Text

Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report and Annual Radioactive Effluent Release Report for 2008
	ML090770152
Person / Time
Site:	Yankee Rowe ; (DPR-003)
Issue date:	03/04/2009
From:	Recasha Mitchell; Yankee Atomic Electric Co
To:	; Document Control Desk, NRC/FSME
References
	BYR 2009-007
	Download: ML090770152 (46)
	v • d • e

YANKEE ATOMIC ELECTRIC COMPANY C-ANEM 49 Yankee Road, Rowe, Massachusetts 01367 March 4, 2009 BYR 2009-007 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, D.C. 20555-0001

Reference:

License No. DPR-3 (Docket Nos. 50-29 and 72-31)

Subject:

Yankee Atomic Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report and Annual Radioactive Effluent Release Report for 2008 Yankee Atomic Electric Company (YAEC) herewith submits the 2008 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 2008; If you have any questions, please contact me at 413-424-5261 Extension 303. or at rmitchell@3yankees.com.

Sincerely, 7E ATOMIC ELECTRIC CO Robert Mitchell ISFSI Manager Attachments c:

S. Collins, Regional Administrator, NRC Region 1 E. Cobey, Decommissioning Branch Chief, NRC Region 1 J. Goshen, Project Manager, NRC Headquarters M. Roberts, NRC Region 1 R. Walker, Director Radiation Control Program, MA DEP 0J

YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION License No. DPR-29 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 2008 March 2009 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 Facility.

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 2008 in compliance with the YNPS Off-Site Dose Calculation Manual (ODCM).

No changes were made to the ODCM during 2008. 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 performed in 2008 also show that operating the YNPS ISFSI results in only a small fraction of the 40 CFR Part 190 direct radiation dose limit of 25 mrem/year to members of the public.

ii

TABLE OF CONTENTS Section Title Paqe 1.0 INTR O D U CTIO N...................................................................................

1 2.0 GENERAL ISFSI AND SITE INFORMATION................................... 2 3.0 PROGRAM DESIGN..........................................................................

2 3.1 M O NITO RING Z O NES....................................................................................... 2 3.2 PATHW AYS M ONITORED..................................................................................

3

3.3 DESCRIPTION

OF M ONITORING PROGRAM............................................................

3 4.0 RADIOLOGICAL DATA

SUMMARY

TABLES.................................

9 5.0 ANALYSIS OF ENVIRONMENTAL RESULTS.................

21 5.1 SAMPLING PROGRAM DEVIATIONS.....................................

21 5.2 DIRECT RADIATION PATHW AY.......................................................................

21

6.0 REFERENCES

22 iii

LIST OF TABLES Table Title Page 3.1 Radiological Environmental Monitoring Program.............................

4 3.2 Radiological Environmental Monitoring Locations.........................

5 4.1 TLD Measurements by Half-Year....................................................

10 4.2 Exposure Rates from TLD Measurements......................................

11 4.3 TLD Data Summary.........................................................................

12 4.4 Direct Dose from ISFSI Operations...............................................

13 iv

LIST OF FIGURES Figure Title Page 3.1 Onsite Direct Radiation Monitoring Locations..............................

6 3.2 Direct Radiation Monitoring Locations (Within 1 mile)....................

7 3.3 O ffsite C ontrol Location...........................................................

8 4.1 Exposure Rate Trend at GM-2..................................................

14 4.2 Exposure Rate Trend at GM-6............................

15 4.3 Exposure Rate Trend at GM-15.................................................

16 4.4 Exposure Rate Trend at GM-16................................................

17 4.5 Exposure Rate Trend at GM-17.................................................

18 4.6 Exposure Rate Trend at GM-21................................................

19 4.7 Exposure Rate Trend at Control Location GM-27...............

20 V

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. It is submitted annually in compliance with the Offsite Dose Calculation Manual (ODCM). The remainder of this report is organized as follows:

Section 2:

Section 3:

Section 4:

Section 5:

Section 6:

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

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.

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).

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.

References Page 1 of 22

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 (Reference 3).

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.

