ML20043D929

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Informs That BNL Summary Data Re Radioactive Effluents for Third & Fourth Quarters 1988 Reviewed,Per 900405 Request. No Changes Necessary.All Vols Reported Were After Compaction
ML20043D929
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/01/1990
From: Loflin L
CAROLINA POWER & LIGHT CO.
To: Tichler J
BROOKHAVEN NATIONAL LABORATORY
References
NLS-90-109, NUDOCS 9006110287
Download: ML20043D929 (2)
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Carol 6na Power & Light Company NLS-90-109 JUN 1 1990 Ms. Joyce L. Tichler Oceanographic & Atmospheric Sciences Div.

Brookhaven National Laboratory Upton, NY 11973

Dear Ms. Tichler:

As requested by your letter dated April 5, 1990, CP&L has reviewed Brookhaven National Laboratory's (BNL) summary data regarding radioactive effluents released by the Brunswick Steam Electric Plant (BSEP) for the third and fourth quarters of 1988 and hereby informs BNL that no changes are necessary. A hand-written note on the summary data indicated that BNL did not receive a copy of the BSEP Semiannual Radioactive Effluent Release Report for January through June 1988 from the Nuclear Regulatory Commission. Therefore, a copy of that report is l provided as Attachment 1 of this letter. I Also, your letter requested that CP&L indicate whether volumes I reported were before or after compaction when solid waste was shipped to a licensed wastt processor for volume reduction.  !

Please note that all volumes reported were after compaction.

CP&L understands that this summary data is to be used for inclusion in the BNL report of radioactive effluents released from commercial nuclear power plants during 1988 which is being j prepared under contract with the Nuclear Regulatory Ccamission.

CP&L also understands that an annual report based on the attached information will be sent to us for review prior to the finalization of the BNL report.

If you have any questions regarding-this information, please call Mr. M. Ron Oates at (919) 546-6063.

Yours very truly, f

A '

L. I. Lof in Manage Nuclear Licen ing Section i

DJK/dk Attachment

  • cc: Mr. S. D. Ebneter Mr. N. B. Le Mr. W. H. Ruland

, t NRC f Document; controls Deskt-w ,+

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9006110287 900601 .

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4 ATTACitMENT 1

Fo^M 22 Q 0 Carolina Power a Light Company i

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Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 e <

August 26, 1988 )

FILE: B09 135100 l SERIAL: BSEP/88-0809 U.S. Nuclear Regulatory Commission-ATTN: Document Control Desk l Washington, DC 20555 {

BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NO. 50-325 AND 50 324 )

LICENSE NO. DPR-71 AND DPR-72 )

SEMIANNUAL RADIOACTIVE EFTLUENT RELEASE REPORT Gentlemen:

Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick ,

Steam Electric Plant covering the period from January 1, 1988, through '

June 30, 1988. -

i This report is submitted in accordance with Technical Specification 6.9.1.8 for Brunswick Steam Electric Plant.-  :

, Very truly yours,  !

NN k

. /YdMw J L. Harness, General Manager Brunswick Steam Electri:-Plant MJP/sh Enclosure cct Mr. B. C. Buckl y Dr. J. N. Grace '

BSEP NRC Resident Office bcci Mr. R. M. Coats Mr. L. E. Jones Mr.-R. B. Starkey Jr.

Mr, A. B. Cutter Mr. M. A. Jones Mr. L. V. Wagoner Mr. W. P. Guarino Mr. L. 1. Loflin Mr. D. C. Whitehead i Mr. J. G. Hammond Mr. R. E. Morgan INPO '

Mr. J. L. Harness Mr. C. H. Moseley On Site Licensing

,Mr. L. P. Hewlett Mr. J. W. Moyer Files BC/A-4 Mr. M. D. Hill Mr. W. R. Murray SHEEC Training Mr. P. W. Howe Mr. B. L. Parks Jr. Reference Library i

)'"~**~ .u,,,,, ._

  • -a

.. . . I Brunswick GtoOa. Electric Plant  ;

Semiannual Radioactive Effluent Report  !

I January 1, 1988 to June 30, 1988 i ATTACHMENTS: -

. PAGES: }

l

1. Supplemental Information 1/1 to 1/4 l
2. Effluent and Waste Disposal Data 2/1 to 2/14 i 1

1

3. 09CH and PCP Revisions 3/1 [

4 Enviromental Monitorins Program '

4/1 to 4/3

5. Inoperable Effluent Instrumentation 5/1 to 5/4 I l
6. Major Modification to Radioactive Waste 6/1  !

Treatment Systems

7. Meteorological Data 7/1 ,

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8. Potential Dose Assessment 8/1-

. 9. Supplement to Previous Semiannual 9/1 to 9/3  !

