ML11126A235

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Yankee Atomic Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report and Annual Radioactive Effluent Release Report for 2010
ML11126A235
Person / Time
Site: Yankee Rowe
Issue date: 04/11/2011
From: Recasha Mitchell
Yankee Atomic Electric Co
To:
Document Control Desk, NRC/FSME
References
BYR 2011-012
Download: ML11126A235 (42)
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Text

YANKEE A TOMIC ELECTRIC COMPANY SYAN [E*, 49 Yankee Road, Rowe, Massachusetts 01367 April 11,2011 BYR 2011-012 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, D.C. 20555-0001

Reference:

License No. DPR-3 (Docket Nos. 50-29 and 72-3 1)

Subject:

Yankee Atomic Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report and Annual Radioactive Effluent Release Report for 2010 Yankee Atomic Electric Company (YAEC) herewith submits the 2010 Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report for the Yankee Atomic Independent Spent Fuel Storage Installation. There were no changes made in Off-Site Dose Calculation Manual in 2010.

If you have any questions, please contact me at 413-424-5261 Extension 303 or at rmitchell( 3yankees.com.

Sincerely, EE ATOMIC ELECTRIC CO Robert Mitchell ISFSI Manager Attachments c: W.Dean, Regional Administrator, NRC Region I J. Joustra, Decommissioning Branch Chief, NRC Region I J. Goshen, Project Manager, NRC Headquarters M. Roberts, NRC Region 1 R. Gallagher, Director Radiation Control Program, MA DEP

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YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION License No. DPR-29 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Januarv - December 2010 RSCS Radiation Safety & Control Services March 2011 Prepared by:

Radiological Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468

EXECUTIVE

SUMMARY

Yankee Nuclear Power Station was permanently shutdown in 1991. All fuel has been transferred into dry storage casks and placed at the Independent Spent Fuel Storage Installation. The Radiological Environmental Monitoring Program (REMP) for the Yankee Nuclear Power Station (YNPS) Independent Spent Fuel Storage Installation (ISFSI) located in Rowe, MA was continued for the period January through December 2010 in compliance with the YNPS Off-Site Dose Calculation Manual (ODCM).

No changes were made to the ODCM during 2010. By design, there are no liquid or gaseous effluents associated with the operation of the ISFSI. Therefore, the ODCM only requires monitoring of direct exposure from the facility. TLDs were used to measure direct gamma exposure at six locations in the vicinity of the ISFSI and one control location 7.6 kilometers away. The results of these measurements showed no significant change in exposure rates and potential doses to-members of the public during the monitoring period.

The results of the monitoring iperf,-r"r-e-in201.0-also show that operating the YNPS ISFSI results in only a small fractionof thpe40 CFR Part 190 and 10 CFR Part 72.104 direct radiation dose limit of 25 mrem/year to members of the public.

Page 2 of 27

TABLE OF CONTENTS Section Title Paqe 1.0 INTR O D UC TIO N.......................................................................................... 6 2.0 GENERAL ISFSI AND SITE INFORMATION ....................................... 7 3.0 PROGRAM DESIGN .................................................................................. 7 3.1 M ONITORING ZONES .............................................................. . . .................. 7 3.2 PATHWAY S MO NFToRED ............................................................................................. 8

3.3 DESCRIPTION

OF M ONITORING PROGRAM ........................................................................ 8 4.0 RADIOLOGICAL DATA

SUMMARY

TABLES ..................................... 13 5.0 ANALYSIS OF ENVIRONMENTAL RESULTS ................................... 26 5.1. SAMPLING PROGRAM DEVIATIONS ....... ..... ........ ......... ........ .........

..... .... 26......

26 5.2 DIRECT RADIATION PATHWAY ............................... 26 6.0 REFER ENC ES ......................................................................................... 27 Page 3 of 27

LIST OF TABLES Table Title Paqe 3.1 Radiological Environmental Monitoring Program ............................ 9 3.2 Radiological Environmental Monitoring Locations ....................... 10 4.1 TLD Measurements by Half-Year ........................................................ 15 4.2 Exposure Rates from TLD Measurements ....................................... 16 4.3 TLD Data Summary ............................................................................... 17 4.4 Direct Dose from ISFSI Operations ..................................................... 18 Page 4 of 27

LIST OF FIGURES Figure Title Paqe 3.1 Onsite Direct Radiation Monitoring Locations ................................ 11 3.2 Direct Radiation Monitoring Locations (Within 1 mile) .................. 12 3.3 Offsite Control Location ........................................................................ 13 4.1 Exposure Rate Trend at GM-2 ............................................................. 19 4.2 Exposure Rate Trend at GM-6 ............................................................. 20 4.3 Exposure Rate Trend at GM-15 ........................................................... 21 4.4 Exposure Rate Trend at GM-16 ........................................................... 22 4.5 Exposure Rate Trend at GM-17 ........................................................... 23 4.6 Exposure Rate Trend at GM-21 .......................................................... 24 4.7 Exposure Rate Trend at Control Location GM-27 ........................... 25 Page 5 of 27

1.0 INTRODUCTION

This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Yankee in the vicinity of the Independent Spent Fuel Storage Installation in Rowe, Massachusetts during the calendar year. Itis submitted annually in compliance with the Offsite Dose Calculation Manual (ODCM).

