ML20211R073
| ML20211R073 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1986 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20211R050 | List: |
| References | |
| NUDOCS 8703030255 | |
| Download: ML20211R073 (20) | |
Text
TRANSMITTAL MANIFEST NDRTHERN STATES PDWER COMPANY NUCLEAR GENERATION DEPARTMENT PRAIRIE ISLAND NUCLEAR GENERATING PLANT Effluent and Waste Disposal Semi-Annual Report for July 1,1986 through December 31, 1986 Manifest Date:
February 28, 1987 USNRC
- Regional Admin-III 1
ANI Library 1
- NRR Project Manager, NRC 1
Westinghouse Electric 2
- DCD-1 W J Johnson
- Resident Inspector 1
R T Meyer R J Jensen 1
J N Sorensen (NUS) 1 L R Eliason 1
C E Agan (FPSI) 3 G T Goering/G H Neils I
(C E Agan, Al Garrow G Charnoff I
and Corporate Library)
M B Sellman 1
PI SAC Secretary 1
B W Clark 1
D C Lowens 1
ERAD Dept.
1 Safety Audit Committee 8
Attn: Records Clerk
- D M Musolf MDH 1
- K J Albrecht
- Attn: Commissioner of Health
- C W Giesler MPCA 1
- F W Hartley
- Attn: J W Ferman
- H S Isbin Prairie Island Plant Manager 10
- J A Thie Monticello Plant 1
- F P Tierney (W A Shamla)
- E L Watzl Media Services Dept.
1 SAC File (Manifest Only)
NSS File 1
NRS File 1
t gHo3030255 070228 g
ADOCK 05000202 PDR i
" Includes a copy of the ODCM R-2 MANIFEST
o
.PINGP 158, R1v. 6 Page 1 of 8 Retention: Lifetime 6
EFFLUENT SEMI-ANNUAL REPORT JULY, 1986 THROUGH DECEMBER, 1986 SUPPLEMENTAL INFORMATION Facilit.y - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 A.
Regulatory Limits 1.
Liquid Effluents:
The dose or dose commitment to an individual from radio-a.
active materials in liquid effluents released from the site shall be limited:
for the Quarter 3.0 mrem Total Body 10.0 mrem Any Organ for the Year 6.0 mrem Total Body 20.0 mrem Any Organ 2.
Gaseous Effluents:
The dose rate due to radioactive materials released in a.
gaseous effluents from the site shall be limited to:
Noble Gases f 500 mrem / Year Total Body
$ 3000 mrem / Year Skin i
I I-131, H-3, LLP 1 1500 mrem / Year Any Organ l
b.
The dose due to radioactive gaseous effluents shall be limited to:
l Noble Gases 5 10 mrad /Qtr Gamma
< 20 mrad /Qtr Beta l
i 20 mrad / Year Gamma 5 40 mrad / Year Beta I-131, H-3, LLP 5 15 mrem /Qtr 5 30 mrem / Year i
PINGP 158, RIv. 6 Pega 2 cf 8 B.
Maximum Permissible Concentrations 1.
Fission and activation gases in gaseous releases:
10 CFR 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.
L asurements 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 l
l 4.
Liquid Effluents:
Total Geli Nuclide Geli l
1.0 BATCH RELEASES (Liquid)
QTR 3 QTR 4 1.1 Number of Batch Releases 1 5.20E+01 4.70F+01 l
1.2 Total Time Period for a Batch Release l
l (hr.)