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 by the ISFSI. The first area is called "indicator stations". The second area is called "control Page 2 of 22

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 2008 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 Insulation (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 3 of 22

Table 3.1 Radiological Environmental Monitoring Program Exposure Collection Analysis Pathway Pathway Number of Routine and/or Numbler of auine 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 4 of 22

Table 3.2 Radiological Environmental Monitoring Locations Station Code GM-27 GM-02 GM-06 GM-15 GM-16 GM-17 GM-21 Station Description Number Nine Road (O)*

Observation Stand (O)**

Readsboro Road Barrier (O)**

Onsite Perimeter (I)**

Distance Zone*

From ISFSI (km) 2 7.60 Direction From ISFSI ENE 11 1*

1 1

1 0.50 1.30 0.24 0.22 0.13 0.17 NW N

NW NNW NNE WSW

2 = Control TLD; 1 = Indicator TLD

- I = Inner Ring TLD; 0 = Outer Ring TLD Page 5 of 22

Figure 3.1 Onsite Direct Radiation Monitoring Locations Page 6 of 22

Figure 3.2 Direct Radiation Monitoring Locations (Within 1 mile)

Page 7 of 22

Figure 3.3 Offsite Control Location Page 8 of 22

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 9 of 22

Table 4.1 TLD Measurements by Half-Year (mR)

Station ID GM-02 GM-06 GM-15 GM-16 GM-17 GM-21 GM-27 Location Observation Stand Readsboro Road Barrier On-site perimeter On-site perimeter On-site perimeter On-site perimeter 1st Half-Year 2nd Half-Year 44 46 41 49 47 55 46 54 50 56 45 47 Control 37 42 Page 10 of 22

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

Station ID GM-02 GM-06 GM-15 GM-16 GM-17 GM-21 GM-27 Direction NW N

NW NNW NNE WSW Control 1st Half-Year 2nd Half-Year Annual Ave 7.4 7.5 7.5 6.7 8.2 7.5 8.1 9.6 8.8 7.9 9.3 8.6 8.8 9.8 9.3 7.6 7.8 7.7 5.8 6.6 6.2 Page 11 of 22

Table 4.3 TLD Data Summary (pR per hour)

Inner Ring TLDs Control TLDs Station With Highest Mean Mean Mean Station #

Mean (Range)

(Range)

(No. Measurements)*

8.2 6.2 GM-17 9.3 (6.7 - 9.8)

(5.8-6.6)

(8.8-9.8)

(12)

(2)

Each "measurement" is based on semi-annual readings Page 12 of 22

Table 4.4 Direct Dose from ISFSI Operations (mrem)

Station ID GM-02 GM-06 GM-15 GM-16 GM-17 GM-21 1st Half-Year Net TLD Calculated Result Dose 7.0 0.4 4.0 0.2 10.0 0.6 9.0 0.5 13.0 0.7 8.0 0.5 2nd Half-Year Net TLD Calculated Result Dose 4.0 0.2 7.0 0.4 13.0 0.7 12.0 0.7 14.0 0.8 5.0 0.3 Annual Dose 0.6 0.6 1.3 1.2 1.5 0.7 Max Dose =>

1.5 Note:

Doses based on a 250 hour0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months occupancy in both of the first and second half-years Page 13 of 22

Figure 4.1 Exposure Rate Trend at GM-2 asbom 7 AM40 GA*#=

5A**=

21114MH 3mOHm 2~b4M 33131 361 m3131 361 i

Result Discrimination Level 30m Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-02-001 GM-02-002 GM-02-003 GM-02-004 GM-02-005 GM-02-006 GM-02-007 GM-02-008 GM-02-009 GM-02-01 0 GM-02-011I GM-02-012 GM-02-01 3 GM-02-014 GM-02-015 GM-02-016 GM-02-017 GM-02-018 03131/2003 06130/2003 09/30/2003 12/31/2003 03/31/2004 0613012004 09/30/2004 12/31/2004 03/3112005 06/30/2005 0913012005 12/31/2005 03/31/2006 12/31/2006 06/30/2007 12/31/2007 06/30/2008 12/31/2008 4.2E+000 pR/ht*

6.9E+000 pR/ht*

6.7E+000 PR/ht*

6.9E+000 PR/ht*

6.0E+000 pR/ht*

7.3E+000 pR/ht*

7.0E+000 pR/ht*

6.8E+000 pR/ht*

5.5E+000 pR/ht*

7.3E+000 pR/ht*

6.7E+000 pR/ht*

6.9E+000 IjR/ht*

6.9E+000 pR/htr 6.9E+000 IjR/ht*

7.0E+000 pPRht*

7.6E+000 pR/ht*

7.4E+000 pR/ht*

7.5E+000 pR/ht*

6.OOE-001 1.OOE+000 8.OOE-001 8.OOE-001 6.OOE-001 1.60E+000 8.OOE-001 8.OOE-001 6.OOE-001 6.OOE-001 1.OOE+000 6.OOE-001 1.40E+000 1.O12+000 6.0012-001 8.OOE-001 8.OOE-001 8.00E-001 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 Results marked with

are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 14 of 22

Figure 4.2 Exposure Rate Trend at GM-6 IMH1I I.

