ML17037C165
| ML17037C165 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/07/1975 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037C165 (8) | |
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NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)
CONTROL NO 734 FILE FROM: Niagara Mohawk Power Cor
- Syracuse, N.Y.
DATE OF DOC DATE R EC'D LTR TWX RPT XX OTHER TO:
Hr.
G ~ Lear ORIG l-signed.
CC OTHER SENTNRC PDR SENT LOCALPDR xxxx CLASS UNCLASS P ROP-INFO XXXX DESCRIPTION:
INPUT NO CYS REC'D ENCLOSURES:
DOCKET NO:
50>>220 Ltr trans the following:
Noble Gas Activity Data ACKNO>VL,ED"VV
,'IO NOT REMOVE PLANT NAME:
Nx.ne Mile Point gl FOR ACTIQN/INFQRMATIQN
(
BUTLER (L)
W/ Copies CLARK (L)
W/ Copies PARR (L)
W/ Copies KNIEL (L)
W/ Copies SCHWENCER (L)
W/ Copies STOLZ (L)
W/ Copies VASSALLO (L)
W/ Copies PURPLE (L)
W/ Copies ZlEMANN (L)
W/ Copies DICKER (E)
W/ Copies KNIGHTON (E)
W/ Copies YOUNGBLOOD W/ Copies REGAN (E)
/ Copies EAR (L)
W+opies SPIES W/ Copies (E)
LPM W/
opres INTERNALDISTRIBUTION F
PC PDR GC, ROOM P-506A
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P: COLLINS D NISE EG OPR FILE 5 REGION (2)
~ YiIPC TECH REVIEW SCHROEDER MACCARY KNIG HT PAWL I CK I SHAO STELLO HOUSTON NOVAK ROSS IPPQ LITQ TEDESCO S,COLLINS LAI NAS BENAROYA VOLLMER DENTON G R I MES GAMMILL KASTNER BALLARD SPANGLER ENVIRO MULLER DICKER KNIGHTON YOUNGBLOOD R~AN 4f R9JECT LDR HARLE S LIC ASST R. DIGGS (L)
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P. KREUTZER (E)
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M. SERVICE (L)
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M. SLATER (E)
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E. COUP.E PETERSON HARTFIELD (2)
KLECKER EISENHUT WIGGINTON EXTERNAL DISTRIBUTION
'CALPDRMhr~o., N.Y.
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NIAGARA MOHAWKPOWER CORPORATION 4I'M, NIAGARA ~)
MOHAWK 300 ERIK BOULEVARD WEST SYRACUSE. N. Y. 13202
- 8~<gkwry'uly 7,
1975 g~~o ~et5 Mr. G. Lear, Chief Operating Reactors Branch 83 Division. of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Elf'~
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Re:
Nine Mile Point Unit 1 Docket No. 50-220
Dear Mr. Lear:
The attached noble gas and iodine activity data for Nine Mile Point Unit 1 is provided in response to your letter of June 10, 1975. It is representative of normal operation for the plant.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION Gerald R
de Vice President En neering Attachment 7343
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Nine Mile Point Unit 1 NOBLE GAS AND IODINE ACTIVITYDATA Noble Gas Activit Data Only the following limited data is available for noble gas activity in the drywell during operation.
The best sample taken occurred when the offgas (summation of the six principal fission gases) l
~ amounted to 200,000 pCi/sec at the Steam Jet Air Ejector (SJAE).
Fission Gas Xe-133 Xe-135 Drywell Gas Sample Ci/cc 6.0 x 10 (-5) 4.0 x 10 (-5)
Offgas Sample at SJAE pci/cc 2.0 x 10 (-1) 5.5 x 10 (-1)
Iodine Activit Data The following is a table of sample results over the last few years showing a comparison between I-131 in the drywell atmosphere, I-131 in the reactor water, and the offgas activity (summation of the six principal fission gases)
I
~ at the SJAE.
Date Drywell I-131 Ci/cc Reactor Water I-131 Offgas.at SJAE Ci/ml 10-16-73 3-27-74 11-13-74 12-5-74 12-13-74 12-20-74 2-3-75 3-20-75
,4-11-75 6-17-75 4.1 x 10(-9) 4.9 x 10(-9) 5.9 x 10(-'10) 4.7 x 10(-10) 2.4 x 10(-9) 1.1 x 10(-9) 4.4 x 10(-9) 4.1 x 10(-9) 1.5 x 10(-7) j:5.j 2.0 x 10(-9) 5.2 x 10(-3) 2.2 x 10(-3) 9.1 x 10(-4) 8.9 x 10(-4) 9.3 x 10(-4) 8.1 x 10(-'3) 1.2 x 10(-3) 4.3 x 10(-3) 4.4 x 10(-3) 4.3 x 10(-3) 4.9 x 10(+4) 6.8 x 10(+4) 7.3 x 10(+4) 7.9 x 10(+4) 3.2 x 10(+4) 5.9 x 10(+4) 8.'2 x 10(+4) 1.0 x 10(+5) 1.2 x 10(+5)"
1.7 x 10(+5)
i'I 1
Notes
[1] At sample time,'-131 concentration in the reactor water was approximately 4.0 x 10(-3) pCi/ml.
[2] Fision gases include:
Kr-85m, Kr-88, Kr-89, Xe-133, Xe-135, and Xe-138.
There is approximately a five minute delay between the reactor and SJAE.
[3]
Leakage of reactor water into the drywell floor drain system was nominally <0.5 gpm for most of the sample periods.
[4]
Experience has shown that a "Distribution Factor" of 1,000,000 is appropriate to approximate airborne I-131 levels during times of normal reactor water leakage, i.e.:
Reactor Water I-131 Ci/ml Distribution Factor
=
Drywell I-131 (pCi/cc)
[5]
Sample taken prior to a drywell purge preceeding reactor shutdown due to high leakage rate of reactor water into drywell floor drain sump.
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