ML20246K236

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Forwards, Effluent & Waste Disposal Semiannual Rept for Jan-June 1989, Revised Repts for 1988,1987 & 1985 & Revised Offsite Dose Calculation Manual
ML20246K236
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/28/1989
From: Fey F
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20246K241 List:
References
NUDOCS 8909050412
Download: ML20246K236 (14)
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Text

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'U Northem States Power Company J 414 Nicollet Mail Minneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 August 28, 1989 Prairie Island Technical Specification TS6.7A S&6 U S Nuclear Regulatory Commission Attention: Document Control Desk Washington, D C 20555 Prairie Island Nuclear Generating Plant Docket No. 50-282 License No. DPR-42 Docket No. 50-306 License No. DPR-60 Effluent and Waste Disposal Semiannual Report fpr January 1, 1989 throuah June 30, 1989 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semiannual Report, covering the first half year of 1989.

Analyses for isotopes Sr-89 and Sr-90 for the 2nd quarter were not completed in time to be included with this report. These analyses results are not expected to significantly change the computed off-site doses, and will be included with the next semiannual report.

Enclosed with this report are amendments to previously submitted Effluent and Waste Disposal Semiannual Reports for 1988, 1987, and 1985 as requested by Chuck Gill of your staff. A cover page with a description brief is attached for each amended reporting period.

The ODCM has also been revised during this reporting period. A '

copy of the ODCM Revision 10, and description summary of the manual changes are included. A copy of the PCP is not attached since it remained unchange during the reporting period.

J 0)

f os :4fg 3 F . L. Fey, Jr., Manager Nuclear Radiological Services Attachment i l 8909050412 890630 PDR ADDCK 050002G2 R PNU

.v. 1 l1989fEffluentiScmicnnual Report l .Rev. 0 4( ,

'iP agafl of'8

g Retention
Lifetime.

EFFLUENT SEMIANNUAL REPORT

.01-JAN-89 THROUGH 30-JUN-89

' SUPPLEMENTAL INFORMATION Facility: Prairie ~ Island Nuclear Generating Plant Licensee: Northern States Power Company.

' License Numbers: EFa-42 & DPR-60 A. Regulatory Limits.

1. Liquid' Effluents:
a. The dose or dose commitment t'o an individual from radioactive materials in liquid effluents released from the site.shall'be.

limited to:

for the quarter 3.0 mrem to the total body 10.0 mrem to any organ 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:

noble gases (500 mrem / year total body 43000 mrem / year skin I-131, H-3, LLP (1500 mrem / year'to any organ

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

noble' gases (10 mrad / quarter gamma (20 mrad / quarter beta (20 mrad / year gamma (40 mrad / year beta I-131, H-3, LLP (15 mrad / quarter (30 mrad / year L. . . .

?"

L-k[ <l'9895 EFFLUENT SEMIANNUAL REPORT' -REV. O ~ PAGE12

~.- .

B. ' Maximum Permissible Concentration-

1. Fission and activation gases in gaseous releases:

10 CFR 20, Appendix B, Table 2,. Column 1:-

2 . - Iodine and particulate with halflives greater than
8. days.in gaseous releases:

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

3. -Liquid e'ffluents.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 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- . 25%

-in" gaseous releases:

'Nuclide GeLi 2'. ~ Iodines in gaseous releases: Total GeLi- 25%'

Nuclide GeLi L 3. Particulate-in gaseous releases: Total GeLi 25%

L.

Nuclide GeLi

4. Liquid effluents Total. GeLi- 25%

Nuclide GeLi l

-l l

l

1989LEFFLUENT SEMIANNUAL REPORT REV. O PAGE 3 1.0 BATCH RELEASES (LIQUID) QTR: 01 QTR: 02 1.1 NUMBER OF BATCH RELEASES 3.40E+01 5.10E+01 1.2 TOTAL TIME PERIOD (HRS) 5.31E+01 7.92E+01 1.3 MAXIMUM TIME PERIOD (HRS) 1.97E+00 2.12E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.56E+00 1.55E+00 1.5 MINIMUM TIME PERIOD (HRS) 2.00E-02 1.27E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 6.01E+03 6.57E+03 2.0 BATCH RELEASES (GASEOUS) QTR: 01 QTR: 02 2.3 NUMBER OF BATCH RELEASES 6.00E+00 1.80E+01 2.2 TOTAL TIME PERIOD. (HRS) 1.00E+01 1.04E+02 2.3 MAXIMUM TIME PERIOD- (HRS) 6.70E+00 1.93E+01 l 2.4 AVERAGE TIME PERIOD (HRS) 1.67E+01 5.81E+00 2.5 MINIMUM TIME PERIOD (HRS) 2.00E-02 5.28E-03 l 3.0 ' ABNORMAL RELEASES (LIQUID) QTR: 01 QTR: 02 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 1

