Text

App I Analysis,Palisades Plant
	ML20236L680
Person / Time
Site:	Palisades, 05000000
Issue date:	05/31/1976
From:	Conway T, Dinunno J, Englehart R; NUS CORP.
To:	;
Shared Package
ML18052B367	List: ML18052B366; ML20236L668; ML20236L672; ML20236L680;
References
	NUS-1729, NUDOCS 8711110012
	Download: ML20236L680 (74)
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4 4 3 t- . t.i \\ 11 .-). Prepared For: a h CONSUMERS POWER COMPANY. 1 'i By R. W. Englehart J.J. Hayes 3 .j D. A. Sullivan l May 1976 4 NUS CORPORATION a. Environmental Safeguards Division 4 Research Placo Rockville, Maryland 20850 ~ Approved: Approved- - l.t Terrold W. Conway i Idseph J. DiNunno - I Manager / Vice President and Radiological / Land Use Programs General Manager s,

q m H l l . TABLE OF. CONTENTS N > .1 y L' Page No. Eval' ation' of Compliance with 10CFR50 Appendix I , I '. u 1.0 Summary and Conclusions.

11 2.0

' Doses from Liquid EffluentsL 4' e '3.0. Doses from Gaseous Effluents - 5 1 II.. Responses to "AdditionalInformation Needed from HoJders of Permits or licenses to Construct or Operate Light-Water-Cooled. Reactors for which Application was filed prior to - j I I' January 2,1971." I Appendix A. Source Term Information A-1 :- Appendix' B Joint Frequency Distributions

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r - i h i L L (^j. LI. x.) . EVALUATION OF COMPLIANCE WITH 10CFR50 APPENDIX I l t 1.0 Summary and Conclusions The Palisades Plant has been evaluated with respect to its ability to meet the requirements set forth in Section II of Appendix I to l 10CFR50. Specifically, Section II of Appendix I sets forth the follow-ing design objectives: i A. The calculated annual total quantity of all radioactive .l material above background to be released from each light-water-cooled nuclear power reactor to unrestricted .j areas will not result in an estimated annual dose or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 millirems to the total body or 10 millirems to any organ. - B.1. The calculated annual total quantity of all radioactive material above background.to be released from each n '~') light-water-cooled nuclear power reactor to the atmosphere - i will not result in an estimated annual air dose from gaseous effluents at any location near ground level which could be. occupied by individuals in unrestricted areas in excess of [ 4 10 millirads for gamma radiation or 20 millirads for beta . radiation. 2. Notwithstanding the guidance of paragraph B.1: j i (a) The Commission may specify, as guidance on design i objectives, a lower quantity of radioactive material above background to be released to the atmosphere if it appears that the use of the design objectives in paragraph B.1 is likely to result in an estimated annual external dose from gaseous effluents to any individual in an unrestricted area in excess of 5 millirems to the total body; and (b) Design objectives based upon a higher quantity of radioactive material above background to be released to the atmosphere than the quantity cpecified in para-graph B.1 will be deemed to moet the requirements for g (,/ 1

7 r y l1 l s0 j keeping levels of radioactive material fri gaseous [ effluents as low as'is tsasonably achievableAf the applicant provides reasonablo assurance that thi i proposed. higher quantity.will: not result in an esti - 1j mater annual external dose from gase'ous effluents l to any individual in unrestricted areas in excess of: 2 5 millirems to the total body er 15 millirems to,the G / g [ j skin. .,e y 3 .l .p. i C. The calculated annual total quantitymof all radioactive iodint J and radioactive material in partic61ste form abo"e background to be released from_ each light-water-cooled nuclear poviur l reactor in effluents to the atmosphere will not result'in an estimated annual dose or dose commitment from such radio-active iodine and radioactive material in particulate form C """ for any individual in an unrestricted area.from all pathways 4 ' 1 f of exposure in excess of 15 millirems to any organ.. 7 j The evaluation shows that potential doses moet these objectives. eMaxim'um -{ fndividual doses have been estimated for normal opereting conditions and f annual average meteorological characteristics. Detailed results are shown in Table 1 for maximum individual doses. Radioactive source terms were calculated according to the guidance of Regulatory Guide 1.112, using the input data described in Appendix A. The source terms are also presented in Appendix A. I Meteorology information used in the calculation of doses is consistent with Regulatory Guide 1.111. 1 Dose calculations were done in a manner consistent with Regulatory Guide l I 1.109. The NRC LADTAP and GASPAR computer codes were used. These results indicate that the maximum radiation doses as calculated for off-site individuals from all normal sources are well within the requirements of Appendix I to 10CFR50. O 2 _mm

m.~...,- l' R- @jpin ho w s s ? f:' R p. y,l -i i1 a r 3;., t l .l14l {f ?, l ,' ;g;& w o ~ m r. 4 /f ' TABLE 1 x~ ~ COMPARISON.0F MAXIMUM COMPUTED DOSES FOR- . PALISADES PLANT WITH APPENDIX I LIMITS ep.: .g m~ f(i t .Maxirhum for. Appendix I ~ gE LApplicable Section s f L of Appendix I" EYaluation = Palisados - t Limits II.A! Maximum doses from liquid i' effluents;: ' Total body 1(mrem /yr): 0 '. 5 3. 3'

Any organ - (mrem /yr):--

0 '. 7 4 '. L i.: II. B.1 ' Maximum air doses from - gaseous effluents;- FGamma: ' (mrad /yr): .0.36l 10 -; Beta. (mrad /yr):'

0.95 20-un '

Maximum external doses

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'from gaseous effluents;- t

Total body -

(mrem /yr): 0.13 5 ' Skin (mrem /yr): 0.35 15

11. C Maximum dose from ' iodine -

and particulate in gaseous effluents; Any organ '(mrem /yr): 2.3 15 f,i i .i 3 J __1_i__ _ _

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.f. ,h Ig) , g].3 }6 ff . (- 3,4 3 1 .1 A. ly i N 7 1 g' 2iO' pose's fr m Liquid-Ef510$nts M j 9 ' y,n t ' ~ 't / Maximum individual dos $s from liquid efflue'nEs were calculated by the NRC LADTAP. computer cod $, using models given in Regulatory Guide l'.109. (March y.1976). Dose factors, bioaccumulation factors, and the shorewidth faNor as givd in Regulator'/Cididd[1.lf'9 and in the LADTAP code were used, as were use facto s for v/atar and fish ingestion $bd for 4 i

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y, n.. 1.3 < / '/ 'M 'l water related activities. l ts .4 . Radioactive hquid wastes from PaliNdes are dischapJed to Lake ; Michigan.- l ,i after dilution wit';( cooling tower blowdown and dilution flow of 60,000 gpm. This flov/;is via low velocity surface distharge at the shoreline.- l Maximum individual doses were calculated for water and fish ingestion, and for external gxposure for shorenne use, swimming, and boating. The water ingestion pathway was analyzed for an individual drinking water from the nearest municipal water ittbke, located at Sout!rHaven. This - o+ location is 5 miles from the plant, where a dilution factor of 1000 was j q assumed to applyj(Ref.1). For the fish pathway, an effectivaidildtihn fa: tor of 15 was used based on E the following factors. [ Sport fish lik(ely to be taken in the area, rainbcw trout, brown 1. trout, lake trout, and salmon, migrate on the order of 0.9 to d 7 miles per day (Ref. 2). Thus, it is unlikely that a fish would i be exposed to an undiluted concentration on an average basis. j 2. According to Reference 2, it is unlikely that fish resident in a plume show increadid concentrations as a result of their presence, sineb the majority of'their uptake occurs through a O 4 l

g=; x v.. - ,f ' 'g-q 1 ( i f~g M ffood chain. :. Because of the migratory nature of these' fish, W .J<

the effective dilution' appropriate for the food chain'must be much greater than that existing at the plant discharge. -

