ML20028G842

Effluent & Waste Disposal Semiannual Rept for Jan-June 1990

ML20028G842
Person / Time
Site:	Prairie Island
Issue date:	06/30/1990
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20028G841	List: ML20028G840 ML20028G842 ML20028G843
References
NUDOCS 9009050107
Download: ML20028G842 (17)

Text

]

i TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY

~

NUCLEAR GENERATION DEPARTMENT ERAIRIE ISLAND NUCLEAR GENERATING PLANT Effluent and Waste Disposal Sealannual Report (gr January 1. 1990 throuah June 30. 1990 Manifest Date: August 29, 1990 USNRC.

4 ANI Library 1

Re!!ional Admin-III.

FPSI 3

NRR Project Manager C E Agan DCD A Garrow Resident Inspector Corporate Library Shaw Pittman Potts &

c Trowbridge 1

1 M E Reddemann 1

J Silberg 1

Westinghouse Electric 2

P H Kamman 10 W J Johnson Prairie Island Plant Manager

.Monticello Plant Manager 1^

R T Meyer c

-ERAD Dept.

1 Safety' Audit Committee.

9 Attn: Records Clerk T M Parker Media Services IJept.

1 K J Albrecht NRS File 1

.C W Giesler NSS File 1

H S Isbin-f

.MDH 1

-F W Hartley 1

' Attn: Commissioner of Health J A Thie

-MPCA 1

F P Tierney Attn: J W Ferman Secretary.

G H Neils File (Manifest only) i l

.i 90090501o7 900829ADOCKoSoogg2 PUR R

at

.. s l'990 EffluWnt S63iannual Report REV. O P0g311 cf:9 Retention 1 Lifetime EFFLUENT SEMIANNUAL REPORT to 31-DEC-89 THROUGH 30-JUN-90 SUPPLEMENTAL INFORMATION Facility:-

Prairie Island Nuclear Generating Plant Licensee:

Northern States Power Company License Numbe~rs: DPR-42 & DPR-60 A.-Regulatory Limits 1.

Liquid Effluents:

4 a.

The dose or dose commitment to 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 s

l 20.0 mrem to any organ

'2.

Gaseous Effluents:

a.

The dose rate due to radioactive materials-released in gaseous efflue.its from the site shall be limited to:

noble gases 4500 mrem / year total body l

43000 mrem / year skin l

=

I-131, H-3, LLP 41500 mrem / year to-any organ l

b.

The dose due to radioactive gaseous effluents shall be p

limited to:

i 4

noble gases 410 mrad / quarter gamma 420 mrad / quarter beta 420 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP (15 mrem / quarter to any organ a

430 mrem / year to any organ

?'.,

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l'990fEFFLUENT StMIANNUAL REPORT REV. Or PAGE 2' I

B.-

_ Maximum Permissible Concentration ll.

Fission and' activation gases in gaseous releases:-

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

-2.-

Iodine.and particulates with halflives gres e r 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 uCi/ml Total Activity i

C.

Average-Energy l

Not applicable to Prairie Island regulatory limits.

l p

D.

Measurements and approximations of total activity 1.

Fission and activation gases Total GeLi 125%

in gaseous releases:

Nuclide GeLi 2.

Iodines.in gaseous releases:

Total GeLi t25%

L Nuclide-GeLi i

3.

Particulates in gaseous releases:

Total GeLi 125%

Nuclide GeLi 4.

Liquid effluents Total GeLi 125%

Nuclide GeLi

...a 1'990LEFFLUENT SEMIANNUAL' REPORT REV.'O

-PAGE 3-

1. 0 : BATCH RELEASES-(LIQUID)-

QTRi 01 QTR: 02 1.1 NUMBER OF BATCH RELEASES 7.70E+01 3.60E+01-1.2 TOTAL TIME PERIOD (HRS) 1.25E+02-6.39E+01-

1. 3 - MAXIMUM TIME PERIOD' (HRai 2.75E+00 7.47E+00 1.4 AVEhAGE TIME PERIOD (HRS) 1.63E+00-1.78E+00-1.5 MINIMUM TIME PERIOD (HRS) 1.33E+00-1.33E+00 1.6-AVERAGE MISSISSIPPI RIVER FLOW (CFS)

{9.38E+03 2.23E+04-2.0 BATCH RELEASES (GASEOUS)

QTR: 01 QTR: 02 2.1 NUMDER OF BATCH RELEASES 3.60E+01 1.50E+01 2.2 TOTAL TIME PERIOD (HRS) 2.67E+02 1.43E+02 2.3 MAXIMUM TIME ?ERIOD (HRS) 2.35E+01 2.40E+01 2.4 AVERAGE TIME PERIOD (HRS) 7.42E+00 9.51E+00 2.5 MINIMUM TIME PERIOD (HRS) 1.00E-02

