ML17037B552
| 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 I2.7B)
V.S. NUCLFAR REGULATOR
.IMISSION DOC~+T NUMBER
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NRC DISTRIBUTION roR PART 50 D+rKFT MATERIAL I ILE NUMBER TO:
MR K R GOLLER LETTER
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NUMBER OF COPIES RECEIVED DESCRIPTION LTR RE OUR 5-6-76 LTR"-TRANS'HE FOLLOWRlo.......
F.NCLOSURE RESPONSES TO APRIL 6p 1976 NRC QUEST10NS......
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PRO JECT MANAGER:
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NIAGARA MOHAWK POWER CORPORATION NIAGARA~
MOHAWK 300 ERIK 60ULKVARDWEST SYRACUSE, H.Y. 13202
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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
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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
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 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 />.
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, inlet 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
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