ML20215M385
| ML20215M385 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 12/31/1986 |
| From: | Canade M, Knapp W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20215M369 | List: |
| References | |
| NUDOCS 8705130210 | |
| Download: ML20215M385 (17) | |
Text
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION Unit Nos. 2 and 3 Docket'Nos. 50-277-& 50-278 SEMI-ANNUAL EFFLUENT RELEASES REPORT NO. 22 REVISION NO. 1 JULY 1, 1986 THROUGH DECEMBER 31, 1986 Submitted to The United States Nuclear Regulatory Commission l
Pursuant to Facility Operating Licenses DPR-44 & DPR-56 kg DC 5
7 R
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION
' Unit Nos. 2 and 3 Docket Nos. 50-277 & 50-278 SEMI-ANNUAL EFFLUENT RELEASES REPORT NO. 22 REVISION NO. 1 JULY 1, 1986 THROUGH DECEMBER 31, 1986 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 & DPR-56 Preparation Directed By:
R. S. Fleischmann, II, Superintendent Peach Bottom Atomic Power Station
l i
l TABLE OF CONTENTS Page No.
I.
Introduction 11 II.
Tables lA - Gaseous Effluents - Summation 1
of All Releases 1B - Gaseous Effluents For Release 2
Point - Main Stack 1C - Gaseous Effluents For Release 4
Point - U/2 & U/3 Roof Vents 2A - Liquid Effluents - Summation of 6
All Releases 2B - Liquid Effluents 7
3C - Classes of Solid Radioactive 9
Waste Shipments III.
Attachments A - Supplemental Information 11 B - Summary of Unplanned Releases 13 Technical Concurrences: (For accuracy of information) 04Y dAV Dird'ctor - Radiation Protection Date
'*y "Jg..
}
Director'- Radwaste
- /
Date
~
-i-
I.
INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2.h(2) applicable during the reporting period, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station Units 2 and 3 for the period July 1 through December 31, 1986.
The notations E and E-are used to denote positive and negative exponents to the base 10 respectively.
The release of radioactive materials during the reporting period was within the Technical Specification limits.
There were no changes to the Off-Site Dose Calculation Manual (ODCM) during the reporting period.
An unplanned release of liquid radioactive material from the Pressure Service Water (HPSW) occurred on September 22, 1986.
This is discussed in the attachment section of the report.
This revised report is being submitted to reflect corrections to several errors which were previously reported.
The following changes have been made:
o Page 1 Total Release 8.98 E3 (3rd Quarter) o Page 2 Xenon-138 4.02 E2 (3rd Quarter)
Total 8.71 E3 (3rd Quarter)
Iodine-133 3.28 E-3 (4th Quarter)
Iodine-135 1.22 E-2 (3rd Quarter)
Total 3.11 E-2 (3rd Quarter) 1.20 E-2 (4th Quarter) o Page 3 Yttrium-91M 3.13 E-2 (3rd Quarter)
Totals 1.43 E-1 (3rd Quarter) o Page 4 Xenon-133M 8.30 E0 (3rd Quarter)
Total 2.66 E2 (3rd Quarter)
Lanthanum-140 3.87 E-4 (3rd Quarter) o Page 5 Totals 3.52 E-2 (3rd Quarter)
In addition, this revised report includes an unplanned release of liquid radioactive material from the Raw Water Sump, which was inadvertently omitted from the previous report.
Attachment B has been revised to reflect this addition.
A bar has been placed in the margin adjacent to the corrected information.
-ii-
i TABLE 1A EFFLUEHT AND WASTE DISPOSAL SEMIAHHUAL REPORT (19868) f GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 2C3 3
4 Error, %
- 4. Fission C activation gases
- 1. Total release Ci 8.98 E3 8.38 E3 54.0 E0
- 2. Average release rate for period uCl/sec 1.14 E3 1.07 E3
- 3. Ocame Air Dose M111trad
- 9. 65 E-2 7. 7 8 E-2 Percent of Tech. Spec.
9.65 E-l
- 7. 78 E-1
- 4. Beto Air Dose Millirad
- 6. 0 6 E-2 5.69 E-2 Percent of Tech. Spec.
- 3. 0 3 E-1 2.85 E-1 l.
