ML20246Q233

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Amend to, Effluent & Waste Disposal Semiannual Rept for Second Half,1988
ML20246Q233
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/1988
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20246K241 List:
References
NUDOCS 8909110396
Download: ML20246Q233 (14)
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Text

{{#Wiki_filter:_ -. jo;_ !1 ANENDNENT to the PRAIRIE ISLAND Effluent'and Waste Disposal Seniannual Report . (for'the 2nd Half year of 1988) This report is being resubmitted to address discrepancies between the report filed to update the composite results and the report submitted to correct the airborne tritium problem detected in 1988. This report also provides the previously omitted 4th quarter analyses results of Sr-89 and Sr-90. \\. 1 h f h I 8909110396 890828 PDR ADDCK 05000282 ' PDR R

.I ' f: y 4 '1'9885EffluentjSamiannual'_ Report REV.E3 -S ir Pag 311 of 8-Re terition: - Lif e time '"~ A, . EFFLUENT' SEMIANNUAL REPORT ~ R 1-JUL-88 THEOUGH 31-DEC-88: ) i SUPPLEMENTAL INFORMATION. j 1 i Facility: ~Pra(rie~ Island-Nuclear Generating Plant ) Licensee: Northern States Power Company l i License Numbers: DPR-42'&'DPR-60 + 1 V

A. Regulatory Limits J

-{ l. Liquid Effluents: 1 1 a. The doseLor dose commitment to an individual'from radioactive materials in liquid effluents released from the site.shall be l limited to. i forithe quarter 3.0 mrem to the' total. body i 10.0 mrem to'any organ-j for'the year-6.0 mrem to the total body 20.0 mrem to any organ 2 Gaseous Effluents: a. The dose rate due to radioactive materials released in ' gaseous effluents from the site shall be limited to: l 3 noble gases 4500 mrem / year total body 43000 mrem / year skin j l I-131, H-3, LLP. 41500_ mrem / year to any organ a b. The dose due to radioactive gaseous effluents shall be limited to: noble gases (10 mrad / quarter gamma 420 mrad / quarter beta 420 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP 415 mrad / quarter 430 mrad / year i

MQ 1988; EFFLUENT SEMIANNUALLREPORT-REV. : 3' PAGE 2-

e B.

-Maximum Permissible-Concentration. 1. Fission and activation gases in gaseous releases: l 110,CFR 20, Appendix =B, Table 2, Column 1 4 2. Iodine.and particulate with: halflives 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: 10cCFR 20, Appendix B,-Table 2', Column 2 4. Liquid effluent ~ dissolved and entrained gases: 2.0E-04 uCi/ml Total Activity .C. Average Energy. Not applicable to Prairie Island regulatory limits. D. Measurements and approximations of total activity 1. Fission and activation gases Total GeLi i25% in gaseous-releases: Nuclide GeLi 2. Iodines in gaseous releases: Total GeLi 25% Nuclide GeLi .3.-' Particulate'in-gaseous releases: Total GeLi 25% Nuclide GeLi 4. Liquid effluents. Total GeLi 25% Nuclide GeLi L____-___________

h.4 1988(EFFLUENT SEMIANNUAL REPORT' REV.J3 PAGE 3 '..( '14 0 ; BATCH RELEASES.(LIQUID) QTR: 03-QTR: 04 ~ 1.1 NUMBER OF BATCH-RELEASES. 6.70E+01 3.90E+01 1.2 TOTAL TIME PERIOD (HRS) 1.12E+02 6.41E+01 1.3 MAXIMUM TIME PERIOD (HRS) 3.30E+00 2.20E+00 '1. 4 ~ AVERAGE TIME PERIOD (HRS) 1.68E+00 1.64E+00 115' MINIMUM TIME PERIOD (HRS) 7.00E-01 1.30E+00 1.6 ' AVERAGE MISSISSIPPI RIVER FLOW (CFS) 4.73E+03 7.20E+03 i I 2.0 BATCH RELEASES (GASEOUS) QTR: 03 QTR: 04 2.1.: NUMBER OF BATCH RELEASES 2.00E+01 9.00E+00 2.2 TOTAL TIME PERIOD (HRS) 3.50E+02 3.52E+01. 2.3 MAXIMUM TIME PERIOD (HRS) 1.68E+02 2.08E+01 2.~4 ' AVERAGE TIME PERIOD (HRS) 1.75E+01 3.91E+00 2.5 MINIMUM TIME PERIOD (HRS) 5.56E-03 2.00E-02 3.0 ABNORMAL RELEASES (LIQUID) QTR: 03 QTR: 04 3.1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 L4.0 ABNORMAL RELEASES (GASEOUS) QTR: 03 QTR: 04 4.1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 - 4.' 2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 l