Report  !

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i ATTACHMENT 1  ;

Supplemental Int'ormation  ;

January 1 to June 30, 1988 >

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1 EFFLUENT WASTL DISPOSAL SEMIANNUAL REPORT  !

Supplemental Information '

Facility: Brunswick Steam Electric Plant  ;

Licensee: Carolina Power and Light Company _  !

t

1. Regulatory Limits-  !

A. Fission and activation gases (Technical Spec. 3.11.2.2)

{

  • (1) Calendar Quarter  !

l (a) 10 mrad samma l (b) 20 arad beta i (2) Calendar Year -

(a) 20 mrad gamma  !

(b) 40 arad beta  !

B. Iodine-131, iodine-133, tritium, and particulates With half-lives greater than eight days (Technical Spec. 3.11.2.3)  !

  • (1) Calendar Quarter i

(a) 15 mram to any organ i

(2) Calendar Year ,

l (a) 30 mrem to any organ _  ;

i C. Liquid effluents (Technical Specification 3.11.1.2) 't

    • (1) Ca'lencar Quarter (a) '3 mram to total body ,

(b) 10 mrem to any organ l {

(2) Calendar Year  !

(a) 6 mrem to total body (b) 20 mrem to any organ lt NOTE: Dose calculations are determinec in accordance with the j off-Site Dose Calculation Manual (CDCM)  ;

  • Used for percent of technical specification limit determinations i in Table 1A.  ;
    • Used for percent of technical specification limit determinations i in Table 2A. ,

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4 .  :

2. Maximum permissible concentrations and dose-rates which determine i maximum instantaneous release rates.

l A. Fission and activation gases-(Technical Specification  !

3.11.2.1.a) l (1) 500 mrea/ year to total body , l (2) 3000 mrom/ year to the skin

}

B. Iodine-131, iodine-133, tritium, and particulates with half- I lives greater than eight days (Technical. Specification 3.11.2.1.b) , ,

L (1) 1500 mrea/ year to any organ C. Liquid effluents '(Technical Specification 3.11.1.1) f 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 5 Table II. column 2 for radionuclides other than noble gases. ,

    • (1) Tritium: MPC = 3 E-03 uC1/mi and [
    • (2) Dissolved and entrained gases: MPC = 2 E-04 uC1/ml  ;
3. Measurements and Approximations of Total Radioactivity l

A. Fission and activation gases i i

Analysis for specific radionuclides in representative grab i samples by gamma spectroscopy. - - .-

B. Iodines Analysis for specific radionuclices collected on charcoal  !

cartridges by samma spectroscopy, i C. Particulates l

) Analysis for specific radionuclides co.lected on filter papers l l by gamma spectroscopy.

j D. Liquids Effluents  ;

Analysis for specific radionuclides or incividual releases [

Oy gamma spectrosecpy. *

    • Used as applicaole limits for Table 2A we. . . < , . .. $- _ _ - . , - _ ,. - - _ m _ . _ . - - _ _ - - -__ -__m_ _ . . _ _ _ _ _-- . . . _ . - - - _ _ _ < . . _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _

4 Nuclear. counting statistics are reported utilizing 11-sigma' error.

Total- error- where freported represents a best- effort' to ,

approximate.the total of al1~ individual-'and sampling errors.

4. Batch Releases A. Liquid ,

(1) Number:of batch releases: 3.06E 02  !

(2) Total, tine' period for batch releases:= 3.31E.04 [

Minutes .

.(3)~ Maximum time period for,a' batch releases- 2.45E 02'  !

Minutes' .

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-(4)iAverage time period for-a batch releases. 1.0SE 02- 'f Minutes- 1 (5)' Minimum-time period 5for a batch release: 6.00E'00-  !

Minutes' ,

(6) _ Average? stream flow during periods- '?

of release of effluent-into a flowing- 9 stream 6.49E-05 i GPM .

