ML20237B633

Forwards Draft Supplemental Testimony by NRC Supporting Facility Conformance W/Requirements of 10CFR50,App I

ML20237B633
Person / Time
Site:	Mcguire, McGuire
Issue date:	03/01/1977
From:	Jay Collins Office of Nuclear Reactor Regulation
To:	Kniel K, Regan W Office of Nuclear Reactor Regulation
References
NUDOCS 8712170016
Download: ML20237B633 (15)

Text

t l-o O s,.

MAR 1 1977 Docket Nos. 50-369/370 MEMORAH0lft Fno: W. Renan, Chief Environmental Proiects Branch, DSE

r. Kniel, Chief, licht uater Reactors Branch No. 2, DPM FRO?i: J. Collins, Chief, Effluent Treatment Systems Branch, DSE -

SUSJECT: eUPPLEtif tJTAL TESTIMM'Y 04 MCOUIP.E !JUCLEAC STATI0H, UNIT N05. 1 & 2, VITH RESPFCT TO APPENDIX I TO 10 CFR PART 50 PLANT !a"E: t!illian c. f'cGuire Nuclear Station, Unit tios.1 and 2 DOCKET HlA Ens: 50-369/370 LICEllSING STAGE: OL

!' MILESTOUT NU"nED: tJ/A DESPONSintg portcg: Epg.3 Pt'0 JECT l'AHACro: 0. Lynch RE00ESTED Cn?'PLETION DATE: tiarch 2,1977 DESCDIPTIn" Or PESPOMr: Appendix I Supniecental Testinnny for ASLB Hearino P.EVIEy eTP.Ti!f: Comlete Enclosed is the OSF Staff Suerlenental Testirony for t'cGuire Nuclear Station,

'Init t ns.1 and 2, addressino confomance with the raceire ents of Anoendix I to 10 CW Part 50.

Based on nur evaluation, wa conclude that the McGuire !!eclear Station confomg to the reonirements of Apnendix I and the Annex, dated <eotenbar 4,1975.

OEIGIliLL SIGIIED 3Y i JOH1; T. COLLINS 3

John T. Collins, Chief Q 21{ggg ]@$8369 Effluent Treatnent Systers Branc5 p PDR Division of Site Safety and Environmental Analysis

Enclosure:

! Staff Supplemental Testimony for "cGuire DISTRIBUTION:

i cc: e.. Hanauer Docket File 50-369 P. nanton " "

50-370 D. le11er u

J NRR Reading File i F. MiraP11a DSE Reading File {

D. Eisenhut ETSB Reading File 1 i B. Gri'nes JTCollins

! M. Villiams (j D. Vassallo ~..  !

k

. i / WM '

. .c =

• _DSE:ETSBfC _DSE: SB DS . Dh)HMB .

B X 231., JB.oegli:df urIe WKreger dA94ciman ,

11 1ns om , 03[01]77 03/ J/77 03/t #77 ' 03/ r/77 03/2_J77 m _ _ _ _ _ _

O O *a 1m W. Regan K. Knfel j

1 cc: cont'd )

R. Vollmer 1 L. Hulman W. Kreger j F. Congel E. Markee ,

E. Ketchen (w/tq) ] '

I. Villalva O. Lynch W. Burke i J. Boegli

L, j -

O .O o-L UNITED STATES OF AMERICA HUCLEAR REGULATORY COMMISSION BEFORE THE' ATOMIC SAFETY AND LICENSING BOARD 4

In the Matter of. ').

)

- Duke Power Company . I Docket Nos. 50-369

) 50-370 ,

(William B. McGuire Nuclear )

Station, Unit Hos.1 and 2 )-

HRC STAFF EVALUATION OF LIOUID AND GASE0US EFFLUENTS WITH RESPECT TO APPENDIX I 0F 10 CFR PART 50 Introduction The Final Environmental Statement (FES) for the Duke Power Company's McGuire Nuclear Station, Unit Hos'.1 and 2, was issued in April 1976{5) The FES indicated that-the Staff was in the process of reassessing the parameters and mathematical models and that a detailed assessment to determine conformance with Appendix I to 10 CFR Part 50 would be completed in connection with the environmental hearing before the Atomic Safety and Licensinp Board. The pur-pose of this testimony is to present the results of that detailed assessment.

