ML20196E613
| ML20196E613 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1987 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20196E604 | List: |
| References | |
| NUDOCS 8803010200 | |
| Download: ML20196E613 (19) | |
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PINGP 158, Rev. 6 Page 1 of 8 Retention: Lifetime EFFLUENT SEMI-ANNUAL REPORT JULY THROUGH DECEMBER, 1987 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generatina Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 A.
Regulatory Limits 1.
Liquid Effluents:
a.
The dose or dose commitment to sn individual from radio-active materials in liquid effluents released from the site shall be limited:
for the Quarter 3.0 arem Total Body 10.0 ares Any Org.in for the Year 6.0 aren Total Body 20.0 aren Any Organ 2.
Gaseous Effluents:
a.
The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:
Noble Gases 5 500 ares / Year Total Body 5 3000 ares / Year Skin I-131, H-3, LLP
$ 1500 ares / Year Any Organ b.
The dose due to radioactive gaseous effluents shall be limited to:
Noble Gases
< 10 mrad /Qtr Gamma I 20 mrad /Qtr Beta i 20 mrad / Year Gamma i 40 mrad / Year Beta I-131, H-3, LLP S 15 ares /Qtr 5 30 meem/ Year 8803010200 880226 PDR ADOCK 05000282 R
PINGP 158, R;v. 6 Pag) 2 cf 8 B.
Maximum Permissible Concentrations 1.
Fission and activation gases in gaseous releases:
10 CTR 20, Appendix B, Table 2, Column 1 2.
Iodine and particulates with half-lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1 3.
Liquid Effluents for radionuclides other than dissolved or entrained gases:
10 CFR 20, Appendix B, Table 2, Column 2 4.
Liquid Effluent dissolved and entrained gases:
2.0E-04 pei/ml Total Activity C.
Average Energy Not applicable to Prairie Island Regulatory Limits.
D.
Measurements and Approximations of Total Radioactivity 1.
Fission and activation gases Total Geli in gaseous releases:
Nuclide Geli 2.
Iodines in gaseous releases Total Geli Nuclide Geli 3.
Particulates in gaseous Total Geli releases:
Nuclide Geli 4.
Liquid Effluents:
Total Geli Nuclide Geli 1.0 BATCH RZLEASES (Liquid)
QTR 03 QTR 04 1.1 Number of Batch Releases l 4.80E+01 4.20E+01 l 1.2 Total Time Period for a Batch Release l
l (hr.)
l 9.13E+ol 6.2sr+01 l 1.3 Maximus Time for a Batch Release (br) l 2.16E+01
.1,90E+00 l 1.4 Average Time for a Batch Release (br) l 1.90E+00 1.sor+oo l 1.5 Minimum Time for a Batch Release (br) l 3.coE-01 1.3cr+oo l 1.6 Ave Mississippi flow during Quarter (CFS)l 9.73r+o3 s. sor+n, l
i l
PINGP 158, Rev. 6 Page 3 cf 8 F
2.0. BATCH RELEASES (Gaseous)