- 1. Total lodine-131 Ci 1.52 E-2
- 1. 3 9 E-2 61.0 E0
- 2. Average release rate f or period uCi/Sec
- 1. 94 E-3
- 1. 7 7 E-3
- 3. Critical Organ Dose Millirem 6.29 E-2
- 5. 72 E-2 Percent of Tech. Spec.
4.19 E-l 3.81 E-1
- . Particulates
- 1. Pcrticulates with half-lives greater than 8 days (includes Alpha and Strontium 89-90)
Cl
- 3. 02 E-3 4.47 E-3 61.0 E0
- 2. Average release rate for period uCl/Sec 3.84 E-4 5.6 9 E-4
- 3. Gross Alpha Radioactivity Ci
- 3. 6 9 E-5 6.17 E-5
- l. Tritium
- 1. Total release Ci 9.88 E0 1.06 El 94.0 E0
- 2. Average release rate for period uCl/Sec 1.26 E0 1.35 E0 TABLE IB EFFLUENT AHD WASTE DISPOSAL SEMIAHHUAL REPORT (1986B)
GASEOUS EFFLUENTS FOR RELEASE POINT: MAIN STACK CONTINUOUS MODE BATCH MODE aclidas Released Unit Quarter Quarter Quarter Quarter 2E3 5
4 5
4 Fission gases Krypton-85M Cl 3.22 El 8.69 El 0.00 EO 0.00 E0 Krypton-87 Ci 8.29 El 6.85 El 0.00 EO 0.00 EO Krypton-88 Ci 7.82 El 1.05 E2 0.00 EO 0.00 E0 Xsnon-135 Ci 6.79 E3 6.05 E3 0.00 EO 0.00 EO Xsnon-155M Ci 1.78 E2 1.62 E2 0.00 EO 0.00 EO Xenon-135 Ci 8.65 E2 1.16 E3 0.00 E0 0.00 EO Xenon-155M Ci 2.58 E2 1.71 E2 0.00 EO 0.00 E0 Xenon-158 Cl 4.02 E2 2.55 E2 0.00 EO 0.00 EO Unidsntified Cl 2.64 El 0.00 EQ 0.00 EO 0.00 E0 Total for period Ci 8.71 E3 8.04 E3 0.00 EO 0.00 E0 Iodines Iodino-151 Ci 5.2 7 E-5 4.91 E-3 0.00 EO 0.00 EO Iodino-135 Cl 1.56 E-2 5.28 E-3 0.00 ED 0.00 E0 lodino-155 Cl 1.22 E-2 5.81 E-3 0.00 EO 0.00 EO Total for period Cl 3.11 E-2
- 1.2 0 E-2 0.00 E0 0.00 E0
, Particulates Strontium-89 Cl 1.04 E-3 1.26 E-3 0.00 EO 0.00 E0 Strontium-90 C1 2.87 E-6
- 5. 7 0 E-6 0.00 E0 0.00 E0 Strontium-91 Cl
- 2. 7 4 E-5 5.24 E-3 0.00 E0 0.00 E0 Cesium-154 Cl
- 2. 7 9 E-5 4.56 E-6 0.00 EO 0.00 E0 Cesium-137 Ci
- 5. 6 6 E-5 1.18 E-5 0.00 EO 0.00 E0 Cesium-138 Ci 7.54 E-2 1.04 E-1 0.00 EO 0.00 E0 B ar i u m-159 Cl 3.22 E-2 5.48 E-2 0.00 EO 0.00 EO Barium-140 Cl 1.08 E-3 1.86 E-3 0.00 EO 0.00 E0 Lanthanum-140 Ci 4.80 E-4 6.18 E-4 0.00 EQ 0.00 E0 Cobalt-57 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 Cobalt-58 Cl 1.00 E-6 0.00 EO 0.00 E0 0.00 E0 -
TABLE IB (Continued) eMNTIHUOUS MODE BATCH MODE ualid.; Released Unit Quarter Quarter Quarter Quarter 2C3 3
4 5
4 Cobalt-60 Ci 6. 2 7 E-6
- 2. 6 0 E-6 0.00 EO 0.00 EO Zinc-65 C1 2.17 E-5 0.00 E0 0.00 EO 0.00 EO Y t t r i u m-91M Cl 3.15 E-2
