Text

Rev 1 to Annual Radioactive Effluent & Waste Disposal Rept for Jan-Dec 1996
	ML20210K140
Person / Time
Site:	Prairie Island
Issue date:	12/31/1996
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20210K130	List: ML20210K125; ML20210K140;
References
	NUDOCS 9708190154
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_

NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATItiG PLANT QfE-EITE RADI ATION DOSE ASEESSMENLEDE January throuah December 1996 An Assessment of the radiation dose due to the release from Prairio Island Nuclear Generating Plant during 1996 was performed in accordanco with the technical Specifications.

Computed dosos were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidolines.

Of f-sito doso calculation formulas and moteorological data from the Off-site Dose Calculation Manual vero used in making this assessment.

Source terms were obtained from tho Annual Radioactivo Effluent and Waste Disposal Report prepared for NRC review for the year of 1996.

i Off-sito Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1.

Critical Rocoptor location and pathways for organ doses are reported in I

Table 2.

Dosos are a small percontage of Appendix I Guidelinos.

1 Off-site Dosos from Liould Release Computed doses due to Liquid releases are reported in Table 1.

Receptor information is reported in Table 2.

Dosos, both whole body and organ, are a small percentage of Appendix I Guidelines.

i}pfes to 3Ddviduals Due to Activities Inside the Site Boundart Occasionally sportsmen enter the Prairie Island sito for recreational activitics.

These individuals are not expected to spend more than a few hours per year within the site boundary.

Commercial and recreational river traffic oxists through this area.

For purposes of estimating the dose due to recreational and river w& tor transportation activities within the site boundary, it is assumed that the limiting doso within the site boundary would be received by an individual who spends a total of seven days por year on the river just of f shore f rom the plant buildings (ESE at 0.2 miles).

The gamma dose from noble gas releases and the whole body and organ dosos from the inhalation pathway due to Iodine 131, Iodino-133, tritium and long lived particulatos were calculated for this location and occupancy time.

Those doses were reported in Tablo 1.

Doses to Individuals Duo to Effluent Roloasos from the ISFSI Two loaded fuel casks were placed in the storage facility during the 1996 calendar year bringing the total number of casks to 5.

There has been no roloase of radioactive effluents from the ISFSI.

9700190154 970814 PDR ADOCK 05000282 R

PDR

4 e

Do'ses to Most Exposed Member of the General Public f rom Reactor Release and Other Uranium Fuel Cycle _ Sources There are no other uranium fuel facilities in the vicinity of the Prairie Island site.

The only other artificial source of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactors.

This direct radiation from pressurized water reactors has been shown to be negligible.

An array of TLD monitoring stations around the perimeter of the site boundary has consistently indicated that plant operation in the past years has no effect on ambient gamma radiation.

Therefore, the most exposed member of the general public will not receive an annual radiation dose f rom reactor effluent releases and all other fuel cycle activities in excess of the sum of the liquid and gaseous whole body and organ doses reported in Table 1 for the site boundary and critical receptor, respectively.

These doses are well below 40 CFR Part 190 standards of 25 mrem to the whole body, 75 mrom to the thyroid, and 25 mrem to any other organ.

Radiation Environmental Monitorina Proaram Samplina Deviations There were no milk or vegetable sampling deviations during this reporting period.

t Radiation Effluent Monitorina Samnlina Deviations Two Steam Generator Monitor Tank composite samples were accidently discarded prior to preparing the composite sample for analyels in accordance with the Off site Dose Calculation Manual Table 2.1 and were therefore not analyzed for Sr-89, St-90, Fe-55 or-alpha.

Causes The samples being discarded was the labels used on the bottles being held for compositing contained misleading information when a

tank was sampled during one surveillance month and actually released during the following month.

Corrective The labels for the bottles being held for composite Action:

analysis were changed to only contain the necessary information to identify the sample. The sample date and release week information was removed from the lable.

Result:

The two tanks involved -contained steam generator blowdown water collected during a dual unit outage.

Sample history indicates that there is no activty concerns with water from this source. The Sr-89, St-90, Fe-55 and alpha results of the remaining waste tanks were assigned to the release volumes from these tanks.

4 4

Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD:

JANUARY thropah DECEMBER ljjft 10 CFR Part 50 Ap.pendix I Guidelines per 2-units shte per year Gaseous.Reltaang Maximum Site Boundary Gamma Air Dose (mrad) 7.95E-05 20 Maximum Site Boundary Beta Air Dose (mrad) 8.91E-03 40 Maximum Off-site Dose to any organ (mrem)*

1.34E-01 30 Uffshore Location Gamma Dose (mrad) 2.12E-04 Total Body (mrom)*

2.36E-01 Organ (mrom)*

2.39E-01 30 Liould Releases l

Maximum Off-site Dose Total Body (mrom) 1.72E-02 6

Maximum Off-site Dose l

Organ - LIVER (mrom) 2.38E-02 20

?

l Limiting Organ Dose Organ - Total Body 1.72E-02 6

i-h

Long-Lived Particulate, I-131, I-133 and H-3 b

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e Table 2 OFF-8ITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEIUDfTAL INFORMATION PERIOD: JANUARY _throuah DECEMBER 1996.