The assessment was performed to determine if the proposed McGuire Huclear ,

Station, Unit Nos.1 and 2, met the numerical design objectives specified in I Se::tions II. A, II.8, II.C and II.D of Appendix I of 10 CFR Part' 50.I4I On September 4,1975, the Commission amended Appendix I of 10 CFR Part 50 to provide persons who have filed applications for construction permits for light-water-cooled nuclear power reactors which were docketed on or after January 2,1971, and prior to June 4,1976, the option of dispensing with l

i

. - . ... . 1 D O the cost-benefit analysis required by Paragraph II.D of Appendix I. This j i

option permits an apolicant to design his radwaste management systems to l I

satisfy the Guides on Design Objectives for Light-Water-Cooled Nuclear Power  ;

Reactors proposed in the Concluding Statement of Position of the Regulatory ,

Staff in Docket RM 50-2, dated February 20, 1974. As indicated in the State--

ment of Considerations included with the amendment, the Commission noted it -

is unlikely that further reductions to radioactive material releases would '

i be warranted on a cost-benefit basis for light-water-cooled nuclear power reactors having radwaste systems and eauipment determined to be acceptable under the proposed Staff design objectives set forth in RM 50-2.

On June 4,1976(,I December 9,1976 I and February 7,1977,I Duke Power Company.provided the necessary information to permit an evaluation with respect to Appendix I to 10 CFR Part 50!O The applicant elected to show conformance with the Commission's September 4,1975 amendment to Appendix I in lieu of performing a detailed cost-benefit analysis as reauired by .

Section II.D of Appendix Ib Evaluation The staff has evaluated the radioactive waste management systems for McGuire Nuclear Station, Unit Hos. l' and 2, to reduce the ouantities of radioactive materials released to the environment in liouid and gaseous effluents. These I

I

_ _ __ _ . A

\. ) U 1

systems have been previously described in Section 3.5 of the Final Environ-mental Statement (FES), dated April 1976.5)I Since the FES, the applicant has included in his design a purge system for each unit to draw air from the lower containment through prefilters, high efficiency particulate air (HEPA) filters and charcoal adsorbers to the plant vent at an average continuous rate of I 100 scfm. These purges will be continuously monitored and sampled prior to release.

Based on information provided by the applicant, referenced above, on more recent operating data applicable to the McGuire Nuclear Station, and on changes in our calculational model, we have generated new liouid and gaseous source terms to determine confornance with Appendix I. These values are not substantially different from those given in Tables 3.4 and 3.5 of the FES that were calculated for the purpose of an upper bound analysis.

The new source terms, shown in Tables 1 and 2, were calculated using the models and methodology described in HUREG-0017(6) ( reviously titled draft Regulatory Guide 1.BB). A list of the paraneters used in calculating the source term was given in Table 3.2 of the FES, except that the parameter

" Annual Freauency of Containment Purges (at power)" is replaced by the parameter " Contained Normal Purce Rate (cfm)" and the value is chanced from 4 to 100. This change was reauired in order to consider the containment purge system desion modification. These source terms were used to calculate the doses using the guidance in Regulatory Guide 1.109.7II

1 O _4 O l

We have made reasonable estimates of averaae atmospheric dispersion conditions for the McGuire Nuclear _ Station site using our' atmospheric dispersion model for long-term releases (Saoendorf and Goll) . This model is based upon the'

" Straight-Line Trajectory Model" described in Regulatory Guide 1.111, " Methods .

of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents from Light-Water-Cooled Reactors." The model assumes ground level releases, based on the criteria established in Regulatory Guide 1.111. Non-continuous and intermittent gaseous releases were evaluated separately from continuous releases. The calculations also include an estimate of maximum increase in calculated relative concentration and deposition due to open terrain recir-culation of airflow not considered in the straight-line trajectory model.