- 4. 05 E-2 0.00 EO 0.00 E0 I:. din -153 Ci 2.87 E-4 1.79 E-5 0.00 EO 0.00 E0 Copp r-64 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 EO Rubidium-88 Ci 0.00 E0 0.00 EO 0.00 EO 0.00 E0 Manganese-54 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 E0 Strontiun-92 Ci 0.00 EO 0.00 EO 0.00 EQ 0.00 E0 Cadalun-109 Cl 1.15 E-S 0.00 EO 0.00 EQ 0.00 E0 icchno t iun-9 911 Ci 2.10 E-6 4.S0 E-6 0.00 EO 0.00 E0 Tellurium-132 Ci 1.60 E-6 1.13 E-5 0.00 EO 0.00 E0 llo lybdenum-9 9 Cl 0.00 E0 1.50 E-6 0.00 EO 0.00 E0 IndinL-132 Cl 0.00 E0
- 1. 6 7 E-4 0.00 EO 0.00 E0 letals Ci 1.45 E-1 1.06 E-1 0.00 EO 0.00 EO - _ - _ - _ - _ _ - _ - _ _ _ _
TABLE 1C EFFLUENT AHD WASTE DISPOSAL SEMIAHHUAL REPORT (1986B)
GASEOUS EFFLUENTS FOR RELEASE POINT: U/2 C U/5 Roof Vents CONTIHUOUS MODE BATCH MODE luclidas Released Unit Quarter Quarter Quarter Quarter 2C5 5
4 5
4
. Fission gases Krypton-85M Ci 4.27 El 3.71 El 0.00 EO 0.00 E0 Krypton-87 Ci 4.80 E0 2.86 EO 0.00 EO 0.00 EO Krypton-88 Cl 1.54 E-1 7.68 EO 0.00 E0 0.00 EO 9
Xenon-135 Ci 6.12 El 6.18 El 0.00 EO 0.00 E0 Xenon-155M Ci 5.50 EO 0.00 EO 0.00 EO 0.00 EO Xenon-135 Ci 1.08 E2 2.19 E2 0.00 EO 0.00 EO Xcnon-155M Ci 4.28 E0 1.80 El 0.00 EO 0.00 E0 Xenon-138 Ci 0.00 E0 0.00 EO 0.00 EO 0.00 EO Unidantified Ci 5.70 El 0.00 EO 0.00 EO 0.00 E0 Total for period Ci 2.66 E2 5.46 E2 0.00 E0 0.00 EO Iodines Iodine-151 Ci
- 9. 94 E-3
- 9. 0 5 E-3 0.00 EO 0.00 E0 Iodine-135 Ci 5.55 E-2 1.45 E-2 0.00 EO 0.00 EO Iodine-135 Ci 2.50 E-2 0.00 E0 0.00 EO 0.00 E0 Total for period Ci 6.84 E-2
- 2. 5 5 E-2 0.00 E0 0.00 EO Particulates Strontium-89 Cl 2.19 E-4
- 1. 02 E-3 0.00 EO 0.00 E0 Strontium-90 Cl 1.54 E-5 6.99 E-5 0.00 EO 0.00 E0 Strontium-91 Cl
- 1. 75 E-5 9.15 E-4 0.00 EO 0.00 E0 Cesium-154 Ci 0.00 E0
- 2. 9 6 E-5 0.00 E0 0.00 E0 Costum-137 Ci 0.00 E0 2.51 E-5 0.00 EO 0.00 E0 Cesium-158 Cl 8.86 E-3 1.55 E-2 0.00 EO 0.00 E0 Barium-139 Cl 1.21 E-2 7.20 E-5 0.00 E0 0.00 E0 B ar i u m-14 0 Cl 1.02 E-3 1.24 E-5 0.00 EO 0.00 E0 Lenthanum-140 Ci 3.87 E-4 2.55 E-4 0.00 EO 0.00 E0 Cobalt-57 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 E0 Cobalt-58 Ci
TABLE 1C (Continued)
CONTIHUOUS MODE BATCH MODE luclidas Released Unit Quarter Quarter Quarter Quarter 2E3 3
4 3
4 Cobalt-60 Cl
- 5. 0 5 E-5 0.00 EO 0.00 E0 0.00 EO Zinc-65 Ci 8.16 E-5 0.00 EO 0.00 EO 0.00 EO Y t t r ium-91M Ci 9.05 E-3
- 5. 9 7 E-5 0.00 E0 0.00 E0 Iodine-155 Cl 1.27 E-3 2.18 E-3 0.00 E0 0.00 E0 Copper-64 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 EO Rubidium-88 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 Manganese-54 Ci 0.00 EO 0.00 E0 0.00 EO 0.00 E0 Strontium-92 Ci 1.45 E-4
- 2. 52 E-4 0.00 E0 0.00 E0 Sodium-24 Cl 2.14 E-4 0.00 EO 0.00 EO 0.00 EO Molybdenum-99 Ci 4.05 E-6 4.50 E-6 0.00 EO 0.00 E0 T echnet ium-99M Ci 5.70 E-6 0.00 E0 0.00 EO 0.00 E0 Iodine-152 Cl 0.00 EO 7.28 E-5 0.00 EO 0.00 E0 Manganese-54 Cl 0.00 E0 2.17 E-5 0.00 EO 0.00 E0 Manganese-56 Ci 0.00 EO 5.89 E-5 0.00 EO 0.00 E0
