View source for BSEP-96-0258, Semi-Annual Radioactive Effluent Release Rept 960101-0630

{{Adams
| number = ML20117G774
| issue date = 08/28/1996
| title = Semi-Annual Radioactive Effluent Release Rept 960101-0630
| author name = Levis W
| author affiliation = CAROLINA POWER &amp; LIGHT CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000324, 05000325
| license number = 
| contact person = 
| document report number = BSEP-96-0258, BSEP-96-258, NUDOCS 9609050321
| document type = ENVIRONMENTAL MONITORING REPORTS(&amp;RADIOLOGICAL)-PERIODIC, TEXT-ENVIRONMENTAL REPORTS
| page count = 35
}}

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                                   .                                                                        i 1
CP&L
        -                                                                                                  I f
Carolina Power & Light Company P.O. Box 10429 Southport, NC 28461                                                                               l 6
SERIAL: BSEP 96-0258 AUG S81995                                                                                        j United States Nuclear Regulatory Comminion                                                        ;
ATTENTION: Document Control Desk                                                                  '
Washington, DC 20555 i
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2                                                  f DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT                                                   ,
1 Gentlemen:                                                                                       .;
5 Enclosed is the Semi-Annual Radioactive Effluent Release Report for the Brunswick Steam           l Electric Plant, Units 1 and 2 covering the period from January 1,1996 through June 30,            [
1996.                                                                                             ;
3
;        This report is submitted for the Brunswick Steam Electric Plant in accordance with Technical      i
.        Specification 6.9.1.8.                                                                            l
 !       Please refer any questions regarding this letter to Mr. Ralph Schlichter at (910) 457-2235.
f i                                                                                                          i Sincerely,                                     a i                                                               .
l                                                            W. Levis - Director Site Operations            j i                                                            Brunswick Steam Electric Plant                 .
WGR/gmt

==Enclosure:==

f
: 1. Report                                                                                i
: 2. List of Regulatory Commitments                                                        !
cc:      Mr. S. D. Ebneter, NRC Regional Administrator, Region 11 Mr. C. A. Patterson, NRC Senior Resident Inspector - Brunswick Plant Mr. D. C. Trimble, Jr., NRR Project Manager - Brunswick Plant The Honorable H. Wells, Chairman - North Carolina Utilities Commission 9609050321 960828
[0h    ;
PDR      ADOCK 05000324 R                        PDR

P 1
l ENCLOSURE 1 BRUNSWlCK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62
                                                                             ]
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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1
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32 Pages Enclosed l
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i Brunswick Nuclear Plant Semiannual Radioactivo Effluent Report January 1, to June 30, 1996 ATTACHMENTS:                                             PAGES:
: 1. Supplemental Information                           2-6
: 2. Effluent and Waste Disposal Data-                 7 - 21
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: 3. Environmental Monitoring Program                  22 - 24 1              4. Effluent Instrumentation                           25 - 28
: 5. Major Modification to Radioactive Waste           29 Treatment Systems
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4               6. Meteorological Data                               30
: 7. Annual Dose Assessment                             31
{               8. ODCM and PCP Revisions                            32

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i ATTACHMENT 1 J
l            Supplemental Information January 1, to June 30, 1996 i
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   ..   ._ _ _ _ _ _. _...__ _ _ . . _ . , - . . _ . _ . ~ _ . . - . _ . . _ _ - _ _ _ . . _ _ _.__                                     - _ . . _ _ _ _ _ . _ _ _ _ _ _
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l                                                                               EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT                                                 ;
;                                                                                                   Supplemental Information f
l                                 Facility:                                 Brunswick Nuclear Plant                                                                       !
