ML20027D370
| ML20027D370 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/26/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-02-02.C, TASK-2-2.C, TASK-RR LSO5-82-10-073, LSO5-82-10-73, NUDOCS 8211040206 | |
| Download: ML20027D370 (5) | |
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October 26, 1982 Docket No. 50-155 LS05-82-10-073 Mr. David J. VandeWalle Nuclear Licensing Administrator Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. VandeWalle:
SUBJECT:
SEP TOPIC II-2.C. ATMOSPHERIC TRANSPORT AND DIFFUSION CHARACTERISTICS FOR ACCIDENT ANALYSIS - BIG ROCK POINT Enclosed is the staff's revised final evaluation of SEP Topic II-2.C for Big Rock Point Plant. The previous evaluation of June 23, 1982, derived the X/Q values at the outer boundary of the low population zone distance based on the minimum distance of a variable outer boundary. The outer boundary distance has now been redefined as 2.5 miles (4023m) and new X/Q values have been determined for the outer boundary using Regulatory Guide 1.3.
This evaluation will be a basic input to the integrated safety assess-ment 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 NRC criteria relating to this subject are modified before the integrated assessment is completed.
Sincerely, i
Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated 4 O cc w/ enclosure:
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OFFICIAL RECORD COPY usa m m L u m nac ronu ais oo-sonmcu cuo 4
Mr. David J. VandeWalle CC Mr. Paul A. Perry, Secretary U. S. Environmental Protection Co~nsumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue
" Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman.
U. S. N0 clear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Aig Rock Point Nuclear Power Pl. ant 9-ATTN: gg. C. J. Hartman
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e Mr. John O'Neill,11 FTant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664
.c Chri sta-Maria Mr.~ Jim E. Mills Route 2, Box 108C
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Route 2, Box 108C Charlevoix, Michigan 49720 Charlevoix, Michigan 49720 William J. Scanlon, Esquire 2034 Pauline Boulevard Chairman County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector E
Big Rock Point Plant 0'ffics of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720
~
' Herbert Semmel Hurst & Hanson Counsel for Christa Maria, et al.
311 1/2 E. Mitchell Urban Law Institute Petoskey, Michigan 49770 Antioch School of Law 2633 16th Street, NW Washington, D. C.
20460
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Mr. David J. VandeWalle 1
I cc Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board
. U. S. Nuclear Regulatory Commission t!ashington, D. C.
20555 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 t
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o SEP TOPIC II-2.C ATMOSPHERIC TRANSPORT AND DIFFUSION CHARACTERISTICS FOR ACCIDENT ANALYSIS BIG ROCK POINT I.
INTRODUCTION The safety objective of this review is to determine the appropriate onsite and near-site atmospheric transport and diffusion characteristics necessary to establish conformance with the 10 CFR Part 100 guidelines.
In particular, the short-term relative ground-level air concentrations (X/Q) are determined for use in estimating offsite exposures resulting from postulated accidents.
II.
REVIEW CRITERIA Section 100.10 of 10 CFR Part 100, " Reactor Site Criteria," states that meteorological conditions at the site and surrounding area should be considered in determining the acceptability of a site for a power reactor.
III.
RELATED SAFETY TOPICS Topic II-1. A, " Exclusion Area Authority and Control" provides the proper exclusion boundary distance over which the licensee has control. Various section XV topics utilize the atmosphere dispersion coefficients to determine the offsite radiological consequences of postulated accidents.
4 IV.
REVIEW GUIDELINES The atmospheric dispersion factors were calculated using the methodology, outlined in Regulatory Guide 1.3, " Assumptions Used for Evaluating the l
Potential Radiological Consequences of a loss of Coolant Accident for Boiling Water Reactors."
V.
EVALUATION On June 23, 1982, the staff issued an SER on Topic II-2.C, which was based on Consumers Power Company evaluation submitted by letter dated April 6,1982.
The staff SER derived the X/Q values at the outer boundary of the low population zone (LPZ) based on the minimum distance (805 l
meters) of a variable outer boundary as defined in the licensee's i
submittal of April 6,1982. The actual LPZ boundary is 2.5 miles (4023m) and the LPZ X/Q values have been recalculated based on this distance.
The evaluation was done using the meteorological diffusion parameters described in Regulatory Guide 1.3 since no meteorological observations have been made onsite in twenty years.
The staff has confirmed that the Regulatory Guide 1.3 parameters are conservative. This confirmation was done with the methods of the guide as described below and resulted
in the values given in Table 1 at the 805 meter exclusion area boundary and at the 2.5 mile (4023m) re-defined distance to the outer boundary of the low population zone distance.
Table 1: Relative Concentration at Big Rock Point 3
Time Relative Concentration X/Q sec/m 0-2 hours EAB 6.7 x 10 4 0-8 hours LPZ 8.0 x 10-5 8-24 hours 1.7 x 10-5 1-4 days 5.5 x 10-6 4-30 days 1.2 x 10-6 These values are derived from figure 3A with the application of the building wake dispersion correction factor in figure 2 of Regulatory Guide 1.3 for a 500 square meter building surface area. The above values should be used for all contained release accidents.
The licensee has proposed the installation of a meterological monitoring system in accordance with requirements of Regulatory Guide 1.23 and NUREG-0654. As a result, a Regulatory Guide 1.145 probabilistic analysis can be performed for the site once an annual cycle of data is available.
VI.
CONCLUSION The staff concludes that the X/Q values presented in Section V are appropriate for estimating exposures from postulated accidents and should be used in all but~ steam line break accident calculations.
This provides a conservative assessment compared to the use of methods in conjunction with Regulatory Guide 1.145, which is the basis of current review for new licenses.
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