I B. Gaseous-(1) Number..of' batch releases: 0.00E-00 A l  ! ?,. . Minutes (2) Total-time' period for a batch release: 0.00E 00 "r Minutes i

(3) Maximum time neriod1for a batch releasei 0.00E'00' 1 Minutes

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(4) Average time period for a batch release 0.00E 00 Minutes. q (S) Minimum time period for a batch release 0.00E 00' Minutes. ,

S. Abnormal releases

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A. Liquid 1 J

p-L (1) Number of releases: 0.00E 00 ..

. . l (2) Total activity released: 0.00E 00 Curies l l-B. Gaseous .

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(1) Number of releases: 0.00E CO 1 L

(2) Total activity releared: 0.00E 00 i

! Curies

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-. l ATTACHMENT 2

{

Effluent, and Waste _ Disposal Data ,

j Brunswick Steam-Electric: Plant-January 1,'1988 to[ June-30, 1988-Enclosure i . . .

l Table'1Ai Gaseous Effluents'- Summation of all Releases 1

Table 18: caseous Effluents = Elevated Releases l' Table ICs- Gaseous Effluents -10round Level Releases

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Table 2At - Liquid Effluents'- Summation-of.all Releases g

Table:28: Liquid Effluents.

Lower Limits of Detection Solid Waste and Irradiated Fuel Shipments Ta ble ' ~3 :

Enclosure 2 Combustion of Waste Oil i

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'Taolel1A

"* . EffAbent anc'Wooto Disponni:Semlannual R vort. Year 1988~

Gaseous Effluontsf- Summation of:all Roloasos:

. i Est, j Total QDL.t. Q.st, L Qtr.1 Error.%

A.; Fission gng' Activation ,  !

QAAAB.

1. Total release. C1 2.01El02 2.26E 02 1.15E.02-
2. Average' release uCi/sec-'2~56E 01 . 2.87E'011 '

rate- f or-- period .

3. Percent of-technical s}

specification. limit  % -4.68E-02 5.58E 62 B. Iodines -

1.-Total I-131' C1. 1.90E-03 -1,67E-03) .7,00E 01' '

2.-Average release uC1/sec 2.'42E-04'- 2.12E '

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rate for period . i C. P,,,grt icu l a tes ,

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1. Total release C1 1.08E-02 6.95E-02 7.00E 01-
2. Average release uC1/sec'1.37E-03 8.84E rate for period- '

.3. Gross alpna

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Ci- S.27E-06--4.80E-06 D. Tritium

1. Tctal release C1 1.04E 00 1.24E 00' '7.00E 01 l
2. . AveraRe reler,.se .uC1/Sec 1. :;2E-ul l'.57E-U1 1 rate for perloo O E. Iocine_-13la. 1.9c.tD3 .1_3.?a Tritiupt  !

iLQs. P_4J3 A su 143 g ,

n 1, Total tielease 1 ~1.0eE v0 1.J2E 00

2. Average release uCi/Fa0 1.34E-01 1.edE-01 rate tor period
3. Percent of tecnnical specification limit f. ' 7'. 2 7 E-02 6.93E-02 2/2

,..g ~,;..

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raelo 18

=Efflucnt anc Wooto'DisposalcSemiannual~Roport -

~ Year 1989 Gaseous Efiluents'--: Elevated Releases Continuous'. Release.

Nuclides Released Mn13, 0_tr 1. Q11.1

1. Fission Gases ,.

argon-41 C1: 4.72E-01 8.64E-01 Xrypton-85m Ci- 5.45E 00 1.52E 01 krypton Ci~ < LLD 2.34E-01 krypton-88: aci '2. 21 E . 00 - 1.20E 01 xenon-133 HCi 3.22E-01 8.79E:01-xenon-135m- Ci < LLD '1.73E 00 xenon-135 -

Ci 7.84E-01 1.80E 00 xenon-137- Ci" <.LLD -5.20E 00

- o) xenon-138 QL i (LQ -4.32E-01 total for period :C1 4.11E 01 1.25E:02 l

2. Iodines iodine *131 -

C1 1.46E-03 5.98E iodine-132 C1 ( LLD 2.37E  !

iodine-133, ' C1- 3.39E-03 3.55E )

iodine-134 C1 <1LLD- 2.16E-04: 1 iodino-135- Q1- . 1 (kQ~ 4.02E-03 1:

total for period Ci 4.85E-03 1.08E-02

3. 23rticulates .

p chromium-Si C1. 1.88E-04 1.42E  !

