L-PI-10-028, Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM)
| ML101390197 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/12/2010 |
| From: | Schimmel M Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-10-028 | |
| Download: ML101390197 (27) | |
Text
XcelEnergy-MAY 1 2 2010 L-PI-10-028 TS 5.5.1.c TS 5.6.3 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42, DPR-60 and SNM-2506 2009 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM)
Pursuant to the applicable Prairie Island Nuclear Generating Plant (PINGP) Technical Specifications (TS), Appendix A to Operating Licenses DPR-42 and DPR-60, and the requirements of the Offsite Dose Calculation Manual, Northern States Power Company, a Minnesota Corporation (NSPM), doing business as Xcel Energy, submits the 2009 Annual Radioactive Effluent Report which is comprised of the following reports: contains the Off-Site Radiation Dose Assessment for the period January 1, 2009 through December 31, 2009 in accordance with the requirements of the ODCM. contains the Annual Radioactive Effluent Report, Supplemental Information, for the period January 1, 2009 through December 31, 2009 in accordance with the requirements of TS 5.6.3 and the ODCM. contains the Low Level Waste Disposal Annual Report, Solid Waste and Irradiated Components Shipments, for the period January 1, 2009 through December 31, 2009 in accordance with the requirements of TS 5.6.3 and the ODCM. contains a complete copy of the entire ODCM (H4), Revision 23, dated 5/29/09. Enclosure 5 contains a complete copy of the entire ODCM (H4), Revision 24, dated 9/17/09. In accordance with the requirements of TS 5.5.1.c., the changes are identified by markings in the margin of the affected pages. The manual also contains a Record of Revisions which includes a summary of the revision changes (refer to page 11 of the ODCM).
A ocflc 1717 Wakonade Drive East a Welch, Minnesota 55089-9642 Telephone: 651.388.1121 kl(gA
0'6,.
Document Control Desk Page 2 The Process Control Program (PCP) for Solidification/Dewatering of Radioactive Waste from Liquid Systems (D59) has not been revised since the 2008 Annual Effluent report was submitted, therefore it is not included with this report.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (5) cc: Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator
ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 01, 2009 - December 31, 2009 9 pages follow
PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1, 2009 - December 31, 2009 An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2009 was performed in accordance with the Offsite Dose Calculation Manual as required by Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report prepared for NRC review for the year of 2009.
Off-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ doses are reported in Table 2. Gaseous release doses are a small percentage of Appendix I Guidelines.
Off-site Doses from Liquid Release Computed doses due to liquid releases are reported in Table 1. Critical receptor information is reported in Table 2. Liquid release doses, both whole body and organ, are a small percentage of Appendix I Guidelines.
Doses to Individuals Due to Activities Inside the Site Boundary Occasionally sportsmen enter the Prairie Island site for recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary. Commercial and recreational river traffic exists through this area.
For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off-shore from the plant buildings (ESE at 0.2 miles). The gamma dose from noble gas releases and the whole body and organ doses from the inhalation pathway due to Iodine 131, Iodine-i133, tritium and long-lived particulates were calculated for this location and occupancy time. These doses are reported in Table 1.
Critical Receptor location and pathways for organ doses are reported in Table 2.
Page 1 of 9
ABNORMAL RELEASES There were no abnormal releases for 2009.
40CFR190 COMPLIANCE The calculated dose from the release of radioactive materials in liquid or gaseous effluents did not exceed twice the limits of 10CFR50, Appendix I, therefore compliance with 40CFR190 is not required to be assessed, in this report.
SAMPLING, ANALYSIS AND LLD REOUIREMENTS The minimum sampling frequency and lower limit of detection (LLD) requirements, as specified in ODCM Tables 2.1 and 3.1 were not exceeded in 2009.
The contingency requirements in ODCM Tables 2.2 and 3.2 were exceeded in 2009, as follows:
1R15, Condenser Air Ejector Monitor, was declared out-of-service on March 30, 2009 and remained out-of-service till August 20, 2009. In accordance with ODCM Table 3.2, "With the number of channels Operable less than required by the Minimum Channels Operable requirement, air ejector operation may continue provided that grab samples are taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.".
