Text

2005 Annual Radiological Effluent Release Report and Offsite Dose Calculation Manual for Yankee Atomic Electric Co
	ML061230081
Person / Time
Site:	Yankee Rowe; (DPR-003)
Issue date:	04/26/2006
From:	Jeffery Lynch; Yankee Atomic Electric Co
To:	; Document Control Desk, NRC/FSME
References
	BYR-06-031
	Download: ML061230081 (47)
	v • d • e

YANKEE ATOMIC ELECTRIC COMPANY Telephone (413)424-526 49 Yankee Road, Rowe, Massachusetts 01367 NKEE April 26, 2006 BYR 2006-031 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-001

Reference:

License No. DPR-3 (Docket No. 50-29)

Subject:

2005 Annual Radiological Effluent Release Report and Offsite Dose Calculation Manual Yankee Atomic Electric Company (YAEC) herewith submits its 2005 Annual Radiological Effluent Release Report (ARERR) and Revision 18 to the Offsite Dose Calculation Manual (ODCM). The ARERR provides a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released at the Rowe site and also includes a summary of estimated dose commitments from all radioactive liquid and gaseous effluents released in 2005. This information is submitted in accordance with the Quality Assurance Program (formerly referred to as the Yankee Decommissioning Quality Assurance Program) and the ODCM.

The enclosed Revision 18 of the ODCM is being submitted in accordance with Appendix D, Section B.5.d.3, of the YDQAP. This revision of the ODCM was approved on August 4, 2005.

Should you have any questions regarding this submittal, please contact Alice Carson at (301) 916-3995 or the undersigned at (413) 424-2261.

Very truly yours, YANKEE IC ELECTRIC COMPANY Joseph Lynch Regulatory Affairs Manager Enclosure cc:

S. Collins, NRC Region I Administrator J. Hickman, NRC Project Manager 14 DDI

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)

YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS JANUARY 1, 2005 - DECEMBER 31, 2005 DOCKET NO. 50-29 LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY Rowe, Massachusetts AREVA DOC. # 47-9016838-000

NOTES:

1.

Yankee Nuclear Power Station's last day at any power level was October 1, 1991. The facility is permanently shut down and in the final stages of decommissioning with all primary plant systems and buildings having been dismantled and removed from the site. Due to ceased power operations, short-lived nuclides have been deleted from the gaseous and liquid effluent tables. Their activity concentrations in the fuel inventory have decayed to zero values. All spent fuel and other radioactive materials that had been stored in the Spent Fuel Pool have been relocated to an on-site dry fuel storage facility with no effluent release points.

ii

TABLE OF CONTENTS

1.0 INTRODUCTION

1 2.0 METEOROLOGICAL DATA.

3 3.0 DOSE ASSESSMENT.

4 3.1 Doses From Liquid Effluents....................................................................

4 3.2 Doses From Noble Gases..

4 3.3 Doses From Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days....................................................................

4 3.4 Total Dose from Direct External Radiation, Plus Liquid and Gaseous Effluents............... 5

4.0 REFERENCES

6 Appendix A: Radioactive Liquid Effluent Monitoring Instrumentation...............

........................ A-1 Appendix B: Radioactive Gaseous Effluent Monitoring Instrumentation.............

..................... B-1 Appendix C: Liquid Holdup Tanks..................................................................... C-1 Appendix D: Radiological Environmental Monitoring Program................................................. D-1 Appendix E: Land Use Census................................................................... E-1 Appendix F: Process Control Program (PCP)...................................................................

F-1 Appendix G: Off-Site Dose Calculation Manual (ODCM)......................................................... G-1 Appendix H: Radioactive Waste Treatment Systems.............................................................. H-1 Appendix l: Supplemental Information...................................................................

1-1 Appendix J: Sewage Sludge Disposal...................................................................

J-1

-iii-04W

LIST OF TABLES TABLE IA:

TABLE 16:

TABLE IC:

TABLE 2A:

TABLE 2B:

TABLE 3:

TABLE 4:

TABLE 5:

TABLE 6:

Gaseous Effluents - Summation of All Releases.................................................... 7 Gaseous Effluents - Elevated Releases.........................................................

9 Gaseous Effluents - Ground Level Releases........................................................ 10 Liquid Effluents - Summation of All Releases....................................................... 12 Liquid Effluents - Routine Releases........................................................

14 Solid Waste and Irradiated Fuel Shipments........................................................ 18 Maximum Off-Site Doses and Dose Commitments to Members of the Public........ 20 Total Dose to Maximum Off-Site Individual (40CFR190)....................................... 21 1992-1996 Meteorological Data Joint Frequency Distribution............................... 22

-iv-04OM}0

ANNUAL (2005) RADIOACTIVE EFFLUENT RELEASE REPORT YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS

1.0 INTRODUCTION

The Yankee Decommissioning Quality Assurance Program (YDQAP), Appendix D, requires that an Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted (to the NRC) before May I of each year. This report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the site. The material provided is (1) consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) for solid waste, and (2) is in conformance with 1 OCFR50.36a and Section IV.B.1 of Appendix I to 1 OCFR50. ODCM Control 7.2 details the specific information to be included in the annual report.

In July 2002, the first dry spent fuel storage canister was placed on the Independent Spent Fuel Storage Installation (ISFSI) pad located within the station's protected area. By design, there are no liquid or gaseous effluent release pathways from storage canisters once placed on the ISFSI pad. In June 2003, all transfers of spent fuel and greater than Class C materials requiring storage in the ISFSI were completed. Following the completion of these transfers to dry storage, the Spent Fuel Pool (SFP) water inventory was processed by filtration and demineralization and released to the environment as a controlled liquid waste discharge in accordance with our NPDES permit and the ODCM. The discharge of the SFP water represented the last major source of station process water requiring processing as part of station decommissioning. Potential sources of waste water remaining which could require treatment include items such as equipment decontamination, laboratory drains and building sumps / french excavations that handle ground water and potential surface runoff (construction dewatering).

Tables 1A through 3 list the recorded radioactive gaseous (including postulated airborne materials) and liquid effluents and solid waste, respectively, with data summarized on a quarterly basis for the year. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 2005, as well as the direct dose from station related activities, including the ISFSI. Table 5 summarizes the total dose to the maximally impacted off-site individual from all station related sources for 2005.

As required by ODCM Control 7.2.b, dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the models and parameters identified in the ODCM (Reference 1). These dose estimates were made using a Method II analysis as described in the ODCM. A Method II analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) using historic meteorological data. For gaseous releases, five years of historic (1992-1996) quarterly meteorological data were used for determining the gaseous pathway doses. As required by Control 7.2.b, this report also includes an assessment of the radiation doses from radioactive effluents to W040

member(s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period, there were no recreational facilities open to the public inside the site boundary (on land), nor was permission requested or granted for recreational use of station property. Shoreline activities associated with Sherman Pond and the Deerfield River were included in the dose assessments to the maximum individual. The dose impacts for over-water activities, such as boating, are not significant due to the self-shielding of water and the transient nature of the activity leading to low occupancy times. The limited use of the Information Center on-site is associated with educational activities as they pertain to the operation /

decommissioning of the station and as such, is not included under Control 7.2.b.