manganese-54 C1 12.90E 4.51E-05 l

-cobalt-58 LCi 7.63E-05 1~.59E-06 cobalt-60 .C1 2.48E-04 4.21E-05 q strontium-89 C1 1.80E-OS L.83E-04  ;

strontium-90 C1 3'.95E-07 8'.93E-07 cesium-137 C1 1.09E-05 7.47E-06' il barium-140 '

Ci < LLD' 1.63E-04 '

lanthanum-140 gi 1, k(p j. dth total for period Ci 'W.32E-04 5. bee-04 4 Tritium hycrogen-3 C1 5.80E-02 4.88E-01 j

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% "'hWS 4 $ M

Table-1C-Effluent 1and Waste Disposal 1 Semiannual'Re,0crt:

Year:1988 Gaseous Effluents - Ground Level. Releases Continuous Release' Nuclides Released ,

g--

  • g_q 1. gg C
1. Fission-Gases xenon-133- C1 1431E 01- 3.78E-00?

xenon-135 QL 1.47E~Q1

-total for period-9.-70E"QL (Ci 1.60E'02' 1'01E 02-

2. Iodines iodine-131. C1 -4.42E-04 l'.'07E-03 iodine-132' 'Ci 'r-LLD 1.15E-02.-

iodine-133 Ci- =5.24E-04 8.81E-03?

iodine-134 Cil (aLLD. 12'.06E -

iodine-135- . Qi, 1.LkQL 1,27E-02' total for period- 10 1 9. 66E-04 -; ; 5. 47E-02;

3. Particulates '

chromium-51 Ci 4.18E-03' 6.35E-02 ..

manganese-54 C1- 2.06E-03: L1.57E-03 cobalt-58 C1" -3.60E-04 ?1.25E-03 cobalt-60 Ci *

'2.16E-03 1.49E-03:

iron-59  : Ci: 1.02E-03 ~ 1.05E-04 strontium-89 aCin -3.86E 9'08E-05 strontium-90 Ci *

<lLLD -1.27E-06 niobium-95 .Ci- 1.03E-05: < LLD-cesium-134. LC11 <nLLD: 6:53E-06 cesium-136 C1. L< -L L D - 1.89E-08 cesium-137 Cii -4.81E-05 .2.47E barium-140 Ci" 4.21E-05: 4.09E-04 lanthanum-140 Ci :4T30E-05* 2.46E-04 cerium-144 9.1, $,. Q.6f-91 . _ (LQ <

total for period 'C1 9.95E 6.89E 4 Tritium hydrogen-3 C1 9.8SE-01. 7.47E-01 2/4 3

LTablo 2A-

Effluent and, Waste Disposal!SemiannualiReport Year 1988 Liquid' Effluents.'-: Summation of all Releases a

.9_qt 2 E31 I.e q

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Qt111 l Q,1;r.,1 F

2 Error A.' Fission t[11, Activation E.t2 ducts ,  ;

1. Total:relea'seI(excluding ,Ci- 1. 80 E- O'1 3.48E-01 3.50E 01 .

tritium, gases.-& alpha)- 4 3

.2'. Avg. diluted. cone.- uC1/ml- 6.55E 7.79E-09  ;

3. Percent limit- 7. 5.52E-01 ~ 8.46E-01 .

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B. Tritium

s 1.' Total. release' .C1 - 16.59E 00 4.'62E600 4'.00E 00i or

2. Avg. diluted conc, uC1/ml- 2.4CE-07 '1.03E q
3. Percent limit ,

4 8.00E-03 3.43E-03 ,

C. Dissolved gag (ptrained_ Oases .

.. T

1. Total release- ~C1 2.08E-03' -1.57E 02)L3.50E Olf  !
2. Avs. c11utec conc. - uC1/ml 7.-56E-11 3.'51E -f
3. Percent 11mit'  % 3.78E-05. 1.76E-04'

[

D. Gross AJ.pha radioactivity  ;

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1. Total release 0.00E 00 0.00ELOO ' 4'. 0 0 E c 01- I l E . y_.9.b(1D_t 91 WAJ_LA liters 1.21E 07 L1.06E-O'7 1'.25EcO1 F. . T o t a l c_ f, g J.J_u t i o n W A.q q t

( ustpq q.qr_i_Ilg tpleaseg '

[9,I_ ay_tr.AKg (LL. g.q!L.,L liters 2. 75E 10 4.47E 10 .1.30E 01 G. Vo lu mt 9_(, c oo li ng w__a_qrtt liters 2.05E 11 4.31E-11 dis c ha raq.4 [tgp1 pla nt. -

