BSEP-87-1173, Revised Semiannual Radioactive Effluent Release Rept for Jan-June 1987
| ML20236C837 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1987 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| BSEP-87-1173, NUDOCS 8710270357 | |
| Download: ML20236C837 (31) | |
Text
{{#Wiki_filter:- ' ATTACHMENT 1 Supplemental Information January 1 to June 30, 1987
'1 l
l 1 l l l l l l A
- m. ,
9 !
, 7 ,.
.j; f.
I l' EFFLtENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plant Licensee: Carolina Power & Light Company I L1. Regulatory Limits { A. Fission and activation gases (Technical Specification 3.11.2.2)
*(1) Calendar Quarter (a) 10 mrad gamma (b) 20 mrad beta .
(2) Calendar Year I (a) 20 mrad ganna (b) 40 mrad beta G. Iodine-131,. Iodine-133, tritium, and particulate with talf-lives greater than eight days (Technical Specification 3.11.2.3)
*(1) Calendar Quarter (a) 15 mrem to any organ .
(2) . Calendar Year (a) 30 mrem .to any organ C. Liquid effluents (Technical Specification 3.11.1.2)
**(1) Calendar Quarter (a) 3 mrem to toal body (b) 10 mrem to any organ l (2) Calendar Year (a) 6 mrem to total body (b) 20 mrem to any organ NOTE: Dose calculations are determined in accordar.ce with the Off-site Dose Calculation Manual (ODCM).
Used for percent of technical specification limit determinations in Table 1A.
** Used for percent of technical specification limit determinations in Table 2A.
f 1/2 l
l , gy ,,
,. z ,
l
- 2. Marinam permissible concentrations and dose rates which determine -1==
instantaneous release rates. .
"A. Fission'and activation gases (Technical Specification 3.11.2.1.a)
(1) 500 mrem / year to total body (2) 3000 mrem / year to the skin B. Iodine-131, Iodine-133, tritium and particulate with half-lives greater than eight days (Technical Specification 3.11.2.1.b) (1) 1500 mrem / year to any organ l C. Liquid effluents (Technical Specification 3.11.1.1) The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than noble gases.
** (1) Tritium: MPC = 3.00E-03 pCi/ml and
** (2) Dissolved and entrained gases: MPC = 2.00E-Ol4 pCi/ml ,
I
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Analysis for specific radionuclides in representative grab samples by gamma spectroscopy.
B. Iodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy. C. Particulate i Analysis for specific radionuclides collected on filter papers by ganana spectroscopy. D. Liquid Effluents 1 Analysis for specific radionuclides of individual releases by gamma spectroscopy. l ** Used as applicable limits for Table 2A 1/3 I' l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Nuclear counting statistics are reported utilizing 1-sigma error. Total error
~
where reported represents a best effort to approximate the total of all indi-vidual and sampling errors.
- 4. Batch Releases
'A. Liquid (1) Number of batch releases: 3.40E+02 (2) Total time period for batch releases: 4.06E+04 Minutes (3) W ri-n= time period for a batch release: 1.85E+02 Minutes (4) Average time period for a batch release: 1.19E+02 Minutes (5) Minimum time period for a batch release: 1.00E 00 Minutes (6) Aversge stream flow during periods of release of effluent into a flowing stream: 4.69E+05 gpm B. Gaseous (1) Number of batch releases: 0.00E 00 (2) Total time period for a batch release: 0.00E 00 Minutes (3) W r1=n= time per!cd for a batch release: 0.00E 00 Minutes (4) Average time period for a batch release: 0.00E 00 Minutes (5) Minimum time per lod fer a batch release: 0.00E 00 Minutes
- 5. Abnormal Releases A. Liquid f (1) Number of releases: 3.00E 00 (2) Total activity released: 7 20E-02 Ci a On April 26, 1987, at approximately 10:30 a.m. and 3:00 p.m., releases i were made via the U/2 service water system. Both releases were monitored ]
by the U/2 service water radiation monitor uld lasted for approximately J one minute. At the time of these releases, the U/1 service water was j being diverted to the U/2 service water system. However, some activity j was detected by the U/1 service water radiation monitor indicating a I release to the U/1 discharge tunnel, which was not in service during j this time due to scheduled outage activities. This activity was later ! released on May 1, 1987, when the U/1 service water system was returned to normal serv $ce. The cause of these releases was a leak from the U/1 residual heat removal system to the U/1 service water system. f B. Gascous l l I (1) Number of Releases: 0.00E 00 (2) Total Activity released: 0.00E 00 Ci l ! j 1/4 f l l l
. ,, ; .y j . ;. 7 ,
p; V' yyg Effluent and Waste Disposal Data Brunswick Steam Electric Plant i January 1 to June 30, 1987
' Enclosure 1:
o Table IA: Gaseous Effluents - Summation of All Releases Table-1B: Gaseous Effluents - Elevated Releases Table 1C: Gaseous Effluents - Ground Level Releases
' Table 2A: Liquid Effluents - Summation of A11' Releases Table 2B:-' Liquid Effluents Lower Limits of Detection-Table 3: Solid Waste and Irradiated Fuel Shipments Enclosure 2:
Combustion of Waste Oil i 2/1
.. , . ~- - -
- p. .O 0 .;
