ML20127J638
| ML20127J638 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/20/1974 |
| From: | James Shea, Ziemann D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20127J619 | List: |
| References | |
| NUDOCS 9211190386 | |
| Download: ML20127J638 (2) | |
Text
~
11 i.
- ,y i
l 1
.p-
/,:
/ji.
SAFETY 27ALLETION BY THE DIRECTORATE OF LICE 35ING i
SUPPORTIBC AMEND 0!NT NO. 5 TO LICENSE DPb22
~
Y-333r3EE5 SvAvan POWER OMPANY e
~
MoltrICELLD m1CTE.AR CENERATING FLANT DOCKET M0. 50-263 Introduction By letter dated July 8,1974, Northern States Power Company requested a change to Provisional Operating License No. DFb22 for-the Monticello Nuclear Generating Plant. The proposed change would increase the licensed inventory of byproduct material by an amount of 250 mil 11 curies of kryptoo-85.
Discussion The changa proposed by the licensee would allow the use of kryptore-85 to verify industry data used in the calibration of the reactor building vent monitor. The Technical Specifications appended to-Provisional Operating License 30. DPR-22 require -calibration of the reactor building vest monitor every three months..
Der review of this proposed change to Section 2.C of Provisional-Operating License No. DPR-22 considered the N of aseid==tal release of the total 250 mil 11 curies of kryptee-85.. Our analysis of-an accidental rolesso at gromd level of the total krypton-SS inventory-assuming 2 hour-5 percentile accident meteorological conditions (I/Q-= 1.5 x 10-3 sec/m3) at the nearest site boundary -(Wi m) resulted in a whole body dose of leJ8 than 2.5 x-10-2'mRae (beta plus samma radiation). Hvon 1f such an accidental relamme occurred every tima
- calibration of the reactor buildine vent annitor is required 1(four
~
tiana per year), the annual whole body dose weeld be less-than 1 x 10-1 ar.aa:. We understand that the smallest amount. ef' krypton-85, required for a temaniagful calibration will be used and an amount of ic:ypton-85 less than 250 mil 11 curies will' be used daring any enlibration
~
of the' reactor building vent twnitor. Such whole body doses are 1ess than'O.02 percent of allowable : annual daaan for unrestricted areas-given in la CPP.,20.rt 20.-
..-...-,4
~~-- -
OFFICE >
SURNAME >
DATE>
.44-i.-aineen..*>cv.
"* ' Fnem AEC.Ste IRev.9 53) AECM 0240 -
92?.1190386 740820 PDR ADOCK.05000263L P'
fDR
-(
=.
j i
2-Conclusion i
We have concluded, based on the analysis discussed above, that because the amendment does not involve a significant increase in the probability or consaquences of accidente creviously considered and does not involve
~
a significant decrease in a e ifety margin, the action does not involve a significant hazards consideration. We also conclude that there is reasonable assuranea (i) that the activities authorised by this amendment
~
can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in complianes with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
o t
O cm.=> d - 7 M ch James J. Shea Operating Reactors Branch #2 Directorate of Licensing
/sNum D. anan Dennis L. Zions,an, Chief Operating Reactors Branch #2 Directorate of Licensing
.DE Dates d
- omct, SURNAME >
DATE >
,_ L, Form AEC-518 (Rev. 9-53) AEC310240 een eu-14-s t eos-1 ums
,