe enclosed revisions.8gOP2303b78300244PDRADOCKoPDRPIIl I'f3.1.4 Maximum Coolant ActivitS ecifications:3.1.4.1 Whenever the reactor is critical or the reactor coolantaverage temperature is greater than ...

Forwards NPDES monthly discharge monitoring repts for Aug 1979.

*.b'Af(412) 456-6000435 Sixtn Avenuegeguran. penns9vaniaSeptember 29, 1979Director of Nuclear Reactor RegulationAttn: Mr. Robert W. Reid, ChiefOperating Reactor Branch, No. 4United States Nuclear Regulatory CommissionWashington, D.C. 20555Subject: BVPS No. 1Docket No. 50-334Li...

Rev 0 to Calculation 0024-00099-MOT-01, "Selection of Ground Motion for A-46 Evaluation."

___.__________ - _ - - . ..-.-'DOCUMENT APPROVAL COVER SHEETvDOCUMENT NURI IER: 0024-00099-MOT-01DOCUMENT TITLE: Selection of Ground Motion for A-46VECTRAEvaluationDOCWENmPE:CUENT: NUSCO1CALCULADoNSPECORCADONPROJECT:Millstone Unit 2 Auxiliary BuildinaREPORTDOCUMENT PERPROJECT ...

Forwards responses to 820820 acceptance review questions re OL application,scheduled for NRC review in Nov.Marked-up FSAR pages included where changes became necessary due to responses.

4-:*.Washington Public Power Supply SystemP.O. Box 968 3000 GeorgeWashnigton Way Richtand, Washington 99352 (509)372-5000Docket No. 50-508G03-82-1228i'ovember 30, 1982Mr. G. W. Knighton, ChiefLicensing Branch No. 3US Nuclear Regulatory CommissionWashington, D.C. 20555Subject: ...

"Visual Exam Results of Segment 2,Fort St Vrain Fuel Elements 1-2415,1-0172,2-2693,1-0108 & 5-0801."

rok 1485Mtv. tilson(PED-81-2200)ISSUE SUMMARYTITLE: VISUAL EXAMINATION RESULTS OF SEGMENT 2 FSV OR&D 5APPROVAL LEVELFUEL ELEMENTS 1-2415, 1-0172, 2-2693, 1-0108 G DV & SAND 5-0801O DESIGNDISCIPLINE SYSTEM 00C. TYPE PROJECT DOCUMENT NO.ISSUE N0JLTR.N 18 RTE 6400 906577 /2QUALIT...

Forwards design info re addition of shunt trip to reactor protection sys trip breakers for NRC review & approval.Shunt trip capability poses no unreviewed safety question.W/two oversize diagrams.Aperture cards are available in PDR.

---ARKANSAS POWER & LIGHT COMPANYPOST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501)371-4000June 7, 19831CAN068306Director of Nuclear Reactor RegulationATTN: Mr. J. F. Stolz, ChiefOperating Reactors Branch #4Division of LicensingU. S. Nuclear Regulatory CommissionWashington, ...

"Fort St Vrain-Tendon Requirements Based on Safety Consideration."

-,_ _ . _ . . . , , -_..... ._ _ _ _ _ _ _ . . _ . . . . . . . _ . . . _ . _ . . _ . _ _ _ . . . . ..... _ _ _ _ _ _ .,oA use Imav. ietes).ISSUE SUMMARYTITLEFSV - TENDON REQUIREMENTS BASED ON SAFETYDR&DAPPROVAL LEVEL _2O DV & SCONSIDERATION.g| DESIGNDISCIPUNE SYSTEM 00C. TYPE ...

Motion to revise wording of Issue 8 re hydrogen control, aligning wording w/true intent & w/Commission new hydrogen control rule for degraded core accidents.Certificate of Svc encl.

n . -.1' phoi}'.. -- - ,,January 22,'1985*E,' UNITED STATES OF AMERICAE[U-NUCLEAR REGULATORY COMMISSION*: - -.N '23 U.-BeFore the Atomic Sofety and Licensing Board:qIn the Motter of )1~ 'THE CLEVELAND ELECTRIC Docket Nos. 50-440 OL.'ILLUMINATING CO. ET AL. )50-441.0L ,-t.,) 's...

Confirms 840623 verbal communication re organizational entity & 10CFR50.55(f) implications.Existing QA program description unchanged w/exception of organizational name changes.

y . ,, .Ph/.2., - ,/Wendell P. Johnson'Vice PresidentAugust 31,_1984-WPJ - 060SBN- 708T.F. B7.1.2United States Nuclear. Regulatory CommissionRegion I631 Park AvenueKing of Prussia, PA 19406' Attention:Dr, Thomas E. Murley'Regional AdministratorReferences:-(a) Docket Nos. 50-44...

Proposed tech specs associated w/various ESF systems following design basis fuel handling accident.

__ . - - --t $ c N A 3 |* & # # ~ W |##']''Ay z en z*;5DEFINITIONS!|REACTOR PROTECTION SYSTEM RESPONSE TIME!)'1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from,when the monitored parameter exceeds its trip setpoint at the channel sensor|until de-ener...