On May 7, 2009, the contingency sampling was performed at 10:00 am. On May 8, 2009, the day shift failed to perform the required contingency sampling.
The night shift noted the missed sample and performed contingency sampling on May 9, 2009, at 00:11.
No activity was identified in the sample preceding or following the missed sample.
Corrective Actions included individual and departmental counseling. Additionally, line items were added to the shift scheduler requiring signature verification for completion of contingency sampling.
The event and corrective actions were captured in Action Request 01181462.
Page 2 of 9
MONITORING INSTRUMENTATION There were six (6) occurrences when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable as required by ODCM Tables 2.2 and 3.2, as noted:
- 1. 1R12, UNIT ONE SHIELD BUILDING VENTILATION MONITOR 1R12, Unit One Shield Building Ventilation Monitor is defined as a process radiation monitor. Operability requirements are defined by ODCM Table 3.2, Radioactive Gaseous Effluent Monitoring Instrumentation. If 1R12 is out of service and not restored within 30 days, an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.
The monitor was removed from service on March 18, 2009 at 14:55, due to failure of SP- 1027. The monitor failed to generate the adequate response to a routine bug check.
The monitor was returned to service on September 16, 2009 at 16:15, for a total of 182 days 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 20 minutes out of service.
No compensatory sampling was required during the out of service period, per ODCM Table 2.2.
The long extended duration out of service period was due to quality of detector tubes in stock. The instruments are old and the past vendor could no longer supply tubes. Qualification of a new vendor ensued, however to support plant activities the decision was made to remove the tube from 2R12 and restore 1R12.
This transferred the issue from 1R12 to 2R12, but supported Refueling Outage 1R26 activities.
The ultimate resolution will be the R-12 replacement project scheduled to be completed in 2010.
- 2. 2R12, UNIT TWO SHIELD BUILDING VENTILATION MONTIOR 2R-12, Unit Two Shield Building Ventilation Monitor is defined as a process radiation monitor. Operability requirements are defined by ODCM Table 3.2, Radioactive Gaseous Effluent Monitoring Instrumentation. If 2R12 is out of service and not restored within 30 days, an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.
Page 3 of 9
The monitor was removed from service on September 9, 2009 at 13:40, for detector swap, to support restoration of 1R12.
The monitor was returned to service on January 30, 2010, for a total of 143 days 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 20 minutes out of service time in 2009/2010. This out of service straddles a calendar year and is captured in the 2009 report, because the majority of the out of service time was in 2009 and the monitor did not exceed 30 days out of service in 2010. It will not be recaptured in the 2010 report. If it had exceeded 30 days in 2010 the out of service period would be recaptured in the 2010 report.
2R12 was removed from service to restore 1R12 and support Refueling Outage 1R26 activities, as described in 1R12 out of service report. Challenges with detector tubes, as described previously, precluded the prompt restoration.
The ultimate resolution will be the R-12 replacement project, scheduled to be completed in 2010.
- 3. 1R15, Condenser Air Ejector Monitor 1R-1 5, Condenser Air Ejector Monitor is defined as a process radiation monitor.
Operability requirements are defined by ODCM Table 3.2, Radioactive Gaseous Effluent Monitoring Instrumentation. If 1R- 15 is out of service and not restored within 30 days an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.
The monitor was removed from service on March 30, 2009 at 11:36, due to failure of SP-1027. A bug point response was less than the tolerances.
The pulse transformer and all 6 capacitors in the preamp were replaced and subsequent bugging was satisfactory. The monitor was returned to service on August 20, 2009 at 15:55 for a total of 143 days 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 19 minutes out of service.
Compensatory sampling was performed, per ODCM Table 3.2, with one exception, as noted in this report.