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11988' EFFLUENT SEMIANNUAL' REPORT REV. 31 PAGE 4' ' ~ ' . TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES L QTR: 03 QTR: 04 5.0 : FISSION AND ACTIVATION GASES 5.1 TOTAL. RELEASE (CI) 1.64E-02 2.20E-02' 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.09E-03 2.80E-03 5.3. GAMMA DOSE (MRAD) 4.29E-06 3.70E-06~ 5.4 BETA DOSE (MRAD) 1.25E-04 1.74E-04 5.5 : PERCENT OF GAMMA TECH SPEC (%) 4.29E-05 3.70E-05. 5.6 PERCENT OF BETA TECH SPEC (%) 6.25E-04 8.70E-04 6.0 IODINES-6.1 TOTAL I-131 (CI) 2.40E-07 3.10E-07 6.2-AVERAGE ~ RELEASE RATE (UCI/SEC) 3.05E-08 3.94E-08 7.0 PARTICULATE 7.1 TOTAL RELEASE (CI) 6.90E-05 5.95E-06 7.2 AVERAGE RELEASE RATE (UCI/SEC) 8.78E-06 7.57E-07 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 5.12E+01 3.11E+01-8 :2 AVERAGE RELEASE RATE (UCI/SEC) 6.51E+00 3.96E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 6.51E+00 3.96E+00 10.0 DOSE (MREM) 1 26E-01 5.60E-02 11.0 PERCENT OF TECH SPEC (%) 8.40E-01 3.73E-01 .12.0 GROSS ALPHA (CI) 1.24E-07 1.65E-07 w

-1988: EFFLUENT SEMIANNUAL REPORT' REV. 3 PAGE 5 ~

TABLE 1C ~

GASEOUS EFFLUENTS --GROUND LEVEL RELEASES- .13.0L FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS .QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI '1.42E-02 2.05E-02 XE-133 CI 2.20E-03 1.51E-03 XE-133M' CI-636E-06 XE-135-CI: 2.27E-06 TOTAL CI 0.00E+00 0.00E+00 1.64E-02 2.20E-02: 14.0 IODINES - CONTINUOUS. MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131-CI 2.40E-07 3.10E-07 TOTAL CI 2.40E-07 3.10E-07 0.00E+00 0.00E+00 15.0 PARTICULATE CONTINUOUS MODE BATCH MODE-NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 CD-109 CI 4.81E-06 CO-58 CI 3.79E-08 CO-60 CI 3.94E-07 1.14E-06 C3-137. CI 2.10E-07 7.90E-10 SR-89 CI 6.60E-05 SR-90 CI 5.88E-08 2.31E-06 TOTAL CI 7.01E-07 5.95E-06 6.83E-05 7.90E-10 a a_.

i 1988 EFFLUENT SEMIANNUAL' REPORT. REV. 3 PAGE 6' 4 ' TABLE 2A ) I LIQUID EFFLUENTS - SUMMATION OF_ALL. RELEASES i 4 l QTR: 03 QTR: 04 16.0. VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 5.62E+07-2.25E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.49E+11 1.75E+11 ' 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 2.17E-01 1.98E-02 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.46E-09 1.13E-10 19.0 TRITIUM 19.1 ' TOTAL RELEASE (CI) 6.21E+01 1.21E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4.16E-07 6.92E-07 - 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI)- 5.01E-04 2.31E-03 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 3.36E-12 1.32E-11 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 4.16E-07 6.92E-07 23.0 TOTAL BODY DOSE (MREM) 3.91E-04 3.05E-04 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 1.48E-03 1.09E-03 24.2 ORGAN BONE GI-LLI - 25.0 PERCENT OF TOTAL BODY TECH SPEC. LIMIT (%) 1.30E-02 1.02E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 1.48E-02 1.09E-02 1 = _ - - _

1988 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 7

TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 AG-110M CI 5.06E-04 4.13E-04 BE-7 CI 6.11E-05 2.76E-05 CO-58 CI 8.04E-04 2.01E-03 Co-60 CI 4.98E-04 7.83E-04 CR-51 CI 4.59E-04 5.74E-04 CS-138 CI 9.68E-06 FE-55 CI 2.09E-01 1.36E-02 FE-59 CI 1.26E-03 1.05E-03 MN-54 CI 1.63E-05 6.06E-05

.NA-24 CI 1.74E-05 NB-95 CI 1.29E-05 4.14E-05 NB-97 CI 8.99E-06 8.79E-06 RH-105 CI 3.77E-06 5.74E-06 SB-122 CI 8.20E-05 SB-124 CI 1.03E-03 2.29E-04 SB-125 CI 2.38E-03 1.66E-04 SC-47 CI 1.68E-04 7.01E-03 SN-113 CI 5.12E-04 6.59E-04 SR-89 CI 2.43E-04 SR-90 CI 1.13E-05 SR-92 CI 8.71E-06 ZN-65 CI 1.08E-05 1.07E-05 ZR-95 CI 7.88E-06 3.74E-05 ZR-97 CI 1.47E-05 1.24E-05 TOTAL CI 2.54E-04 0.00E+00 2.17E-01 1.98E-02 l r ___,______m_