Assessment of radiation doses (including direct radiation) to the most likely exposed real member(s) of the public for the calendar year for the purposes of demonstrating conformance with 40CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," also are included.

All calculated dose estimates for this reporting period are well below the regulatory dose criteria of 10CFR Part 50, Appendix I and 40CFR Part 190.

Appendices A through J indicate the status of reportable items per the requirements of the following documents:

Appendix Title Requirement Reference A

Radioactive Liquid Effluent Monitoring Instrumentation The requirement to maintain operable liquid monitoring instrumentation has been deleted.

(0CM, Rev.18)

B Radioactive Gaseous Effluent Monitoring The requirement to maintain Instrumentation operable gaseous monitoring instrumentation has been deleted.

(ODCM, Rev.18)

C Liquid Holdup Tanks YDQAP; Appendix D, Section H D

Radiological Environmental Monitoring Program ODCM (Rev.18) Control 4.1 E

Land Use Census ODCM (Rev.18) deleted the requirement to conduct a census.

F Process Control Program (PCP)

PCP Control 2.0 G

Offsite Dose Calculation Manual (ODCM)

ODCM (Rev.18) Control 7.2 H

Radioactive Treatment Systems ODCM (Rev. 18) deleted the requirement to report changes.

Supplemental Information Regulatory Guide 1.21 J

Sewage Sludge Disposal ODCM (Rev.18) Appendix A -0-4Q06

2.0 METEOROLOGICAL DATA Five years of historic meteorological data (1992-1996) collected from the site's 200-foot meteorological tower, located approximately 180 meters north of the vapor container, were used to model the atmospheric dispersion of airborne effluents. The tower instrumentation was designed to meet the requirements of Regulatory Guide 1.23 (Reference 3) for meteorological monitoring. A summary of the 1992-1996 meteorological data is provided in Table 6 of this report.

All gaseous releases are considered to be ground level since the 150-foot primary vent stack was removed during decommissioning.

Atmospheric diffusion was calculated using quarterly historical data along with the recorded quarterly effluent information. CHI/Q and D/Q values were derived for all receptor points using a straight-line airflow model. All dispersion and deposition factors have been calculated employing appropriate source configuration considerations and removal mechanism (e.g., dry deposition) described in Regulatory Guide 1.111 (Reference 4).

Terrain elevations, including downwind valley flow corrections for the surrounding area, were factored into the calculation of CHI/Q and D/Q values at each receptor location. 0420Ma

3.0 DOSE ASSESSMENT 3.1 Doses From Liquid Effluents Control 3.1 limits doses from liquid effluents to a member of the public to those specified in 10CFR Part 50, Appendix I. These limits are 3 mrem per year (1.5 mrem per quarter) for the total body and 10 mrem per year (5 mrem per quarter) for any organ. By implementing the requirements of I OCFR Part 50, Appendix I, Control 3.1 assures that the release of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."

Exposure pathways that could exist as a result of liquid effluents are fish, direct exposure from river shoreline sedimentation, milk and meat via animal ingestion of the Deerfield River water, and meat, milk, and vegetable pathways via crop irrigation with water withdrawn from the Deerfield River. Drinking water and aquatic invertebrate pathways do not exist downriver of the Yankee Nuclear Power Station at Rowe. The dose analysis for the liquid pathways assumes a dilution based on the monthly average flow at the Sherman Dam.

The whole body and organ doses due to liquid effluents were determined by summing the contributions from all pathways. The whole body and organ doses to a member of the public from liquid effluents are given in Table 4. The estimated quarterly and annual doses due to liquid effluents are well below the IOCFR Part 50, Appendix I dose criteria of Control 3.1.

For 2005, there were no liquid effluent releases from the station during the first quarter, therefore, no corresponding projected dose impact to the public. Liquid effluents releases were recorded during the second, third, and fourth quarters of the year.

3.2 Doses From Noble Gases In 2003, the last of the potential station sources (spent fuel stored in the SFP) of noble gases was eliminated with the transfer of the spent fuel to dry storage in the ISFSI during the first and second quarters of the year, and the processing and release of the SFP water inventory during the third and fourth quarters of the year. As such, no releases of noble gases occurred in 2005, and no quarterly or annual gamma and beta air doses were calculated.

3.3 Doses From Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days ODCM Control 3.5 prior to Revision 18 limited the organ doses to a member of the public from tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10CFR Part 50, Appendix 1 (7.5 mrem per quarter and 15 mrem per year). By implementing the requirements of 10CFR Part 50, Appendix I, Control 3.5 assures that the releases of tritium and particulates in gaseous effluents will be kept "as low as is reasonably achievable." It should be noted that, due to the permanent shutdown of the O4aOM 0

station (last power operation was in October 1991), the lodine-131 source term has decayed away and no longer has the potential to affect dose assessment.

Airborne particulate releases were calculated for the first and second quarters of 2005 using localized air sample data taken in close proximity to demolition of reactor support and spent fuel pool foundation structures. The third and fourth quarter 2005 postulated airborne activity was projected by conservative assumptions on residual soil and concrete concentrations. These estimates were based on the upper bound potential for the release of residual radioactivity associated with soil and concrete that had been cleared by Final Status Survey (FSS), and was subsequently processed by Thermal Desorption heat treatment for the breakdown of PCB's. Estimated airborne releases of radioactivity were not actually measured.

Exposure pathways that could exist as a result of the release of particulates and tritium to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat, and milk. Dose estimates for 2005 were made at the site boundary, historical nearest resident, nearest vegetable garden, and nearest meat animal in each of the sixteen principle compass directions. Doses were calculated for pathways that were determined by the field survey in the past to represent the local site environment. Conservatively, a vegetable garden is assumed to exist at each milk animal location when the milk pathway is included. Furthermore, the meat pathway is assumed to exist at locations where identified in the past. Meat and milk animals are assumed to receive their entire intake from pasture during the second and third quarters. In fact, there is little to no dairy operations or cattle farms in the local site area.

The organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bones, liver, kidneys, thyroid, lungs, and skin for adults, teenagers, children, and infants. The maximum estimated quarterly and annual organ doses due to tritium and particulates at any of the off-site receptor locations are reported in Table 4. The doses to all other organs at all other locations for all other age groups are less than the doses reported in Table 4. The estimated organ doses from tritium and particulates in gaseous effluents are well below the 1 OCFR Part 50, Appendix I dose criteria of Control 3.5.

3.4 Total Dose from Direct External Radiation, Plus Liquid and Gaseous Effluents The annual total dose or dose commitment to any member of the public due to releases of radioactivity and direct radiation from fixed sources are limited to the EPA's radiation protection standards for the uranium fuel cycle (40CFR190). The dose limits are set to less than or equal to 25 mrem per year to the total body or any organ, except the thyroid, which is limited to less than or equal to 75 mrem per year.

