ML100750343

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Yankee Atomic Independent Spent Fuel Storage Installation, Submittal of 2009 Annual Radiological Environmental Operating Report and Annual Radioactive Effluent Release Report
ML100750343
Person / Time
Site: Yankee Rowe
Issue date: 03/09/2010
From: Recasha Mitchell
Yankee Atomic Electric Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
BYR 2010-009
Download: ML100750343 (46)
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YANKEE ATOMIC ELECTRIC COMPANY 49 Yankee Road, Rowe, Massachusetts01367 March 9, 2010 BYR 2010-009 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 2009 Yankee Atomic Electric Company (YAEC) herewith submits the.2009 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 2009.

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

Sincerely, Y ~A)TOMIC ELECTRIC CO Robert Mitchell ISFSI Manager Attachments c: S. Collins, Regional Administrator, NRC Region I J. Joustra, Decommissioning Branch Chief, NRC Region 1 J. Goshen, Project Manager, NRC Headquarters M. Roberts, NRC Region 1 R. Gallagher, Director Radiation Control Program, MA DEP

YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION License No. DPR-29 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Januarv - December 2009 SRSCS Radiation Safety & Control Services March 2010 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 2009 in compliance with the YNPS Off-Site Dose Calculation Manual (ODCM).

No changes were made to the ODCM during 2009. 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 2009 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.

Page 2 of 27

TABLE OF CONTENTS Section Title Paqe

1.0 INTRODUCTION

.......................................................................................... 6 2.0 GENERAL ISFSI AND SITE INFORMATION ........................................ 7 3.0 PROGRAM DESIGN .................................................................................. 7 3 .1 MONITO RING Z ONES .................................................................................................. 7 3.2 PATHWAYS MONITrORED ............................................................................................. 8

3.3 DESCRIPTION

OF MONITORING PROGRAM ........................................................................ 8 4.0 RADIOLOGICAL DATA

SUMMARY

TABLES ..................................... 13 5.0 ANALYSIS OF ENVIRONMENTAL RESULTS ................................... 26 5.1 SAMPLING PROGRAM D EVLATIONS ....................................................................... ....... 26 5.2 DIRECT RADLATION PATHIWAY ................. .. ..............................26 6.0 'REFERENCES ......................................................................................... 27 Page 3 of 27

LIST OF TABLES Table Title Page 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 D ata S um m ary ......................................................................... 17 4.4 Direct Dose from ISFSI Operations ............................................... 18 Page 4.of 27

LIST OF FIGURES Figure Title Page 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-1 5.. .............. .......... 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. It is 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

.performanceo.f~the-p rogram~in.meeting*ODCM-req uirementsis~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 (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 Page 7 of 27

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 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 2009 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 atree, 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 T[Ds.re p*Ia--ed avarious l6c-atio ns around-th-If-dpend--tfSpenf FStF-iStorage Insulation (ISFSI). Table 3.2 lists the Station IDCodes, 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 Pand/or a th w a yN u b rofoR Number Routine Collection Analysis Analysis ut n SSample mple Sampling Frequency Type Frequency Media Locations Mode 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 (0)** 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 NNE 0.13 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 byTLDs 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 41 TLD Measurements by Half-Year (mR)

Station ID Location 1st Half-Year 2nd Half-Year GM-02 Observation Stand 39 38 GM-06 Readsboro Road Barrier 37 42 GM-15 On-site perimeter 57 50 GM-16 On-site perimeter 41 34 GM-17 On-site perimeter 39 50 GM-21 On-site perimeter 42 49 GM-27 Control 36 38 Page 15 of 27

'Table 4.2 Exposure Rates fromTLD Measurements (pR per hour)

Station ID Direction 1st Half-Year 2nd Half-Year AnnualAve GM-02 NW 6.9 6.1 6.5 GM-06 N 6.5. 7.0 6.7 GM-15 NW 11.1 8.8 9.9 GM-16 NNW 7.4 5.2 6.3 GM-17 NNE 6.9 8.8 7.9 GM-21 WSW 7.6 8.6 8.1 GM-27 Control 6.2 6.1 6.2 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)*

7.6 6.2 GM-15 9.9 (5.2-11.1) (6.1-6.2) (8.8-11.1)