22OH OM*.i=

3et we wt MIt 381 Result

" Discrimination Level I

Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-06-001 GM-06-002 GM-06-003 GM-06-004 GM-06-005 GM-06-006 GM-06-007 GM-06-008 GM-06-009 GM-06-010 GM-06-011 GM-06-012 GM-06-013 GM-06-014 GM-06-01 5 GM-06-016 GM-06-017 GM-06-018 03/31/2003 06/30/2003 09/30/2003 12/3112003 03/31/2004 06/30/2004 09/30/2004 12/31/2004 03/31/2005 06/30/2005 09/30/2005 12/31/2005 03/31/2006 12/31/2006 06/30/2007 12/31/2007 06/30/2008 12/31/2008 4.7E+000 liR/hr 7.6E+000 ;jR/ht*

7.3E+000 IIR/ht*

7.3E+000 piRht' 5.8E+000 pR/lvr 7.7E+000 pjR/ht*

7.8E+000 hjR/ht*

7.GE+OOO ljR/ht*

5.7E+000 IjR/ht*

7.5E+000 pR/ht*

7.4E.OOO pR/ht*

7.2E+000 I1R/ht*

7.2E+000 pR/ht*

7.7E+000 pR/hr*

7.6E+000 ijR/ht 9.OE.OOO pR/ht*

6.7E+000 pR/ht*

8.2E+000 pR/ht*

6.O0E-001 6.00E-001 8.OOE-001 1.OOE+000 6.00E-001 1.20E+000 6.OCE-C0l 8.OOE-001 8.OOE-O01 6.OOE-O01 8.OOE-001 I.OOE+000 I.OOE+000 8.OOE-001 4.OOE-001 8.00E-001 6.00E-001 8.OOE-C00 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 Results marked with

are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 15 of 22

Figure 4.3 Exposure Rate Trend at GM-1 5 I2M!4 6a*#

Go**=

Uoo.=

29OHM a=**

3=I MI1 lei 361 w6 I

" Result Discrimination Level I

Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-15-001 GM-15-002 GM-15-003 GM-15-004 GM-15-005 GM-15-006 GM-15-007 GM-15-008 GM-15-009 GM-15-010 GM-15-011 GM-15-012 GM-15-013 GM-15-014 GM-15-015 GM-15-016 GM-15-017 GM-15-018 03/31/2003 06/30/2003 09/30/2003 12/31/2003 03/31/2004 06130/2004 09/30/2004 12/3112004 03/31/2005 06/30/2005 09/30/2005 12/31/2005 03/3112006 12/31/2006 06/30/2007 12/31/2007 06/30/2008 12/31/2008 6.2E+000 pR/ht*

8.7E+000 JR/ht*

7.8E+000 pR/ht*

8.OE+000 pR/ht*

6.5E+000 pR/ht*

7.3E+000 pR/ht*

7.9E+000 JR/ht*

8.3E+000 pR/ht*

7.3E+000 pR/ht*

7.6E+000 pR/ht*

8.3E+000 R/lht*

8.IE+000,R/hr*

8.OE+000 pR/ht*

9.1 E+000 pR/ht*

1.OE+001 JR/ht*

I.OE+001 pR/ht*

8.1 E+000 pR/ht*

9.6E+000 JR/hit*

8.OOE-001 8.0OE-001 1.OOE+000 1.OOE+000 6.OOE-001 1.20E+000 8.O0E-001 6.O0E-001 1.60E+000 4.OOE-001 6.OOE-001 8.OOE-001 8.OOE-001 8.O0E-001 6.O0E-001 1.OOE+000 8.OOE-001 1.OOE+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 Results marked with

are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 16 of 22

Figure 4.4 Exposure Rate Trend at GM-16 Iab4QI A6~4M 11N11 Ml' af1 aell 301 361 I