R 'I JFor the; purpose of this' analysis, a factor of 15 is' believed to be suitably - ~ conservative'., j d

Source terms used in this analysis are presented in' Appendix A.-

- I . The' calculated ~ doses' to' maximum in'dividuals from liquid effluents' are - l summarized'in Table 2, which also. presents the pertinent LADTAP input ~ data used.in this analysis. 13;0 .-Doses'from Gaseous Effluents . Maximum individual doses from gaseous effluents were calculated by the. 5 NRC GASPAR computer code, using models given in Regulatory Guide:1.109 (March,' 1976). The basic source term and meteorological data' entering into the calculations'are described in Appendix A and Appendix B respectively.. Calculations' of maximum individual doses from gaseous effluents have been made for the following exposure pathways: 1. External dos'es due to cloud immersion. 2. External exposure to materials deposited on the ground. 3. Internal exposure.via food chain pathways, including vegetation, meet, cow milk and goat milk. l 4. Internal exposure via inhalation. ) A11' standard or default GASPAR parameter values were utilized, including l 1 dose conversion factors, food intake rates, stable element transfer coeffi- ) cients, and time delays.- s m

t 00000 na 00000 f ) 1 r n y I 5 ) ) ) ) ) / 1 4 2 )4 5 1 s r ( ( ( ( ( r e r ( 1 65 9 6 h g ev 90461 3 r d a i o l 90000 n L 6 4441 7 i e r h 60449 e yb 1 1 1 2 T /g 5 K ( se ) ) ) ) ) 4 2 )4 5 1 t n 00000 1 y - - - - (- a e R e 607 72 d ( ( ( ( ( T 1 1 665 o 705 9 3 B 91 461 4 e 5 g T 2344 1 S s y 3 a )r N U / de O m t I 00000 e n t l S T u ) e r m T A ) 3 s d 1 0222 3 e L L A 231 1 5 ( r ( U U 7 s n p ( t SC l 3 i EL u k e RA s S 9 s ) e o C D r R h NE h t ( A S e n e s 2 O a A m o h E T D D t ) ) ) ) ) ) i 1 435 5 1 T L A L r s B DA t 24000 t r ( ( ( ( ( ( e A i l e 636 49 4 l T T U s 1 2 l u v 91 9 21 0 a U D n d i m I a A L 66781 7 PV r s NI T D e I r PN a AI s T D M n r a AU ) ) ) ) ) ) o g 1 435 5 1 LM t y o r c I d ( ( ( ( ( ( X a o 566 4 9 4 d A F B 269 21 3 n M n a o 501 1 5 T 55781 5 s i 1 0 1 t l u 0 a l 1 u - i d 0 D i 1 v i x dn 5 i 2 r y y e 5 a a h n n t t ot e h n o o = w w h n o i i e o t ot ) i s a i s s t 1 s a t t e u P s e u P s s ( egeg egeg e 5 r gn n n e e r gn n n s I i g u n i g S o 2 I i i u n s I rl mn s I rl mn L mi A D 5 e e e e mi o ht r o ht r t t p sa oia p oia T s a i h wo O x i h wo x FWSSB T E FWSSB E

v i [% ' ? }- U Computed ' doses include the' open site terrain correction factor for the appropriate distance, as given in Regulatory Guide 1.111 (March,1976). The occupancy and shielding factor of 0.7, as given in Regulatory Guide 1.109, was applied. Maximum off-site air doses were determined,'among over-land locations, to be 0.95 mrad /yr for beta radiation and 0.36 mrad /yr gamma radiation at 0.48 miles in both the'SSE and SSW directions. I ' Meteorological dispersion and deposition data were reviewed in con-junction with data pertaining to nearest residences, vegetable gardens, -milk, and meat animals within five miles to determined locations where specific exposure pathways would result in maximum doses. ; The GASPAR ~ input data used to analyze doses at the locations so identified are pre-sented in. Table 3.- Dose results for each location are presented in Table 4. Including both the plume and ground contamination doses, the highest computed external dose rates are about 0.13 mrem /yr to the total body and 0.35 mrem /yr to the skin (both at 0.63 miles S). The highest computed dose due to non-noble gas isotopes is 2.3 mrem /yr to the thyroid of a child (0.88 miles ENE at the nearest garden). i I I a l J

DD 3 2 1 8 1 ) m d ) ) ) ) ) e/ 6 6 6 7 7 t c ee ( ( ( ( ( lp (s 6 7 9 5 6 6 6 6 8 2 eQ s D/ 4 1 1 1 1 n X o i taco ) L m ) ) ) ) e ) l / 6 6 6 7 7 t ac a ( ( ( ( i ( me 6 6 3 0 1 r 6 r s 5 0 1 6 8 p 0 5 7 0 o( o 0 N Q r 5 2 2 2 1 p 1 0 0 1 8 A / T X p A A D ro f T U e P u l l N n a a I o e m k V w i R t c i l A p n n i o P i e n A M C r 3 S c d e t t k A i d a a l s s r E G e e a e o i L D R G M G M B N AT O ITAC e O r L y u er t n u l L l s e t n a a d s A o I c p r a i C t o a p E c E E E E l n g o n P e S N S N N n n o r S i E E E w s i t D o a n e r l g o wi g o h s r w e g l e e b l e r t a t k u t a a t r e c t s e e g n a c) t ns e e , i p m v s a y wl m/ ae m e 3 8 0 0 5 g t l si 6 8 0 5 7 r f o b o D (M a a c a r i f t t 0 0 1 2 2 P e n r e d l a g e e h e e e n t s y v f e o f f f c r f o o o r n n n n e o o o o t i i i i a t t t t w c c c c o a a a a r r r r r i N 1 2 3 4 5 F F F F A >a I