The remainder of this report is organized as follows:

Section 2: Provides a brief description of the Yankee site and its environs.

Section 3: Provides a description of the overall REMP design. Included is a summary of the ODCM requirements for REMP sampling, tables listing TLD monitoring locations with compass sectors and distances from the plant, and maps showing the location of each of the TLD monitoring locations.

Section 4: Provides a complete set of TLD data showing measured results (mR),

TLD data converted to exposure rates (pR per hour) and calculated doses (mrem per year). This section also provides the summarized exposure rate data in the format specified by the NRC Branch Technical Position on Environmental Monitoring (Reference 1).

Section 5: Provides the results of the calendar year monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year is analyzed.

Section 6: References Page 6 of 27

2.0 GENERAL ISFSI AND SITE INFORMATION The Yankee Nuclear Power Station site is located on over 1800 acres in a predominantly rural area of northwestern Massachusetts, three-quarters of a mile south of the Vermont border. The site resides in the town of Rowe, Massachusetts, approximately 9 air miles east-northeast of North Adams, Massachusetts. The surrounding area is heavily forested and lightly populated. Hills bounding the river valley rise 500 to 1000 feet above the site, reaching elevations of 2100 feet.

The Deerfield River is used extensively for hydroelectric power generation both upstream and downstream of YNPS. The Sherman Dam, immediately adjacent to the site, operates as a hydroelectric generating station. Sherman Pond, the impoundment behind this dam, had been used as a source of cooling water for the former power-plant.

The former nuclear power plant was voluntarily shut down on October 1, 1991 after 31 years of operation. The site was involved in the process of decommissioning over the years which involved the disassembly and removal of the plant components and structures and was completed in 2006. This process took place in strict conformance with USNRC regulations. Oversight of the site closure process also took place from the U.S. Environmental Protection Agency, the Massachusetts Department of Environmental Protection, and Massachusetts Department of Public Health.

3.0 PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Yankee Nuclear Power Station ISFSI was designed to provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits. The direct dose limit for members of the public from operation of the ISFSI is 25 mrem per year (References 3 and 4).

The detailed sampling requirements of the REMP are given in the ODCM. The sampling requirements specified in the ODCM are summarized in Table 3.1 of this report. Details of the monitored locations are shown in Table 3.2, as well as Figures 3.1 through 3.3 of this report.

Page 7 of 27

3.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the ISFSI to levels found in areas not influenced bythe ISFSI. The first area is called "indicator stations". The second area is called "control stations". The distinction between the two is based on relative direction from the facility and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to releases and that due to other fluctuations in the environment, such as seasonal variations in the natural background.

3.2 Pathways Monitored Based on the design of the ISFSI, only the direct radiation exposure pathway is monitored by the REMP. This pathway is monitored by the collection of thermoluminescent dosimeters (TLDs) which are described in more detail below.

3.3 Description of Monitoring Program 3.3.1 Direct Radiation Direct gamma radiation exposure was continuously monitored during 2010 with the use of thermoluminescent dosimeters (TLDs). At each monitoring location, these TLDs are sealed in plastic bags and attached to an object such as a tree, fence or utility pole. The TLDs are posted and retrieved on a quarterly basis. All TLDs are provided and processed by a National Voluntary Laboratory Accreditation Program (NVLAP) certified vendor. The TLDs are placed at various locations around the Independent Spent Fuel Storage Installation (ISFSI). Table 3.2 lists the Station ID Codes, distances and direction of the TLDs from the ISFSI.

3.3.2 Special Monitoring Special samples can be taken that are not required in the ODCM. The sample locations do not appear in Table 3.1 or 3.2 of this report. For the monitoring period, no special samples were collected as part of the YNPS ISFSI Radiological Environmental Monitoring Program.

Page 8 of 27

Table 3.1 Radiological Environmental Monitoring Program Exposure Collection Analysis Pathway Pathway Number of Nmbler aR ine Routine Collection Analysis Analysis Sample Locations Mode Frequency Type Frequency Media LctosMd Direct Total Locations: 7 Continuous Semi-annual Gamma Each TLD Radiation (6 around dose (TLD) perimeter of the site and 1 offsite control location)

Page 9 of 27

Table 3.2 Radiological Environmental Monitoring Locations Distance Direction Station Code Station Description Zone From ISFSI From ISFSI (km)

GM-27 Number Nine Road (O)* 2 7.60 ENE GM-02 Observation Stand (O)** 1 0.50 NW GM-06 Readsboro Road Barrier (O)** 1 1.30 N GM-15 Onsite Perimeter (1)** 1 0.24 NW GM-16 Onsite Perimeter (I)** 1 0.22 NNW GM-17 Onsite Perimeter (I)** 1 0.13 NNE GM-21 Onsite Perimeter (I)** 1 0.17 WSW

  • 2 = Control TLD; 1 =Indicator TLD
    • I = Inner Ring TLD; 0 = Outer Ring TLD Page 10 of 27

Figure 3.1 Onsite Direct Radiation Monitoring Locations Page 11 of 27

Figure 3.2 Direct Radiation Monitoring Locations (Within 1 mile)

Page 12 of 27

Figure 3.3 Offsite Control Location Page 13 of 27

4.0 RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples, which were collected during the monitoring period.

Data from direct radiation measurements made by TLDs are provided in Table 4.1.

