ML20092M254
| ML20092M254 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/31/1991 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20092M241 | List: |
| References | |
| NUDOCS 9202270227 | |
| Download: ML20092M254 (68) | |
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l Brunswick Steam Electric Plant Somlannual Radioactivo Effluent Report July 1, to Docombor 31, 1991 ATTACilMENTS : PAGES:
- 1. Supplemental Information 7
- 2. Effluent and Wasto Disposal Data 0 - 22
- 3. Environmental Monitoring Program 23 --25
- 4. Effluent Instrumentation 26 - 29
- 5. Majo'r Modification to Radioactive Wasto 30 Treatment Systems
- 6. Motoorological Data 13 1
- 7. Annual Dose Assessment 32_-:47
Page 1 9202270227 911231 PDR ADOCK 05000325 R. PDR 1
ATTACHMENT 1 Supplemental Information July 1, to December 31, 1991 s Page 2 I
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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plant Licensee: Carolina Power and Light company
- 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 (2) Calendar Year (a) 20 mrad gamma (b) 40 mrad 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 (a) 15 mrem to any organ (2) Calendar Year (a) 30 mrom to any organ (3) Calendar Quarter for Burning Contaminated Oil (a) 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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- 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 (2) 3000 mrem / year to the skin B. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.1.b)
(1) 1500 mrom/ year to any organ 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.
- (l) Tritium: MPC = 3 E-03 uCi/ml and
- (2) Dissolved and entrained gases: HPC = 2 E-04 uCi/ml
- 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. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.
D. Particulates for Burning Oil Analysis for specific radionuclides by grab samples of each batch of oil to be burned.
E. Liquids Effluents Analysis for specific radionuclides of individual releases by gamma spectroscopy.
- Used as applicable limits for Table 2A Page 4
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: 2.60E+02 (2) Total time period for batch releases: 2.73E+04 Minutes (3) Maximum time period for a batch release: 2.15E+02 Minutes (4) Average time period for a batch release: 1.05E+02-Minutes (5) Minimum time period for a batch release: 7.00E+00 Minutes (6) Average; stream flow during periods of release of effluent into a flowing '
stream : 6.43E+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 (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:
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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 abnormal releases that exceeded'10CFR50 limits See Page 6 for a discussion of release events that occurred Page 5 l
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Non-Routine Releases Liquid Releases - Total Releases = 2.00E+00 Total curies = 8.34E-04
- 1. Storm Drain Basin The Storm Drain Basin was released to the discharge canal via the emergency discharge line 2 times during periods of heavy rainfall.
It was necessary to open the emergency discharge line to prevent flooding in critical plant areas.
Release 1 lasted 64 minutes and released approximately 1.18E+06 gallons of water containing 2.91E-04 curies. The activity released was 1.79E-04 curies of I-133 and 1.12E-04 curies of Xe-135.
Release 2 lasted 71 minutes and released approximately 2.07E+06 gallons of water containing 5.43E-04 curies. The activity released was 4.31E-04 curies of I-133 and 1.12E-04 curies of Ru-103.
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Discussion of Tritium in the Storm Drain Collection Pond Approximately 3.7E+07 gallons containing 1.88E+01 curies of tritium was released from the Storm Drain Collection Pond (SDCP) to the Intake Canal during this reporting period. The tritium was found during an investigation by the plant staff. The source of tritium in this pathway is from small steam leaks in the Turbine Buildings. During normal operations tritium is being released via the swamp coolers that are used for cooling the air in the Turbine Buildings. Water that overflows from the swamp coolers discharges tc the Storm Drain Collection Basin (SDCB) within the Protected Area and is then pumped to the SDCP. The SDCD and the SDCP are discussed in the FSAR and the Technical Specifications. The SDCP is a permitted release point approximately 39 acres in size which requires sampling and analysis prior to release but does not include tritium analysis unless the trigger level based on gamma isotopic analysis is exceeded. Since the gamma isotopic of the SDCP effluents is <LLD, tritium analysis is not required by the Technical Specifications. However, the SDCP effluent water that was analyzed during the investigation revealed detectable tritium activity and is therefore being reported for your information.
As per 10CFR20 Appendix B, this nuclide may be considered as not present in a mixture since the ratio of the concentration of that nuclide in the mixture to the concentration limit for that nuclide specified in Table II of Appendix B does not exceed 1/10 MPC and tne total MPC is less than 1/4.
A conservative calculation using the above source term based on 1/10 of the-10CFR50 Appendix I limit, yielded approximately 5.6E-02 % of the limit. Thece dose calculatior.s show that the impact to the environment is insignificant and provides the basis for not amending past reports. Curies of tritium released from the.
SDCP will be reported in future I N ioactive Effluent Release Reports as long as tritium is detectable in the SDCP effluent.
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ATTACHMENT 2 Effluent and Waste Disposal Data Brunswick Steam Electric Plant July 1, to December 31, 1991 Enclosure 1 Table 1A: 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-all Releases Table 2B: Liquid Effluents Lower Limits of Detection Table 3: Solid Waste and Irradiated Puel Shipments Enclosure 2 Combustion of Waste Oil l
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TABLE 1A Effluent and Waste Disposal Semiannual Report for Year 1991 Gaseous Effluents - Summation of all Releases Est. Tot.
Unit Qtr 3 Otr 4 Error %
A. EJSSION AND ACTIVATION GASEE
- 1. Total release Ci 2.02E+02 9.95E+01 1.15E 02
- 2. Average rel;a.e uCi/ccc 2.54E+01 1.25E+01 rate for period
- 3. Percent of technical specification limit % 2.30E-02 1.20E-02 B. IODINES
- 1. Total I-131 Ci 5.90E-03 1.30E-03 7.00E 01
- 2. Average release uCi/sec 7.42E-04 1.64E-04 rate for period C. PARTICULATES
- 1. Total release Ci 2.49E-03 4.01E-03 7.00E 01
- 2. Average release uCi/sec 3.13E-04 5.04E-04 rate for period
- 3. Gross alpha Ci 3.27E-06 4.64E-06 D. I,ritium
- 1. Total release Ci 9.59E+00 8.63E-01 7.00E'01
- 2. Average release uCi/sec 1.21E+00. 1.09E-01 rate for period E. IODINE-131. IODINE-133. TRITIUM AND PARTICULATES
- 1. Total Release Ci 9.61E+00 -8.76E-01 i
l 2. Average release uCi/sec 1.21E+00 '1.10E-01 rate for period
- 3. Percent of technical specification limit % 2.16E-01 5.80E-02 F. PARTICULATES VIA BURNING CONTAMINATED OIL'
- 1. Total Release Ci 0.00E-00 0.00E-00
! 2. Average release I rate for period uCi/sec 0.00E-00 0.00E-00
- 3. Percent of technical specification limit- % 0.00E+00 0.00E+00 Page 9-
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TABLE IB Effluent and Waste Disposal Semiannual Report for Year 1991 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 3 Otr 4
- 1. EISSION GASES argon-41 Ci 1.52E-01 <LLD krypton-85m Ci 1.69E+01 1.30E+01 krypton-87 C1 1.40E+00 5.05E-01 krypton-88 Ci 1.73E+01 6.11E+00 xenon-131m Ci 2.83E+00 <LLD xenon-133 Ci 7.41E+01 3.80E+01 xenon-135m Ci 1.04E+01 4.86E+00 xenon-135 Ci 9,49E+00 7.52E+00 xenon-137 Ci 1.37E+01 2.72E+00 xenon-138 gi 6.68E+00 6.26E-01 total for period C1 1.53E+02 7.33E+01
- 2. IODINES iodine-131 Ci 4.02E-03 5.36E-04 iodine-132 Ci 1.56E-03 <LLD iodine-133 Ci 7.25E-03 1.34E-03 iodine-135 gi 3.97E-03 <LLD total for perled Ci 1.68E-02 1.88E-03
- 3. PARTICULATES -
chromium-51 Ci 1.51E-04 <LLD manganese-54 Ci 9.72E-07 8.93E-06 cobalt-60 Ci 6.97E-05 5.91E-05 strontium-89 C1 1.07E-04 3.87E-05 strontium-90 Ci 9.21E-07 <LLD tellurium-129m Ci 3.43E-05 <LLD cesium-137 Ci 4.78E-05 1.87E-06 barium-140 Ci 2.68E-04 7.69E-05 lanthanum-140 Ci 4.45E-04 9.06E-05 cerium-141 Ci 8.36E-07 <LLD cerium-144 gi 5.24E-06 <LLD total for period C1 1.13E-03 2.76E-04
- 4. TRITIUM hydrogen-3 Ci 6.12E+00 1.56E-01 Page 10
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4 TABLE 10 Effluent and Waste Disposal Semiannual Report for Year 1991 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Otr 3 Otr 4
- 1. EIEELQN GASES krypton-85 Ci 5.88E-05 <LLD xenon-133m Ci 1.63E-01 <LLD xenon-133 Ci 1.53E+01 8.36E+00 xenon-135m C1 1.77E+00 1.82E+00 xenon _135 Q1 3.13E+Q1 1.60E+01 total for period Ci 4.86E+01 2.62E+01
- 2. IODINES iodine-131 C1 1.88E-03 7.68E-04 iodine-132 C1 1.37E-02 8.66E-03 iodine-133 Ci 1.23E-02 6.40E-03 iodine-134 Ci 2.42E-03 1.53E 03 iodine-135 C1 1.65E-02 9.92E-03 total for period Ci 4.68E-02 2.73E-02
- 3. PARTICULATES chromium-51 Ci 9.14E-04 6.21E-04 manganese-54 Ci 7.52E-05 9.37E-04 cobalt-57 Ci 1.00E-08 <LLD cobalt-58 Ci 5.13E-05 2.04E-04 iron-59 Ci <LLD 7.41E-05 cobalt-60 C1 2.90E-04 1.85E-03 strontium-89 Ci 5.45E-06 4.58E-06 strontium-90 Ci- 2.64E-07 '1.40E-08 antimony-124 Ci <LLD 1.68E-OL cesium-137 Ci 2.02E-06 1.22E-05 lanthanum-140 Ci 4.18E-06 5.04E-06 barium-140 Ci 1.13E-05 4.12E-06 corium-141 C1 1.54E-06 <LLD cerium-144 C1 1.08E-06 <LLD total for period C1 1.36E-03 3.73E-03
- 4. TRITIUM hydrogen-3 Ci 3.47E+00 7.07E-01 TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1991 Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released Unit Otr 3 Qtr 4
- 1. PARTICULATES
- Ci N/A N/A
- No contaminated oil was incinerated during this reporting period.