9 4 S n 8 8 9 T i 3 6 4 4 7 N k A S 3 1 5 6 3 F N I ) ) ) ) ) 1 2 2 2 2 y d ( ( ( ( ( 4 8 o 3 3 7 B. 1 4 5 8 9 T 1 1 5 6 3 ) ) ) ) ) ) io 2 1 1 1 2 1 10 d r 3 3 5 f ( ( ( ( ( ( 4 4 0 B 1 4 2 3 2 6 4 y h T 1 1 3 2 1 7 5 1 2 ) ) ) ) ) ) ) 2 1 2 2 2 ( ( ( ( ( ( ( N 8 8 6 5 4 6 0 E n R i 3 6 1 9 1 4 9 k D S 3 1 5 4 6 3 1 L r I I y / I mC e ) ) ) ) ) ) ) 1 2 2 1 2 2 2 r y m d ( ( ( ( ( ( ( o 3 3 2 2 6 6 3 N B. 1 4 2 0 1 6 0 A T 1 1 5 5 6 3 2 G R O S D ) ) ) ) ) ) N 1 2 1 ) 2 1 1 N d O ( ( ( ( ( ( i 0 A ( o IT P r 3 3 8 3 2 4 6 1 4 5 4 6 8 7 A y U h C O O T 1 1 2 1 7 3 2 R L G LA E G I ) ) ) ) ) ) C A S 1 2 2 1 ) 2 3 2 4 E R E P Y E ( ( ( ( ( ( ( 8 8 9 7 0 2 7 L S B G n B R S A i 3 6 0 3 5 7 7 k A E N S 3 1 5 2 3 1 8 T O S E F O ET S D TL L ) ) ) ) ) ) ) U A 1 2 2 1 2 2 3 S U y ( - d ( ( ( ( ( ( E D o 3 3 3 3 2 4 7 R I V B. 1 4 1 4 5 8 4 E I S D T 1 1 5 2 3 1 9 O N D I M ) ) ) ) ) ) U 1 2 1 ) 1 1 1 d M 0 i ( ( ( ( ( ( ( o X I r 3 3 0 1 0 8 4 A 1 4 4 7 1 5 8 y h M T 1 1 3 1 1 2 1 ) ) ) ) ) ) ) 1 2 2 1 2 2 3 S T ( ( ( ( ( ( ( 8 8 0 9 6 6 3 L n U i 3 6 2 9 0 3 3 k D S 3 1 9 1 5 1 6 A a t ) ) ) ) a 1 2 2 1 ) ) ) d 2 2 3 y d ( ( ( ( ( ( ( n o 3 3 5 5 9 5 9 o B. 1 4 2 0 0 4 7 it T 1 1 9 2 5 1 6 ac o l r o f n 3 o n k k e i o l l l t i i b p i d i n M M a t r e n a e T l t c t m u a d a a w e s r e u o h a e r o o e l n D P G I G M G C S no ita 1 2 3 4 5 c n I g

2 Oi REFERENCES 1. Hough, J. L., et al,. " Lake Michigan Hydrology Near Palisades Park, Michigan," Consumers Power Company. 2. Spigarelli, S. A., Cesium-137 Activities in Fish Residing in Thermal Discharges to Lake Michigan. Health Physics 30, j 411-413 (1976). 3. Spigarelli, S. A., et al, ANL-RER Ann. Report, ANL-7960 (III), 69-112-(1973). i i l 1 i I i 10

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[' Q 11.1 RESPONSES TO "\\DDITIONAL INFORMATION NEEDED FROM HOLDERS 'OF PERMITS OR I. CENSES TO CONSTRUCT OR OPERATE LIGHT-WATER-- COOLED REACTORS FOR WHICH APPLICATION WAS FILED PRIOR TO-L JANUARY 2,1971" The following numbered' items are responses to requests for information ' contained in Enclosure 2 to a letter dated Febmary 19, 1976 from.the Director of Nuclear Reactor Regulation, NRC, to R.- B. Sewell, Consumers Power Company regarding Palisades Plant, Docket No. ' 50-255. 1. - The information requested in Appe'ndix B of U.S. NRC Regulatory Guide 1.112 is provided.in Appendix A. 2 '. Distances by sector to the nearest residence, meat animal,- j vegetable garden, cow, and goat to five miles are presented in. h Table 2.1. i r l ( 3. X/ Q and D/Q. estimates out to five miles from the site for the i locations noted in Response 2 are provided in Tables 3.1 and '3.2 respectively. ) 4. The annual average X/Q values were calculated based on on-site Palisades data monitored September 1,1973 through August 31, ) 1974. Annual joint frequency distributions of stability by wind speed and wind djrection were used as input for these calculations. Atmospheric stability classes were determined from g data (standard deviatjon of the wind direction) except that 6T data were used to deter-mine stability class for all observations with mean wind speeds less than 2 mph (generally variable flow). Wind data were monitored at i the 55 ft level. A more detailed description of the meteorological moni-toring facility and representative 5esW6f the~ data are addressed in ~ Responses 6b and 6c. 11

s E E E E E E E E E E E E E 0 0 0 N 5 N N 3 N N N N N N N N N N t 0 4 a O O O O O O O O o O O O O O 'c 2 3 5 G N N N N N N N N N N N N N E E E E E E E E E E E E s 5 0 0 0 0 N N N N N N N N w N N 7 N N 0 8 O O O O O O O O o O O O O 2 4 3 5 C N N N N N N N N N N N N tf .q s T 0 S 0 E E E E E E E E E 5 3 0 8 0 3 0 0 0 N N N N N N N N R 6 8 1 5 A 2 9 9 5 0 O O O O O O O O 1 2 0 2 1 1 2 1 N N N N N N N N E n N e 1 d E r 2 H a E T G L B O A T T SEL I M e E E E E E E E E E E n 0 0 0 0 0 0 1 0 1 N 1 N N N N N N N N N i 9 0 v O O O O O O O O O O o 2 3 5 1 2 B N N 5 N N N N N N N N ecne 8 5 8 6 0 3 8 3 0 E E E E E E E d 3 2 8 0 0 1 6 8 5 N N N N N N N i O O O O O O O s 1 1 0 1 1 1 0 0 1 e R N N N N N N N W W W W ro E E E E WS N WN tc N E N S E S S WWWN N N e N N E E E S S S S S S

i .a 6 6 7 7 7 8 0n ~ 0 0 0 0 0 0 8o 1 d 3 0 3 7 1 4 S t e e 9 1 3 1 1 4 s sf a fb o e. =. 6 6 7 7 7 8 er d ba e 0 0 0 0 0 0 E ld du S 8 8 9, 2, 0 1 l ie l 9 l 3 1 1 5 wt c S n n e d i s e et t o crpn 5. 6 7 7 7 8 e f ss 0 0 0 0 0 0 f E aaa w S 4 6 6 9 9 9 rs o e n 1 1 5 2 1 7 t u cl o i eat sv e l 5 6 7 7 7 8 eQ p ) 0 0 0 0 0 0 h e E T/ d S 2 4 6 3 5 1 X /m e E c 1 1 4 2 1 6 m e 's . u w )6 l s o0 p ( l S f - ; N 5 6 7 7 7 8 0 s q) E ) r d 0 EU 4 O 0 0 0 0 0 0 n o p Y )f I t 7 2 TL i 4 5 9 w2 c I A / T E 4 5 8 a o S V C 1 n f E 1 1 4 2 1 5 e e 3 SEQ/ R ht t 1 t t n 8 I ( 1 D/- D i e 3 cwm h r X A 3 S 7 D 7 7 7 8 h 's s t i E/ 6 7 E I L LG1 N 0 0 0 0 0 0 wiu B A A/ E I j 6 P R9 W N 8 9 2 6 0 1 md A a T E( E V 8 9 3 1 1 4 o0 r1 n A f i L n xar A o0 re i 0. t U t 5 6 7 7 7 8 c N 0 0 0 0 0 0 e2 n N r e A E 6 8 8 8 8 2 d .o i ,p N 1 1 5 2 1 7 eg.h h t t ei ( s w ad l e e dt 5 6 7 7 7 8 ad e o 0 0 0 0 0 0 i n vm E if e N 0 2 0 0 3 2 e r w N 1 1 4 2 1 5 d bb o l saf ^ i r ei nr a oa i e t en c et e u 1 e r c i l t n) 5 4 3 3 2 0 d ah vg am 0 1 2 3 4 7 d t t ( 8 4 0 6 2 0 nQa s 2 4 5 7 2 t / r i D WXt 1 s O ( U l

