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DOE Presentation, "Savannah River Site Salt Waste Disposal NRC Onsite Observation Visit January 25", 2017 SRR-CWDA-2017-00007, Revision 1.

1SAVANNAH RIVER SITE • AIKEN, SC • www.SRRemediation.comWe do the right thing.SAVANNAH RIVER SITE • AIKEN, SC • www.SRRemediation.comSAVANNAH RIVER SITE SALT WASTE DISPOSALNRC ONSITE OBSERVATION VISITJANUARY 25, 2017Waste Disposal AuthoritySRR-CWDA-2017-00007, Revision 12SAVAN...

Memorandum - Issuance of the External Review Board Summary Documents as Required under Sub-Task 1.3 of User Need Request NRR-2014-004.

December 1, 2017 . MEMORANDUM TO: David W. Alley, Chief Piping and Head Penetration Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation Steve R. Ruffin, Chief (A) Vessels and Internals Branch Division of Materials and License R...

LER 87-010-00:on 870512,ESF actuations occurred.Caused by inadequate plant procedure.Plant operators restarted reactor protection sys motor generator A & returned RHR shutdown cooling & RWCU sys to operation within 1/2 h.W/870611 ltr.

ACCESSION NHRFAG IL: 50-397~iJTH. NANEWASHINGTON> SPOWERS> C. N.RECIP. NANEREG T'NFORNATION DISTR IHU ON YSTEN (R IDB >8706190065 DOC. DATE: 87/06/li NOTARIZED: NQMPPSB Nuclear Prospect>Unit 2, WashingtonPublic PoweAUTHOR AFFILIATIONL. Washington Public Power SupplySystemWashi...

Regulatory Audit Plan for November 28-30, 2017, Safety System Digital Platform MELTAC [Mitsubishi Electric Total Advanced Controller] Topical Report Revision 0.

September 27, 2017 Mr. Gilbert W. Remley Nuclear Systems Department Manager Mitsubishi Electric Power Products, Inc. 547 Keystone Drive Warrendale, PA 15086 SUBJECT: REGULATORY AUDIT PLAN FOR NOVEMBER 28-30, 2017, “SAFETY SYSTEM DIGITAL PLATFORM – MELTAC [MITSUBISHI ELE...

Audit Plan for Review of Probabilistic Risk Assessment, Severe Accident Evaluation and Reliability Assurance Program as Part of the NuScale Power, LLC Design Control Document Design Certification.

1 U.S. NUCLEAR REGULATORY COMMISSION REGULATORY AUDIT OF PROBABILISTIC RISK ASSESSMENT, SEVERE ACCIDENT EVALUATION, AND RELIABILITY ASSURANCE PROGRAM AS PART OF THE NUSCALE POWER, LLC DESIGN CONTROL DOCUMENT DESIGN CERTIFICATION DOCKET NO. 52-048 AUDIT PLAN APPLICANT: Nu...

Responds to NRC 900713 ltr re violations noted in Insp Rept 50-323/90-13.Corrective actions:maint procedure will be developed for installation & maint of Woodward governor for auxiliary feedwater pump speed control.

Pacific Gas and Electric Company 77 Beate StreetSan Francisco CA 94106415I973-4684TWX 910-372-6587'IO'p)pA<~James D. ShifterSenior Vice President andGeneral tAanager.tfuctear Pcv;er GenerationAugust 13, 1990PGEE Letter No. DCL-90-204U.S. Nuclear Regulatory CommissionATTN: Docu...

Comment (2) from Lauren Stewart Regarding Regulatory Improvements for Power Reactors Transitioning to Decommissioning.

PUBLIC SUBMISSIONAs of: 5/1/17 8:20 AMReceived: April 30, 2017Status: Pending_PostTracking No. 1k1-8w4p-9iqgComments Due: June 13, 2017Submission Type: WebDocket: NRC-2015-0070Regulatory Improvements for Power Reactors Transitioning to DecommissioningComment On: NRC-2015-0070-...

Responds to GL 89-10,Suppl 5, "Inaccuracy of MOV Diagnostic Equipment."

- . - .i'',',.]..t, ;LF CREEKWe) NUCLEAR OPERATING CORPORATION|14Forrest T. RhodesSeptember 29* 1993iVice Pruident EnginwnngET 93-0111-U. S. Nuclear. Regulatory CommissionATTN: Document Control DeskMail Station P1-137!Washington, D. C. 20555?!Reference: NRC letter dated June 2...

LER 90-018-00:on 900705,reactor trip w/turbine trip occurred.Caused by contact closure of electrohydraulic control oil pressure switches satisfying two out of three logic.Pressure switches relocated.W/900803 ltr.