~~1odine-154 Cl 0.00 E0 1.91 E-4 0.00 E0 0.00 E0 j
Iodine-135 Ci 0.00 E0 1.17 E-3 0.00 EO 0.00 ED Totals Cl 3.52 E-2 3.40 E-2 0.00 EO 0.00 E0 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 l
{
TABLE 2A EFFLUEHT AHD WASTE DISPOSAL SEMIAHHUAL REPORT (19868)
LIQUID EFFLUEHTS - SUMMATION OF ALL RELEASES Unit quarter Quarter Est. Total 2C3 3
4 Error, %
Fission C activation gases l.
Total release (not including Ci
!. Average diluted concentration uCi/ml 8.64 E-10 8.51 E-10 during period Millirem 9.67 E-3
- 1. 8 6 E-2
- b. Body Dose Poecent of Technical Specification X
3.22 E-1 6. 2 0 E-1
- i. Pune Dose Millirem
- 8. 7 9 E-5 1.56 E-2 Porcent of Technical Specification X
- 8. 7 9 E-2 1.56 E-1
, Tritium
- l. Total release Ci 8.15 E0 1.71 El 39.0 E0
- t. Average diluted concentration uC1/ml 1,48 E-7 1.65 E-7 during period Dissolved and entrained gases
- 1. Total release Ci 1.12 E-1 2.11 E-1 42.0 E0
- 2. Avorego diluted concentration during period uCl/ml 2.03 E-9
- 2. 0 3 E-9
. Gross alpha radioactivity 1.
Total release Cl
- 3. 9 7 E-5 1.29 E-4 59.0 E0
- 2. Average diluted concentration during period uCl/ml 7.19 E-13 1.24 E-12
. Volume of waste released (prior to dilution) liters 4.06 E6 7.16 E6 32.0 EO Volume of dilution water used during period liters 5.52 E10 1.04 E11 50.0 EO
TABLE 2B EFFLUENT AHD WASTE DISPOSAL SEMIAHHUAL REPORT (1986B)
LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE clidas Released Unit Quarter Quarter Quarter Quarter 2C3 5
4 5
4 rantium-89 Ci 0.00 EO 0.00 E0 1.56 E-4 2.54 E-4 rontium-90 Ci 0.00 EO 0.00 EO 7.20 E-5 9.27 E-5 phs Ci 0.00 EO 0.00 EO 5.97 E-5 1.29 E-4 itium Ci 0.00 EO 0.00 EO 8.15 E0 1.71 El osphorus-52 Ci 0.00 EO 0.00 EO 8.16 E-4 4.82 E-4 on-55 Cl 0.00 EO 0.00 E0 3.84 E-4 5.44 E-5 non-151M Ci 0.00 EO 0.00 EQ 0.00 EO 0.00 E0 non-155M Ci 0.00 EO 0.00 E0 1.06 E-5 2.19 E-5 non-135 Cl 0.00 EO 0.00 EO 6.54 E-2 7.8 0 E-2 non-135 Ci 0.00 EO 0.00 EO 4.55 E-2 l.12 E-1 non-138 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 EO ypton-OSM Cl 0.00 EO 0.00 EO 0.00 EO 0.00 EO ypton-87 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 EO ypton-88 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 E0 inon-155M Cl 0.00 EO 0.00 E0 2.26 E-3
- 1. 92 E-2 ing nose-54 Ci 0.00 EO 0.00 EO 4.68 E-5 2.86 E-4 ilnium-154 Ci 0.00 EO 0.00 E0 1.58 E-3 2.11 E-5 istum-137 Ci 0.00 EO 0.00 E0 1.95 E-3
- 5. 6 7 E-3 istum-138 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 nc-65 Ci 0.00 EO 0.00 EO 7.28 E-3 1.57 E-2 idium-24 Cl 0.00 EO 0.00 EO 7. 0 2 E-4 2.25 E-3