(12) (2) (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 3.0 0.2 0.0 0.0 0.2 GM-06 1.0 0.1 4.0 0.2 0.3 GM-15 21.0 1.2 12.0 0.7 1.9 GM-16 5.0 0.3 0.0 0.0 0.3 GM-17 3.0 0.2 12.0 0.7 0.9 GM-21 6.0 0.3 11.0 0.6 1.0 Max Dose => 1.9 Note:

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 Page 18 of 27

Figure 4.1 Exposure Rate Trend at GM-2 640e+013 MOe+ODD 1.00e00 0.00e+=O

=J31 M31 3*i MJ31 3/31 3M31 Result Discrimination Level Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-02-001 03/31/2003 4.2E+000 pR/h t* 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 lJRIh t
  • 8.OOE-001 2.5E+000 GM-02-004 12/31/2003 6.9E+000 pIJRh t
  • 8.OOE-001 2.5E+000 GM-02-00U U131/3 I"zUU 56E000-RJhR/t*f 600E-00-1 25E: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/h t 8.OOE-001 2.5E+000 GM-02-008 12/31/2004 6.8E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-02-009 03/3112005 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.OOE-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.OE+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
  • 6.00E-001 2.5E+000 GM-02-020 12/31/2009 6.1E+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 1A0e+OO1 A

III.ljj111ýý ý GbW+MOO LOWe+000 2.00"M~

O.ODe+ODKD 3/31 311 3.W1 '13 3131 =/31 Result Discrimination Levei Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-06-001 03/31/2003 4.7E+000 pR/h t

  • 6.OOE-001 2.5E+000 GM-06-002 06/30/2003 7.6E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-06-003 09/30/2003 7.3E+000 pR/h t
  • 8.00E-001 2.5E+000 GM-06-004 12/31/2003 7.3E+000 pR/h t
  • 1:OOE+000 2:5E+000

-- GM:06z005 03/311/20047 *E-l00 Rh-tU 600E--001--

GM-06-006 06/30/2004 7.7E+000 pR/h t

  • 1.20E+000

~2.5E+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 pR/h 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 09/30/2005 7.4E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-06-012 12/31/2005 7.2E+000 pR/h t
  • 1.00E+000 2.5E+000 GM-06-013 03/31/2006 7.2E+000 pR/h t
  • 1.00E+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 pR/h t* 8.OOE-001

.2.5E+000 GM-06-019 06/30/2009 6.5E+000 pR/h t

  • 6.OOE-001 2.5E+000 GM-06-020 12/31/2009 7.OE+000 pR/h t
  • 6.OOE-001 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 120D4OO1 i.00"Mi 8&eOOO 6ML400DO 2.DBODe-XI (100"Mc 3113131 W/1 331 3/31 3131 3/31 Result Discrimination Le l Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-15-001 03/31/2003 6.2E+000 pjR/h t

  • 8.OOE-001 2.5E+000 GM-15-002 06/30/2003 8.7E+000 ljR/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 8.0E+000 pR/h t
  • 1.OOE+000 2.5E+000

-GM--15=005- 03/3112004 7.3ErVuu Fr/h t 6.OOE:z001 2:5EFD004 GM-15-006 06/30/2004 7.3E+000 pR/h t

  • 1.20E+000 2.5E+000 GM-15-007 09/30/2004 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-15-008 12/31/2004 8.3E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM- 15-009 03/3112005 7.3E+000 pR/h t
  • 1.60E+000 2.5E+000 GM-15-010 06/3012005 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 8.1E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-15-013 03/31/2006 8.0E+000 pR/h t* 8.OOE-001 2.5E+000 GM-15-014 12/31/2006 9-1E+000 pR/h 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 1.0E+001 IpR/h t* 1.OOE+000 2.5E+000 GM-15-017 06/30/2008 8.1E+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 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 1D~e+001 8110e+ODD 200e+=O 0.00e+000 3 Rs31 l 31 3/31 3W31 1 Result Diciiato ee 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 I.OE+001 pR/h t
  • 6.OOE-001 2.5E+000 GM-16-003 09/30/2003 7.OE+000 PR/h t
  • 6.00E: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 03/13T2004' oZC'uVuu run T" &8UE001Y GM-16-006 06/30/2004 6.1E+00 pJR/h t* 1.60E+000 2.5E+000 GM-16-007 09/30/2004 7.1E+000 pR/h t* 1.OOE+000 2.5E+000 GM-16-008 12/31/2004 7.OE+000 PJR/h t

