ML20024F205

From kanterella
Revision as of 00:08, 16 February 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept Jan-June 1983. W/830829 Ltr
ML20024F205
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/30/1983
From: Musolf D
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8309090045
Download: ML20024F205 (9)


Text

_ _ - - - . - - _ _ _ - _ __ __- __ - __-___ _ ______ _

PINGP 158, Rev. 5 Page 1 of 8 Retention: Lifetime EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT January THROUGH 3,in, t on I l

SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60

1. Regulatory Limits
a. Liquid Effluents:
1. The dose or dose commitment to an individual from radio-active materials in liquid effluents released from the site shall be licited:

for the Quarter 3.0 mrem Total Body 10.0 mrem Any Organ for the Year 6.0 aren Total Body 20.0 mren Any Organ

b. Gaseous' Effluents: =
1. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:

Noble Gases 1 500 mren/ Year Total Body 1 3000 mrem /Yesr Skin I-131, H-3, LLP 1 1500 arem/ Year Any Organ

2. The dose due to radioactive gaseous effluents shall be limited to:

Noble Goes 1 10 mead /Qtr Gamma i 20 mead /Qtr Beta i 20 mead / Year Gamma 5 40 mead / Year Beta I-131, H-3, LLP $ 15 mrem /Qtr 1 30 mres/ Year 8309090045 830829 PDR ADOCK 05000282 R PDR fg6 I I

PINGP 158, Rav. 5 Paga 2 of 8

2. Maximum Permissible Concentrations
a. Fission and activation gases in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column 1

b. Iodine and particulates with half-lives greater'than 8 days

('

in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column I

c. Liquid Effluents for radion6clides other than dissolved or entrained gases:

10 CFR 20, Appendix B, Table 2, Column 2

d. Liquid Effluent dissolved and entrained gases:

2.0E-04 pei/ml Total Activity 3.0 Averste Energy Not applicable to Prairie Island Regulatory Limits.

4.0 Measurements and Approximations of Total Radioactivity

a. Fissiod and activation gases Total Geli in gaseous releases: Nuclide Geli
b. Iodines in gaseous releases Total Geli Nuclide Geli
c. Particulates in gaseous Total Geli releases: Nuclide Geli
d. Liquid Effluents: Total. Geli Nuclide Geli BATCH RELEASES
a. Liquid QTR 1 QTR 2 Number of Batch Releases l 6.50E01 5.80E01 l Total Time Period for a Batch Release (br) l 9.66E01 8.63E01 l Maximum Time for a Batch Release (br) l 2.30E00 2.00E00 l Average Time for a Batch Release (hr) l 1.50E00 l 1.50E00 l Minimum Time for a Batch Release (br) l 1.10E00 l 9.00E-01 l Ave Mississippi flow during Quarter (CFS) l 2.82E04 1 3.90E04 l

'. . PINGP 158, R:v. 5

  • Pega 3 of 8
b. Gaseous QTR 1 QTR 2 Number of Batch Releases 1 1_nornn .I  ? norno' l Total Time Period for a Batch Release (br) 11_17Foi i 1_narni l Haximum Time for a Batch Release (hr) l6_anrno l R_nnrnn l Average Time for a Batch Release (br) l 1_90rno i s_Anrnn l Minimum Time for a Batch Release (br) l 2 anron i 9 anrnn l ABNORMAL RELEASES
a. Liquid QTR 1 QTR 2 Number of Batch Releases 1 0.OOFOO l O_OOFOO l Total Activity Release (Ci) l 0.OOEOO O_OOFOO l Total Tritium Release (Ci) 1 0 OOFOO h O_OOFOO l
b. Gaseous 2 QTR _1 __ __ QTR Number of Batch Releases l v . vu t.vu  ; o,oogoo l Tctal Activity Release (Ci) l 0.00E00 l 0.00E00 l i

e

PINGP 158, RIv. 5 Paga 4 of 8 TABLE 1A EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTp 2 'EST TOTAL UNIT l QTR 1 l l l l l l A. Fission and Activation Gases l Total Release Ci l 4.4sF01 l 1_1orn9 l !2.50E0I-l l Average Release Rate pCi/sec l 1. 26 E01 1 1.42E01 l 3.67E-02 8.38E-02 l Gamma Dose arad l l Beta Dose arad 1.35E-01 2.30E-01 l l % of Gamma T.S. Limit l  % l 3.67E-01 8.38E-01 l

