ML20002C632
| ML20002C632 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/08/1978 |
| From: | Skibitsky W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101100625 | |
| Download: ML20002C632 (11) | |
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&r%'JN Q' i l il.'
Director of Nuclear Reactor Regulation
.o Att: Mr Don K Davis, Acting Branch Chief t
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Operating Reactors Branch No 2 7
- pp310N, US Nuclear Regulatory Commission 4 Aces,.m h
Washington, DC 20555 u$
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DOCKET 30-155.. LICENSE DPR.
g BIG ROCK POINT PLANT -
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SITE METEOROLOGY In late December 1977, discussions were held with your staff concerning site meteorology and the Emergency Plan for the Big Rock Point Plant.
Based on these discussions, several areas requiring further amplification were identi-fled.
Included below are the items addresped and Consumers Power Ccmpary
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responses.
Iteq It is the intention of the NRC staff _to use atmospheric effluent data over the period 1972 through 1977 as source term to project future off-site doses with respect to 10 CFR 50, Appendix I.
Response
It is Consumers Power Company's position that effluent releases prior to 1976 are not applicable to future release rates.
It is apparent that even the 1975 effluent data used in our June h,1976 Appendix I submittal is excessively conservative with respect to more recent years.
Release rates have diminished progressively as indicated by Figure I due to fuel improvements and operational changes.
These changes were described on Pages A-1 and A-2 of our original sub-mittal and are updated in Table I, attached.
It is requested that the staff reconsider the use of data prior to 1976 and that the = ore appropriate 1976-1977 effluent release values be utilited for Appendix I calculations since, with the continued long-ter= reduction in effluent release, 1976-1977 values are expected to prove higher than the mean for future plant operation to end-of-life values. Thu.3, the recent data is consMered realis-tically conservative and in.conformance with Appendix I criteria.
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Is meteorological monitoring, similar to the Big Rock Point preoperational' system, required to confirm compliance with Appendix I effluent release criteria?-
Response
It is Consumers Power Company's position that monitoring is not required.
This is based on two factors. First, Appendix I requires that " design basis annual quantities" of various radionuclides be established for each nuclear site, based either upon realistic or conservative dose calculations.
Conservative methods were used, as documented in our June h,1976 submittal, and proposed Technical ~ Specifications-have been submitted based upon conservatively cal-culated design basis annual quantities.
Second, gaseous releases are demon-strated to be extremely stable ~ over operating intervals, intervals which are long relative to significant changes in meteorological conditions. This stability is illustrated in Figures II and III.
Figure II shows daily and weekly off-gas emissions for 1976 and 1977. Figure III indicates off-gas release over a typical 24-hour. period. Constancy of release rate is noted over both the long and short. term. Thus, annual average meteorology is fully applicable for description of gaseous radionuclide behavior and off-site dose analysis as set forth in 10 CFR 50, Appendix I.
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Item Does the meteorological data collection period (upon which the Appendix I sub -
mittal'vas based) represent long-term conditions in the vicinity of Big Rock Point?
-Response The on-site measurement program utilized spanned the peried February 9, 1961 through February: 8, 1963 This 2k-month period was compared to long-term con-ditiong (19ho-1969) at each of the three nearest National Weather Service Sta-tions.llF These stations are East Jordan, lh mi.~.es southeast; Traverse City, h5 miles southwest; and Pellston, 24 miles northeast of the plant. All three stations are second order stations. The first order stations are too far away to be considered as being in the same Michigan c:imatic division.(2)
Figures IV through VI present the mean monthly temperature and one standard de-viation as compared to the 24-month period for each of the three stations. The figurec show that the fluctuations in extremes are lower at East Jordan and Traverse City which are closer to water bodies (as is Big Rock) than Pellston which is' inland.
In general, the 2h-month period of study has shown good correlation with the 30-yesr average, cnd is representative of'long-term conditions in'the vicinity of Big Rock Point.
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References:
'(1) - US Department of Comerce,- 1971:
Climatological Sumnary, Climatography of the United States No 20-20, East Jordan, Pe11ston and Traverse City,.
Michigan, National;.0ceanic!and Atmospheric Administration, Environmental
' ' Data Service, Asheville, North Carolina.
i(2) ': Michigan Weather Service, 197h: Climate of Michigan, Michigan Department of Agriculture, Lansing, Michigan.
Mt4Sd William S Skibitsky.
. Senior Licensing Engineer-CC: JGKeppler, USNRC P
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TABLE I
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CHANGES WHICH HAVE AFFECTED THE BIG ROCK SOURCE TERM Through 1967 changed from mixed fuel cladding types to 100%
Zircaloy clad.
1968 High and low pressure feedvater heaters (70% Cu,
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30% N1) replaced with stainless steel.