-7.00E-02 3.0 ABNORMAL RELEASES (LIQUID)

QTR: 01 QTR: 02 3.1 - NUMBER OF RELEASES 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 3.3 TOTAL TEU2IUM RELEASED (CI) 0.00E+00 0.00E+00-4.0 ABNORMAL RELEASES (GASEOUS)

QTR: 01 QTR: 02 4.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 1

l'990 EFTLUENT-S8MIANNUAL REPORT REY. O PAGE 4

. TABLE 1A GASEOUS EFFLUr.NTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 0.02E+01 3.91E-01 5.2 AVERAGE RELEASE RATE (UCI/SEC) 1.02E+01 4.97E-02 5.3 GAMMA DOSE (MRAD) 5.05E-02 3.25E-05 5.4 BETA DOSE (MRAD) 1.56E-01 3.17E-03 5.5 PERCENT OF GAMMA TECH SPEC (%)

5.05E-01 3.25E-04 5.6 PERCENT OF BETA TECH SPEC (%)

7.80E-01 1.59E-02 6.0 IODINES i

6.1 TOTAL I-131 (CI) 1.42E-03 1.66E-05 6.2 AVERAGE RELEASE RATE (UCI/SEC) 1.81E-04 2.11E-06 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 5.59E-05 5.20E-06 7.2 AVERAGE RELEASE RATE (UCI/SEC) 7.11E-06 6.62E-07 8.P TRI"IUM-8.1 TOTAL RELEASE (CI) 5.91E+01 3.74E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 7.52E+00 4.76E+00 9.0 TOTAL IUDINE, PARTICULATE AND TRITIUM (UCI/SEC) 7.52E+00 4.76E+00 10.0 DOSE (MREM) 2.18E-01 6.86E-02 I

11.0 PERCENT OF TECH SPEC (%)

1.45E+00 4.57E-01 12.0 GROSS ALPHA (CI) 1.56E-07 2.95E-07 i

L

rj q-

'1'990 EFFLUENT SEMI ANNUA!; P,EPORT REV. O PAGE 5 TABLE 1C i

GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR 01 QTR: 02 QTR 01 QTR: 02 AR-41 CI 5.01E-02 KR-85 CI 1.47E+00 3.86E-01 KR-85M CI 1.51E-02 3.02E-03 KR-88 CI 1.28E-04' XE-131M CI 4.2SE-01 4.64E-01 3.92E-03 XE-133 CI 6.11E+01 1.54E+01 1.46E-03 XE-133M CI 5.62E-01 9.37E-02 XE-135 CI 6.45E-01 6.43E-02 TOTAL CI 6.27E+01 0.00E+00 1.75E+01 3.91E-01 l

14.0 IODINES 1

CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 I-131 CI 1.42E-03 1.66E-05 3.91E-06 I-133 CI 3.01E-05 4.54E-06 2.30E-06 TOTAL CI 1.46E-03 2.11E-05 6.12E-06 0.00E+00 l

1 l

1 I

gb,4 1

, j-

. :1'990' EFFLUENT' SEMIANNUAL REPORT ~

REV. O

'PAGE 6 a

+,

i 1 TABLE 2A-GASEOUS EFFLUENTS - SUMMATION OF ALL RELEA$ES 15;0 'PARTICULATES i

CONTINUOUS MODE BATCH MODE.

]

NUCLIDE' UNITS QTR: 01 QTR1 02 QTR 01

-QTRie02 1

C

-CD-109 CI 2.64E-06 2.64E-06 i

Co-60 CI 3.87E-06 1

CS-134 CI 2.34E-06 1.18E-06 1.38E-06 CS-137 CI 8.93E-06 1.38E-06 1.57E-06 l

1 8B-125 CI 1.19E-06 1

SR-89 CI 4.08E-07 3.23E-05

.SR-90

. CI 1.56E-07 3.03E-08 1.13E-06 1

TOTAL CI 1.95E-05 5.20E-J6 3.64E-05 0.00E+00 l

1

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l'990 EFFLUENT SEMIANNUAL REPORT-REv. O PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 16.0 VOLUMC OF WASTE PRIOR TO DILUTION (LITERS) 5.62E+07 6.47E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.09E+11 7.95E+10 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 2.20E-02 7.56E-03 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 2.02E-10 9.51E-11 19.0 TRITIUM