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TABLE 28 Effluent and Waste Disposal Semlannual Report Year 1968 Liquid Effluents - Baten Mode Nuclides Released M OtI, 1 QE 7 e

1. Fission A.D4 activation products sodium-24 C1 1.19E-03 6.13E-03 chromium-51 C1 8.76E-03 3.47E-02 manganese-54 C1 4.21E-02 7.93E-02 1ron-SS C1 1.87E-02 6.57E-03 cobalt-58 C1 8.21E-03 1.56E-02 1ron-59 C1 2.85E-03 7.70E-03 cobalt-60 C1 3.72E-02 1.28E-01 arsenic-76 C1 1.52E-04 4.00E-04 strontium-89 C1 1.86E-04 1.69E-03 strontium-91 C1 < LLD 9.92E-05 yttrium-91m C1 3.47E-06 9.75E-05 strontium-92 C1 3.67E-05 4.33E-05 niobium-95m C1 2.99E-06 < LLD niobium-95 C1 < LLD 2.16E-05 molybdenum-99 C1 < LLD 1.92E-04 technetium-99m C1 3.50E-05 9.05E-04 s11ver-110m Ci 6.95E-05 4.90E-05 antimony-125 C1 1.24E-04 ( LLD iodine-131 C1 7.34E-04 1.19E-03 iodine-132 Ci < LLD 8.52E-05 iodine-133 C1 1.23E-04 1.19E-03 lodine-134 C1 1.2eE-05 2.15E-05 cesium-134 -

C1 1.01E-.02- 1.02E-02 iodine-135 Ci < LLD 8.15E-04 cesium-137 C1 4.88E-02 5.33E-02 cerium-144 C1 7.99E-04 < LLD tungsten-107 91 M1,q5, L Li,2 total for period C1 1.8vE-01 3.48E-01

2. 04S95 argon-41 Ci 5.40E-06 < LLD xenon-13J C1 3.06E-04 2.97E-03 xenon-135m Ci < LLD b.05E-04 xenon- i d. sik 1.J/.7_E.-03 1.42E_02 total for perloo C1 2.08E-u3 1.S7E-02 ,

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, Lower Limits of Detection

. 1 uC1/ml

- l. Liquid Releases 4.97E-09,

  • Sr-90 j Sr-91 8.14E-08 , l=

Nb-95m 4.76E Nb-95 1.84E-08 Mc-99: 1.28E-07 Sb-125 4.61E-08 * -

I-132 E2.01E-08  !

I-135 4.29E-08 i Ce-144 -8.85E-08 W-187: W.09E-08. .-

,- .Ar-411 1.46E-08 Xe-135m! 7.87E-08

2. QAES9.MA. Releases Kr-87 '1.97E-08 - '

Xe-135m: '4'.17E-08 Xe-138 9.82E-08 1

3. Iodines Egi Particulates  !

I-132 '4.16E-13 j

.. I-13S 2.51E-13 Sr-90 :3.59E-16 l Nb 2.27E-14  ;

Cs-134 4'75E-14

. I Cs-13o 3.88E-14 .!'

Ba-140 9.34E-14 La-140' 6.48E-14 i Ce-144 1.76E-13 I l,

NvfEd 1: Tne above values represent typical 'a priori" LLDs-t'or isotopes where values ot "<LLD" are indicatea in iables LA. 16 lu. 2A, and 28.

4: .Wnere activity tor.any nuclice 1s- reportec as " Less tnan LLO". that nuclice.ls consicerec not.present anc tne LLD i activity listec is not consicerec in summary cata.

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Table 3A i

. Effluent and Waste Disposal Semiannual Report Year 1988 Solid Waste and Irradiated Fuel Shipments Waste Class A January through June

1. Total volume shipped (cubic meters) 4,13 E2 Total. Curie quantity (estimated) 1.25 E3
2. Type of Waste Units Six-month Est. Total Period Error,%
a. Spent resins, filter sludges meters 3 1.99 E2 Curies 1.23 E5 1.00E1
b. Dry active waste. compacted, meters 3 2.14 E2 noncompacted Curies 2 14 El 1.00E1
c. Irradiated components meters 3 0.00 EO Curies 0.00 EO N/A
d. Others (oil) meters 3 0.00 EO Curies 0.00 EO N/A I
3. Estimate of major radionuclide composition i
a. Cr-51 2.77 EO%

Mn-54 1,66 El%

Fe-55 4.60 El%

Co-58 1.42 EO%

Co-60 2.86 El%

Ni-63 1.12 E0%

Cs-137 2.50 EO%

b. Cr-51 1.40 E0%

Mn-54 1.11 El%

Fe-55 6.47 El%

Co-58 1.20 EO%

Co-60 1,69 El%

Nia63 .97 EO%

c. N/A N/A
d. N/A N/A S

g e="*, '

-- - -_- ------,-,,m--.--.---...--. . . .. . , , - .