u 6 7 7 7 7 8 0 0 0 0 0 0 8 9 2 0 2 5 N 8 9 3 1 1 4 6 6 7 7 7 8 0 0 0 0 0 0 W N 9 2 0 1 4 7 4 N 9 1 2 1 5, 5 6 7 7 7 8 W 0 0 0 0 0 0 N 1 3 6 0 6 7 1 1 4 2 1 6 W 6 7 7 7 7 8 N 0 0 0 0 0 0 W 3 6 3 7 1 7 8 9 3 1 1 4 ) e 2 5 6 7 7 7 8 f 0 0 0 0 0 0 o W 2 3 4 2 5 9 2 ( 1 1 4 2 1 5 1 ~ 3 EL B 6 7 7 7 8 8 A W 0 0 0 0 0 0 T S W 9 2 1 F. 6 1 6 6 2 1 7 2 6 7 7 7 8 8 0 0 0 0 0 0 W 1 9 6 3 3 3 S 7 7 2 1 8 3 w m 6 7 7 8 8 8 W 0 0 0 0 0 0 S 3 S 9 0 2 9 5 3 4 1 6 3 1 ecna) 5 4 3 3 2 0 t 7 s m 0 1 2 3 4 i( 8 4 0 6 2 0 D 2 4 5 7 2 1 ~ l-

0 0 0 0 E S S 1 9 5 2 4 5 1 8 2 1 6 2 7 8 9 9 0 0 2 0 0 0 0 1 1 E f 4 6 o S 5 3 7 7 1 1 1 3 1 9 3 eg a ~ P 7 9 9 9 0 0 0 0 0 0 1 1 E 3 7 2 7 6 sd S 1 e E wt 1 9 2 1 6 2 oa l i f v d e 8 9 9 0 0 0 r nb ) 0 0 0 1 1 1 iwb a "m - E 5 8 9 7 0 1 n e e ( o 4 3 1 4 2 1 h r i t a S t E c h s U) e c e r E L4 8 9 0 0 0 1 i 0 0 1 1 1 1 h u i T A7 D l E wa ISV/ 2 1 dN 0 5 2 3 8 0 m v SQ3 nE i 3 2 7 3 1 7 oQ 3 E// E DD8 W r/ f L A D B S E3 no G7 A I i. T L A / 8 9 0 0 0 1 t )8 AR1 0 0 1 1 1 1 c0 0 P E/ e8 r V (9 E A' N 6 2 3 9 6 1 i 1 0 d 0 t 2 2 6 2 1 6 L e e A h s2 f U t f n s o e N t N 8 9 0 0 0 1 aet A E 0 0 1 1 1 1 d bir N el w N 5 0 5 9 2 3 nl i i s wi 3 3 8 3 2 8 fe d d8e-st 0 8 9 9 0 0 0 c1 i 0 0 0 1 1 1 n e of x f N 2 4 3 7 2 2 a0 i tcr0 5 4 1 5 3 1 eo rt 2 c i De s. d g ne e ih W T (e cn 5 4 3 3 2 0 a) 0 1 2 3 4 7 s (m t 8 4 0 6 2 0 i 2 4 5 7 2 D 1 s I

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W 0 0 0 0 1 1 N 7 9 9 9 0 ~ N 9 5 2 4 5 1 1 8 2 1 6 2 0 2 0 0 0 0 1 1 W 2 N ~1 3 4 f 0 8 5 o l' 8 2 1 6 2 eg aP 8 9 9 0 0 0 W 0 0 0 1 1 1 N W 0 '7 8 3 7 sd 1 e wt 7 6 l 7 4 1 oa l i f v I e 7 8 9 9 0 0 r nb ) 0 0 0 0 1 1 i wb W3 ~ 4 9 0 1 1 a m n (' e e o 1 1 3 1 7 3 h r i S t t a E c h s U) er c e E L4 8 9 9 0 0 0 i i 0 0 0 1 1 1 h u T A7 2 S V/ DW l I wa 1 dS 3 0 0 0 9 v 1 SQ3 iW m n 3 8 7 2 9 5 1 oQ E// E DD8 W r/ f L A D B S E3 n A I G7 o T L A / 8 9 0 0 0 1 i. t ) AP1 0 0 1 1 1 1 8 c0 P E/ W 0 e8 V (9 1 r S 4 9 1 7 9 i1 0 A d 0 3 2 8 3 2 7 t L e e A h s2 f U t f n N' s o e N 8 9 9 0 0 0 aet t 0 0 0 1 1 1 A W d bir el w S 8 1 2 3 9 1 nl S i i s 4 4 1 5 2 1 f wi e d d8e-st 0 8 9 9 0 0 0 i c1 0 0 0 1 1 1 n e f x of S 9 0 4 5 6 4 ia0 t 5 5 1 6 3 1 cr0 eo rt 2 c i De s. d g ne e ih W T (e cn 5 4 3 3 2 0 a) 0 1 2 3 4 7 s (m t 8 4 0 6 2 0 i 2 4 5 7 2 D 1 n "c l l l

i% ,g Y ) 'u.) The calculation of annual average X/Q values, as presented in Table 3.1, is ' based on the'"'-aight-Line Airflow Model as presented in Regulatory Guide 1 J 1.111 (Ref.1). Conservative adjustment factors were applied to the. X/Q j values as suggested in Reference 1 for sites in open terrain. A further des - cription of airflow trajectories in the site vicinity is addressed in Response 7, including discussion of the use of open terrain adjustment factors.- _l The X/Q values were computed based on the following equation that was . adapted from Reference 1: a f X) 7 7 2.032 F lik - (Eq.1) ] = kQ /j U S i=1 ' k=1 gzg Equation 1 computes the ground level annual average X/Q value for. sector j i ~ at' downwind distance x. This equation assumes a uniform horizontal dis-1 tribution of the effluent within a 22.5 sector based on the 16 compass directions centered on true north (Ref f 1). The definition of symbols is as follows: F fra tion of the time based on all observations that wind Uk speed class k occurs in stability class i and sector J. stability class A through G i = V 17 ) L __.____11_

S effective vertical dispersion parameter for stability = i class 1 (meters) l U,k midpoint of wind speed class k (meters /sec) = I where S is defined (Ref.1): g [ )I 1 ,2 S~ + 0.5 H = z z (Eq. 2)- o vertical dispersion parameter (meters), based on = g 1 Reference 2. height of the containment, 53.3 meters above H = ground level. The factor' O.5H accounts for enhanced diffusion due to the butiding h-wake effects of the containment. The butiding wake factor is not allowed to increase the effective dispersion parameter by more than a factor of Naz* The term F includes all observations associated with sector j and stability class 1. Calms were distributed by the same proportion as the directional distribution within each stability class of the lowest non-calm windspeed class and assigned a windspeed of 0.3 mph.

1 Additionally, a set of X/Q values allowing for plume depletion were generated j

from X/Q values computed per equation 1. For a ground level release, plume depletion is only a function of downwind distance. Depletion factors were obtained from Figure 3 of Reference 1. one-half the starting threshold of the enemometer. 18^

2 [.{: l. .l /f i UI Deposition per square meter (D/Q) for a ground level release was computed based on the' relative deposition curve as presented in Figure' 7 of Reference 1. The following is the equation as indicated in Reference 1: l Relative Deposition) l f)/j-l Conservative Adjustment)l l f () f l l l ( Rate j ( ( Factor i (D/Q)j. 4 2ax (Eq. 3) where f) is the frequency of the wind' direction from sector J. The.meteo-l rological data and conservative adjustment factors are the same as describ-ed in Response 4 (X/Q calculations). 5. ~N/A 6. Meteorological Program Data a) Annual joint frequency distributions of wind speed and wind direction (55 ft level) by atmospheric stability class are presented in Appendix B for the period of September 1,1973 through August 31, 1974.