l 9.04E+01 6.95EiO1 l
1.3 Maximum Time for a Batch Release (br) l 2.17E+00 2.17E400 l
1.4 Average Time for a Batch Release (br) l 1.74E+00 1.66E+00 l
1.5 Minimum Time for a Batch Release (br) l 1.25E+00 1.30E+00 l
1.6 Ave Mississippi flow during Quarter (CFS)l 3.59E+04 3.06E+04. l I
PINGP 158, RLv. 6 Pcg2 3 of 8 2.0. BATCH RELEASES (Gaseous)
QTR 3 QTR 4 2.1 Number of Batch Releases l 1.00E+00 5.00E+00 l 2.2 Total Time Period for a Batch Release (br) l 1.77E+00 4.18E+01 l
2.3 Maximum Time for a Batch Release (hr) l 1.77E+00 3.01E+01 l
2.4 Average Time for a Batch Release (br) l 1.77E+00 8.36E+00 l 2.5 Minimum Time for a Batch Release (hr) l 1.77E+00 5.63E-01 1
3.0 ABNORMAL RELEASES (Liquid)
QTR 3 QTR 4 3.1 Number of Batch Releases l 0.OOE+00 0.Onv+nn l
3.2 Total Activity Release (Ci) l 0.cov+on n nnv+nn l
3.3 Total Tritium Release (Ci)
I o.cov+00 0.nnv+nn l
4.0. ABNORMAL RELEASES (Gaseous)
QTR 3 QTR 4 4.1 Number of Batch heleases l 0.00E+00 0.00E+00 l
4.2 Total Activity Release (Ci) l 0.00E+00 0.00E+00 l
PINGP'158, R v. 6 Paga 4 cf 8 TABLE 1A EFFLUENT SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR1 QTR 4 RR R 5.0 FISSION AND ACTIVATION GASES 5.1, Total Release (Ci) l 9.37E-01 1.18v41
- 2. snvm 1 1 5.2 Average Release Rate (pCi/sec) I 1.19v-01 1 sov+nn 5.3 Gamma Dose (mrad) l 3.54v-04 1.11v-n?
I 5.4 Beta Dose (mrad) l 1_osv-n1 1.sav-n?
l 5.5 % of Gamma T.S. Limit (%)
l 1.s4v-01 1.11v-n1 l
5.6 % of Beta T.S. Limit (%)
l s 2sv_1 i 77p_n1 1
6.0 IODINES 6.1 Total I-131 (Ci)
I s_ssv-n6 R 17v nA 2.50E+01l 6.2 Average Release Rate (pCi/sec) l 7.06E-07 1.04E-04 7.0 PARTICULATES 7.1 Total Release (Ci) l 6.44E-07 0.00E+00 2.50E+01 l 7.2 Average Release Rate (pCi/sec) l 8.19E-08 0.00E+00 8.0 TRITIUM 8.1 Total Release (Ci) l 2.50EMI 3.31E+01 2.50E+01 l 8.2 Average Release Rate (pCi/sec) l 3.18E+00 4.21E+00 9.0 TOTAL IODINE PARTICULATES AND l
l l
l TRITIUM (pCi/sec) l 3.18E+00 l 4.21E+00 l 2.50E+01 l 10.0 DOSE (mrem) l 4.54E-02 l 1.08E-01 l
11.0 % OF T.S. LIMIT
(%)
l 3.03E-01 l 7.20E-01 l
12.0 GROSS ALPHA 12.1 Total Release (Ci) l 1.31E-07 l 1.37E-07 l2.50E+0ll
~
PINGP 158, R;v. 6 Paga 5 cf 8
~
TMEIC EFFLUENT SEMIANNUAL REPORT GASEOUS EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE I
I l
l l
l l
[ NUCLIDE l UNIT l
QTR 3 l
QTR 4 l
QTR 3 l
QTR 4 l
l l
l l
l 1
l 13.0 INDIVIDUAL FISSION AND ACTIVATION GASES l Kr85 Ci 7.06E-01 l
l Kr85m Ci 5.49E-03 l
l Kr87 Ci l
l Kr88 Ci l
