ML18142A211

Radioactive Effluent Release Rept,Jan-June 1984

ML18142A211
Person / Time
Site:	Surry
Issue date:	06/30/1984
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18142A209	List: ML18142A208 ML18142A210 ML18142A211
References
NUDOCS 8503210051
Download: ML18142A211 (22)

Text

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EFFLUENT RELEASE DATA (January 1, 1984 Through June 30, 1984)

-1 850301 8503210000 ~~ 05000280 PDR A

PDR R

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facllltJI Surq l'ovel' &tattoo I.

LIQUID Ul.EASES

1.

01n1** ladloacllYltY (8Y) la)

• Total leleaae (b)

• .&n. Coocentratloo laluaed (c\\

Kalllaua Cooceotrattoo Ralaaaed

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Total leleued (b)

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Total Weue (b)

Aq. Coacentl'atlon blauad

. 4.

Cl'Oaa Alaba ladloactiwltY la)

Total lleleued (b)

An. Coocentl'atloo laluaad

5.

Yol. of Uauld to Dlacb. r.anal Yol. of DJlutloo Uatel'

1.

laotoPu leleaaed HPC uCl/al 1-131 J

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1-llZ IS JU**

1-1:n 1 s 10-*

1-L34 Z :K JU

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• ca- :36 fi S lU

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l'e-S9 Jl *.,....

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la-La-HO ZS 10-1 1111>-8111 tn-..1.H 2

• ID-.,

• 1.-1n I a ID....

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uCUal curl**

11c11a1 Curt**

UCllal Utel'a liter*

Curl**

IUOllT or UUIOACTIVI U'fWIIIII IKMZ&T1

~0-280 and 50-211 J~nnnrv Fo>h-nnrv

• br,-h 4.7HE-1 8.06E-l 5.84E-l

? R'iF-Q 4 75F-Q

? ORF-Q 6.lJE-9 l.27E-8 3.90E-9

1. l51H2 8.49E+l 5.55E+l 7.30 E-7 4.47E-7 2.80E-7

6. 'i4E+o

• 1.39E+O 3.06E-l 1 'i4F-R 1 7RF.-R 1 'i'iF.-Q 2.llE-5 5.99E-6 l.13E-5 l.21E-13 3.28E-14 5.R1E-14 3.27E+7 1 4'iF.+7 1 Q?J;'-"7 1 A'i"'-'-11 J on"'-'-' 1 1 n'Dl:'.J..1 J l.41E-1 1 06F.-1 7 OOF.-?

ft 6 7F.-ft

'i 7n1>-'i

? t. lF.-4

? no... _,

' 'i'iF.-?

l J,l,F.-1

1. ODE 3 2.60E-3

1. llE-4 1 4QF.-l 1 ll5E-?

'i 04F.-?

1 l4F.-1 1 01F-4

? Al,R-1

(, Q?F-?

1. ?6F.-1 l.46E-4 2.72E~4 2.39E-4 l.06E-2 2.62E-2

}.t.?F.-1 R nAJ;"-?

1 ?7F.-1 1 l?F.-1 l nnc--1

,. '*lF.-1 4 RlF.-1 4.50E-6 2 24F.-'>

4.32E-4 2.61JE-4 1.07E-1 1 f.b.F-"}

1 '*""'-"l

? C.AF-L.

l.21E-4 6.74E-4 8.29E-4 5.97E-3 2.21E-1 l.35E-4 1.43E-5 2.69E-2 5.2JE-4 l.89E-3 l.52E-2

"--*1 6.26E-l 1 Q':U:-Q

. R._,..,._q 7.26E+l 4.40E-7 2.RRF.u'I.

l 7'ir:-A 1 li.011L7 1,........ 11 6.20E-2 1.41F.-1 1 0011-£.

2 "HF.-1

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1 ?l.11r1 6.76E-4 8.98E-S 1 7.7E-4 6.24E-3 b."4lt:-J rAG& 1 HAU 1984 u.,v

.1nn*

l.13E+o l.42E-1

">.09E-9 6.44E-10 Q f.l.,11'.-Q 1 llF.-Q 8.09E+1 7 Rll1-"l "I 'if.F-7 1 b.71>-7 2.?l'P.-f-0 l.83E+o Q "'l?'P.-Q 8.13E-9 4 Anll-6 1 J.."ll>-6 2 )b.11'-1£.

7 10111_1 o;;

1 AnF+7 1 f.li.11'+7.

? ?7F.f.11

? ?li.11'+1) l.OBE-1 l.18E-l 7.20E-S l.SIE-4 1.lSE-2

,. J..QF.-1

'i o;;nv-4 J. Af.11'-/,

1 '\\"IV-)

].?RF-2

" 'if.11-'i 5.11F-4

, A"lll'-1 A n11i'-?