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TABLE 2A Effluent and Waste Disposal Semiannual Report for Year 1991 Liquid Effluents - Summation of all Releases Unit Otr 3 Otr 4 Est Tot
% Error A. FISSION AND ACTIVATION PRODUCTS
- 1. Total release (excluding Ci 1.29E-01 2.11E-01 3.50E 01 tritium, gases, & alpha)
- 2. Avg. diluted conc. uCi/ml 3.15E-09 8.29E-09
- 3. Percent limit % 1.68E-01 5.48E-01 B. TRITIUM
- 1. Total release Ci 2.62E+01 l'.25E+01 4,00E 01
- 2. Avg. diluted conc. uCi/ml 6.41E-07 4.92E-07
- 3. Percent limit % 2.14E-02 1.64E-02 C. DISSOLVED AND ENTRAINED GASES
- 1. Total release C1 1.46E-01 6.89E-02 3.50E 01
- 2. Avg. diluted conc. uCi/ml 3.56E-09 2.70E-09
- 3. Percent limit % 1.78E-03 1.35E-03 D. GROSS ALPHA RADIOACTIVITY
- 1. Total release Ci O.00E-00 0.00E-00 4.00E 01-E. VOLUME OF WASTE liters 8.85E+06 1.02E+07 1.25E 01 F. TOTAL OF DILUTION WATER Jused durino release for averaae dil. conc.) liters 4.09E+10 2.55E+10 1.30E 01 G. VOLUME OF CCOLING WATER liters 4.54E+11 2.71E+11 DISCHARGED FROM PLANT Page 12
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TABLE 2D Effluent and Waste Disposal Semiannual Report for Year 1991 i Liquid Effluents - Batch Mode Nuclides Released Unit Otr 3 Qir_1
, 1. FISSION AND ACTIVATION PRODUCTS ,
sodium-24 C1 5.84E-04 9.26E-05 chromium-51 Ci 6.89E-03 3.03E-02 manganese-54 Ci 2.51E-02 2.43E-02 iron-55 Ci 5.12E-03 2.63E-02 cobalt-58 Ci 2.41E-02 2.43E-02 iron-59 Ci 8.79E-05 4.56E-04 cobalt-60 Ci 5.98E-02 1.03E copper-64 Ci 4.93E-04 <LLD zinc-65 Ci <LLD 9.71E-04 zinc-69m Ci 1.56E-06 <LLD arsenic-76 Ci 2.18E-06 <LLD' strontium-89 Ci 3.20E-04 <LLD yttrium-91m Ci 7.44E-05 1.66E-05 yttrium-92 Ci <LLD 3.52E-04 strontium-92 Ci 3.37E-05 2.94E-05 niobium-95 Ci 5.46E-05 1.28E-04 technetium-99m Ci 6.80E-04 2.60E-05 ruthenium-103 Ci 8.20E-07 6.82E-05 silver-110m Ci 2.13E-04 4.74E-05 antimony-124 Ci <LLD 3.54E-04 tellurium-129m C1 1.86E-04 9.47E-05 iodine-131 C1 1.46E-04 1.04E-05 tellurium-132 Ci- 5.15E-06 <LLD iodine-132 C1 2.65E-04 <LLD iodine-133 C1' 2.23E-04 5.98E-05 cesium-134 C1 3.48E-04 2.62E-05 cesium-137 C1 1.25E-03 4.19E-04 barium-140 C1 1.50E-03 <LLD lanthanum-140 C1 1.05E-03 <LLD cerium-141 C1. . <LLD 2.19E-05 cerium-144 Ci .3.15E-05 <LLD hafnium-181 Ci 1.65E-06 <LLD tungsten-187 gi 2.72E-04 <LLD total for period C1 1.29E-01 2.11E-01 l
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TABLE 2B (continued) .
Effluent-and Waste Disposal Semiannual Report for Year 1991 Liquid Effluer:cs - Batch Mode Nuc1 ides Released linit Qt d Otr 4
- 2. GASES krypton-85m Ci 2.17E-06 <LLD.
Xenon-133 Ci 8.38E-02 1.35E-02 xenon-133m Ci 1.34E-03 2.08E-04 xenon-135m C1. 4.19E-05 <LLD xenon-131 gi 6.06E-02 5.52E-02 total for period C1 1.46E-01 6.89E-02 l
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Lower Limits of Detection July through December 1991 uCi/ml
- 1. Liauld Releases 2. Gaseous Releases Zn-65 5.45E-08 Ar-41 2.35E-08 Zn-69m 1.94E-08 Xe-132m .3.02E-07 Cu-64 4.01E-06 Xe-133m 5.73E-08 As-76 4.83E-08 Kr-85 2.31E-06 Y-92 1.22E-07 Sb-124 2.15E-08 3. Iodines and Particulates Te-132 1.41E-08 I-132 2.52E-08 Da-140 6.78E-08 Co-57 2.88E-14 La-140 3.98E-08 Cr-51 2.48E-13 Cc-141 3.00E-08 Fe-59 8.76E-13 Co-144 1.17E-07 Sb-124 4.15E-14 Hf-181 1.78E-08 To-129m 9.77E-13 W-187 7.86E-08 I-132 5.74E-13 Xe-135m 8.78E-08 I-135 3.13E-13 Kr-85m 2.38E-08 Ce-141 5.65E-14 Sr-89 4.25E-09 Ce-144 2.13E-13 Sr-90 7.49E-16 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.
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 1991 Solid Waste and Irradiated Fuel Shipments Waste Class A July throuch Decemb2I
- 1. Total volume shipped (cubic meters) 1.33 E2 Total Curio quantity (estimated) 3.32 E2
- 2. Tyne of Waste Six-month Est. Total Units P_qriQd % Error 3
- a. Spent resins, filter sludges meters 6.46 El Curies 3 3.02 E2 1.00E1
- b. Dry active waste, compacted meters 6.80 El noncompacted curies 3 3.02 El 1.00E1
- d. Others (oil) meters 0.00 E0 Curies 0.00 EO N/A
- 3. Estimate of maior radionuclide comnosition
- a. Cr-51 1.47 EO%
Mn-54 6.35 EO%
Fe-55 5.38 El%
Co-60 3.10 El%
Ni-63 2.00 EO%
Cs-137 2.38 E0%
- b. Mn-54 6.12'E0%-
Fe-55 6.57 El%
Co-60 2.19 El%
Co-58 3.17 EO%
Ni-63 1.69 EO%
- c. N/A N/A
- d. N/A N/A Page 16
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Table 3A (cont.)
