ML20023A807
| ML20023A807 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/14/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| TASK-15-19, TASK-RR LSO5-82-10-040, LSO5-82-10-40, NUDOCS 8210200038 | |
| Download: ML20023A807 (5) | |
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October 14, 1982 Docket No. 50-409 LS05-82-10-040 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South I.JCrosse, Wisconsin 54601
Dear ftr. Linder:
SUBJECT:
SEP TOPIC XV-19, LOSS-0F-COOLANT ACCIDENTS RESULTING FR0tt A SPECTRUM OF PIPING BREAKS WITHIN THE REACTOR COOLANT PRESS' RE J
BOUNDARY (RADIOLOGICAL) - LACP,0SSE Enclosed is the staf f's evaluation of SEP Topic XV-19 for the Lacrosse Boiling Water Reactor. This review is based on an independent analycis made by the staff. The evaluation concludes that your facility meets current licensing criteria for this topic.
This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This assessment may be revised in the future if your facility design is changed or if HRC criteria relating to this subject is modified before the integrated assessment is completed.
Si ncerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure: See next page SE0+
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NRC FORM 318 (10-80) NRCM 024o OFFiClAL. RECORD COPY V
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1 Mr. Frank Linder l
cc Fritz Schubert, Esquire U. S. Environmental Protection 1
Staff Attorney Agency Dairyland Power Cooperative,
Federal Activities Branch.
2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN: Regional Radiation Representative 230 South Dearborn Street O. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.
Janes G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III Washington, D. C.
20036 799 Roosevelt Road Mr. John Parkyn Glen Ellyn, Illinois 60137 La Crosse Boiling Water Reactor Dairyland Power Cooperative Mr. Ralph S. Decker P. O. Box 275 Route 4, Box 1900 Genoa, Wisconsin 54632 Cambridge, Maryland 21613 Mr. George R. Nygaard Charles Bechhoefer, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Board 2307 East Avenue U. S. Nuclear Regulatory Commission La Crosse, Wisconsin 54601 Washington, D. C.
20555 Dr. Lawrence R. Quarles Dr. George C. Anderson -
Kendal at Longwood, Apt. 51 Department of Oceanography Kenneth Square, Pennsylvania 19348 University of Washington Seattle, Washington 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1, Box 276 Genoa, Wisconsin 54632 Town Chairman Town of Genoa Route 1 Genoa, Wisconsin 54632 Chairman, Public Service Commission i
of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 l
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TOPIC XV-19 LACROSSE TOPIC: XV-19, LOSS-OF-COOLANT ACCIDENTS RESULTING FROM A SPECTRUii 0F PIPING BREAKS WITHIN THE REACTOR COOLANT PRESSURE B0UNDARY I.
INTRODUCTION Loss-of-coolant accidents (LOCAs) are postulated breaks in the reactor coolant pressure boundary resulting in a -loss of reactor coolant at a rate in excess of the capability of the reactor coolant makeup system.
A LOCA will result in excessive fuel damage or melt unless coolant is repleni shed. Excessive fuel damage can result in significant radiological consequences to the public via leakage from the containment. SEP Topic XV-19 is intended to assure that the radiological consequences of a design basis LOCA from containment leakage, and leakage from engineered safety features outside containment, are within the exposure guideline values of 10 CFR Part 100.
II.
REVIEW CRITERIA Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction pemit or operating license provide an analysis and evalua-tion of the design and perfomance of structures, systems and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The LOCA is one of the postulated accidents used to evaluate the adequacy of these structures, systems and components with respect to the public health and safety.
In addition,10 CFR Part 100.11 provides dose guidelines for reactor siting against which calculated accident dose consequenci s may be compared.
III. RELATED SAFETY TOPICS Topic III-5.A, " Effects of Pipe Breaks on Structures, Systems and Components Inside Containment," ensures that the ability to safely shutdown or mitigate the consequences of a pipe break accident is maintained.
Various other related topics cover containment integrity and isolation, post-accident chemistry, ESF systems, combustible gas control, and control room habitability.
The atmospheric diffusion parameters were evaluated using methods described in Regulatory Guide 1.3.
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. IV.
REVIEW GUIDELINES The review of the radiological consequences of a LOCA was conducted in accordance with Appendices A, B'and D to Standard Review Plan 15.6.5, TID-14844, and Regulatory Guide 1.3.
The plant is considered adequately designed against a LOCA, and the dose mitigating features are acceptable, if the resulting doses at the Exclusion Area Boundary and the outer boundary of the Low Population Zone-are within the guideline values of 10 CFR Part 100.
V.
EVALUATION The staff reviewed the licensee's submittal for evaluation of a LOCA.
The licensee did not periorm any new analysis of the radiological con-sequences of a postulated LOCA.
Instead, the license referred to the older evaluction provided in Section 14.3.18 of the Safety Analysis Report which showed that the calculated offsite doses meet the exposure guidelines of 10 CFR Part 100.11 wits respect to the adequacy of the distances to the Exclusion Area Boundary and the outer boundary of Low Population Zone.
The staff performed an independent analysis of the radiological con-sequences of the LOCA.
The assunptions used in the calculations are listed in Table 1; the calculated doses are shown in Table 2.
We assumed that decay was the only removal mechanism for the radioactive material assuned to be released to containment.
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The shine or direct gamma dose evaluation is not considered in SRP 15.6.5 because the modern plants for which SRP 15.6.5 was written have thick concrete walls which reduce the potential shine dose to a negligible amount.
However, the Lacrosse containment provides far less shielding from shine than a modern containment.
Guidance for the.evalua-tion of this dose pathway is found in 10 CFR 100.11 which stated, "The calculations described in Technical Information Document 14844 may be used as a point of departure for consideration of particular site requirenents which may result from etaluation of the characteristics of a particular reactor...".
The staff decided that, based on the characteristics of Lacrosse, the shine doses should be included. The shine doses calculated in the staff's Safety Evalu~ation Report for Lacrosse are included in the LOCA doses presented in Table 2.
VI.
CONCLUSIONS The calculated doses, shown in Table 2, resulting from a LOCA meet the dose guidelines of 10 CFR 100.11.
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TABLE 1 Assumptions Used in the Calculations of Offsite Doses Following a Design Basis LOCA at Lacrosse Reactor Power 165 MWt TIO Source Terms in Containment Atmosphere Noble Gases 100% of Core lodines 25% of Core Containment Leak Rate 0.1% per day ESF Leakage Outside the Containment None (ESF recirculation loop is inside the primary containment)
MSIV Leakage 0.045% of the containment volume per day 3
Atmospheric Dispersion Parameters, X/Q - Sec/m 0-2 hours at 338 meter Exclusion Area Boundary 1.9x10-3 0-8 hours at 4827 meter outer boundary of Low Population Zone 5.6x10-5 8-24 hours at 4827 meter outer boundary of Low Population Zone 1.3x10-5 24-96 hours at 4827 meter outer boundary of Low Population Zone 4.0x10-6 96-720 hours at 4827 meter outer boundary of Low Population Zone 9.2x10-7 0
TABLE 2 Calculated Offsite Doses Resulting from a LOCA Exclusion Area Nearest Outer Boundary of Low Boundary (0-2 hours)
Population Zone (0-30 days)
Dose in rems Dose in rems Thyroid Whole Body Thyroid Whole Body Containment Leakage 152 1.0 26 0.1 Shine (direct gamma) 9.6 Total 152 10.6 26 0.1 l
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