Page 4 of 9
- 4. 1R19, UNIT ONE STEAM GENERATOR BLOWDOWN PROCESS RADIATION MONITOR 1R- 19, Radwaste Building Ventilation Monitor is defined as a process radiation monitor. Operability requirements are defined by ODCM Table 2.2, Radioactive Liquid Effluent Monitoring Instrumentation. If 1R-19 is out of service and not restored within 30 days, an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.
The monitor was removed from service on October 26, 2009 at 14:55, due to failure of SP-1028B. The monitor failed a source check. Additionally, placing the selector switch to HV produced a zero reading on the meter.
The detector was replaced and the check source was cleaned to allow for full retraction.
The monitor was returned to service on January 18, 2010 for a total of 84 days 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 25 minutes out of service. This out of service period straddles a calendar year and is captured in the 2009 report, because the majority of the out of service time was in 2009 and the monitor did not exceed 30 days out of service in 2010. It will not be recaptured in the 2010 report. If it had exceeded 30 days in 2010 the out of service period would be recaptured in the 2010 report.
Compensatory sampling was performed, per ODCM Table 2.2.
- 5. UNIT TWO TURBINE BUILDING SUMP COMPOSITOR Unit Two Turbine Building Sump Compositor is defined as a process radiation monitor. Operability requirements are defined by ODCM Table 2.2, Radioactive Liquid Effluent Monitoring Instrumentation. If Unit Two Turbine Building Sump Compositor is out of service and not restored within 30 days, an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.
The Compositor was removed from service on September 1, 2009 at 06:00 due to a failed timer on the collection scoop.
The compositor was returned to service on November 18, 2009 at 17:00 for a total of 78 days 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> and 0 minutes out of service.
Compensatory sampling was performed, per ODCM Table 2.2.
Page 5 of 9
- 6. R-35 RADWASTE BUILDING VENTILATION MONITOR R-35, Radwaste Building Ventilation Monitor is defined as a process radiation monitor. Operability requirements are defined by ODCM Table 3.2, Radioactive Gaseous Effluent Monitoring Instrumentation. If R-35 is out of service and not restored within 30 days, an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.
The R-35 monitor was operable, however the Radioactive Waste Building Ventialtion was secured for an extended period of time. R-35 was sampling a dead header and not performing its intended function for a period of time exceeding 30 days. The Radioactive Waste Building Ventilation was secured for nearly the entire year.
Compensatory sampling is not required, however compensatory sampling was established to ensure quantification of any passive air exchange in and out of the building.
The number of occurrences of Process Radiation Monitors out of service was captured in Action Request (AR) 01204434. The issue is being tracked on the Top Ten Equipment List under AR 00866805. All Radiation Monitors are repairable and the excessive out-of-service time appears to be primarily due to maintenance resources and work prioritization. At screening, Process Radiation Monitors will now receive an elevated prioritization code above that which was previously assigned.
DOSES TO INDIVIDUALS DUE TO EFFLUENT RELEASES FROM THE INDEPENDENT SPENT FUEL STORAGE FACILITY (ISFSI)
One (1) fuel cask was loaded and placed in the storage facility during the 2009 calendar year. The total number of casks in the ISFSI is twenty-five (25). There has been no release of radioactive effluents from the ISFSI.
CURRENT ODCM REVISION The Offsite Dose Calculation Manual was revised TWO (2) times in 2009. The current revision is 24. The revision date of revision 23 is May 29, 2009. The revision date of revision 24 is September 17, 2009. A copy of revision 23 and revision 24 is submitted with this year's report as Enclosures 4 and 5.
Page 6 of 9
PROCESS CONTROL PROGRAM The Process Control Program was not revised in 2008. Current manual revision is 9.
The revision date is April 15, 2008.
INDUSTRY INITIATIVE ON GROUND WATER PROTECTION There were no events requiring NRC reporting, for the Industry Initiative on Groundwater Protection.
