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{{#Wiki_filter:NRCronM195I2.7B)V.S.NUCLFARREGULATOR
{{#Wiki_filter:NRC ronM 195 I2.7B)V.S.NUCLFAR REGULATOR.IMISSION DOC~+T NUMBER+O-QQ,C)NRC DISTRIBUTION roR PART 50 D+r KFT MATERIAL I ILE NUMBER TO: MR K R GOLLER LETTER+ORIGINAL QCOPV ONOTORIZED g VNC LASS IF I E D FEIDM: NIAGARA MOHAWK POWER CORP SYRACUSE, NY G K RHODE INPUT FORM DATE OF DOCUMENT D*T>R>c>lv.D>1 (NUMBER OF COPIES RECEIVED DESCRIPTION LTR RE OUR 5-6-76 LTR"-TRANS'HE FOLLOWRlo.......
.IMISSION DOC~+TNUMBER+O-QQ,C)NRCDISTRIBUTION roRPART50D+rKFTMATERIALIILENUMBERTO:MRKRGOLLERLETTER+ORIGINAL QCOPVONOTORIZED gVNCLASSIFIEDFEIDM:NIAGARAMOHAWKPOWERCORPSYRACUSE, NYGKRHODEINPUTFORMDATEOFDOCUMENTD*T>R>c>lv.D>1(NUMBEROFCOPIESRECEIVEDDESCRIPTION LTRREOUR5-6-76LTR"-TRANS'HE FOLLOWRlo.......
F.NCLOSURE RESPONSES TO APRIL 6p 1976 NRC QUEST10NS......
F.NCLOSURE RESPONSES TOAPRIL6p1976NRCQUEST10NS......
l IDONOT RZMPVZ>>~sT~>>>.:kX,~~,~iI>e, v 4.<ACKNOWLZDgZD SAX>>TY ASSIGNED AD: BRANCH CHIEF: PROJECT IMAGER: LIC.ASST.: Q<nii FOR AC1 ION/INFORMATION ASSXGNED AD: BRANCH CHXEF: PRO JECT MANAGER: LIC.ASST.: REG FILE ICE OELD GOSSICK 5 STAFF lHPC CASE EEANAUER Hr,l".s T MANAGEMENT P COLLINS 1iOUSTON PL7HHSON FED'/EEI"LTEMES SKOV HOLT LPDR: DSM~+3)~'1'Tr,'NSIO ASLB>>cns II nor,>>1;>ia s>>>>>>INTERNAL D SYSTEI43 S!~w..EEEX NEIMAN SCHHOEDER ENGINEERING KNIGEIT PAWLXCKX REACTOR SAFETY HOSS NOVAK HOSKTOCKY CHECK AT 6 I SADiZMAN HUTBEHG EXTERNAL DISTR I8UTION HEG.V-IE LA VOre CONSULTAIfl'S IST RI8UTION'LANT SYSTEMS TEDESCO BENAROYA IPPOLITO OPERATING HEACTO S STELIQ OPERATING TECFE EISEMGJT SFEAO BAEre SCHWENC ER GHIIlES SITE SAT>>"PY 8e WVXHO ANALY~>XS Dpi'y~yg'r P>;I'.ULNAE>BleOOKlrAVEN 11ATL LAB ULIniXON (OmrL RVXHO TECEl'ALLAR r SITE TECH GAMMILL STEPP EIULMAN SXTE ANALYSXS VOLLMER BUNCFr J.COLLINS KREGER CONTROL NUMBER
lIDONOTRZMPVZ>>~sT~>>>.:kX,~~,~iI>e,v4.<ACKNOWLZDgZD SAX>>TYASSIGNEDAD:BRANCHCHIEF:PROJECTIMAGER:LIC.ASST.:Q<niiFORAC1ION/INFORMATION ASSXGNEDAD:BRANCHCHXEF:PROJECTMANAGER:LIC.ASST.:REGFILEICEOELDGOSSICK5STAFFlHPCCASEEEANAUERHr,l".sTMANAGEMENT PCOLLINS1iOUSTONPL7HHSONFED'/EEI"LTEMES SKOVHOLTLPDR:DSM~+3)~'1'Tr,'NSIO ASLB>>cnsIInor,>>1;>ia s>>>>>>INTERNALDSYSTEI43S!~w..EEEXNEIMANSCHHOEDER ENGINEERING KNIGEITPAWLXCKXREACTORSAFETYHOSSNOVAKHOSKTOCKY CHECKAT6ISADiZMANHUTBEHGEXTERNALDISTRI8UTIONHEG.V-IELAVOreCONSULTAIfl'S ISTRI8UTION'LANTSYSTEMSTEDESCOBENAROYAIPPOLITOOPERATING HEACTOSSTELIQOPERATING TECFEEISEMGJTSFEAOBAEreSCHWENCERGHIIlESSITESAT>>"PY8eWVXHOANALY~>XSDpi'y~yg'rP>;I'.ULNAE>
~~~~~yf NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIK 60ULKVARD WEST SYRACUSE, H.Y.13202'8 Kw~June 2, l976 Uo$IPJCISAR RICIMT02T, COhN ISS lOII he/Rdl2T Director of Nuclear Reactor Regulation Attn:Mr.Karl R.Goller, Assistant Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit Docket No.50-220 DPR-63  
BleOOKlrAVEN 11ATLLABULIniXON(OmrLRVXHOTECEl'ALLAR rSITETECHGAMMILLSTEPPEIULMANSXTEANALYSXSVOLLMERBUNCFrJ.COLLINSKREGERCONTROLNUMBER
~~~~~yf NIAGARAMOHAWKPOWERCORPORATION NIAGARA~MOHAWK300ERIK60ULKVARD WESTSYRACUSE, H.Y.13202'8Kw~June2,l976Uo$IPJCISARRICIMT02T, COhNISSlOIIhe/Rdl2TDirectorofNuclearReactorRegulation Attn:Mr.KarlR.Goller,Assistant DirectorDivisionofOperating ReactorsU.S.NuclearRegulatory Commission Washington, D.C.20555Re:NineMilePointUnitDocketNo.50-220DPR-63