The direct measurements converted to exposure rates are provided in Table 4.2.

The summarized exposure rate results, shown in Table 4.3, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). Table 4.4 provides the estimated direct dose from ISFSI operations as determined by TLDs.

Page 14 of 27

Table 4.1 TLD Measurements by Half-Year (mR)

Station ID Location 1st Half-Year 2nd Half-Year GM-02 Observation Stand NR 40 GM-06 Readsboro Road Barrier 44 50 GM-15 On-site perimeter 50 55 GM-16 On-site perimeter 45 49 GM-17 On-site perimeter 48 57 GM-21 On-site perimeter 46 52 GM-27 Control 39 41 GM-27a Control 43 40 NOTE: NR = no reading. The TLD was missing at the time of changeout.

Page 15 of 27

Table 4.2 Exposure Rates from TLD Measurements (pR per hour)

Station ID Direction 1st Half-Year 2nd Half-Year Annual Ave GM-02 NW NR 6.2 6.2 GM-06 N 7.4 8.4 7.9 GM-15 NW 8.8 9.6 9.2 GM-16 NNW 7.7 8.2 7.9 GM-17 NNE 8.3 10.0 9.2 GM-21 WSW 7.9 8.9 8.4 GM-27 Control 6.7 6.4 6.6 NOTE: NR = no reading. The TLD was missing at the time of changeout Page 16 of 27

Table 4.3 TLD Data Summary (pR per hour)

Inner Ring TLDs Control TLDs Station With Highest Mean Mean Mean Station # Mean (Range) (Range) (Range)

(No. Measurements)* (No. Measurements)* (No. Measurements)*

8.3 6.6 GM-17 9.2 (6.2-10.0) (6.4-6.7) (8.3-10.0)

(11) (4) (2)

  • Each "measurement" is based on semi-annual readings Page 17 of 27

Table 4.4 Direct Dose from ISFSI Operations (mrem) 1st Half-Year 2nd Half-Year Net TLD Calculated Net TLD Calculated Annual Station ID Result Dose Result Dose Dose GM-02 NR NR 0.0 0.0 0.0 GM-06 3.0 0.2 9.5 0.5 0.7 GM-15 9.0 0.5 14.5 0.8 1.3 GM-16 4.0 0.2 8.5 0.5 0.7 GM-17 7.0 0.4 16.5 0.9 1.3 GM-21 5.0 0.3 11.5 0.7 0.9 Max Dose => 1.3 NOTES:

1. Doses based on a 250 hour0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> occupancy in both of the first and second half-years
2. NR = No reading. TLD was missing at the time of changeout.

Page 18 of 27

Figure 4.1 Exposure Rate Trend at GM-2 7ADHMOO lco00 14P15 b.9 b e e9 19 Result - Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-02-001 03/31/2003 4.2E+000 pR/ht

  • 6.OOE-001 .2.5E+000 GM-02-002 06/30/2003 6.9E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-02-003 09/30/2003 6.7E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-02-004 12/31/2003 6.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-02-005 03/31/2004 6.OE+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-02-006 06/30/2004 7.3E+000 pR/h t
  • 1.60E+000 2.5E+000 GM-02-007 09/30/2004 7.OE+000 pR/ht
  • 8.OOE-001 2.5E+000 GM-02-008 12/31/2004 6.8E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-02-009 03/31/2005 5.5E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-02-010 06/30/2005 7.3E+000 pR/h t
  • 6.00E-001 2.5E+000 GM-02-011 09/30/2005 6.7E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-02-012 12/31/2005 6.9E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-02-013 03/31/2006 6.9E+000 pR/h t
  • 1.40E+000 2.5E+000 GM-02-014 12/31/2006 6.9E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-02-015 06/30/2007 7.0E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-02-016 12/31/2007 7.6E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-02-017 06/30/2008 7.4E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-02-018 12/31/2008 7.5E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-02-019 06/30/2009 6.9E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-02-020 12/31/2009 6.1E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-02-022 12/31/2010 6.2E+000 pR/h t
  • 6.OOE-001 2.5E+000 Results marked with *.are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 19 of 27

Figure 4.2 Exposure Rate Trend at GM-6 tJM&oW 7A\

AM.e+00 I

CLeODS=

I - Result - Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-06-001 03/31/2003 4.7E+000 pRIh t