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Licensee:                                 Carolina Power and Light Company i
: 1. Regulatory Limits
,                                                A. Fission and activation                                    gases (Technical Spec. 3.11.2.2)                            ;
{                                                    *(1) Calendar Quarter
;                                                                         (a) 10 mrad gamma (b) 20 mrad beta j                                                         (2) Calendar Year i
3-                                                                        (a) 20 mrad gamma
{                                                                         (b) 40 mrad beta 1
l                                            B. Iodine-131, iodine-133, tritium, and particulates.with half j                                                        lives greater than eight days (Technical Spec. 3.11.2.3) l'                                                   *(1) Calendar Quarter
!                                                                         (a) 15 mrem to any organ i
l                                                         (2) Calendar Year I                                                                         (a) 30 mrem to any organ 1
                                                     * (3) Calendar Quarter for Burning Contaminated Oil l
}                                                                         La) 436 uCi
}
(4) Calendar Year for Burning Contaminated Oil (a) 872 uCi C. Liquid effluents (Technical Specification 3.11.1.2)
                                                 * * (1) Calendar Quarter (a)               3 mrem to total body (b) 10 mrem to any organ (2) Calendar Year (a)                6 mrem to total. body (b) 20 mrem to any organ NOTE:                       Dose calculations are determined in accordance 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.                                                       !
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l     '2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and activation gases (Technical Specification 3.11.2.1.a)
(1)   500 mrem / year to total body i
(2) 3000 mrem / year to the skin
                                                                                           ]
B. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification l              3.11.2.1.b) l             (1) 1500 mrem / year to any organ C. Liquid effluents (Technical Specification 3.11.1.1)                           l The concentration of radioactive material released in                        1 liquid effluents to unrestricted areas after dilution in                    i the discharge canal shall be limited to the concentrations                  !
specified in 10CFR20, Appendix B, for radionuclides other than noble gases.
              * * (1) Tritium: limit = 1 E-03 uCi/ml and
              * * (2) Dissolved and entrained gases: limit = 2 E-04 uCi/ml
: 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases                                                 i 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. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.
i D. Particulates for Burning Oil Analysis for specific radionuclides by grab samples         f each batch of oil to be burned.
E._ Liquids Effluents l              Analysis for specific radionuclides of individual releases by gamma spectroscopy.
!      *
* Used as applicable limits for Table 2A.
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Nuclear counting statistics are reported utilizing 1-sigma error.
Total error where reported represents a best effort to approximate the total of all individual and sampling errors.
: 4. Batch Releases A. Liquid (1) Number of batch releases:                     1.41E+02 (2) Total time period for batch releases:         1.78E+04 Minutes (3) Maximum time period for a batch release:      2.11E+02 Minutes (4) Average time period for a batch release:       1.26E+02 Minutes (5) Minimum time period for a batch release:       1.00E+00 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream :                                     5.14E+05 GPM B. Gaseous
(                (1) Number of batch releases:                     0.00E 00 Minutes (2); Total time period for a batch release:        0.00E 00 Minutes s     '
               ;.(3) Maximum; time period'for a batch release:     0.00E 00 q-_               Minutes me:periodJforTa batch release:     0.00E 00 Minutes Da batch. release:   0.00E 00 Minutes 0.00E+00 4
0.00E+00 1        -. Curies:
f0.00E+00'~
005+00
                                                                             'see t
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Nuclear counting statistics are reported utilizing 1-sigma error.
Total error where reported represents a best effort to approximate the total of all individual and sampling errors.                   1
: 4. Batch Releases                                                              ]
A. Liquid (1) Number of-batch releases:                         1.41E+02         ;
(2) Total time period-for batch releases:             1.78E+04 l                                                                       Minutes (3) Maximum time period for a batch release:          2.11E+02 Minutes         {
(4) Average time period for a batch release:          1.26E+02 Minutes         i 1
                                                                                        \
(5) Minimum time period for a batch release:          1.00E+00         1 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream :                                          5.14E+05         1 GPM              l B. Gaseous                                                                  ;
(1) Number of batch releases:                         0.00E 00         !
Minutes (2) Total time period for a batch release:            0.00E 00 Minutes (3) Maximum time period for a batch release:          0.00E 00 Minutes (4) Average time period for a batch release:          0.00E 00 Minutes (5) Minimum time period for a batch release:          0.00E 00 Minutes
: 5. Abnormal releases
* A. Liquid (1) Number of releases:                               0.00E+00 (2) Total activity released:                          0.00E+00 Curies B. Gaseous (1) Number of releases:                               0.00E+00 (2) Total activity released:                          0.00E+00 Curies
* There were no abnonnal releases that exceeded 10CFR20 or 10CFR50 limits. See page 6 for a discussion of release events that occurred.