==DearSir:==
==Dear Sir:==
YourApril6,l976letterrequested radioactive methyliodidedecontamination testinformation fortheEmer-gencyVentilation SystematNineMilePointUnitl.Theattachedresponses addressthequestions contained in'thatletter.Sincerely,NIAGARAMOMWK"POWERCORPORATION EMERALDKODEVicePresident
Your April 6, l976 letter requested radioactive methyl iodide decontamination test information for the Emer-gency Ventilation System at Nine Mile Point Unit l.The attached responses address the questions contained in'that letter.Si ncerel y, NIAGARA MOMWK"POWER CORPORATION EMERALD K ODE Vice President-ngineering
-ngineering
/sz Attachment 5888  
/szAttachment 5888  
$~y'lg fcmw<g'I~%4 IL hp I C ll RESPONSES TO APRIL 6I l976 NRC QUESTIONS NINE MILE POINT UNIT l DOCKET NO.50-220 DPR-63 R~euest 1 The date the sample of'harcoal was obtained, and the method under which it was obtained (eg, canister and grain thief').a.l0/29/73-Cartridge, Emergency Ventilation System b.l0/27/75-Cartridge, Emergency Ventilation System R~euesL 2 The time interval the charcoal had been installed in the system, and the approximate number of hours the appropriate ESF syst'm had been in operation with the tested charcoal.Res onse 2 The samples were obtained by removal of cartridges installed at the time of the initial bed loading.The cartridges contained charcoal from that loading.Initial plant criticality was achieved 9/5/69.a.Time interval: '0/29/73 sample: Approximately four calendar years l0/27/75 sample: Approximately six calendar years
$~y'lgfcmw<g'I~%4ILhpICll RESPONSES TOAPRIL6Il976NRCQUESTIONS NINEMILEPOINTUNITlDOCKETNO.50-220DPR-63R~euest1Thedatethesampleof'harcoal wasobtained, andthemethodunderwhichitwasobtained(eg,canisterandgrainthief').a.l0/29/73-Cartridge, Emergency Ventilation Systemb.l0/27/75-Cartridge, Emergency Ventilation SystemR~euesL2Thetimeintervalthecharcoalhadbeeninstalled inthesystem,andtheapproximate numberofhourstheappropriate ESFsyst'mhadbeeninoperation withthetestedcharcoal.
Resonse2Thesampleswereobtainedbyremovalofcartridges installed atthetimeoftheinitialbedloading.Thecartridges contained charcoalfromthatloading.Initialplantcriticality wasachieved9/5/69.a.Timeinterval:
'0/29/73sample:Approximately fourcalendaryearsl0/27/75sample:Approximately sixcalendaryears


