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| {{#Wiki_filter:ACCELERATED DISRIBUTIONDEMONSTTIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9010050242 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DIS RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9010050242 DOC.DATE: 90/09/20 NOTARIZED: |
| 90/09/20NOTARIZED: | | NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. |
| NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
| Rochester Gas6ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. | | Project Directorate I-3 DOCKET 05000244 |
| ProjectDirectorate I-3DOCKET05000244
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|
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsDesignAnalysis4525-1,"FaultCurrentAnalysisforPowerDistribution Sys,"Rev1&DesignAnalysis4525-2.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR
| | Forwards Design Analysis 4525-1,"Fault Current Analysis for Power Distribution Sys," Rev 1&Design Analysis 4525-2.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR |
| $ENCL$SIZE:TITLE:ORSubmittal: | | $ENCL$SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| 05000244RECIPIENT IDCODE/NAME PDl-3LAJOHNSON,A INTERNAL:
| | 05000244 RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1'1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E G FILE Ol NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| NRR/DET/ECMB 9HNRR/DST8E2NRR/DST/SICB 7ENUDOCS-ABSTRACT OGC/HDS2RES/DSIR/EIB EXTERNAL: | | PLEASE HELP US TO REDUCE iVASK!CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15 |
| NRCPDRCOPIESLTTRENCL11221111111'101111RECIPIENT IDCODE/NAME PD1-3PDNRR/DOEA/OTSB11 NRR/DST/SELB 8DNRR/DST/SRXB 8EGFILEOlNSICCOPIESLTTRENCL11111111101111NOTETOALL"RIDS"RECIPIENTS:
| |
| PLEASEHELPUSTOREDUCEiVASK!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR17ENCL15
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| \f$a IIIIIIIIIII/ | | \f$a IIIIIIIIIII/ |
| IIIIIIIIIIII | | IIIIIIIIIIII |
| ~AirOall*///IjI//Ij/I//III/III g!p',ROCHESTER GASANDELECTRICCORPORATION o89EASTAVENUE,ROCHESTER N.Y.14649-0001 ROBERTC.MECREDYVicePresident CinnaNuctearProduction September 20,1990TEt.EPHONE ArtEAcooE7re546.2700U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-3Washington, D.C.20555 | | ~Air Oal l*///Ij I//Ij/I//III/III g!p', ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C.MECREDY Vice President Cinna Nuctear Production September 20, 1990 TEt.EPHONE ArtEA cooE 7 re 546.2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555 |
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| ==Subject:== | | ==Subject:== |
| OffsitePowerSystemAnalysesR.E.GinnaNuclearPowerPlantDocketNo.50-244
| | Offsite Power System Analyses R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==DearMr.Johnson:== | | ==Dear Mr.Johnson:== |
| Peryourrequest,weareenclosing copiesofDesignAnalysis4525-1"FaultCurrentAnalysisofPowerDistribution System"Rev1andDesignAnalysis4525-2"Adequacy ofElectricSystemVoltages" Rev1foryourreview.Theseanalysesquantifytheeffectsassociated withtherecentlycompleted offsitepowerreconfiguration (EWR'4525).EWR4525modifiedtheoffsitepowersystemsuchthattherewouldbeadedicated 34.5/4.16kV transformer associated witheachofthetwoindependent offsitetransmission lines.Station204energizes transformer 12AwhichisnowthenormalsourceofpowerforBus12AandsafetytrainAwhileStation13Aenergizes transformer 12BwhichisnowthenormalsourceofpowerforBus12BandsafetytrainB(seefigure1).Thisnormalconfiguration isreferredtoasthe50/50modesinceeachindependent offsitepowersourcesupplies1/2oftherequiredoffsitepower.Theoperators stillhavetheabilitytoputtheoffsitepowersystemineitherthe100/0mode(Transformer 12Bsuppliesalloffsitepower)orthe0/100mode(Transformer 12Asuppliesalloftheoffsitepower).Thenormalconfiguration priortoEWR4525wastohavealloffsitepowersuppliedbytransformer 12A.EWR4525hassignificantly reducedthelikelihood ofasimultaneous lossofoffsitepowertobothsafetytrainsandhasimprovedsystemperformance sincetheelectrical loadisnownormallydividedbetweentwotransformers.