Table 3 lists relative concentration and deoosition values used in the dose estimates which are summarized in Table 4 Included in our analysis are dose evaluations of three effluent cateanries:

1) pathways associated with liquid effluent releases to Lake Norman, 2) noble gases released to the atmosphere, and 3) pathways associated with radioiodines, particulate, carbon-14, and tritium released to the atmosehere.

The dose evaluaticn of pathways associated with liouid effluents was based on the maximum exposed individual. For the total body dose, the individual is an adult consuming 21 Kg/yr of fish harvested in the immediate vicinity of the discharge, and recreational use of the shoreline in the immediate vicinity of the discharge for 12 hr/yr. In terms of body organs, the maximum exposed l

individual is an infant who consumes 510 liters /yr of water from Lake Morman in the vicinity of the plant effluent discharge.

[: - - - - - - - - - _ - - - - _ _ _

,. . 4 t

The dese evaluation of noble gases released to the atmosphere included a calculation of beta and gamma air doses at the site boundary and total body and skin doses at the_ residence having the highest dose. The maximum air I doses at or beyond the site boundary were determined to occur _0.5 mile NE j of the facility. The location of maximum total body and skin doses were determined to be at a residence located 0.5 mile East.

The dose evaluation of pathways associated with radioiodine, particulate, carbon-14 and tritium released to the atmosphere was also based on the maximum exposed individual. The maximum individual is a child who con-sumes 26 Kg/yr of leafy vegetables at a residence located 0.5 mile E of the site and inhales radionuclides at this location.

Since the Guides _ on Design Objectives apply to all licht-water-cooled reactors at a site, it is necessary to compare the total dose from Unit Nos.1 and 2 with the design objectives contained in the September 4,1975 amendment to Appendix I (Annex, RM 50-2). Table 4 provides a comparison of the calculated f 1

doses, with the design objectives of Sections II.A, II.B, and II.C of Appendix I and the design objectives set forth in RM 50-2. ~!

l As shown in Table 1, we calculate the quantity of radioactive materials released in liquid effluents from Unit No.1 or Unit No. 2 to be less than 4

5 Ci/yr, excluding tritium and dissolved noble cases. Using the calculated releases given in Table 1, and the methodology given in Regulatory Guide 1.109, i

we calculate the annual dose or dose commitment to the total body or to any organ of an individua1 g in an unrestricted area to be less than 5 mrem /yr/ site

-_______-__Q

OV O i

as shown in Table 4. Based on our evaluation, we conclude that the liouid waste management systems for the McGuire Nuclear Station, Unit Nos.1 and 2, conform to the numerical desian objectives of RM 50-2 and therefore meet the requirements of Section II.D of Appendix I.

Using the calculated releases of radioactive materials in gaseous effluents from Unit No.1 or Unit No. 2, given in Table 2, we calculate the annual gamma and beta air doses at or beyond the site boundary to be less than 10 mrad / site and 20 mrad / site, respectively, as shown in Table 4. As shown in Table 2, we calculate the release of iodine-131 to be less than 1 C1/yr/ unit. Using the calculated releases for iodine-131, given in Table 2, we calculate that the dose or dose commitment to any organ of an individual in an unrestricted area to be less than 15 mren/yr/ site, as shown in Table 4. Based on our evaluation, we conclude that the gaseous waste management system for the McGuire Nuclear Station, Unit Nos.1 and 2, conform to the numerical design objectives of RM 50-2 and therefore meet the requirements of Section II.D of Aopendix I.

Conclusion Based on our evaluation, we conclude that the radioactive waste management systems proposed for the McGuire Nuclear Station, Unit Hos.1 and 2, are capable of maintaining releases of radioactive materials in liauid and gaseous effluents _ during normal operation, including anticipated operational occurences such that the doses will not exceed the numerical design objec-tives of Section II.A, II.8, and II.C of Appendix I of 10 CFR Part 50.