Effluent and Waste Disposal Semiannual' Report for Year 1991 Solid Waste and Irradiated Fuel Shipments
- 4. Cross reference table, waste stream. form. and container tvoo.
Stream Form Container tvoo No. of shinments
- a. Resin Dewatered & Type A/ Type B 9/4 Solidified *
- b. Dry active Compacted /non- STP 19 waste compacted waste
- c. Irradiated N/A 0 components
- d. Other N/A 0
- solidification agent or absorbent (e.g., cement, urea formaldehyde) NONE
- 5. Shloment Disposition
- a. Polid Waste Number of Shipments Mode of Transnortation ' Destination 32 Sole Use CNSI/Barnwell SC
- b. Irradiated Components Number of Shinments Mode of Transnortation Destination l
t 0 N/A N/A l
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TABLE 3D t for Year 1991 i posal Semiannual Repordiated Fuel Shipments Effluent and Waste D sSolidJ.111y Waste 3hrsusIb Dannabsr and Irra 7.69 EO meters) 9 89 El Elfit9 S l AS A _D Est. Total d ((cubicestimated) Six-month
- 1. Tp.lal_yoltimp_gllippsTotal Curic quantity1.0E1% 3 7.69 E0 meters 9 89 El N/A
- 2. Ty m f._ East _q t r sludges Curies 0.00 L4 meters 0.00 E0 N/A
- a. Spent resins, fil ewaste,Curies compacted, 3 0.00 EO
- b. Dry active meters 0.00 E0 N/A and noncompacted ts Curies
- 0 00 EO
- c. Irradiated componen meters 0.00 EO Curies (describe)
- d. Others dip _nu_glidq._p.pppSalt1QD 4.86 E0t
- 3. Esti]Itate._.gi Aah.a Mn-54 4.57 El%
Fc-55 1.79 E0t Co-58 4.24 El%
- a. Co-60 3.01 EO%
Ni-63 1.29 EO%
Sb-125 N/A N/A N/A N/A b.
N/A N/A
- c. add _.chgr_typa i antG d.
C. J a g g _ y_c. h b h q,_girqam_f_QIM_.DDI.1YPA__
- 4. 0/2 S1IED Type A/ Type B 0 Dewatered & N/A
- a. Resin Golidified Compacted /non- 0
- b. Dry active compacted N/A waste 0 N/A
- c. Irradiated components absorbent N/A
- d. Other
- Solidification agent orurea formaldehyde)
(e.g., cement, Page 18
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TABLE 3B
, Effluent and Waste Disposal Semiannual Report for Year 1991 Solid Waste and Irradiated Fuel Shipments
- Waste Class B July throuch December
- 1. Total volume _ghinned (cubic meters) 7.69 EO
, Total Curio quantity (estimated) 9.89 El
- 2. Type of Waste Six-month Est. Total Units 3 Period % Error
- a. Spent resins, filter sludges meters 7.69 E0 1.0El%
Curies 3 9.89 E1
- b. Dry active waste, compacted, meters 0.00 EO N/A and noncompacted Curies 0.00 E0 3
- d. Others (describe) meters 0.00 20 N/A Curies 0.00 EO
- 3. Estimate of maior radionuclide compositiqn
. a. Mn-54 4.86 EO%
! Fe-55 4.57 El%
Co-58 1.79 E0%
i Co-60 4.24 El%
Ni-63 3.01 E0%
Sb-125 1.29 EO%
- b. N/A N/A
- c. N/A N/A l d. N/A N/A
- 4. Cross reference table, waste stream, form and container tvoe Stream Form Container tvoe No. of shinments
- a. Resin Dewatered & Type A/ Type B 0/2 Solidified
- b. Dry active Compacted /non- N/A 0 compacted waste
- c. Irradiated N/A 0 components
- d. Other N/A 0
- Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A Page 18 i
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Table 3B (cont.) ;
Effluent and Waste Disposal Semiannual Report for Year 1991 '
Solid-Waste and Irradiated Fuel Shipments 5.Shioment Discosition
- a. Solid Waste Number of Shloments Mod.p of Transportation Destination 2 SOLE USE CNSI/BARNWELL S.C.
- b. Irradiated Fuel Humber of Shioments Mode of Transportation Destination 0 N/A N/A l
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TABLE 3C Effluent and Waste Disposal Semiannual Report for Year 1991 Solid Waste and Irradiated Fuel Shipments Waste Class C July through December
- 2. Tvoe of Waste Six-month Est. Tot.
Units 3 Period % Error
- a. Spent resins, filter sludges meters 0.00 EO N/A Curies 3 0.00 E0
- b. Dry active waste, compacted meters 0.00 EO N/A and noncompacted Curies 0.00 E0 3
- c. Irradiated components meters 0.00 EO N/A Curies 3 0.00 E0
- 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-reference tabic, waste stream, form and container type Stream Form Container Tvoe No. of shipmentq
- a. Resin Dewatered & N/A 0/0 Solidified *
- b. Dry active Compacted /non- N/A 0 waste compacted
- c. Irradiated Type B 0 components
- d. Others N/A 0
- -Solidification agent or absorbent (e.g., cement, urea formaldehyde) NONE Page 20
Table 3C (cont.) l Effluent and Waste Dispocal Semiannual Report for Year 1991 l Solid Waste and Irradiated Fuel Shipments 1
- 5. ShiDment Disppp_it.iDB
- a. Solid Wasto Number of Shitments Mode of Transportation Destination 0 N/A N/A
- b. Irradiated Fuel (non-burial)
Number of Shloments Mode of Transoortation Destination 2 Railcar/IF300-CASK. CP&L/SHNPP Sole Use i
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-atze - - a 2 a a wa- -mzmoa i eoes, .Sw-n,s1. ,,,a A~p>+ A--be-- X- <LM - 4 e- %~ eWm5,- e*L6w,4s--Lw-LLa-,pnu ,+-,-,ub, ENCLOSURE 2 Combustion of Waste Oil July 1, to December 31, 1991 No contaminated waste oil was incinerated during this reporting period.
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ATTACHMENT 3 Environmental Monitoring Program July 1, to December 31, 1991 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census l
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EllCIDSURE 1 Milk and Vogotation Sample Locationn July 3, to December 31, 1991 llo milk namplo locations were availablo during this time parlod.
Vegetation samplo locations romained unchanged.
Page 24 l
EllCIASURE 2 i i
Land Uso Consus
'uly 1, to December 31, 1991 b
The 1991 Land Uso Consus was performed during the period of August !
16 to August 20, 1991. lio locations woro identiflod that aro reportable in the Semiannual Radioactivo Effluent Release Report.
l 5
,f-Page 25 2
. _ - _ , _ . _ _ . _ _ . . . _ _ _ --m._..___ . _ _ __ . . . . _ ..
ATTACl! MENT 4 Effluent Instrumentation I July 1, to December 31, 1991 Enclosure 1: Radioactivo Liquid Effluent Monitoring Instrumentation.
Enclosure 2: Radioactivo Gaseous Effluent Monitoring l l
Enclosure 3: Liquid floid-Up Tank t
9
.)
Page 26-l l
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E!1CI45URE 1 July 1, te December 31, 1991 Radioactivo Liquid Effluent Monitoring Instrumentation The liquid radwasto offluent flow measurement device (2-G16-FIT-11057) was inoperablo '.*or greater than 30 days during this period.
The instrument was not returned to service within a 30 day period ;
due to the inability to calibrate the instrument within its
< design accuracy. A Plant Modification installed now instrumentation in December of 1991.