  • 6.OOE-001 2.5E+000 GM-06-002 06/3012003 7.6E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-06-003 09130/2003 7.3E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-004 12/31/2003 7.3E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-06-005 03/31/2004 5.8E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-06-006 06/30/2004 7.7E+000 pR/h t
  • 1.20E+000 2.5E+000 GM-06-007 09/30/2004 7.8E+000 pR/h t
  • 6.OOE-001 2,5E+000 GM-06-008 12/31/2004 7.6E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-009 03/31/2005 5.7E+000 pRIh t
  • 8.OOE-001 2.5E+000 GM-06-010 06/30/2005 7.5E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-06-011 09/3012005 7.4E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-012 12/31/2005 7.2E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-06-013 03/31/2006 7.2E+000 pR/h t
  • 1 .OOE+000 2.5E+000 GM-06-014 12/31/2006 7.7E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-015 06/30/2007 7.6E+000 pR/h t
  • 4.OOE-001 2.5E+000 GM-06-016 12/31/2007 9.OE+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-017 06/30/2008 6.7E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-06-018 12/31/2008 8.2E+000 JR/h t
  • 8.OOE-001 2.5E+000 GM-06-019 06/30/2009 6.5E+000 JR/h t
  • 6.OOE-001 2.5E+000 GM-06-020 12/31/2009 7.OE+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-06-021 06/30/2010 7.4E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-022 12/31/2010 8.4E+000 pR/h t
  • 8.OOE-001 2.5E+000 Results marked with
  • are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 20 of 27

Figure 4.3 Exposure Rate Trend at GM-15 1-2ne+001

&OBe+O0 A=O 20e.01)"

- Result - Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-15-001 03/31/2003 6.2E+000 pR/h t

  • 8.OOE-001 2.5E+000 GM-15-002 06/30/2003 8.7E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-15-003 09/30/2003 7.8E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-15-004 12/31/2003 8.OE+000 pR/h t
  • 1.00E+000 2.5E+000 GM-15-005 03/31/2004 6.5E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-15-006 06/30/2004 7.3E+000 pRJh t
  • 1.20E+000 2.5E+000 GM-15-007 09130/2004 7.9E+000 pjR/h t
  • 8.OOE-001 2.5E+000 GM-15-008 12/31/2004 8.3E+000 pRIh t
  • 6.OOE-001 2.5E+000 GM-15-009 03/31/2005 7.3E+000 pR/h t
  • 1.60E+000 2.5E+000 GM-15-010 06/30/2005 7.6E+000 pR/h t
  • 4.OOE-001 2.5E+000 GM-15-011 09/30/2005 8.3E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-15-012 12/31/2005 8.1 E+000 pRIh t
  • 8.OOE-001 2.5E+000 GM-15-013 03/31/2006 8.0E+000 pR/h t
  • 8.O0E-001 2.5E+000 GM-15-014 12/31/2006 9.1E+000 pRIh t
  • 8.OOE-001 2.5E+000 GM-15-015 06/30/2007 1.OE+001 pR/h t
  • 6.OOE-001 2.5E+000 GM-15-016 12/31/2007 1.OE+001 pR/h t
  • 1.OOE+000 2.5E+000 GM-15-017 06/30/2008 8.IE+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-15-018 12/31/2008 9.6E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-15-019 06/30/2009 1.1E+001 pR/h t
  • 1.20E+000 2.5E+000 GM-15-020 12/31/2009 8.8E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-15-021 06/30/2010 8.8E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-15-022 12/31/2010 9.6E+000 pR/h t
  • 1.OOE+000 2.5E+000 Results marked with
  • are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 21 of 27

Figure 4.4 Exposure Rate Trend at GM-16 1twe+W1

&2DMw Result Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-16-001 03/31/2003 7.2E+000 pR/h t

  • 1.OOE+000 2.5E+000 GM-16-002 06/30/2003 1.OE+001 pR/h t
  • 6.OOE-001 2.5E+000 GM-16-003 09/30/2003 7.0E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-16-004 12/31/2003 7.3E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-16-005 0313112004 5.9E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-16-006 06/3012004 6.1E+000 pR/h t
  • 1.60E+000 2.5E+000 GM-16-007 09/30/2004 7.IE+000 pR/h t
  • 1.00E+000 2.5E+000 GM-16-008 12/31/2004 7.0E+000 pR/h t
  • 6.00E-001 2.5E+000 GM-16-009 03/31/2005 5.9E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-16-010 06/30/2005 6.3E+000 pR/h t
  • 4.OOE-001 2.5E+000 GM-16-011 09/30/2005 8.5E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-16-012 12/31/2005 8.0E+000 pR/h t
  • 1.00E+000 2.5E+000 GM-16-013 03/31/2006 7.9E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-16-014 12/31/2006 8.1E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-16-015 0613012007 8.2E+000 pR/h t
  • 6.00E-001 2.5E+000 GM-16-016 12/3112007 9.2E+000 pR/h t
  • 1.00E+000 2.5E+000 GM-16-017 06/30/2008 7.9E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-16-018 12/31/2008 9.3E+000 pR/h t
  • 1.00E+000 2.5E+000 GM-16-019 06/30/2009 7.4E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-16-020 12/31/2009 5.2E+000 pR/h t
  • 6.00E-001 2.5E+000 GM-16-021 06/30/2010 7.7E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-16-022 12/31/2010 8.2E+000 pR/h t
  • 8.00E-001 2.5E+000 Results marked with
  • are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 22 of 27