1 Table'1A I .
; Gaseous.; Effluents:- Summation of. All-tieleases.in 1907.
y Est. t Total Unit- Otr 1; Gtr 2 Error.%. i
'A. Fission and' activation .j gases
.m 1. Tota l - r el ea se ;- Cl 8'.17E C3 6.00E 03 '1.15E 02 l
~
L 2 .~ ' Average release rate' 'uCi/sec 1.05E 03 7.63E 02 for' period {". ;
.i
- 3. . Percent of technical.
specification limit -% 3.62E-01 2.72E J
-8. Indines.
- 1. Total. iodine-131- Ci> 5.86E-03 4.85E-03 '7.00E 01 N
- 2. Aver a g'e - r el ea se . r a te . uCi/sec 7.54E-04 6.17E-04 for: period C. -Particulate l
- 1. ' Tot'al r el e a s'e Ci 8.52E-03 1'.83E-02 7.00E 01:
- 2. Ave' rage' release rate' uCi/sec 1.10E-03' 2.33E ,.
for' period
- 3. Gross-alpha Ci 3.31E-05 1.44E-05.
D. Tritium
- 1. -Total release Ci 9.28E-01 6.56E-01 7.00E 01 2.- Average release rate uCi/sec 1.19E-01 8.34E-02 for period l
E. ' Iodine-131, Iodine-133, Tritium l and Particulate 1 1.. Total release Ci 9.61E-01 7.12E-01 I
- 2. . Average release rate uCi/sec 1.23E-01 9.06E-02 1 for veriod l
- 3. Percent of technical ,% 2.05E-01 1.93E-01 specification limit 2/2
P Table 1B Effluent and Waste Disposai' Semiannual Report Year 1987
.' Gaseous Effluents - Elevated Release Continuous Release Nuclide.s Released Unit Gtr 1 Otr 2-
- 1. Fission Gases argon-41 Ci 7.21E 00 6.90E 00 krypton-85m . Ci 4.52E-01 8.74E-01 krypton-87 Ci 3.66E-00 2.15E 00 l krypton-88 Ci 1.02E 00 (LLO xenon-133 Ci (LLD 5.98E 00 xenon-135m Ci 2.16E 01 2.50E 01 xenon-135 Ci 7.73E 00 9.41E 00 l
xenon-137 Ci 1.21E 02 1.82E 02 xenon-138 Ci 7.05E 01 5.90E 01 total for period Cl 2.33E 02 2.91E 02 l 2. Iodines iodine-131 Cl 5.11E-03 2.47E-03 iodine-132 Cl 1.07E-02 6.75E-03 lodine-133 Ci 1.46E-02 1.04E-02 iodine-135 Cl 1.17E-02 6.03E-03 total for period Ci 4.21E-02 2.56E-02 1
- 3. Particulate chromium-51 Ci 3.15E-04 3.91E-04 manganese-54 Ci 2.67E-05 1.02E-04 cobalt-58 C1 (LLD 6.00E-06 ,
cobalt-60 Ci 4.06E-05 9.83E-05 strontium-89 Ci 1.01E-03 1.07E-03 strontium-90 Ci 3.63E-06 3.95E-06 cesium-137 Ci (LLD 5.75E-06 barium-140 Cl 1.31E-03 1.81E-03 lanthanum-140 Ci 9.02E-04 1.18E-03 total for per. lod Ci 3.60E-03 4.67E-03
- 4. Tritium hydrogen-3 Ci 4.62E-01 3.34E-01 2/3
7_, 3
, u .,
y w; .( l - 1 Tab 1'e11C .