  • 6.OOE-001 2.5E+000 GM-16-009 03/31/2005 5.9E+000 pJR/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 pJR/h t
  • 8.OOE-001 2.5E+000 GM-16-012 12/31/2005 8.OE+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-16-013 03/31/2006 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-16-014 12/31/2006 8.1E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-16-015 06/30/2007 8.2E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-16-016 12/31/2007 9.2E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-16-017 06/30/2008 7.9E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-16-018 12/31/2008 9.3E+000 pR/h t
  • 1.OOE+000 2.5E+000 GM-16-019 06/30/2009 7.4E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-16-020 12/31/2009 5.2E+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 22 of 27

Figure 4.5 Exposure Rate Trend at GM-17 r 6'MI 7'.'de LIJI#1 RclaR:,ý" nýss;

-Ta'lID an 1O00DOO1 6440e+OD 2=0~+=

=9~+DO

=3I MJi M,3 Mi31 MJi Result Discrimination Le Sample Name Date Collected Result 2 Sigma Error Discrimination Level GM-17-001 03/31/2003 6.IE+000 pR/h t

  • 6.00E-001 2.5E+000 GM-17-002 06/30/2003 9.OE+000 pR/h t* 8.00E-001 2.5E+000 GM-17-003 09/30/2003 8.9E+000 pR/h t* 8.00E-001 2.5E+000 GM-17-004 12/31/2003 8.9E+000 pR/h t* 1.40E+000 2.5E+000 U0IB-1/2fG4 6:13E*OOiiRM-t-' 6:00E001 2:5E+000 --

GM-17-006 06/30/2004 7.7E+000 pR/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 pR/h t
  • 8OOE-001 2.5E+000 GM-17-009 03/31/2005 6.9E+000 pR/h t
  • 1.20E+000 2.5E+000 GM-17-010 06/30/2005 7.7E+000 pR/h f
  • 6.00E-001 2.5E+000 GM-17-011 09/30/2005 8.OE+000 pR/h t
  • 8.00E-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
  • 8.00E-001 2.5E+000 GM-17-014 12/31/2006 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 9.0E+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-17-017 06/30/2008 8.8E+000 pR/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
  • 6.00E-001 2.5E+000 GM- 17-020 12/31/2009 8.8E+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 23 of 27

Figure 4.6 Exposure Rate Trend at GM-21 IJD+"Ml 6.ODD+OcD 240"M+t~

O.O~e+OOO R3eu31 .331 331

- 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

  • 8,00E-001 2.5E+000 GM-21-002 06/30/2003 8.7E+000 pR/h t
  • 1.00E+000 2.5E+000 GM-21-003 09/30/2003 8.OE+000 pR/h t
  • 8.OOE-001 2.5E+000 GM-21-004 12/31/2003 8.5E+000 pR/h t
  • 1.20E+000 2.5E+000

--- GM-2-1005- 03/--1/2004- 6. E+0001ARII--,0E=0 .. ....

-2;5E-+000-GM-21-006 06/30/2004 7.3E+000 pR/h t

  • 1.20E+000 2.5E+000 GM-21-007 09/30/2004 7.8E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-21-008 12/31/2004 8.4E+000 pR/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.OOE-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 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 7?0Oe+000

&ODDe+=O 3-01)"MO 2.00Le+=~

O.ODe+Ox) 3A41 331 3.11 3W31 MI3 aMi M/3 Result - Discrimination LeveZ 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.OE+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-003 09/30/2003 6.1E+000 pR/h t
  • 6.OOE-001 2.5E+000 GM-27-004 12/31/2003 6.1E+000. pR/h t* 8OOE-001 .2.5E+000 I

1VI-L-UU0 U01I) ILzUU1+ - -4+

E DI0 -fRlh--t4U00E-01W - 25=-*000 GM-27-006 06/30/2004 5.1E+000 pR/h t

  • 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 5.0E+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+000 PR/h t
  • 6.OOE-001 2.5E+000 GM-27-015 06/30/2007 6.3E+000 PR/h t
  • 6.OOE-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
  • 6.0OE-001 2.5E+000 GM-27-020 12/31/2009 6.1 E+000 pR/h t
  • 6.O0E-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

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 overtime 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 2009 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 Page 26 of 27

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 5. The maximum calculated annual dose at that location is 1.9 mrem. This value is only 8 percent of the 25 mrem per year limit. For reference, this location is less than 800 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 NuclearPower Operation".