-7+,,.,. . +5h OI #;,p. .,.e>.SNew;Hompshire'a' Ted C. Feigenboum :p. P7Senior Vice Presidsnt and,iChief Operatino Officer 1y,y; .',ii s 1>.|NYN 90150t9- August 3,1990 .j.j-m,'1). United States Nuclear Regulatory Commission"g. Washington, D, C. 20555, nk61#' Attention:- ' Docu...

LER 95-002-00:on 950226,SG pressures lowered & SG water level began to increase,reaching high-high setpoint & initiated automatic FW isolation.Caused by leak-by on SG. Limit switches properly set.W/950317 ltr.

',. . . - -%6 ,'; ! . 3 sw1_/ Georgia Power Company - M ~i *Tc s-_._..40 invemess Center Parkway~' "*- -Post Offce Box 1295-W'"Birmingham. Alabama 35201 -Telephone 205 877 7122 '-'i**. Georgia Power. C. K. McCoyVce President. NuclearVogne Pro 3ectthe southern electrc System-Ma...

Response to staff 840315 interrogatories re Eddleman 11 & 116.Documents will be provided for insp & copying where identified & not in possession of NRC.Certificate of Svc encl.Related correspondence.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ __ _ _ - _ _ _ _ _; -.7"%)3-($7' EuTED CORRESPONDENTUAnril 19, 198hUNITED STATES OF AMERICADOCKETEDU990NUCLEAR BEGULATORY COMMISSIONi'84 APR 25 A10:21BEFORE THE ATOMIC SAFETY AND LICENSING BOAEDGlenn O. Bright[g...

LER 91-026-00:on 910727,actuations occurred on primary containment isolation sys when 4 KV emergency bus transferred to startup feed.Caused by Phase B arcing. Isolations reset & disconnect repaired.W/910826 ltr.

._ . . - . _ . _ _ . _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ . . . _ _ . _ . _ . _ _ , _ _ _ _ .%ecell 91-141.% .4.(ie#f)\ \ e*%)'l'illt.AI)lti,l'lil A !!!.f:CTitlC COSil%NYitN;)/i.,unnorn,u,nsm imiinunosit n i ibisaos4% ),n# i k lu. h nuo lunu l'34nu u wnm-wi mm or i u e niv api'i ...

Monthly operating rept for May 1995 for Three Mile Island Nuclear Station.W/950612 ltr.

+a , .<.p.GPU Nuclear Corporation.Nhh hfP.O. Box 480Route 441 South. .:Middletown, Pennsylvania 17057-0480(717)944-7621Writer's Direct Dial Number:(717) 948-8005June 12,1995C311-95-2269U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555Gentleme...

AO 50-219/74/39:on 740714,electromatic relief valve pressure switches IA83A,B,C & E found to trip at pressures in excess of max allowable value of 1070 psig.Caused by setpoint repeatability.Switches reset.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.. .eN,:.Oo- VF& y.,...,q%..%W/ pJ r f4 #..eq2hI " .,.,, [',^ bp :%A'lQ,)To:James P. O'ReillyDirectorate of Regulatory Operations -r-Region I%..@|f*';D,/ ''-x\lY631 Park AvenueKing of Prussia, Pennsylvania 19406b8I Y.',, . < ,s.-,/From:Jersey C...

Responds to IE Bulletin 83-06 re nonconforming matl supplied by Tube-Line Corp.Subj matls used in important-to-safety sys.Flanges in augmented fuel pool cooling sys installed by Capital Pipe affected.Flanges determined adequate.

F-.. .*.GPU Nuclear CorporationNuclearm'en=388,nf orked River,New Jersey 08731-0388609 971-4000Writer's Direct DialNumber:November 23, 1983Dr. Thomas E. Murley, AdministratorRegion iU.S. Nuclear Regulatory Commission631 Park AvenueKing of Prussia, PA 19406Dear Dr. Murley:Subje...

Forwards revised JCO that bounds reactor core designs w/ U-236 average enrichments less than 4.5%,as requested in NRC 931130 ltr.This includes Unit 2 Cycle 6,Unit 1 Cycle 7 & Unit 2 Cycle 7 fuel cycles.

. e , , .-. - ,. _ .~ . . g; 9'4HA--- - -. - - - . - -Tennem va, Aumomy em o%e tu nema, tam tre,eme anaMarch 4, 1994U.S. Nucicar Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555Gentlemen:In the Matter of )Docket Nos. 50-327Tennessee Valley Authority )50-3...

Forwards revised response to matls selection portion of Open Item F1.9-1.