Result Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-16-001 GM-16-002 GM-1B-003 GM-16-004 GM-16-005 GM-16-006 GM-16-007 GM-16-008 GM-16-009 GM-16-010 GM-i16-011 GM-16-012 GM-16-013 GM-16-014 GM-16-015 GM-16-016 GM-16-017 GM-16-018 03/31/2003 06/30/2003 09/30/2003 12/31/2003 03/31/2004 06/30/2004 09/30/2004 12/31/2004 03/31/2005 06/30/2005 09/30/2005 12/31/2005 03/31/2006 12/31/2006 06/30/2007 12/31/2007 06/30/2008 12/31/2008 7.2E+000 lIR/ht*

I.OE+001 MR/hi*

7.OE+O00 pR/ht*

7.3E+000 pR/ht*

5.9E+000 pR/ht*

6.1 E+000 pR/ht*

7.1E+000 pR/ht*

7.OE+000 pMRht*

5.9E+000 pR/ht*

6.3E+000 pR/ht*

8.5E+000 pR/ht" 8.OE+000 pR/ht*

7.9E+000 fIR/ht*

8.1 E+000 pR/ht*

8.2E+000 pR/hl*

9.2E+000 pR/ht*

7.9E+000 pR/ht*

9.3E+000 pR/ht*

1.OOE+000 6.OOE-001 6.OOE-001 8.OOE-001 8.OOE-001 1.60E+000 1.OOE+000 6.OOE-001 6.00E-001 4.OOE-001 8.OOE-001 1.OOE+000 8.OOE-001 8.OOE-001 6.OOE-001 1.OOE+000 8.OOE-001 1.OOE+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E'-000 Results marked with

are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 17 of 22

Figure 4.5 Exposure Rate Trend at GM-17 r I 2MMM OQMMH wol 331 "I1 361 I -,,

Result Discrimination Level I

Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-17-001 GM-17-002 GM-17-003 GM-17-004 GM-17-005 GM-17-006 GM-17-007 GM-17-008 GM-17-009 GM-17-010 GM-17-011 GM-17-012 GM-17-013 GM-17-014 GM-17-015 GM-17-016 GM-17-017 GM-17-018 03/31/2003 06/30/2003 09/30/2003 12/31/2003 03/31/2004 06/3012004 09130/2004 12/3112004 03/31/2005 06/30/2005 09/30/2005 12/31/2005 03/31/2006 12/31/2006 06130/2007 12/31/2007 06/30/2008 12/31/2008 6.1E+000 pR/htr 9.OE+000 IjR/ht" 8.9E+000 jR/ht*

8.9E+000 pR/ht*

6.8E+000 iJR/ht*

7.7E+000,R/ht*

8.6E+000 JR/hi*

8.7E+000 pR/ht*

6.9E+000 jR/ht*

7.7E+000 'R/ht*

8.OE+000,R/ht*

8.3E+000 pR/ht*

8.1E+000 pR/ht*

7.9E+000 pR/hr*

8.5E+000 MR/htr 9.OE+000 pR/ht*

8.8E+000 MR/ht*

9.8E+000 pR/ht*

6.OOE-001 8.OOE-001 8.OOE-001 1.40E+000 6.OOE-001 1.40E+000 1.20E+000 8.OOE-001 1.20E+000 6.OOE-001 8.OOE-001 8.00E-001 8.OOE-001 8.OOE-001 1.20E+000 8.OOE-001 8.OOE-001 1.OOE+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 Results marked with

are greater than 2 Sigma Error.

Results marked with t are greater than the Discrimination Level Page 18 of 22

Figure 4.6 Exposure Rate Trend at GM-21 124MI 8SM44 64*IM 4,1116411 221"M 0914M 301 wlo 301 aet Result Discrimination Level I

Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-21-001 GM-21-002 GM-21-003 GM-21-004 GM-21-005 GM-21-006 GM-21-007 GM-21 -008 GM-21-009 GM-21-010 GM-21-011 GM-21-012 GM-21-013 GM-21-014 GM-21-015 GM-21-016 GM-21-017 GM-21-018 03/31/2003 06/30/2003 09/30/2003 12/31/2003 03/31/2004 06/30/2004 09/30/2004 12/31/2004 03/31/2005 06/30/2005 09/30/2005 12/31/2005 03/31/2006 12/31/2006 06/30/2007 12/31/2007 06/30/2008 12/31/2008 6.OE+000 IJR/ht*

