ML19332A819
| ML19332A819 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/12/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Peoples D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009180428 | |
| Download: ML19332A819 (6) | |
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August 12, 1980 Docket No. 50-10 Mr. D. Louis Peoples Director of Nuclear Licensing Commonwealth Edison Cogany Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Peoples:
RE: SEP TOPIC XV-20. " RADIOLOGICAL CONSEQUENCES OF FUEL DAMAGING ACCIDENTS (INSIDE AND OUTSIDE CONTAINMENT)" - DRESDEN 1 indicated th. t you have examined our draft Your letter dated June 11, 1980, a
evaluatien of thc subject topic dated March 26, 1980. You suggested editor-ial or corrective charges to the assessment to make it more accurately reflect your facility design. We have incorporated your suggested modifications in the enclosed ?ssessment. With these modifications our review of SEP Topic XV-20 is co@iete and will be a basic input to the integrated assessment of your facility.
The subject assessment co@ ares your facility design with the criteria currently used by the staff in licensing new facilities. This assessment may need to be re-examined if you modify your facility or if the criteria are changed before we comlete our integrated assessment.
Sincerely,
& h.f6U JW 4)ennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Operating Reactors
Enclosure:
Cogleted SEP Topic XV-20 cc w/ enclosure:
See next page 80091%0 $$$,
Mr. D. Louis Peoples August 12, 1980 cc w/ enclosure:
Isham, Lincoln & Beale Director, Technical Assessment Counselors at Law Division One First National Plaza, 42nd Floor Office of Radiation Programs Chicago, Illinois 60603 (AW-459)
U. S. Environmental Protection Mr. B. B. Stephenson Agency Plant Superintendent Crystal Mall #2 Dresden Nuclear Power Station Arlington, Virginia 20460 Rural Route #1 Morris, Illinois 60450 U. S. Environmental Protection Agency U. S. Nuclear Regulatory Commission Federal Activities Branch Resident Inspectors Office Region V Office Dresden Station ATTN: EIS C0ORDINATOR I
RR #1 230 South Dearborn Street Morris, Illinois 60450 Chicago, Illinois 60604 Susan N. Sekuler Resident Inspector Assistant Attorney Genercl Dresden Nuclear Power Station Environmental Control Division c/o U. S. NRC 188 W. Randolph Street Rural Route #1 Suite 2315 Morris, Illinois 60450 Chicago, Illinois 60601 Morris Public Library 604 Liberty Street Morris, Illinois 60451 Chai rman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Department of Public Health ATTN: Chief, Division of Nuclear Safety 535 West Jefferson Springfield, Illinois 62761
r, DRESDEN 1 XV-20 RADIOLOGICAL CONSE0VENCES OF FUEL DAMAGING ACCIDENTS (INSIDE AND OUTSIDE CONTAINMENT)
The safety objective of this topic is to assure that the offsite doses resulting from fuel damaging accidente during fuel handling are well within the guideline value of 10 CFR Part 100.
The design basis fuel handling accident for Dresden 1 is the postulated drop of the fuel basket damaging 16 assemblies. The postulated consequences of this accident and the dropping of one* assembly in the Fuel Building are given in Table XV-1.
The assumptions and input parameters used in calc,ulating the potential consequences are given in Table XV-2.
The analysis was performed following the assumptions and procedures indicated in SRP 15.7.4 and Regulatory Guide 1.25.
The acceptance criteria of the SRP specify that the doses should be " appropriately within the guidelines" of 10 CFR Part 100.
" Appropriately within the guidelines" has been defined by the staff as a thyroid dose less than 100 rem.
This is based on the probability of these accidents relative to the probability of other accidents which are evaluated against the Part 100 exposure guidelines. Whole body doses were considered but they are not controlling due to the decay of the short-lived radioisotopes prior to the fuel handling.
On the basis of the results as given in Table XV-1, we conclude that the radiological consequences are appropriately within the guidelines of 10 CFR Part 100.
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References:
1.
- Letter, D'. Ziemann to W. G. Counsil, December 20, 1979, Fuel Handling Accident Inside Containment.
2.
Letter, M. S. Turbak to D. L. Ziemann, Refueling Accident Analysis.
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T TABLE XV-1 CALCULATED DOSES FOR FUEL HA.NDLING ACCIDENTS Doses,(Rem)
Thyroid Whole Body Exclusion Area Boundary (EAB) 2-Hour Doses:
Fuel Building 3
0.2 0.4 Accident Inside Containment 56 4
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TABLE XV-2 ASSUMPTIONS USED FOR THE FUEL HANDLING ACCIDENT Power Level
'700 Mwt Operating Time 3 years Peaking Factor 1.5 Nunber of Fuel Assemblies Damaged Inside Containment
- 16 Number of Fuel Assemblies Damaged In the Fuel Building 1
Number of Fuel Assemblies in Core 464 Shutdown Time Before Start of Refueling 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Activity Release From Pool Regulatory Guide 1.25 Credit for Charcoal Filters None D>2 hr, X/Q Value, Exclusion Area Boundary 3
(ground level release) 1.0 x 10-4sec/m f
- 16 assemb1'es gay be damaged with a drop of the fuel basket.
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