b.approximate numberofhours:Priorto10/29/73sample:10hrs/yearx5years*=50hoursPriorto10/27/75sample:50hrs(priorto10/73sample)+10hrs/yrx2yrs(testing)
b.approximate number of hours: Prior to 10/29/73 sample: 10 hrs/year x 5 years*=50 hours Prior to 10/27/75 sample: 50 hrs (prior to 10/73 sample)+10 hrs/yr x 2 yrs (testing)+20 hrs (purge prior to 1974 outage, est.)+41 hrs (purge prior to 1975 outage, actual)131 hours.s*Includes initial plant startup time plus four calendar years.~Re uesC 3 The laboratory that performed the radioactive test.Nuclear Containment Systems, Inc.P.O.Box 19827 Columbus, Ohio 43129 (614)252-1420 R~euese 4 The test agent (ie, elemental iodine or methyl iodide).Res onse 4 a.10/'29/73-Elemental iodine and methyl iodide'b.10/27/75-Methyl iodide
+20hrs(purgepriorto1974outage,est.)+41hrs(purgepriorto1975outage,actual)131hours.s*Includes initialplantstartuptimeplusfourcalendaryears.~ReuesC3Thelaboratory thatperformed theradioactive test.NuclearContainment Systems,Inc.P.O.Box19827Columbus, Ohio43129(614)252-1420R~euese4Thetestagent(ie,elemental iodineormethyliodide).Resonse4a.10/'29/73
-Elemental iodineandmethyliodide'b.10/27/75-Methyliodide


R~euest5Thetestconditions (eg,temperature, relativehumidity, inletconcentration anddurationoftest).TestresultsshouldindicatewhetherRDTM16-ITprocedures werefollowed.
R~euest 5 The test conditions (eg, temperature, relative humidity, inlet concentration and duration of test).Test results should indicate whether RDT M16-IT procedures were followed.The test conditions of RDT 816-IT, including temperature, relative'humidity, i nlet concentration and test durati on, were followed using the following options: a.10/29/73 sample: 25 Cg ambient pressure, 70~relative humidi ty b.10/27/75 sample: 190 F, one atmosphere, 958 relative humidity~Re uest 6 The removal efficiency obtained, and the experimental error (if known).a.10/29/73 Emergency Ventilation System Cartridge 8 1" depth 99.96'.iodine removed 92.W'ethyl iodide decontaminated 8 2" depth 100.000 iodine removed 99.0C methyl iodide decontaminated 10/27/75 II11 Emergency Ventilation System Cartridge 8 2" depth 97.82K'ethyl iodide decontaminated The experimental error was not known.  
Thetestconditions ofRDT816-IT,including temperature, relative'humidity, inletconcentration andtestduration,werefollowedusingthefollowing options:a.10/29/73sample:25Cgambientpressure, 70~relativehumidityb.10/27/75sample:190F,oneatmosphere, 958relativehumidity~Reuest6Theremovalefficiency
: obtained, andtheexperimental error(ifknown).a.10/29/73Emergency Ventilation SystemCartridge 81"depth99.96'.iodineremoved92.W'ethyliodidedecontaminated 82"depth100.000iodineremoved99.0Cmethyliodidedecontaminated 10/27/75II11Emergency Ventilation SystemCartridge 82"depth97.82K'ethyl iodidedecontaminated Theexperimental errorwasnotknown.  


R~euest7Anyunusualoperation conditions orotherinformation youmayconsideruseful.None.
R~euest 7 Any unusual operation conditions or other information you may consider useful.None.
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Revision as of 02:00, 8 July 2018

Nine Mile Point Unit 1 - Letter Responding to 04/06/1976 Letter Requesting Radioactive Methyl Iodide Decontamination Test Information for the Emergency Ventilation System
ML17037B552
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/02/1976
From: Rhode G K
Niagara Mohawk Power Corp
To: Goller K R
Office of Nuclear Reactor Regulation
References
Download: ML17037B552 (12)


Text

NRC ronM 195 I2.7B)V.S.NUCLFAR REGULATOR.IMISSION DOC~+T NUMBER+O-QQ,C)NRC DISTRIBUTION roR PART 50 D+r KFT MATERIAL I ILE NUMBER TO: MR K R GOLLER LETTER+ORIGINAL QCOPV ONOTORIZED g VNC LASS IF I E D FEIDM: NIAGARA MOHAWK POWER CORP SYRACUSE, NY G K RHODE INPUT FORM DATE OF DOCUMENT D*T>R>c>lv.D>1 (NUMBER OF COPIES RECEIVED DESCRIPTION LTR RE OUR 5-6-76 LTR"-TRANS'HE FOLLOWRlo.......

