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

NRC ronM 195 V.S. NUCLFAR REGULATOR .IMISSION DOC~+T NUMBER I2.7B) +O- QQ,C)

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NIAGARA MOHAWK POWER CORPORATION NIAGARA 300

~ MOHAWK ERIK 60ULKVARD WEST SYRACUSE, H.Y. 13202 '8 June 2, l976 Kw~ 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

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RESPONSES TO APRIL 6I l976 NRC QUESTIONS NINE MILE POINT UNIT l DOCKET NO. 50-220 DPR-63 R~euest 1 date the sample of'harcoal was obtained, and the method under The 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 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> 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 />.

• Includes initial plant startup time plus four s

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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