ML20041D904
| ML20041D904 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/05/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-02-02.C, TASK-2-2.C, TASK-RR LAC-8006, NUDOCS 8203090509 | |
| Download: ML20041D904 (2) | |
Text
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- PO BOX 8.7 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN 64601 1
(608) 788-4000 1
January 5, 1982 In reply, please refer to LAC-8006 t
DOCKET NO. 50-409 U. S. Nuclear Regulatory Commission y
I.
ATTN:
Mr. Darrell G. Eisenhut, Director Division of Licensing
,p Ad, Office of Nuclear Reactor Regulation V-Division of Operating Reactors lief C
'M Washington, D. C.
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SUBJECT:
DAIRYLAND POWER COOPERATIVE
{ MQN$((f' LA CROSSE BOILING WATER REACTOR (LACBWR)
TOC PROVISIONAL OPERATING LICENSE NO. DPR-45
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SEP TOPIC II.2.C - ATMOSPHERIC TRANSPORT AND
//2Tp DIFFUSION CHARACTERISTICS FOR ACCIDENT ANALYSIS
Reference:
(1)
DPC Letter, LAC-7387, Linder to Eisenhut, dated February 27, 1981.
Gentlemen:
Enclosed find Safety Evaluation Report (SER) for SEP Topic II.2.C, Atmospheric Transport and Diffusion Characteristics for Accident Analysis, which we have prepared for the La Crosse Boiling Water Reactor.
Our letter, Reference 1, identified topics for DPC to submit for NRC evaluation.
The subject topics were listed in the schedule submitted with Reference 1.
If there are any questions regarding this letter, please contact us..
Very truly yours, 4
i DAIRYLAND POWER COOPERATIVE Atla
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Frank Linder, General Manager FL:TAS:JDP:af 7
A cc:
J. G. Keppler, Reg. Dir., NRC-DRO III
'NRC Resident Inspector I/
i 8203090509 820105 PDR ADOCK 05000409 P
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N LA CROSSE BOILING WATER REACTOR SYSTEMATIC EVALUATION PROGRAM SAFETY EVALUATION REPORT TOPIC II.2.C
' ATMOSPHERIC TRANSPORT AND DIFFUSION CHARACTERISTICS FOR ACCIDENT ANALYSES This analysis is pursuant to Section 50.24 of 10 CPR Part 50,
" Domestic Licensing of Production and Utilization Facilities".
It follows Regulatory Guide 1.3,
" Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors".
LACBWR SITE LACBWR is located on the east shore of the Mississippi River, within the Mississippi River Valley.
Five hundred foot bluffs rise rather abruptly about 1000' from_the plant.
The plant stack is 350 feet tall.
For this reason, terrain plays a major factor in $/Q calcul-ation, the full stack height (100m) was used.
However, for the. low population zone * (48 28m) calculations, the ground level case is assumed.
$/O CALCULATIONS AT EXCLUSION AREA BOUNDARY AND LOW POPULATION' ZONE Reference is made to NRC Regulatory Guide 1.3.
The following $/Q data is submitted, interpolated using the data in Regulatory Guide 1.3, and consistent with the previous mentioned terrain limitations:
3 Time Period Distance
$/O Sec./m 5
0-2 Hrs.
E.A.B.
(338 m) 1.5x10 5
0-8 Hrs.
L.P.Z.
(4828 m) 6.3x10 s
8-24 Hrs.
L.P.Z.
(4828 m) 1.3x10 6
1-4 Days L.P.Z.
(4828 m) 4.3x10 7
4-10 Days L.P.Z.
(4828 m) 9.2x10 This is a preliminary submission.
By May 15, 1982, we will compute the site dependent $/Q values following the.aethod outlined in Regul-atory Guide 1.145.
Site meteorology from 1978 and 1979 will be utilized for this analysis.
- From LACBWR Safeguards Report, August 1967, ACNP-65544.
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