4.0 ABNORMAL RELEASES (GASEOUS) QTR: 01 QTR: 02 4.1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 I

l

[ ,. 1989 EFFLUENT _ SEMIANNUAL REPORT REV. O PAGE 4

. TABLE 11A

-GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 8.16E-02 1.29E+02 5.2 AVERAGE RELEASE RATE (UCI/SEC) 1.04E-02 6.10E-01 5.3 GAMMA DOSE (MRAD) 1.02E-04 5.70E-03 5.4 BETA DOSE'(MRAD) 4.17E-04 1.61E-02 5.5 PERCENT OF GAMMA TECH SPEC (%) 1.02E-03 5.70E-02 5.6 PERCENT OF BETA TECH SPEC (%) 2.09E-03 8.05E-02 6.0 IODINES 6.1 TOTAL I-131 (CI) 6.74E-07 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 8.58E-08 0.00E+00 7.0 PARTICULATE 7.1 TOTAL RELEASE (CI) 1.71E-06 0.00E+00 7.2 AVERAGE RELEASE RATE (UCI/SEC) 2.18E-07 0.00E+00 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 2.12E+01 2.79E+01 0.2 AVERAGE RELEASE RATE (UCI/SEC) 2.70E+00 3.55E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.70E+00 3.55E+00 10.0 DOS 2 (MREM) 3.83E-02 5.02E-02 l

11.0 PERCENT OF TECH SPEC (%) 2.55E-01 3.35E-01 12.0 GROSS ALPHA (CI) 1.75E-08 4.99E-08

______--_ _ - D

,, .1989 EFFLUENT' SEMIANNUAL REPORT .REV. O PAGE 5

. TABLE'1C

-GASEOUS EFFLUENTS - GROUND LEVEL RELEASES l

13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE.

NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 92 AR-41 CI 1.17E-02 KR-85 CI 1.4SE-02 3.47E-02 KR-85M CI 1.45E-0E 3.28E-06 XE-131M- CI 4.87E-04 7.14E-03 XE-133 CI 1.25E+01 6.54E-02 3.38E-01 XE-133M CI 8.47E-04 2.14E-03 XE-135 CI 3.98E-04 1.18E-03 TOTAL CI 0.00E+00 1.25E+01 8.16E-02 3.95E-01 14.0 IODINES CONTINUOUS MODE EATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 r

I-131 CI 6.74E-07 TOTAL CI 6.74E-07 0.00E+00 0.00E+00 0.00E+00 15.0 PARTICULATE CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 CO-60 CI 1.30E-06 CS-137 CI 4.13E-07 TOTAL CI 1.71E-06 0.00E+00 0.00E+00 0.00E+00

1989' EFFLUENT' SEMIANNUAL REPORT REV. 0 -PAGE 6 j

z. TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 16.0 VOLUME OF NASTE PRIOR TO DILUTION (LITERS) 4.04E+07 4.21E+07

( -17.0 VOLUME OF DILUTION HATER (LITERS) 1.29E+11 7.95E+10 l

18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.12E-01 2.81E-02 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 8.68E-10 3.53E-10 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 6.20E+01 1.05E+02

.19.2 AVERACE DILUTED CONCENTRATION (UCI/ML) 4.81E-07 1.32E-06 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 5.11E-03 2.89E-02 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 3.96E-11 3.64E-10 1989 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 7 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 4.81E-07 1.32E-06 23.0 TOTAL BODY DOSE (MREM) 2.60E-04 3.12E-04 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 2.60E-04 1.53E-03 24.2 ORGAN TTL BODY BONE l

l 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 8.67E-03 1.04E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 8.67E-03 1.53E-02 1

1989 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 7

. TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 AG-110M CI 3.27E-05 6.48E-04 CO-58 CI 2.30E-04 1.46E-03 CO-60 CI 1.26E-04 6.25E-04 CR-51 CI 5.55E-04 CS-134 CI 9.74E-08 CS-137 CI 5.56E-07 FE-59 CI 4.07E-04 1.69E-03 FE-55 CI 1.11E-01 1.45E-02 I-131 CI 2.96E-05 MN-54 CI 1.27E-06 4.00E-05 NB-95 CI 3.10E-05 NB-97 CI 9.11E-06 7.95E-06 SB-122 CI 5.86E-06 2.99E-05 SB-124 CI 8.88E-05 8.05E-04 SB-125 CI 2.44E-04 4.51E-04 SC-47 CI 2.48E-06 1.16E-04 SN-113 CI 1.22E-04 6.05E-04 SR-89 CI 6.55E-03 SR-92 CI 1.50E-06 ZR-97 CI 6.52E-06 TOTAL CI 0.00E+00 0.00E+00 1.12 E -01 2.81E-02

S

,, 1989 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 8 l

. TALLE 2A (CONTINUED)

. LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

~28.0 DISSOLVED AND ENTRAINED GASES ,

. CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 AR-41 CI 3.09E-06 KR-85M CI 5.58E-06 XE-131M CI 6.28E-O' XE-133 CI 4.53E-03 2.80E-02 XE-133M CI 7.67E-05 1.85E-04 XE-135 CI 5.01E-04 9.57E-05 TOTAL CI 0.00E+00 0.00E+00 5.11E-03 2.89E-02

m.y.