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.l Tabl+ 3A~~(cont.).

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-. Effluent andLWaste Disposal Semiannual Report Year 1988 l Solid Wasteland Irradiated Fuel Shipments I 1

Cross reference table, waste stream, form, and 'coritainer: type.

~ ~

4.  :
l. Stream Eggg . Container'ly.g3 i gf,Lahioments" q
a. Rosin .Dewatered'& ' Type A/ Type BP  : 39/00= l Solidified *' I
b. Dry active-Compacted /non ' STP 27 waste compacted waste' ,
c. Irradiated N/A 'N/A components
d. Other N/A- N/A: .

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  • solidification agent or absorbent. '

(e.g..? cement, urea: formaldehyde) . CEMENT-

5. Shipment Disposition V
a. Solid Waste '

Number of Shipments Mode of Transportation Destination y 40 Sole Use CNSI/Barnwell 1

SC 2e Sole Use SEU/ Oak Ridge 2 TN  ;

p D. Irradiated Components i Number of Shipments Mode of Transportation Destination O N/A N/A L.

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Table 38 Effluent and Waste Disposal Semiannual Report Year 1988 Solid Waste and Irradiated Fuel Shipmrnes Waste Class B Januarv through June

1. Total volume shipped, (cubic meters) 0.00 EO Total Ci quantity (estimated)
2. Type of Waste Unita Six-month Est. Total Period Error,%
a. Spent resins, filter sludges meters 3 'N/A N/A Curies
b. Dry active waste, compacted, meters 3 N/A N/A and noncompacted Curies
c. Irradiated components meters 3 N/A N/A Curies
d. Others (describe) meters 3 N/A N/A Curies
3. Estimate of major radionuclide composition
a. N/A N/A
b. N/A N/A
c. N/A N/A
d. N/A N/A 4

Cross reterence table, waste stream, form and container type Stream Egra g_qa19. Gad'. 13.P.R h 21. shiomerLig,

a. Resin Dewatered & N/A N/A Soliditied
b. Dry active Compacted /non- N/A N/A compacted waste
c. Irradiated N/A components
d. Other N/A Solidification agent or absorbent (e.g.. cement, urea farmaldehyde) N/A 1

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1 Table 3B(cont;) . l Effluent:and Waste Disposal--Semiannual Report Year 1988.'

; Solid Waste and Irradiated-Fuel
Shipments-l 1

-5. Shipment Disposition. ,, l L

l if a'. Solid Waste. <

I l Number of Shipments Modei of. Transportation ~ . Destination

,s l N/A -

N/A' -

N/A: '

2

~

.k

b. Irradiated Fuel y Number.of Shipments . Mode of. Transportation- Pastination:  : i N/A N/k. 'N/A:

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Ta ble -: 3C-Effluent and Waste Disposal Semiannual-Report Year 1988

~ Solid Waste' andE lrradiated Fuel Shipments 3 Waste-Class C . January through June.

i

1. Total'voluee. shipped, (cubic meters)- 0 '00 E0 ,

l

. Total C1_ quantity (estimated)  ;

2. Type of Waste Unit- Six-month Est. Total .

Period LError,%- l l

a. Spent resins, filter sludges s meters 3 N/A: j JCuries -l
b. Dry active waste, compacted

_ meters 3 'N/A  !

and noncompacted y c.. Irradiated components meters 3- N/A' s

Curies

d. Others (describe) meters 3 N/A .

Curies -

[

3. Estimate of major radionuclide' composition
a. 'N/A O. N/A
c. N/A

.- j

d. N/A ,

l 4 Cross reference table waste stream, . form.and c'ontainerftype- I Stream F&ra Qontutte.t TREs. . N_92 gf_ shipments.

y a. Resin Dewatered & N/A N/A Solicified *

u. Dry active Compacted /non- N/A N/A waste compacted
c. Irradiated N/A N/A ,

components

d. Others N/A. N/A i
  • Solidification agent or absorbent i (e.g., cement, urea formaldehyde) N/A 2/12

..,s, , , .y -

Table ac~(cont.F l.