O _,_ O Our evaluation also shows. that the applicant's prooosed desian of the liauid and gaseous waste treatment systems for McGuire fluclear Station, Unit Nos.1 and 2, satisfies the design objectives set forth in RM 50-2 specified in the option provided by the Commisson's September 4,1975 amendment to Appendix I -

and, therefore, meets the requirements of Section II.D of Appendix I of 10 CFR Part 50.

We conclude that when the McGuire Nuclear Station, Unit Nos.1 and 2, becomes operational, the liauid and gaseous radwaste treatment systems will reduce radioactive materials in effluents to "as low as is reasonably achievable" levels in accordance with 10 CFR Part 50.34a and, therefore, are acceptable.

Based on the NRC staff's evaluation, the proposed liouid and gaseous radwaste management system for the McGuire Nuclear Station, Unit Nos.1 ard 2, meet the criteria given in Appendix I and are, therefore, acceptable.

4 Jacaues S. Boegli, Senior Nuclear Engineer Effluent Treatment Systems Branch Division of Site Safety and Environmental Analysis Office of Nuclear Reactor Regulation ,

l

)

___ _ _a

O O l

i

'1 i

Wayne L. Britz, Environmental Scientist l Radiological Assessment Branch i Division of Site Safety and Environmental Analysis Office of Nuclear Reactor Regulation i

Leta P. Andrews,. Meteorologist Hydrology-Meteorology Branch Division of Site Safety and Environmental Analysis Office of Nuclear Reactor Reaulation i

Sworn and subscribed before me, a Notary Public in and for the County of Montgomery, State of Maryland, this the day of March, 1977.

Carol J. Durham My commission expires July 1,1978.

J

o.

REFERENCES-

'o

1. " Evaluation of Comoliance with 10 CFR 50 Appendix I and Supporting Information", Duke Power Company, McGuire. Nuclear Station, June 4,1976.

2. Ibid. Revised pages on gaseous release points submitted by letter dated December 9, 1976.

3. Ibid. Revised pages on critical airborne radiciodine pathways, sub-mitted by letter dated February 7,1977.

4. Code of Federal Regulations,10 Eneray, Parts 0 to 199, Revised as of January 1,1976, U.S. Government Printing Office, Washington, D.C.

5. Staff of the U.S Nuclear Regulation Commission, " Final Environmental Statement Related to the Operation.of William B. McGuire Nuclear Station, Unit Nos.1 and 2, Docket Hos. 50-369 and 50-370",

Washington, D.C., April 1976.

6. NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liouid Effluents from Pressurized Water Reactors (PWR-GALE Code)," Office of Standards Development, U.S. Nuclear Regulatory Commission, April 1976.

7. Staff of the U.S. Nuclear Regulatory Commission, Reculatory Guide 1.109,

" Calculation of Annual Average Doses to Man from Routine Releases of Reactor Effluents for the Purcose of Implementing Appendix I," March 1976.

8. Sagendorf, J. F., and Goll, J. T., "X00000, Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations," (DRAFT).

Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.,1976.

9. Staff' of the U.S Nuclear Regulatory Commission, Regulatory Guide 1.111

" Methods of Estimating Atmosoberic Transport and Dispersion of Gaseous Effluents in Routine Releases from Licht-Water-Cooled Reactors,"

March 1976.

l TABLE 1 O  !

CALCULATED RELEASE OF RADI0 ACTIVE MATERIAL IN LIQUID EFFLUENT FROM THE W. B. MCGUIRE NUCLEAR STATION, UNITS 1 & 2 Radionuclides I I

Activation-Corrosion Products Ci/yr/ reactor Cr-51 1.2(-4)b Mn-54 1(-3)

Fe-55 1.2(-4) l Fe-59 7-Co-58 5.1 - '

Co-60 8.8 -

Np-239 4(-5)

Fission Products Br-83 3(-5)

Rb-86 1(-5)

Sr-89 2(-5)