  • , LPINGP 753. Rev.-'2.

. Page:1- of: 5 V.,  : Retention: Lifetime

~

', = PRAIRIE ISLAND. NUCLEAR. GENERATING PLANT Period: 1-1-89 to 6-30-89 NORTHERN STATES POWER- License No. DPR ' SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT l

Table I: Solid Waste and Irradiated Fuel Shipments

1. ' Solid! Waste Total Volumes and' Total Curie ~ Quantities:

.I l l 1 Container l ..

l I l Disposal 1 I ' Type of Waste'- l Units l Totals ~ l'l Volumes 1

-l (List) l^

3 A. Resins- I ft g  ; l l l 1 I l-l 1. Ci j ,l l l- l l l l-1 I i i 1.

l- 1 I 3

.B. Dry-Compacted ft  ;

I l Ci- l l- 1 I I l l 'l

'l- 1 I I l l I C. Non-Compaeted I ft i.329.3 l 96 l l l l l l' l l Ci l . 0.11021 _ l i I I I .I I I I I I I I I 3

l D. Filter Media j ft  ;  ;  ;

I I I I i l l Ci l 1 I 1 l l 1 l

.I I I I I l l 3 ;  ;  ;

1'S. Spent Fuel l ft I I I I l

.I' I Ci l l l

l. I I I I O l- l l l l IBM

~-- -~-~-' ~ -~ - -

fp.. , % .;

. , ,:j PINGP 753,.Rev.l2-

. Page :27 >

, 'z: _

i(h Y PRAIRIE - ISLAND NUCLEAR - GENERATING PLOTT Perio'd : 1-1-89 to '6-30 . NORTHERN-STATES' POWER License No. DPR-42

SOLID RADIOACTIVE' WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1
Solid. Waste and Irradiated Fuel-Shipments (Continued) .
2. Principal Radionuclides Composition by Type of. Waste:

TYPE (From Page 1) Percent Nuclide Abundance C

  • Pn-55 10.2-n 8 . 5 ,__

Co-60 6.4

  • Ni-63 2.4 An-110m 2.0 Sb-125 0.8 Co-58 0.7 Cs-137 0.3-O 1

1 :-.

O ~

  • = Inferred - Not Neasured on Site e IBM l~

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l: 'PINGP 753,'Rev.:2'

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i:4

. iPage 3-lf -

fy L- )'# ~ PRAIRIE ISLAND NUCLEAR GENERATING PLANT

. NORTHERN STATES POWER Period: 1-1-89 to 6-30-89 License No. DPR ,

SOLID' RADIOACTIVE WASTE' DISPOSAL' SEMI-ANNUAL REPORT J Table I: . Solid Waste and Irradiated Fuel. Shipments.(Continued)

L- 2. Principal Radionuclides Composition by Type of Waste (Continuation):

Percent l' T'IPE (From Page 1) Nuclide. Abundance 1

'l i

t O

  • = Inferred - Not Measured on Site l

IBM -

L w---_-__- _ _ _ _ _ _ - _ _ _ _ - - _ _

6.

PINGP 753, Rev. 2 Page 4

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-89 to 6-30-89 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 2 TRUCK QUADREX RECYCLE CENTER

4. Irradiated Fuel Shipments:

[}

%._./

Number of Shipments Mode Destination 0

i.

I s /

IBM L__________._._________..____.

m f 9 .- ~

PINGP 753, Rev. 2 l

,,- Page 5

\_,)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-89 to 6-30-89 {

NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

5. Shipping Container and Solidification Method:

Disposal No. Volume Activity Type of Container Solidif.

(Ft3) (Ci) Waste code Code 88-34 19 9 . _8_ __ 0.0723 r- L N/A 88-35 129.3 0.0384s C L N /A

,/~\

LJ TOTALS 2 329.3 0.11075 CONTAINER CODES: L = LSA (Shipment Type) A = Type A B = Type B Q = Highway Route Controlled Quantity SOLIDIFICATION CODES: C = Cement TYPES OF WASTE: A = Resins

,/~3 B = Dry Compacted

'y/ C = Non-Compacted D = Filter Media S = Spent Fuel IBM

_ _ - _ - . . _ _ _ _ _ _ _ _ _ _ -______--________________-_J

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