ML19283B664
| ML19283B664 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/27/1979 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7903060176 | |
| Download: ML19283B664 (11) | |
Text
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- 6 HSP NORTHERN STATES POWER COMPANY M I N N E APO LI S. M O N N E SOTA 55401 February 27, 1979 Mr J G Keppler, Director, Region III Office of Inspection & Enforcenent U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr Keppler:
PRAIRIE ISLANis NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semiannual Report for July 1 - December 31, 1978 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating Licenses DPR-42 and DPR-60, we are sub-mitting two copies of the Ef fluent and Waste Disposal Semiannual Report covering the peried July 1,1978 through December 31, 1978.
Beginning with the Ef fluent and Waste Disposal Semisnnual Report f or January 1,1979 - June 30,1979, we will discontinue reporting nuclides at their lower limit of detection (LLD) levels when they are not detected in plant releases. This is being done to conform to the latest guidance f rom the Division of Operating Reactors contained in the Appendix I standardized Technical Specifications, dated November 15, 1978. It is our belief that reporting only "real" releases will clarify the Semiannual Effluent and Waste Disposal Report and increase its usefulness.
Yours very truly, h.
L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/deh cc: Director, IE, USNRC (c/o DSB) (6)
G Charnoff 790306ol%
MPCA Attn: J W Ferman Attachments
EFFLUENT AND WASTE DIS?0 SAL SEMIANNUAL REPORT July 1, 1978 THROUGH December 31 1978 Supplemental Intornatiot.
Facility - Prairie Island Nuclear Generating Plar.t_
Licensee - Northern States Power Company License Nos. - DPR-42 DPR-60 1.
Regulatory Limits Action is required if the rate of release of radioactive materials, when averaged over a three-month period, is such that these quantities, if continued at the same release rate for a year, would exceed twice the design objectives. Design objectives are:
a.
Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:
9 1 1 1300 m /sec MPC b.
Iodines and particulates with half-lives greater than 8 dcys in gaseous releases:
9 1
1 67 m /sec MPC f
c.
Liquid Effluents:
1.
Annual total quantity of radioactive materials in liquid waste, exclusing tritium ard dissolved gases, of 5 Ci per unit.
2.
Annual average con:entration of radioactive materials in liquid waste, prior to dilution in the Mississippi River, excluding tritium and dissolved gases, of 2 x 10-8 uCi/ml.
Annualaverageconcentrationoftritiuminliguidwaste, prior to 3.
dilution in the Mississippi River, of 5 x 10-uCi/ml.
2.
Maximum Permissible Concentrations a.
Fiscion and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:
10CFR20, Appendix B, Table 2, Column 1 PINGP 158 Rev. 2 2.
Maximum Permissible Concentrations b.
Iodine and particulates with half-lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1 c.
Liquid Effluents:
10 CFR 20, Appendix B, Table 2, Column 2 3.
Average Energy Not applicable to Prairic Island Regulatory Limits.
4.
Measurements and Approximations of Total Radioactivity a.
Fission and activation gases Total Geli in gaseous releases:
Nuclide Geli b.
Iodines in gaseous releases Total Gell Nuclide Geli c.
Particulates in gaseous Total Geli releases:
Nuclide Geli d.
Liquid Effluents:
Total Gross Beta Gamma Nuclide Geli BATCH RELEASES a.
Liquid QTR 3 QTR 4 Number of Batch Releases 7.8E01 4.8E01 Total Time Period for a Batch Release (hr) 1.14E02 6.91E02 Maximum Time for a Batch Release (br) 2.50E00 2.50E00 Average Time for a Batch Release 6.)
1.50E00 1.40E00 Minimum Time for a Batch Release shr) 1.20E00 6.00E-01 Ave Mississippi flow during Quarter (CFS) 2.39E04 9.74E03 b.
Caseous QTR 3
QTR 4
Number of Batch Releases 7.0E00 3.0 LOO Total Time Period for Batch Releases (hr) 8.06E01 8.01E01 Maximum Time for a Batch Release (hr) 3.71E01 4.03E01 Average Time for a Batch Release (hr) 1.15E01 2.67E01 Minimum Time for a Batch Release (hr) 7.0E-01 1.35E01 PINGP 158 Rev. 2 ABNORMAL RELEASES a.