l Xe133 Ci 9.37E-01 6.40E+00 4.31E+00 l
l Xe135 Ci 2.67E-01 l
l Xe135m Ci
-l l Xe138 Ci l
l Xe131m Ci 7.23E-02 l
l Ar41 Ci l
l Xe133m Ci 5.26E-02 l
1 I
l i
o l
l l Total Ci 9.37E-01 6.40E+00 0.00E+00 5.41E+00 l
14.0 ICDINES (Ci) l 1131 1 Ci 5.55E-06 8.17E-04 l
l I133 Ci 1.43E-05 l
l 1135 Ci l
l Total Ci 5.55E-06 8.31E-04 0.00E+00 0.00E+00 l
CONTINUOUS MODE BATCH MODE l
l l
l l
l l
l NUCLIDE l
UNIT l
QTR 3 l
QTR 4 l
QTR 3 l
QTR 4 l
l l
l l
I I
i 15.0 PARTICULATES (Ci) l Sr89 Ci l
l l Sr90 Ci l
l Cs134 Ci l
l Cs137 Ci 8.66E-07 l
l Ba-La140 Ci l
l CoS8 Ci l
l Co60 Ci l
l l
l Total Ci R.66F-07 0.00E+00 0.00E+00 0.00E+00 l
PINGP 158, Rsv. 6 P:g2 6 of 8 TABLE 2A EFFLUENT SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR 3 QTR 4 E
i 16.0 VOLUME OF WASTE (Prior to Dilution) l Liters l 4.26F+07 l 5.57E+07 l2.50E+01 l 17.0 VOLUME OF DILUTION Water (liters) l Liters l 2.59E+11 l 1.56E+11 12.50E+01 l 18.0 FISSION AND ACTIVATION PRODUCTS l
l 18.1 Total Release W/0 H-3, (Ci) l l
' 2.50E+01 l Rad Gas, Alpha l 2.52E-03 1.61E-02 18.2 Average Diluted (pCi/ml) l Concentration l 9.75E-12 l
1.03E-10 l
19.0 TRITIUM 19.1 Total Release (Ci) l 2.05E+02 9.84E+01 2.50E+01 l 19.2 Average Diluted (pCi/ml) l 7.92E-07 6.32E-07 Concentration l
l l
20.0 DISSOLVED AND ENTRAINED GASES 20.1 Total Release (Ci) l 2.70E-02 8.34E-04 12.50E+01 l 20.2 Average Diluted (pCi/ml) l 1.04E-10 Concentration l
l 5*35E-12 l
21.0 GROSS ALPHA 21.1 Total Release (Ci) l 0.00E+00 l 0.00E+00 12.50E+01 l 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (pCi/ml) l 7.92E-07 l 6.32E-07 12.50E+01 l
PINGP 158, R v. 6 P:ge 7 of 8 TABLE 2A EFFLUENT SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l UNIT l
QTR 3 l
QTR 4 l
l 1-lE
%l 23.0 TOTAL BODY DOSE (mrem) l 4.70E-04 l
3.24E-0 l
l J
24.0 CRITICAL ORGAN DOSE (arem) l 5.19E-04 4.02E-04 l
(organ) l GI GI l
25.0 % TOTAL BODY T.S. LIMIT (%)
l 1.57E-02 l 1.08E-02 l
26.0 % OF CRITICAL ORGAN
(*4) l l
l T.S. Limit l 5.19E-03 l 4.02E-03 l
I l
l i
i i
PINGP 158, R;.v. 6 P,tg2 8 of 8 TABLE 2A EFFLUENT SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONTINUOUS MODE BATCH MODE l
l l
1 I
i l
l NUCLIDE l UNIT l
QTR 3 l
QTR 4 l
QTR 3 l
QTR 4 l
l l
l l
l l
l 27.0 INDIVIDUAL LIQUID EFFLUENT l Sr89 Ci l
l Sr90 Ci l
l Cs134 Ci 6.30E-06 l
l Cs137 Ci 1.62E-05 l
l 1131 Ci 1.55E-05 l
l CoS8 Ci 4.09E-04 2.97E-03 l
l Co60 Ci 2.86E-05 5.44E-04 5.05E-04 l
l Fe59 Ci 6.72E-04 l
l Zn65 Ci l
