ML20053D330
| ML20053D330 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/15/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-15-18, TASK-RR LAC-8026, NUDOCS 8206040312 | |
| Download: ML20053D330 (3) | |
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5/28/82 - Duplicate of letter originally sent at earlier date.
D DA/RYLAND h
k COOPERAT/VE e0 eOx en. 2 sis EAST AV
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SOUTH
. LA CAOSSE W1SCONSIN $4601 (608) 788 4 000 January 15, 1982 In reply, please refer to LAC-8026 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
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR(LACBWR)
PROVISIONAL OPERATING LICENSE NO.
- RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURE OUTSIDE CONTAINMENT (BWR)
Reference:
(1)
DPC Letter, LAC-7387, Linder to Eisenhut, dated February 27, 1981.
Gentlemen:
Enclosed find Safety Evaluation Report (SER)
Consequences of Main Steam Line Failure Outside Containmentfor Radiological (SEP-XV-18) which we have prepared for the La Crosse Boiling Water (BWR),
Reactor.
Our letter, Reference 1, identified topics for DPC to sub it f NRC evaluation.
mitted with Reference 1.The subject topic was listed in the schedule sub-m or If there are any questions regarding this letter, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE IGSIGTAID ORIGINAL s
fertificd Sy__
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Frank Linder, General Mannger FL:JDP:af cc:
J. G. Keppler, Reg. Dir., NRC-DRO III NRC Resident Inspector f
9 OS 8206040312 820115 PDR ADOCK 05000409 p
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SYSTEMATIC EVALUATION PROGRAM SAFETY EVALUATION REPORT TOPIC XV-18 RADIOLOGICAL CONSEQUENCES Ol' MAIN STEAM LINE FAILURE OUTSIDE CONTAINMENT (BWR)
The radiological consequences of a main steam line failure outside containment was evaluated for the LACBWR. A complete break of the 10-inch main steam line at full power operation was assumed to occur outside the containment building releasing primary-system steam to the atmosphere.
Closure of the reactor building steam isolation valve terminated the release.
The reactor coolant I-131 activity was assumed to be the technical specifi-cation limit for reactor operation. The results of the evaluation showed the thyroid dose to an individual at the exclusion area boundary to be less
(
than 1 rem and a small fraction of the 10 CFR Part 100 limit.
1 The guidelines outlined in NRC Regulatory Guide 1.5 were folleved for the evaluation. The reactor building isolation valves were assumed to close at the technical specification limit of 10 seconds with 17,000 pounds of liquid and steam released 2 (valve closure beginning at 4 seconds with com-plete closure at 14 seconds). The technical specification limit for reactor coolant activity during operation is less than, or equal to, 0.2 pCi/gm DOSE EQUIVALENT I-131.
The I-131 concentration in the reactor coolant was conservatively assumed to be 0.2 pCi/gm and to be completely airborne follow-ing the release.
The atmospheric dispersion factor at the exclusion area boundary was conservatively estimated to be 9 x 10-4 s/m3 and was based on NRC Regulatory Guide 1.5 guidelines. The I-131 inhalation dose conversion i
3 factor was 1.49 x 10-3 arem/pCi.
The thyroid dose at the exclusion area
[
boundary to an individual was calculated to be 0.7 rem.
The doses calculated above are below the 10 per cent of the 10 CFR Part 100 exposure guidelines and, therefore, comply with the SRP criterion.
The plant is adequately designed against failure of the main steam line outside containment.
REFERENCES 1.
NRC Regulatory Guide 1.5, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors."
2.
" Technical Evaluation of La Crosse Boiling Water Reactor Emergency Core Cooling System," Gulf United, Report No. SS-942, May 31, 1972.
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3.
NRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I.
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