Liquid QTR 3
QTR 4 0
0 Number of Releases 0
0 Total Activity Released (C1)
Total Tritium Released (C1) 0 0
b.
0 Number of Releases Total Activity Releases (C1) 1.05E01 0
e PINGP 158 TABLE lA Rev. 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR_L QTR_4-ERROR A.
Fission and Activation Gases Total Release
- Ci 8.78E02 5.42E01 50%
Average Release Rate
- pCi/sec__
l.13E02 6.97E00 B.
Short Lived Particulate (t1/2 < 8 days)
T'.al Release
- Ci 0
0
+ 50%
Iverage Releace Rate
- PCi/sec 0
0 C.
Tritium Total Release
- Ci 2.74E01 2.48E01 t 50%
Average Release Rate
- PCi/sec 3.48EOO 3.15E00 Total A & B 6 C pC1/sec 1.19E02 1.01E01
% of Design Objective 2.99E01 3.03E00 D.
Iodines Total I131*
Ci 9.88E-05 1.llE-04
- t 50%
Average Release Rate
- pCi/sec 1.27E-05
- 1. 42 E-05 E.
Long Lived Particulates (cl/2 > 8 days)
Total Release
- Ci 2.25E-07 1.90E-05
+ 50%
Average Release Rate
- pCi/sec 2.89E-08
- 2. 42 E-06 Total D & E pC1/sec 1.27E-05
- 1. 66 E-05
% of Design Objective 1.88E-01 2.19E-01 F.
Gross Alpha ITotal Release
- C1 3.79E-09 1.73E-08
_100%
- All release amounts, concentrations, and % of design objective calculations are based on actual measured activity released.
PINCP 158 Rev. 2 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS CONTIWUOUS MODE BATCH MODE I
NUCLIDE UNIT QTR _3_
QTR _3, QTR1_
QTR 4__
1.
Fission and Activation Gases Kr85**
Ci
< 8.75E03
<2.35E00
<1.63E-01
<2.40E-02 Kr85m**
Ci
< 6. 51E00
<1.76E00
<1.22E-01
<1.80E-02 Kr87**
Ci
< 3. 25E00
<8.82E-01
<6.10E-02
<9.01E-03 Kr88**
Ci
< 1.19E01
<3.23E00
<2.23E-01
<3.30E-02 Xe13 3**
Ci
< 1.09E03
<2.94E02
<2.03E01
<3.01E00 Xe135**
Ci
< 2.64E01
<5.59E00
<4.59E-01
<5.71E-02 Xe135b**
Ci
< 7. 60E-01
<2.06E-01
<1.40E-02
<2.10E-03 Xe138**
Ci
< 2.16E00
<5.88E-01
<4.10E-02
<6.01E-03 Xe131m**
Ci
< 6. 51E00
<1.76E00
<1.22E-01
<1.80E-02 Ar41*
Ci
< 3. 50E01
<3.63E01
<7.56E-01
<6.38E-01 Xe133m**
Ci
< l. 30E01
<3.53E00
<2.49E-01
<3.60E-02 To t al **
Ci
<1.20E03
<3.50E02
<2.25E01
<3.85E00 2.
Iodines 1131*
Ci
<l.37E-04
<1.47E-04
<4.0RE-07
<2.99E-06 1133*
Ci
< 3. 35E-05
<3.45E-05 1.01E-05 8.01E-65 I135*
Ci
<1.04E-04
<1.08E-04
<1.12E-06
<1.34E-06 Total
- Ci
< 2. 7 5E-04
<2.90E-04
<1.16E-05
<1.23E-05 CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR _3,_
QTR 4_
QTR 3_
QTR 4_.,
3.