QTR 03 QTR 04 2.1 Number of Batch Releases l 1.00E+00 1.00E% 0 l 2.2 Total Time Period for a Batch Release (hr) l 2.80E+00 2.80E+00 l 2.3 Maximus Time for a Batch Release (br) l 2.80E+00 2.80E+00 l 2.4 Average Time for a Batch Release (br) l 2.80E+00 2.80E+00 l 2.5 Minimum Time for a Bater. Release (hr) l 2.80E+00 2.80E+00 l 3.0 ABNORMAL RELEASES (Liquid)
QTR 03 QTR 04 3.1 Number of Batch Releases l 0.00E+00 0.00E+00 l 3.2 Total Activity Release (Ci) l 0.00E+00 0.00E+o0 l 3.3 Total Tritium Release (Ci) l 0.00E+00 0.00E+00 l 4.0. ABNORMAL RELEASES (Gaseous)
QTR 03 QTR 04 4.1 Number of Batch Releases l 0.00E4co 0.ooE4co l 4.2 Total Activity Release (Ci) l 0.00Ee0 0.coE+oo l f
.e' 8
PINGP 158, Rev. 6 Page 4 of-8 n
TABLE 1A l
EFFLUENT SEMIANNUAL REPORT f
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES i
i I
E T
UNIT QTR g QTR g 5.0 FISSION AND ACTIVATION GASES 5.1 Total Release-(Ci) l 5.44E-02 6.95E-02
- 2. 50E+01 l L
5.2 Average Release Rate (pCi/sec) l 6.92E-03 8.38E-03 l
5.3 Gamma Dose (arad) l 4.40E-06 5.20E-06 l
5.4 Beta Dose (arad) l 4.42E-04 5.66E-04 l
5.5 % of Gamma T.S. Limit (%)
l 4.40E-05 5.20E-05 l
5.6 % of Beta T.S. Limit (%)
l 2.21E-03 2.83E-03 l
[
6.0 IODINES 6.1 Total I-131 (Ci) l 0.00E+00 0.00E+00 2.50E+01l 6.2 Average Release Rate (pCi/sec) l 0.00E+00 0.00E+00 7.0 PARTICULATES 7.1 Total Release (Ci) l 0.00E+00 O.00E+00 2.50E+01l l
7.2 Average Release Rate (pCi/sec) l 0.00E+00 0.00E+00 I
8.0 TRITIUM 8.1 Total Release (Ci) l 4.64EMO 6.68E400
- 2. 50E+01 l I
8.2 Average Release Rate (pCi/sec) l 5.90E-01 8.50E-01 9.0 TOTAL IODINE PARTICULATES AND l
l l
l l
TRITII;M (pCi/sec) l 5.90E-01 l
8.50E-01 l 2. 50E+01 l 10.0 DOSE (ares) l 6.15E-03 l
1.41E-02 l
l 11.0 ".OF T.S. LIMIT
(%)
l 4.10E-02 i
9.40E-02 l
f 12.0 GROSS ALPHA l
12.1 Total Release (Ci) l 1.38E-07 j 3.68E-08 l2.50EF31l
(
,--n.------.-.m._
n
PINGP 158, Rev 6 i
'Pa80 5 of 8 TABLE 1C i
EFFLUENT SEMIANNUAL REPORT GASEOUS EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MCDE BATCH MODE I
i 1
l l
l l
l NUCLIDE l UNIT l
QTR E l
QTR 04 l
QTR 03 l
QTR 04 l
l l
l I
I I
l l
13.0 INDIVIDUAL FISSION AND ACTIVATION GASES l Kr85 Ci 5.40E-02 6.94E-02 l
i l Kr85m Ci l
l Kr87 Ci l
l Kr88 Ci l
l Xe133
-Ci 3.52E-04 1.20E-04 l
l Xe135 Ci
/. 62E-06 l
i l Xe135m Ci l
l Xe138 Ci l
l Xe131m Ci l
l l Ar41 Ci l
l Xe133m Ci l
l l
l l
I L
l~
1 l,fotal Ci 0.00E+00 0.00E+00 5.44E-02 6.95E-02 l
14.0 IODINES (Ci) l 1131 Ci l
i l 1133 Ci l
l 1135 Ci l
l Total Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
[,
CONTINUOUS MODE BATCH MODE l
l l
l l
l l
l NUCLIDE l
UNIT l
QTR 03 l
QTR 04 l
QTR E l
QTR 04 l
l l.