4.78E-4 4 11 F.-7 l.04F-2 1 t.lF.-1

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l.68E-1 1 'lf.11-'i "I

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._ 'lOV.-4 6-928-2

._ 10:v.1 6_428-1 2.02E 3 1.348+0 1.168 3 3.54E-l 7 ?QP..1 2.41F.-7 5.64E 4 4 O?R.7 3.82E 3 4.828 3 1.558 2 9.77E *"l 3~12E-'-2 2.IJIJR-2 Z Ul'OI' 4.HE+l 1

4,;.iu.n

13. l9E* *ti 15_ }.AR-2 14 lilR-li 5_AAP.-3

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1. 72£-4 l-1.4E-l 9.AfiR *5 1"4 OlR-7 lfi 70R -">

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4. ICJEr-5 l'l.. ">11'-'l 3.25E 4 4.lOE-*

l-3?R *'l 8.30£-j 2.91£-3

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LIQUID ULIAl!S (CDl 1T)

IIIIIIH

1.

laotopea bleaaed Hl'C.,..,,_1 Ce-141 9 a 10-~

Ce-144 1 z 10-!

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total Balneeaa

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4.

total trttl*

5.

total Partlc:ulate Cn,aa &lplUl ladloactbitY

6.

HHlala Roble Oaa llal... a lat*

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1.

ferc:eat of Applicable Ualt for Techalcal BPeclflc:atloaa

. (al liable Caaea

. (b)

Baloaeaa

- (cJ l'artlculaten

8.

laotope11 leleaa"'h r.,,...,_

- (a) l'artlculateu Ctt-134 1:1:-s1*

Ca-137 i:e-118

!;lo-~8 Co-60 Hn-~

Pe-59 llt=BB nron or uo10ACrlft lffUlllltD Deknre,o..ieo.11111 5o--211 JAn"~-**

FahrHDr~

M"'rr-h 8.61JE-'i I ?f,F.-3

1. 24E-1 l 'i4F.-1 2.l'iF.-,

1 ?4R-1 F. ? 1 F'.+n 1 1m:+n

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I. ))F.-1 I 7'iE-1 3.SOE-2 4.ll1F-,

'i 1)/;J," *2 6.9lR-4 l

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8.17E-3 5.06E-3 14.A?li';.1 l.46E+O 7 0/,'ll-1 1 R 1 F.-1 I A 7s;-.._,

1,u;i:r.+J 6.21E+2.

3.21E-1 6.ll1F.-2 l.78E-2

7. 2,;r;_1,.

6.33E-4 l.16E-4 9.]4F.... 1 1.uor.+u

] * ]AP"'-0 8.25E-7 5.08E-7 l.56E-7 l.89E+4 4.23E+4 fi. 5SIH2 9.20E-2 6,77E-l 4.lOE-1 2.6IE-2

'I 'lnF-1 4.4"iF.-2 7 'i'i'll'.-1 3.59E-3

• 1 "tl;,R-1 l.BlE-4 7,1/;F-'i 1 QlF.-'-

I. "tDll:'-A 2.0BE-4 7.lOE-5 I. 77F.-4

6. f,ni;--f, I 'iAF-7 1 lQF-<;

4 'i71i"-'i l,99E-5 l.85F.-'>

1 QIV-"1

4. IOE-8 1 ""1-"1 4.62E-4 3.02E-4

' iACB 2 uAl, 1984

• Anril *

.June 4 7CJE-5 1 Af,fl'.-t.

]. il;l.11-'i 1 f, 7F-A

' ORll'-A

') 1'*"-"

4.JOE-2 1 '>017_')

2.52E-2 2.76E+o 1 D/.17.LI\\

l.61E+o S.BIJE-2 7 Q'IF-1 I 11;1111-t 1 1711'-'>

4.05E-2 1 C>J.,F.-?

5.06E-S.

4 JIJlll:'. 'i J.7AF-'i 2 17F.-4

?. ')QR-A l.84E-4 3.77E-3 3.97R-4 3.20E-'1 7 A"111'-]

II; 1\\111'-1

t. a:ns,.1 1 93E+3 l

• 111,w;'-4-'1

'i.Anl,"'-7 l.12E-2

'I n',F.- "l

'I Q71l'-"l 7.24E-4 7.20E-5 9.69E-5 l 0.'JJ;~

l.J9E+l

.J *.J~f;-tt.l 5.83E-7 l.49E-7 3.68E.:7 4.46E+4 4 37E-&.I..

2.32E+1 L 35E"'-ll I '>lll.:-.u.