> bolt-58 Ci 0.00 EO 0.00 E0
- 2. 95 E-4 9.52 E-4
> bolt-60 Ci 0.00 E0 0.00 EQ 5.12 E-3
- 9. 0 4 E-3
> dine-151 Ci 0.00 EO 0.00 E0 1.19 E-2
- 2. 75 E-5 5.64 E-4
>dino-135 Cl 0.00 EO 0.00 E0 8.06 E-4 2.84 E-5 nelum-140 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 EO - - - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ -
i TABLE 2B (Continued)
CONTIHUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter 2C5 5
4 5
4
- lidas Rolessed Cl 0.00 EO 0.00 EO 0.00 EO 0.00 EO ptun t um-25 9 Cl 0.00 EO 0.00 EO 5.27 E-3 4.55 E-3 romium-51 Cl 0.00 EO 0.00 EO 0.00 E0
- 2. 6 9 E-5 6.45 E-4 chnotlum-99M Cl 0.00 EO 0.00 EO 0.00 EO 5.91 E-4 dino-152 Ci 0.00 E0 0.00 ED 1.4 6 E-6 1.29 E-4 rentlum-92 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 timony-122 C) 0.00 EO 0.00 EO 0.00 EO 0.00 E0 lllurium-152 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 E0 obium-95 Cl 0.00 EO 0.00 E0 1.35 E-3 9.51 E-4 in t h:num-140 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 idmium-109 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 islum-156 Ci 0.00 EO 0.00 E0 2.5 9 E-4 5.81 E-4 ilvor-It0M Cl 0.00 EO 0.00 E0 1.59 E-5 0.00 E0 in ium-144 Cl 0.00 EO 0.00 EO 0.00 EO 0.00 LO stimony-124 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0
-en-5 9 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 m i lu rium-129M Ci 0.00 EO 0.00 EO 0.00 EO 0.00 E0 ellurium-151M Cl 0.00 EO 0.00 EO 0.00 EO 0.00 E0 irconium-95 Ci 0.00 EO 0.00 EO 0.00 EO 0.00 EO erium-141 Ci 0.00 EO 0.00 EO
- 6. 0 6 E-3 1.15 E-2 opper-64 otal f or Period (above)
Cl 0.00 EO 0.00 EO 8.51 E0 1.74 El - _ - _ - _ _ _ _ _. _
PEACH 80TTOM UNITS 2 & 3 JULY 1 TO DECEMBER 31 1996 - CLASSES OF SOLID RADICACTIVE' WASTE SHIPMENTS Individust Total Container (waste & Container)
Total a waste Description Volume Volume Total principal of Shipments (Source of maste)
Container / Type (cubic feet)
(cubic feet)
Corte Radionuclides CLAS$ A 132 Deustered HIC /LSA 7.5 13.860 501.478 Zn 65 Cs 134 Co 60. Cs 137 Rosin Type A Cash 4
Solidtfled 55 Ga1 Drum /
7.5 2220 1.271 Zn 65 Co 60. Cs 137. H3. C14 Liould (Ott)
Strong. 79ght Container 1
Non-Compacted 55 Ga1 Drum /
7.5 105 2.541 Co 60 In 65. Cs 134 Cs 137 Trash L5A Type A Cask l
Cla55 AaB 2
Deustered HIC /LSA 7.5 165 153.527 In 65. Cs 134 Co 60 Cs 137 Restn Type A Cask 1
l Cla55 8 5
De=stered HIC /LSA 7.5 345 839.452 2n 65. Cs 134 Co 60. Cs 137 Restn Type A Cask CLASS B&C None CLASS C 1
Irradiated Steet Liner /
57 57 14300 Fe 55. Co 60 N1 63. un 54 Reactor Type 8 Cash Components.