Page 27 of 27

YANKEE NUCLEAR POWERSTATION INDEPENDENT SPENT FUEL STORAGE, INSTALLATION License No. DPR-29 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January -December2009 SRSCS Radiation Safety & Control Services March 2010 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 2009. There were no gaseous or liquid releases in 2009.

Table 3 summarizes waste shipped off-site for disposal for each half year of 2009. There were no waste shipments in 2009. There was one shipment of contaminated equipment to an authorized licensee for decontamination and re-use. Records of this shipment are available for review at the site.

Appendices A through D indicate the status of reportable itemsper the requirements of the Off-site Dose Calculation Manual (ODCM). There were no reportable items in 2009.

Page 1 of 17

Table 1A YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2009 Gaseous Effl uents-S ummation of Al1 Re leases 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, 2009 Gaseous Effluents-Summation of All Re leases A. Hission,,an1d.ActjvaitionGases f

1. Total Release Ci NIA* N/A* N/A*
2. Average release rate for period pCi/sec N/A* N/A*
3. Percent of regulatory limit  % N/JA* N/A*
1. Total Ilodi ne-131 Ci N/A* N/A* N/A*
2. Average. release rate forperiod iJCi/sec N/A* N/A*
3. Percent of regulatory limit  % N/A* N/A*

C. Pkti 9 K < _____

1. Particulates with T-1/2 > 8 days Ci N/A* N/A* N/A*
2. Average release rate for period pCi/sec NIA* N/A*
3. Percent of regulatory limit  % N/A* N/A*
4. Gross alpha radioactivity Ci N/A* N/A*
1. Tota I release Ci N/A* N/A* N/A*
2. Average release rate for period IJCi/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 (ISFS I)

Page 3 of 17

Table 1B YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2009 Gaseous Effluents-Elevated Re leases Continuous Mode Batch Mode Nuclides Released Unit 1st 2nd 1st 2nd Quarter Quarter Quarter Quarter Krypton-85 Ci N/A* N/A* N/A* N/A*

Krypto n-85m Ci N/A* N/A* N/A* N/A*

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

Krypto n-88 Ci NIA* N/A* N/A* N/A*

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

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

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

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

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

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

Iodi ne-131 Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Radium-226 Ci 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 (ISFS I)

Page 4 of 17

Table 1B YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2009 Gaseous Effluents-Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter Krypto n-85 Ci N/A* N/A* N/A* N/A*

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

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

Krypto n-88 Ci N/A* NIA* N/A* N/A*

Xenon-i 33 Ci N/A* N/A* NIA* N/A*

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

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

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

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

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

Iodi ne-1 31 Ci N/A* N/A* N/A* N/A*

Iodi ne-1 33 Ci N/A* N/A* N/A* N/A*

Iodi ne- 135 Ci N/A* N/A* N/A* N/A*

Tota Ifor period Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

Barium-Lanthanum-1 40 Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

Radium-226 Ci 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 Sto rage Installation (ISFS I)

Page 5 of 17

Table 1C YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2009

.Gaseous Effluents-Ground Level Releases Continuous Mode Batch Mode Nuclides Released Unit 1st 2nd 1st 2nd Quarter Quarter Quarter Quarter Krypto n-85 Ci N/A* N/A* N/A* N/A*

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

Krypto n-87 Ci N/A* N/A* N/A* N/A*

Krypto n-88 Ci N/A* N/A* N/A* N/A*

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

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

Xenon-135m Ci N/A* N/A* N/A* N/A*

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

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

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

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

lodi ne-1 33 Ci N/A* N/A* N/A* N/A*

lodine-135 Ci N/A* I N/A* N/A* N/A*

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

g1s,171417ý.Eý115 Stronti um-89 Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

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

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

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

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

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

Radium-226 Ci 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 6 of 17

Table 1C YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2009 Gaseous Effluents-Ground Level Releases Continuous Mode Batch Mode Nuclides *Released Sni Unit 3rd Quarter 4th Quarter I 3rd Quarter 4th Quarter Krypton-85 Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

Xenon-135m Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

Iodi ne-135 Ci N/A* N/A* N/A* N/A*

Total for Deriod Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

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

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

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

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

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

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

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

Radium-226 Ci 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 17

Table 2A YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2009 Liquid Effluents-Summation of All Releases

~Nuclid'e-s Rbleas'ed Ui>n At ~ 2~ 1Est.Tot~fl' A.,Fission and Activation Products

1. Total Release (not i ncludi ng Ci N/A* N/A* N/A*

tritium, gases, alpha) .