I I
I I
I
.l l
r 15.0 PARTICULATES (Ci) 0.00E+00
- 0. OE+00 0.00E+00 l
l Sr89 Ci O.00E+00 l Sr90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
l l Cs134 Ci l
l Cs137 Ci l
f l~8a-Ls140 Ci l
[
l CoS8 Ci l
~
[Co60 Ci l
l l
l Total I Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
I
PINGP 158, Rev. 6 Page 6 cf 8 TABLE 2A EFFLUENT SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR 03 QTR 04 16.0 VOLLHE OF WASTE (Prior to Dilution) l_ Liters l
4.93E+07 l
4.16E+07 l 2.50E+01l 17.0 VOLUME OF DILUTION Water (liters) l Liters l
2.56E+11 l
1.79E+11 I 2.50E401l 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 Total Release W/0 H-3, (Ci) l l
l l
Rad Gas, Alpha l
8.17E-03 1.95E-03 2.50EM1l 18.2 Average Diluted (pCi/ml) l Concentration l
3.19E-11 l
1.09E-11 l
19.0 TRITILH 19.1 Total Release (Ci) l 1.21EM2 l
4.86E+01 2.50E+01l 19.2 Average Diluted (pCi/ml) l l
Concentration l
4.73E-07 l
5.51E-07 l
20.0 DISSOLVED AND ENTRAINED GASES 20.1 Total Release (Ci) l 2.61E-04 9.32E-04 2.50E+01l 20.2 Average Diluted (pCi/ml) l Concentration l
1.02E-12 l
5.21E-12 l
l 21.0 GROSS ALPHA i
l 21.1 Total Release (C1) l 0.00E+00 l
0.00E+00 l 2.50E+01l 22.0 TOTAL TRITILN, FISSION AND ACTIVATION PRODUCTS (pCi/ml) l 4.73E-07 i
s.stE-07 l, snr4nt l l
l l
L._
PINGP 158, Rev. 6 P ge 7 cf 4 TABLE 2A ETTLUENT SLMIANNUAL REPORT LIQUID EFTLUENTS - SUMMATION OF ALL RELEASES l
l l
I TOTE l UNIT QTR g l
QTR E l ERROR %
I l
l l
1 23.0 TOTAL BODY DOSE (area) l 2.91E-04 l
2.75E-04 l 24.0 CRITICAL ORGAN DOSE (area) 2.97E-04 2.99E-04 l (organ) ci t ivn l
25.0 % TOTAL BODY T.S. LIMIT (%)
l 9.70E-03 1
9.17E-03 l 26.0 1 0F CRITICAL ORGAN
(%)
l l
l T.S. Limit l
2.97E-03 l
2.99E-03 l
PINGP 158, Rev. 6 Page 8 cf 8 TABLE 2A EFFLUENT SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONTINUOUS MODE BATCH MODE l
l l
l l
l 1
l NUCLIDE l UNIT l
QTR_0_3 l
QTR 04 l
QTR 03 l
QTRE l
3 l
l l
l I
l l
27.0 INDIVIDUAL LIQUID EFFLUENT l Sr89 Ci 0.cor+oo 0.cormo 0.cormo 0.00EMO l
l Sr90 Ci 0.ontmo 0.00r+00 0.00E+00 0.00EMO l
l Cs134 C1 1.77E-06 l
l Cs137 Ci 6.92E-06 1.32E-05 l
l I131 Ci l
l CoS8 Ci 4.42E-04 5.28E-05 l
l Co60 Ci 2.57E-04 4.69E-04 l
l Fe59 Ci
~l
~
l Zn65 Ci l
l Mn54 Ci l
l Cr51 Ci 4.57E-05 l
l Zr-Nb95 Ci l
l Mo99 Ci l
l Ba-La140 Ci l
l Fe-55 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Ci 0.00E+00 0.00E+00 7.42E-03 1.41E-03 l
l l Total Ci 0.00E400 0.00E400 8.17E-03 1.95E-03 l
- Additional Nuclides from Attachment 1.