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CJ.41E-2

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3.. 48E-5 4.SOE-4 1,.,..,._,,

1 01R -A

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'I 71Jo"-'i l, _ 1 'JF-f,

'i l.11l'-7 l AO.Jl-4 9 ffl'P'.-'i 1,;1.,._,;

? -,c.,_ 7 3 SIE-6 l.19E-3 8.5SE-4 7.JOE-4 u1iJU.

J:56B-,I 5.)lR-.1 2.60E-1 1.588+1 8.538-1

.l.728-1 l.32E-4 6 10R-4

2. 54E-?

6.14E+3 9.95E-2 2.37B-3 2.:.!HE+l 2.59B-6 5.lOE-4

.1 4"]R *"1 l.87E-4 5.76R-'i 3.SSE-4 4 11.R.,;.

3.54E-3

% *unror "4.0'IR-"i.;

,I '2AV-A

'.L21R-?

1

":IIAV.&.ft 7.25£-2 l... '-R-2

1. 1 ?R-li

5. 36R..:.."i 2.168-.3 5,.,,u_._-,

R.,lf.R-"4 2.01B-4 l.9UHO' 2_?nR-7

,1_ 'l.j!R-'i l.22E-4 l.59R-'i 4 QHR.,;.

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~ :

r&CILlfl I Surry Paver Station II.

AIUOIIIIB Ill.IA.SIS (mHT1D.)

UHlTS I. Jaotopea Relea*ed tcoa*tvJ UJ..all l*J Particulate* (con*t.)

tlb-95 Zn-6S Zr-95 lu-101 (b)

Balot1 e1111 I-Ill l-ll2 I-Ill 1-134 1-1]5 (c)

Casea

&-Ill le-Illa 1-ns lr-85a lr'-8S lr-87 lr-88 Ar~l Ill.

SOUD UD IOACnVI VASTB DIBPOSAL (a) Total Aaouat SalH VHte rt]

Packa*ed (h) latfaated Tatel Actiwl~

Olri**

(c) llat* of Shipment aDd DlannaitlOD Januarv 1.27F.-7

2. ~-u.*-'3 8.86E-4 l.47E+2 7./,'>V-J J.92E+3 3.'.>2E+O

Barnwell, s.c.

u,on OP UDIOACTIYK lnuJIHIS nomsr, 50-218 aa11,~211 l!'ebruarv

!-f;:irch Anrf 1

'1 7'iF.-7 3.97E-J A 1111'-1 2.75E-4 l AlF.-':1 2.O'IE-4 2..t..QF.-2 l,: '7F.-"l 1,..... _1 7.70E-1 6.31E-3 l.17E-3 l.OOE+J 6.02E+2 l.8SE+3

6. 71E+O l.98E-l 7.79E+o 4.61.F.+0 l.85E+l s.nnF.+1 8_ I "11'-7

(, ""F.-'-7 4.5BE+3 2.87E+3 l.93E+3 1 i,..........

'4-BlE+O 1 -.,,,....._n Barnwell ~arnwel.l Barnwell, s.c.

s.c.

i::: r..

1-"'* 7'i 7,; 2-9.14.1 'i 13-1.R.ll '*-1.,,_ 7'i 77

,n_,1_.,,.

lfi..11.2R

?"7 27.7A 17Q I

PACI J na ___

1_984 H"IV

.June rorAL

! lnor 1 '7'P!-7 l.OBB-8

') '1111'-'t 3.45E-.s 4 7f:t.R-2 !& no;;'R--:t 2.52E-4 l.04E-6 4.57E-J :J.8AII'-*

'i Qf'iF.-l,.

5.17E-.t..

l 77R-7 17 '7.All'-':1

+

l.52E-2 l-2qR-1 l.72E+3 5.JJE+2 5.BSE+J 4.97R+2 9.18E+o

2. 77E-l

,_47F.+1 17 n.::v~n L l2F.+2 4.i;AF.,+-1 2.61E+2 :2_27R+]

2.67E-1 1 l.l.11'-I 7.59R-1 Ii *"-11-,

3.JBE-1 4 lnP' -1 11

,IQII'_.,

2.84£+3 2.94E+3 Q

101'".&.I\\

2.24E+o B-.mwell,

!amwell, i::: r.

i::: r.'

5-2-3.24

~-I. 11 77 29

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• _;__.\\-,.*

. *. ~.:-.