'EffiuenL andaWaste-Disposal ^ Sem i annual' ~ R epor t ' . Year 1907. l
' Gaseous'EffluentsL-; Ground Level Releases .]
. Continuous ~ Release '
B , INuclides; Released Unit' Gtr 1 Otr 2
'1".'i: i ss i on Ga ses
; krypton-88 Ci- .<LLD 1.06E 00 .;
senon-133: Cl. 7.62E 02 8.10E 02 xenon-135 . Ci. 7.18E 03 4.90E 03 s---._- -_. -_---- ----- .- - -._ - - _'.- _.- - - - - -.- - - - - - - - - , total fo'r period. Ci 7.94E 03 5.71E 03 I 1 i 2.lodines
. iodine-131 Cl- 7.46E-04 2.38E-03 ;j lodine-132 Ci 1.70E-03 3.06E-02 i w - iodine-133 Ci 3.80E-03 .2.22E-02 l lodine-135- Ci. 1.37E-03 .4.26E-02'
----------------------_.------------------------------- ]
total forLperiod .' C i 7.62E 9.78E-02 l 4
- 3. Particulate chromium-51 Ci 3.30E-03 9.22E-03
]"
manganese-54~ Ci 5;67E-04 1.52E-03 cobalt-58 .Ci 1.15E-04 3.95E-04 ;
'i r on-59; Cl 1.00E-04 2.13E-04 !
cobalt-60 Ci 7.06E-04 '1.61E-03 q s trontium-09' Ci 2.68E-05 '6.69E-05 j strontium-90 Ci' <1.42E-07 8.63E-07 a cesium-137 Ci l'.71E-05 0.73E-06' -l barium-lanthanumu140 cerium-141 Ci Ci (LLD-(LLD 5.75E 1.65E-05. j
.H total for period Ci 4.92E-03 -1.36E-02 ,
4.Tr.itiumi j hydrogen-3 Ci 4.66E-01 3.22E-01 l 1 i r 1 2/4 1 =___u___- -
. x.: ay~ ~. .
.I rl j .
TABLE 2A EffluentLand. Waste Disposal. Semiannual Report Year ~1987-LiquidiEffluents -' Summation of All Releases
. . 1
'ljnit' Qtr l' Qtr-2' Est Tot'. :j Error,.%~
lA. Fission and activation 1 productsL
']
- i
? 1'. To t a l release;(excluding Ci 4.46E-02 1.92E-01 3.50E 01' d
- tr i.t'l um , g a ses , a l p h a ) l
. ~ d 2.Av. dilutedLeoncentration uCi/ml 1.40E-09. 4.78E-09 1 t
- 3. Percent ~1'imit %. 1.57E-01 7.38E-01 B;1 Tritium 1'. Total release Cl- 3.58E-00 3.76E 00 ~4.00E 01 2.Av. diluted concentration uCi/ml 1.12E-07 9.30E-08
- 3. Pertent .11mi tf % 3.73E-03 3.13E C. Dissolved and-entrained gases
.1. Total release ;Ci 9.00E-02 4.90E-O' 3.50E 01 2.Av. . diluted, concentration uCi/mi 2.82E-09 1.22E-09
- 3. Percent limit % 1.41E-03 6.10E-04
- 0. Gross alpha' radioactivity
- 1. Total release Ci 0.00E 00 0.00E 00 4.00E 01 i
E. Volume of waste liters 1.34E 07 1.24E 07 1.25E 01 F. Total volume of dilution water (L) (used during released for av. 1 diluted concentra tion ) liters 3.19E 10 4.01E 10 1.30E 01 1.