Page 7 of 9
Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY throuqh DECEMBER 2009 10 CFR Part 50 Appendix I Guidelines for a 2-unit site per year Gaseous Releases Maximum Site Boundry Gamma Air Dose (mrad) 8.22E-05 20 Maximum Site Boundry Beta Air Dose (mrad) 8.98E-03 40 Maximum off-site Dose to any organ (mrem)* 2.63E-02 30 Offshore Location Gamma Dose (mrad) 4.2 1E-06 Total Body (mrem)* 1.09E-03 Organ (mrad)* 1.09E-03 30 Liquid Releases Maximum off-site Do Total Body (mrem) 1.91E-03 Maximum Off-site Dose Organ - GI TRACT (mrem) 6.91E-03 20 Limiting Organ Dose Organ - GI TRACT (mrem) 6.91E-03 6
- Long-Lived Particulate, 1-131, 1-133 and Tritium
Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION January 1, 2009 - December 31,.2009 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents)
Sector WNW 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 Liquid Releases Maximum Off-site Dose Location Downstream Pathway Fish Page 9 of 9
ENCLOSURE2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 01, 2009- December 31, 2009 9 pages follow
2609 Annual Radioactive Effluent Report REV. 0 Page 1 of 9 Retention: Lifetime ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-09 THROUGH 31-DEC-09 SUPPLE NTAL INFORMATION
.Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits
- 1. Liquid Effluents:
- 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
- 500 mrem/year total body
- 3000 mrem/year skin 1-131, 1-133, H-3, LLP *1500 mrem/year to any organ
- b. The dose due to radioactive gaseous effluents released from the site shall be limited to:,
noble gases *10 mrad/quarter gamma
- 20 mrad/quarter beta
<20 mrad/year gamma
- 40 mrad/year beta 1-131, 1-133, H-3, LLP <15 mrem/quarter to any organ
- 30 mr em/year to any organ
2009 Annual Radioactive Effluent Report Rev. 0 PAGE 2 B. Water Effluent Concentration
- 1. Fission and activation gases in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1
- 2. Iodine and particulates with half lives 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:
10 CFR 20, Appendix B, Table 2, Column 2
- 4. Liquid effluent dissolved and entrained gases:
2.OE-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.
D. Measurements and approximations of total activit,
- 1. Fission and activation gases : Total Gem +/-25%
in gaseous releases: Nuclide Gem
- 2. Iodines in gaseous releases: . Total Gem +/-25%
Nuclide Gem
- 3. Particulates in gaseous releases: Total Gem +/-25%
Nuclide Gem
- 4. Liquid effluents Total Gem +/-25%
Nuclide Gem E. Manual Revisions
- 1. Offsite Dose Calculations Manual latest Revision number:
Revision date :
- jiOc'
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 3 1.0 BATCH RELEASES (LIQUID)