EFFLUENT RELEASE DATA (July l, 1984 Through December 31, 1984)

._.. *t

. u EFFLUENT ANO WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/84 TO 12/31/84 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Page 7 of 10 SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR, FOURTH QTR,

% EST, ERROR A, FISSION AND ACTIVATION PRODUCTS 1, TOTAL RELEASE (NOT INCLUDING TRITIUM~ GASES, ALPHA)

CI UCI/ML 2, AVG OIL, CONC, DURING PERIOD 3, PERCENT OF APPLICABLE LIMIT B, TRITIUM 1, TOTAL RELEASE 2, AVG OIL, CONC, DURING 3, PERCENT OF APPLICABLE CI PERIOD UCI/ML LIMIT C, DISSOLVED ANO ENTRAINED GASES 1, TOTAL RELEASE 2, AVG OIL, CONC, DURING PERIOD 3, PERCENT OF APPLICABLE LIMIT D, GROSS ALPHA RADIOACTIVITY 1, TOTAL RELEASE E, VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

F, VOLUME OF DILUTION WATER USED DURING PERIOD CI UCI/ML CI LITERS LITERS

1. 94E 00 2,70E-09 S.95E-02

1. 75E 02 2,44E-07 8,12E-03

1. 33E 00 1,8SE-09 9,25E-04 1,71E-05 6,47E 08 7,20E 11 3,94E 00 1, OSE-08, 6,82E-02

1. 30E 02 3,SSE-07 1,lSE-02 9,77E-02 2,67E-10 1,33E-04 9,56E-04 9,91E 08 3,66E 11 2,SOE 01 2,SOE 01 2,SOE 01 2,SOE 01 3,SOE 00 3,SOE 00 J

.,1 j

• J

,*j

.1,i I,\\

EFFLUENT ANO WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/84 TO 12/31/84 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT A. FISSION & ACTIVATION GASES

l. TOTAL RELEASE CI 2, AVG. RELEASE RATE FOR PERIOD UCI/SEC B *. IODINE 1, TOTAL I-131 CI 2, AVG RELEASE RATE FOR.PERIOD UCI/SEC C. PARTICUL~TE 1, HALF-LIVES >8 DAYS CI

2. AVG RELEASE RATE FOR PERIOD UCI/SEC

3. GROSS ALPHA RADIOACTIVITY CI D. TRITIUM

1. TOTAL RELEASE CI

2. AVG RELEASE RATE FOR PERIOD UCI/SEC PERCENTAGE OF T,S, LIMITS CRITICAL ORGAN DOSE RATE TOTAL BODY DOSE RATE SKIN DOSE RATE THIRD OTR.

5,0lE 02 6,31E 01 3,09E-03 3,8SE-04

1. 79E-03 2,25E-04 1,71E-06 5,47E 00 6,89E-01 2,71E-02 2,24E-Ol 8,72E-02 FOURTH QTR, 3,16E 02 3,97E 01 2, 28E-0.3 2,87E-04 l.60E-03 2.0lE-04 1,97E-06 1,02E 01 1,28E 00 2,34E-02 9!04E-02 3.57E-02 Page 4 of 10

% EST. ERROR 2,SOE 01 2,SOE 01 2,SOE 01 2,SOE 01

~; * -

-.* *-** *-*,_.*.::. -........,. ~: *-,...... '-',*.*..,:.* ;*:,; _.,, -<~- l ___.,,;. **-** ; :., \\,:...* :..:. ~; ~-.* '*

TABLE 18 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/84 TO 12/31/84 GASEOUS EFFLUENTS-MIXED-MOOE RELEASES SURRY POWER STATION UNITS 1&2 1, FISSION & ACTIVATION GASES KR-85 KR-85M KR-87 KR-88 XE-133 XE-135 XE-135M XE-138 XE-133M XE-131M AR-41 TOTAL FOR PERIOD 2, IODINES I-131 I-133 I-135 I-132 TOTAL FOR PERIOD

3. PARTICULATES SR-89 SR-90 CS-134 CS-137 BA-140 LA-140 C0-58.

C0-60 RB-88 CS-138 MN-54 SB-125 C0-57 SR-92 TC-99M CR-51 NB-95 RU-103 UNIT CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CONTINUOUS MOOE THIRD FOURTH QUARTER QUARTER O.OOE-01 O,OOE-01 2,89E-02 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 2,76E 01 4,60E 01 9,92E-Ol O,OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 l,71E-Ol 3.45E-Ol O,OOE-01 6,35E-Ol O.OOE-01 O,OOE-01 2,88E 01 4.70E*Ol 1.28E-05 2,33E-07 1,89E-06 O,OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O,OOE-01 1.47E-D5 2.33E-D7 O.OOE-01 O.OOE-01 O.OOE-01 1.91E-10 6,38E-07 3.71E-07 1,SOE-06 1,17E-06 O.OOE-01 O,OOE-01 O.OOE-01 O,OOE-01