l Mn54 Ci 7.84E-06 2.60E-06 l
l Cr51 Ci 2.16E-04 l
l Zr-Nb95 Ci l
l Mo99 Ci l
l Ba-La140 Ci l
l Fe-55 Ci 4.49E-03 l
i From ATT #1 Ci 0.00E+00 1.30E-06 1.56E-03 1.17E-02 l
l Total Ci 0.00E+00 5.24E-05 7.01E-03 1.61E-02 l
CONTINUOUS MODE BATCH MODE I
l l
l 1
I I
l NUCLIDE l UNIT l
QTR 3 l
QTR 4 l
QTR 3 l
QTR 4 l
l l
l l
l l
l 28.0 DISSOLVED AND ENTRAINED GASES l Xe133 Ci 2.40E-02 7.92E-04 l
l Xe133m Ci 2.28E-04 l
l Xe131m Ci 1.25E-04 l
l Xe135 Ci 2.31E-04 4.17E-05 l
l Kr85m Ci 4.30E-06 l
l Kr85 Ci 2.47E-03 l
l l Kr88 Ci l
l i
I l Total Ci 0.00E+00 0.00E+00 2.71E-02 8.34E-04 l
ATTACHMENT 1 ADDITIONAL NUCLIDES LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 3 QTR 4 QTR 3 QTR 4 Ag-110m Ci 9.38E-04 8.27E-04 Na-24 Ci 5.37E-06 Nb-97 Ci 1.30E-06 1.42E-05 1.90E-05 Rh-105 Ci 6.08E-05 Sb-122 C1 1.58E-04 Sb-124 Ci 1.09E-04 4.88E-03 Sb-125 Ci 4.47E-04 4.87E-03 Sc-47 C1 2.00E-06 4.45E-04 Sn-113 Ci 7.69E-06 4.08E-04 Sr-85 Ci 1.07E-05 Sr-92 Ci 1.73E-06 Zr-97 Ci 3.40E-05 2.29E-05 Subtotal Ci 0.00E+00 1.30E-06 1.56E-03 1.17E-02 l
l
PINGP 753, Rev. 1 Retention:
Lifetime Page 1 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7/1/86 n 1/1/87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:
Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Total Volumes and Measured Curie Quantities:
1.
Type of Waste:
Container Units Total Volumes A.
Resins CU-FT 211 135/76 Ci 138.819 B.
DAW CU-FT 1140 7.5 (Compacted)
Ci 2.493 C.
DAW CU-FT 288 96 (Non-compacted)
Ci 0.038 D.
S.
l l
I l
l l
l
PINGP 753, Rev. 1 Retention:
Lifetime Page 2 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7/1/86 to 1/1/87 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
Cs-137 44.7 Co-60 26.4 Cs-134 18.5 Ni-63 7.8 Fe-55 0.9 Mn-54 0.8 C-14 0.4 H-3 0.4 Fe-55 33.6 B
Ni-63 18.7 11 - 3 13.9 Ag-110M 12.4 Co-60 9.3 Cs-137_
4.0 Co-58 2.8 Cs-134 1.9 C-14 0.8 I
- = Inferred - Not Measured on Site
PINGP 753, Rev. 1 Retention:
Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:
7/1/86 to 1/1/87 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
- = Inferred - Not Measured on Site
PINGP 753, Rev. 1 Retention:
Lifetime Page 4 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:
7/1/86 to 1/1/87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:
Solid Waste and Irradiated Fuel Shipments (Continued) 3.
Solid Waste Disposition:
Number of Shipments Mode Destination 2
Truck Barnwell, SC 2
Truck Richland, WA B.
