ML20023A802

Forwards Evaluation of SEP Topic XV-20, Radiological Consequences of Fuel Damaging Accidents. Evaluation Will Be Included in Integrated Safety Assessment.Thyroid Dose at Exclusion Area Boundary within 10CFR100 Requirements

ML20023A802
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-15-20, TASK-RR LSO5-82-10-038, LSO5-82-10-38, NUDOCS 8210200031
Download: ML20023A802 (5)

Text

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2 October 14, 1982 i

Docket No.40-409 LS05-82 038 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601

SUBJECT:

SEP TOPIC XV-20, RADIOLOGICAL CONSEQUENCES OF FUEL DAMAGING ACCIDENTS - LACROSSE Enclosed is the staff's evaluation of SEP Topic XV-20 for the Lacrosse Boiling Water Reactor. This evaluation is based on our review of your topic safety assessment report submitted by letter dated March 12,1982, and an independent analysis cade by the staff.

The evaluation concludes that the dose to the thyroid at the exclusion area boundary is above the Standard Review Plan (HUREG-0800) guidelines of 75 rem, but within the 10 CFR Part 100 requirement of 300 rem.

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 H. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

Enclosure:

As stated cc w/ enclosure: See next page DSa use

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CC Fritz Schubert, Esquire U. S. Environmental Protection r

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 i

Morgan, Lewis & Bockius 1800 M Street, N. W.

James G. Keppler, Regional Administrator i

Washington, D. C.

20036 Nuclear Regulatory Comission, Region III 799 Roosevelt Road i

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 i

i Genoa, Wiscor. sin 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 Comission La Crosse, Wisconsin 54601 Washington, D. C.

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Dr. Lawrence R. Quarles Dr. George C. Anderson I

Kendal at Longwood, Apt. 51 Department of Oceanography Kenneth Square, Pennsylvania 19348 University of Washington i

Seattle, Washington 98195 U. S. Nuclear Regulatory Comission Resident Inspectors Office Rural Route #1, Box 276 Genoa, Wisconsin 54632 I

Town Chairman Town of Genoa Route 1 Genoa, Wisconsin 54632 Chairman, Public Service Comission of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 p

SYSTEMATIC EVALUATION PROGRAM TOPIC XV-20 1

LACROSSE t

TOPIC: XV-20, RADIOLOGICAL CONSEQUENCES OF FUEL DAMAGING ACCIDENTS I.

INTRODUCTION The safety objective of this topic is to assure that the offsite doses from fuel damaging accidents, as a result of fuel handling within the r

containment, are well within the guideline value of 10 CFR Part 100.

II.

REVIEW CRITERIA L

Section 50.34 of 10 CFR Part 50, " Contents of Applications: Technical Information," requires that each applicant, for a construction pemit or operating license, provide an analysis and evaluation of the design i

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. A fuel handling accident in i

the fuel handling and storage facility resulting in damage to fuel cladding and subsequent release of radioactive material is one of the l

postulated accidents used to evaluate the adequacy of these structures, i

systems and components with respect to public health and safety.

In addition,10 CFR Part 100 provides dose guidelines for siting of nuclear power plants to which calculated consequences of fuel damaging accidents may be compared.

III. RELATED SAFETY TOPICS The review of the fuel damaging accidents did not consider fuel damage as a result of drops of the spent fuel cask or other heavy objects which can be carried either over an open reactor vessel or the spent fuel pool. Review of the drops of casks and heavy objects is covered in two SEP Topics, IX-2, " Overhead Handling Systems-Cranes," and XV-21

" Spent Fuel Cask Drop Accidents."

Atmospheric diffusion parametiers were evaluated using methods described in Regulatory Guide 1.3.

IV.

REVIEW GUIDELINES l

Accidents involving spent fuel within the containment were reviewed following the assumptions and procedures outlined in Standard Review Plan (SRP) Section 15.7.4 and Regulatory Guide 1.25.'

The dose to an individual at either the Exclusion Area Boundary or outer boundary of l

l l

. the Low Population Zone fran a postulated fuel handling accident should be "well within" the exposure guidelines of 10 CFR Part 100.

"Well within" the guidelines of 10 CFR Part 100 has been defined as less than 75 rem to the thryoid in the SRP.

(Whole body doses are also examined but are not controlling due to the decay of the short-lived radioiso-1 topes prior to fuel handling.) This "well within" criterion is based on the probability of this event relative to other events which are evaluated against 10 CFR Part 100 exposure guidelines.

The review considers single failure, seismic design and equipment qualification only when the potential consequences might exceed the guidelines of 10 CFR Part 100 in the absence of containment isolation and effluent filtration.

V.

EVALUATION The staff has reviewed the licensee's submittal of the evaluation of j

the radiological consequences of fuel handling accidents, and has perfonned an independent evaluation of the postulated accident.

The i

staff assumed that a single failure assembly is dropped into the fuel i

pool during refueling operations and that all of the fuel rods in the assembly are damaged, releasing radioactive materials in the fuel gaps into the pool.

The radioactive material that would escape from the pool was then assumed to be released via the containment exhaust dampers to the atmosphere. Contrary to contemporary reactors, Lacrosse has no filter system capability to mitigate the consequences of a fuel handling accident. The analysis was performed using the guidelines and require-ments of SRP Section 15.7.4 and Regulatory Guide 1.25.

The list of assunptions and parameters used in the analysis is given in Table 1 and the calculated doses are summarized in Table 2.

VI.

CONCLUSION F

The offsite thyroid doses at the Exclusion Area and Low Population Zone Boundary for the postulated fuel handling accident are calculated to be 138 rems and 4 rems, respectively.

The whole body doses are lower (see Table 2).

These doses are within 10 CFR Part 100, but the thyroid dose at the EAB is not well within the 10 CFR Part 100 dose guideline value.

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• l TABLE 1 Fuel Handling Accident Assumption for Lacrosse Powe r 165 MWt Radial Peaking Factor (BWR) 1.5 Decay Time 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Number of Fuel Rods Affected 96 Total Number of Rods in the Core 6912 Filter Efficiency 0.0%

Iodine Decontamination Factor in Pool 100 3

Diffusion Parameter, X/Q at 338 m'eter Exclusion 1.9x10 sec/m Area Boundary TABLE 2 Radiological Consequences of Fuel Handling Accidents Dose to Thyroid Whole Body Dose Rems Rems Exclusion Area Boundary 138 6

Low Population Zone Outer Boundary 4

' 0.2

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