.,~'GE Nuclear Energy,m. ,.p - ...-.a4,=w..~ni- .Ilb (u"..f! J'WV!T;16 Y}!) b4? [N .?tlh 5March 10,1994 Docket No. 52-001I"Chet Poslusny, Senior Proj,ect ManagerStandardization Project DirectorateAssociate Directorate for Advanced Reactorsand License Renewal ;Office of the Nuc...

Notification of completion of requirements of GL 89-10, "Safety-Related Motor-Operated Valve Testing & Surveillance."

- - .- -Q ...The Lightc o mp a ny South Tesas Project 1.lectrk Generating StationP. O. Itos 289 Wadm orth. 'l e sas 774 81lloustosi tightitig A PowerST-HL-AE-4827File No. G03.0810CFA50.54(f)June 28, 1994U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashingt...

LER 91-001-00:on 910122,containment ventilation isolation actuation occurred while plant in third refueling outage. Caused by spurious actuation of radiation monitoring sys. Training bulletin issued re event.W/910221 ltr.

,._ .. - - - . -.- -- .- _- .,...-.:'The Light-companyI'O. Itox 1700 llouston ' lex.a 77001 (71:1) ""8 Wilflouston 1.ighting A: PowcrFebruary 21 1^91ST '.it- Af 3698File No.* G2610CFR50.73U. S. Nuclear Regulatory CommissionAttention: Document Control DeskVashington, DC 20$55So...

Westinghouse Completion of Confirmatory Order Commitments Under EA-16-173

Westinghouse Non-Proprietary Class 3 (9 Westinghouse Director, Office of Enforcement U.S. Nuclear Regulatory Commission Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-000 I Westinghouse Electric Company LLC Columbia Fuel Site 5801 Bluff Rd Hopkin...

LER 90-003-00:on 900320,containment purge isolation signal & control room ventilation isolation signal generated after initiation of containment vent.Caused by localized accumulation of gaseous activity.W/900419 ltr.

,...s: ...WQ4.F CREEK'NUCLEAR OPERATING CORPORATIONJohn A. BeneyVice ProeisontNucteer OperationsApril 19, 1990NO 90-0126U. S Nuclear Regulatory ConunissionATTH: Document Control DeskMail Station P1-137Washington, D. C. 20555Subject: Docket No. 50-482: Licensee Event Report 90-...

LER#78-044/03L-0 on 781214:during 1978 refueling outage, certain surveillance tests req by Tech Specs could not be performed because of shutdown condition.Facil Lic Change #77-11 submitted to NRC on 781109 to delete requirements.

. ._. - - - - - _ .tmLICENSEE EVENT REPORT.*e@tri. EASE PRINT GQ TYPE ALL REQUIRED INFOKMATItN) lCON 7act BLOCx: 11 I I I Ii'oit| |*I I" IF |C IS 11 l@| o I O I O I O lo Io lo lo In lo In l@lhI1|11111l@lsa7$d@I ]4 s ucassas cessi* *$WGEN44N4MHm:$ :S WOEN$t Tvel 4J57*'*0,"[l L ...

Proposed Tech Specs re RCS flow rate & nuclear enthalpy rise hot channel factor measurement.

Cb*.,.Attachment 3Technical Specification 3/4.2.3 - RCS Flowrate and Nucicar Enthalpy RiseHot Channel FactorProposed Change*Revise Specification 3.2.3.e and Figure 3.2-3 to reduce the measurementuncertainty for total RCS flow.This results in a decrease in the minimumRCS flow f...

Responds to violations noted in Insp Rept 50-382/91-17 & Enforcement Action 91-069.Corrective actions:event will be discussed,on recurring basis,w/personnel prior to each refueling outage work.

. . . . .. .... . .. - . - - . - - . _ _ . _ _ _ _ _ . _ _ _ _ _ . _ _ . _ _ . _ _*M Entergy Operations,Inc.==~ ENTERGY.t*i4_ _ _ - . _ _ _ _ _ . _ _ , . _ . _ _ _ _ _ _ _ - _ . - _ _ . . - - ~ _ ~ . _ . _ _ _ _ _ _ . . _ _ _ _ . _ _ - ._.R. F. DurskiW3F1-91-0370A 1. 05QAJuly ...

Forwards signed response to Tracked Info Items 045 & 050 re Q-interface const work permits.

",, .CONSUMERS POWER COMPANYSo-35i xIDtinD EnERcr CEurER$O'.- g'Transmittal No:CEC- 7285Date: February 6, 1984To: Stone & WebsterP O Box 1963Midland, MI 48640j| r . n_n i PM. . ST f F F-; _,;._! _ _ . . : -_ F -_ 'l _ l . . _ ._. L -.Attached Is:_Partial Response To]!i_i.. . ....