Mo-99 3(-3)

Tc-99m 2.6(-3)

Te-127m 2(-5)

Te-127 2(-5)

Te-129m 9(-5)

Te-129 5(-5)

I-130 1.2(-5)

Te-131m 6(-5)

Te-131 1(-5)

I-1 31 8.9(-2)

Te-132 9(-4)

I-132 1.8(-3)

I-133 3.3(-2)

Cs-134 2(-2)

I-135 6.l(-3)

Cs-126 1.9(-3)

Cs-137 2.9(-2)

Ba-137m 4.6(-3)

Ba-140 4.6(-3)

La-140 1(-5)

All Others" 6(-5)

Total ('except H-3) 2.2(-1)

H-3 - 470 NOTE: a = Nuclides whose release rates are less than 10-5 Ci/yr/ reactor are not listed individually, but are included in the category "All Others".

b = Exponential notation: 1(-4) = 1 x 10-4 3 1

i

~

. *i

. TABLE 2 O

CALCULATED RELEASES OF RADI0 ACTIVE MATERIAL IN GASE0US EFFLUENT FROM W. B. MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (Ci/yr/ reactor)

Decay Reactor Auxiliary Turbine Condenser Radionuclides Tanks Building Building Building Air Ejector Total Kr-83m a a a a a a Kr-85m a 3 2 a 1 6 Kr-85 250 6 a a a 260 Kr-87 a a 1 a a 1 Kr-88 a 3 4 a 3 10 Kr-89 a a a a a a Xe-131m - 5 9 a a a 14 Xe-133m a 22 2 a 1 25 Xe-133 4 1800 110 a 69 2000 Xe-135m a a a a a a Xe-135 a 15 7 a 4 26 Xe-137 a a a a a a Xe-138 a a 1 a a 1 1-1 31 a 1(-2)b 4.5(-3) 3.9(-4) 2.8(-2) 4.3(-2) l I-133 a 3.5(-3) 6.4(-3) 5.3(-4) 4(-2) 5(-2)

Mn-54 4.5(-3) 1.9(-4) 1.8(-4) c c 4.9(-3)

Fe-59 1.5(-3) 6.6(-5) 6(-5) c c 1.6(-3)

Co-58 1.5(-2) 6.6(-4) 6(-4) c c 1.6(-2)

Co-60 7(-3) 3(-4) 2.7(-4) c c 7.6(-3)

Sr-89 3.3(-4) 1.5(-5) 1.3(-5) c c 3.6(-4)

Sr-90 6(-5) 2.6(-6) 2.4(-6) c c 6.5(-5)

Cs-134 4.5(-3) 1.9(-4) 1.8(-4) c c 4.9(-3)

Cs-137 7.5(-3) 3.3(-4) 3(-4) c c 8.1(-3)

C-14 8 a a a a 8 H-3 - - - - -

960 Ar-41 c 25 e c c 25 NOTE: "a" appearing in the table indicates release is less than 1.0 C1/yr for noble gas, 0.0001 Ci/yr for iodine.

b = Exponential notation: 1(-4) = 1 x 10~4 c = Less than 1% of total for this nuclide.

_ R c ) )

_ i 5 5 d - -

a o (

(

Qi 7 3

/ r .

D X e 6

_ N P A

)

Q e ) )

/ s 7 8 Qa X - -

( / e ( (

Dl 4 6 N e O R 1

. I T s A u ) )

RY o 5 5 TR a u -

(

NA Qn (

EM /i 8 2 4 CM Xt NU n 3 1 0 OS o 1 C C E x ET VA 1 I M )

=

TI i AT m 4 LS ( ) -

EE e 4 0 t R c 5 5 5 5

(

- 1 E n . .