The Unit #2 Service Water Radiation Monitor (2-D12-RM-K605) was inoperable for a period greater than 30 days during this reporting ;
period due to the system being bypassed for the Unit #2 Outago.
k 1
I Page 27
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.__ -_.._m . . _ _ _ _ _ _ _ _ . . _ . . . . _ _ . _ _ _ _ _ _ _ __._ _ _ _
ENCLOSURE 2 July 1, to December 31, 1991 Radioactivo Gascous Effluent Monitoring Instrumentation Unit 1 & 2 Main Condensor Off-Gas treatment system explosivo gas ,
monitors ig2)-OG-AIT-4284 (SJAE. A.ll, Analyzer) , 1(2)-OG-AIT-4285 l (SJAE.A.lly Analyzer), 1(2)-OG-AIT-4324 (SJAE.B.ll y Analyzor) , and l 1(2)-OG-AIT-4325 (SJAE . B. li2 Analyzer) woro inoperable for greator l than a 30 day period during July 1 to December 31, 1991. Due to design problems, those monitors woro not roturned to service within 30 days.
The Unit #2 Reactor Roof Vent Monitor ( 2-CAC-AQll-12 64 -3 ) was inoperable for a period greator than 30 days during this reporting period. System modifications woro mado such that continuous collection of particulate and iodino samplos could bo maintained during sampling and maintenanco evolutions. The delay in return to service was caused by design problems that were discovered during this evolution. During acceptance testing it was found that the system had considerable air inloakago. Differences betwoon system photoholic indication and a calibrated rotameter lead to an in-depth investigation of the system's integrity. The new location of the photoholic sensing orifice made it possible for the first time to identify an inloakage problem associated with the detector, sample holder chambers, and pump seals. When identifiable sources of ininakago were removed from the system, the previously used flow rate of 3 sofm could not be obtained even when subjecting the system to considerable vacuum (greater than 10 inchos of lig) . The short term solution was to operate the reconfigured monitor using an auxiliary sample pump'at 2 scfm. The data that is collected during the next reporting period will be evaluated against past data to determine if the magnitudo of the problem has had any impact on past reports. The long *rrm solution is to remove the existing samplo pumps via plant modification and install sealed shaft sample pumps capable of maintaining a desired sample flow rate and provido indication of seal failure.
l Page 28 l
___ _......_.._____..______m________._.-.. . . . _ _ _ __. _ . -_ ._. _
6 ENCIASURE 3 Liquid lloid-Up Tank July 1, to December 31, 1991 j I
- llo liquid hold-up tank excoo %d b '
3 t! limit during this reporting period.
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Page 29 wesyv7vw-Nc w -
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ATTACHMENT 5 Major Modificationu to the Radioactivo Wanto Troatment System i July 1, to Docomber 31, 1991 As por footnote 7 to Technical Specification 6.15, a discuncion of any major modifications to the radioactive wasto treatment systems will be submitted with the Final Safety Analysin Report updato.
4 i
Page 30
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I 4
i 1 ATTACllMENT 6 Heteorological Data July 1, to December 31, 1991 i
Au por Technical Specification 6.9.1.10.a footnoto 6, the annual summary of notoorological data collected over the calendar year i
- will bo submitted to a filo and will be available for NRC review I upon request.
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Page _ '31
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ATTACHMENT 7 Annual Dose Assosoment January 1, to December 31, 1991 Attached is the annual dono assessment for the Drunswick Steam Electric Plant for the timo period of January 1, to Decembo- 31, 1991.
Enclosuro it Annual Liquid Doso Assosoment Enclosuro 28 Annual Gaseous Doso Assessment Page-32
E Enclosure 1 Annual Liquid Doso Assessment IllCLUDED AREt Sito Specific Data Sourco Torm As Iow As Ronsonably Achievablo Maximum Individual Doso Summary - Total Integrated and Rocreation Population Doso l
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I-Page.33-r l _
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i ANNtJAL OSEP UNITS 1 AND 2 LIQUID RELEASES 1991 i
DISCMARGE=1.52E+03 CFS SOURCE TEEN m>LTIPLIEe=1.OCE+00 f I
5ALTWATER SITE 1
r NO RECONCENTR ATION MODEL !
s FRACTION --- ADoLT=0.Tt t
! 50-MILE PGPULATION=2.82E+05 TEE N A GE R =0.11 1
' CHILD =0.19 .
l DOSE FACTOR LIBRARY CONTAINS 696 ENTRIE$ I i
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l Enclosuro 2 Annual Gaseous Doso Assessment l
JNCLUDED ABEL 1
Source term for the throo releano modos and the sito aggregato Total 50 milo Integrated Population Doso by pathways and organs l
11ypothetical maximum individual organ doso due to Iodinos, Particulatos, and Tritium for a cow milk pathway at_ 4.75 miles
,' llorthoast. l 1
Maximum sito boundary dose by age group and organs for all ,
pathways. ;
Estimated individual organ dose using the 1991 Land Uso Connus for I the worst sector and existing pathways.
Maximum site boundary dose duo to Iodinos, Particulatos, and i Tritium for oxisting pathways. ;
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Page 38 1
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.AL #ADIOLOGICAL EFFLUEMT REPORT!*sG RUM DATE: 02/11/92 :
CP&L SES atm TierE r 12:54:09 INPuf SOURCE TEpars [
GA$RPT THIS 1991 SOURCE TERM (GROUNO LEVEL) BSEP UMETS 1 AND 2 l 1 H - 3 '3.440E+00 1 25 MM- 54 1.030E-06 [
27 CO- 57 1.COOE-08 !
27 CO- 60 7.260E-06 j 5.880E-05 36 RR- 85 38 SR- 89 5.750E-06 .
44 RU-103 4.840E-OS [
53 I -131 2.8BOE-04 53 I -132 7.160E-05
- 53 1 -133 8.390E-04 53 1 -135 2.100E-04 '"
54 AE-133 7.340E+00 54 XE-135 7.690E+00 f 56 BA-140 5.720E-06 r 57 LA-140 5.040E-06 l 58 CE-141 G.570E-08 i 58 CE-144 1.490E-06 i
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RuN DATE: 02/11/92 ,
CP&L SEMI-oNeuct RAD 10LOGICat EFFLUENT REPORTING ROM TIwEt 12:54 09 GOSRPT RADIATION DOSES AT LELECTED LOCAT'ONS J
4 TMIS 1991 LOURCE TERu (GRDuMD LEVEL) BSEP UNITS 1 AND 2 1991 50uMCE TERM (MIAED wODE) 05EP UNITS 1&7 1991 SOURCE TERM (ELEVATED MODE) S5EP UM1TS 1&7 SPECIAL LOCATION METERS DIR PL GR IN v Cm Gu w ;
1
- 3 SITE BOUNDARY 1127.0 NE O 1 1 O O O O
. ANNUAL BETA AIR DOSE = 6.389E-03 u!LLRaoS
= 5.751E-03 MILLRaOS l onNuAL Gamma AIR DOSE l MIDNEY TMvROID LUNG SalN TOTAL Booy GI-TRACT BONE LIVER 8.397E-03 9.51BE-03 8.44JE-03 9. 74dE-0 3 ,
ADutT 8.389E-03 8.394E-03 7.713E-03 8.393E-03 i
1 7.708E-03 7.709E-03 7.70BE-03 7.7C8E-03 9.067E-03 GRouMD PL ANE 7.708E-03 7.708E-03 7.708E-03 6.785E-04 5.239E-06 6.849E-04 6.886E-04 1.809E-03 7.344E-04 INMALATION 6.811E-04 6.861E-04 8.400E-03 8.4GSE-03 9.840E-03 8.474E-03 9.750E-03 t TEENAGER 8.394E-03 8.399E-03 7.715E-03 t f 70HE-03 7.70ME-03 7.70HE-03 7.70ME-03 7.708E 93 9.067E-03 j GROUND PLANE 7.708E-03 7.7DSE-03 2.137E-03 7.656E-04 6.876E-04 6.863E-04 b.908E-04 T.2J7E-06 6.9tSE-04 6.vb7E-04 IMHALATION 8.371E-03 8.325E-03 f.OOSE-02 8.380E-03 9.671E-03 CHILD 8.316E-03 8.316E-03 7.718E-03 7.70SE-03 7.708E-03 7.708E-03 9.067E-03 !