Irradiated Fuel Shipments:
Number of Shipments Mode Destination 0
PINGP 753, Rev. 1 Retention:
Lifetime Page 5 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7/1/86 to 1/1/87 NORTHEP.N 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 86-27 135 93.975 A
A 86-29 76 44.844 A
A 86-33 96 0.001 c
1.
86-33 600 1.661 B
L 86-35 192 0.037 C
L 86-35 540 0.832 B
L 1
1 l
l CONTAINER CODES:
L = LSA A = Type A B = Type B Q = Large Quantity SOLIDIFICATION CODES:
C = Cement TYPES OF WASTE:
A = Resins l
B = Dry Compacted C = Non-Compacted D = Wst. Conc.
S = Spent Fuel l
l L
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE RADIATION DOSE ASSESSMENT FOR January 1 - December 31, 1986 An assessment of radiation dose due to releases from the Prairie Island Nuclear Generating Plant during 1986 wae narformed in accordance with the Technical Specifications. Computed doses were well below the 40 CFR Part 190 and 10 CFR Part 50, Appendix I standards and guidelines.
Offsite dose calculation formulas and meteorological data were used from the Offsite Dose Calculation Manual in making this assessment.
Source terms were obtained from the two Effluent and Waste Disposal Semi-Annual 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 Liquid Release Computed doses due to liquid releases 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 Boundary Occasional sportsmen will 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 dose due to recreational and river trans-l portation 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 Exposed Member of the General Public from Reactor Releases and Other Nearby Uranium Fuel Cycle Sources There are no uranium fuel cycle facilities in the vicinity of the Prairie Island site.
l i
_ ~ - _.
-2 The only other source of exposure to the general public in addition to the plant gaseous and liquid effluents 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 acti-vities 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 the 40 CFR Part 190 standards of 25 mrem to the whole body or any organ (except the thyroid) and 75 mrem to the thyroid every 12 months.
~
f I
i l
l l
r i
F..
TABLE 1 0FFSITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1986 10 CFR Part 50 Appendix I Gaseous Releases Guideline Per Unit Per Year Maximum Site Boundary Gamma Air Dose (mrad) 0.019 20 Maximum Site Boundary Beta Air Dose (mrad)*
0.071 40 Maximum Offsite l
Dose to Any Organ (mrem)
Total 0.334 30 Offshore Location (mrem, 7 days / year)
Whole Body 0.0002 10 Organ 0.0003 30 Liquid Releases Maximum Offsite Whole Body Dose (mrem)
Total
.0020 6
Maximum Offsite Organ Dose (mrem)*
Total
.0025 20
-4 TABLE 2 0FFSITE RADIATION DOSE ASSESSMENT SUPPLEMENTAL INFORMATION - PRAIRIE ISLAND PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1986 Gaseous Effluents Maximum Site Boundary Dose Location (from building vents)
Sector WNW Distance (mi) 0.36 Offshore Location Within Site Boundary Sector ESE Distance 0.2 Maximum Offsite Dose Location Sector SSE Distance (mi) 0.6 Pathways
- Ground, Inhalation, Vegetables Age Group Child Organ Thyroid j
{
Liquid Releases i
Maximum Offsite Dose Location Downstream f
Pathways Fish l
Age Group Adult l
Organ Thyroid i
i l
l PI 0FFSITE DOSE ASSESS LTR i
e REVISION 8 Prairie Island Nuclear Generating Plant Offisite Dose Calculation Manual In accordance with the Prairie Island Technical Specifications 6.5 E, Offsite Dose Calculation Manual (00CM), the following changes to the ODCM are reported:
A.
Retype and format of total manual B.
Addition of Discharge Canal Monitor Setpoint calculations These changes do not reduce the accuracy or reliability of dose calculations or setpoint determinations.
These changes were reviewed and found acceptable by the Prairie Island Operations Committee on November 14, 1986.
D Instructions for Entering Revision 8 to the ODCM Manual Remove the existing contents of the ODCM Manual and replace it with the attached pages.
R-2 LETTER