8.7E+000 jR/ht*

8.OE+000 hR/ht*

8.5E+000 JR/ht*

6.4E+000 IjR/ht*

7.3E+000 jR/ht*

7.SE+000 pR/ht*

8.4E+000 iJR/ht*

6.5E+000 pR/ht*

7.3E+000 pR/ht*

7.9E+000 pR/ht*

7.9E+000 JR/ht*

7.9E+000 pR/ht*

8.OE+000 IJR/ht*

8.3E+000 jR/ht*

9.4E+000 jR/ht*

7.6E+000 pR/ht*

7.8E+000 pR/ht*

8.OOE-001 1.OOE+000 8.OOE-001 1.20E+000 6.OOE-001 1.20E+000 6.OOE-001 1.OOE+000 6.OOE-001 8.OOE-001 8.00E-001 8.OOE-001 1.40E+000 8.OOE-001 8.OOE-001 1.OOE+000 8.OOE-001 8.OOE-001 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 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 22

Figure 4.7 Exposure Rate Trend at Control Location GM-27 GANN=

SAO"=

4-wQ 0

29104 14MH O0b-M 3-1 MIz 30t 361 361 Result Discrimination Level0 ]

Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-27-001 GM-27-002 GM-27-003 GM-27-004 GM-27-005 GM-27-006 GM-27-007 GM-27-008 GM-27-009 GM-27-010 GM-27-01 1 GM-27-01 2 GM-27-013 GM-27-014 GM-27-015 GM-27-016 GM-27-01 7 GM-27-01 8 03131/2003 06/30/2003 09/30/2003 12/31/2003 03/31/2004 06/30/2004 0913012004 12/31/2004 03/31/2005 06/30/2005 09/30/2005 12/31/2005 03/31/2006 12/31/2006 06/30/2007 12/31/2007 06/3012008 12/31/2008 4.2E+000 pR/ht*

6.OE+O0O PR/ht*

6.1 E+000 IpR/ht*

6.IE+OOO IjR/ht*

4.8E+000 IaR/ht*

5.1 E+OOO pR/ht*

6.5E+000 pR/ht*

6.3E+000 &IR/ht*

5.OE+000 IJR/ht*

6.4E+000 fiR/ht*

5.8E+000 pR/ht*

6.2E+000 pR/ht*

6.3E+000 pR/ht*

6.5E+000 pR/ht*

5.8E+000 IJR/ht*

6.6E+000 p~R/ht*

4.OOE-001 6OOE-001

&00E-001 8.00E-001 4.OOE-001 1.20E+000 6.O0E-001 4.O0E-001 6.OOE-001 4.OOE-001 6.OOE-001 6.OOE-001 I.00E+000 6.00E-001 6.OOE-001 6.00E-001 6.OOE-001 6.OOE-001 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 2.5E+000 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 22

5.0 ANALYSIS OF ENVIRONMENTAL RESULTS 5.1 Sampling Program Deviations A sampling program deviation is defined as samples that are unobtainable due to hazardous conditions or to malfunction of sampling equipment. Such deviations do not compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for this Radiological Environmental Monitoring Program.

No deviations of the sampling requirements occurred during this monitoring period.

5.2 Direct Radiation Pathway 5.2.1 Exposure Rates Direct radiation is continuously measured at 6 indicator locations surrounding the YNPS ISFSI, along with 1 control location at Number Nine Road using thermoluminescent dosimeters (TLDs). These dosimeters are collected semi-annually for readout at the NVLAP certified dosimetry services vendor.

Review of the data in Tables 4.2 and 4.3 shows that all indicator locations were slightly elevated in comparison to the control location exposure rates. Figures 4.1 through 4.7 provide exposure rate trends of the monitoring locations since 2003. Review of Figures 4.1 through 4.7 shows no significant difference in exposure rates over time at either the indicator or control locations. The data listed under each of the trend graphs show values for the result errors and discrimination levels. Note that these values are estimated and are shown only for information.

5.2.2 Direct Doses from ISFSI Operations The ODCM specifies that a cumulative dose estimate from direct radiation is required to be determined semi-annually. This dose estimate is the potential dose to any real member of the public that could use portions of the site or be present adjacent to the site for recreational activities throughout the year. The ODCM states 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 2008 dose estimate assumes a total of 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months occupancy for the dose calculation; of which 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months 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 Page 21 of 22

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 ID number GM-17. The maximum calculated annual dose at that location is 1.5 mrem. This value is only 6 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".

Page 22 of 22

YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION License No. DPR-29 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2008 March 2009 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 2008. There were no gaseous or liquid releases in 2008.

Table 3 summarizes waste shipped off-site for disposal for each half year of 2008. There was no waste shipped in 2008.