1 ATTACHMENT A SUPPLEMENTAL INFORMATION Ocility:
Peach Bottom Units 2 & 3 icenses:
DPR-44 DPR-56 Regulatory Limits (Technical Specification Limits)
A.
Noble Gases:
1.
$ 500 mrem /Yr - total body
" instantaneous" limits per 5 3000 mrem /Yr - skin Tech. Spec. 3.8.C.l.a 2.
$ 10 mrad - air gamma quarterly air dose limits per 5 20 mrad - air beta Tech. Spec. 3.8.C.2.a 3.
$ 20 mrad - air gamma
- yearly air dose limits per 5 40 mrad - air beta Tech. Spec. 3.8.C.2.b B.
Iodines, Tritium, Particulates with Half Life > 8 days:
(
l.
$ 1500 mrem /Yr - any organ
" instantaneous" limits per (inhalation path)
Tech. Spec. 3.8.C.l.b 2.
515 mrem - any organ
- quarterly dose limits per Tech. Spec. 3.8.C.3.a 3.
5 30 mrem - any organ
- yearly dose limits per Tech. Spec. 3.8.C.3.b C.
Liquid Effluents:
1.
Concentration < 10 CFR 20,
" instantaneous" limits per Appendix B, Ta51e II, Col. 2 Tech. Spec. 3.8.B.1 2.
5 3.0 mrem - total body quarterly dose limits per 5 10 mrem - any organ Tech. Spec. 3.8.B.2.a 3.
5 6.0 mrem - total body
- yearly dose limits per 5 20 mrem - any organ Tech. Spec. 3.8.B.2.b Maximum Permissible Concentrations MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.
The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified nuclides are used to calculate permissible release rates and concentrations for liquid releases per Peach Bottom Technical Specification 3.8.B.l.
(10)
ATTACHMENT A (CCntinued)
Avnrage Energy Not applicable.
M'^^urements and Approximations of Total Radioactivity A.
Fission and Activation Gases i
The method used is the Nuclear Data 6600/6700 Counting System
- Gas Marinelli
~
B.
Iodine The method used in the Nuclear Data 6600/6700 Counting System
- Charcoal Cartridge C.
Particulate:
The method used is the Nuclear Data 6600/6700 Counting System
- Air Particulate Sample, 47 mm filter D.
Liquid Effluents:
The method used is the Nuclear Data 6600/6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter bottle.
B9tch Releases A.
Liquid Q3 Q4
- of Batch Releases:
54 91 Total Time for batch releases, minutes 13440 25350 Maximum time period for a batch release, minutes 340 340 Average time period for batch release, minutes 249 279 Minimum time period for a batch release, minutes 240 240 Dilution 5.52 E10 1.04 Ell B-Gaseous:
N/A Abn*rmal Releases A.
Liquid See Attachment B B.
Gaseous:
None (11)
ATTACHMENT B Unplanned Liquid Release Via 3B High Pressure Service Water An unplanned 11guld release of radioactive High Pressure Service Water occurred on September 22, 1986.
The release was detected by a series of peaks on the High Pressure Service Water radiation monitor; however, the series of spikes on the strip chart of this event could indicate possible radiation transients at the monitor.
The High Pressure Service Water was not operating at the time.
No grab sample was obtained during the 30 minute duration of the event.
Calculated doses are based on the methodology presented in the Offsite Dose Calculation Manual, assuming a release rate of 3 gpm (monitor sample flow rate) and average release concentrations based on the radiation monitor's strip chart.
The whole body dose from this release was calculated at 7.91E-6 mrem, and the bone dose was calculated at 8.97E-6 mrem.
Unplanned Liquid Release Via the Raw Water Sump An unplanned liquid release of radioactive water through the Raw Water Sump occurred on November 13, 1986, caused by a 55 gallon drum which was routinely released through the sump.
The release was discovered following a review of drum sheets which indicated that the drum contained radioactive water.
A grab sample was obtained.
Calculated doses are based on the methodology presented in the Offsite Dose Calculation Manual, assuming a release rate of 10 gpm and release concentrations based on an actual grab sample.
The whole body dose from this release was calculated at 5.16 E-7 mrem, and the bone dose was calculated at 3.92 E-7 mrem. - _ _ _ _ _ _ _ _ _ _ - _ _ _ _