| | Per your request, we are enclosing copies of Design Analysis 4525-1"Fault Current Analysis of Power Distribution System" Rev 1 and Design Analysis 4525-2"Adequacy of Electric System Voltages" Rev 1 for your review.These analyses quantify the effects associated with the recently completed offsite power reconfiguration (EWR'4525).EWR 4525 modified the offsite power system such that there would be a dedicated 34.5/4.16kV transformer associated with each of the two independent offsite transmission lines.Station 204 energizes transformer 12A which is now the normal source of power for Bus 12A and safety train A while Station 13A energizes transformer 12B which is now the normal source of power for Bus 12B and safety train B (see figure 1).This normal configuration is referred to as the 50/50 mode since each independent offsite power source supplies 1/2 of the required offsite power.The operators still have the ability to put the offsite power system in either the 100/0 mode (Transformer 12B supplies all offsite power)or the 0/100 mode (Transformer 12A supplies all of the offsite power).The normal configuration prior to EWR 4525 was to have all offsite power supplied by transformer 12A.EWR 4525 has significantly reduced the likelihood of a simultaneous loss of offsite power to both safety trains and has improved system performance since the electrical load is now normally divided between two transformers. |
| Theprimaryobjective ofDesignAnalysis4525-2istodemonstrate thatthereconfigured offsitepowersupplywillbecapableofmaintaining adequatevoltagesforallrequiredoperating conditions.
| | The primary objective of Design Analysis 4525-2 is to demonstrate that the reconfigured offsite power supply will be capable of maintaining adequate voltages for all required operating conditions. |
| Theresultsindicated thatbothoffsitesourcesr5'ot0050242 9005'20PDR4DOCK05000244PPDCgooI Il'IF"~A,4'3 (circuit751fromStation204&767fromStation13A)arecapableofproviding adequatevoltagesforallrequiredfunctions.
| | The results indicated that both offsite sources r 5'ot0050242 9005'20 PDR 4DOCK 05000244 P PDC goo I I l'I F"~A,4'3 (circuit 751 from Station 204&767 from Station 13A)are capable of providing adequate voltages for all required functions. |
| Twospecialcasesarediscussed belowwhichrepresent thelimitingcases:1.Thecomputersimulations indicated thatbothoffsitesourcesmayhavedifficulty inmaintaining adequatevoltagesduringthestartupofaReactorCoolantPump(RCP)forthespecialcasewhentheoffsitegridvoltagewasatitsminimumvalue(33kvforcircuit751and116kvforcircuit767).Thisissueiscurrently beingaddressed bymodifying theRCPnormalstartprocedures.
| | Two special cases are discussed below which represent the limiting cases: 1.The computer simulations indicated that both offsite sources may have difficulty in maintaining adequate voltages during the startup of a Reactor Coolant Pump (RCP)for the special case when the of f site grid voltage was at its minimum value (33 kv f or circuit 751 and 116 kv for circuit 767).This issue is currently being addressed by modifying the RCP normal start procedures. |
| Theoperators havebeeninstructed toverifythatadequateprestartvoltagesexistpriortoattempting anRCPstart.Wehavecalculated circuit767mayalsohaveasimilarproblemwhenattempting aSteamGenerator Feedwater Pump(SGFWP)Start.Thiscomputeranalysisiscurrently beingreevaluated todetermine ifanyexcessive conservatism ispresentintheanalysisandifrequired, theSGFWPstartprocedure willalsobemodified.
| | The operators have been instructed to verify that adequate prestart voltages exist prior to attempting an RCP start.We have calculated circuit 767 may also have a similar problem when attempting a Steam Generator Feedwater Pump (SGFWP)Start.This computer analysis is currently being reevaluated to determine if any excessive conservatism is present in the analysis and if required, the SGFWP start procedure will also be modified.It should be noted that Circuit 767 has not had any difficulty to date in starting either the RCP or the SGFWP.2.The worst case Loss of Coolant Accident (LOCA)simulation assumes two degraded operating conditions: |
| ItshouldbenotedthatCircuit767hasnothadanydifficulty todateinstartingeithertheRCPortheSGFWP.2.TheworstcaseLossofCoolantAccident(LOCA)simulation assumestwodegradedoperating conditions:
| | operating solely on line 767, (100/0 mode), and a min'imum grid voltage (116kv).The results show all bus voltages above 414 volts, indicating that all of the 1E pump motors will operate and that the undervoltage relaying on these busses will not disconnect them from offsite power.However, the lowest 480 volt MCC voltage was 405 volts, which is lower than RG&E's acceptance criteria.The only loads on the MCCs required to mitigate this accident would be MOVs.We believe that the MOVs will operate properly at this voltage, however, to provide greater assurance we have revised our operating limits to which the offsite grid, voltages will be controlled when safeguards equipment is required.When the offsite supply is provided in the 100/0 mode (767 is the lone source)the grid voltage will be maintained no lower than 118 kv.A simulation has been run at this voltage which provided results within all acceptance criteria.Historical data demonstrates that the grid voltage is at least 118 kv over 95%of the time.For the normal operating mode, in the 50/50 configuration, the simulation results show that all of the voltages are within the established criteria, even at the minimum grid voltage of 116 kv.It should be noted that this potential low voltage condition was not created by the reconfiguration of the offsite power system and in fact, the likelihood of the condition occurring was signifi-cantly reduced.The ability to run the offsite power system in the 50/50 mode was a major objective of the power system reconfigura-tion project (EWR 4525).It should also be noted that the most severe LOCA simulation for circuit 751 (0/100 mode and minimum source voltage 33kv)resulted in acceptable voltages. |
| operating solelyonline767,(100/0mode),andamin'imumgridvoltage(116kv).Theresultsshowallbusvoltagesabove414volts,indicating thatallofthe1Epumpmotorswilloperateandthattheundervoltage relayingonthesebusseswillnotdisconnect themfromoffsitepower.However,thelowest480voltMCCvoltagewas405volts,whichislowerthanRG&E'sacceptance criteria. | | The primary objective of Design Analysis 4525-1 was to verify that the reconfiguration of the offsite power system did not result in excessive short circuit duties for either the new or existing equipment. |
| TheonlyloadsontheMCCsrequiredtomitigatethisaccidentwouldbeMOVs.WebelievethattheMOVswilloperateproperlyatthisvoltage,however,toprovidegreaterassurance wehaverevisedouroperating limitstowhichtheoffsitegrid,voltageswillbecontrolled whensafeguards equipment isrequired.
| | The results indicated. |
| Whentheoffsitesupplyisprovidedinthe100/0mode(767isthelonesource)thegridvoltagewillbemaintained nolowerthan118kv.Asimulation hasbeenrunatthisvoltagewhichprovidedresultswithinallacceptance criteria.
| | that the reconfiguration had a negligible impact on the short circuit duties for the existing'quipment and that all of the new equipment was specified with short circuit ratings well in excess of the calculated duties.The existing equipment was found to have adequate short circuit capacity for all cases except for one case of diesel generator testing, discussed below: A special case involving the diesel generator when it is in its monthly test configuration was computer simulated and it was determined. |
| Historical datademonstrates thatthegridvoltageisatleast118kvover95%ofthetime.Forthenormaloperating mode,inthe50/50configuration, thesimulation resultsshowthatallofthevoltagesarewithintheestablished | | that potential short circuit duties could exceed acceptable limits.This is a low probability event requiring a phase-to-phase fault occurrence during a two hour test period.The consequence of such an event is an economic concern only, not a safety issue.The event could result in a shutdown of the plant for repairs.Safeguard system redundancy could be reduced, however, the event would not require the use of the safeguards system for plant shutdown.This condition was not created.by the reconfiguration of the offsite power system and various alternatives to resolve this issue are currently being evaluated. |
| : criteria, evenattheminimumgridvoltageof116kv.Itshouldbenotedthatthispotential lowvoltagecondition wasnotcreatedbythereconfiguration oftheoffsitepowersystemandinfact,thelikelihood ofthecondition occurring wassignifi-cantlyreduced.Theabilitytoruntheoffsitepowersysteminthe50/50modewasamajorobjective ofthepowersystemreconfigura-tionproject(EWR4525).ItshouldalsobenotedthatthemostsevereLOCAsimulation forcircuit751(0/100modeandminimumsourcevoltage33kv)resultedinacceptable voltages.
| | We expect to be able to inform you of our intended corrective action by October 30, 1990.Very truly yours, Robert C.Mecre THM/122 Att'achments xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector |
| Theprimaryobjective ofDesignAnalysis4525-1wastoverifythatthereconfiguration oftheoffsitepowersystemdidnotresultinexcessive shortcircuitdutiesforeithertheneworexistingequipment.
| | ~~~OI=I=SITE DISTRIBUTION SYSTEM EV/R 4525 SIA I jA SIA.204 TO CSU TRAIISfOIII If ft 52 I 2II~I 12IIX tie 12BY NO 12A E Y 12AX 52 NO 12AY NC 52 52 ftEMOVAQLE Llt IK TO VI GEtIERA)OR DUMMY BREAKER DUMMY BREAKER 52 52 52 52 52 5)52 IO SIA.TO STA.SI RV.SLRV.1ftAtIS.IRArIS.lI I 7 pl 6'..Al I IY fRAltl-Il-TO STA.SE RV.TRAtIS.g 15 TO STA.SERV.TRAtlS.(IS TO STA.TO SIA.SERV.SERV.TRAtlS.TRAtIS.pl 4 glS SAF CiY TRAltl"A"}} |
| Theresultsindicated.