Direct external dose from fixed sources of radioactive materials, such as the on-site ISFSI, was evaluated by comparing the Station's 2005 TLD data for offsite indicator stations versus the control and outer ring (beyond 6 miles) locations. Since there was no distinguishable difference between the indicator measurements at the site boundary or beyond and the control measurements, it was concluded that there is no measurable station-related direct radiation dose for 2005. W420M0

Table 5 shows that the total dose to the maximum off-site individual for 2005 is well below the EPA dose limit criteria.

4.0 REFERENCES

1.

YNPS Offsite Dose Calculation Manual (ODCM), Revision No. 18, effective date, August 4, 2005.

2.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance With 1 OCFR Part 50, Appendix I," U.S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977.

3.

Regulatory Guide 1.23, "On-Site Meteorological Programs (Safety Guide 23)," U.S. Nuclear Regulatory Commission, Office of Standards Development, February 1972.

4.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water

- Cooled Reactors," U.S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977. 04/2OI06

TABLE 1A (Sheet 1 of 2)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases Est. Total Unit I Quarter 1 l Quarter 2 l Error, %

A.

Fission and Activation Gases

1. Total Release Ci Note 1 Note 1

2.

Average Release Rate for Period JCilsec Note 1 Note 1

3.

Percent of Control Limit Note 1 Note I B.

lodines(b)

C.

Particulates

1. Particulates with Half-lives > 8 days Ci 2.61E-04 5.07E-04

+/-3.OOE+01

2.

Average Release Rate for Period pCi/sec 3.36E-05 6.44E-05

3.

Percent of Control Limit(c) 2.21 E-02 5.37E-02

4.

Gross Alpha Radioactivity Ci 1.34E-07 1.32E-06 D.

Tritium

1. Total Release Ci 1.42E-03 3.15E-03

+/-3.OOE+01

2.

Average Release Rate for Period t

pCi/sec t 1.83E-04 (d)

I 4.01 E-04 (d)

I

3.

Percent of Control Limit Note 1:

There are no fission or activation gases available for discharge.

ND Not detected by local area temporary air particulate sampling.

(a)

Noble gas effluents have been deleted due to permanent plant shutdown.

(b)

Iodine-131 (and 1-133,1-135) data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

(c)

Per ODCM Control 3.5, the percentage of the limit is based on the combined dose contribution from lodines, tritium, and particulates with half-lives greater than 8 days. Percent of limits are calculated using ODCM Method II dose equations (Revision 17 to ODCM).

(d)

Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3. WM=80

TABLE 1A (Sheet 2 of 2)

Yankee Nuclear Power Station, Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases l

lEst.

Total Unit I Quarter 3 l Quarter 4 l Error, %

A.

Fission and Activation Gases

1. Total Release Ci Note 1 Note 1

2.

Average Release Rate for Period jCi/sec Note 1 Note 1

3.

Percent of Control Limit(a)

Note I Note I B.

lodines(b)

C.

Particulates (Note 2),

1. Particulates with Half-lives > 8 days Ci 2.95E-07 1.79E-08 i:3.00E+01

2.

Average Release Rate for Period pCi/sec 3.71 E-08 2.28E-09

3.

Percent of Control Limitc) 1.17E-03 3.35E-06

4.

Gross Alpha Radioactivity Ci ND D.

Tritium (Note 2),

1. Total Release Ci 3.20E-02

+/-3.OOE+01

2.

Average Release Rate for Period

3.

Percent of Control Limit I

VCi/sec-1--

4.03E-03 (d)

-4 (d)

I Note 1:

There are no fission or activation gases available for discharge.

Note 2:

Releases of tritium and particulates in air were projected by calculation and conservative assumptions based on upper bound potential for residual radioactivity associated with soil and concrete cleared by Final Status Survey (FSS), being released in air as a result of treatment by Thermal Desorption for breakdown of PCB's. Airbome releases not actually measured.

ND Not detected by local area temporary air particulate sampling.

(a) Noble gas effluents have been deleted due to permanent plant shutdown.

(b)

Iodine-131 (and 1-133,1-135) data have been deleted. These nudides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

(c)

Per ODCM Control 3.5, the percentage of the limit is based on the combined dose contribution from iodines, tritium, and particulates with half-lives greater than 8 days. Percent of limits are calculated using ODCM Method II dose equations (Revision 17 to ODCM).

(d)

Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3.

Dash indicates no release of this type. 04no0M

TABLE 1 B (Sheet 1 of 1)

Yankee Nuclear Power Station. Rowe. Massachusetts 200§ Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Releases The primary vent stack was removed from service on February 3, 2004, with no recorded effluents for 2004 prior to its abandonment. As a result, there is no longer an elevated gaseous release path. W20 C6

TABLE 1C (Sheet I of 2)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode(a)

Nuclides Released Unit Quarter I Quarter 2 Quarter I Quarter 2

1.

lodines b)

2.

Particulates Strontium-90 Ci 7.71 E-07 4.43E-07 Cesium-134 Ci 8.36E-10 8.36E-10 Cesium-137 Ci 2.20E-05 1.27E-05 Cobalt-60 Ci 7.73E-06 1.03E-04

__Iron-55 Ci 8.83E-06 9.86E-05 Nickel-63 Ci 5.59E-06 7.39E-05 Plutonium-238 Ci 2.25E-09 4.25E-08 Plutonium-239, 240 Ci 5.48E-09 1.78E-08 Plutonium-241 Ci 1.36E-07 3.89E-07 Americium-241 Ci 5.44E-09 1.53E-08 Curium-243, 244 Ci 9.94E-09 1.97E-08 Silver-108M Ci ND 2.32E-07 Antimony-125 Ci ND 1.56E-06 Carbon-14 Ci 2.16E-04 2.16E-04 Total for Period Ci 2.61 E-04 5.07E-04 ND Not detected by local area temporary air particulate sampling.

(a)

There are no longer any batch mode gaseous releases.

(b)

Iodine-131,1-133 and 1-135 data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

Dash indicates no release of this type. 04QO C6

TABLE IC (Sheet 2 of 2)

Yankee Nuclear Power Station, Rowe, Massachusetts 2005 Annual Radioactive Effluent Release Report Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode(a)

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

3.

lodines°

4.

Particulates Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci 2.31 E-07 1.40E-08 Cobalt-60 Ci 6.41 E-08 3.88E-09 Iron-55 Ci Nickel-63 Ci Plutonium-238 Ci Plutonium-239, 240 Ci Plutonium-241 Ci Americium-241 Ci Curium-243, 244 Ci Silver-1 08M Ci Antimony-125 Ci Total for Period Ci 2.95E-07 1.79E-08

Note: Releases estimated by calculation and conservative assumptions on upper bound of potential residual radioactivity associated with soil and concrete cleared by Final Status Survey (FSS), with subsequent treatment by Thermal Desorption for breakdown of PCB's.

