ML20058D143
| ML20058D143 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/20/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| TASK-15-13, TASK-RR LSO5-82-07-044, LSO5-82-7-44, NUDOCS 8207270034 | |
| Download: ML20058D143 (6) | |
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..w July 20,1982 Docket No. 50-409 LS05-82-07-044 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601
Dear Mr. Linder:
SUBJECT:
LACROSSE - SEP TOPIC XV-13, SPECTRUM 0F R0D DROP ACCIDEllTS By letter dated March 5,1982, you submitted a safety assessment report for Topic XV-13 (doses). The staff has also made an independent review of this topic and has concluded that the Lacrosse design for mitigating the consequences of a control rod drop accident is acceptable.
Enclosed is the final safety evaluation report for this topic.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch flo. 5 Division of Licensing
$ 60 Y l
Enclosure:
As stated cc w/ enclosure:
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OFFIClAL RECORD COPY usom isai-mm mc ronu ais commncu om
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Mr. Frank Linder CC Fritz Schubert, Esquire U. S. Environmental Protection Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN:
Regional Radiation Repr~esentative 230 South Dearborn Street
- 0. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.
Mr. John H. Buck Washington, D. C.
20036 Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.
20555 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. Hygaard Charles Bechhoefer, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensin'g 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
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Seattle, Washington 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Of fice James G. Keppler, Regional Administrator Rural Route #1, Bcx 276 Nuclear Regulatory Commission, Region III Genoa, Wisconsin 54632 799 Roosevelt Road Glen Ellyn, Illinois 60137 Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board l
Route 1 U. S. Nuclear Regulatory Commission j
Genoa, Wisconsin 54632 Washington, D. C.
20555 Chairman, Public Service Commission of Wisconsin Hill Farms State Office Building f-Madison, Wisconsin 53702 Alan S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
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LACROSSE XV-13 SPECTRUM 0F ROD DROP ACCIDENTS 1.
INTRODUCTION An uncoupled control rod may hang up in the core when the control rod is withdrawn and drop later when the consequences are most severe.
As a result, radioactivity may be released from the core to the environment via the turbine and condenser.
SEP Topic XV-13 is intended to review the plant response and evaluate the radiological consequences of this accident.
II. REVIEW CRITERIA Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance 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 f acility.
The control rod drop accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to public health and safety.
In addition, 10 CFR Part 100.11 provides dose guidelines for a Design Basis Accident.
III. RELATED SAFETY TOPICS Topic Il-2.C, " Atmospheric Transport and Diffusion Characteristics for Accident Analysis" provides the meteorological data used to
. evaluate the offsite doses. Topic III-8.B. " Control Rod Drive Mechanism Integrity" evaluates the reliability and operability of control rod drives.
Various other SEP topics evaluate such related items as containment isolation, containment leak testing and ESF systems.
IV. REVIEW GUIDELINES The review of the radiological cor.cequences of a control rod drop accident was conducted in accordance with the Appendix to Standard Review Plan 15.4.9.
The plant is considered adequately designed against a control rod drop accident and the consequences acceptable if the resulting doses at the Exclusion Area and the Low Population Zone Boundaries are well within (25 percent of) the guideline values of 10 CFR Part 100.
V.
EVALUATION The licensee submitted an evaluation of SEP Topix XV-13 on March 5, 1982.
In this evaluation the licensee concluded that the acceptance criterion of the Appendix to SRP Section 15.4.9 was met. The staff performed an independent review of the radiological consequences of this accident using the guidance in the Appendix, and the assumption that the fuel-clad gap activity was the same as that 'specified in Regulatory Guide 1.77.
The staff estimated that 310 fuel rods would experience cladding perforation out of the core total of 6912 rods.
A sunnary of the assumptions used in the staff's analysis are presented in Table XV-13.1.
- VI. CONCLUSION Using the assumptions outlined above and summarized in Table XV-13.1, the resultant doses at the Exclusion Area Boundary are 0.4 rem to the thyroid and 0.04 rem whole body. The resultant doses at the outer boundary of the LPZ are 0.05 rem to the thyroid and <0.01 rem whole body. The calculated radiological consequences are less than the the acceptance criteria of the Appendix to SRP Section 15.4.9 (Revision
- 1) and, therefore, the staff concludes the the Lacrosse design for mitigating the consequences of a control rod drop accident is acceptable.
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T' TABLE XV-13.1 ASSUMPTIONS USED FOR THE CONTROL ROD DROP ACCIDENT 1.
Power (MWt) 165 2.
Amount of fuel f ailure-clad perforation (rods) 310 3.
Total number of fuel rods 6912 4.
Peaking factor 1.5 5.
Condenser leak rate (%/ day) 1 6.
Accident duration (hours) 24 7.
Activity release from f ailed fuel (%)
iodines 10 noble gases 10 8.
Activity released to the coolant which reaches the condenser (%)
iodines 10 noble gases 100 9.
Partition f actor in the condenser iodines 10 noble gases 1
- 10. X/Q's (sec/ cubic meters) 0 - 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> EAB*
(338 meters) 1.9 E-4* *
- O - 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> LPZ**
(4827 meters) 5.6 E-5 8 - 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LPZ (4827 meters) 1.3 E-5
- Exclusion Area Boundary (10 CFR Part 100)
- Outer Boundary of the Low Population Zone (10 CFR Part 100)
- *
- 1. 9 E-4 = 1. 9 x 10 -4 = 0. 0 0019