1969 - 1973 Mixed oxide recycle performed at 12-13 kg per core.
1971 & 1972 Fuel channels modified for improved coolant distribu-tion and reduced crud deposition.
1972 cleanup system heat exchangers (70% Cu, 30% Ni) re-placed with stainless steel.
1973 changed six fuel bundles to 11 x 11 array from origi-nal 9 x 9 - provides approximately 20% increased heat transfer from rods.
1968 - 1975 new fuel impurity levels decreased - hydridine kw red.
1974 Continued changeover to 11 x 11 arrays for a totai of 18 such bundles. Increased mixed oxide loading to 38
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kg.
July 1974 startup power ramping limited to 3% per hour to reduce fuelpellet/claddinginteraction.
1974 - 1975 Eccs " final acceptance criteria" limits maximum power in fuel bundle.
Increased 11 x 11 arrays to approximately 75% of core.
. Mixed oxide loading increased to approximately 50 kg.
1976 - 1977 Following vendor's PCIOMR (fuel preconditioning) recom-mendations on startups.
1978 & beyond completing changeover to 11 x 11 arrays.
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.(, x BIG ROCK POINT NUCLEAR PLANT Compart::on of Monthly Averago Tomparaturos at East Jordan f( 80 70 L1 kn .a, 60 +_ TT x
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~ U U a: 0 b X g 40 E ^ s J. N 30 x .C E A 20 w 10 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 30-YEAR MAXIMUM EXTREME 30-YE A k MEAN PLUS ONE - STANDARD DEVIATION 30-YEAR ME AN (1940-1969) rX FEB 1.1961 - JAN 31.1963 ave RAGE 30-YEAR MEAN MINUS ONE STANDARD DEVIATION f, 30-YEAR MINIMUM EXTREME P00R ORIGINAL
( BIG ROCK POINT NUCLEAR PLANT Comparison of Monthly Averags Tempsraturcs at Pellston ( 80 ] 70 60 u .u D -1 n N () ~ o 50 ~r _m g y O w 3 d0 U x { { 4-U 30 3 X 20 .I. ~' ( p .3. 10 0 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 30 YEAR MAXIMUM EXTREME - 2 30-YEAR MEAN PLUS ONE - STANDARD DEVIATION 30-YEAR ME AN (1940-1969) M FEB 1.1961 - JAN 31.1963 AVE RAGE 30 YEAR MEAN MINUS ONE STANDARD DEvl ATION 30-YEAR MINIMUM EXTREME P00R ORIGINAL
f k FIGURE 31 BIG ROCK POINT NUCLEAR PLANT (. Comparison of Monthly Average Temperatures at Traverse City 80 70 11 A U --x- - 60 L1 W _t x n 50 -y-e U 30 x C. b 20 .x. b 10 0 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 30-YEAR MAXIMUM EXTREME =- 30-YEAR MEAN PLUS ONE - STANDARD DEVIATION X 30-YEAR ME AN (1940-1969) F / FEB 1.1961 - JAN 31,1963 AvERAC' ! 30-YEAR ME AN MINUS ONE STANDARD DEVI ATION 30-YEAR MINIMUM EXTREME ' P00R ORIGINAL
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) DISTRIBUTION FOR INCOMING MATERIAL 50-155 REC: DAVIS D K ORG: SKIBITSKY W S DOCDATE: 02/08/78 NRC. CONSUMERS PWR DATE RCVD: 02/10/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED LTR 1 ENCL 40
SUBJECT:
RESPONSES TL AREAS REQUIRING FURTHER AMPLIFICATION OF THE DEC 1977 DISCUSSIONS CONCERNING SITE METEOROLGY AND THE EMERGENCY PLAN FOR THE SUBJECT FACILITY. W/ATT CHANGES WHICH HAVE AFFECTED THE FACILITY SOURCE TERM AND GRAPHS. REVIEWER INITI AL: XJM PLANT NAME: BIG ROCK PT DISTRIBUTOR INITI AL-onoooo*********** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ****************** GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE. (DISTRIBUTION CODE AOO1) FOR ACTION: BRANCH CHIEF DAVIS **W/7 ENCL ecti"T* TEE **W/E @ NRC PDR**W/ ENCL INTERNAL: r I & E**W/2 ENCL OELD**LTR CNLY HANAUER**W/ ENCL CHECK **W/ ENCL EISENHUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL GRIMES **W/ ENCL J COLLINS **W/ ENCL J. MCGOUGH**W/ ENCL EXTERNAL: LPP.'S CHARLEVOIX, MI**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL [ DISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 79^^t^^22 SIZE: 3P+1P+6P f/ o0000****************************** THE END
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