I b)

A description of meteorological data representativeness with respect to local diffusion patterns and long-term representa-1 tiveness was provided in a submittal frem Consumers Power to NRC (Ref.4). c) The on-site meteorological program at the Palisades Plant consists of a wind direction, speed and variance sensor and two temperature sensors. Wind direction, speed and variance are measured by a MRI combined cup and vane sensor (Model No.1075). Ambient temperature and a {

Monthly distributions are contained in Reference 3 i

19 i

differential temperature are measured using Rosemount temperature sensors in Climet aspirated shields (Rosemount 104ABG-l'and Climet 016-1). All data are recorded (15-minute time intervals) continuously on magnetic tape - t (Westinghouse WR-4C). Wind direction and speed sensors' starting threshhold is ( l 0.75 mph. Wind direction accuracy is 1.5%, variance accuracy is 5% and speed accuracy is 1-25 mph 10.75 mph,. l l 2 5-30 mph i 1.0 mph and 50-100 mph 12.0 mph. The l ambient temperature range is from -20 F to +100 F i 0.375 F, and differential temperature from -4 F to +8 F i 0.174 F. The equipment is mounted on a 55-foot utility pole on top of a sand dune located behind the site information center. This places the wind speed / direction sensor at approximately stack height. Temperature sensors are placed approximately 45 feet apart. Additional information on the Palisades meteorological tower and surrounding topographic features is presented in Reference 4. d) Response 9 shows that gas batch releases occur pre-ferentially during daytime hours when atmospheric dis-persion conditions are generally more favorable. Under these conditions, use of the average annual X/Q is consid-ered conservative for dose estimation purposes. In Reference 4, Palisades meteorological data have been shown to correlate well'with University of Michigan cooling tower study data O 20

he 7 c i

k,.

,N I f f d N and-X/Q's' derived from the Palisades ' data result in conservative values relative to Natibnal' Weather Service 1 - Data for Muskegon., d -7. Figure 7.1.is an annual.. wind rose for the Palisades site based on the data period 'of September 1,1973 through August 31, 1974. The j . wind direction ' distribution is fairly uniformly distrib'uted; the predom-3 linant flow is from the SE, with 'a' secondary maximum from the'W. L On-j . shor'e flow from Lake Michigan occurs approximately.55 percent of thei time.f Mean wind' speeds associated with onshore flow are relatively_ high as observed in Figure.7.1. j l The Palisades Nuclear Station is' located on the eastern shore of Lake

Michigan; the meteorological tower situated approximately 900 ft from -

the shoreline. Excluding approximately 100 ft of beach, the vicinity - of the site is characterized by. wooded terrain with distinct hill's of ' ') approximately 100 to 200 ft in height. After the first mile inland, the overall terrain rises gradually.or remains j level depending on the sector. The effect of the dense tree cover, 'i:\\ averaging approximately 30 ft in height.on the nearby dunes, would be . expected to generally increase mechanical turbulence locally and some-- what decrease mean wind speeds.. Another significant localized modification to general airflow for this site is associated with the land-lake interface. Particularly during conditions with light winds and weak pressure radients, airflow patterns are considerably complicated by the localized flow. However, for annual average X/Q calculations straight-line trajectory models are considered to be a reasonable estimate (Ref. 5); particularly when con-servative adjustment factors (based on open terrain value in Reference 1) tO( 21 = _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ - - _ _ _ _ - _ _ _.

N NNW NNE NW / 7 NE ',L ~__ n-- Wim EN'E N j. i ~. f 10 Calm E ,g ) { 1 10 5 3 9 / s WSW ESE 1 1 l SW SE SSW SSE musummmme Wind Direction (%) reer/m Wind Speed (mph) +' l Figure 7.1 Palisades, Enclosurc 2 Annual Wind Rose (9/1/73 - 8/31/74) O 22

w r-c " ' ;[- if: ,;,s ~ '.c ,i y _y. t 1 M 4. are.'used to account for typical open terrain airflow variations. ,q After the first mile inland, airflow encounters relatively' minor topographic.

discontinuities._.

8 ' One copy of the topographical: maps covering'a' ten-mile radius'.from; y s . the Palisades Plant is included with this submittal ~., y t Maximum topographical elevation'versus distance from Palisades in each sector, in one' mile increments, is providedlin Table 8.1. (ltj i 9. The number of gas batch releases from the venting'pointiat top of' W . the containment building versus time of day is presented in Figure 9.1. It-is seen from this plot that the number of releases:is much lower during nighttime and early morning he'urs than during daytime hours. The numbers q of releases are maximum in mid-afternoon and minimum before sunrise. O

Diurnal distribution of the mean hourly _ win'd speed was' examined for the.

1

region.. The' time of minimum wind speed is usually reached at about 2000 EST. The speed then remains constant or rises slowly for the rest of the night until dawn.~ The wind speed increases during the day until the time of maximum wind speed is reached usually about 1400 EST.

The diurnal distribution of percentage frequency of stable atmospheric conditions also exhibits similar fluctuations (see FSAR, Appendix D, Figure 2). Generally, the most favorable dilution conditions occur during daytime hours. L 'It is concluded that the maximum number of gas batch releases occurs "during the atmospheric conditions which are favorable to good dispersion. .The average annua 1X/Qfor the site for estimating radiological doses from 'these releases would be conservative. j 23 n o

a. W r._ N W a_ N W a W W w* O S W M O W RF S 9 E C N 0 A W w 0 0 4 0 1 0 0 0 0 T S 0 6 2 4 2 0 0 0 4 2 S S 7 7 8 7 8 7 7 7 7 7 I D F O a ) 0 0 1 0 0 0 0 0 0 0 N L S 2 6 5 8 6 0 2 0 8 8 O S 7 7 7 6 6 7 7 7 6 7 T M I C N te E 0 0 0 3 0 9 0 0 0 0 U e S 8 0 6 6 0 0 8 3 8 2 F F S 7 7 6 6 7 7 6 6 6 7 1 ( A 8 R S E A.O L T B S C 0 0 0 0 0 0 0 0 0 0 E 8 6 8 0 0 0 0 0 2 2 A N E S 7 6 6 7 7 7 7 7 7 7 T O S ~ IT Y A B V S E 0 0 2 0 0 0 0 0 0 0 E E S 8 4 8 2 8 0 2 2 2 2 L D E 7 6 6 7 6 7 7 7 7 7 E A E S T IL IS A F P F 0 0 0 0 0 0 0 0 0 0 O E 8 2 8 2 0 0 8 0 0 8 7 6 6 7 7 7 6 7 7 6 M U na M E 3 0 2 0 0 0 0 2 4 9 g i N I 1 4 6 0 0 6 4 6 7 8 h X E 8 6 6 7 7 6 6 6 6 6 c A i M M e 0 0 0 0 0 0 0 0 0 1 E 0 0 6 6 8 8 6 2 4 4 k N 8 7 6 6 6 6 6 6 6 6 aL y b de E i N 0 0 0 0 0 0 0 0 0 0 p u 4 4 0 4 4 6 8 6 8 6 N 7 7 7 6 6 6 6 6 6 6 cc o s i N aera ~ s e tac e i c )s 0 d 1 2 3 4 5 6 7 8 9 1 n n e I al t i sM O 1 2 3 4 5 6 7 8 9 i D( = 1 I