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i Discussion of Tritium in the Storm Drain Collection Pond
*                                                                                                (
a
                    'Approximately 1.79E+07 gallons-containing 1.50E+01 curies                   '
of tritium were released from.the Storm Drain Collection'                   ;
j                    Pond (SDCP) . to the Intake Canal during this reporting                     l
}                    period. The SDCP is a permitted release point.                          ;
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<                                                                                                 l t        ' NOTE 1:       Curie totals are included in the quarterly summaries in Table 2A and
.                        2B.
/                                                                                       .
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,           NOTE 2:     The quantity of rainwater released from the Storm Drain Collection Basin and/or the Storm Drain Collection Pond is not included in VOLUME   ,
OF WASTE on Table 2A.                                                    l l
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I ATTACHMENT 2 l
Effluent and Waste Disposal Data                 l Brunswick Nuclear Plant                     ;
I January 1, to June 30, 1996 l
Table 1A:   Gaseous Effluents - Summation of all Releases       i 1
Table 1B:   Gaseous Effluents - Elevated Releases e
Table 1C:   Gaseous Effluents - Ground Level Releases Table 1D:   Gaseous Effluents - Ground Level Releases for      !
Burning Contaminated Oil.                          ,
i Table 2A:   Liquid-Effluents - Summation of all Releases Table 2B:   Liquid Effluents - Batch Mode Lower Limits of Detection
!       Table 3A:   Solid Waste and~ Irradiated Fuel Shipments - Waste j                   Class A Table 3B:   Solid Waste and Irradiated Fuel Shipments - Waste
,                   Class B f       Tab 2.e'3C: Solid Waste and Irradiated Fuel Shipments - Waste 4
Class C Combustion of Waste Oil
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TABLE 1A Effluent and Waste Disposal Semiannual Report for Year 1996 Gaseous Effluents - Summation of all Releases                                        '
Est. Tot.
Unit             Otr 1    Otr 2        Error %
A. FISSION AND AC"'IVATION                                                                           ;
GASES                                                                                             '
: 1. Total release                                Ci          4.03E+02  7.40E+01   4.50E+01   i
: 2. Average release                           uCi/sec           5.13R+01   9.41E+00.             i rate for period                                                                          f
: 3. Percent of technical                                                                     '
specification limit                            %        4.54E-02   1.61E-02 B. IODINES
: 1. Total I-131                                   Ci        1.30E-02   1.71E-03   3.50E+01
: 2. Average release                         uCi/sec 1.65E-03           2.17E-04 rate for period C. PARTICULATES NOTE 1
: 1. Total release                                 Ci          3.98E-03  8.72E-04 3.50E+01     ,
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: 2. Average release                         nCi/sec           5.06E-04  1.11E-04             1 rate for period
: 3. Gross alpha                                 Ci            9.48E-06  4.16E-07             :
D. TRITIUM                                                                                            I
: 1. Total release                               Ci            6.81E+00  4.60E+00 3.00E+01     l l
: 2. Average release                         uCi/sec           8.66E-01  5.85E-01 l
rate for period l         E. IODINE-131. IODINE-133. TRITIUM AND PARTICULATES                                     NOTE 1
: 1. Total Release                                Ci           6.84E+00 4.62E+00               l I
l                  2. Average release                       uCi/sec             8.70E-01  5.87E-01 rate for period
: 3. Percent of technical specification limit                          %          5.09E-01  5.89E-02 F. PARTICULATES VIA BURNING CONTAMINATED OIL
: 1. Total Release                                Ci           7.07E-05  0.00E+00
: 2. Average release rate for period                    uCi/sec             8.99E-06  0.00E+00 i                 3. Percent of technical specification limit                       %            1.62E+01  0.00E+00
(
NOTE 1: This includes the number of curies released via incineration.