Particulates Sr89*
Ci
<7.69E-08
<7.97E-08
< 4. 31E-06
<5.20E-06 Sr90*
Ci
<1.36E-07
<1.41E-07
< 7. 64E-06
<9.20E-06 Cs134*
Ci
<4.31E-05
<4.47E-G5
< 4.66E-07
< 5. 59 6-0 7 Cs]37*
Ci
<4.23E-05
<4.38E-05
< 4. 54E-07
<5.48E-07 Ba-La140*
Ci
<1.02E-04
<1.06E-04
<' 10E-06
<1.33E-06 CoS8*
Ci
<3.31E-05
<4.60E-05
<. 56E-07
<4.29E-07 Co60*
Ci
<4.57E-05
<5.49E-05
< 4 94E-07
<5.94E-07 Cd109*
Ci
<4.33E-05
<4.50E-05
< 4. 56E-07
< 5.62E-07
.Eh124*
Ci
<4.80E-05
<4.99E-05
< 5. 2DE-07
< 6. 24E-07 Na24*
Ci
<3.01E-05
< 3.12E-05
< 3. 24E-07
< 3. 89 E-07 C o57*
Ci
<3.63E-05
<3.77E-05
< 3. 91E-07
< 4. 71E-07 Cc144*
Ci
<2.80E-04
< 2. 91E-04
< 3.03E-06
< 3. 63E-06 Z r-Nb 95
- Ci
<6.90E-05
<7.15E < 7.4 3E-07
< 8. 9 5 E-07 Rb88*
Ci
<8.60E-05
< 8.92E-05
< 9. 25E-07
<i.12E-06 PINGP 158 Rev. 2 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS 3.
Particulates Sr85*
Ci
<3.56E-05
<3 70E-05
<3.84E-07
<4.64E-07 Mn54*
Ci
<3.50E-05
<3.72E-05
<3.75E-07
<4.52E-07 Cs138*
Ci
<4.31E-05
<4.47E-05
<4.64E-07
<5.59E-07 Y88*
Ci
<1.98E-05
<2.05E-05
<2.13E-07
<2.56E-07
- All "less than" numbers are based on the sum of the nuclides actually measured in the release plus the 'ower Itnit of detection (LLD) levels for all other nuclides listed in Reg Guide 1.21 not detected in the ventilation air discharges.
- Noble gas releases are based on the following:
- 1. Xe-133 Quantity reported is equal to Xe-133 actually detected in releases plus quantity at LLD level assumed to be released continuously.
- 2. Other isotopes Quantity reported is equal to quantity actually detected in releases plus quantity in (1) above multiplied by ratio of isotope to Xe-133 derived from PWR GALE Code.
This method results in a conservative reported value for individual isotopes. The extremely low concentrations of noble gases in air discharged from the plant precludes using the results of isotopic analyses to quantify individual isotopes.
PINGP 158 Rev. 2 TABLE 2A EFFLUENT AND WASTE DISP 0AL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR _3 QTR 4--
- 4 A.
Fission and Activation Products Total Release W/0 H-3, Rad Gas, Alpha
- C1 1.33E-03 8.45E-04
+ 50%
Average Diluted Concentration
- pCi/ml 2.61E-12 4.29E-12
% of T. S. Annual Curie Design Objective 1.33E-02 8.45E-03 B.
Tritium Total Release
- Ci 1.07E02 8.61E01
+ 25%
Average Diluted Concentration
- pCi/ml 2.10E-07 4.37E-07
% of T. S. Annual Design Objective Conc
- 4.20E00 8.74E00 C.
Dissolved and Entrained Gases Total Release
- Ci l
7.14E-02 1.08E-01
+ 50%
Average Diluted Concentration
- pCi/ml l 1.40E-10 5.48E-10 D.
Gross Alpha Total Release
- C1 0
0
_t_ 50 7.
E.
Volume of Waste (Prior to Dilution) l liters 7.08E07 l 5.92E07
- t25%
l F.
Volume of Dilution Water l liters )
5.09E11 1.97 Ell
_-E 50%
l
- All release amounts, concentrations, and percent of design objective calculations are based on actual measured activity released.