2. 61E--07 2,22E-D8 l,03E-05 3,8DE-06 O,OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 3,36E-07 7,SSE-08 l,56E-07 O,OOE-01 2,12E-08 2,12E-09 O.OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 BATCH THIRD QUARTER l,43E-01 l,59E-02 O,OOE-01 l,72E-02 3,18E 01 2,72E-01 O,OOE-01 O,OOE-01 2,0SE-01 6,38E-01 3,07E-03 3.31E 01 2,73E-06 3,35E-07 O.OOE-01 O.OOE-01 3.06E-06 O.OOE-01 O,OOE-01 1.94E-08 5,42E-08 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 2,85E-03 O.OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 Page 5 of 10 MO-OE FOURTH QUARTER D,DOE-01 O,ODE-01 O,OOE-01 O,OOE-01 6,57E 01 2,13E-02 O,OOE-01 O,OOE-01 5.44E-01 5,83E-Ol 3,80E-03 6.68E 01 9,0SE-05 4,llE-07 O,OOE-01 6,06E-07 9,lSE-05 O,DOE-01 O,OOE-01 3,94E-08 l,99E-07 O,OOE-01 O,OOE-01 5,56E-D8 O,OOE-01 6,62E-06 O.OOE-01 5,12E-D8 O,OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 O,DOE-01 O,OOE-01 O,OOE-01 J

-:1

• ~......

TABLE lC EF=~UENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/84 TO 12/31/84 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Page 6 of 10 CONTINUOUS MODE BATCH MO.DE SURRY POWER STATION UNITS 1&2 1, FISSION & ACTIVATION GASES KR-85 KR-85M KR-87 KR-88 XE-133 XE-135 XE-13SM XE-138 XE-133M XE-131M AR-41 TOTAL FOR PERIOD 2, IODINES I-131 I-133 I-135 I-132 TOTAL FOR PERIOD 3, PARTICULATES SR-89 SR-90 CS-134 CS-137 BA-140 LA-140 C0-58 C0-60 RB-88 CS-138 MN-54 SB-125 C0-57 SR-92 TC-99M CR-51 NB-95 RU-103 UNIT THIRD QUARTER CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI 1,52E 02 CI 1.25E 01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI

1. oSE 02 CI 1,74E-03 CI 2,66E-03 CI 9,64E-04 CI 3,12E-04 CI S,68E-03 CI O,OOE-01 CI 3,17E-07 CI 2,40E-04 CI 1,34E-03 CI O,OOE-01 CI O,OOE-01 CI.

7,llE-06 CI 1,21E-04 CI l,54E-02 CI 4,30E-04 CI 4,49E-06 CI o.ooE-01.

CI O,OOE-01 CI 4,16E-06 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 FOURTH THIRD FOURTH*

QUARTER QUARTER QUARTER O,OOE-01 D,ODE-01 2,66E-03 O.OOE-01 O,OOE-01 1,72E-05 O,OOE-01 O,ODE-01 O.OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 2,72E 02 2,02E 02 O,OOE-01 2,74E 00 1.SOE-02 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 2,85E-03 O,OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O,OOE-01 O.OOE-01*

O.OOE-01 2,7SE 02 2.02E 02 3,81E-04 1,33E-03 1,81E-03 3,57E-04 2,30E-04 7,26E-05 3,87E-04 O,OOE-01 1,74E-05 D,OOE~Ol 3,40E-05 5,85E-05 1,13E-03 i.ssE-03 1.96E-03 O,OOE-01 O,OOE-01 O.OOE-01 8,0lE-08 1,16E-06 2.8SE-08 2,58E-04 1,25E-05 1,45E-05 7.69E-04 3,33E-OS *S.03E-OS O.OOE-01 O,ODE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 l,lSE-04

9. l 7E- 08 4.89E-05 3,0lE-04 1,29E-OS 2,97E-05 O,OOE-01 O,OOE-01 S.71E-05 O.OOE-01 O.OOE-01 O.OOE-01 O,OOE-01 7,28E-07 1.64E-09 O,OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O,OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O,OOE-01 3.74E-05 O.OOE-01 O.OOE-01 7.87E-08 7,74E-07 O,OOE-01 O,OOE-01 3,27E-06 O,OOE-01 O,OOE-01

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TABLE 28 EFFLUENT ANO WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/84 TO 12/31/84 Page 8 of 10 SURRY POWER STATION UNITS 1&2 SR-89 SR-90 CS-134 CS-137 I-131 C0-58 C0-60 FE-59 ZN-65 MN-54 CR-51 ZR-95 NB-95 M0-99 TC-99M BA-140 LA-140 CE-141 I-133 CS-136 SB-125 RB-88 NA-24 SB-124 RU-103 CE-144 TE-132 C0-57 AG-110M SR-92