Appendices A through D indicate the status of reportable items per the requirements of the Off-site Dose Calculation Manual (ODCM). There were no reportable items in 2008.

Page 1 of 17

Table 1A YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2008 Gaseous Effluents-Summation of All Releases i', Nuclides Released Unit 1st 2nd Est. Total I

Qdarter Quarter ErrOr, %

F.A.

Fcsnonand Activation Gases,

1. Total Release Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit

+

N/A*

1. ~ ~ ~

~

j:

Toa4oie11________

1. Total Iodine-131 Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit N/A*

N/A*

1. Particulates with T-1/2 > 8 days Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit N/A*

N/A*

4. Gross alpha radioactivity Ci N/A*

N/A*

D~. T ritiiri1,

1. Total release Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit 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 2 of 17

Table 1A YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2008 Gaseous Effluents-Summation of All Releases

Nuclides Released

-Unit 3rd 4th Est. Total Quarter Quarter Error, %

A. Fission and:Activation Gases

1. Total Release Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit N/A*

N/A*

1. Total Iodine-131 Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit N/A*

N/A*

1. Particulates with T-1/2 > 8 days Ci N/A*

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit N/A*

N/A*

4. Gross alpha radioactivity Ci N/A*

N/A*

1. Total release Ci I

N/A*

2. Average release rate for period uCi/sec N/A*

N/A*

3. Percent of regulatory limit 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 3 of 17

Table 1 B YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2008 Gaseous Effluents-Elevated Releases Cnntiniinii~ MndA Ratrch MndA Nuclides Released Unit 1st 2nd 1st 2nd N e R Quarter Quarter Quarter Quarter Krypton-85 Ci N/A*

N/A*

Krypton-85m Ci N/A*

N/A*

Krypton-87 Ci N/A*

N/A*

Krypton-88 Ci N/A*

N/A*

Xenon-1 33 Ci N/A*

N/A*

Xenon-1 35 Ci N/A*

N/A*

Xenon-1 35m Ci N/A*

N/A*

Xenon-1 38 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

Iodine-131 Ci N/A*

N/A*

Iodine-133 Ci N/A*

N/A*

Iodine-1 35 Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

Strontium-89i N/A*

N/A N/A N/A*

Strontium-89 Ci N/A*

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-1 34 Ci N/A*

N/A*

Cesium-I 37 Ci N/A*

N/A*

NIA*

Cobalt-60 Ci N/A*

N/A*

Barium-Lanthanum-140 Ci N/A*

N/A*

Others-Plutonium-238 Ci N/A*

N/A*

Curium-243,244 Ci N/A*

N/A*

Uranium-234 Ci N/A*

N/A*

Uranium-238 Ci N/A*

N/A*

Thorium-232 Ci N/A*

N/A*

Radium-226 Ci 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 17

Table 1 B YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2008 Gaseous Effluents-Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter Krypton-85 Ci N/A*

N/A*

Krypton-85m Ci N/A*

N/A*

Krypton-87 Ci N/A*

N/A*

Krypton-88 Ci N/A*

N/A*

Xenon-1 33 Ci N/A*

N/A*

Xenon-1 35 Ci N/A*

N/A*

Xenon-1 35m Ci N/A*

N/A*

Xenon-1 38 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

Iodine-131 Ci N/A*

N/A*

Iodine-133 Ci N/A*

N/A*

Iodine-1 35 Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

Strontium-89 Ci N/A*

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-134 Ci N/A*

N/A*

Cesium-1 37 Ci N/A*

N/A*

Cobalt-60 Ci N/A*

N/A*

Barium-Lanthanum-140 Ci N/A*

N/A*

Others-Plutonium-238 Ci N/A*

N/A*

Curium-243,244 Ci N/A*

N/A*

Uranium-234 Ci N/A*

N/A*

Uranium-238 Ci N/A*

N/A*

Thorium-232 Ci N/A*

N/A*

Radium-226 Ci 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 17

Table 1C YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2008 Gaseous Effluents-Ground Level Releases Continuous Mode Batch Mode Nuclides Released Unit 1st 2nd 1st 2nd Quarter Quarter Quarter Quarter Krypston-85aes Ci N/A*