-G. Volume of cool ing water
. 'd i s c le a r g ed from plant liters 2.02E 11 2.62E 11 2/5 r
, ;)" * '
.j 1 j 3
' '~
" TABLE 20 l Effluent and Waste DisposalLSemiannual Report: Year:1987 Liquid. Effluents ' Batch Mode f
!Nuclides Released. -Unit- Otr 1 Gtr 2
- 1. Fission and activation products- 1<
? chromium-51 Ci 5.86E 1.39E-02
. manganese-54 Ci 6.60E-03 1.18E-01 !
Iron-55 Cl 9.93E-03 3.08E-03 neptunium-239 Ci < LLD 4.80E-06' a K.. ' cob a l t-58. Cl 1.09E-03. 9.19E-03 ; y ' Iron-59 '
-Ci 1.17E-04 4.41E-03 Ci 1.8BE-02 cobalt-60 '4.07E-02 1 arsenic-76 Ci 2.62E-05 2.53E-04 i
-iodine-132 Ci ( LLD 1.24E-05 strontium Cl 1.04E-04 2.04E-05 yttrium-91m . Ci .1.68E-05 ( LLD antimony-125 Ci < LLD 2.74E-04 i niobium-95 Ci ( LLD 3.15E-05 -i technetium-99m Cl 1.42E-04' 5.65E-05' ,
zinc-65 Cl (LLD 8.50E-06 '! te11urium-132 Ci ( LLD. 5.81E-07 silver-110m Ci 2.20E-04 8.06E-05 ' f l od i ne-131 - Ci 1.16E-04 9.24E-04 I lodine-133 Ci '1.97E-05 4.05E-04 cesium-134L Ci 6.16E-05 1.27E-05 i cesium-137 Ci 1.24E-03 7.16E-04
-lanthanum 140 C i- 28E-04 (LLD .;
-lanthanum-142 Ci sLLD 1.81E-06 tungsten-187 Ci < LLD 1.79E barium-139 Ci 1.07E-04 (LLD strontium-89 Ci 8.51E-05 '<LLD total for period Cl 4.46E-02 1.89E-01 I
1 1 l -
~
I L i-l l 2/6 ! ( I a: 2 -_ _ ______ _____ _ ._
y,m - ,
. N '
TABLE 20 (cont).
. Effluent'.and Waste Disposal Semiannual Report Year. 1987-i' >
LLiquid Effluents - BatchLMode i! l t J
<2. Gases- ,
argon-41 Ci < LLD- 2.08E-05 I krypton Ci < LLD. 2.20E-03 krypton-85m Ci 9.43E-06 8.62E-06
,< xenon-131m Ci 7.14E-04 (LLD-
. xenon-133 ,
Ci 2.56E-02. 1.14E-02 i xenon-133m
^
Cl 3.19E-04 4.63E-05 l xenon'-135m Ci 1.06E-04 4.14E-05
- x en on-135 Ci 6.33E-02 .3.53E-02' total for; period. Ci .9.00E-02 4.90E-02 I
l l 4. l s
/
1 i
.j l
1 1 l l 1 2/7 ! I A -.-- - _ - - _ - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - -
Lower Limits of Detection UCi/ml 1
.i.' Liquid; Releases. 2.. Gaseous Releases-
-Y-91m' 2.69E-08 Kr-88 3.65E-08
- Ba-139 8.86E-08 Xe-133 -2.62E-08 LSb-125 -5.73E-08 Kr-85 15.69E-06' Nb-95 12.31E-08
'2n-65 2.22E-08 3. Iodines and Particulate 1'
-Te-132 1.50E-08:
La-142 4.23E-08. Ba-140 9.94E Np-239 1.08E-07 La-140 1.26E-13 , W-187 8.16E-08 Ce-141 4.23E-14 Ar-41' -3.18E-08' Co-38 3.62E-14 I-132 3.10E-08 .Cs-137 2.46E-14 , Sr-89 2.92E ' G-Alpha 2.85E-08 La-140 2.91E-08 Xe-131m ~6.67E-07 ' 1 NOTES 1: 1The above values represent ~ typical 'a priori' LLDs for . isotopes where values of '< LLD' are indicated in Tables l
- 1A, 10, 1C,2A and 28. ;