!-132 I-135 I-134 ND-147 BI-207 NA-22 FE-55 NP-239 TOTAL FOR PERIOD XE-133 XE-135 KR-85M XE-133M KR-88 AR-41 XE-131M XE-135M KR-87 LIQUID EFFLUENTS CONTINUOUS MODE UNIT THIRD QUARTER CI O.OOE-01 CI O.OOE-01 CI S.53E-02 CI 1.41E-01 CI 6,26E-04 CI 7,49E-05 CI 8,17E-04 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI 3,37E-05 CI S.64E-03 CI O,OOE-01 CI 1.95E-05 CI 3,76E-04 CI O,OOE-01 CI

• 6,33E-05 CI O,OOE-01 CI O,OOE-01 CI O.OOE-01 CI O.OOE-01 CI 1,69E-03 CI 7,99E-04 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O,OOE-01 CI O.OOE-01 CI O.OOE-01 CI O,OOE-01 FOURTH QUARTER O.OOE-01 O.OOE-01 9,76E-02 2.99E-01 2,20E-04 6,77E-03 4,52E-03 O,OOE-01 O,OOE-01 O,OOE-01 3.20E-03 O.OOE-01 1,93E-04 O.OOE-01 2.19E-05 O,OOE-01 O,OOE-01 1.0SE-05 5.SOE-05 O,OOE-01

4. 53E-O-S O.OOE-01 7.52E-05 0.00~-01 2,llE-05 O.OOE-01 2,31E-04 9,17E-06 O,OOE-01 O.OOE-01 D,DDE-01 O.OOE-01 O,OOE-01 1,84E-03 O,OOE-01 O.OOE-01 O,OOE-01 O,OOE-01 BATCH MODE THIRD QUARTER O,DDE-01 O.OOE-01 3.99E-01 8,71E-Ol 9.26E-02 6,63E-02 2,SlE-01 1,SOE-04 2,54E-04 7,73E-03 2,77E-03 6.39E-04 2,67E-03 4,7SE-04 1,03E-03 6, 17E-OS 3,20E-03 2,lDE-04 6.llE-03 1.6SE-03 3,74E-03 2,21E-03 4,36E-OS 1,SOE-04 3-.lSE-04 8.23E-04 6,90E-05 4.02E-04 1.98E-03 S,82E-04 l.98E-04 1.20E-04 3.44E-05 6,19E-06 2,29E-os*

2,42E-06 l.93E-02 O.OOE-01 FOURTH QUARTER 5,69E-04 O.OOE-01 2,99E-01 6.SSE-01 5,53E-02

1. lOE OD 6,46E-01 2,49E-03 1,32E-04 1,35E-02 3,29E-01 3.92E-02 4.SSE-02 3,14E-04 3.68E-04 1.86E-05 8,SoE-03 3.96E-03 7.04E-04 8,54E-04 S.90E-02 O.OOE-01 1,2DE-02 6,22E-02 1,34E-02 2.19E-02 2,07E-03 2.SOE-03 2,03E-02 7.46E-03 3.oOE-03 O.OOE-01 O.OOE-01 6,94E-05 Q.OOE-01 O,OOE-01 8,89E:..02 6.03E-04 CI CI CI CI CI CI CI CI CI CI 2.07E-01 4,14E-01 l.74E 00 3.53E 00

6. 66E-02 4.07E-04 O,OOE-01 l,OBE-04 5,25E-05 O.OOE-01 3,81E-04 O.OOE-01 O,OOE-01 2,39E-03 7,40E-06 O.OOE-01 O,OOE-01

-O.OOE-01 O.OOE-01 2,22E-04 O,OOE-01 O,OOE-01 1.12E 00 1.25E-Ol 1,39E-03 6,SDE-03 l,32E-03 5,02E-05 1,96E-03 l,60E-03 O,DDE-01 7.36E-02 l.89E-02 4.73E-04 l,SSE-04 l,23E-04 2.04E-04 l,42E-03 l,72E-04 2,23E-OS

.}

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 7/01/84-12/31/84 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1

• Type of waste Unit

a.

Spent resins, filter sludges. evaporator m3 bottoms, etc.

Ci

b.

Ory compressible waste, contaminated m3 equip., etc.

Ci C.

lrradiatsd components. control m3 rod!, etc.

Ci

d.

Other (describe) m3 Solidified Oil Ci

2. Estimate of major nuclide composition (by type of waste)

a.

Co-60 Co-58 Cs-137 Fe-55 Nl-63 Cs-134 Mn-54 Cr-51

b.

Cs-137 Fe-55 Co-60 Cs-134 H-3 Ni-63

.co-58 C.

d.

