ML17037B552

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
Issue date:	06/02/1976
From:	Rhode G Niagara Mohawk Power Corp
To:	Goller K Office of Nuclear Reactor Regulation
References
Download: ML17037B552 (12)

Text

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

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~~~~~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.

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