ND Not detected by local area temporary air particulate sampling.

(a)

There are no longer any batch mode gaseous releases.

(b) lodine-131,1-133 and 1-135 data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

Dash indicates no release of this type.

- 1 1 -

041201D

TABLE 2A (Sheet 1 of 2)

Yankee Nuclear Power Station, Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases Unit Quarter1 Quarter 2 TErrort A.

Fission and Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci 1.16E-05

-t2.OE+01

2.

Average Diluted Concentration During Period ACi/ml 3.88E-08

3.

Percent of Applicable Limit(a) 1.06E-01 B. Tritium

1. Total Release Ci 7.98E-03

+/-1.00E+01

2.

Average Diluted Concentration During Period PCi/ml 2.67E-05

3.

Percent of Applicable Limit(a) 8.90E-01 C.

Dissolved and Entrained Gases

1. Total Release Ci 2.OE+01 l

2.

Average Diluted Concentration During Period ACi/ml

3.

Percent of Applicable Limitfb)

D. Gross Alpha Radioactivity

1. Total Release Ci I

ND 1+/- 3.50E+01 E. Volume of Waste Release (prior to dilution)

Liters 0

2.99E+05 I *1.OOE+01 F. Volume of Dilution Water Used During Period l Litersl 0

O I

.50E+01 ND Not detected in liquid effluents.

(a) Concentration limits specified in Appendix B to IOCFR20.1-20.602, Table II, Column 2 (ODCM Control 2.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

(b)

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

Dash indicates no release of this type. 04r6

TABLE 2A (Sheet 2 of 2)

Yankee Nuclear Power Station, Rowe, Massachusetts 2005 Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases Est. Total Unit Quarter 3 Quarter 4 Error, %

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci 6.56E-07 ND

+/-2.OOE+01

2.

Average Diluted Concentration During Period PCimI 7.62E-10

3.

Percent of Applicable Umit'a' 2.54E-03 B. Tritium

1. Total Release Ci 1.04E-02 2.12E-04

+/-1.OOE+01

2. Average Diluted Concentration During Period pCi/ml 1.21 E-05 2.80E-06

3.

Percent of Applicable Limitfs) 4.03E_1 9.33E-02 C.

Dissolved and Entrained Gases

1. Total Release Ci

-+/-2.OOE+01

2.

Average Diluted Concentration During Period PCi/mi

3.

Percent of Applicable Limit(b)

D. Gross Alpha Radioactivity

1. Total Release Ci ND ND

+/-3.50E+01 E. Volume of Waste Release pror to dilution)

Liters 8.61 E+05 7.57E+04

+/-1

.50E+01 F. Volume of Dilution Water Used During Period l Liters 0

1 0

+/-

l 17.50E+01l ND Not detected in liquid effluents.

(a) Concentration limits specified in Appendix B to IOCFR20.1-20.602, Table II, Column 2 (ODCM Control 2.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

(b) The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

Dash indicates no release of this type. 04r06

TABLE 2B (Sheet 1 of 2)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Liquid Effluents - Routine Releases Continuous Mode Batch Mode I Nuclides Released I

Unit I Quarter II Quarter 2 l Quarter I Quarter2 Strontium-90 Ci ND Cesium-134 Ci ND Cesium-137 Ci 2.45E-06 Cobalt-60 Ci 9.1 BE-06 Iron-55 Ci ND Unidentified Ci ND I

Total for Period (above)

I Ci I

l.16E-05 ND Not detected in liquid effluents.

Dash indicates no release of this type. MW06

TABLE 2B (Sheet 2 of 2)

Yankee Nuclear Power Station, Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Liquid Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter4 Quarter3 Quarter4 Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Cobalt-60 Ci X

6.56E-07 ND Iron-55 Ci ND ND Silver-108M Ci ND ND Unidentified Ci ND ND Total for Period (above)

Ci l

l 6.56E-07 ND ND Not detected in liquid effluents.

Dash indicates no release of this type. 04Q1tO6

TABLE 3 (Sheet I of 4)

Yankee Nuclear Power Station. Rowe, Massachusetts 2005 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments

1. First and Second Quarters A. SOLID WASTE SHIPPED FOR BURIAL OR DISPOSAL (not Irradiated fuel) 6-month Est. Total

1. Type of Waste Unit Period Error, %

a.

Dry Active Waste: (D & D Composite Waste:

m3 8.4E+03 25 demolition rubble, compactable trash, noncompactable Ci (est.)

1.67 trash)

Class A Container: metal boxes (intermodal, sealand, gondola)

b. Soil:

m3 19.3 25 Class A Ci (est.)

1.04E-04 Container: metal boxes (B-25 metal box, drums)

2. Estimate of Nuclide Composition > 1% (by type of waste)

a. Hydrogen-3 (tritium)%

11.6 Iron-55 40.1 Cobalt-60 17.5 Nickel-63 21.3 Cesium-137 6.5 Carbon-14 1.0

b.

Cobalt-60 I_%

4 48.4 Silver-108m 18.4 Cesium-1 37 j

33.2

3. Solid Waste Disposition Number of ShiDments 76 1

8 13 Mode of Trans ortation Truck/rail Truck Truck Truck/Rail Destination Envirocare, Clive, Utah Envirocare, Clive, Utah Duratek, Inc. Bear Creek, TN RACE, LLC,Memphis, TN mom0l0

TABLE 3 (Sheet 2 of 4)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments I. First and Second Quarters (continued)

B. IRRADIATED FUEL SHIPMENTS (Disposition): None 04r.o=0

TABLE 3 (Sheet 3 of 4)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Reort Solid Waste and Irradiated Fuel Shipments II. Third and Fourth Quarters A. SOLID WASTE SHIPPED FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-month Est. Total

1. Type of Waste Unit Period Error, %

a.

Dry Active Waste: (D & D Composite Waste: demolition rubble, m3 1.09E+04 25 compactable trash, noncompactable trash)

Ci (est.)

5.08 Class A Container: metal boxes (intemnodal, B-25, gondola, sealand)

2. Estimate of Nucllde Composition > 1% (by type of waste)

a.

Hydrogen-3 (tritium) o 1

3.6 Iron-55 62.5 Cobaft-60 21.3 Nickel-63 8.9 Cesium-1 37 2.3

3. Solid Waste Disposition Number of Shioments 149 4

Mode of Transportation Truck/rail Truck Truck Destination Envirocare. Clive, Utah Envirocare, Clive, Utah Duratek, Inc., Bear Creek, TN 04MM

TABLE 3 (Sheet 4 of 4)

Yankee Nuclear Power Station. Rowe, Massachusetts 2005 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments II. Third and Fourth Quarters (continued)

B. IRRADIATED FUEL SHIPMENTS (Disposition): None 04noM6

TABLE 4 (Sheet 1 of 1)

Yankee Nuclear Power Station. Rowe, Massachusetts 2005 Annual Radioactive Effluent Release ReDort Maximum (a) Off-Site Doses and Dose Commitments to Members of the Public(b)

Source Unit l St Quarter 2nd Quarter l3 Quarter 4 h Quarter Year(c)

1. Liquid Effluents Whole Body J

mrem 0 (d) 2.81E-05(')

9.52E-06(0 5.63E-08(0 l

3.77E-05 Critical Organ j mrem 0 (d) 5.30E-05('l 9.54E-06(

l 5.63E-080 l 6.26E-05

2.