CONTINUOUS MODE BATCH MODE l
l l
l l
l l
l NUCLIDE l UNIT l
QTR 03 l
QTR 04 l
QTR_03 l
QTR 04 l
l l
l l
l l
l 28.0 DISSOLVED AND ENTRAINED GASES l Xe133 Ci 2.59E-04 8.72E-04 l
l Xe133s Ci l
l Xe131m Ci l
l Xe135 Ci 1.77E-06 5.98E-05 l
l Kr$5a Ci l
l Kr85 Ci l
l Kr88 Ci l
l l
l l
l Total
' Ci 0.00EMO 0.00E+00
- 2. M E-04 4.32E-04 l
7 ATTACHMENT 1 ADDITIONAL NUCLIDES i
LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR C1 QTR 04 QTR 03 QTR 04 5
AG-110M CI 5.76E-05 4.59E-04 CS-138 CI 6.15E-05 t
NA-24 CI 3.43E-06 i
NS-97 CI 1.99E-05 2.50E-05 L
58-124 CI 4.32E-03 7.49E-05 i
SB-125 CI 2.71E-03 2.90E-04 t
SC-47 CI 2.49E-04 S.47E-04 ZR-97 CI 1.79E-Or l
SUBTOTAI CI 7.42E-03 1.41E-02 I
I l
E k
l l
I l'
f PINGP 753, Rev. - 1 Retention:
Lifetime Page 1. of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Total Volumes and Measured Curie Quantities:
1.
Type of Waste:
Contr.iner Units
_ Total Volumes A.
Resin Cu - f:
810.3 172.5 (1 @ 120.3)
C1 391.814 B.
Dry compacted Cu - ft 2829 7.5 C1 23.899 C.
Non-Compacted Cu - ft 20.8 C1 0.037 D.
Filter Cartridges Cu - ft.
163.3 163.3 Cf 1.922 S.
--.7
-.e r
PINGP 753, Rcv. 1 Retention:- Lifetime Page 2 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 2.
Measured Major Nuclide Composition by Type of Waste:
TYPE (From Page 1)
Nuclide Percent A
- H-3 15.0 CO-36 21.1 SB-125 0.8
- FE-55 44.8
- H-3 20.7 Co-58 0.8 NB-95 0.6
__MN-54 1.2 CO-60 11.4 AG-110M 0.5
- FE-55 41.3
- N1-63 22.9 _,_
- = Inferred - Not Measured on Site
PINGP 753, Rev. 1 Retention:
Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period; 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel. Shipments (Continued) 2.
Measured Major Nuclide Composition by Type of Waste (Continuation):
TYPE (From Page 1)
Nuclide Percent C
- H-3 61.7
- FE-55 17.0
- H-3 2.7 D
CO-60 23.7
.;-14 4.8
- TI-63 6.7
~
~
- = Inferred - Not Measured on Site I
PINGP 753, Rsv. 1 Retention:
Lifetime Page-4 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 3.
Solid Waste Disposition:
Number of Shipments Mode Destination 10 Truck Richland, Washington 1
Truck Barnwell,'S.C.
1 Truck Beaty, Nevada B.
Irradiated Fuel Shipments:
Number of Shipments Mode Destination Oe t
PINGP 753, Rev. 1 Retention:
Lifetime Page 5 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued)
C.
Shipping Container and Solidification Method:
No.
Volume Activity Type of Container Solidify (Ft3)
(Ci)
Waste Code code 87-26 172.5 2.758 A
L NA 87-27 585.0 7.225 B
L NA 87-28 172.5 7.496 A
L NA 87-29 570.0 3.586 B
L NA 87-30 163.3 1.922 D
L NA 87-32 120.3 373.448 A
B NA 87-34 172.5 2.014 A
L NA 87-38 570.0 5.962 B
L NA 87-41 172.5 6.098 A
_ L NA 87-43 534.0 3.563 B
L NA 87-31 570.0 3.563 B
L NA 87-39 20.8 0.037
_C L
NA TOTALS 12 3823.4 417.672 CONTAINER CODES:
L = LSA A = Type A B = Type B i
Q = Large Quantity SOLIDIFICATION CODES:
C = Cement TYPES OF WASTE:
A = Resins B = Dry Compacted C = Non-Compacted D = Wsw4erter. Filter Cartridges l
S = Spent Fuel I
. NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE RADIATION DOSE ASSESSMENT FOR January 1 - December 31, 1987 An assessment of radiation dose due to releases from the Prairie Island Nuclear Generating Plant during 1987 was performed in accordance with the Technical Specifications.