Figure 4.5 Exposure Rate Trend at GM-17 777-e,,ý7 77 1.oDB+OD1 4&00e+OD ObOe+001)

- Result - Discrimiation' Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-17-001 03/31/2003 6.tE+000 pR/h t

  • 6.OOE-001 2.5E+000 GM-17-002 06/30/2003 9.OE+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-17-003 09130/2003 8.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-17-004 12/31/2003 8.9E+000 jR/h f
  • 1.40E+000 2.5E+000 GM-17-005 03/31/2004 6.8E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-17-006 06/3012004 7.7E+000 jR/h t
  • 1.40E+000 2.5E+000 GM-17-007 09/30/2004 8.6E+000 pR/h t
  • 1.20E+000 2.5E+000 GM-17-008 12/31/2004 8.7E+000 VR/h t
  • 8.OOE-001 2.5E+000 GM-17-009 03/31/2005 6.9E+000 jR/h t
  • 1.20E+000 2.5E+000 GM-17-010 06/3012005 7.7E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-17-011 09/30/2005 8.OE+000 jR/h t
  • 8.OOE-001 2.5E+000 GM-17-012 12/31/2005 8.3E+000 PR/h t
  • 8.OOE-001 2.5E+000 GM-17-013 03/31/2006 8.1E+000 pR/h t
  • 8.O0E-001 2.5E+000 GM-17-014 12/3112006 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-17-015 06/30/2007 8.5E+000 pR/h t
  • 1.20E+000 2.5E+000 GM-17-016 12/31/2007 9.OE+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-17-017 06J3012008 8.8E+000 JR/h t
  • 8.OOE-001 2,5E+000 GM-17-018 12/31/2008 9.8E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-17-019 06/30/2009 6.9E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-17-020 12/31/2009 8.8E+000 pR/h t
  • 8.OOE-001 2.511+000 GM-17-021 06/30/2010 8.3E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-17-022 12/3112010 I.OE+001 pR/h t
  • 1.OOE+000 2.5E+000 Results marked with 'are greater than 2 Sigma Error.

Results marked with tare greater than the Discrimination Level Page 23 of 27

Figure 4.6 Exposure Rate Trend at GM-21 4bo0e+=o b

I - Result - Discrimination Level Sample Name . Date Collected Result 2 Sigma Error Discrimination Level GM-21-001 03/31/2003 6.OE+000 pR/h t

  • 8.OOE-001 2.5E+000 GM-21-002 06/30/2003 8.7E+000 jR/h t
  • 1.OOE+000 2.5E+000 GM-21-003 09130/2003 8.OE+000 jR/h t
  • 8.OOE-001 2.5E+000 GM-21-004 12/31/2003 8.5E+000 JR/h t
  • 1.20E+000 2.5E+000 GM-21-005 03/31/2004 6.4E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-21-006 06/30/2004 7.3E+000 JR/h t
  • 1.20E+000 2.5E+000 GM-21-007 09/30/2004 7.8E+000 JR/h t
  • 6.OOE-001 2.5E+000 GM-21-008 12/31/2004 8.4E+000 jR/h t
  • 1.OOE+000 2.5E+000 GM-21-009 03/31/2005 6.5E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-21-010 06/30/2005 7.3E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-011 09/30/2005 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-012 12/31/2005 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-013 03/31/2006 7.9E+000 pR/h t
  • 1.40E+000 2.5E+000 GM-21-014 12/31/2006 8.OE+000 pR/h t
  • 8.00E-001 2.5E+000 GM-21-015 06/30/2007 8.3E+000 pR/h t
  • 8.OOE-001 2.5E+'000 GM-21-016 12/31/2007 9.4E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-21-017 06/30/2008 7.6E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-018 12/31/2008 7.8E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-019 06/30/2009 7.6E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-020 12/31/2009 8.6E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-021 06/30/2010 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-022 12/31/2010 8.9E+000 pR/h t
  • 8.00E-001 2.5E+000 Results marked with
  • are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 24 of 27

Figure 4.7 Exposure Rate Trend at Control Location GM-27 7AWeOO a00e44E 00eoe4m0 S

I - Result " Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-27-001 03/31/2003 4.2E+000 pR/h t