QTR: 01 QTR: 02 QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 2.20E+01 2.OOE+01 3.90E+01 5.60E+01 1.2 TOTAL TIME PERIOD (HRS) 4.04E+01 3.75E+01 7.63E+01 1.14E+02 1.3 MAXIMUM TIME PERIOD (HRS) 2.28E+00 2.27E+00 3.17E+00 4.22E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.84E+00 1.87E+00 1.96E+00 2.03E+00 1.5 MINIMUM TIME PERIOD (HRS) 1.50E+00 1.30E+00 1.50E+00 8.83E-01 1.6 AVERAGE MISSISSIPPI RIVER FLOW CFS) 1.36E+04 2.70E+04 8.26E+03 1.66E+04 2.0 BATCH RELEASES (AIRBORNE)
QTR: 01 QTR: 02 QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 0.00E+00 3.OOE+00 9.OOE+00 6.80E+01 2.2 TOTAL TIME PERIOD (HRS) [ 0.OOE+00 2.85E+00 9.19E+01 i 9.78E+02 2.3 MAXIMUM TIME PERIOD (HRS) [ 0.00E+00 2.85E+00 2.40E+01 2.40E+01 2.4 AVERAGE TIME PERIOD (HRS) 0.00E+00 9.51E-01 1.02E+01 1.44E+01
[
2.5 MINIMUM TIME PERIOD (HRS) 0.00E+00 5.00E-04 1.92E+00 3.25E-02 3.0 ABNORMAL RELEASES (LIQUID) f I QTR: 01 QTR: 02 QTR: 03 QTR: 04 3.1 NUMBER OF BATCH RELEASES P 0.00E+00 I 0.OOE+00 0.00E+00 0.OOE+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.0 ABNORMAL RELEASES (AIRBORNE)
QTR: 01 - QTR: 02 QTR: 03 QTR: 04 4.1 NUMBER OF BATCH RELEASES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.2 TOTAL ACTIVITY RELEASED (CI) LP 0.00E+00 0.005+00 ]0.00E+00 I 0.00E+00
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 4 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 QTR 03 QTR: 04 II I I I 5.0 FISSION AND ACTIVATION GASES 0.00E+00 11.37E-01 2.81E-01 6.84E-01 5.1 TOTAL RELEASE (CI) 5.2 AVERAGE RELEASE RATE (UCI/SEC) 0.OOE+00 1.74E-02 [ 3.57E-02 8.70E-02 5.3 GAMMA DOSE (MRAD) 0.OOE+00 ] 9.89E-06 2.16E-05 5.07E-05 5.4 BETA DOSE (MRAD) 0.OOE+00 1.12E-03 j 2.29E-03 5.57E-03 5.5 PERCENT OF GAMMA TECH SPEC (% 0.OOE+00
- 1 9.89E-05 I' 2.16E-04 5.07E-04 5.6 PERCENT OF BETA TECH SPEC (% 0.OOE+00 5.59E-03 1.14E-02 2.79E-02 1 1 6.0 IODINES 6.1 TOTAL 1-131 (CI) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.2 AVERAGE RELEASE RATE(UCI/SEC)-- 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 r - T T 1 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 0.OOE+00 j 0.OOE+00 0.OOE+0o 6.72E-06 7.2 AVERAGE RELEASE RATE (UCI/SEC) 0.OOE+00 0.OOE+00 j 0.OOE+00 8.55E-07 L _ _ _ _ I_ _ __ _ _ I __ _ _
8.0 TRITIUM F T I 1 8.1 TOTAL RELEASE (CI) k1.65E+00 3.49E+00 3.77E+00 1.48E+
8.2 AVERAGE RELEASE RATE (UCI/SEC)
I 2-09E-01 4 .44E-01 I 4.79E-01 I1.88E-01J 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.09E-01 i 4.44E-01 i-4.79E-01 1.88E-01 10.0 DOSE FROM IODINE, LLP, AND TRITIUM (MREM) 2.95E-03 6.25E-03 1.45E-02 2.67E-03
.1 7 I 1 7 0 11.0 PERCENT OF TECH SPEC (%)
1.96E-02 4.17E-02 9.64E-02 1.78E-02 I...