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O\\ l REFERENCES j e 1. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," II.S. Nuclear Regulatory Commission, March 1976. 2. Slade, D. H., Editor, Meteorology and Atomic Energy, TID-24910, U.S. Atomic Energy _ Commission, Section 3-3, 1968. I' 3. Letter, Sewell (Consumers Power) to Knighton (NRC), July 15, 1975,

Subject:

Docket 50-255 License DPR-20, Palisades Plant Amendment 28, Section 7, Appendix F. 4. Letter, Bixel (Consumers Power) to Director of Nuclear Reactor Regulation (NRC), October 6,1975,

Subject:

Docket 50-255 License DPR-20, Palisades Plant Amendment 28, Section 7, Appendix F. 5. Van derHoven, I., " Atmospheric Transport and Diffusion at Coastal Sites," Nuclear Safety, September 1967, Vol. 8, No. 5, pp 490-499. ? r O1 26 --__--__-_--_a

1 1 ir s l t .i m \\ .i. m APPENDIX A . i Source Term Information . 1 t' J.' J .I i I = = t I 1 l \\ I

h;'h g : '~ . :,, Y p 1

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.g j APPENDIX A - . x.- g . SOURCE TERM INFORMATION-a.- The information requested in Appendix B of U.S. NRC Regulatory Guide 1 '1.112, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors, Data ) i Needed for Radioactive Source Term Calculations'for Pressurized Water. J 1 LReactors," is provided herein. This is the' latest. version of Appendix D ] ~ of Draft Regulatory Guide ~ 1.BB. .( y a Source terms to the environment, obtained by using the GALE Code and j the information presented here, are included. ') P l i. u 7 .j. i { -] 4 rt i J A. j

1. General i })e a. Maximum core thermal power. 2 638 MWt 5 Source: FSAR, Palisades 11 ant, Docket No. 50-255 b. The quantity of tritium released in liquid and gaseous ' effluents. Liquids: 520 Ci/yr - Gases: 530 C1/yr Source: NUREG-0017 and GALE run 2 ' Primary System a. Total mass of coolant.in the primary system, excluding pressurizer and pr' mary coolant purification system, at i full power. 481,674 lb Source: Plant Technical Data Book l l b. Average primary system letdown rate to the primary coolant j purification. system. 40 opm Source: FSAR Table 1.1 c. The average flow rate through the primary coolant purification i l system cation demineralizers. 5opm Source: Engineering judgement l d. Average shim bleed flow. 1.4 gpm Source: Plant Staff O A-2 a mmm i __mma

m

.]

1, p,g + 4 u _1, 1 '/'i :_ . T. '

m k.

' 3. - Secondary System a. The number and type of steam generatois'; the type of chemistry used; carry-over factor for iodine and y non-volatiles. 2,; recirculating type; AVT_, ['#' j' " Source: Plant Staff ,c Carry-over factors: Iodines 1.'01 ', non-volatile's O' 0019" i Source: NUREG-0017 - g b. Total steam flow in secondary system. 6 ' 11. 6 x 10 'Ib/hr Source: FSAR Table 4.5 ?' c. Mass of liquid in each steam generator at full power.. 12 0,341 lb Source: Steam Generator Instruction Manual 'I CE Book Number 29 66-13, pp 'l-3. 7N i d. The primary-to-secondary leak rate 100 lb/ day Source: NUREG-0017 e. Description of steam generator blowdown and blowdown i purification systems. Steam generator blowdown rate. The blowdown treatment system is described on draw 7 "' ings M-22 6 and M-651. A full flow Powdex condensate demineralized is being installed; alternate blowdog treatment is to flash and direct to the main condenser L for treatment by the condensate demineralized. Blow-down rate is 10,000 lb/hr. Source: Referenced drawings and plant staff (drawings attached). . r. U A-3 m__ _m.___.__.__

1 f. Fraction of blowdown treated and applicable DF's. Fraction treated is l.0 by either method described in 3.e. Applicable DF's: Treatment Method' .I_, _C_s Other Misc. Waste System 100 2' 100 Condenser demin. 10 2 10 ) -) Source: Plant Staff and NUREG-0017 i e g. Condensate demineralizers (1) Flow rate .l_6,800 opm (2) -Demineralized type - Powdex j (3) Number and size - 4, 5600 gpm each i (4) Replacement frequency -One everv 7 to 30 days l 1 (5) Ultrasonic resin cleaning - No - ] -(6) Regenerant volume - Not regenerated Source: Plant Staff 4. Liquid Waste Processing Systems a. Tabular information See Table B-1 (1) Clean waste system (also processes shim bleed) normal treatment includes degassing of shim bleed, collection' in four 50,000 gallon clean waste receiver tanks, pro-cessing through two (in series) H+OH-boron saturated ion exchangers, a 20 gpm evaporator, and a polishing demineralized (H+0H ). Process liquid is normally ~ totally recycled for primary system makeup. For the purpose of this analysis, processing is assumed to j include only one H+0H boron saturated ion exchanger, ~ evaporator treatment, and 100 percent discharge through two 5500 gallon treated waste monitor tanks. O l A-4

e i:

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MkN#NmNNw =Ome@9NmNMMMPWMmmNwMmN m u K4 w> M W HwNNmwnc wmomNmmNmOOONmNmmeMmO E U0000000 MOOOOOOOOOOOOOOOOOOOOO m W MmW++ ++ ++ + H+ + + 94 0 +9 3 +++ 3 9 + 9 + + 0 ++ T M JM WWWWWWW UWWWWWWWWWWWWWWWWWWWWW 3 4 $>CmMOOMNr Tho@ CFNOphMereceeDOHCO M W A42hCOMwem OmNN@cPahwNONrhwhmmkN4 J JO4 e e e e e e e O e e e o e e e e e e e e e e e e e e o e e M W 4w NMPWhwN 2*ONNwMmerwmwee>Newwwem K g I 2 E 0 W r W M 2 1 3 O M O 1 1 F E 3 M M OmW@@eOP M4POphhapommNNMWeekhcOOJW J KmM@mm4M Me#@PNNNNMMMMMMMMMMMow du M U N N M mmmmmmmmmmmmmmmmmJHu u 3 DEFWWOO4 MeTouwWWWMWMWMMMMMM444JOW 2 uu2WhuuZ 62MEbbebe U uumeJ4ew A-6

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Sources!of information are the attached P & ID's and

. process flow diagrams for system capability; plant K ' staff for average input flows, fraction of primary coolant-q system activity, and normal operating mode. Collection, H U processing, and discharge times and system DF's are. q calculated in accordance with NUREG-0017 - l (2) Dirty waste system normal treatment' includes collections in one 3800 gallon dirty waste drain tank (internally i split into two sections), holdup in three 20,000 callon miscellaneous waste holdup tanks, evaporation-(at 20 gpm), and demineralization in one of two H+OH 'lon- ~ L exchangers (the other is currently dedicated to blowdown, processing). ' Processe'd liquid'is directed to a 75,'000-gallon utility water storace tank, from which 100% is being recycled. ' For the purpose of this analysis the same treatment is assumed, but the processed liquid is t 1 directed to the filtered waste monitor tank (5500 gal) from which 100 percent is discharged. Source's of information are the attached P & ID's and -i process flow diagrams for system capacility; plant staff for average input flows, fraction of primary coolant system l activity, and operating mode. Collection, processing, and discharge times and system DF's are calculated in i accordance with NUREG-0017. (3) Steam generator blowdown presently is being treated in l the dirty waste system by one H+OH ion exchanger and ~ is completely recycled for in plant use (primarily for j secondary system make-up). The plant is being modified A-7 ___ _ A