  • 4.OOE-001 2.5E+000 GM-27-002 06/30/2003 6.0E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-003 09/30/2003 6.1E+000 pRh/h
  • 6.OOE-001 2.5E+000 GM-27-004 12/31/2003 6.1E+000 pR/h t 8.OOE-001 2.5E+000 GM-27-005 03/31/2004 4.8E+000 pR/h t
  • 4.OOE-001 2.5E+000 GM-27-006 06/30/2004 5.1E+000 pR/ht
  • 1.20E+000 2.5E+000 GM-27-007 09/30/2004 6.5E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-008 12/31/2004 6.3E+000 pR/h t
  • 4.OOE-001 2.5E+000 GM-27-009 03/31/2005 5.OE+000 pR/h t 6.OOE-001 2.5E+000 GM-27-010 06/30/2005 6.4E+000 pR/h t 4.OOE-001 2.5E+000 GM-27-011 09/30/2005 5.8E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-012 12/31/2005 6.2E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-013 03/31/2006 6.3E+000 pR/h t 1.OOE+000 2.5E+000 GM-27-014 12/31/2006 6.3E+O0O pR/h t
  • 6.OOE-001 2.5E+000 GM-27-015 06/30/2007 6.3E+000 pR/h t
  • 6.O0E-001 2.5E+000 GM-27-016 12/31/2007 6.5E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-017 06/30/2008 5.8E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-018 12/31/2008 6.6E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-019 06/30/2009 6.2E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-020 12/31/2009 6.1 E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-021 06/30/2010 6.7E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-022 12/31/2010 6.4E+000 pR/h t
  • 6.OOE-001 2.5E+000 Results marked with
  • are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 25 of 27

that direct exposure above background can be estimated by subtracting the average TLD value of the control station from the indicator location measurements.

As in previous years, the 2010 dose estimate assumes a total of 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> occupancy for the dose calculation; of which 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> are used in both the first and second half-years. The most likely location for exposure to a member of the public from the ISFSI is in Sherman Reservoir for boating and fishing; however, the time estimates are conservatively applied to all monitoring locations.

Table 4.4 presents the results of the dose calculations. The highest calculated dose is at Station IDnumber GM-1 7. The maximum calculated annual dose at that location is 1.3 mrem. This value is only 5 percent of the 25 mrem per year limit. For reference, this location is less than 500 feet from the ISFSI. This represents a very conservative dose estimate because a member of the public would normally be situated further away in the reservoir.

6.0 REFERENCES

1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
2. Yankee Nuclear Power Station Off-site Dose Calculation Manual, Revision 21.
3. 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation".
4. 10 CFR Part 72.104, "Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS".

Page 27 of 27

YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION License No. DPR-29 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2010 SRSCS Radiation Safety & Control Services March 2011 Prepared by:

Radiological Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468

EXECUTIVE

SUMMARY

Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2010. There were no gaseous or liquid releases in 2010.

Table 3 summarizes waste shipped off-site for disposal for each half year of 2010. There were no waste shipments in 2010.

Appendices A through C indicate the status of reportable items per the requirements of the Off-site Dose Calculation Manual (ODCM). There were no reportable items in 2010.

Page 2 of 15

Table 1 YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Gaseous Effluents-Summation of All Releases N/A*= Not Applicable There are no gaseous effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 3 of 15

Table 1A YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Gaseous Effluents - Ground Level Releases - Batch Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter Krypton-85 CiIN/A* NIA* N/A* N/A* N/A*

Krypton-85m Ci N/A* N/A* N/A* N/A* N/A*

Krypton-87 Ci N/A* N/A* N/A* N/A* N/A*

Krypton-88 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-133 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35m Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 38 Ci N/A* N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A* N/A*

Total for period Ci N/A* N/A* N/A* N/A* N/A*

Iodine-131 Ci N/A. N/A* N/A* N/A* N/A*

Iodine-1 33 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-1 35 Ci N/A* N/A* N/A* N/A* N/A*

Total for period Ci-- N/A* N/A* N/A* N/A* N/A*

.tro nt um-8!9.N.

111 1.Ji N-A Strontium-89 Ci N/A* N/A* N/A* N/A* N/A*

Strontium-90 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-134 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-137 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A*

Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A*

Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A*

Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-234 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-238 Ci N/A* N/A* N/A* N/A* N/A*

Thorium-232 Ci N/A* N/A* N/A* N/A* N/A*

Radium-226 Ci N/A* N/A* N/A* N/A* N/A*

N/A*= Not Applicable There are no gaseous effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 4 of 15

Table 1B YNPS ISFS1 Effluent and Waste Disposal Annual Report 2010 Gaseous Effluents - Ground Level Releases - Continuous Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter Krypton-85 Ci N/A* NIA* NIA* NIA* NiA*

Krypton-85m Ci N/A* N/A* N/A* N/A* N/A*

Krypton-87 Ci N/A* N/A* N/A* N/A* N/A*

Krypton-88 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-133 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35m Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 38 Ci N/A* N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A* N/A*

Totifrerd Ci N/A* NIA* N/A* N/A* N/A*

Iodine-131 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-133 Ci N/A* N/A* N/A* N/A* N/A*

lodine-135 Ci N/A* A*

N/A* NACiN/A* N/A*

N/A* N/A*

Strontium-89 Ci N/A* N/A* N/A* N/A* N/A*

Strontium-90 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-134 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-1 37 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A*

Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A*

Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A*

Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-234 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-238 Ci N/A* N/A* N/A* N/A* N/A*