12.0 GROSS ALPHA (CI) - 0.00E+oo 1 0.OOE+00 I
III .OOE+00 0.OOE+00
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 5 TABLE iC GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CI) 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE I UNITS L ~fi IQTR:- 01 iQTR:
i 02 I QTR: 03 1QTR: 04
______________________ 1i QTR: 01 iQTR:
i 02 1QTR: 03 1QTR: 04 KR-85 CI 1.37E-01 2.80E-01 6.83E-01 XE-133 CI I i Sj2.11E-05 8.87E-04 1.04E-03 XE-135 CI
QRUNITS T QTR: 03 i* QTR: 04 QTR: 01 QTR: 02 QTR: 03 QTR: 04 TOTALS CI 0.00E+00 0.00E+ 0.00E-E+00 00E+00, 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 6 TABLE IC GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CONTINUED) 15.0 PARTICULATES CONTINUOUS MODE BA TCH MODE NUCLIDE SI UNITS II j QTR: 01 I
QTR: 02 i
QTR: 03 I
QTR: 04 II QTR: 01 I
QTR: 02 QTR: 03 QTR: 04 co-58 CI II 1 o 1 6.72E-06 TOTALS CI 0 .OOE+00 0 .005+00 0.OOE+00 6 .72E-06 10 .OOE+00 1.0.00E+0 0 0.005+00 0.005+00
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 7 TABLE 1A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 QTR: 03 QTR: 04 II I I 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 3.07E+07 3.43E+07 4.06E+07 6.35E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.84E+l1 1.02E+11 2.35E+11 1.62E+11 18.0 FISSION AND ACTIVATION PRODUCTS 4.62E-02
))
18.1 TOTAL RELEASES W/O H-3, RADGAS, ALPHA (CI) 1.70E-02 3.40E-02 3.10E-01 I
18.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 2.51E-10 I 1.67E-10 1.45E-10 1.91E-09 19.0 TRITIUM + I 19.1 TOTAL RELEASE (CI)
[ 9.81E+0l 2 .35E+02 1.29E+02 5.62E+01 19.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 5.32E-07 2.30E-06 5.48E-07 J 3.47E-07 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 3.94E-03 19.95E-05 T2.17E-03 17.16E-03 20.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 2.14E-ii 1 9.72E-13 9.24E-12 4.42E-11 21.0 GROSS ALPHA (CI) o.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 22.0 TOTAL TRITIUM, FISSION & ACTIVATION PRODUCTS (UCI/ML) 5.33E-07 2.30E-06 5.48E-07 3.49E-07 23 .0 TOTAL BODY DOSE (MREM) 2.52E-04 5.31E-04 3.32E-04 7.99E-04 24 .0 CRITICAL ORGAN I I 24.1 DOSE (MREM) 2.52E-04 5.31E-04 3.32E-04 5.15E-03 24.2 ORGAN TOT BODY L
TOT BODY TOT BODY jI GI TRACT I
25.0 PERCENT OF TECHNICAL SPECIFICATIONS LIMIT (%) 8.40E-03 1.77E-02 1.11E-02 2.66E-02 I
26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
8 E 8.-40E-03 1"77E-02II 1"11E-02 I 5 5"15E-02 I L -____
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 8 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (CI)
- 27. 0 INDIVIDUAL LIQUID EFFLUENT CONTINUOU S MODE BATCH MODE INUCLIDE UNITS IQTR: 01 QTR: 02 QTR: 03 QTR: 04 TR: 01 QTR: 02 QTR: 03 QTR: 04 II I I I I i I AG-110M II C 5.58E-03 3.61E-03 6.09E-03 5.52E-03 cO-57 CI 5.82E-05 1.31E-05 8.66E-06 4 53E-04 co-58 CI 6.06E-03 9.45E-04 4.60E-03 9.98E-02 co-SO I cI H 1.54E-03 4.48E-04 3.12E-03 1.44E-02 CRF511 I Fl 1- 1.55E-04 5.64E-04 4 .97E-02 18E-06
- jCS-134 CI I 7.