| |
| thatthereconfiguration hadanegligible impactontheshortcircuitdutiesfortheexisting'quipment andthatallofthenewequipment wasspecified withshortcircuitratingswellinexcessofthecalculated duties.Theexistingequipment wasfoundtohaveadequateshortcircuitcapacityforallcasesexceptforonecaseofdieselgenerator testing,discussed below:Aspecialcaseinvolving thedieselgenerator whenitisinitsmonthlytestconfiguration wascomputersimulated anditwasdetermined.
| |
| thatpotential shortcircuitdutiescouldexceedacceptable limits.Thisisalowprobability eventrequiring aphase-to-phase faultoccurrence duringatwohourtestperiod.Theconsequence ofsuchaneventisaneconomicconcernonly,notasafetyissue.Theeventcouldresultinashutdownoftheplantforrepairs.Safeguard systemredundancy couldbereduced,however,theeventwouldnotrequiretheuseofthesafeguards systemforplantshutdown.
| |
| Thiscondition wasnotcreated.bythereconfiguration oftheoffsitepowersystemandvariousalternatives toresolvethisissuearecurrently beingevaluated.
| |
| Weexpecttobeabletoinformyouofourintendedcorrective actionbyOctober30,1990.Verytrulyyours,RobertC.MecreTHM/122Att'achments xc:Mr.AllenR.Johnson(MailStop14D1)ProjectDirectorate I-3Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector
| |
| ~~~OI=I=SITE DISTRIBUTION SYSTEMEV/R4525SIAIjASIA.204TOCSUTRAIISfOIII Ifft52I2II~I12IIXtie12BYNO12AEY12AX52NO12AYNC5252ftEMOVAQLE LltIKTOVIGEtIERA)OR DUMMYBREAKERDUMMYBREAKER52525252525)52IOSIA.TOSTA.SIRV.SLRV.1ftAtIS.IRArIS.lII7pl6'..AlIIYfRAltl-Il-TOSTA.SERV.TRAtIS.g15TOSTA.SERV.TRAtlS.(ISTOSTA.TOSIA.SERV.SERV.TRAtlS.TRAtIS.pl4glSSAFCiYTRAltl"A"}} | |
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Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
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ACCELERATED DIS RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9010050242 DOC.DATE: 90/09/20 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET 05000244
SUBJECT:
Forwards Design Analysis 4525-1,"Fault Current Analysis for Power Distribution Sys," Rev 1&Design Analysis 4525-2.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR
$ENCL$SIZE: TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1'1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E G FILE Ol NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASK!CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15
\f$a IIIIIIIIIII/
IIIIIIIIIIII
~Air Oal l*///Ij I//Ij/I//III/III g!p', ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C.MECREDY Vice President Cinna Nuctear Production September 20, 1990 TEt.EPHONE ArtEA cooE 7 re 546.2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555
Subject:
Offsite Power System Analyses R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Johnson:
Per your request, we are enclosing copies of Design Analysis 4525-1"Fault Current Analysis of Power Distribution System" Rev 1 and Design Analysis 4525-2"Adequacy of Electric System Voltages" Rev 1 for your review.These analyses quantify the effects associated with the recently completed offsite power reconfiguration (EWR'4525).EWR 4525 modified the offsite power system such that there would be a dedicated 34.5/4.16kV transformer associated with each of the two independent offsite transmission lines.Station 204 energizes transformer 12A which is now the normal source of power for Bus 12A and safety train A while Station 13A energizes transformer 12B which is now the normal source of power for Bus 12B and safety train B (see figure 1).This normal configuration is referred to as the 50/50 mode since each independent offsite power source supplies 1/2 of the required offsite power.The operators still have the ability to put the offsite power system in either the 100/0 mode (Transformer 12B supplies all offsite power)or the 0/100 mode (Transformer 12A supplies all of the offsite power).The normal configuration prior to EWR 4525 was to have all offsite power supplied by transformer 12A.EWR 4525 has significantly reduced the likelihood of a simultaneous loss of offsite power to both safety trains and has improved system performance since the electrical load is now normally divided between two transformers.
The primary objective of Design Analysis 4525-2 is to demonstrate that the reconfigured offsite power supply will be capable of maintaining adequate voltages for all required operating conditions.