N/A*

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

N/A*

Krypton-85m Ci N/A*

N/A*

Krypton-87 Ci N/A*

N/A*

Krypton-88 Ci N/A*

N/A*

Xenon-133 Ci N/A*

N/A*

Xenon-1 35 Ci N/A*

N/A*

Xenon-1 35m Ci N/A*

N/A*

Xenon-i 38 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

lodine-131 Ci N/A*

N/A*

Iodine-1 33 Ci N/A*

N/A*

Iodine-1 35 Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

Strontium-89 Ci N

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

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-1 34 Ci N/A*

N/A*

Cesium-I 37 Ci N/A*

N/A*

Cobalt-60 Ci N/A*

N/A*

Barium-Lanthanum-140 Ci N/A*

N/A*

Others-Plutonium-238 Ci N/A*

N/A*

Curium-243,244 Ci N/A*

N/A*

Uranium-234 Ci N/A*

N/A*

Uranium-238 Ci N/A*

N/A*

Thorium-232 Ci N/A*

N/A*

Radium-226 Ci 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 6 of 17

Table 1C YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2008 Gaseous Effluents-Ground Level Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th N

J Quarter Quarter Quarter Quarter Krypton-85 Ci N/A*

N/A*

NIA*

Krypton-85m Ci N/A*

N/A*

Krypton-87 Ci N/A*

N/A*

Krypton-88 Ci N/A*

N/A*

Xenon-133 Ci N/A*

N/A*

Xenon-1 35 Ci N/A*

N/A*

Xenon-1 35m Ci N/A*

N/A*

Xenon-1 38 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

I

ýIi n es

~

._IWV___

,odine-131 Ci NIA*

NA*

N/A*

Iodine-1 33 Ci N/A*

N/A*

Iodine-135 Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

Strontium-89 Ci N/A*

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-134 Ci N/A*

N/A*

Cesium-1 37 Ci N/A*

N/A*

Cobalt-60 Ci N/A*

N/A*

Barium-Lanthanum-140 Ci N/A*

N/A*

Others-Plutonium-238 Ci N/A*

N/A*

Curium-243,244 Ci N/A*

N/A*

Uranium-234 Ci N/A*

N/A*

Uranium-238 Ci N/A*

N/A*

Thorium-232 Ci N/A*

N/A*

Radium-226 Ci 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 17

Table 2A YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2008 Liquid Effluents-Summation of All Releases

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

2. Average diluted concentration

.uCi/mI N/A*

N/A*

during period

3. Percent of applicable limit N/A*

N/A*

B. Tritium

1. Total Release Ci N/A*

N/A*

2. Average diluted concentration

.uCi/mI N/A*

N/A*

during period

3. Percent of applicable limit N/A*

N/A*

C. Dissolved and Entrained Gases

1. Total Release Ci N/A*

N/A*

2. Average diluted concentration

.uCi/mI N/A*

N/A*

during period

3. Percent of applicable limit N/A*

N/A*

D. Gross Alpha Radioactivity

1. Total release Ci N/A*

N/A*

2. Average diluted concentration

.uCi/mI N/A*

N/A*

during period E. Volume of Waste Released (prior Liters N/A*

N/A*

to dilution)

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

N/A*

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 17

Table 2A YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2008 Liquid Effluents-Summation of All Releases

.'.Nuclides Released:

Utdht.

Total Quarter Qualrter Err0or, %

A. Fission and Activation Products

1. Total Release (not including Ci N/A*

N/A*

tritium, gasesalpha)

2. Average diluted concentration

.uCi/ml N/A*

N/A*

during period

3. Percent of applicable limit N/A*

N/A*

B. Tritium

1. Total Release Ci N/A*

N/A*

2. Average diluted concentration

.uCi/ml N/A*

N/A*

during period

3. Percent of applicable limit N/A*

N/A*

C. Dissolved and Entrained Gases

1. Total Release Ci N/A*

N/A*

2. Average diluted concentration

.uCi/ml N/A*

N/A*

during period

3. Percent of applicable limit N/A*

N/A*

D. Gross Alpha Radioactivity

1. Total release Ci N/A*

N/A*

2. Average diluted concentration

.uCi/ml N/A*

N/A*

during period E. Volume of Waste Released (prior Liters N/A*

N/A*

to dilution)

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

N/A*

During Period I

I 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 17

Table 2B YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2008 Liquid Effluents Continuous Mode Batch Mode Richdes Released

'.unit.