GROUND PLANE 7.708E-03 7.708E-03 7.70HE-03 7.708E-03 6.718E-04 6.038E-04 6.077E-04 9.65SE-06 6.123E-04 6.168E-04 2.337E-03 IWnALATION 6.077E-04 7.715E-03 8.CO3E-03 8.064E-03 9.643E-03 8.102E-03 9.414E-03 INFANT 8.058E-03 8.057E-03 7.708E-03 7.709E-03 7.700E-03 7.708E-03 7.708E-03 9.067E-03 GROuMD PLAME 7.708E-03 7.700E-03 3.934E-04 3.472E-04 3.487E-04 6.873E-06 3.540E-04 3.557E-04 1.935E-03 INMALATIUM 3.499E-04 i
I I
e
ATTACHMENT 8 Off-Site Doso Calculation Manual (ODCM) and Process control Program (PCP) Revisions July 1, to December 31, 1991 Brunswick Steam Electric Plant There were no revisions made to the Process Control Program during this reporting period.
Revisions 12 and 13 were made to the off-Sito Doso Calculational Manual during this timo period.
- 1. In revision 12, Pago 3-30 of the ODCM was revised to updato the table with the results of the latest Land Uso Consus.
- 2. In revision 13, Pago E-1 of the ODCM was revised por Plant Modification to change the Liquid Effluent Flow Rato Measuromont Doviso.
A copy of Revisions 12 and 13 to the ODCM are included as a part of this attachment.
l l
l l
Pago 48
ATTAC104E!rt A REQUEST TOR OTT SITE DOSE CALCUIATION MAlfUAL CHANGE e llI. ba d i Date *7" // ~ #[/ Rev. /d.
Originator: ,
S r.g.s and S.ceton. Revt.edi c,ver ow e
,r,.. / /t Al' / /-/AAu / art,i .
a na e s _ No '
t Reseon for Cuang.: Tal k 2.2- 2. w n undded to h. eentshd l\
i wM M resalh & W d mel+ lu) the (m a s .
1 Safety Analysis Complete: I/4 Date: 7-II 'I/ .'
y "
REVIEWS:
ommen ot Recommended Date: 4-//-9/
1 - a.T3 A facSafetyReviewer
<///g/4/ !!
sua 75ehef7 dannend2/Not decommended Date:
2nd Safety Risviewer (L omnende ot Recommended Date: 9-//-9 /-
C #
ff=C Pfoject Specialist
@ommeng/Not Recommended Date: 9- /l* M/
>n
_ Op g i$/s . ,Special Projects J omine Not Recommended Date: 9-/T 9/ '
v 1 Enc Manager APPROVALS:
/h ot Recommended Date:- 9d /
anager . E&RC
,! ML unsend ,^' t ";;e_.;;.d:d Ste: dd /'
I PNSC Ch an t Recommended Date: 9 M Al
/ R t General ~hgar coamaan u
Page 6 of 7 [';
O.E&RC.4261 Rev. 1
CACIMDir 2 (Cont'd) l REVISION 2 10Cm50.59 PROGRAM MANUAL page39 ATTACIDdENT A CP&L SAFETY REVIEW PACL\GE Page l of 3 SAFETY REVIEW COVER SHEET DOCUMENT NO. O D c rn REY.NO. /9 DESCRIPTTON OFTTILE: 6rrsIrr DMI c'A t rul A Tmy lh ANun L.
1
- 1. Assigned Responsibilities:
Safety Analysis Pnparen I&Oen Lead 1st Salery Reviewer: MIv/1hwe <
- .nd Safety Renewen V L. ii n hg r,u. !
- . Safety Analysis Preparer: Complete PART!. SAFETY ANALYSIS
- Safety Analysis Preparer liudC3IGNATURE gy q.// 9 /
Lesa ist Safety Renewen Complete Pm il. Item Classt5 canon.
- Lesa 1st Safety Renewer
- Pm i!I may be completec. If either quescon 1 or 2 is 'ves.' *
- hen Pm IV is not required.
!. Lesa ist SJety Renewen Dete:mine which DISCIPLDIES are requirca for renew of this item (including own) and marx the appropnate block (s) below.
DiScTPI INES Recuired* (Print Namei Slennnnt;Date iSten n (1 NuclearPlant Operanons (j Nuclear Engmeenng g Myh n4mi
[] Electncal
()Instrumentanon & Contml
[] Strucmral
() Metallurgy 90.emistry/Radioenemtsuv '
I a' Du ( _dadbn v-f/_9/
V ~'
(? Health Physte:
(j AdministranveControis
- 6. A QUALIFIED SAFETY REVIEWER will be assigned for each DISCIPLINE markrd in step 5 and his/her name pnnted in the space prtmded. Each person listed shall perform a S AFETY REVIEW and prtmde input into the Safety Review Peb y
- 7. ne Lead 1st Safety Reviewer will assure that a Pm III or Part IV is completed (see sep 4 above) and a Pan VI if required (sec 9.b of Part II). Esch penon listed in stes 5 shril sign and date next to his/her name in step 5, inhag completion of a SAFETY 3EVIEW.
S. 2nd Safety Reviewn Perform a SAFETY REVIEW in accordance with Seccon 8.0.
2nd Safety Reviewer b su N oW+ Date <,'/4/f /
DISCIPLINE: m" / 6%' c 4~ -
.Y.c Fa
, 9. PNSC review iW7 If "yer' mach Pm V and marr reason 0 0
! below:
O Potenttal UNREVIEWED SAFETY QUESTION O Quesnan 9 of PartIV answemi"Yes" g Other(rpectfy): Onnt' am N5c ,m/N _
e 0 AI.109 Rev. 001 Page 75 of 87 \
ATTAQDiDir 2 (Cont'd)
REVISION 2 10CFR50.59 PROGRAM MANUAL PageoO ATTACIMErrr A CP&L SAFETY REVIEW PACKAGE Page A of $
PARTI: SAFETY ANALYSIS (See insuuctions in Secuan 8.4.0
( Attaca additional theets as necessary)
DOC." TENT NO. oDc en REY.NO. /A DEsCawnOu oralAsaE:
llpriaf0<l Tafa. u .3. en u, e. wo s, je,
,, a fen f w; fk 11* lcd r e < ed tw>J usa 'b, sus , c % ae,/ ,,,,,g ves:Jed u HE 18 I p n.le e le r,a ni a mesfy nrbr e x w y s,e n;ia
,, A u,,,e & p eh n n At a) +r o. 9 w,lo -
ANAL.YS15: Liedd'sa Tau l'l, 7 ) - 3 0 on uit e 70 cetirpriiit t urar,ev< N ,,r $ at r n ernn nif H n.:u ,a ti n r < vmen (m. l "
,< .,,I n . n :< i e <. % :n s a la r ,- ,, , ,J </e , s er+ s f 6 l- _
,, n 1 <4 s Isi, < %< < fn e e r- em m ed m f ,< iew Ad Uthhm % % iIk a Ilse s fr o
+,, h, l'e b . ,ce n s ec ., u l ,, os %,, h re ' e 4 Jo set 1r rh e- p u b h c m a 1 { . m fe,n ni a ,,, l: . F r. .ci n .,i w. e ,. < a ffI.ad e fern s ,sIJ, 6
REFE?INCES:
P5 h h re dr < Toble<$5 bks _ _ %, hte o f whe n a encm '
hrh N*CS h ]Nle4 , ?lll'o Ils e 3/4 II ..i l/LJ .13 . 2 lo. l3 0 M.109 Rn. 001 Page 76 of 87 l l
ATTAC10tLYT : (Cone'd)
REVISION 2 10CFR50.59 PROGRAM MANUAL Page el ATTACHMENT A CP&L SAFETY REVEW PACKAGE Page1of 8 PARTII: ITEM CLASSIFICATION DOCUMEhTNO. Obc m REY NO, Q Xct F.a
- 1. Does mis item represene
- a. A changn to the facility as cesenbed in the S AFETY g p -
ANALYSIS REPORT 7
.. b. A change to the wvcsis.-es as desenbed in the SAFETY g y ANALYSIS REPORT 7
- . A test or exocriment not cesatoed in the SAFETY g g-ANALYSIS REPORT 7
- . Does mis item mycive a change to the individual plant Opennng g y 5 License or to its Technical Spect5 canons?
.. Does mis item rerpire a revision to the FSAR7 g (y
- a. Does tnis item involve a change to the Offsite Dose C*ninnna (y g Manual?
- 5. Does thu item constimte a change to the Process Control Pregam? O 9-
- 6. Does this item myolve a major change to a Radwaste Trunnant 0 O' System?