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TABLE 1B Effluent and Waste Disposal Semiannual Report for Year 1996 j
Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released                   Unit     Otr 1     Otr 2
: 1. FISSION GASES                                                 l argon-41                             Ci       3.26E-01 < LLD krypton-85m                          Ci       3.10E+01 3.13E+00 krypton-87                           Ci      2.28E+01  < LLD krypton-88                           Ci       3.47E+01 1.92E+00 xenon-133m                           Ci       9.36E-02 < LLD xenon-133                            Ci       1.74E+02 4.76E+00 xenon-135m                           Ci       1.36E+01 2.65E+01 xenon-135                            Ci       5.44E+01 7.60E+00 xenon-137                            Ci       2.77E+01 3.71E+00 xenon-138                            C1       2.21E+01 2.42E+01  (
total for period                     Ci       3.81E+02 7.18E+01 i
: 2. IODINES                                                       l Ci iodine-131                                    1.71E-03 1.66E-03 iodine-132                           Ci       1.88E-02 7.70E-03 iodine-133                           Ci       1.04E-02 8.75E-03 iodine-134                           Ci       < LLD    2.38E-03 iodine-135                           Ci       1.60E-02 1.34E-02 total for period                     Ci      4.69E-02  3.38E-02
: 3. PARTICULATES manganese-54                         Ci       1.31E-05 < LLD cobalt-58                            Ci       1.20E-05 < LLD cobalt-60                            Ci       1.43E-04 < LLD strontium-89                         Ci       5.79E-05 1.65E-04 strontium-90                         Ci       3.94E-07 5.67E-07 cesium-137                           Ci       3.71E-06 < LLD barium-140                           Ci       4.87E-05 1.82E-04 lanthanum-140                        Ci       7.52E-05 3.56E-04 total for period                     Ci       3.54E-04 7.04E-04
: 4. TRITIUM hydrogen-3                           Ci       1.22E+00 1.71E+00 Page 9

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I TABLE 1C Effluent and Waste Disposal Semiannual Report for Year 1996 Caseous Effluents - Ground Level Releases Continuous Release Nuclides Released                           Unit        Otr 1-                 Otr 2
: 1. FISSION GASES krypton-85m                                 Ci          3.15E-01               < LLD xenon-133                                   Ci          1.38E+01               < LLD xenon-135                                   Ci          7.61E+00               2.22E+00 total for period                            Ci          2.17E+01               2.22E+00
: 2. IODINES iodine-131                                  Ci          1.12E-02               5.69E-05 iodine-132                                  Ci          6.34E-03               < LLD iodine-133                                  Ci          3.96E-03               3.14E-04 iodine-135                                  Ci          4.08E-03               < LLD total for period                            Ci          2.56E-02               3.71E-04
: 3. PARTICU'.ATES   NOTE 1 chromium-51                                 Ci          2.63E-04               7.62E-06 manganese-54                                Ci          2.97E-04               3.66E-06 cobalt-58                                   Ci          1.69E-04               4.34E-06 iron-59                                     Ci          8.41E-05               < LLD     .
cobalt-60                                   Ci          2.00E-03                1.24E-04 I strontium-89                                Ci          3.98E-05                1.18E-06 l strontium-90                                Ci          2.15E-06               3.37E-07 niobium-95                                  Ci          3.60E-05               < LLD zirconium-95                                Ci          2.00E-05               < LLD ruthenium-103                               Ci          1.23E-05                < LLD    l cesium-134                                  Ci          2.05E-04                1.03E-05 cesium-137                                  Ci          1.80E-04                1.65E-05 barium-140                                  Ci          1.06E-04                < LLD lanthanum-140                               Ci          1.80E-04                < LLD    I cerium-141                                  Ci          5.30E-06                < LLD cerium-144                                  Ci          2.93E-05                < LLD hafnium-181                                 Ci          4.03E-08                < LLD    i americium-241                               gi          4.61E-06                < LLD    !
total for period                            Ci          3.63E-03                1.68E-04
: 4. TRITIUM hydrogen-3                                  Ci          5.60E+00                2.90E+00 NOTE 1: This includes the number of curies released via incineration.