H-3 Cs-137

3. Solid Waste Disposition Number of Shipments 12 12 l:lo.dLof Icaosportatioo Truck Truck

8. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments 0

l:lo.dLof Inmsportatjon Not Applicable 6-month Period 4.49E+01 1.02E+03 3.52E+02 6.79E+OO O.OOE+OO O.OOE+OO 7.B6E+OO 2.12E-01 4.16E+01 1.61E+Ol 1.52E+01 a.30E+oo-6.13E+oo 4.79E+OO 2.21E+OO 1.20E+OO 2.59E+01 2.23E+01 2.02E+01 1.32E+01 9.54E+OO 4.17E+OO 3.76E+OO O.OOE+OO 9.73E+01 1.04E+OO Destjnatjon Barnwell, SC Richland, WA Est. Total Error, ii; 5.00E+OO 3.00E+01 5.00E+OO 3.00E+01 O.OOE+OO O.OOE+OO 5.00E+OO 3.00E+01 Destjnatjon Not Applicable Page 9 of 10

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j A ttachrnen t 1 Page 10 of 10 Curies - Mixed Mode Airborne Releases The following activity represents mixed mode releases for the first six months of 1984.

This activity is included in the tables listed on pages 1-3 of Attachment 1:

Isotope Activity ( Curies)

Xe-133 6.33E+2 Xe-133m 2.3SE+O Xe-135

1. 36E+ 1 Xe-13lm 2.lOE+O KR-85m S.75E-l KR-88

4. lOE-1 I-131 2.0SE-4 I-132 l.57E-7 I-133 3.83E-S I-135 S.37E-6 H-3 l.SOE+l Cs-134 2.07E-5 Cs-137

3. 77E-5 Co-58

8. 42E-6 Co-60 6.52E-S Mn-54 l.14E-6 Rb-88 1.14E

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1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Body (mRem) 6.70 E-3 1.03 E-2 9.34 E-3 2.22 E-2 4.85 E-2 ANNUAL AND QUARTERLY DOSES LIQUID GASEOUS Thyroid GI-LL!

Gamma Beta (mRem)

(mRem)

(mRad)

(mRad) 2.54 E-2 1.37 E-2 1.11 E+O 3.24 E+O 2.19 E-2 1.59 E-2 3.35 E+O 8.60 E+ 1 5.87 E-3 8.92 E-3 3.32 E-1 8.94 E-1 5.76 E-3 2.20 E-1 1.37 E-1 4.08 E-1 5.89 E-2 2.58 E-1 4.93 E+O 1.31 E+l Page 1 of 1 Thyroid (mRem) 6.69 E-1 2.72 E-1 6.12 E-2 4.48 E-2 1.05 E+O

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Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (0DCM)

There were no licensee initiated changes made to the Offsite Dose Calculation Manual during the period July 1, 1984 through December 31, 1984.

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REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP)

Page 1 of 5

1.

A revision to the Process Control Program was approved on November 27, 1984.

a.

Surry Power Station currently does not operate a permanent system to solidify radioactive wastes onsite and therefore, relies upon vendor supplied systems.

When solidification is required, a vendor will supply a temporary onsite solidificat-ion system, set of operating procedures and a PCP. Upon approval by the Station Nuclear Safety and Operating Committee, the procedures would be incorporated into appropriate operations and/or Health Physics Procedures as an Attachment.

Incorporating vendor operating procedures and PCP into station procedures requires wide distribution to all holders of Health Physics and/or Operations procedures. The change made to the PCP in November provided the flexibility to incorporate vendor supplied procedures and PCP as an Attachment or by reference.

b.

The Surry PCP lists criteria which vendor supplied PCP's must comply with to insure the overall conformance of the solidified waste product. This revision did not alter these criteria, therefore, the change did not reduce the overall conformance of the solidified waste product.

c.

The following pages contain a copy of the changes to the PCP and documentation that the change was reviewed by the Station Nuclear Safety and Operating Committee.

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.i r SURllY POWER STAl'ION Pi.OCEDtT.RE TYPE PROCEDURE:

PROCESS CONTROL PROGRAM TITLE:

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM lIST OF EFFECTIVE REVISIONS:

SECTION

~

1.0 08-02-84 2.0 08-02-84 3.0 NOV 2 7 1984 4.0 NOV 2 7 1984 5.0 08-02-84 6.0 NOV t 'I 1984 7.0 08-02-84 8.0 08-02-84 (3

• Page 2 of 5 (l)

PROCEDURE. Process NUMBER: Contr. Pro *

(2)

DAl'E:

NOV 2 ? SS.

4)

UNIT iJ:

1 & 2 (5)

(6 THINK ALAR RECOMMEND APPROVAL:

(7)

J:\\J.a. Ua -

DA:rE: / I -

t;°*

(9)

(10)

DATE: // - 2o-Yf' AP~OVED STATION.NUCLEAR SAFETY AND OPERATING COMMITTEE:

(11)

(12)

) 41141'1 L Jw4arz DAl'E: 11-1.7-84

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Page 3 of 5 PCP-7.0

• NOV 2 7 1S84 3.0 System Description [continued]

3.2 Solidification System [continued]

The system operating procedures for solidification will be submit-ted to Vepco for determination of compliance with the Process Control Program.