,S a 0 0 0 0 1 x u 3 2O t)

D se  ;

1 E D l i c L Nl Dr n = r B AI u o )

A o i T 1 D S t 4 h E a -

.S m t (

SU no o 1 O or n N) iF  ;

Q t( l T/ c E E E E a n r I D e N N i o a N( r t i e U i i n t y f D e a /

,0 n t NI o p n sk o es OT x I I TS n n e l AO e e a TP d d , i e SE r r t D y y a a r n R r r g g e e 5 c A a a . t n E r d d , , e o L o n n e e m p n C t u u c c x o U p o o n n r e N e B B e e e p , e c d d E e e e i i s -

l R R t t s s I i i e e d s bs U S S R R n r G r r o e s C o o c t M t t e e sd c c e

s m a e

j j n n

.E .E i i eh g g

.d r .d r s s

) gl i gl i t t e .

dBA .

dBA i i s g l g l n n dt a s d B yr s d B yr u u o e k l re k l re l n B eas n B eas Q Q ro e a nin a nin / / er R T r il e T r il e X D Pf e o bid o bid ce y t rxn y t rxn - -

rp a c uuo a c uuo uy c a TAC c a T A C. a b c oT e e e e -

S( D R D R

l1iiil I .'

) .

• ( ? ,

m,)u t

t e .

i s

t t tt t t t i i ii i i i e n n nn n n n h u u uu u u u t d / / // / /

e r r rr r r r t t s y y yy y y y a ae / / // / /

s l s m m dd m m m uo e e aa e e e r

t D cD r r rr r r i N l m m mm m m m n u

A a C 1 9 48 7 6 7 a) . 2 2 9 3

2 0 13 5 0 0 0 o 7 t H9 y T1 l I

W , p 5 c p 2 s a Y e e e ee e e e DA v t t tt t t t s NM i i i ii i i i e A( t s s ss s s s v b c / / // / / / i xe r r rr r r r t 1 C.b ) ej y y yy y y

/

y c e

.I5 nb / / // / /

SI7 nO m m dd m m m j O 9 A e e aa e e e b ND1 n r r rr r r r o N g m m mm m m m n TA

, i .

I 4 s 5 5 00 5 5 5 g .

e 1 2 1 1 i N

U B. R D s e

IE

,I B d N M e O ,E s

T I A.P 4 T e AIE h '.

E TIS t y L S ( . r B S s 5 , o A RNX e t t tt t t t 7 e g T AOE v i i ii i i i 9 r e EIN a i n n nn n n n 1 o t _

LTN l t u u uu u u u f a .

c e c

/ry CCA / / // / / . _.

UE xe r r rr r r 5 4 r NS , ij y y yy y y 7 e s

, D. db / / // / / / 9 r h i _

E nO m m dd m m m 1 e T h R0I e e e aa e e e b t I 5I pn r r rr r r r ,

m U pg m m mm m m m 5 t

e s

t o

GTN Ai 5 y p CRO s 3 0 00 5 5 i MAI e 1 1 2 1 1 a e s d PT D M S a e F C b d

, , d ORE l 2 6 e a FS - l NC l) o a) 4 1 t O ld i 4 8 i n S0 ai n de mr 9 0 s e I 1 m o a ah oe 1 4 e R o mr Rt rv a y

. b AO r) oy f fi . .

PT ft rh o ro et l

n -

p p n o

l n v e

M lft OI yu d y n h ad , ,

o a C dd nt s r d a td gl 0 0 n h X oaan t iro Oe ri 4 4 e s I n b( ga n aib f s oh v e m D o s rf e a o da ne y(

c V

V

. i g

s a

u N i t l son u n l g

i E r n ay i l ina n al n t P e e t a y( f itlil ee as y r r

s i r

P t u own f e oaka sRe e e A i l thas E set usu e r oa e e v l T r f t y os d d nse t w t t i b C f oaoa s dooioi i eh h s s t o d E t pt w a dt vt v ddp et i i c n n h G a i i ois sa g g e a d el et maed ed il o op e e j o i sl sa e mt snsn ccmD R R b t 4 u oaop l aeoioi iut O 1 q D D b GBD D d nA l l d -

i o a a a n e n L N R r r g t o e e i i b d d s m r e e e i a F F D L C a b c d "