Airbome Effluents Tnitium and mrem 1.66E-036) 4.03E-030 )

8.81 E-05(k) 2.5 1 E-07 5.78E.03 Particulates (Max Organ) l mrem l l 4

____81E5 l0l Noble Gases mrad 0

0 00()

0 0 0)

(B eta A ir)

(l

)

___l)

Noble Gases mrad 0 0) 0 (1 0 0)

O(D0 (1)

(Gam m a Air)

(

l

)

3.

Direct Dose Direct External Dose rnrem (m )

°

(

m) o (m)

O (m

)

o (i)

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

(k)

(I)

(m)

'Maximum means the largest fraction of corresponding 10 CFR Part 50, Appendix I, design dose objective.

The numbered footnotes indicate the location of the dose receptor, age group, and organ, where appropriate.

'Maximum' dose for the year is the sum of the maximum doses for each quarter. This results in a conservative yearly dose estimate, but still within the limits of 10 CFR Part 50.

There were no liquid releases during the first quarter of 2005.

Critical age group: Adult.

Critical age group: Child Maximum organlage group: Liver/child.

Maximum organlage group: GI-LLI/child.

Maximum organlage group: Liver, kidney, lung, GI-LLI, and thyroid of a child SW & WSW, 1300 meters: Bone of Child SW & WSW, 1300 meters: Liver of Child There were no releases of noble gases in 2005.

2005 TLD data for off-site (site boundary) indicator stations and control / outer ring (beyond 6 miles) stations were compared. No statistical difference which could be attributed to station sources was identified. 04/20106

TABLE 5 (Sheet 1 of 1)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report Total Dose to Maximum Off-Site Individual (40CFR190)

Total Body Maximum Organ(a)

Pathway (mrem)

(mrem)

Direct External 0.0 0.0 Liquids 3.77E-05 6.26E-05 Airborne 7.40E-04 5.78E-03 Annual Total 7.78E-04 5.84E-03 (a) Maximum organ includes consideration of the thyroid. 04/20/06

r-F U

I I.

f F

f rF-(

( r-I X

TABLE 6 (Sheet I of 8)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

1.

199.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) =

.09 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 0

0 1

2 0

0 0

1 0

4 (1)

.00

.00 2.56 5.13

.00

.00 2.56

.00 10.26 (2)

.00

.01 4-7 0

0 0

1 0

2 0

0 0

3 (1)

.00

.00 2.56

.00 5.13

.00

.00 7.69 (2)

.00

.01 8-12 0

1 0

0 0

0 2

3 13 6

1 0

0 0

0 26 (1)

.00 2.56

.00

.00 5.13 7.69 33.33 15.38 2.56

.00

.00 66.67 (2)

.00

.01

.03

.01

.00

.06 13-18 0

0 0

0 5

1 0

0 0

6 (1)

.00

.00 12.82 2.56

.00

.00 15.38 (2)

.00

.01

.00

.01 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 0

1 1

2 0

0 0

1 2

5 18 7

1 0

0 1

0 39 (1)

.00 2.56 2.56 5.13

.00

.00 2.56 5.13 12.82 46.15 17.95 2.56

.00

.00 2.56

.00 100.00 (2)

.00

.01

.04

.02

.00

.09 (1)-PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 04no/os

(

¶ -

f

(

It r

r I

TABLE 6 (Sheet 2 of 8)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Freauency Distribution

2.

199.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) =.36 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 1

1 1

0 0

5 (1)

.68

.00

.00 3.42 (2)

.00

.01 4-7 1

0 0

2 11 5

6 3

1 0

0 0

0 29 (1)

.68

.00

.00 1.37 7.53 3.42 4.11 2.05

.68

.00

.00 19.86 (2)

.00

.03

.01

.00

.07 8-12 0

1 0

0 0

3 6

14 49 20 0

0 0

93 (1)

.00

.68

.00

.00 2.05 4.11 9.59 33.56 13.70

.00

.00 63.70 (2)

.00

.01

.03

.12

.05

.00

.23 13-18 0

1 0

0 0

0 12 6

0 0

0 19 (1)

.00

.68

.00

.00 8.22 4.11

.00

.00 13.01 (2)

.00

.03

.01

.00

.05 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 2

3 1

1 1

0 0

5 17 19 67 29 1

0 0

146 (1) 1.37 2.05

.68

.00

.00 3.42 11.64 13.01 45.89 19.86

.68

.00

.00 100.00 (2)

.00

.01

.00

.01

.04

.05

.16

.07

.00

.36 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)-PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH)

- 23 04rAM

r-U~

I

{-

I I '.

( e r

(t e-f f

f TABLE 6 (Sheet 3 of 8)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Freguencv Distribution

3.

199.0 FTWIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 1.24 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 1

1 5

3 0

0 0

1 1

0 0

0 1

0 0

13 (1)

.20

.98

.59

.00

.20

.00

.20

.00

.00 2.55 (2)

.00

.01

.00

.03 4-7 0

3 2

0 1

3 2

17 24 21 22 16 6

3 1

0 0

121 (1)

.00

.59

.39

.00

.20

.59

.39 3.33 4.71 4.12 4.31 3.14 1.18

.59

.20

.00

.00 23.73 (2)

.00

.01

.00

.01

.00

.04

.06

.05

.04

.01

.00

.29 8-12 1

4 1

0 0

0 2

7 17 42 122 107 10 2

1 2

0 318 (1)

.20

.78

.20

.00

.39 1.37 3.33 8.24 23.92 20.98 1.96

.39

.20

.39

.00 62.35 (2)

.00

.01

.00

.02

.04

.10

.30

.26

.02

.00

.77 13-18 2

2 0

0 0

0 1

4 20 27 2

0 0

58 (1)

.39

.00

.20

.78 3.92 5.29

.39

.00

.00 11.37 (2)

.00

.01

.05

.07

.00

.14 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 4

10 8

3 1

3 4

25 43 67 164 150 18 5

3 2

0 510 (1)

.78 1.96 1.57

.59

.20

.59

.78 4.90 8.43 13.14 32.16 29.41 3.53

.98

.59

.39

.00 100.00 (2)

.01

.02

.01

.00

.01

.06

.10

.16

.40

.36

.04

.01

.00

.00 1.24 (1)-PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 04C6=

[*

I f

(

I I

T f

I

(

f F

I X TABLE 6 (Sheet 4 of 8)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

4.