Thorium-232 Ci N/A* N/A* N/A* N/A* N/A*

Radium-226 Ci N/A* N/A* N/A* N/A* N/A*

N/A*= Not Applicable There are no gaseous effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 5 of 15

Table IC YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Gaseous Effluents - Elevated Releases - Batch Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter Krypton-85 Ci N/A* N/A* N/A* N/A* N/A*

Krypton-85m Ci N/A* N/A* N/A* N/A* N/A*

Krypton-87 Ci N/A* N/A* N/A* N/A* N/A*

Krypton-88 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 33 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35m Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 38 Ci N/A* N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A* N/A*

Taforeriod Ci N/A* N/A* N/A* N/A* N/A*

lodine-131 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-133 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-135 Ci N/A* N/A* N/A* N/A* N/A*

Totalforeo Ci N/A* N/A* N/A* N/A* N/A*

Strontium-89 Ci N/A* N/A* N/A* N/A* N/A*

Strontium-90 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-134 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-137 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A*

Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A*

Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A*

Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-234 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-238 Ci N/A* N/A* N/A* N/A* N/A*

Thorium-232 Ci N/A* N/A* N/A* N/A* N/A*

Radium-226 Ci N/A* NIA* N/A* N/A* NIA*

N/A*= Not Applicable There are no gaseous effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 6 of 15

Table 1D YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Gaseous Effluents - Elevated Releases - Continuous Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter Krypton-85 Ci N/A* N/A* N/A* N/A* N/A*

Krypton-85m Ci N/A* N/A* N/A* N/A* N/A*

Krypton-87 Ci N/A* N/A* N/A* N/A* N/A*

Krypton-88 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 33 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35 Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 35m Ci N/A* N/A* N/A* N/A* N/A*

Xenon-1 38 Ci N/A* N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A* N/A*

Total for period -Ci NA /* NA /* NA Iodine-131 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-1 33 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-1 35 Ci N/A* N/A* N/A* N/A* N/A*

Total for period Ci N/A* N/A* N/A* N/A* N/A*

Strontium-89 Ci N/A* N/A* N/A* N/A* N/A*

Strontium-90 gi N/A* N/A* N/A* N/A* N/A*

Cesium-134 C N/A* N/A* N/A* N/A* N/A*

Cesium-137 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A*

Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A*

Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A*

Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-234 Ci N/A* N/A* N/A* N/A* N/A*

Uranium-238 Ci N/A* N/A* N/A* N/A* N/A*

Thorium-232 Ci N/A* N/A* N/A* N/A* N/A*

Radium-226 Ci N/A* N/A* N/A* N/A* N/A*

N/A*= Not Applicable There are no gaseous effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 7 of 15

Table 2 YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Liquid Effluents - Summation of All Releases A. Fission and Activation Products Total Release (not including Ci N/A* N/A* N/A* N/A* N/A*

tritium, gases, alpha)

Average diluted concentration pCi/ml N/A* N/A* N/A* N/A*

during period__ _ __ _ _ __ _ _ __ _ _ _ _ _ _

Percent of applicable limit  % N/A* N/A* N/A* N/A* .

B. Tritium Total Release Ci N/A* N/A* N/A* N/A* N/A*

Average diluted concentration during period Percent of applicable limit pCi/ml

{ N/A*

N/A*

N/A*

N/A*

N/A*

N/A*

N/A*

N/A*

C. Dissolved and Entrained Gases _ _ _

Total Release - Ci N/A* N/A* N/A* N/A* N/A*

Average diluted concentration pCi/ml N/A* N/A* NIA* N/A*

during period Percent of applicable limit I ________

NIA*

I _________

NIA* NIA* N/A*

D. Gross Alpha Radioactivity ___...._

Total release Ci N/A* N/A* N/A* N/A* N/A*

Average diluted concentration pCi/ml N/A* N/A* N/A* N/A*

during period ________

E. Volume of Waste Released Liters N/A* N/A* N/A* N/A*

(prior to dilution) _________

F. Volume of Dilution Water Liters N/A* N/A* N/A* N/A*

Used During Period *______

N/A*= Not Applicable There are no liquid effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 8 of 15

Table 2A YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Liquid Effluents - Batch Mode Strontium-89 Ci N/A* N/A* N/A* N/A* N/A*

Strontium-90 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-1 34 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-1 37 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-131 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-58 Ci N/A* N/A* NIA* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A*

Iron-59 Ci N/A* N/A* N/A* N/A* N/A*

Zinc-65 Ci N/A* N/A* N/A* N/A* N/A*

Manganese-54 Ci N/A* N/A* N/A* N/A* N/A*

Chromium-51 Ci N/A* N/A* N/A* N/A* N/A*

Zirconium-Niobium-95 Ci N/A* N/A* N/A* N/A* N/A*

Molybdenum-99 Ci N/A* N/A* N/A* N/A* N/A*

Technetium-99m Ci N/A* -N/A* N/A* N/A* N/A*

Barium-Lathanium-140 Ci N/A* N/A* N/A* N/A* N/A*

Cerium-141 Ci N/A* N/A* N/A* N/A* N/A*

Others-Iron-55 Ci N/A* N/A* N/A* N/A* N/A*

Antimony-125 Ci N/A* N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A* N/A*