F.NCLOSURE RESPONSES TO APRIL 6p 1976 NRC QUEST10NS......

l IDONOT RZMPVZ>>~sT~>>>.:kX,~~,~iI>e, v 4.<ACKNOWLZDgZD SAX>>TY ASSIGNED AD: BRANCH CHIEF: PROJECT IMAGER: LIC.ASST.: Q<nii FOR AC1 ION/INFORMATION ASSXGNED AD: BRANCH CHXEF: PRO JECT MANAGER: LIC.ASST.: REG FILE ICE OELD GOSSICK 5 STAFF lHPC CASE EEANAUER Hr,l".s T MANAGEMENT P COLLINS 1iOUSTON PL7HHSON FED'/EEI"LTEMES SKOV HOLT LPDR: DSM~+3)~'1'Tr,'NSIO ASLB>>cns II nor,>>1;>ia s>>>>>>INTERNAL D SYSTEI43 S!~w..EEEX NEIMAN SCHHOEDER ENGINEERING KNIGEIT PAWLXCKX REACTOR SAFETY HOSS NOVAK HOSKTOCKY CHECK AT 6 I SADiZMAN HUTBEHG EXTERNAL DISTR I8UTION HEG.V-IE LA VOre CONSULTAIfl'S IST RI8UTION'LANT SYSTEMS TEDESCO BENAROYA IPPOLITO OPERATING HEACTO S STELIQ OPERATING TECFE EISEMGJT SFEAO BAEre SCHWENC ER GHIIlES SITE SAT>>"PY 8e WVXHO ANALY~>XS Dpi'y~yg'r P>;I'.ULNAE>BleOOKlrAVEN 11ATL LAB ULIniXON (OmrL RVXHO TECEl'ALLAR r SITE TECH GAMMILL STEPP EIULMAN SXTE ANALYSXS VOLLMER BUNCFr J.COLLINS KREGER CONTROL NUMBER

~~~~~yf NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIK 60ULKVARD WEST SYRACUSE, H.Y.13202'8 Kw~June 2, l976 Uo$IPJCISAR RICIMT02T, COhN ISS lOII he/Rdl2T Director of Nuclear Reactor Regulation Attn:Mr.Karl R.Goller, Assistant Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit Docket No.50-220 DPR-63

Dear Sir:

Your April 6, l976 letter requested radioactive methyl iodide decontamination test information for the Emer-gency Ventilation System at Nine Mile Point Unit l.The attached responses address the questions contained in'that letter.Si ncerel y, NIAGARA MOMWK"POWER CORPORATION EMERALD K ODE Vice President-ngineering

/sz Attachment 5888

$~y'lg fcmw<g'I~%4 IL hp I C ll RESPONSES TO APRIL 6I l976 NRC QUESTIONS NINE MILE POINT UNIT l DOCKET NO.50-220 DPR-63 R~euest 1 The date the sample of'harcoal was obtained, and the method under which it was obtained (eg, canister and grain thief').a.l0/29/73-Cartridge, Emergency Ventilation System b.l0/27/75-Cartridge, Emergency Ventilation System R~euesL 2 The time interval the charcoal had been installed in the system, and the approximate number of hours the appropriate ESF syst'm had been in operation with the tested charcoal.Res onse 2 The samples were obtained by removal of cartridges installed at the time of the initial bed loading.The cartridges contained charcoal from that loading.Initial plant criticality was achieved 9/5/69.a.Time interval: '0/29/73 sample: Approximately four calendar years l0/27/75 sample: Approximately six calendar years

b.approximate number of hours: Prior to 10/29/73 sample: 10 hrs/year x 5 years*=50 hours Prior to 10/27/75 sample: 50 hrs (prior to 10/73 sample)+10 hrs/yr x 2 yrs (testing)+20 hrs (purge prior to 1974 outage, est.)+41 hrs (purge prior to 1975 outage, actual)131 hours0.00152 days <br />0.0364 hours <br />2.166005e-4 weeks <br />4.98455e-5 months <br />.s*Includes initial plant startup time plus four calendar years.~Re uesC 3 The laboratory that performed the radioactive test.Nuclear Containment Systems, Inc.P.O.Box 19827 Columbus, Ohio 43129 (614)252-1420 R~euese 4 The test agent (ie, elemental iodine or methyl iodide).Res onse 4 a.10/'29/73-Elemental iodine and methyl iodide'b.10/27/75-Methyl iodide

R~euest 5 The test conditions (eg, temperature, relative humidity, inlet concentration and duration of test).Test results should indicate whether RDT M16-IT procedures were followed.The test conditions of RDT 816-IT, including temperature, relative'humidity, i nlet concentration and test durati on, were followed using the following options: a.10/29/73 sample: 25 Cg ambient pressure, 70~relative humidi ty b.10/27/75 sample: 190 F, one atmosphere, 958 relative humidity~Re uest 6 The removal efficiency obtained, and the experimental error (if known).a.10/29/73 Emergency Ventilation System Cartridge 8 1" depth 99.96'.iodine removed 92.W'ethyl iodide decontaminated 8 2" depth 100.000 iodine removed 99.0C methyl iodide decontaminated 10/27/75 II11 Emergency Ventilation System Cartridge 8 2" depth 97.82K'ethyl iodide decontaminated The experimental error was not known.

R~euest 7 Any unusual operation conditions or other information you may consider useful.None.

A I'I;0~~