7 Does this item involve a change to the T9*l SpmMmnn" ~ O P Eqcpment List?
- 3. Does this item impact the NPDES Permit (all 3 sites) or constimte g V in heviewed environmenni ouesnon* (SHNPP Environmental Plan. Scenen 3.1) or a "sinn6dnt envuonmental impact" (BSEP)7
- 9. Does this item invoht a change to a previously accepted:
- a. Quality Assurance Program g ty
- b. Secunty Plan unch' ding Trumng, Qn= lim"nna_ :ml 0 0-Connngency Plans)?
- c. Emsy Plan? g O'
- d. tr L; i : Spem Fuel Storage Ins =lMna lieme? (If "yes." g (V refer to Secnon 8.12. "Quesuon 9," for special *%.
Complete Part VI : accordanc.: with Secuon 8.4.6)
SEE SECTION 8.4.2 FOR INS'IRUCTIONS FOR EACH "YES" ANSWER.
REFERENCES. List FSAR and Te<++l SpmMannn references used to answer questions 1 9 above. Idennfy spedic reimunce enm used fcc any "Yes" anrwer.
/9 O f M vt n p 1&n, ra n & u to ts sM;en is-Taek Veres _h h c , So e + 1/ n I, e
0 AI-109 Rev. 001 Page 77 of 87 j
ATTAC10 TENT :-(Cont d)i REVISION 2 10CFR50.59 PROGRAM MANUAL Pageo2 ATTACHMENT A CP&L SAFETY REVIEW PACKAGE Psge 4 of 8 PART III: UNREVIEWED SAFETY QUESTION DETERMINATION SCREEN coCnIENT NO. ODC M REV.NO. / 3.
.Yu &
- l. Is this chanac 6:lig addressed by another completed () y UNREVIEWED SAFETY QUESTION detenmnanon? (See Secnons 7.2.1. ? 2.5, ana 7.9.1.1) -
REFERENCE DOCGIENT: REV.
.Yu &
- . For procedures. :s tne change a non. intent change which onig(check () .
s11that apply): tSee Secnon 7? ' 1)
() Correcu typographical enors which do not alter the mesmng orintent -
of the rA: or.
1 0 Adds or revises steps for clarih- (provided they are consistent with the enginal purpose or applicahtlity of ther wedates; or.
() Changes the title of an orpmmional position: or.
- ) Changes names, addresses, or telepnene numbers of persons: or.
[] Changes the designanon of an item of equipment where the .
equipment is the same as tne original eqmpment or is an authonzed replacemerx: or. .
[] Changes a g- "a tool or ' . ~ - to an eqmvalent substmue: or.
() Changes th:fannat of a re_% without altenng the meaning.-
inens, orccsuenc cr 0 Deless s pastorallof a rsh the deleted pornons of which are _.
wholly covtsed by ayrwed plant rwhe?
. If the answer to either Quesnan 1 or Question 2 in PART III Is "Yes." then PART IV need not be completed.
i l
e O M-109 Rev. 001 Page!78 of $7
AITAC10ENT 2 (Cone'O REVISION 2 10CFR50.59 PROGRAM MANUAL - Palt 03 ATTACIBiENT A CP&L SAFETY REVEW PACKAGE Page $ of 3 PART IV: UNREVIEWED SAFETY QUESTION DETERMINATION DOCUMENTNO. o(M rn REV. NO. /cl.
Using the SAFETY ANALYSIS developed for the change, test or crperunent, as well as other requued references (LICENSINO B ASIS DOCUMENTA'ITON. Design Drawmgs, Design Basis Documents, codes, etc.), the preparer of the Unreviewed Safety Quesnon Deternunanon must direct:v answer esca of the following seven quesnons and mare a determmanon of whether an UNREVIEWED SAFEIY QUESTION extsts.
A WRITTEN BASIS IS REQUIRED FOR EACH ANSWER
.-- y May tne crocosen acnvity increese the proeability of occunence of () y
- n ur +nt evaluarea creviousty in the S AFEIY ANALYSIS REPORT 7
%1kkd
- 2. May the proposed acuvity increase the consecuences of an accident [] y evaluated ousi in S ANALYSIS REPORT?
- 3. May the proposed scavity increase the probability of occurrence of [] V a malfuncnon of ecmoment important to safety evaluated previously mth< DFETY ANALYSIS RJIPORT?
O* Afhoc$+pf
.t. May the proposed activity incesse the consequence of a O P malfuncnon of eqmpment 6ww to safety ev= hn* previously inthe SAFETY ANALYSI# AEPORT7
% hf % hed
- 5. May the evM activity create the p@iBry of an ~htof a diffaent type than any evaluated previously in tt9 S AFETY 0 F ANALYSIS REPORT?
f.a e 4trar[ec/ \ 0 AI-109 Rev. 001, p,g, 79 og 37 i
'TTAODEhr 2 (Cont' d)
REVISION 2 10CFR50.59 PROGRAM MANUAL PagetA ATTACHMEZR A CP&L SAFEIT REVIEW PACKAGE- Page 12 _ of 8 PARTIV: (Continued) Y.c 32
- 6. May the proposed acnvity cre:ue the possibility of a m*1fnnt nnn of 0 y eqmpment important to safety of a different type than any evaluated previously in the SAFE"'Y ANALYSIS REPORT 7
<ee A rf a c L # </
?. Does the proposed acuvity tiduce the margm of safety as defined in 0 R-
.-- de bans of any Techmemijmemnon?
S o c- 11theled L 3ased on the answers to ouesnons ! 7. does this item result in an [] g-UNREVIEWED SAFETY QUESUON7 If the answer to any of the ' quesnans 1-7 is "Yes" den me item is ceme6a to consutute an UNREVIEWED SAFETY QUESTION.
- 9. Is PNSC review reguud for any of the followmg tmnnt? O 7 If. in answermg quescon 1 or 3 "No," It was detemuned that the probability inc: case una small relative to the uncercunties: or, in answermg quesnan 2 or 4 "No," it was determinea dat the doses increased, but the dose was sdllless than the NRC ACCEPTANCE LIMIT:
or in answermg quesson 7 "No " a patsmeter would be closer to the NRC ACCEPTANCE LIMIT, but the end resuit was sid1 wirG the NRC ACCEPTANCE LIMIT; then PNSC l review is imuus
REFERENCES:
opp r,TV Dow cd t cu L A Tiw mpeu A L.- p: s A tt Irdot Tnblo & Mtwf f L'e i t! n U, S*r f:en I C O c fs n I 3-To r i m e I cu n is er % s EaM , he M ?la .!:. o yta.in.3 , 1/4,C.5 6 . '4 . b,/? ned BdWS This Unreviewaf Safety Quesnon Detamnannn is for the following DISCIPLINE (s): ( AMi+"al Part IV famts may be inh as ayeursm.) l t 0 NucicarPlamOpes OSur i l 0 Nuclear Engmeenng 0 Metallurgy 0 M4 *=1 77L ""riPadi~ himy 0 E-l 0 Heath Phyncs O h" =+ & Canoi 0 Ad-nnmauve Connel: l , 0 AI.109 Rev. 001 Page 80 of 87
Page 8 of 8 UNREVIEWED SAFETY QUESTION DETERMINATION OFF-SITE DOSE CALCULATION MANUAL REVISION 12
- 1. THIS REVISION TO THE ODCM DOES NOT EFFECT ANY INITIATING SYSTEMS, STRUCTURES, OR COMPONENTS. THE CHANGES MADE WERE TO UPDATE TABLE 3.2-2 DISTANCE TO CONTROLLifuk lDCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi) AS INDICATED BY THE 1990 LAND USE CENSUS. IMPLEMENTATION OF THIS REVISION WILL NOT INCREASE THE PROBABILITY OF ANY ACCIDENT PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT.
- 2. THESE CHANGES TO THE ODCM DO NOT ALTER OR CHANGE THE INITIAL CONDITIONS OF ANY ACCIDENT OR EFFECT MITIGATING SYSTEMS, STRUCTURES, OR COMPONENTS. THEREFORE, THE CHANGES WILL NOT INCREASE THE CONSEQUENCES OF ANY ACCIDENT PREVIOUSLY EVALUATED
~
IN THE SAFETY ANALYSIS REPORT.