199.0 FTWIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 46.68 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

1 0

0 0

1 (1)

.00

.01

.00

.01 (2)

.00

.00 C-3 299 588 303 121 89 87 85 80 81 132 224 161 97 79 99 124 0

2649 (1) 1.56 3.07 1.58

.63

.46

.45

.44

.42

.69 1.17

.84

.51

.41

.52

.65

.00 13.81 (2)

.73 1.43

.74

.29

.22

.21

.19

.20

.32

.55

.39

.24

.19

.24

.30

.00 6.45 4-7 786 1407 437 174 174 183 237 322 561 795 1107 761 509 358 376 454 0

8641 (1) 4.10 7.33 2.28

.91

.95 1.24 1.68 2.92 4.14 5.77 3.97 2.65 1.87 1.96 2.37

.00 45.05 (2) 1.91 3.42 1.06

.42

.45

.58

.78 1.36 1.93 2.69 1.85 1.24

.87

.91 1.10

.00 21.02 8-12 935 1264 163 35 37 32 39 82 162 525 792 942 569 258 241 441 0

6517 (1) 4.87 6.59

.85

.18

.19

.17

.20

.43

.84 2.74 4.13 4.91 2.97 1.34 1.26 2.30

.00 33.97 (2) 2.27 3.08

.40

.09

.08

.09

.20

.39 1.28 1.93 2.29 1.38

.63

.59 1.07

.00 15.86 13-18 216 446 19 3

0 2

1 1

11 39 172 265 68 13 11 47 0

1314 (1) 1.13 2.32

.10

.02

.00

.01

.06

.20

.90 1.38

.35

.07

.06

.25

.00 6.85 (2)

.53 1.09

.05

.01

.00

.03

.09

.42

.64

.17

.03

.11

.00 3.20 19-24 12 28 1

0 0

2 5

10 2

0 0

1 0

61 (1)

.06

.15

.01

.00

.01

.03

.05

.01

.00

.01

.00

.32 (2)

.03

.07

.00

.01

.02

.00

.15 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 2248 3733 923 333 300 304 362 485 815 1493 2300 2139 1245 709 727 1067 0

19183 (1) 11.72 19.46 4.81 1.74 1.56 1.58 1.89 2.53 4.25 7.78 11.99 11.15 6.49 3.70 3.79 5.56

.00 100.00 (2) 5.47 9.08 2.25

.81

.73

.74

.88 1.18 1.98 3.63 5.60 5.20 3.03 1.73 1.77 2.60

.00 46.68 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 04r0n6

Or C

(-

F-U 1r-V Ir U

I

(

I

(

TABLE 6 (Sheet 5 of 8)

Yankee Nuclear Power Station, Rowe, Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

5.

199.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 40.08 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 999 2950 1363 527 310 271 231 250 295 401 523 315 191 171 204 309 0

9310 (1) 6.06 17.91 8.27 3.20 1.88 1.65 1.40 1.52 1.79 2.43 3.17 1.91 1.16 1.04 1.24 1.88

.00 56.51 (2) 2.43 7.18 3.32 1.28

.75

.66

.56

.61

.72

.98 1.27

.77

.46

.42

.50

.75

.00 22.65 4-7 455 2014 392 83 66 59 74 168 242 501 730 340 172 92 151 164 0

5703 (1) 2.76 12.23 2.38

.50

.40

.36

.45 1.02 1.47 3.04 4.43 2.06 1.04

.56

.92 1.00

.00 34.62 (2) 1.11 4.90

.95

.20

.16

.14

.18

.41

.59 1.22 1.78

.83

.42

.22

.37

.40

.00 13.88 8-12 121 331 52 2

1 4

2 17 38 238 176 122 55 22 22 33 0

1236 (1)

.73 2.01

.32

.01

.02

.01

.10

.23 1.44 1.07

.74

.33

.13

.20

.00 7.50 (2)

.29

.81

.13

.00

.01

.00

.04

.09

.58

.43

.30

.13

.05

.08

.00 3.01 13-18 16 64 7

2 0

0 0

0 4

40 37 26 6

0 1

4 0

207 (1)

.10

.39

.04

.01

.00

.02

.24

.22

.16

.04

.00

.01

.02

.00 1.26 (2)

.04

.16

.02

.00

.01

.10

.09

.06

.01

.00

.01

.00

.50 19-24 0

7 0

0 0

0 9

2 0

0 0

18 (1)

.00

.04

.00

.05

.01

.00

.11 (2)

.00

.02

.00

.02

.00

.04 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 1591 5366 1814 614 377 334 307 435 579 1180 1475 805 424 285 378 510 0

16474 (1) 9.66 32.57 11.01 3.73 2.29 2.03 1.86 2.64 3.51 7.16 8.95 4.89 2.57 1.73 2.29 3.10

.00 100.00 (2) 3.87 13.06 4.41 1.49

.92

.81

.75 1.06 1.41 2.87 3.59 1.96 1.03

.69

.92 1.24

.00 40.08 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C-CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 04rA

1' f

I

(

I

[

V X

C F

1 r

TABLE 6 (Sheet 6 of 8)

Yankee Nuclear Power Station. Rowe, Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Freauency Distribution

6.

199.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 8.76 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 156 433 448 220 148 132 112 86 105 133 152 99 92 50 71 83 0

2520 (1) 4.33 12.02 12.44 6.11 4.11 3.67 3.11 2.39 2.92 3.69 4.22 2.75 2.55 1.39 1.97 2.30

.00 69.98 (2)

.38 1.05 1.09

.54

.36

.32

.27

.21

.26

.32

.37

.24

.22

.12

.17

.20

.00 6.13 4-7 69 257 83 27 17 10 25 39 54 100 144 68 38 32 34 26 0

1023 (1) 1.92 7.14 2.30

.75

.47

.28

.69 1.08 1.50 2.78 4.00 1.89 1.06

.89

.94

.72

.00 28.41 (2)

.17

.63

.20

.07

.04

.02

.06

.09

.13

.24

.35

.17

.09

.08

.06

.00 2.49 8-12 4

13 0

0 0

0 2

6 14 7

4 1

0 0

0 51 (1)

.11

.36

.00

.06

.17

.39

.19

.11

.03

.00

.00 1.42 (2)

.01

.03

.00

.01

.03

.02

.01

.00

.12 13-18 1

5 0

0 0

0 1

0 0

7 (1)

.03

.14

.00

.03

.00

.19 (2)

.00

.01

.00

.02 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 230 708 531 247 165 142 137 125 161 239 311 174 134 83 105 109 0

3601 (1) 6.39 19.66 14.75 6.86 4.58 3.94 3.80 3.47 4.47 6.64 8.64 4.83 3.72 2.30 2.92 3.03

.00 100.00 (2)

.56 1.72 1.29

.60

.40

.35

.33

.30

.39

.58

.76

.42

.33

.20

.26

.27

.00 8.76 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C-CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 0406

F-1 '(

1 I, -

r.

r' X

I r

TABLE 6 (Sheet 7 of 8)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

7.