./ ' '1 i to include a full flow-condenser demineralized (Powdex). When installation is complete, an alternative treatment method will be to direct flashed blowdown to the con- ) denser hotwell for treatment by the condenser deminerali-zer. By either method the processed 11 auld is fully re-cycled and source terms are not significantly affected. For tha purpose of this analysis, treatment in the Miscellaneous Waste System and complete discharce is assumed. Source of information is plant staff and httached P & ID's and process flow diagrams for system operation capabilities and plans. i b. P & ID's attached (1) CVCS, Drawing M-202 ) (2) Clean waste system, Drawing M-210 (3) Dirty waste / caseous waste systems, Drawing M-211 -l (4) Steam cenerator blowdown system, Drawing M-226 (5) Clean radwaste evaporator system, Drawino M-650 (6) Miscellaneous radwaste evaporator system, Drawing M-651 Process flow diagrams (1) Radwaste System Flow Diagram i 5. Gaseous Waste Processing System a. Volume of gases stripped from the primary coolant 140 ft / day or 41,000 ft /yr Source: NUREG-0017 b. Description of process used to hold up gases stripped from the primary system during normal operations and shutdown. The cas surge tank collects from sources as shown on 1 A-8 . _ - _. - _ _. _ - _ _D

l i l \\ FSAR Figure 11. 9 (attached). The gas surge tank dis-charges to one of three compressors which pressurizes i one of six waste gas decay tanks. There are three 100 cubic foot tanks and three 225 cubic foot tanks, all having a design pressure of 120 psig. Source: FSAR Section 11 c. Description of normal operation Operating mode is to alternate large and small tanks. Fill time is calculated at 7.8 days; holdup time is calculated at'31 days, based on one tank being filled ~ and one held in reserve. Source: Plant Staff and NUREG-0017 d. HEPA filter There is a HEPA filter on the waste cas syste_m discharge. DF taken is 100 for particulate. Source: NUREG-0017 e. N/A f. P & ID's and process flow diagram attached. (1) Dirty waste / gaseous waste systems, Drawing M-211 (2) Radwaste System Flow Diagram 6. Ventilation and Exhaust Systems See Table B-3 O A-9 I

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m.. 4 i e ENCLOSURE 2 O PROPOSED TECIINICAL ' SPECIFICATIONS CHANGE T I .i i O L-_ m

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,1.~ .b s-I - r ' F i CONSUMERS' POWER COMPANYJ i 1 , p'0CKET 50-255~ .,j REQUEST FOR CHANGE D.THE TECHNICAL' SPECIFICATIONS 'l 4 LICENSE:DPR-20 3_ s,c -] J [, lFor the; reasons hereinafter-set' forthL it is requested that the Technical Speci : i

ficationsLeontained in Provisional Operating' License DPR-20,l ocket 50-255, Tissued?

'N D - to Consumers Power. Company-on October 16; 1972 be' changed as follows. I. LCHANGESL - H 1 AL Change t'he :first paragraph of, the objective of.Section 3 9' as follows': T ~ "Tocdefine the condition forL release of radioactive vastes to the closed-- N[ cycle. cooling blowdown discharge mixing basin and'to thetplant vent'to assure that any radioactive' material released is 'keptLas low as' is-rea- - sonably achievable in conformanceivith 10 CFR,50, Appendix I, and~in'anyt j\\ . event, is within the limits t of 10 CFR 20." a .4 f B., Add'new Section.3 9.6 to read as follows: "3 9.6' Notwithstanding Specifications 3 9 1 through 3 9 5 and'Special i Technical Specifications Section S-2, the quantity of all radio-nuclides determined to be released during any' calendar: quarter i shall not. exceed'one' half the design basis annual quantity' cal-culated'from values in Table 3 9.6-1. Calculations shall be . erformed for each batch release, and weekly for continuous-p 1 g f <~0.5 j releases by the formula: I < A /C wherei Ag = Cumulative quarterly activity of nuclide i identi- .) fied in liquid releases _ (C1). O = Design objective annual quantity of radionuclides i g from Table 3 9.6-1 (C1). The design objective annual quantities of liquid radioactive effluent are based upon 3 millirem to the total body or 10 millirem to any organ of a real individual." a >O 1 I / y

m... g, Q', y },, 3' + 3 at y + fi j '4l ~#- 1 y. (..; 3 O. Renumber.the following sections.as;specified below: H F." ~ "" - m L. Present Number Pr'oposed' New Number t. ~ ' ' .3 9.6' 3 9.T! s Y 397L 3 9.8 r -398.

3 9'9 3 9 94

.3910 3 9 10E 3 9 11 s Gaseous Waste Gaseous Waste ~ '3 9 11-3912 319 12- -3 9 13-i .D.. Change number and. reference.of 3 9 13'as follows: H "3 9 14: Following isolation and prior _to. release of gaseous wastes: from the waste gas-decay, tanks, the' contents.shall be sampled and analyzed to determine compliance with 3 912 jarid 3 913." w ? E. Renumber Section 3 9 1h as~3 9 15 F. Add new Section.3 9'16 as~follows: i "3 9 16. Notwithstanding Sections 3 9 12'through 3 9 15:and Special Technical Specifications Section S-2 5,; the quantity of all - radionuclides' determined to be released during any calendar quarter shall not exceed one half the-design basis annual quan-tity calculated from the values given in Table 3 9 16-1. Calculations shall be performed for each batch release, and-n . weekly for continuous releases.by the formula: fE5,A/Cf <_ 0 5 g where: Ag = Cumulative quarterly activity of nuclide i identi-fied in gaseous relea.se'(Ci). A C = Design objective annual. quantity of nuclide i from 1 Table 3 9 16-1. The design objective annual quantities of gaseous effluents, and radioiodines and radionuclides in particulate form released' to the atmosphere, are based on: (1) ' Air dose of 10 millirem from beta radiations or 20 milli-rem from gamma. 1. L 2 ___..i_______________________.________