-{
2: Where activity for any nuclide is reported as 'Less than { LLD' , that nutilde is considered not present and the 1 LLD activity listed is not considered in summary data . sj 3 I i i 1 1 l u I l L 2/8
y-l
}
l i TABLE 3A Effluent _and Waste Disp'osal Semiannual Recort Year- 1987-Solid Waste'and' Irradiated Fuel' Shipments daste' Class A January through June l'. Total. volume sh'ipped, cubic meters 5.35E 02 Total Ci quanti ty (estimated) 2.66E 03 2.-Type'of Waste Units Six-Month 'Est. Total Period Error,;% a . Spen t 'res ins, f il ter sl udges cubic meters 1.98E 02 Curles 2.64E 03 1.00E 01
- b. Dry 1 active waste, compacted, -cubic meters 3.37E 02 noncompacted Curies 1.90E 01 1.00E 01 c.~ Irradiated componentu: cubic meters N/A Curies N/A N/A d.Others' ' cubic meters N/A . ,
Curies N/A N/A. 3.Eutimate of major radionuclides composition a.- Cr-51 1.55E 01 % Mn-34 1.50E'01 % Fe-55 3.16E 01-% Co-38 2.35E 00 % + Co-60 3.00E 01 % Ni-63 1.51E 00 % Cs-137 2.60E 00 %
- b. Cr-31 4.39E 00 % !
- Mn-54 8.84E 00 %
Fe-35 5.68E 01 % Co-60 2.47E 01 % Ni-63 1.03E 00 % Cs-137 1. 5E 00 %
- c. N/A N/A l
- d. N/A N/A 1
1 2/9 l
ry ,
- p. .. ,
e a, (. !
.h -.
B TABLE 3A (cont) E F Fl uent and Was t,e D i sposal Semiannual Report Year. -1987 Soll'd Waste.and Irradiated Fuel ~ Shipments l
- 4. Cross reference table,' waste. stream, Form,conteiner 1,ype.
,h Form No.Shioments' St, ream -Container Type ;
- a. Rewin Dewatered 6 Type-A/ Type B 39/00 1-Solidified * ' .
4
- b. Dry active Compac ted/non - '
~c; waste c.omp a c ted LSA/STP li ,
waste. j
- c. Irraciated N/A' N/A !
componentu-
- d. 'Other N/A N/A
- Solidification agent or-absorbent (e.g.,
. cement, urea formaldehyde, etc.) CEMENT:
- 3. Shipment, Disposition. j,.
p a.. Solid, Waste Number or Shipments.. Mode of Transportation ' Destination ,
.50 Sole Use CNSI-Barnwell, SC l
.~
1
- b. Ireadiated Fuel
, Number of Shipments ' Mode of Transportation Destination N/A N/A N/A l f
L. 2/10
- l. - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
> JT
~
g eg.bgry?w 7 whhh , h, h - h{ , V . a,9y) V eec. u , >r< w" : ~ b:~. - R .y. . $
-1 f;1. .
ect + b) f:? , 3 i
, 4j! .
'is. q e
Q.. Kb z ggw r "
~
y J h (, 7. [(Eff'fl uhn k. t;. a ndl%nste'-
' i* ' f
E*, m ;
& .aTABLE 3D- i s J M , D i soosa10 Sem i annua l R ep or t .- . ' Year 1937 :-
- p h OW ,
! sq '
y 4 + r 4:f.,:! ,; 9%.. n i: t
-t ,
l gW r Wau til C1 aus 84 (G January;through June. - gM - ' ' X Q@Ydf g>o l'.aTot'41 vo'li>'J'Weii
;W :. . - . .