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e TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1996 Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Reler. sed                  Enit      Otr 1    Otr 2
: 1. PARTICULATES manganese-54                           Ci      6.12E-07 0.00E+00 cobalt-60                              Ci      6.21E-05 0.00E+00 cesium-137                             Ci      7.99E-06 0.00E+00 hafnium-181                           Ci       4.03E-08 0.00E+00 total                                  Ci      7.07E-05 0.00E+00 I
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TABLE 2A Effluent and Waste Disposal Semiannual Report for Year 1996 Liquid Effluents - Summation of all Releases Unit            Otr 1              Otr 2            Est Tot
                                                                                                                % Error A. FISSION AND ACTIVATION PRODUCTS             NOTE 1
: 1. Total release (excluding                             Ci        3.26E-02             2.59E-03           4.00E 01 tritium, gases, & alpha)
NOTE 2                                                                      l
: 2. Avg. diluted conc.                              uCi/ml         1.11E-09             4.82E-10
: 3. Percent limit                                       %         9.19E-02             3.38E-03 l
1 B. TRITIUM NOTE 1
: 1. Total release                                        Ci        2.99E+01             3.49E+00 4.50E 01 NOTE 2
: 2. Avg. diluted conc.                              uCi/ml         1.02E-06             6.49E-07
: 3. Percent limit                                       %         1.02E-01             6.49E-02 i
C. DISSOLVED AND ENTRAINED GASES NOTE 1
: 1. Total release                                        Ci        7.54E-03             6.82E-04           4.00E 01 NOTE 2
: 2. Avg. diluted conc.                              uCi/ml         2.57E-10             1.27E-10
: 3. Percent limit                                       %         1.29E-04             6.34E-05 D. GROSS ALPHA RADIOACTIVITY
: 1. Total release                                       Ci        < LLD                < LLD            4.00E 01 E. VOLUME OF WASTE NOTE 2                             liters          8.46E+06           7.74E+05           1.50E 01 F. TOTAL OF DILUTION WATER (used durina release for averace dil. conc.)                         liters         2.93E+10             5.37E+09           1.30E 01 G. VOLUME OF COOLING WATER                           liters         2.55E+11             4.81E+11 DISCHARGES FROM PLANT NOTE 1: Includes rad.onuclides released via abnorrnal and/or nonroutine releases.
NOTE 2: Does not include rainwater released (i.e. Storm Drain Collection Basin and/or Storm Drain Collection Pond.)
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TABLE 2B Effluent and Waste Disposal Semiannual Report for Year 1996 Liquid Effluents - Batch Mode Nuclides Released                  Unit     Otr i          Otr 2
  - 1. FISSION AND ACTIVATION PRODUCTS chromium-51                          Ci     1.11E-03       1.34E-04 manganese-54                         Ci     7.65E-04       2.82E-05 iron-55                              Ci     3.03E-03       4.95E-05 cobalt-58                            Ci     3.31E-04       7.18E-06 cobalt-60                            Ci     2.66E-02       1.94E-03 technetium-99m                       Ci     6.91E-06     ' < LLD ruthenium-106                        Ci     2.64E-05       < LLD iodine-131                           Ci     2.43E-04       4.69E-05 tellurium-132                        Ci     4.39E-06       3.61E-06 iodine-133                           Ci     3.32E-05       6.41E-05 cesium-134                           Ci     1.42E-04       3.11E-05 cesium-137                           Ci     3.13E-04       2.81E-04 lanthanum-140                        Ci     1.90E-05       < LLD cerium-141                           Ci     1.18E-05       < LLD hafnium-181                          C1     2.64E-05       < LLD total for period                     Ci     3.26E-02       2.59E-03
: 2. DISSOLVED AND ENTRAINED GASES xenon-133                            Ci     4.64E-03       1.72E-04 xenon-135                            Ci     2.90E-03       5.10E-04 total for period                     Ci     7.54E-03       6.82E-04 e
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(                               Lower Limits of Detection 1
January 1, to June 30, 1996                      l pCi/ml
: 1. Licuid Releases                         2. Gaseous Releases Ar-41            1.55E-08 Mn           2.14E-08                 Kr-85m           5.66E-09
        'Fe-55            5.15E-08                 Kr-87            2.67E-08 Co-58            2.34E-08                 Kr-88            2.43E-08 Fe'59            4.04E-08                 Xe-133           1.48E-08
        -Co-60            2.42E-08                 Xe-133m          4.65E-08 Zn-65            4.26E-08                 Xe-135           6.4OE-09  !