.) 1 i< ~Y "(2)' Dose to a real individual of 5 millirem total body or 15 millirem to skin. '(3) Dose to a real individual of 15 millirem to any organ from radioiodines and radionuclides in particulate form." G. Renumber the following sections specified below: Present Number Proposed Number i 3915 3917 3 9.16 3918 H.~ Add new Section 3.9.19 as follows: "3.9 19 In the event the quarterly values calculated for released nuclides i exceed one half the design basis guides in Specifications 3 9.6~ j or 3.9 16, the following actions shall be taken: (1) Perform an investigation to identify the cause for such release rates; j (2) Define and initiate a program of corrective action; and (3) Report these actions to the Commission within 30 days from [V,-~,T the end of the quarter during which the release occurred." I. Delete presently numbered Sections 3 9.17 and 3 918. J. In the basis, change the last three lines of the first paragraph on Page 3-53a to read as follows: ... reduce the discharged radioactivity to levels which are as low as is reasonably achievable, and in any event in accordance with Special Tech-nical Specifications Section S-2.2 and 10 CFR 50, f,ppendix I." K. In the basis on Page 3-54, change the first paragraph to read as follows: "A high radiation monitor shall signal to automatically close the vaste gas decay tank discharge valve when the. release rate exceeds that speci-fled in Specifications 3.912 and 3.913 If the gaseous vaste cannot be i released at levels within the requirements cf 10 CFR 20, Appendix B, the reactor shall be placed in the hot shutdown condition in order to elimi-nate the production of fission gases." L. In the basis on Page 3-5b, change the second paragraph to read as follows: "The 15-minute limitation on gaseous release rates, not in excess of 10 times the annual average limit, allows operational flexibility. Quarterly f% g ) releases vill be maintained in conformance with Specification 3.9 16." v 3 = - - - - - - - - -. _ _ - - - - - _ - - - - _. -

i o M. In the basis on Page 3-5h, change the last line to read as follows: "... nearest postulated cov 1.5 miles southeast of' the plant. Use of the 1.5-mile distance is conservative based upon present.loca-l tion of the nearest actual cow." i N. In the basis on Page 3-55, change the first sentence of the first i paragraph to read as follows: "The formula of. Specification'3 9 12 j insures that 10 CFR 20 annual average dose rates -vill not be exceeded-at'the point of maximum offsite dose. Application of this formula is 1 contingent upon release quantities remaining within the limits of Specification 3 9 16." 0. In the basis on Page 3-56,. add new paragraph following end of the first paragraph as follows: "The annual design basis quantities specified in Tables 3 9.6-l'and 1 l

3 916-1 are based on models and data contained in the June 4,1976 Appendix I submittal. The design basis quantities are in accordance with the guidelines of Appendix I to 10 CFR 50. Conformance with

,.m Appendix I is deemed a conclusive showing of compliance with the 'as low as practicable' requirements of 10 CFR Sections 50.3ha and 50.36a. Design objective annual quantities are based on models and data such j that the annual exposure of an individual is unlikely to be substan-tially underestimated." P. Add new Section b.11.4 as follows: "h.ll.h A curvey vill be performed annually, at the beginning of the agricultural season (May through June), to confirm locations of the nearest milk cow, milk goat, moat animal, vegetable garden (>500 square feet in area), and resident in each sector to a distance of 5 miles from the release point." Q. Renumber the l'ollowing sections as specified below: 'Present Number Proposed Number 4.11.h 4.11 5 h.11.5 4.11.6 h.ll.6 4.11.7 4.11 7 h.ll.8 fq t L/ h

ll I t r. J-l~ %./ R. In'the basis on Page 4-56, change Item 1-to read as follows: ) "1. Measurement of radiation levels in the sampled media is done in 1 such a manner to assure compliance with 10 CFR 20, Special Tech nical Specifications and 10 CFR 50, Appendix I." S.-. Add the following two' tables.to the. basis of Section 3 9 (following Page 3-56): 1 I \\ Q) i l t I l i f^%. h 'J 5

,b 1 b. t f V i p -l p j

, ("5j.

t s . TABLE 3.9.6-1 Liquid Effluent Design Objective Annual Quantities i d Design Objective Dose Factor Annual Quantity 4 Nuclide Organ (mrem / Curie) (Curies) I -H-3' Tot' Body 1.31E-06 2.29E+06 I Cr-51 GI 1.49E-03 6,730' 'Mn-54' GI 6.22E-02 '161 Fe-55 GI 1.21E- 02 827 zFe.GI 3.7TE-02' 265 I Co-58 GI 8.38E-03 1,190 co-60: Tot Body b.50E-01 .6.67 Rb-86 Tot Body. 2.28E-01 13.2 l Sr-89 Bone 1.0TE-02 935 1 [\\ .Sr-90 Bone 1.'6hE-01 61.0 Mo-99 GI 1.11E-03 9,020 Te-99m GI 6'88E-05 145,000' Te-127m GI 1.Q1E-01 99.2 Te-127 GI 2.85E-02 259 l Te-129m GI' 2 57E-01 38.9 Te-131m GI 3 73E-01 26.8 Te-132 GI 3.h2E-01 29 2 I-130 Thyroid 5.28E-02 190 I-131 Thyroid 3.2hE-01 30 9 I-132 Thyroid 1.32E-02 755 I-133 Thyroid 4.05E-02 254 I-135 Thyroid 2.83E-02 353 Cs-134 Tot Body 2.83E+00 1.06 Cs-136 Tot Body 3 9hE-01 ' 7.61 Cs-137 Tot Body .1.67E+00 1.80 Ba-lho GI 1.86E-03 5,390 -[j ' La-lho GI 2.57E-02 390 Np-239 GI 2.66E-03 3,750 i 6 t

._--..y i h; .i ~# ((,-. s 3 .v' TABLE 3 9.16-1 Gaseous and Particulate Design Objective Annual Quantities Design Objective Dose Factor Annual Quantity Nuclide _ Organ (mrem / Curie) (Curies) L ,H-3 Soft Tissue 2 70E-04 55,600 'C-lh Soft Tissue 4.40E-02 341 Ar-h1 Air' Dose (Y) 3 53E-03 2,830 Mn-54 GI 5.87E-01 25.6 Co-58 GI 2.66E-01 56.h I Co-60 GI 1.40E+00-10 7~ Fe-59 GI 5.ShE-01 27.1 'Kr-85m Air Dose (B) 1.20E-03 16,600 Kr-85 Air Dose (B) 1.01E-03 19,800 l [ Kr-87 Air Dose (B) 7.80E-03 2,560-Kr-88 Air Dose (y) 5.88E-03 1,700 Sr-89 Bons 2.5hE+01 0 590 Sr-90 Bone 9.67E+02 0.016 - j 7-131 Thyroid 1.60E+01 0 938 I-133 Thyroid 3.8hE-01 39 1 Xe-131m Air Dose (B) 4.02E-04 h9,700 Xe-133m Air Dose (B) 8.08E-Oh 24,800 l' Xe-133 Air Dose (B) 2.82E-Oh 70,900 Xe-135 Air Doue,(B) 1 57E-03 12,800 Cs-134 Liver 1 73E+01 0.869 Cs-137 Kidney 1.95E+00 7.68 j l q) l 7 1 1 u_____._ _j

s b %) II. DISCUSSION This Technical Specifications Change.is proposed as required by 10 CFR 50,. Appendix I and is based on a report titled, " Appendix.I Analysis - Palisades Plant," prepared by the NUS Corporation. This report is transmitted (see En-I closure 1) along with this proposed Technical Specifications Change. The proposed change will bring the present Technica1' Specifications into con-' formance with Appendix I and the "as low as practicable" requirement.of 10 CFR 50.3ha'and 10 CFR 50 36a. III.- CONCLUSIONS Based on the foregoing, the Palisades Plant. Review Committee has concluded that this proposed Technical Specifications Change does not involve an unreviewed 4 4 safety question. j f CONSUMERS POWER COMPANY ,. ~. 'By C. R. Bilby (Signed) f .C. R. Bilby, Vice President Svorn and subscribed to before me this 4th day of June 1976. Sylvia B. Ball-(Signed) (SEAL) l Sylvia B. Ball, Notary Public ' Jackson County, Michigan My commission expires April 13, 1980. [ % 8 L 1-- __ __ U}}

ML20236L680

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