• • • SEE ATTACHED NOTE FOR ADDITIONAL TRITIUM DOSE CALCULATIONS 19.1 TOTAL RELEASE (CI) 1.69E+02 9.21E+01 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.55E-06 1.16E-06 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 1.17E-02 3.32E-03 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.07E-10 4.18E-11 21.0 GROSS ALPHA (CI) 0.00E+00 4.40E-05 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 1.55E-06 1.16E-06 23.0 TOTAL BODY DOSE (MREM) 4.66E-04 2.76E-04 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 4.66E-04 2.76E-04 24.2 ORGAN TTL BODY TTL BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

1.55E-02 9.20E-03 1

l 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

1.55E-02 9.20E-03 i

u 1990 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 8 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 1.76E-03' 2.16E-03 BE-7 CI 1.11E-05 2.11E-04 CO-58 CI 2.00E-03 9.64E-04 i

Co-60 CI 7.63E-04 1.09E-03

'h CS-134 CI 3.10E-06 CS-137 CI 8.90E-06 1.83E-05 CR-51 CI 9.73E-05 FE-55 CI 1.63E-02 1.82E-03

{

FE-59 CI 3.10E-05 I-131 CI 2.75E-04 MN-54 CI 9.64E-06 2.02E-05 NB-97 CI 3.75E-05 2.11E-05 SB-122

'CI 4.10E-06 SB-124 CI 8.92E-05 2.22E-04 SB-125 CI 1.54E-04 8.25E-04 SC-47 CI 5.34E-05 3.25E-06.

SN-113 CI 3.59E-05 1.06E-04 SR-89 CI 2.63E-04 i

SR-90 CI 1.22E-05 SR-92 CI 2.38E-06 TC-99M CI 2.32E-06 ZR-97 CI 6.07E-05 i

TOTAL CI 2.75E-04 0.00E+00 2.17E-02 7.56E-03 V

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l't.

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? '1990[ EFFLUENT SEMIANNUAL REPORT.i REV4.,0 LPAGE 9 TABLE?2A-LIQUID EFFLUENTS ---SUMMATION'0F-'ALL-RELEASES'

'i

'2820 DISSOLVED AND ENTRAINED GASE8' i

l

-CONTINUOUS MODE

. BATCH MODEi i

l

~NUCLIDE=

, UNITS

.QTR: 01

'QTR: 02 QTRt~.01 QTR ~02 l

l#

XE-131M CI 4.50E-04 i

.r i

XE-133-

'CI

<1.12E-02:

2.99E '

i XE-133M.

CI

,2.65E.05 l'8.1E-05,

'I q

XE-135 CI

-3.65E-05L 3.16E-04 i

e m;

q o

TOTAL:

CI 1.17E-02 3.32E i K

3.-

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h ATTACHMENT TO THE 1990 ErrLUENT SEMIANNUAL' REPORT i-Liquid Pathway Dose Calculation Quarters 1 and 2.

1990 i

Summary

_The' total liquid doses-to the critical receptor for the first and

'second quarters of 1990 are 0.0400 and 0.0299_ mrem, respectively.

These doses are reported in this attachment to the semiannual report.

Background

In October, 1989 a well water sample of a residence close to PI showed low levels of tritium.

Initial dose calculation results showed.

estimated liquid pathway doses a hundred times higher than those reported in past semiannual reports.

These results indicated that a new dose pathway should be considered.

Investigation-into the cause of the tritium contamination' led to the assumption that the flow of water is from the discharge canal downhill toward the Vermilion river.

The resident's well draws from the groundwater between the canal and the Vermilion river.

ODCM Considerations The following calculation is independent of the ODCM.

At this time no change will be made to the ODCM.

Efforts are currently under way to determine if.the tritium levels in the well can be reduced by physical modifications to the discharge structures and/or adjustments to the l

discharge methods.

Results of these efforts should be available in 1990 and the problem will be eliminated or appropriate ODCM changes will be made.

D3se Calculation Assumptions For the purpora of dose calculation, the dose-maximizing assumption was made that the receptor's concentration of tritium in body water and organic molecules is equal to the average concentration in the M

discharge canal.

The dose conversion factor for this assumption is l

I taken from page 9-3 of NUREG/CR-3332.

Its value is 102 mrem / year per_

i L

uCi/ liter of tritium in the body.

When adjusted for the units reported for the discharge canal concentration, the dose conversion L

factor is 2.55E4 mrem / quarter per uCi/ml.

1 L

Discussion The clevated tritium levels were found at the residence which is the critical receptor (0.6 miles to the SSE of the site) for Prairie Island.

Therefore, the dose calculated for waterborne tritium is added to the critical receptor's fish pathway dose.