~ '1986 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 8 . TABLE 2A (CONTINUED) LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 28.0 DISSOLVED AND ENTRAINED GASES ~ CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 AR-41 CI 1.78E-06 KR-85M CI 2.65E-06 XE-133 CI 4.87E-04 1.90E-03 XE-135 CI 1.46E-05 4.01E-04 TOTAL CI 0.00E+00 0.00E+00 5.01E-04 2.31E-03 l l l I l 1 1 i

(,. d.R >.n ! ~ b' PINGP 753, Rev. 1. .. Retention: Lifetime-

Page 1 of 5 PRAIRIE ISLAND ~ NUCLEAR GENERATING PLANT Period: 7-1-88 to 12-31-88

' NORTHERN STATES POWER License No. DPR-42 (1 4 ~ SOLID RADI0 ACTIVE-WASTE DISPOSAL SEMI-ANNUAL REPORT k Table I:- Solid Waste and Irradiated Fuel Shipments -V.;4 eft *fiRi%requm*W sum ;2:: druimamrd 22Mstm4WM ;'fp@pe;iW;;.esqq A. Solid' Waste Total Volumes and Measured Curie Quantities: 1.. Type of Vaste: Container. E Units Total Volumes A. Bead Resins ft 3 998.3 5@ 172.5/135.8 C1 134.59 .B. C.- Non-comoscted Daw ft 3 97.2 96 Ci 0.334 D.- Filter media ft 3 163.3 163.3 C1 1.6a1 .S. t P e 4 _~..n,N- - -. _ - - -.. = _. - - - _. _, - - - _ _. - - - -. _. -.. - - - _ _... _ - - - - _ - - - -. _ - - - _ _ - _ _ _ _ - - _ - _ _ _ _ _.. - _ _ _ _ - _ _

m; PINGP 753, Rev. 1 Retention: Lifetime Page 2 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-88 to 12-31-88 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:

r..-me w.m.e.sM:-TYPE *(From-Pagel)'+~?"+ F*F"'iwNuclide's @ le Percent 99790N't' A

C060 35.8 CS137 25.2

  • NI63 20.6
  • FE55 10.6 CS134 6.4 SB122 0.5
  • H3 0.5 MN54 0.2
  • C14
0. ?.
  • H3 40.5 C
  • FE55 28.7
  • NI63 16.0
  • C14 3.8 C060 7.9 S3125 0.7 C058 0.8
  • = Inferred - Not Measured on Site

v .PINGP'753, Rev. 1 Retention: Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-88 to 12-31-88 . 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 Vaste (Cont.nuation): 4 ' ~~ '"#N fn:!ENE?(FroE' Pig'e'1)'#259*'* N#d&t!!!fNtMlideW"4 Percent 'WDFt-T

  • FESS 44.6 D
  • H3 25.4 C060 17.0
  • NI63 4.8
  • cla 3.7 CS137 1.4 SB125 0.9 AG110M-0.7 CS134 0.5 l

l

  • = Inferred - Not Measured on Site N:-_-_ ___- __ ____

R PINGP 753, Rev. 1 Retention: Lifetime Page 4 of-5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Per ' 7-1-88 to 12-31-88 NORTIERN STATES POWER Lice..de No. DPR-42 SOLID RADIOACTIVE VASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued) 3. Solid Waste Disposition: _..._e.- Number. o f Shipments.

s. rMode y '::;.g.== t Destination ' '

" ?;s '~ 2 TRUCK Scientific Ecology Group TRUCK Bar=well, SC 6 TRUCK Richland, WA B. Irradiated Fuel Shipments: Number of Shirments Mode Destination 0

r, PINGP 753, Rev. 1 Retention: Lifetime Page 5 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-88 to 12-31-88 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SElil-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 87-39 66.60 0.1499 C L N/A 87-40 30.60 0.1840 C L N/A 88-25 172.50 3.0030 A L N/A 88-26 172.50 2.3500 A L N/A ~ 88-27 172.50 1.5600 A L N/A 88-29 163.30 1.6810 D L N/A 88-30 172.50" 1.5620 A L ~s71~ '~ 88-31 172.50 1.4140 A L N/A ~ 88-32 135.80 124.7000 A B N/A TOTALS 9 1258.80 136.6039 CONTAINER CODES: L = LSA A = Type A B = Type B Q = Large Quantity SOLIDIFICATION CODES: C = Cement TYPES OF WASTE: A = Resins B = Dry Compacted C = Non-Compacted , D = Filter Media i S = Spent Fuel l - - - - - - - - - - - - - _ - _ _ _ _ _ _ _ _ - _ _. _ _ _}}

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