Upon approval by the Station Nuclear Safety and Operating Committee, the procedures will be incorporated into the appropriate Operations and/or Health Physics Procedures as an attachment or by reference.

The solidiiicat_ion system will not be considered operable until the operating procedures are approved by Vepco *

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4.0

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Page 4 of 5 PCP-10.0 lfOV ! 7 834 Waste Sources and Characteristics [continued]

4.2 Filter Elements 4.3 Mechanical filters normally using wound cartridge are usad for removing particulate matter from systems described in Section 4.

Spent filter elements are removed from systems and placed in storage bunkers to await processing and shipment.

The filter elements are stabilized by cement encapsulation prior to shipment.

Methods and procedures for encapsulation have been approved by the Burial Site operators.

Alternate pack.aging methods such as placement in high integrity containers may be considered.

Uti-lization of these methods would be subject to approval by the Burial site.

Organic Waste Oil used in systems for cooling and lubrication which comes into contact with radioactive contamination, must be processed to ensure compliance with Burial site requirements.

Oily waste is generated by system leakage or from normal system replacement and stored until the batch can be processed.

All contaminated waste oil requiring burial at a radioactive waste burial grounds will be stabilized by solidification. Solidification equipment, materials and procedures will be supplied by the contractor and included as an attachment to, or referenced by station approved'procedures.

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6.0 Contractor Services/Station Interface and Reouireil)ents PCP-14.0 Page 5 of 5 NOY 2 7 1984 Currently-there is no installed solidification system onsite to process wastes that require solidification.

In the event such services are required, a contractor will be requested to submit, for approval, solidification system operating procedures, a list of physical inter-.

faces, materials required, and a list of expected utility/contractor responsibilities.

The solidification system operating procedures will be reviewed in '

accordance with the Process Control Program to determine adequate station control and Quality Assurance criteria are met.

Once approved by the Station Nuclear Safety Operating Committee, the system operating procedures will be incorporated into, or *referenced by existing Health Physics and/or Operations Controlling Procedures.

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MAJOR CHANGES TO RADIOACTIVE UQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS Page 1 of 1 There were no major changes to Surry's Radioactive Liquid, Gaseous or Solid Waste Treatment Systems during the period of July 1, 1984 through December 31, 1984.

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Page 1 of 1

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C INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION Technical Specification 3.7.E.2 requires the Semi-Annual Report to include an explanation why monitors required by Technical Specification Tables 3. 7-5 (a) and 3. 7-5 (b) which were determined inoperable, were not returned to operable status within 30 days.

Three monitors require explanation under this criteria for the period of July 1, 1984 through December 31, 1984. They are the Component Cooling Service Water Monitor, Unit #2 Discharge Tunnel Monitor and the Waste Gas Holdup System Explosive Gas Oxygen Monitor.

1.

The Component Cooling Service Water Monitor (RM-SW-107) was inoperable prior to this reporting period. The offline Radiation Monitor is operable but pumps bringing service water to the monitor failed. Repeated efforts to return the pumps to operable status failed and on June 4, 1984, a Design Change (84-25) was initiated to replace the monitoring system.

Grab Sampling, required by Table 3.7-5 (a) when the monitor is out of service, has been performed since the monitor became inoperable.

The Grab Sampling will continue until Design Change 84-25 is completed.

2.

The Unit #2 Discharge Tunnel Monitor (RM-SW-220) was determined inoperable prior to this reporting period.

The inline monitor housing experienced corrosion problems and requires redesign to provide stronger support. An Engineering Work Request (EWR 83-12) was initiated on October 28, 1983.

All Effluent Releases via this pathway have been diverted to the Unit # 1 Discharge Tunnel.

3.

The Waste Gas Holdup System Explosive Gas Oxygen Monitor (GW-102A and GW-102B) was inoperable prior to this reporting period. Repeated attempts to return the monitor to service during the months of June, July and August of 1984 failed and an Engineering Work Request (EWR 84-268) was initiated on August 31, 1984 to correct the problem.

Grab Sampling, required by Technical Specification Table 3. 7-5 (b) when the monitor is out of service, has been performed since the monitor became inoperable. The Grab Sampling will continue to satisfy the monitoring requirements until the installation of the new monitors.

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~,'J UNPLANNED RELEASES Page 1 of 1 There have been no Unplanned Liquid or Gaseous Releases that exceeded Technical Specification 3.11.A.1.a or 3.11.B.1.a during the period of July 1, 1984 through December 31, 1984.