Computed doses were well below the 40 CFR Part 190 and 10 CFR 50, Appendix I standards and guidelines.
Offsite dose calculation formulas and meteorological data from the Offsite Dose Calculation Manual were used in making this assessment.
Source terms were obtained from the two Effluent and Waste Disposal Semiannual Reports prepared for NRC review during the year.
Offsite Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1.
Critical receptor location and pathways for organ doses are reported in Table 2.
Doses, both whole body and organ, are a small percentage of Appendix I guidelines.
Offsite Doses from Licuid Release Computed doses due to liquid are reported in Table 1.
Receptor information is reported in Table 2.
Doses, both whole body and organ, are a small percentage of Appendix I guidelines.
Doses to Individuals Due to Activities Inside the Site Boundarv Occasionally sportsmen enter the Prairie Island site for recreational activities.
These individuals are not expected to spend more than a few hours per year within the site boundary.
Commercial and recreational river traffic exists through this area.
For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off shore from the main plant buildings (ESE at 0.2 miles).
Whole body and inhalation organ doses were calculated for this location and occupancy time.
These doses were reported in Table 1.
Doses to Most Excosed Member of the General Public from Reactor Releases and Other Nearby Uranium Fuel Cycle Sources There are no uranium fuel facilities in the vicinity of the Prairie Island site.
1
The only other source of exposure to the general public in addition to the plant gaseous and liquid releases is from direct radiation.
Pressurized water reactor direct radiation has been shown to be negligible.
An array of TLD monitoring locations at the site boundary has consistently indicated that plant operation in recent years has had no effect on ambient gamma radiation.
Therefore, the most exposed member of the general public will not receive a radiation dose from reactor releases and all other fuel cycle activities in excess of the sum of the liquid and gaseous whole body and organ doses reported in Table 1 for the site boundary and critical receptor, respectively.
These doses are well within 40 CFR Part 190 standards of 25 mrem to the whole body or any organ (except thyroid) and 75 mrem to the thyroid every 12 months.
l 2
l
TABLE 1 OFFSITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD:
JANUARY 1 throuch DECEMBER 31, 1987 10 CFR Part 50 Appendix I Gaseous Releases Guideline per Unit per Year Maximum Site Boundary Gamma Air Dose (mrad)
.0002 20 Maximum Site Boundary Beta Air Dose (mrad)
.0069 40 Maximum Offsite Dose to any Organ (mren)*
Total
.0657 30 Offshore Location (mrem, 7 days / year)
Whole Body
<.0001 10 Organ
<.0001 30 Licuid Releases Maximum Offsite Whole Body Dose (mrem)
Total
.0012 6
Maximum Offsite Organ Dose (mrem)
Total
.0025 20
3 l
l I.
TABLE 2 OFFSITE RADIATION DOSE ASSESSMENT SUPPLEMENTAL INFORMATION - PRAIRIE ISLAND PERIOD: JANUARY 1 throuah DECEMBER 31, 1987 Gaseous Effluents Maximum Site Boundary Dose Location (from building vents)
Sector WNW Distance (mi) 0.36 Offshore Location Within Site Boundary Sector ESE Distance (mi) 0.2 Maximum Offsite Dose Location Sector SSE Distance (mi) 0.6 Pathways
- Ground, Inhalation, Vegetables Age Group Child Organ Thyroid Licuid Releases Maximum Offsite Dose Location Downstream Pathways Fish Age Group Adult Organ Thyroid 4