ML20054K858

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Forwards Potential Accident Consequence Assessment Atmospheric Dispersion Model Calculations, in Support of SEP Topic II.2.C Re Atmospheric Transport & Diffusion Characteristic for Accident Analysis
ML20054K858
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 06/29/1982
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20054K859 List:
References
TASK-02-02.C, TASK-2-2.C, TASK-RR LAC-8365, NUDOCS 8207060225
Download: ML20054K858 (2)


Text

____ -__ -__

O DA/RYLAND COOPERA7/VE

  • PO. BOX 817
  • 2615 EAST AV SOUTH
  • LA CROSSE. WISCONSIN 54601 (608) 788 4 000 June 29, 1982 i

In reply, please refer to LAC-8365 DOCKET NO. 50-409 U.

S. Nuclear Regulatory Commission ATTN:

Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Division of Operating Reactors Washington, D.

C.

20555 3

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSF. BOILING WATER REACTOR (LACBWR) i PROVISIONAL OPERATING LICENSE NO. DPR-45 SEP TOPIC II.2.C - ATMOSPHERIC TRANSPORT AND DIFFUSION CHARACTERISTICS FOR ACCIDENT ANALYSIS

Reference:

(1)

DPC Letter, Linder to Eisenhut, LAC-8006, dated January 5, 1982 Gentlemen:

The licensee prepared Safety Evaluation Report (Reference 1) for SEP Topic II.2.C stated that site dependent X/Q values would be submitted at a later date.

The attached report includes the determinations of X/Q for the LACBWR and completes the licensee's SER for this topic.

Very truly yours, DAIRYLAND POWER COOPERATIVE

/

Frank Linder, General Manager FL:TAS:JDP:af f

Attachment - (2 copies) l cc:

J.

G.

Keppler, Reg. Adm., NRC-DRO III NRC Resident Inspector Q

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LA CROSSE BOILING WATER REACTOR SYSTDIATIC' EVALUATION PROGRAM SAFETY EVALUATION REPORT TOPIC II.2.C ATMOSPHERIC TRANSPORf AND DIFFUSION CHARACTERISTICS FOR ACCIDENT ANALYSES This analysis is pursuant to Section 50.24 of 10 CFR 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 within 1000 feet from the plant. The plant stack is 350 feet tall.

For this reason, terrain plays a major factor in y/Q calculation. Therefore, in those cases where the, bluff height exceeds the stack height, the dispersion equation becomes a ground level calculation.

Thus, for the E.A.B.* (338 m) y/Q calculation, the full stack height (100 m) was used. However, for the L.P.Z.* (4800 m) calculations, the ground level case be-comes most restrictive.

y/Q CALCULATIONS AT EXCLUSION AREA BOUNDARY AND IDW POPULATION ZONE The following 'f/Q data is submitted based upon guidance and procedures found in Regulatory Guides 1.3.and 1.145, and consistent with the previous mentioned terrain limitations. The calculations incorporate on-site meteorological data from the years of 1978 and 1979.

It should be noted that the exact computing methodology dif fers from that outlined in Regulatory Guide 1.145, but satisfies the intent of this evaluation.

Time Period Distance v/Q Sec./m 0-2 Hrs.

E.A.B.

(338 m) 1.4x10

~

-5 ((NE) 0-8 Hrs.

L.P.Z.

(4828 m) 3.1x10 SSE) 8-24 Hrs.

L.P.Z.

(4828 m) 2.3x10-5 (SSE)

-5 1-4 Days L.P.Z.

(4828 m) 1.1x10-6 (SSE) 4-10 Days L.P.Z. (4828 m) 6.1x10 (SSE)

This submission is intended to be complete. A report describing the calculations and numerical results is included.

  • From LACBWR Safeguards Report, August 1%7, ACNP-65544.