Gaseous _ Releases l

Maximum Site Boundary Dose Location (from Building Vents)

Sector WNW i

Distance (miles) 0.4 Offshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-site Sector SSE Distance (miles) 0.6 Pathways

Plume, Ground, Inhalation, Vegetables Age Group Child Linuld Releases Maximum Off-site Dose Location Downstream Pathway Fish

1996 Annu:1 R0dio3ctivo Efflu0nt R0 port REV. 1

. Pcg3 1 of 9 Retention Lifetime.

ANNUAL RADIOACTIVE RFFLUENT REPORT 01-JAN-96 THROUGH 29-DEC-96 SUPPLEMENTAL INFORMATION Facility:

Prairie Island Nuclear Generating Plant Licensee Northern States Power Company License Numbets: DPR-42 & DPR-60 A. Regulatory Limits

- 1.

Liquid Effluents:

1 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 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 s 500 mrem / year total body 53000 mrem / year skin I-131, I-133, H-3, LLP

$1500 mrem / year to any organ l

b.

The dose due to radioactive gaseous effirents released from the site shall be limited to:

-noble gases

.s10 mrad / quarter-gamma s20 mrad / quarter beta l

520 mrad / year gamma s40 mrad / year beta I-131, I-133, H-3, LLP s15 mrem / quarter to any organ 530 mrem / year to any organ l

_,,_m_

--_~,x-.m_

1996 ANNUAL RADIOACTIVE EFFLUENT REPORT REVo 1 PAGE 2 B,.

Maximum Permissible Concentration 1

1.

Fission and activation gases in gaseous releases:

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

Iodine and particulates with half lives greater j

than 8 days in gaseous releases:

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

1 l

3.

Liquid effluents for radionuclides other than dissolved or entrained gases:

OLD 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 125%

in gaseous releases:

Nuclide GeLi 2.

Iodines in gaseous releases:

Total GeLi 125%

Nuclide GeLi 3.

Particulates in gaseous releases:

Total GeLi 125%

Nuclide GeLi 4.

Liquid effluents Total GeLi 125%

Nuclide GeLi E.

Manual Revisions 1.

Offsite Dose Calculations Manual latest Revision number:

14 Revision date 05/15/96 Revision #14 of the ODCM and a description of the changes are submitted with this report for review.

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-4 190G ANNUAL RADIOACTIVE EFFLUENT LEPORT RE7. 1 PAGE 7 Yassa 2A I.IOWID EN - SMIOR OF ALL Ram STR 01 QTE: 02 QTas 03 QTR 04 16.0 VOLUME OF WARTE PRIOR TO DILUTION (LITBES) 8.34E+07 6.71E+07 7.21E*07 6.973+07 17.0 VOLUME OF DILUTION WATER (LITERS) 8.985+10 S.51E+10 2.70E+11 2.01E+11 18.0 FISSIOS A m ACTIVATION F20DOCTS 18.1 TOTAL RELEASE W/ft N-3, RADGAS, ALPHA (CI) 2.205-01 4.453-02 2.70E-01 2.273-02 3

18.2 TVERAGE DILUTRD CONCENTRATION (UCI/ML) 2.453-09 5.223-10 1.003-09 1.133-10 19.0 TRITIWut 19.1 TOTAL RELEASE (CI) 1.673+02 1.283+02 1.99E+0' 1.33E+02 19.2 AVERAGE DILUTED CONCEPTRATION (UCI/NL) 1.863-06 1.50s-06 7.37B-07 6.623-07 23.0 DISSOf.TED AEm ENTRAINED SASSE 1

20.1 TOTAL RELEASE (CI) 6.335-04 5.275-04 6.575-04 7.975-05 3

20.2 AVERAGE DILUTED (*ONCENTRATION (UCI/NL) 7.045-12 6.193-12 2.435-12 3.973-13 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I

22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/NL) 1.865-S6 1.50E-06 7.37E-07 6.623-07 23.0 TOTAL BODY DOSE (MREM) 4.65E-03 3.81E-03 5.063-03 3.735-03 24.0 CRITICAL OeOAM 24.1 DOSE (MREN) 4.655-03 3.613-03 5.06E-03 3.73E-03 l

24.2 ORGAN TOT BODY TOT BODY TOT BODY TOT BODY l

1 25.0 PERCBNT OF TOTAL BODY TECE SPEO LIMIT (%)

1.553-01 1.273-01 1.69E-01 1.243-01 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

1.553-01 1.27E-01 1.695-01 1.245-01 l-

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