This overestimates the dose because the tritium dose from eating fish is accounted for twice.

l l

l 1'

PagO 2 It'should be noted that_the total airborne dose (99% plus of-which is l

-dueuto tritium) is greate: than the total waterborne tritium dose.

t Even though the newly identified pathway delivers additional tritium

.to the critical receptor it is a lower concentration than that already in the body due to airborne exposure.

Dose calculation r

Average Dose Diluted whole-Fish Total Body

+ Pathway -

Liquid i

Quarter Conversion X

Tritium

=

Factor Concentration Dose Dose Dose (mrem / quarter (uCi/ml)

(mrei)

(arem)-

(mrem) per uci/ml) 1 2.55E4 1.55E-6 3.95E-2 4.66E-4 4.00E 2 2.55E4 1.16E-6 2.96E-2 2.76E-4 2.99E-2 Dose Report LIQUID EFFLUENTS - SUMMATION OF WATERBORNE TRITIUM AND F3

' PATHWAYS QTR:

01 QTR:

02 I

a TOTAL BODY DOSE (MREM) 4.00E-02 2.99E-02 l

CRITICAL ORGAN DOSE-(MREM) 4.00E-02 2.99E-02 ORGAN TTL BODY TTL BODY PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

1.33E+00 9.97E-01 5

PERCENT-OF CRITICAL ORGAN TECH SPEC LIMIT (%)

1.33E+00 9.97E-01 f

i

'PINGP 753 Rev. 2 Page 1 of 5 Retention:

Lifetima I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-90 to 6-30-90 NORTHERN STATES POWER License No. DPR-42 S_0 LID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:

Solid Waste and Irradiated Fuel Shipments 1.

Solid Waste Total Volumes and Total Curie Quantities:

1 I

I I

container l

l l

Disposal Type of Waste Units Totals Volumes (List) 3 A. Resins l

ft l

135.8 135.8 l

l Ci 39.998 l

l l

IB. Dry-Compacted l

ft M

I, Ci t.y Q.

1 1 C. Non-Compacted l

ft j

3 l

1 I

I l

I Ci

[

l l

l l

1 1

I D. Filter Media ft i

1 1

l Ci l

i I

l 1

l S. Spent Fuel ft i

I L

I I

l Ci i

l l

l I

I l

I I

l l

l l

1 1

IBM

o.

ti

).

3,c

.c -

PIN (P 753, R;v. 2 '

Pcsi.2

[

JRAIRIE ISLAND NUCLEAR' GENERATING PLANT Period: 1-1-90 to 6-30-90 i

elORTHERN STATES POWER

~

License No. DPR-42 l

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT

-Table'1:

Solid Waste and Irradiated Fuel Shipments (Continued) f

. }

2 ~. -

Principal Radionuclide Composition by' Type of Waste:

.I i

-Percent j

TYPE (From Page 1)

Nuclide Abundance

-j A

C060 44.7 4

N163 26.6

- i FESS 12.7 0S137 11.6 j

CS134 3.1

• __ 3

- 1.1 H

Cl4 0.1 t

th

(

-i t

r f

5 i

' k l

l u

l..

H1

• = Inferred - Not Measured on Site IBM r

n.

2 1

~

PINGP-753, Rsv. 2

. Pcgo 3.

h

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0-4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period t.1-1-90 to 6-30, NORTHERN STATES POWER License No. DPR !

l' SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT L

b Table 1:~ Solid Waste and Irradiated Fuel Shipments (Continued) 2.

Principal Radionuclide Composition by_ Type of Waste (Continuation):

Percent TYPE.(From Page'1)

Nuclide.

. Abundance-F-

l-

.1

,i V

<b I

(

i i;

n e

j

[

• = Inferred - Not Measured on Site IBM-a.

i

F ',

'io PINGP 753, R3v. 2 PcgJ.4 f

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-90 to 6-30-90 NORTHERN STATES POVER License No. DPR-42

. SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT t

Table 1:

Solid Waste and Irradiated Fuel Shipments (Continued) 3.

Solid Waste Disposition:

Number of Shipments Mode Destination 1

TRUCK BARNWELl,, SC.

4.

Irradiated Fuel Shipments:

Number of-Shipments Mode Destination 0

P f

+

IBM

PINGP 753 R;v. 2 Pcga 5 l

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-90 to 6-30-90 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.

l (Ft3)

(Ci)

Waste Code code 90-05 135.8 39.999 A

L N /A l

l i.

TOTALS 1

135.8 39.998 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 B = Dry Compacted C = Non-Compacted D = Filter Media S = Spent Fuel IBM i

I