Total for period (above) Ci N/A* N/A* N/A* N/A* N/A*

Dissolved and Entrained Ci N/A* N/A* N/A* N/A* N/A*

Gasses Tritium Ci N/A* N/A* N/A* N/A* N/A*

Gross Alpha Ci N/A* N/A* N/A* N/A* N/A*

N/A*= Not Applicable There are no liquid effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 9 of 15

Table 2B YNPS ISFSI Effluent and Waste Disposal Annual Report 2010 Liquid Effluents - Continuous Mode

____r Qu ~ ~ fte ruit Quaiite Strontium-89 Ci N/A* N/A* N/A* N/A* N/A*

Strontium-90 Ci N/A* N/A* N/A* N/A* NIA*

Cesium-134 Ci N/A* N/A* N/A* N/A* N/A*

Cesium-137 Ci N/A* N/A* N/A* N/A* N/A*

Iodine-131 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-58 Ci N/A* N/A* N/A* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A*

Iron-59 Ci N/A* N/A* N/A* N/A* N/A*

Zinc-65 Ci N/A* N/A* N/A* N/A* N/A*

Manganese-54 Ci N/A* N/A* N/A* N/A* N/A*

Chromium-51 Ci N/A* N/A* N/A* N/A* N/A*

Zirconium-Niobium-95 Ci N/A* N/A* N/A*1. N/A* N/A*

Molybdenum-99 Ci N/A* N/A* N/A* -N/A*. N/A*

Technetium-99m Ci N/A* N/A* N/A* N/A* N/A*

Barium-Lathanium-140 Ci N/A* N/A* N/A* N/A* N/A*

Cerium-141 Ci N/A* N/A* N/A* N/A* N/A*

Others- Iron-55 - Ci N/A* N/A* N/A* N/A* N/A*

Antimony-1 25 Ci N/A* N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A*. N/A*

Total for period (above) Ci N/A* N/A* N/A* N/A* N/A*

Dissolved and Entrained Ci N/A* N/A* N/A* N/A* N/A*

Gasses Tritium Ci N/A* N/A* N/A* N/A* N/A*

Gross Alpha Ci N/A* N/A* N/A* N/A* N/A*

N/A*= Not Applicable There are no liquid effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFSI)

Page 10 of 15

Table 3 YNPS ISFSI Effluent and Waste Disposal Annual Report First Half 2010 Low Level Waste Shipments Resins, Filters and Evaporator Bottoms Volume " CurieslShipped Waste Class Solidifying Agent W m Curies A 0 0 0 B 0 0 0 C 0 0 0 All 0 0 0 Major radionuclides for above data:

brvyActiv6:Waste Volume Curies Shipped Waste Class Solidifying Agent ftu mu Curies A 0 0 0 B 0 0 0 C 0 0 0 All _ __0 0 0 Major radionuclides for above data:

Irradiated Components Volume Curies Shipped Waste Class Solidifying Agent timi Curies A 0&- 0 0 B 0 0 0 C 0 0 0 All 0 0 0 Major radionuclides for above data:

Other Waste Volume Curies Shipped Waste Class Solidifying Agent ft m3 Curies A 0 0 0 B 0 0 0 C 0 0 0 All 1 0 0 0 Major radionuclides for above data:

Page 11 of 15

Table 3A YNPS ISFSI Effluent and Waste Disposal Annual Report Second Half 2010 Low Level Waste Shipments Resins, Filters and Evaporator Bottoms Volume Curies Shipped Waste Class Solidifying Agent ftW m_ Curies A 0 0 0 B 0 0 0 C 0 0 0 All 0 0 0 Major radionuclides for above data:

Dr Active Waste Volume Curies Shipped Waste Class Solidifying Agent fti M3 Curies A 0 0 0 B 0 0 0 C 0 0 0 All 0 0 0 Major radionuclides for above data:

Irradiated Components Volume Curies Shipped Waste Class Solidifying Agent W ms Curies A 0 0 0 B 0 0 0 C 0 0 0 All 0 0 0 Major radionuclides for above data:

Other Waste Volume Curies Shipped Waste Class Solidifying Agent ft3 m_3 Curies A 0 0 0 B 0 0 0 C 0 0 0 All 0 0 0 Major radionuclides for above data:

Page 12 of 15

Appendix A Radiation Dose Assessment There were no gaseous or liquid effluent releases in 2010. Therefore, an assessment of radiation doses to the most likely exposed member(s) of the public to show compliance with 40CFR190 or 10CFR72.104 from effluents was not required.

Page 13 of 15

Appendix B Unplanned Releases There were no unplanned releases of radioactive materials in effluents in 2010 Page 14 of 15

Appendix C Off-site Dose Calculation Manual Changes There were no changes to the Off-site Dose Calculation Manual in 2010.

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