Effluent and-Waste Dirposal Semiannual-: Report- Year 1988-Solid Waste and, Irradiated-Fuel Shipments-

5. Shipment Disposition ,

a .t Solid Waste Number of Shipments Mode of. Transportation Destination-  :

N/A - N/A - N/A' b.-Irradiated Components -

Number of Shipments . Mode-of: Transportation Destination' O >N/A N/A:

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  • A* D=41 M + 5 wt -

. v, ENCLOSURE: 2 Combustion _of Waste 011' During the firstiquarterr 7.78E 02 gallons'of-waste oil'containing 1.39E-00 uC1 were disposediof by incineration.- During'the second quarter. 5.78E 02 gallons of waste oil'lcontaining 8.01E uci-were disposed-of.by incineration. -

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' ATTACHMENT 3- '

Off-Site Dose Calculation Manual (ODCM)'and Process Control'. Program (PCP) Revisions ,

, , t e

r January'1.1.to June.30, 1988 [

Brunswicki Steam Electric Plant y

There were no revisions made'to theEOff-site Dose Calculation?  !

Manual (ODCM) or-the Process Control Program-(PCP) during.this.

}

time period.

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. ATTACHMENT 41 Enviremental Monitoring Program-January 1..to-Junel 30,'1988 l

.I Enclosure-1: Milk and-_vesetable sample Locations j Enclosure 2: - Land Use. Census I

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. - ENCLOSURE 1 1 1

Milk.and Vegetable Sample Locations No milk' sample locations were available during this time period.

Vegetable sample locations were unchanged 'during this time -

period.

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ENCLOSURE 2 Land Use~ Census-No~new locations were identified that are reportable in the. .i

.\

' semiannual ~ Radioactive Effluent Release' Report as per Technical 'l

' Specification 3.12.2.a and b.; ,

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  • I N. ' ' * .* ** Y NT.J M

k ATTACHMENT 5 1-Inoperable Effluent Instrumentation January'1, to' June 30, 1988 i e i Enclosure-1: Radioactive Liquid Effluent Monitoring' Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring--  :

Instrumentation '

Enclosure 3:~ Liquid Hold-Up Tank-  !

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_ _ . . _ _ . . ~ __ _ .

.. -ENCLOSURE l' Radioactive Liquid Effluent Monitoring Instrumentation The liquid radwaste offluent flow measurement gevice-(2-016-FIT-N'J57 ) was inoperable for greater than 30 days during-this ~

time period._ .

This instrument was not returned to service withinea' 30' day l period due to the-inability to calibrate the. instrument within its design accuracy. ' -

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~ENCLOSukE=2 L.

Radioactive. Gaseous:EffluentfMonitoring, instrumentation =

Unit :1 & 2 Main Condenser Of f-Gas - treatment: yystem explosive gas monitors 1(2)aOG-AIT-4284z(SJAE.A.H2 Analyzer). 1(2)-OG-AIT-4285 (SJAE.A.H2 Analyzer), 1(2)-OGL AIT-4324_(SJAE.B.H2' Analyzer), and 1( 2)-OG- AIT-4325 - (SJ AE. B. H2 ' Analyzer ) were inoperable for: greater _i

- . :l Ethan a 30 day period during January 1.to June 30, 1988.

j.

.Due_to 1

design problems, these monitors'were not returned to service within? j-30 days, j

Units 1 and 2. Reactor andLTurbineibuildings roof-vent' flow monitor elements: 1-VA-FE-3356.1-VA-FE-3358 2-VA-FE-3356 and 2-VA-FE-3358-were inoperaole for s'. eater than'a 3u day period during January 1, i to June 30, 1988. Due.to design problemu these monitors were not i

.i returned to service within 30; days.

Unit l' Turbine ouilcing root vent' flow monitor totalizer.'l-VA-FIO-3358 was inoperable fer greater 1tnan a au day, period during i

-l January 1. to June J0. 19 8 8 =. 62cause it would not meet tne acceptance 4riteria of an cperhtional' test. Investigations have oeen made and cnanges are currentiv underway to return--

i 1-vA-fiQ-3356 to an operable status.