.l % of Beta T.S. Limit l  % l 6. 75 E-01 1.15E00 l B. Iodines l Total 1131 Ci l Z . 34 E-04 l 5.16E-03 lt2.50E01 l l__A*:erage Release Rate ' pCi/sec l 2.98E-05 l 6.56E-04 l C. Particulates l Total Release lCi l 3. 46 E-07 l 1.13E-07 l12.50E01 l l Average Release Rate i pCi/sec l 4.40E-U5 l 1.44E-05 l D. Tritium l Total Release lCi l 1.81E01 l 1.88E01 lt2.50E01 l l Average Release Rate l pCi/sec l 2.30E00 l ,2.39E00 l l Total B & C & D l pCi/sec l 1.81E01 l 1.88E01 l!2.50E01 l l Dose l mrem l 5.11E-02 l 4.19E-01 l l % of T.S. Limit l  % 1 3.41E-01 l 2.79E00 l E. Gross Alpha l Total Release lCi l 0.00E00 l 0.00E00 lt2.50E01 l

'. . PINGP 158, Rrv. 5 Pega 5 ef 8 TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS CROUND LEVEL RELEASES CONTINUOUS MODE BATCH N0DE

! l l l l l l l NUCLIDE l UNIT l QTR1 l QTR1 l QTR 1 l QTR2 l l l l l l l l

1. Fission and Activation Gases l Kr85 Ci 9.77E01 l 7.04E-01 l l 7.33E-01 l l Kr85m Ci l l I l l Kr87 Ci l l l l l Kr88 Ci l l l l Xe133 Ci 2.2/EUU 5.90EUl l l Z.33EU1 l l Xe135 'Ci 3.43E-01 4./ZEUU l 6.06E-01 l l Xe135m l Ci l l l Xe138 I Ci l l l l Xe131m Ci l a u r_nq l l l l Ar41 Ci l l l  !

l Xe133m F Ci I 9 tav_ns '

l 1 97p_n1 l l 1 I l l l l  !! I l l l l l l l l l Total I Ci 9.93EU1 l 9.44EU1 l U.UUEE l

4. 3 U t,U1

_l

2. Iodines l 1131 l Ci l 2.34E-04 l 5.16E-03 l l 3.4 7E-06 l l __I133 l Ci l 2.10E-04 l 7.22E-04 l l 5.36E-07 l l 1135 l Ci l I l l l Total l Ci I 4.44E-04 5.88E-03 1 0.00r.09 I 4. 01E-06 l CONTINUOUS MODE BATCH MODE I l l l l l l l NUCLIDE l UNIT l QTR 1 l QTR 2 l QTR 1 l QTR 2 l l l l l l l l
3. Particulates l Sr89 I Ci 3 9ar_ny l l Sr90 l Ci l' AW_no l l Cs134 l Ci l l l l l Cs137 I Ci l l l l l Ba-La140 l Ci l l l l,CoS8 l Ci  ? 1?r_n7 1 inr_n? I l l

, l Co60 1 Ci l l l l 1 1 I I l l l l Total I Ci l 3.46E-07 1.13E-07 1 0.00E00 l 0.00ECO l

s^

PINGP 158, Rzv. 5 Page 6 of 8 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL REL~2SES l UNIT l QTR 1 l QTR 2 lE l l l l l A. Fission and Activation Products l Total Release W/0 H-3, I l  !

l Rad Gas, Alpha ci 2.10 E-04 2. 39 E-03 l !2.50E01 Ig l l l Average Diluted i l pCi/ml 6.05E-14 5.24E-13 l Concentration I B. Tritium l Total Release Ci l 1.12E02 1.66E02 !2.50E01 l

  • '8' *d '
pCi/ml 3.23E-08 3.64E-08 l Total A & B l pCi/ml l 3.23E-08 l 3.64E-08 l l Total Body Dose' l mrem l 2.39E-04 l 4.36E-04 l l Critical Organ Dose l mrem l 4.80E-04 l 1.57E-03 l l l Organ l GI l THYROID l l % Total Body T.S. Limit l  % l 7.93E-03 l 1.45E-02 l l % of Critical Organ l g l l l l T.S. Limit l l 4.80E-03 l 1.57E-02 l C. Dissolved and Entrained Gases l Total Release l Ci l 3'HE-0) l /.23E-02 ltZ.50 E01 l l Average Diluted l l l Concentration lE'"

l ll 1.50E-14 l 1.59E-ll l D. Gross Alpha l Total Release l Ci l O 00'00 l u.uur.vu ltz.3ucul l E. Volume of Waste (Prior to Dilution) l Liters 1 3.22E07 l 2.71E07 62. 50 E01 l F. Volume of Dilution Water l Liters l 3.47E12 l 4.56E12 h2.50E01 l