Mo-99            1.24E-07                 Xe-138           2.12E-07 Tc-99m           9.81E-09 Ru-106           1.50E-07              3. Todines and Particulates   i l        I-131            8.48E-09                                            l Cs-134           1.14E-08                 Alpha            1.70E-15  l l        Cs-137           1.37E-08                                            i La-140           2.41E-08                 Mn-54            5.82E-14 Ce-141           2.23E-08                 Co-58            4.37E-14 Ce-144           7.82E-08                 Fe-59            1.27E-13 Hf-181           1.68E-08                 Co-60            6.20E-14 Sr-89            2.35E-08                 Zn-65            8.23E-14 Sr-90            1.15E-08                 Sr-89            3.30E-15 Alpha            3.22E-08                 Sr-90            1.20E-15 Nb-95            3.90E-14 l        Kr-87            3.73E-08                 Zr-95            7.35E-14 Kr-88            5.02E-08                 Mo-99            3.37E l        Xe-133           3.77E-08                 Ru-103           5.71E-15 l        Xe-133m          1.12E-07                 I-131            2.96E-14 Xe-135           1.34E-08                 I-132            4.17E-13 Xe-138           1.37E-07                 I-133            1.01E-13 I-134            2.58E-11  1 I-135            6.10E-13 Cs-134           3.52E-14  )
i I
Cs-137           2.95E-14 Ba-140           1.49E-13 La-140           4.69E-14 Ce-141           3.38E-14 l                                                  Ce-144           1.55E-13 l
Hf-181           3.15E-14 Am-241           1.54E-13 NOTES 1: The above values represent typical ''a priori" LLDs for isotopes where values of "<LLD" are indicated in Tables 1A, 1B, 1C, 2A, and 2B. Also included are isotopes specified in Technical Specifications.
2: Where activity for any nuclide is reported as " Less than LLD", that nuclide is considered not present and the LLD activity listed is not considered in summary data.
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TABLE 3A Effluent and Waste Disposal Semiannual Report for Year 1996 Solid Waste and Irradiated Fuel Shipments Waste Class A                                 January throuch June i
: 1. Total volume shioned (cubic meters):             0.00E+00 Total Curie quantity (estimated)               0.00E+00
: 2. Tvoe of Waste                               Six-month     Est. Total Units      Period       % Error   I
: a. Spent resins, filter sludges   meters' O . 00E+00 Curies 0.00E+00          N/A
: b. Dry active waste, compacted    metersa 0.00E+00 noncompacted                   Curies 0.00E+00           N/A    l
: c. Irradiated components          meters
* 0.00E+00 Curies 0.00E+00           N/A
: d. Others                         meters2 0.00E+00 Curies    0.00E+00        N/A
: 3. Estimate of maior radionuclide comoosition l
I
: a.        N/A
: b.        N/A l
: c.        N/A
: d.        N/A t
l-NOTE:
Solid Radioactive Waste was shipped for processing, however, not for final disposal during the report period. Access to the burial facility at Barnwell, South Carolina was not available.
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l Table 3A (cont.)
Effluent and Waste Disposal Semiannual Report for Year 1996 Solid Waste and Irradiated Fuel Shipments
: 4. Cross reference table, waste stream, form, and container tvoe.