199.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 2.79 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 30 88 83 54 60 41 47 46 44 41 52 31 15 13 16 16 0

677 (1) 2.62 7.68 7.24 4.71 5.24 3.58 4.10 4.01 3.84 3.58 4.54 2.71 1.31 1.13 1.40 1.40

.00 59.08 (2)

.07

.21

.20

.13

.15

.10

.11

.10

.13

.08

.04

.03

.04

.00 1.65 4-7 14 54 27 16 12 9

18 38 26 73 86 29 14 10 10 4

0 440 (1) 1.22 4.71 2.36 1.40 1.05

.79 1.57 3.32 2.27 6.37 7.50 2.53 1.22

.87

.35

.00 38.39 (2)

.03

.13

.07

.04

.03

.02

.04

.09

.06

.18

.21

.07

.03

.02

.01

.00 1.07 8-12 0

3 0

0 0

0 3

8 8

4 2

0 0

28 (1)

.00

.26

.00

.26

.70

.35

.17

.00

.00 2.44 (2)

.00

.01

.00

.01

.02

.01

.00

.07 13-18 0

0 0

0 1

0 0

1 (1)

.00

.09

.00

.09 (2)

.00

.00 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 44 145 110 70 72 50 65 84 73 122 147 64 31 23 26 20 0

1146 (1) 3.84 12.65 9.60 6.11 6.28 4.36 5.67 7.33 6.37 10.65 12.83 5.58 2.71 2.01 2.27 1.75

.00 100.00 (2)

.11

.35

.27

.17

.18

.12

.16

.20

.18

.30

.36

.16

.08

.06

.05

.00 2.79 (1)-PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 0420 06

fr-X

( -

t r -

I r

r r

r T

rI r

TABLE 6 (Sheet 8 of 8)

Yankee Nuclear Power Station. Rowe. Massachusetts 2005 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

8. 199.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED(MPH)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL CALM 0

0 0

1 0

0 0

1 (1)

.00

.00 (2)

.00

.00 C-3 1486 4061 2204 928 608 531 475 463 526 707 951 606 395 313 391 533 0

15178 (1) 3.62 9.88 5.36 2.26 1.48 1.29 1.16 1.13 1.28 1.72 2.31 1.47

.96

.76

.95 1.30

.00 36.93 (2) 3.62 9.88 5.36 2.26 1.48 1.29 1.16 1.13 1.28 1.72 2.31 1.47

.96

.76

.95 1.30

.00 36.93 4-7 1325 3735 941 300 270 264 356 587 918 1497 2095 1217 740 495 572 648 0

15960 (1) 3.22 9.09 2.29

.73

.66

.64

.87 1.43 2.23 3.64 5.10 2.96 1.80 1.20 1.39 1.58

.00 38.83 (2) 3.22 9.09 2.29

.73

.66

.64

.87 1.43 2.23 3.64 5.10 2.96 1.80 1.20 1.39 1.58

.00 38.83 8-12 1061 1617 216 37 38 36 43 109 230 836 1174 1208 641 283 264 476 0

8269 (1) 2.58 3.93

.53

.09

.10

.27

.56 2.03 2.86 2.94 1.56

.69

.64 1.16

.00 20.12 (2) 2.58 3.93

.53

.09

.10

.27

.56 2.03 2.86 2.94 1.56

.69

.64 1.16

.00 20.12 13-18 235 518 26 5

0 2

1 1

16 83 248 325 76 13 12 51 0

1612 (1)

.57 1.26

.06

.01

.00

.04

.20

.60

.79

.18

.03

.12

.00 3.92 (2)

.57 1.26

.06

.01

.00

.04

.20

.60

.79

.18

.03

.12

.00 3.92 19-24 12 35 1

0 0

2 14 12 2

0 0

1 0

79 (1)

.03

.09

.00

.03

.00

.19 (2)

.03

.09

.00

.03

.00

.19 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 4119 9966 3388 1270 916 833 875 1160 1690 3125 4482 3368 1854 1105 1239 1709 0

41099 (1) 10.02 24.25 8.24 3.09 2.23 2.03 2.13 2.82 4.11 7.60 10.91 8.19 4.51 2.69 3.01 4.16

.00 100.00 (2) 10.02 24.25 8.24 3.09 2.23 2.03 2.13 2.82 4.11 7.60 10.91 8.19 4.51 2.69 3.01 4.16

.00 100.00 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C-CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 04rZ01M

APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation The requirements governing the operability of radioactive liquid effluent monitoring instrumentation were removed from the ODCM (Control 5.1) with the implementation of Revision 18 to the ODCM. The plant-installed processing pathway with its associated monitor was abandoned on July 21, 2004, as part of decommissioning activities.

A-1 04/2016

APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation The requirements of ODCM governing the operability of radioactive gaseous effluent monitoring instrumentation were removed from the ODCM per Revision 17 to the ODCM in 2004 with the removal of the primary vent stack from service on February 3, 2004, as part of station decommissioning.

B-1 04006

APPENDIX C Liquid Holdup Tanks Requirement:

Response

The Yankee Decommissioning Quality Assurance Program (YDQAP),

Appendix D, Section H, limits the quantity of radioactive material contained in any outside temporary tank. With the quantity of radioactive material in any outside temporary tank exceeding the limits of the YDQAP, a description of the events leading to this condition is required in the next Annual Radioactive Effluent Release Report.

The limits of the Yankee Decommissioning Quality Assurance Program were not exceeded during this reporting period.

C-1 04eO(2O

APPENDIX D Radiological Environmental Monitoring Program Requirement:

Response

The Radiological Environmental Monitoring Program is conducted in accordance with ODCM Control 4.1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 4.1, ODCM Control 4.1 requires a description of the reasons for not conducting the program as required and that plans for preventing a recurrence be included in the next Annual Radioactive Effluent Report.

The requirements of ODCM, Control 4.1, governing the conduction of the REMP were met for this reporting period.

D-1 04rZ6

APPENDIX E Land Use Census Revision 18 to the ODCM (implemented in August, 2005) eliminated the need to perform an annual land use census as a result of the removal of the last significant airborne effluent release sources due to site decommissioning activities. No land use census was therefore conducted in 2005.

E-1 104C

APPENDIX F Process Control Proaram (PCP)

Requirement:

Response

PCP Control 2.0 requires that licensee-initiated changes to the PCP be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made.

There were no changes to the PCP during the reporting period.

F-1 0420M0

APPENDIX G Off-Site Dose Calculation Manual (ODCM)

Requirement:

ODCM Control 7.2 requires that licensee-initiated changes to the ODCM be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.

Response

Revision 18 to the ODCM was approved for implementation on August 4, 2005.

These licensee-initiated changes that make-up Revision 18 include:

1.

Elimination of airborne release pathway assessments and dose consequence calculation requirements following completion of site demolition activities for buildings and structures that had a history of radioactive material contamination, thereby removing the airborne effluent potential (dust or resuspended particulates).

2.