;n pued > cub i c 5't'r5:-
7 24 Eoo' 'N : . . . , . . . .A
, GTbtal C I? quan L i by 4(eutimated)
.,'g,~ # 1.63E 03 q&, ,
m > /. x ,. y. cli' b ;. . ;
- g. , y-ny y; 3. >.... ' .%, ~ +' ..
r, . . , a M ' O y 2.(Typefof' Waste ' .. Uni'ts Six-Month! Est'.T c t a ll , Period Error;:% 1
,o , 1 > !
a fSp ent-ires i n s , F-.l'i ter isl udg es . cubic ~ meters 7.14E 00;
. . . s .h wCurles 1. 65E.,03 ' t . 0 3E 01h, .
b".DM'. m e tive , wa ste , conoActed , -cubic 1 meters N/A' ,- 3. q ;
- o, mchicolap' acted ' "
-Curies N/A
~
--N/A:
N cGrc'ad i a ted > comp on en tu s-
~ '
Scubic meters, ' N/A .t 1E,
; A in . . . . _
's(Curies <
N N/A !M/A 1 '
' d'.O th er s ( d escr I b e ) : cubic' meters N/A -
1
.m =
!, jQ '
= i Cur'ies N/A'
.N/A-
i'S
'l
' ' dif ' 3.Est i ma tw 'uf..' ma jor r ac ionucl i de comp'os i t i oni
~
ygf$ qs d T' - f'a. T
<L m Cc-51 Mn -34 2.67E'01
'1'.20E 01 '
- a p'" :lE ,
w. q< w Fe-55 4.52E 01 c
? A U m
Fe -39 B.76E-01 ' +
- 4. %, '
W s m 1197E 00
,Mk ?' t Co-58 g ny u. 'k Co 1415E 01 < :
r c.. I y:- y( y.~p b ' b '. N/A. N/A s Yb 1 j c. f X N/A N/A"
. .. ,j y T,6 - diH d.- Y
' N/A N/A
" t k'
- 4. Cross reference table,saste stredm., form, container type. ,
.i.
Stream Form Ccitainer Type No2Ehisments nau ', " s y h ,.s a. Resin Solsiiried Type A/Ty}/s.. B %/0.' r ~ i 4' ' ' s .Dey active Compacted /non- ' i; , ,[. waste compacted .N/A 'd, N/A' b y) ..
,Teradiated waste 9. g .
s j
.q' q c.
N/A ' N/A4 q , -I cbduor a r - Otthyr gents /' ! f .., N/A 'N/A d.,j i 2M d i F ic4 6 r@ dent or(i absorcen\ t f" , 1 ( e ., g y . c emen L , l<, *4;Jl urMa formaYd;*hydb, etc. \ Cement
\
a'> f i ,
,- ,)* 'n
y i
.L t YY $
y/' y w rl, - y ,
, j q , .
n,,
= _ _ _ - _ 1- . b1
g ., . yy .
-r;
,4 ' ' W\ \
'N
} jQ. v&" [i
,. 1; s A, A ,
.w
, , I .1 . g '. E o :.e
! y" ,, ..t,.
, j u o.? .pp, i
!) ' TABLE 38 (cont) 'p '~
(- Effluent.and Waste D'isposal' Semi ~ annual Report'. .. Y e a [ ' 1 9 0 7 ':'Io . LSolId Waste-and Irradlated FueltShipments y.'_ '-
-/'
u'),h.
.fj . ;
- 3. -l Sh i p mdri t . D i sp os i t i on ' .
,t.
I'
- a. . Solid. Waste t
~ -t Number of Shipments: Mode of Transportation Destination
.. -2 . Sole use CNSI- b~ ( .Barnwel l,f G i m, . ,
')'
b.- Irradi'ated Fuel t.
. . . - 4 Number of. Shipments b'j 1 j Mode.of Traniiporation bks.tination 'l y 's ' ,s. .,
~N/A ,, .N/A- N/A. ll '
S 3 c , t i
)
)~
) i i
4
)
.Y 2/12 i
m= - yin
)
m ,
;r ,
j, .' ' i
'4 ;
. 1
. TABLE.3C 4EFfulent and Waste. Disposal temiannual Report Year 1907 Sol id Waste: and' Irrad iated Fuel Shipments N 1 Waste Clasu C .