- 3. UPDATING THE ODCM WITH THE MOST RECENT LAND USE CENSUS RESULTS DOES NOT EFFECT THE PERFORMANCE OR OPERATION OF ANY IMPORTANT TO SAFETY EQUIPMENT AND WILL NOT INCREASE THE PROBABILITY OF OCCURRENCE OF MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT. ,
- 4. IMPORTANT TO SAFETY EQUIPMENT IS NOT Et'FECTED BY THIS PROCEDURE AND THEREFORE THE CONSEQUENCE OF A MALFUNCTION OF IMPORTANT TO SAFETY EQUIPMENT WILL NOT BE INCREASED.
- 5. IMPLEMENTATION OF THIS CHANGE WILL NOT CREATE THE POSSIBILITY OF AN ACCIDENT OF A DIFFERENT TYPE THAN PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT. THE CHANGE TO TABLE 3.2-2 CHANGES THE LOCATION OF THE NEAREST RESIDENT IN ONE SECTOR AND THE NEAREST GARDEN IN TWO SECTORS.
- 6. THE CHANGES DO NOT EFFECT ANY EQUIPMENT IMPORTANT TO SAFETY AND THEREFORE WILL NOT CREATE THE POSSIBILITY OF A MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY OF A DIFFERENT TYPE THAN PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT.
- 7. ALTHOUGH THE ODCM IS REFERENCED IN SEVERAL SECTIONS OF THE TECHNICAL SPECIFICATIONS, THESE CHANGES WILL NOT REDUCE THE MARGIN OF SAFETY AS DEFINED IN THE TECHNICAL SPECIFICATIONS.
i 1 4 l l e 1
.- .. - . - . . .- _.. ~. .. .-. . . ~ . - - .-_ ...- .-- - -
I t BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM) REVISION 12 DOCKET NOS. 50-324 50-325 CAROLINA POWER & LIGHT COMPANY e i V
I LIS* OF EFFECTIS.'E PACES ODCM Pare (s) Revision i 12 11 11 111 9 iv-viii 6 ix 11 1-1 8 2 2-2 0 2 2-6 1 2-7 0 2 2-10 1 2 2-12 8 2 2-14 1
.- 2 2-16 8 3 3-12 4 3-13 1 3-14 4 '
3-15 5 3 3-18 4 3-19 6 3-20 1 3-21 8 3-22 9 3-23 1 3-24 4 3-25 1 3-26 4 3-27 6 3-28 8 3-29 i 3-30 12 3-31 '4 3-32 1 3-33 8 3 3-36 1 3 3-38 4 3-39 6 l 3-40 7 3-41 l' 3-42 9 3 3-45 1 3 3-48 4 3-49 1 3 3-68 8 4 4-3 11 4-4 7 4 4-6 11 5-1 0 6 6-2 0 6-3 4 ODCM (BSEP) 1 -Rev. 12 e l l
TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED TROM TFE BRUNSWICK PLANT CENTER (Mi) Site Milk Milk Meat Nearest Nearest Sector Boundary Cow Goat Animal Resident Carden
- NNE 0.7 - - - 1.2 1.2 NE 0.7 4.75* - - - -
... ENE 0.7 - - - - -
E 0.7 - - - - - ESE 0.7 - - - 1.6 - SE 0.7 - - - 0.9 - SSE 0.7 - - - 1.0 - l S 0.8 - - - 1.5 1.6 SSW 0.8 - - - 1.2 1.5 SW 0.7 - - - 1.0 1.0 WSW 0.7 - - - 1.1 1.1 W 0.7 - - - 0.8 0.8 l WNW 0.6 - - - 0.9 0.9 SW 0.6 - - - 0.9 0.9 l NNW 0.6 - - - 0.8 4.8 N 0.7 - - - 0.9 -
- A " hypothetical" cow milk pathway is located at this point in.accordance i
with 5.3.1 of NUREG 0133. 1 ODCM (BSEP) 3-30 Rev. 12 er
l - l ATTACHMENT A REQUEST FOR OFF SITE DOSE CALCULATION MANUAL CHANCE Rev. /$ Originator: [uS 4 4.- N?oth ?/v Date: <r// #/4 / Pages and Sections Revised: _ d u c J A rt f /. (( - fMv 6"/ i-9 i Reason ior Change: //ndat 24/rt i ev d mruEbr4s-r AtSS}rtuw*JaAmi_ g m u u b<ss Det ,n!Lur'A/d 4/-tXl0 ~ i A bu 82M2, o Date: ///M/9 / > Safety Analysis Completo: _ W i REVIEVS: A472> mendhot Recomended Date: ///1//9/ . wra ^ 1st Safety Reviewer becomen ot Recomended Date: / f 4f-Tl II eM ' , M ad Safety Reviewer l d us v/E&C Project Specialist
~
6comendefNoe asco ended Date: it-as-ai '
#, A (Recomende&Not Recomended Date: '// J/,-9/
Oper ons - pecial Projects ot Recomended Date: /4 9/ r . V ~ E&C Kanager l APPROVALS: [1(anager - E6RC M mend ot Recomended Date: /2!?(/
' L / /
, Oth men /Ne t L w-..& d n = c e : /NS/?/'I PNSCCha.p n /N Recomended Date: 111 I /
gt General hadager Page 6 of 7 l
**~
0-EARC 4261 Rev. 1
- . _ _ . . . - - . _ . . - - -. - .. . - - . . . - - - --.. - . ~. - . .- -.- - . - .-_. ..-. - . 4
. l l
ATTAQ0G2f7 2 (Cont'd) 10CFR30.59 PROGRAM MANUAL page 39 REVISION 2 ATTACHMENTA CP&LSAFEIY REVEW PACKAGE Page / oi [ j I SAFETT REVEW COVER SHEET Bod /(A REY. NO. 13 l DOCUMENTNO. DESCRIFIION OF'! TILE:
/)n,7e /.he ddad1E //aud.-
l
- 1. Assigned #PW13h Sdeny ' T..y ..
1<hu M24adn>2 h- sh *,V landist Revuwer: 2ndsdeny Rayswer: , T. w . A4 r i 2. ics PARTL SAFETY ANALYSIS Safety Analysis 7.w . Comp $%h Sdety Analyns F. y.iw p/fr/ff shNAWM DATE
!.and 1st Safety Reviewen Conmism Part II. Item m = demaan
- 1. .
I.ead 1st Safety Reviewer: P:triIII may be compican. If either quesnan 1 or 2 Is 'ves.'
- then PartIV is notim e 3.
Lead 1st Safety Reviewen Deartmne which DISCIPLINES are r%=.4 forreyww of this iam d~+dag own) and marie the appropnam block (s) below, ofictPLINES Remmni- (Print Namer WI ONaciestPtanscv 4-w 0 Nucles' N= - at 0 Mechancal 0Esencai 0 lassmaa"="na & Connel
- 0sencised O Messilurgy M ChannsavrPubv a-imy I, % rp 4,ad- 4~- p a////,i 0 Health Physms 0 AdamusiranveConmus
- 6. - A QUALIFIED SAFETY REVEWER will be assigned for each DISCIPLINE markedin sep 3 and hisAer nuns pnmed in che specs pnmded. Each person lised shall perionn a L
SAFETY REYEW and pumdainput ano ths Safety Review Package.
- 7. TheLead1stSafety RayswerwinassesthataPartIEcrPartIVis-- .' -1(seesssp 4 above) and a Part VIif W_ (ses 9.b of Part At Each person linedin sa 5 shan sign and das next to hi:Aer name in assp 5, indicanng z-- ;'r ==- of a SAFETY : EVIEW.
- 8. 2nd Safety Rom-. . F - SAFETY REVIEW in acconiance with Secnon LQ.'