Stream        Form         Container tvoe     No. of shioments l                                                                                        \
l                                             Type A/ Type B                             {
: a. Resin       Dewatered &         N/A                N/A Solidified
* 1 I
: b. Dry active Compacted /          N/A                N/A                1 l                  waste       Noncompacted                                              I waste
: c. Irradiated                      N/A                N/A components i
: d. Other                           N/A                N/A                I
* solidification agent or absorbent (e.g., cement, urea formaldehyde)                       j
: 5. Shioment Discosition
: a. Solid Waste Number of Shioments       Mode of Transportation     Destination 0                        N/A                     N/A
: b. Irradiated Fuel Number of Shioments           Mode of Transoortation     Destination 0                          N/A                       N/A l
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TABLE 3B Effluent and Waste Disposal Semiannual Report for Year 1996 Solid Waste and Irradiated Fuel Shipments Waste Class B                                   January throuch June
: 1. Total volume shioned (cubic meters)              0.00E+00 Total Curie quantity (estimated)                 0.00E+00
: 2. Tvoe of Waste                                 Six-month   Est. Total Units      Period     % Error
: a. Spent resins, filter sludges      meters' O.00E+00 Curies    0.00E+00     N/A
: b. Dry active waste, compacted,       meters'   O.00E+00 and noncompacted                  Curies    0.00E+00     N/A
: c. Irradiated components             meters'   O.00E+00 Curies    0.00E+00     N/A
: d. Others (describe)                  meters'   O.00E+00 Curies    0.00E+00     N/A
: 3. Estimate of maior .adionuclide composition
: a.        N/A
: b.        N/A
: c.        N/A
: d.        N/A I
i NOTE:
Solid Radioactive Waste was shipped for processing, however, not          ;
for final disposal during the report period. Access to the                '
burial facility at Barnwell, South Carolina was not available.
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TABLE 3B (cont.)
Effluent and Waste Disposal Semiannual Report For Year 1996             '
Solid Waste and Irradiated Fuel Shipments
: 4. Cross reference table, waste stream, form and container tvoe 1
Stream         Form         Container tvoe    No. of shioments Type A/ Type B
: a. Resin          Dewatered &        N/A              N/A Solidified
: b. Dry active     Compacted /        N/A              N/A waste         Noncompacted waste
: c. Irradiated                       N/A              N/A components
: d. Other                             N/A              N/A
* Solidification agent or absorbent (e.g., cement, urea formaldehyde) l 5.Shioment Discosition
: a. Solid Waste Number of Shioments        Mode of Transoortation     Destination 0                        N/A                     N/A
: b. Irradiated Fuel Number of Shioments        Mode of Transportation     Destination 0                        N/A                     N/A Page 18

     . - .. -. . - .          . -  ..    .....     .-. - - . - ~. . - - ~ .. -                   . ... .. .. . , _ .
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TABLE 3C                                                               l Effluent and Waste Disposal Semiannual Report for Year 1996 Solid Waste and Irradiated Fuel Shipments Waste Class C                                                Januarv throuch June
: 1.      Total volume shicoed (cubic meters)                                   0.00E+00                           ;
Total Curie quantity (estimated)                                      0.00E+00
: 2. Tvoe of Waste                                                   Six-month        Est. Total                    ,
Units                  Period      % Error                   :
: a. Spent resins, filter sludges            meters 8                0.00E+00                             3 Curies                 0.00E+00      N/A                    i
: b. Dry active waste, compacted              meters 3                0.00E+00                             )
and noncompacted                    Curies                 0.00E+00      N/A
: c. Irradiated components                   meters'                 O.00E+00 Curies                 0.00E+00      N/A                     l
: d. Others (describe)                       meters'                 O.00E+00 Curies                 0.00E+00      N/A
: 3.       Estimate of maior radionuclide comoosition
: a.           N/A
: b.           N/A
: c.           N/A
: d.           N/A i
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A TABLE 3C (cont.)
Effluent'and Waste Disposal Semiannual Report for-Year 1996 Solid Waste and Irradiated Fuel Shipments
: 4. Cross reference table, waste stream, form and container tvoe Stream         Form-         Container Tvoe   No. of shioments Type A/ Type B
: a. Resin          Dewatered &           N/A            0
                           . Solidified *
: b. Dry active     Compacted             N/A            0 waste         Noncompacted waste
: c. Irradiated                           N/A            0 components
: d. Others                               N/A            0
* Solidification agent or absorbent (e.g., cement, urea formaldehyde)         N/A
: 5. Shioment Discosition
: a. Solid Waste Number of Shioments        Mode of Transportation     Destination 0                       N/A                   N/A
: b. Irradiated Fuel (non-burial)
Number of Shioments        Mode of Transoortation     Destination 4                 Rail Car IF-300 Cask     CP&L/SHNPP Sole Use Page 20

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ATTACHMENT 2 (Cont.)