Reduction in REMP sampling to eliminate airborne pathways (i.e., air sampling, food product collection, and outer area TLD monitoring) due to the elimination of the airborne effluent potential.

3.

Elimination of annual requirement for the performance of a Land Use Census as a result of the removal of airborne effluent potential.

4.

Elimination of liquid effluent monitoring/sampling requirements associated with process pathways and discharge points that no longer exist due to decommissioning activities.

5.

Minor editorial changes to consolidate the pages of the report, eliminate reference to materials and terminology no longer included in the ODCM, or update references to supporting materials.

The need for gaseous dose and set-point equations and methodology, along with the need for environmental monitoring of airborne pathways, have been eliminated from the ODCM as a direct result of potentially signfficant airborne radioactivity source terms being eliminated from the site due to the completion of plant dismantlement (demolition) activities of potentially contaminated structures.

The removal of all original plant liquid effluent control equipment has also removed the need to maintain ODCM controls previously associated with that equipment. In addition, no new or different type of effluent release condition has been created. Therefore, the proposed changes to the ODCM will maintain the level of radioactive effluent control required by 10CFR20.106 (IOCFR20.1301),

40CFR190, 10CFR50.36a, and Appendix I to 10CFR50 and not adversely impact the accuracy or reliability of effluent, dose, or set-point calculations that still remain (i.e., those associated with potential radioactive liquid effluent releases).

G-1 04=6

APPENDIX H Radioactive Waste Treatment Systems Requirement:

Response

ODCM Control 7.3 and PCP Control 3.0 require that licensee-initiated major changes to the radioactive waste systems be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

As part of decommissioning, the liquid waste evaporation processing system was permanently secured from operation on June 1, 2004. The primary vent stack gaseous treatment system was secured from operation on February 3, 2004.

Control 7.3 of the ODCM was deleted as part of Revision 18 to the ODCM H-1 0401206

APPENDIX I Supplemental Information

1. Control Limits - Dose and Dose Rate Control and Category

a. Noble Gases Control 3.3, Total Body Dose Rate Control 3.3, Skin Dose Rate Control 3.4, Gamma Air Dose Control 3.4, Gamma Air Dose Control 3.4, Beta Air Dose Control 3.4, Beta Air Dose Limit Deleted Deleted Deleted Deleted Deleted Deleted

b.

Iodine-1 31, Tritium, and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days Control 3.3, Organ Dose Rate Control 3.5, Organ Dose Control 3.5, Organ Dose

c.

Liquids Control 3.1, Total Body Dose Control 3.1, Total Body Dose Control 3.1, Organ Dose Control 3.1, Organ Dose 1500 mrem/year 7.5 mrem/quarter 15 mrem/year 1.5 mrem/quarter 3 mrem/year 5 mrem/quarter 10 mrem/year

2. Control Limits - Concentration Control and Category

a. Liquids Control 2.1, Total Sum of the Fraction of MPC (10CFR20, Appendix B, Table II, Column 2), excluding Noble Gases less than:

Control 2.1, Total Noble Gas Concentration Limit 1.0 Deleted I11 04r20106

3. Measurements and Approximations of Total Radioactivity

a. lodines. Particulates There are no longer any iodine isotopes available for discharge. The original installed airborne effluent sampling system was installed on the plant vent stack which was taken out of service on February 3, 2004. Temporary local area air particulate samplers are used during building demolition to confirm minimal dust borne releases due to building dismantlement. The errors associated with the determination of particulate effluents were estimated to be +/-30 percent.

b. Liquid Effluents A gamma isotopic analysis is performed on a representative sample using a Marinelli Beaker geometry for each batch discharge. Composite sample discharges are analyzed for Strontium-90, Iron-55 and gross alpha activity.

Tritium analysis is performed on a representative sample for each batch discharge.

The errors associated with these measurements are as follows: fission and activation products, +/-20 percent; tritium, +/-10 percent; and alpha activity, +/-35 percent.

1-2 04/2a 06

4. Batch Releases

a. Liquids Routine First Quarter Releases Number of batch releases 0

Total time period for batch releases (minutes)

Maximum time period for a batch release (minutes)

Average time period for batch releases (minutes)

Minimum time period for a batch release (minutes)

Average stream flow (Sherman Dam) during period (cfs) 858 Average discharge rate (gpm)

Routine Second Quarter Releases Number of batch releases 4

Total time period for batch releases (minutes) 1710 Maximum time period for a batch release (minutes) 750 Average time period for batch releases (minutes) 427 Minimum time period for a batch release (minutes) 210 Average stream flow (Sherman Dam) during period (cfs) 606 Average discharge rate (gpm) 46 Routine Third Quarter Releases Number of batch releases 12 Total time period for batch releases (minutes) 10,054 Maximum time period for a batch release (minutes) 1,935 Average time period for batch releases (minutes) 838 Minimum time period for a batch release (minutes) 240 Average stream flow (Sherman Dam) during period (cfs) 294 Average discharge rate (gpm) 23 Routine Fourth Quarter Releases Number of batch releases 1

Total time period for batch releases (minutes) 315 Maximum time period for a batch release (minutes) 315 Average time period for batch releases (minutes) 315 Minimum time period for a batch release (minutes) 315 Average stream flow (Sherman Dam) during period (cfs) 900 Average discharge rate (gpm) 64 1-3 304

b. Gases There are no longer any batch-mode gaseous releases associated with station systems.

5. Abnormal Releases ODCM Control 7.2 requires the reporting of any unplanned releases from the site to the site boundary of radioactive material in gaseous and liquid effluents made during the reporting period.

a. Liquid There were no non-routine liquid releases during the reporting period.

b. Gases There were no non-routine gaseous releases during the reporting period.

1-4 04/2016

APPENDIX J Sewage Sludae Disposal Requirement:

Response

ODCM, Appendix A requires that for periods in which disposal of septage occurs, the licensee shall report in the Annual Radioactive Effluent Release Report, the volume discharged, liquid and solid fractions, and total activity discharged.

There was one sewage disposal shipment (February 22) made in 2005.

Volume discharged: 6,500 gallons Liquid fraction (by weight) of waste: 0.835 Solid fraction (by weight) of waste: 0.165 Nuclide content in liquid fraction (pCi/gm): ND (a)

Nuclide content in solid fraction.:

Total radioactivity discharged:

Cs-137 = 8.25E-08 pCi/gm (wet)

Co-60 = 4.81E-07 lCi/gm Ni-63

= 1. 25E-06 pCi/gm Cs-137 = 3.35 E-01 pCi Co-60 = 1.95 E+00 pCi Ni-63

= 5.07 E+00 iuCi Total:

7.36 E+00 pCi (a) Not Detected J-1 04206

ML061230081

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1.0 INTRODUCTION

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ML061230081
Site:	Yankee Rowe (DPR-003)
Issue date:	04/26/2006
From:	Jeffery Lynch Yankee Atomic Electric Co
To:	Document Control Desk, NRC/FSME
References
BYR-06-031
Download: ML061230081 (47)
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ML061230081

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