cs-137 CI 1.11E-06 1.30E-06 4.02E-05 FE-55 ICI 6.86E-03 4.54E-03 1.35E-02 8.48E-02 FE-59 + CI I H 2.12E-04 7.61E-06 F 1.18E-04 4.39E-03 1-131 CI F 5.30E-06 8.82E-06 LA-140 CI F 3.70E-06 4.75E-06 F[ -[ -
MN-54 c CI 1.01E-04 1.89E-05 1.03E-04 1.67E-03 NB-95 CI 1.90E-04 F 7.92E-06 6.1OE-05 9.77E-03 NB-97 CI 1.69E-04 4.67E-04 F 1.10E-03 5.18E-04 RB-89 SB-122 SB-124 c
CI CI CI I
F 2.03E-03 I
i 1.35E-06 2.26E-04 1.36E-05 8.62E-05 1.35E-03 SB-125 II- CI
+
2.30E-02 6.75E-03 4.61E-03 2.97E-02 SB-126 CI I I 2.79E-06 7.66E-06 I IF i :SC-46 CI Fi 2.47E-05 FSE-75 CI +
1.77E-05 SN-113 CI_ _ 8.15E-05 F 1.50E-03
+
SSR-92 C 2.63E-05 F 1.45E-06 7.84E-05
+
F TE-123M ZN-65 CI cF I
_____________ .1-______________
1.85E-05 II i_
7.38E-05 I _ _ _ _ CII_ _I 2.43E-04 (CONTINUED)
2009 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 9 TABLE 2A LIQUID EFFLUENTS - SUMMATION. OF ALL RELEASES (CONTINUED) 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS KQTR:01 SI IQTR: 02 I QTR: 03 IQTR:
I 04 I j QTR: 01 l QTR: 02 f BATCH I QTR: 03 Il QTR: 04 ]
iI i I I i; ZR-95 CI 1.43E-04 1.02E-05 6.04E-03 TOTALS CI 0.00E+00 0.00E+00 0.00E+i00 10.00E+00 14.62E-02 1 1.70E-02 1 3.40E-02 1 3.10E-01 28.0 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 03 QTR: 04
- QTR: 01 QTR: 02 QTR: 03 QTR: 04 85 CI 3.92E-03 1.99E-03 7.16E-03
_____-- 4--
XE-133 CI 1.73E-05 9.26E-05 1.61E-04 I-XE-135 CI ,-6.O85E-06 1.69E-05 [
TOTALS CI 0.OOE+00 Li.OOE+oLJ 0.OOE+O0 [ .OOE+OOJ f3.94E-0 9.95E-05 2.17E-03 1 7.16E-03
ENCLOSURE 3 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENT SHIPMENTS January 01, 2009 - December 31, 2009 4 pages follow
PINGP 753, Rev. 9
Reference:
RPIP 1314 Page 1 of 4 Doc Type/Sub Type: RPC/DATA Retention: Lifetime +
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/09-12/31/09 NORTHERN STATES POWER License No. DPR-42/60 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENT SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
- 1. Solid Waste Total Volumes, Total Curie Quantities, and Major Nuclides:
Major Nuclides for the Above Table:
Ni-63, Co-60, Fe-55, Cs-137, H-3, Co-58, Ni-59, Sb-125, Cs-134.
1.66E+04 4.71 E+02 4.24E-01
.4 I-I~i-1.66E+04 1 4.71 E+02 4.24E-01 Major Nuclides for the Above Table:
Fe-55, Co-58, Co-60, Ni-63, Nb-95
PINGP 753, Rev. 9 Page 2 of 4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/09-12/31/09 NORTHERN STATES POWER License No. DPR-42/60 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENT SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
. (NOT IRRADIATED FUEL) [continued]
Major Nuclides for the Above Table:
N/A Curie 1.28E+03 3.62E+01 1.74E-02 1.28E+03 3.62E+01 1.74E-02 Major Nuclides for the Above Table:
Cr-51, Fe-55, Co-58, Co-60, Ni-63, Zr-95, Nb-95, Ag-110m.
PINGP 753, Rev. 9 Page 3 of 4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/09-12/31/09 NORTHERN STATES POWER License No. DPR-42/60 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENT SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
Major Nuclides for the Above Table:
H-3, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sb-125, Cs-134, Cs-137.
PINGP 753, Rev. 9 Page 4 of 4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/09-12/31/09 NORTHERN STATES POWER License No. DPR-42/60 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENT SHIPMENTS B. PROCESS CONTROL PROGRAM CHANGES (NOT IRRADIATED FUEL) [continued]
- 2. Process Control for Solidification/Dewatering of Radioactive Waste from Liquid Systems Current Revision Number: 9 Effective Date: 4/15/08 If the effective date of the PCP is within the period covered N OTE: by this report, then a description and justification of the changes to the PCP is required H4 (ODCM) 8.1 m. Attach the sidelined pages to this report.
Changes/Justification:
N/A