                                    . Combustion of Waste Oil January 1, to June 30, 1996 l
l         During this reporting period, approximately 3.48E3 gallons of t
contaminated waste oil were incinerated in the on site oil incinerator.      The total activity contained in this quantity of waste oil included 6.21E-05 curies of Cobalt-60, 7.99E-06 curies
;         of Cesium-137, 6.12E-07 curies of Manganese-54, and 4.03E-08 curies of hafnium-181.
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l l          .
l                               ATTACHMENT 3
(                     Environmental Monitoring Program l
l                       January 1, to June 30, 1996 I
Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census
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~
l ATTACHMENT 3 (Cont.)
ENCLOSURE 1 Milk and Vegetation Sample Locations January 1, to June 30, 1996 No milk samples were identified during the last Land Use Census, therefore, no milk locations were available during this time period.
I Vegetation sample locations remained unchanged.
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* V ATTACHMENT 3 (Cont.)
ENCLOSURE 2 Land Use Census January 1, to June'30, 1996 The results of'the 1996 Land Use Census will be reported in the next Semiannual Radioactive Effluent' Release Report.
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l ATTACHMENT 4 Effluent Instrumentation January 1, to June 30, 1996 Enclosure 1: Radioactive Liquid Effluent Monitoring  i Instrumentation.                        '
l Enclosure 2: Radioactive Gaseous Effluent Monitoring Enclosure 3: Liquid Hold-Up Tank                     I l
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ATTACHMENT 4 (Cont.)
ENCLOSURE 1 Radioactive Liquid Effluent Monitoring Instrumentation  j January 1, to June 30, 1996 No Radioactive Liquid Effluent Monitoring Instrumentation was l inoperable for greater than 30 days.
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ATTACHMENT 4 (Cont.)
ENCLOSURE 2 Radioactive Gaseous Effluent Monitoring Instrumentation January 1, to June 30, 1996 No Radioactive Gaseous Effluent Monitoring Instrumentation was inoperable for greater than 30 days.
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a ATTACHMENT 4 (Cont.)
ENCLOSURE 3 Liquid Hold-Up Tank
,                            January 1, to June 30, 1996 No liquid hold-up tank exceeded the 10 Ci limit during this reporting   period.                                         )
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1 ATTACHMENT 5                        l l
Major Modifications to the Radioactive Waste Treatment System January 1, to June 30, 1996 l
As per footnote 7 to Technical Specification 6.15, a discussion {
I of any major modifications to the radioactive waste treatment systems will be submitted with the Final Safety Analysis Report update.
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\

ATTACHMENT 6 Meteorological Data January 1, to June 30, 1996 As per Technical Specification 6.9.1.10.a footnote 6, the annual summary of meteorological data collected over the calendar year will be submitted to a file and will be available for NRC review upon request.
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4 ATTACHMENT 7 Annual Dose' Assessment January 1, to June 30, 1996 As per Technical Specification 6.9.1.10.b, an assessment of radiation doses due to the radioactive liquid and gaseous effluents released during the calendar year will be reported within 90 days after January 1 of each year.                The annual dose assessment is not included with this report.
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l ATTACHMENT 8 Off-Site Dose Calculation Manual (ODCM) and          l 1
Process Control Program (PCP) Revisions January 1, to June 30, 1996 i'                                                                     1 l
There were no revisions made to the Off-Site Dose Calculation   :
Manual or Process Control Program during this reporting period. j 4
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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR 62 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1
LIST OF REGULATORY COMMITMENTS                                  I The following table identifies those actions committed te by Carolina Power & Light Company in this document. Any other actions discussed in the submittal represent intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.
Committed Commitment                                      date or outage None E2-1 1
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