"1992 Santee Cooper Annual Rept," for VC Summer Nuclear Station.

* GI ,, , p.. . . ' ''e.. :. . . ., . .+Av - - g'..- -."' " - j', . . , . * . .' ', ' ' . '. , ..... , . .,. . ' . ' . . . . _ .. .. . . q1am g.. . . - -. . -. _;.R.. . . . .,,'........y-' '. .a, '3_'.- ',E%.. r* 5 i s-i'.'. . ~/.3'.'i..,1';.,'*i .. . . . ._* ; ''4- -.- ;' '''...

Forwards documentation of discussions held at 840323 meeting re environ qualification of safety-related electrical equipment.Documentation includes proposed resolutions to deficiencies noted in 830111 draft SER.

. . . . . .- .. . . . . . . . . . . . . . . . . . - . . .. -. -- .- . - __- _ _;. .g|,,.. ,..- - - -. _ . .Omaha Public Power District1623 Harney Omaha, Nebraska 68102402/539 4000May 31, 1984'LIC-84-121,Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. Nu...

Transcript of HA Hutchinson 840227 testimony re CYGNA rept & incident surrounding contract & onsite audit conducted by CYGNA.Pp 1-79.

.!|-{-UNITED STATES OF AMERICA~NUCLEAR REGULATORY COMMISSION-.a/In the matter of:Investigative Interview ofHeyward A. Hutchinson, Jr.*,Docket No.-../iLocation: Arlington, Texas Pages:1 through 79Date: Monday, February 27, 1984.8410310200 840308PDR ADOCK 05000445GPDR.~.~L-TAYLO...

Rev 1 to "Evaluation of SI-860,SI-857 & RC-515/516 Bonnet Pressurization."

!iNUCLEAR POWER BUSINESS UNrrCALCULATION REVIEW Aht APPROVALCalculation #9 /. - o o (o 1Number of PagesIOETitle of Calculation:E,,LL.3 S sr no's , sr-8 s7 'a .-bk sres-/s 6 s'3=a4- h< es aMr.0 .O Original Calculation13'QA-ScopeEr'hevised Calculation. Revision #/O Superseding C...

Matls licensing package for amend 37 to license 24-00624-02 for Trinity Lutheran Hosp.Control:393550.

-_ - _ _ _ _ - _ - _ _ _ _ _ _ _-e.q'Wa*MMCMT"ITEMTWFMM*iTMMrMM ~ 'MMMMMMMMM'37'"4I 2,7 une r-ma u.s. Ut AR REGULATORY COMWSSIONpygg g PAGESiLkense numberF,*i24-00624-02 >|,1MATERIALS LICENSE;+gg g ,,,,c, ,, ,3, ,iSUPPLEMENTARY SHEET030-022804_.piFAmendment No. 37 p';,ii,4Trin...

Revised emergency plan implementing procedures,including EP R-1 re personnel injury or illness,EP R-6 re radiological fire,EP M-6 re nonradiological fire & EP G-1 re accident classification.W/841025 ltr.Related correspondence.

PGandE Lotter N3.: DCL-84-336ENCLOSURE 1Updates Included In This SubmittalDIABLO CANYON EMERGENCY PLAN'IMPLEMENTING PROCEDURES. Volume 3AUpdated Tables of ContentsEP R-1,Revision 14EP R-6, Revision 8EP M-6, Revision 10EP G-1, Revision 5EP G-2, Revision 5Volume BUpdated Table o...

Application for amends to Licenses NPF-9 & NPF-17,revising Tech Specs re plant operating limitations affected by use of optimized fuel assembly designs.Fee paid.Marked-up Tech Specs encl.

,DDume POWER GOMPANYP.O. IBOX Wit *49MN. N.c. 28g4;!HAL 3. TtJCMENTER EP980MEmmaanNovember 16, 1984 == ==== -Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D. C.20555Attention: Ms. E. G. Adensam, ChiefLicensing ...

"Final Rept:Shallow,High-Resolution Seismic Profiling of Five Georgia River Localities." Viewgraphs of 820914 presentation on postulated millet fault encl.

. - __ - _ _. . . ,--. L ij ,8'.5,y.... . .... .RECEIVED.AUG W32Gart,. .FINAL REPORT: SHALLOW, HIGH-RESOLUTIONSEISMIC PROFILING OF FIVE. GEORGIA RIVER LOCALITIES( d., Uu & letv: A.S' '$Ea d. :0-CM,& , [ &.t.,M n-&*"h9 1to .iThe Earth and Water Divisionof theGeorgia Department ...

State of CA Dept of Water Resources suppl to 771121 answers to first set of interrogatories,amended 780331. Organizational charts of Dept of Water Resources attached in reply.Certificate of Svc encl.

iQ f f';>f {$|*m9DOCKETED \\USNRC m -,9-FEB 191999 > y; UNITED STATES OF AMERICA.NUCLEAR REGULATORY COMMISSION" ''Office of the SecretaryD:Le:ing & senjeeqBranchIBEFORE_ THE_ ATOMIC SAFETY AND LICENSING BOA Co,ii-In the Matter of:));PACIPIC GAS AND ELECTRIC) NRC Docke t No. P-...