s2nd 1 t,

.2nd

`jQzater

QqAiier

ýQuarterA -Qua rter Strontium-89 Ci N/A*

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-1 34 Ci N/A*

N/A*

Cesium-1 37 Ci N/A*

N/A*

Iodine-131 Ci N/A*

N/A*

Cobalt-58 Ci N/A*

N/A*

Cobalt-60 Ci N/A*

N/A*

Iron-59 Ci N/A*

N/A*

Zinc-65 Ci N/A*

N/A*

Manganese-54 Ci N/A*

N/A*

Chromium-51 Ci N/A*

N/A*

Zirconium-Niobium-95 Ci N/A*

N/A*

Molybdenum-99 Ci N/A*

N/A*

Technetium-99m Ci N/A*

N/A*

Barium-Lathanium-140 Ci N/A*

N/A*

Cerium-141 Ci N/A*

N/A*

Others-Iron-55 Ci N/A*

N/A*

Antimony-125 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period (above)

Ci N/A*

N/A*

Xenon-1 33 Ci N/A*

N/A*

Xenon-1 35 Ci 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 17

Table 2B YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2008 Liquid Effluents Continuous Mode Batch Mode i '; Nuclides Released

' Unit 3rd 4th

3rd, 4th

' Quarter arter Quarter QUarter Strontium-89 Ci N/A*

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-1 34 Ci N/A*

N/A*

Cesium-1 37 Ci N/A*

N/A*

Iodine-131 Ci N/A*

N/A*

Cobalt-58 Ci N/A*

N/A*

Cobalt-60 Ci N/A*

N/A*

Iron-59 Ci N/A*

N/A*

Zinc-65 Ci N/A*

N/A*

Manganese-54 Ci N/A*

N/A*

Chromium-51 Ci N/A*

N/A*

Zirconium-Niobium-95 Ci N/A*

N/A*

Molybdenum-99 Ci N/A*

N/A*

Technetium-99m Ci N/A*

N/A*

Barium-Lathanium-140 Ci N/A*

N/A*

Cerium-141 Ci N/A*

N/A*

Others-Iron-55 Ci N/A*

N/A*

Antimony-125 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period (above)

Ci N/A*

N/A*

Xenon-133 Ci N/A*

N/A*

Xenon-1 35 Ci 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 11 of 17

Table 3 YNPS ISFSI Effluent and Waste Disposal Semiannual Report First Half, 2008 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste

a. Spent resins, filter sludges, evaporator bottoms, etc.

b. Dry compressible waste, contaminated equipment, etc.

c. Irradiated components, control rods, etc.

Unit 6-Month Period m 3 0.0 Ci 0.0 m 3 0.0 Ci 0.0 m 3 0.0 Ci 0.0 Est. Total Error,

2. Estimate of major nuclide composition (by type of waste)

a. No Shipments 0

b. No Shipments 0

c. No Shipments 0

3. Solid Waste Disposition Number of Shipments None Mode of Transportation Destination B. Irradiated Fuel Shipments (Disposition)

Number of Shipments None Mode of TransDortation Destination Page 12 of 17

Table 3 YNPS ISFSI Effluent and Waste Disposal Semiannual Report Second Half, 2008 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste

a. Spent resins, filter sludges, evaporator bottoms, etc.

b. Dry compressible waste, contaminated equipment, etc.

c. Irradiated components, control rods, etc.

Unit 6-Month Period m 3 0.0 Ci 0.0 m 3 0.0 Ci 0.0 m 3 0.0 Ci 0.0 Est. Total Error,

2. Estimate of major nuclide composition (by type of waste)

a. No Shipments 0

b. No Shipments 0

c. No Shipments 0

3. Solid Waste Disposition Number of Shipments None Mode of Transportation Destination B. Irradiated Fuel Shipments (Disposition)

Number of Shipments None Mode of Transportation Destination Page 13 of 17

Appendix A Radioactive Effluent Doses There were no gaseous or liquid effluent releases in 2008. Therefore, an assessment of radiation doses to member(s) of the public allowed for recreational activities inside the site boundary was not required.

Page 14 of 17

Appendix B 40CFR190 Limits The limits specified in 40CFR190 were not exceeded in 2008. Therefore, an assessment of radiation doses to the most likely exposed real member(s) of the public was not required.

Page 15 of 17

Appendix C Unplanned Releases There were no unplanned releases of radioactive materials in effluents in 2008.

Page 16 of 17

Appendix D Off-site Dose Calculation Manual Changes There were no changes to the Off-site Dose Calculation Manual in 2008.

Page 17 of 17

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Issue date:	03/04/2009
From:	Recasha Mitchell Yankee Atomic Electric Co
To:	Document Control Desk, NRC/FSME
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