Unit 2 Main Condenser Ofi-Gas treatment svstem Argumented Off-Gas l

(AOO) monitor' 2- AuG-RI-lu3 was inoperaole t'or greater than 30 a ,

day period during January'1. to June JU. 1986. Duw to the Unit I refueling outage this monitor was not returned to service within 30 days. 4 L

S/3

. . ~ . . ,,1

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I ENCLOSURE 3':

Ciquid' Hold-Up~ Tank. '

No liquid hold-up tank exceeded the 10. ci limit. auring this- time period. l

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4 ATTACHMENT 6 1

P Major. Modifications'to the Radioactive Waste. Treatment. Systems. 1 January 1 to June 30.'1988.' '

Discussion of major modifications to the Radioactive' Waste Treatment'

.l' 1

Systems', if'any. will be' submitted with the'FinaleSafety Analysis:

Report update as allowed by. footnote. 7 to -Technical. Specification j P 6.15. ,

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ATTACHMENT 7 Meteorologic'al Data:

1 Brunswick Steam Electric-Plant- '

L January:1 to' June;30.-1988 As per Technical specification!6.9.1.10.a footnote 6. the' annual l

summary of-meteorological data collected:over.the calendar $ year.will. l l

be submitted to.a file-and will be available for NRC review upon. )

1 request. '

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-ATTACHMENT 8 f

' Potential Dose: Assessment'-

Brunswick-Steam Electric-Plant- [

January 1 to June 30' }

1988;. 8 i

As . required by Technical Specification 6.9.1.10.b. ' an assessment  !

of' radiation doses due to the radioactive;1iquid.and saseous.

effluents' released'during the' calender year.will;be reported q within 90 days after January 1 of each year; and.is not_ included {

in this report, j g

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i ATTACHMENT 9-  !

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.' SUPPLEMENT'TO PRE'VIOUS .i SEMIANNUdL REPORT ',

BrunswickE SteamiElectric P1pnt.

JanuaryL1'.<to June'30,-1988~

f i

Enclosure-1: DISCUSSION. l

.. . .t Enclosure.2: DATA TABLE '

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. ENCLOSURE 1 -

l DISCUSSION-

-f Supplement to the Effluent and ' Waste ' Disposaf; Semiannual Report l -

is as'foi-lows:

' Report Period AffactDd.EAgg, July-- December, 1987 TABLE 2A, page 2/5 Supplementation'is provided..as a replacement page with change?

bars indicating new information.. Corrections were made to that i

fourth quarter of the July to December 1967. Semiannual Report. The 9 Total-release. Average dilutec concentration.,and' Percent limit

  • corrections to lhe fourth quarter 1987 Were due'.to the tritiQm- -

.t

.'1W7 beins; .ekcluded! in' TABLE. 2A.'-

concentration- tor Decemoer -

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2 ENCLOSURE 2 l e

DATA TABLE *  :

5 I,

The corrected data table is as follows: f e

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  • w 48 #ve- ,
  • NGus $ P44 md

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' Table 2A I Effluent and Waste Disposal' Semiannual Report Year 1987 i Liquid Effluents - Summation of all Releases Unit Ctr 3 Otr 4 Est Tot

% Error A. Fission and activation products *

1. Total release (excluding Ci 2.63E-01 2.15E-01 3.50E 01 tritium, gases, & alpha)
2. Avg. diluted conc. uC1/ml 4.21E-09 3.69E-09
3. Parcent limit  % 2.34E-01 1.39E-01 B. Tritium
1. Total release C1 2.77E 00 9.22E 00 4.00E 00 l
2. Avg. diluted conc. uCi/r 4.44E-08 1.58E-07 l
3. Percent limit  % 1.48E-03 5.28E-03 l C. Dissolved and Entrained gases .
1. Total release Ci 3.30E-02 5.53E-02 3.50E 01 I
2. Avg. diluted cone, uC1/ml 5.29E-10 9.50E-10
3. Percent limit  ?. 2.64E-04 4.75E-04 1

D< Oross alpha radioactivit'y l

1. Total release 9.41E-04 1.15E-04 4.00E 01 E. Volume of waste liters 1.02E 07 1.18E 07 1.25E 01 F. Total of dil. water liters- 6.24E 10- 5.82E 10 1.30E 01 Ausec curing released '

for avcTage dil, coac.)

G. Volume of cooling Water liters SiO9E 11 4.4?E 11 discharged frem plant AMENDMENT 1 )

AUGUST 1988 2/5 d

,

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