.- 6' -

PINGP 158, Rsv. 5 Page 7 of 8 TABLE 2A h~

EFFLUENT AND WASTE DISPOSAL 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 1 l QTR 2 l QTR1 l QTR 2 l l l l l l l l l Sr89 l Ci l i 1 l l Sr90 Ci l l

l Cs134 Ci 8.10E-06 l l Cal 37 Ci 8.88E-06 l l 1131 Ci 1.58E-04 1 1.86E-03 l

,l'CoS8 Ci 5.95E-05 1.08E-05 2.62E-04 l

.l Co60 Ci 4.94E-06 1.78E-04 4.05E-06 l l Fe59 Ci I '

l l Za65 Ci '

l l l Mn54 '

Ci l l Cr51 Ci l l Zr-Nb95 Ci l l 1.58E-05 l l Mo99 Ci l l l Ba-La140 l Ci ll 11 l l

-l Tc-99m I Ci 11 l l _,Ce- 141 Ci l l I-133 = Ci l 2.57E-05 l l Total Ici I 4.94E-06 l 2.18E-04 l 2.05E-04 1 2.17E-03 l CONTINUOUS MODE BATCH MODE l l l l l l l l NUCLIDE l UNIT l QTR 1 l QTR 2 l QTR 1 l QTR 2 l l l l l l l l

.l.Xe133 l Ci l l 2.89E-05 l 7.llE-02 l

.l Xel33m l Ci l -l 1 3.76E-04 l

-l Xel31m l Ci l ll l 1.70E-05 5.43E-04 l l Xel35 l Ci l l 5.96E-06 1 2.80E-04 l l Kr85m l Ci l l l Kr85 l Ci l l l Kr88 l Ci l l l 1 l

l I l l 1 l l l- 1 l l l l l l Total I Ci 1 0.00E00 1 0.00E00 l 5.tqE-Os l 7.23E-02 l

___.__.___d_..________._ _ - - - - -

'i~ '

PINGP'158, Rzv. 5 Pega 8 of 8 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID RADIOACTIVE WASTE SEMI-ANNUAL REPORT JAN 1981_ THROUGH 3rm ions Volume 1 i Percent Container (FT3) Curie Quantity Radionuclides Abundance Type Quantity CEMENTED 1.11E 03 1.31E01 Co 60 9.16E01 DOT 7A 1.34E02 WASTE Cs 134 9.90E-01 TYPE A Cs 137 6.39E-00 55 GAL Mn 54 1.02E00 AND 83 GAL DRUM COMPACTED 2.37E03 2.29E00 Ag110M 3.77E00 DOT 7A 3.22E02 TRASH Cs 137 4.24E00 TYPE J Co 58 2.94E00 55 GAL Mn 54 1.10E00 DRUM Co 60 8.79E01 DEWATERED 3.30E02 4.53E00 Co 60 9.72E01 3.00E00 RESIN Mn 54 1.01E00 Cs 137 1.80E00 STEEL LINER NON-COMPACTED 2.14E03 3.20E-01 Sb 124 7.51E-01 WOOD 2.20E01 TRASH Ag 110M 3.47E00 AND Cs 137 3.00E00 METAL Nb 95 8.35E-01 BOXES Co 58 3.49E01 Mn 54 2.16E00 Co 60 5.49E01 Tetal Volume s agA3 FT3 Tc*al Curie Content 7.ngmi Curies 1

Curie Quantity and Radionuclides are measured not estimated

/

Dfn G Northem States Power Company 414 Nicollct Mall Minneapoks. Minnesota 55401 Telephone (612) 330-5500 August 29, 1983  ;

D/RA i 6 .i l A //i; 4  ! j 6.L . I i A

Regional Administrator  ; i 4

Region III -ib[.x..  :  ;;k ~

U S Nuclear Regulatory Commission C: l l i j 799 Roosevelt Road ka j t <

Glen Ellyn, IL 60137 7C~l t.2illiX6d PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semiannual Report for January 1. 1983 through June 30, 1983 In accordance with the Prairie Island Technical Specifications, Appendbc A to Operating Licenses DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semiannual Report covering the first half of 1983.

b Nu David Musolf Manager - Nuclear Support rvices D!Bf/bd cc: Document Control Desk, USNRC (1)

Project Manager, USNRC Resident Inspector, USNRC

, G Charnoff MPCA Attn: J W Ferman g Attachment j ,

i

/

S e

4