January . through June- ) 1 1 i
'1. Total volume.sh'ihped, cubic. meters N/A- l l
Total Cl qua,nkty (estimated) N/A 1
- 2. Type of Waste Units Six-Month Est. Total' Y Period Error,-%
k
- a. Spent, resin 6,fi,1terzsludges cubic meters N/A Curles N/A N/A b .Dep ac t i vri wa ste , compacted , cubic meters N/A 1 n o n c or.ib e,c'e e d . Curies. N/A N/A' l c.Irradipted. components: cubic. meters N/A Curies N/A' N/A ;
d . O th er s ( d ech, r i b e ) : cubic meters N/A Curies N/A N/A 3.EsLimate of major radionuclides' composition
- a. N/A N/A 1
- b. N/A N/A l l
- c. N/A N/A i
- d. N/A N/A j
- 4. Cross reference table, waste stieam, form, container type. l 1
Stream Form Cuntainer Type No. Shipments I i.
- a. Resin Dewatered 6 N/A N/A Solidified *
- b. Dry active Compacted /non-waste compacted N/A N/A waste
- c. Irradiated N/A N/A cumponen ts
- d. Others N/A N/A
- Solidification agent or absorbent (e.g.,
cement, urea formaldehyde, etc.) N/A l l 1-l2 l1 2/13 L I L t _ _ __ ____ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
.I
.g. . _
h:
- f. s si '
TABLE 3C (cont) Effluent and- Waste Disposal Semiannual- Report Year 1987 Solid Waste and Irradiated. Fuel Shipments U. Shipment, Dispoul. tion - I
- a. Solid Waste Number of Shipments. Mode of Transportation. Destination N/A N/A N/A a
l b.Irra'iated. d Components
. Number of Shipments Mode-of Transportation Destination N/A. N/A- N/A '
1 1 1
- l t
a 2/14
,, i <
EBCIMURE 2 Combustion of Waste Oil
~ During the first quarter, a total of 1.35 E03 gallons with 1.82 E00 uCi of
' waste oil were disposed of by incineration. During the second quarter, a total of 2.31E02 gallons with' 3.2h3 E-01901 of oil were disposed of by incineration.
A h l l 4
.i i
i f' I l 4 2/15 L
h c j i t ATIACEMENT 3 i? ( Off-site Dose' Calculation Manual (ODCM) and' l 4 . Process Control Program (PCP) Revisions January 1 to June 30, 1987 Brunswick Steam Electric Plant (. There were no revisions made to the Off-site Dose Calculation Manual (ODCM) [. l' or to the Process Control Program (PCP) during this time period. l l i l J l l 3/1 1 1
; c.
ATTACIDG2fT 4 Environmental Monitoring Program January 1 to June 30, 1987 Enclosure 1: . Milk and' Vegetable Sampie Locations i. Enclosure 2: Tand Use Census 4 i i i i d 1 u ,
'l l
i e 4/1
ar ~ EBCLOSURE 1 Milk and Vegetable Sample Locations i 1 i No milk' sample. locations were available during this time period. Vegetable f i sample ' locations were unchanged during this time period. 1
.[
6 s i
?
i 1 i h/2
+ , ,
'l o '. ,
i EECLOSURE 2 v k 0 rand Use Census A
'I No new locations were identified that'are reportablelin the Semiannual' Radio-
. active Effluent' Release Report as per Technical: Specification 3.12.2.a and b.
i , ;s, l 1
.i '
1 l i i I l 1 0 l l l l l i f 1 i h/3 a
s-i
- 4 ,, s i
1
' ATTACHMENT 5 ' !
Inoperable Effluent Instrumentation January 1 to June'30, 1987 ;
' Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation Enclosure'2: Radioactive Gaseous Effluent Monitoring Instrumentation Enclosure 3: . Liquid Hold-up Tank t
l i l
~I 1
m i j i il 5/1 c l
7,1 - ..- ENCLOSURE 1 Radioactive Liquid Effluent Monitoring Instrumentation
.The'U/1 main. service water effluent radioactivity monitor (1-D12-RM-K605) was inoperable for greater than.a 30 day period during January 1 to June 30, 1987 This monitor was not returned to service within a 30 day period due to j i
maintenance activities and the time involved to perform a plant modification I i 1 to' connect the monitor to the Emergency Response Facility Information System. -j 1 1 1 1 1 i i l I l l l l l l l l 5/2 l t
[ .