The results indicated that both offsite sources r 5'ot0050242 9005'20 PDR 4DOCK 05000244 P PDC goo I I l'I F"~A,4'3 (circuit 751 from Station 204&767 from Station 13A)are capable of providing adequate voltages for all required functions.
Two special cases are discussed below which represent the limiting cases: 1.The computer simulations indicated that both offsite sources may have difficulty in maintaining adequate voltages during the startup of a Reactor Coolant Pump (RCP)for the special case when the of f site grid voltage was at its minimum value (33 kv f or circuit 751 and 116 kv for circuit 767).This issue is currently being addressed by modifying the RCP normal start procedures.
The operators have been instructed to verify that adequate prestart voltages exist prior to attempting an RCP start.We have calculated circuit 767 may also have a similar problem when attempting a Steam Generator Feedwater Pump (SGFWP)Start.This computer analysis is currently being reevaluated to determine if any excessive conservatism is present in the analysis and if required, the SGFWP start procedure will also be modified.It should be noted that Circuit 767 has not had any difficulty to date in starting either the RCP or the SGFWP.2.The worst case Loss of Coolant Accident (LOCA)simulation assumes two degraded operating conditions:
operating solely on line 767, (100/0 mode), and a min'imum grid voltage (116kv).The results show all bus voltages above 414 volts, indicating that all of the 1E pump motors will operate and that the undervoltage relaying on these busses will not disconnect them from offsite power.However, the lowest 480 volt MCC voltage was 405 volts, which is lower than RG&E's acceptance criteria.The only loads on the MCCs required to mitigate this accident would be MOVs.We believe that the MOVs will operate properly at this voltage, however, to provide greater assurance we have revised our operating limits to which the offsite grid, voltages will be controlled when safeguards equipment is required.When the offsite supply is provided in the 100/0 mode (767 is the lone source)the grid voltage will be maintained no lower than 118 kv.A simulation has been run at this voltage which provided results within all acceptance criteria.Historical data demonstrates that the grid voltage is at least 118 kv over 95%of the time.For the normal operating mode, in the 50/50 configuration, the simulation results show that all of the voltages are within the established criteria, even at the minimum grid voltage of 116 kv.It should be noted that this potential low voltage condition was not created by the reconfiguration of the offsite power system and in fact, the likelihood of the condition occurring was signifi-cantly reduced.The ability to run the offsite power system in the 50/50 mode was a major objective of the power system reconfigura-tion project (EWR 4525).It should also be noted that the most severe LOCA simulation for circuit 751 (0/100 mode and minimum source voltage 33kv)resulted in acceptable voltages.
The primary objective of Design Analysis 4525-1 was to verify that the reconfiguration of the offsite power system did not result in excessive short circuit duties for either the new or existing equipment.
The results indicated.
that the reconfiguration had a negligible impact on the short circuit duties for the existing'quipment and that all of the new equipment was specified with short circuit ratings well in excess of the calculated duties.The existing equipment was found to have adequate short circuit capacity for all cases except for one case of diesel generator testing, discussed below: A special case involving the diesel generator when it is in its monthly test configuration was computer simulated and it was determined.
that potential short circuit duties could exceed acceptable limits.This is a low probability event requiring a phase-to-phase fault occurrence during a two hour test period.The consequence of such an event is an economic concern only, not a safety issue.The event could result in a shutdown of the plant for repairs.Safeguard system redundancy could be reduced, however, the event would not require the use of the safeguards system for plant shutdown.This condition was not created.by the reconfiguration of the offsite power system and various alternatives to resolve this issue are currently being evaluated.
We expect to be able to inform you of our intended corrective action by October 30, 1990.Very truly yours, Robert C.Mecre THM/122 Att'achments xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
~~~OI=I=SITE DISTRIBUTION SYSTEM EV/R 4525 SIA I jA SIA.204 TO CSU TRAIISfOIII If ft 52 I 2II~I 12IIX tie 12BY NO 12A E Y 12AX 52 NO 12AY NC 52 52 ftEMOVAQLE Llt IK TO VI GEtIERA)OR DUMMY BREAKER DUMMY BREAKER 52 52 52 52 52 5)52 IO SIA.TO STA.SI RV.SLRV.1ftAtIS.IRArIS.lI I 7 pl 6'..Al I IY fRAltl-Il-TO STA.SE RV.TRAtIS.g 15 TO STA.SERV.TRAtlS.(IS TO STA.TO SIA.SERV.SERV.TRAtlS.TRAtIS.pl 4 glS SAF CiY TRAltl"A"