PINGP 158 Rev. 2 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPCRT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR 3_
QTR 4_
QTR 3_
QTR 4_
Sr89*
Ci
<1.41E-03
<1.19E-03
<4.45E-OS
< 2. 40E-05 SrS0*
Ci
<2.49E-03
<2.12E-03
<7.88E-05
<4.29E-05 Csl34*
Ci
<2.14E-03
<l.81E-03
<1.06E-04
<4.35E-05 Csl37*
C1
<2.21E-03
<1.87E-03
<l.20E-04
<4.29E-05 1131*
Ci
<2.40E-03
<2.02E-03
<7.96E-05
<4.05E-05 CoS8*
Ci
<1.74E-03
<1.47E-03
<1.14E-04 2.00E-04 Co60*
Ci
<2.19E-03
<1.85E-03 6.87E-04 4.85E-04 Fe59*
Ci
<4.03E-03
<3.45E-03
<1.27F-04
<6.87E-05 Zn65*
Ci
<3.70E-03
<3.12E-03
<1.17E-04
<6.29E-05 Mn54*
Ci
<1.78E-03
<1.51E-03
<8.53E-05
<7.69E-05 Cr51*
Ci
<2.33E-03
<1.98E-03
<7.67E-05
< 3. 9 8E-05 Zr-Nb95*
Ci
<3.61E-03
<3.05E-03
<1.15E-04
<6.91E-05 Mo99*
Ci
<3.05E-03
<2.59E-03
<9.60E-05
<5.17E-05 Ba-la140*
Ci
<6.20E-03
<5.24E-03
<1.95E-04
<1.05E-04 Ag110m*
Ci
<1.92E-03
<1.62E-03
<3.61E-04
<7.48E-05 Na24*
Ci
<1.46E-03
<1.23E-03
<4.59E-05
<2.47E-05 W187*
Ci
<l.78E-03
<1.51E-03
<6.36E-05
<3.03E-05 Sb124*
Ci
<2.09E-03
<1.77E-03
<1.51E-04
<4.80E-05 Sr85*
Ci
<2.12E-03
<1.79E-03
<6.69E-05
<3.61E-05 Csl36*
Ci
<1.69E-03
<1.43E-03
<6.93E-05
<2.87E-05 Z r-Nb 9 7
- Ci
<1.84E-03
<1.55E-03
<6.50E-05
<3.12E-05 Cd109*
Ci
<5.59E-03
<4.75E-03
<1.77E-04
<9.53E-05 Rb 88*
Ci
<4.17E-03
<3.54E-03
<1.37E-04
<7.11E-05 CE-139*
Ci
<3.22E-03
<2.73E-03
<1.02E-04
<5.45E-05 Y-BB*
Ci
<9.60E-04
<8.13E-04
<3.36E-05
<1.63E-05 Total
- Ci
<6.61E-02
<5.60E-02
<3.31E-03
<1.86E-03 Continuous Mode Batch Mode NUCLIDE UNIT QTR 3_
QTR 4_
QTR 3_
QTR 4_
Xel33*
Ci
<1.75E-02
<1.48E-02 7.02E-02 1.08E-01 l
Xe133m*
Ci
<2.49E-02
<2.12E-02
<1.03E-03
<9.67E-03 Xe131m*
Ci
<1.28E-01
<1.09E-01 s6.00E-03
<2.18E-03 Xe135
- Ci
<2.59E-03
<2.19E-03
<9.30E-04
<1.18E-04 Kr85m*
Ci
<3.47E-03
<2.94E-03
<1.09E-04
<5.87E-05 Kr85*
Ci
<5.27E00
<4.45E00
<1.66E-02
<8.95E-03 Kr88*
Ci
<7.25E-03
<6.13E-03
<2.28E-03
<1.23E-03 s.
PINGP 158 Rev, 2 TABLE 2A EFFLUEcT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
- All "less than" numbers are based on the sum of the nulcides actually measured in the release plus the lower limit of detection levels for all other nuclides listed in Reg Guide 1.21 not detected in the release.
TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July 1,1978 through December 31, 1978 Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Shipped Offsite for Burial or Dispasal (not irradiated fuel) 1.
Type of Waste 6 Month Est. Total Unit Period Error %
a.
Spent Resins Ci b.
Dry compressible waste, contaminated ft 6.7E03 equipment, evaporator, bottoms, etc.
Ci 2.3E01
+ 25%
c.
Irradiated components, control rods, ft etc.
Ci None d.
Other (describe) ft Ci None 2.
Estimate of major nuclide composition (by type of waste).
a.
None b.
Co-58 6.3E00 Cs-137 2.5E01 Cs-134 2.0E01 Co-60 1.7E01 Sb-124 1.9E01 Others 1.3E01 None c.
d.
None 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 7
Truck Richland, Washington B.
Irradiated Fuel Shipments (disposition)
None