;. +
i ,. - ,- .v ! E5 CLOSURE 2 Radioactive Gases Effluent Monitoring Instrumentation r l the U/1 Turbine Building ventilation noble gas monitor (1-D12-RM-k5k8-1) was
' inoperable for a period of greater than 30 days during January 1 to' June 30,
- 1987. ~ This monitor was not returned to service within a 30 day preiod due ic the time involved in performing plant modification for system connection to the Emergency Response Facility Infor1mation System, and additional maintenance problems that were discovered during this time frame.
Units 1 and 2 main condensor off gas treatment system explosive gas monitors 1(2)-0G-AIT-k284, 1(2)-0G-AIT-k285, 1(2)-0G-AIT-k324, and 1(2)-0G-AIT-k325 were inoperable for greater than a 30 day period during January 1 to June 30, 1987. Due to design problems, these monitors were not returned to serivce within
-30 days.
Units 1 and 2, Reactor and Turbine Building roof vent monitor flow elements, 1-VA-FE-3356, 1-VA-FE-3358, 2-VA-FE-3356, and 2-VA-FE-3358 were inoperable for greater than a 30 day period during January 1 to June 30, 1987. Due to de-sign problems, these monitors were not returned to. service within 30 days. 5/3
l' ,' l l l f ENCLOSRUE 3 i l l Liquid Hold-up Tank l l 1 No liquid hold-up tank exceeded the 10 C1 limit between the dates of January 1 to June 30, 1987. 4 i l 1 l 1 I i I l l l 1 5/h
*'c c
1
- r. i ATTACBGMT 6 Major Modifications to the Radioactive" Waste Treatment Systems January 1 to June 30, 1987 l
Discussion of. major modifications to Radioactive Waste Treatment Systems, if any, vill be submitted with the Final Safety. Analysis Report update ) as allowed by footnote 7 to Technical Specification 6.15 i 1
)
)
l i I J l l I i l I l l i 6/1 l L_-___._._.._-____--_-. _ i
e ,- ; 1 ATTACIDENT T 4 Meteorological Data i Brunswick Steam Electric Plant i January 1 to June 30, 1987 l As required by Technical Specification 6.91.10.a footnote 6, the annual simenry
. . i of meteorological data collected over the calendar year will be submitted to a i file within 90' days of January 1, 1988, and will be available for NRC review upon request.-
1 l 1 l l l
)
l I i i f i 7/1 l l t
= .,. - n -)
=. ' W. "..
4
;, .. ; ?
- f ATTACHMENT 8 Potential Dose Assessment January 1 to June 30, 1987
.As required by. Technical. Specification 6.9.1.10.b, an assessment of radiation doses due to the radioactive liquid and gaseous effluents released durin -the
' calendar year will be reported within 90 days after January 1 of each year,'and is not included in this report.
i l l I l l
.)
1 l f i 8/1 l U-.__-----
.j CD&L - ,
' Carolina Power & Light Company
- a. 1 Brunswick' Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 hMg m ;j October 23, 1987- $7 j
> to . t
. u)
FILE: .B09-135100 10CFR50.g(2)- SERIAL: BSEP/87-1173. I U.S.. Nuclear ~ Regulatory Commission ATI'N : : Document Control Desk Washington, DC 20555 1 BRUNSWICK' STEAM CLECTRIC PLANT UNITS 1 AND 2 l DOCKET NOS. 50-325 AND 50-324 :l LICENSE NOS. DPR-71 AND DPR-62 RESUBMITTAL OF SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Gent 1emen: Per the request of the Brunswick Project Manager at.NRR, enclosed is a resubmittal of the Semiannual Radioactive Effluent Release Report for
- i. : Brunswick Steam Electric Plant covering the period from January 1, 1987,
.through June 30, 1987. Due to an administrative error in addressing the ,
original submittal report cover letter, the NRC Document Control Desk was not ' provided with the original copy of th9 report. In addition, portions of the
. original submittal of this report were determined by NRR to be illegible.
'This report is submitted in accordance with Technical Specification 6.9.1.8 i
- for Brunswick Steam Electric Plant. 1 I
Very truly urs, l 1 5 ! . . le , General Manager Brunswick Steam Electric Plant L MJP/ah.
~
b . Enclosure , l cc: Dr. J. N. Grace- l 1 Mr. E. D. Sylvester BSEP NRC Resident Office V h/ ;\ __ = _ _ _ _ . -___}}