2ndSafety Reviewer - 4- Dam li m I ! DISCIPLINE: hA / hih PNSCmvmw W'tIf"yes" anach Part V a madereason 9. 0 PoenedUNREVIEWED SAFEIYQtansuGN 0'Quesnan g oder(speedy): 9 of PartIV ooem answered"Yes" d g ,ng ~ me uh a 0 AT,-109 Rev. 001 -
~ _ _ _ _
75 of 87~
.\
. . _ . . . - - . - - - . . _ . _ . . ~ - - . - - - . - - - . ~ - - . ~ . . - . . - - . -
ATIACHNENT 2 (Cont'd) 10CF"J0.59 PROGRAM MANUAL Pap o0 REVISION 2 L ATTAGMENT A 5' C?&LSAFETY REVIEW PACKAGE Pap . .o Oi I PARTh SAFETY ANALYSIS (Seeinssacnonsim Secana A4.1) (Anaca addhional absets as necessary) 60M REY.NO. /3 - DOCUMENTNO. DESCRIPT!0N OFCHANGE:
/le/>fe *//M
- u M o mx A / M - 1 / n l. Ghd4lb s
-gs 's /r1 u a & N mi he r i w_
ANALYSl5: N1aX AAA 4h0O n ^ * && & ]A<rd inhnt A M L A L n d +_ab '1%, $ - J12AL1
/Js /d_vka , 'k M w) An's4. )b >;, &
i n. An-s i a M 0 m ;A L Au 'Jhc emu A' ' Lad AL/som< X Alt d w i .> 4 AM Ardd> . G/a Hu
- Kner A1nMJ & n.,
/n bMwA- L ed llrtJ & .1&>l(C is l>&h // b W
& ::. A n/m1 ' A6 -
a.!smLJ AL sts.:, m%w /n JLo Sn. *f y fA L Mv /EL ris n a ., , -A v
^x- N Lk t' M s w .k_
'()bt"Al Y44'A.eY M $&N ubl. n>> d sA 1 - ahW + Sr- E 't.41/c sA s stb 1 *u ^ Y $ Pdix21 AAna - As.s : k J
~
9)h a a n.ovo. l l' REFERENGI: , FM Gho40 i e-A *t,.yno,aev. 001I _ . - ~ . . - . -. Page 76 o{87:- { ,
. ~ . _ . . _ _ . - - . _ - . - . . . . . - . . - - . - . _ - . - - - . - . _ - - . - - - .. - - . _ . ._..
I ATTACHKENT 2 (Cont'd) r
- Pap til 10CFR50.59 PROGRAM MANUAL REVISION 2 ATTAGMENTA CPAd., SAFETY REVIEWPACKAGE Pap 3 of 1 PARTII: ITEM cr mrs1 CATION REY.NO. /3 DoctSGDTTNO.
06ea _ 1 81 .fA
- 1. Does thisimm =Pmann the facility as hW in ths SAFETY Q ,, g
- a. A 0 g' b.
A chsap m ths,.as as @enW in the SAFETY
-ANALYS5 REPORT 7 0 Gr
- c. A innor-not oescribedin the SAFETY ANALYSE REPORT 7
' Does inis iam involve a chang to the indip.J ! plant Operanng 0 8' L.lecassortoint TechacalSp- " i- 7 j- Doss this inun napms a revision to the FSAR7 0 W 3.
Does diis iam involve a chang to the OEshs Dose n'~ 8 *= 5' O 4 Manasif g' Does this iam consinns a chang to the Pmcas Comed Ptogram? Q 5. Does this iam involve a major chany to a Radwass Ticaansac Q g 6. Sysuma? Dass this inns involve a chany to the Technical Si+ :~ ----- 0 B' 7. EquipmentList! g l Does skin ions impact the NPDES Parant (all 3 sims) or consanna Q 3. sa "ungsviewed enstramnensi quesnon" (SHNPP Envuonmenssi Plan. Secann 3.1) or a "si - ? ==
. -- -! W (BSEP)?
9. Does ibis iam involve a changs to a previnasty acosynt O B'
' QualirTA8m'='sP80sma .
g-l sesexyPlan(innimiins Tmining,q ", t and. O b.. , ConnapacyPlass)? g'.
-O l c. EmmpanyPlan! _
g' L te Spent Fusi Storage Insmilmion liennes? Of "yes," Q d. l sder a Secuan L41 *Quescon 9." for spaced N. l G-;i-m Part VI: =cordsaca with Secnon L4.6) SEE SECHON t.4.2 POR INSTRUCDONS FOR EACE"YES" AN REFERENCES. List FSAR and,Tecimical SW"% nad to answer quasions 1
"# mferencs sections used for any Yes" answer.
above. IdE5aff T-i 1 DM 4/-edd . 00 tai LiuaA*r E y, 7pg g7
- A AI.}09 Rav. 001 _ _ - - _ _ - - _ _
ATTAQOENT 2 (Cont'd) 10CFR50.59 PROGRAM MANUAL Page el REVISION 2 ATTACHMENT A I of f CP&1. SAFETY REVEW PACKAGE Page PART m: UNREVu:.wt.u SAFETY QUESTI' OETERMINATION SCREEN BOcx REY. NO. /4 DOCQiENTNO. , YJa 32 1. Is this change 6dlx addressai by mher completai [g UNREVIEWED SAFETY QUESTION dempmnmann? (See Secnons 7.2.1. 7 " 9. and 7.9.1.1) REFEENCE DOCDENT:
' //ert 4/grl 9/-oslo REV. O YJ2 S.2 i For g Ass. is the change a non. intent chsnge which only (chect [g allthatapply): (See Secnon 7.7 ' 1)
Q Com: cts typogrrphirsi errors which do am alter the memamg orintent ofthe r- cr. 0 . win m Icwses seps for clar*mnan (provided they a!c enancem with the enginalpurpose or =paHe W7 ofthe p 6 4 or. O N5c thetideof an m- --- i--- I p-: e= or.
;) Changes names, addresses or =';+ w numbersy of ms or, if Changes the designanon of an item of eqmpm-~ where the oris an punharmd q5=. - =- is
= the or. same as the original %.y.6 .
q , g Sang a ip-- M ool t y *..... u...... to an eqtr!Yalent s"him** ar. O Changes the formatof a r e. without miterms the meaning, iment,orconte:::: or 0 Deletes
- Part or allof a et- ": + the deleted ph of which are who!!y emmi.dby .ermJpiam r e_- ' e7 If the answerto eitherQuesnan 1 or Quescon 2 la PART M is "Yes " then PART IV oced om
_. ..f rd e-
-g p g 73 og 37
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W e BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM) REVISION 13 DOCKET NOS, 50-324 50-325 CAROLINA POWER & LICHT COMPANT l er
l LIST OF EFFECTIVE PAGES ODCM Page(s) Revision 13 1-11 9 111 6 iv-viii 11 ix 8 1-1 0 2 2-2 1 2 2-6 0 2-7 1 2 2-10 8 2 2-12 1 2 2-14 8 2 2-16 4 3 3-12 1 3-13 4 3-14 5 3-15 4 3 3-18 6 3-19 1 3-20 8 3-21 9 3-22 1 3-23 4 3-24 1 3-25 4 3-26 6 3-27 8 3-28 ~ 1 3-29 12 3-30 4-3-31 1 3-32 8 3-33 1 3 3-36 4 3 3-38 6 3-39 7 3-40 1 3-41 9 3-42 3 3-45 1 4 3 3-48 1 3-49 i 8 3 3-68 l 4 4-3 11 4-4 7 4 4-6 11 5-1 0 6 6-2 0 6-3 4 i Rev. 13 ODCM (BSEP) 1 L
1
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LIST OF EFFECTIVE PACES
-l (Continued) \
ODCM l Page(s) Revision-0 A-1 4 A-2 0
-A A-4 4-
.A A 0 ,
-A A-9 4 A A-13 0 A A-15 4
A A-19 0 A A-21' 4
-A-22:
0 A A-28 B-1-- B-33 0 8 C 0~
-C C-8 8
C-9 C C-13 0 8 C-14 C-15 8 C-16 C C-18 0 D D-2 1 E-1 13 11 E-2 E 10 F F-3 0 1 G-1 H H-5 9 Rey, 13 .i 11 ODCM~(BSEP)
. e - _.
-e APPENDIX E RADIDACTIVE LIQUID AND CASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS
- 1. Liquid Effluent Monitoring Instruments Liquid Radvaste Radioactivity Monitor 2-Dl?-RM-K604-A.
Liquid Radvaste Effluent Flow Measurement 2-G16-FIT-N057 B. l_ Device C. Main Service Water Effluent Radioactivity 1(2)-D12-RM-K605-Monitor D. Stabilisai: ton Pond Ef fluent Composite 2-DST-XE-5027 Sampler E. Stabilizatf.on Pond Effluent Flow 2-DST-FIT-5026 Measurement Device Condensate Storage Tank Level Indicating 1(2)-CO-LIT-1160 ( F. Device l
\
ODCM (BSEP) . E-i Rev. 13 er j
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