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

during period 3.-Percent of applicable limit  % N/A* NIA*

D. Gross Alpha Radioactivity

_ 1._Tota.I reIease I.- . . ........ ...... C.i........ N/A* . . .- N/A--* - N/A-

2. Average diluted concentration pCi/ml NIA* 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, 2009 Liquid Effluents-Summation of All Releases Nu618 Reea'e Un$~t 3rd 4f4h~ EsLt.Ta441 I _________jQua4rter Q4ya rte. 4Error,,%

A. Fission and Activation Products

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

tritium, gases,alpha)

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

during period

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

B. Tritium

1. Total Release Ci N/A* N/A* N/A*
2. Average diluted concentration pCi/ml N/A* N/A*

during period

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

.C. Dissolved and Entrained Gases

1. Total Release Ci N/A* N/A* N/A*
2. Average diluted concentration pCi/ml N/A* N/A*

during period

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

D. Gross Alpha Radioactivity

__l.'otalrelease_ *_C.i _N/A* ... N/A* N/A*_

2. Average diluted concentration pCi/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 N/A*= Not Applicable There are no liquid effluents associated with the Yankee Nuclear Power Station Independent Spent Fuel Storage Installation (ISFS I)

Page 9 of 17

Table 2B YNPS ISFSI Effluent and Waste Disposal Annual Report First and Second Quarters, 2009 Liquid Effluents Continuous Mode Batch Mode

_____A',d

___________ n~i Am~t~~ ~~itr 2-aie A`S QLaIQd Strontium-89 Ci N/A* N/A* N/A* N/A*

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

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

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

Iodi ne-131 Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

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

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

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

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

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

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

.,,.,L I It: I b- 'I11U II -U3 '- I)Ili,% - IM/' - I NII/" I MN1%"

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

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

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

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

Xenon-1 35 Ci 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 17

Table 2B YNPS ISFSI Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2009 Liquid Effluents Continuous Mode Batch Mode Strontium-89 Ci N/A* N/A* N/A* N/A*

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

L EJ A

  • ______ .(k-II'ý-fl&..n I- tA-* . I 1=..'-I WLIIVIIý- 11W11- ý I1 I mi /-I 1 1411--t I 11ý 1 Air-%

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

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

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

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

Xenon-1i35 Ci 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 (ISFS I)

Page 11 of 17

Table 3 YNPS ISFSI Effluent and Waste Disposal Semiannual Report First Half, 2009 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site forBurial or Disposal (Not Irradiated Fuel)

1. Type of Waste Unit 6-Month Est. Total Error, Period  %
a. Spent resins, filter sludges, m3 0.0 evaporator bottoms, etc. Ci 0.0
b. Dry compressible waste, m3 0.0 contaminated equipment, etc. Ci 0.0
c. Irradiated components, m3 0.0 control rods, etc. Ci 0.0
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 Mode of Transportation Destination None B. Irradiated Fuel Shipments (Disposition)

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

Table 3 YNPS ISFSI Effluent and Waste Disposal Semiannual Report Second Half, 2009 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste Unit 6-Month Est. Total Error, Period
a. Spent resins, filter sludges, m3 0.0 evaporator bottoms, etc. Ci 0.0
b. Dry compressible waste, m3 0.0 contaminated equipment, etc. Ci 0.0
c. Irradiated components, m3 0.0 control rods, etc. Ci 0.0
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 Mode of Transportation Destination None B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of TransDortation -Destination None Page 13 of 17

Appendix A Radioactive Effluent Doses There were no gaseous or liquid effluent releases in 2009. Therefore, an assessment of radiation doses to member(s) of the public allowed for recreational activities inside the site boundary was not required.

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Appendix B 40CFR190 Limits The limits specified in 40CFR190 were not exceeded in 2009. Therefore, an assessment of radiation doses to the most likely exposed real member(s) of the public was not required.,

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Appendix C Unplanned Releases There were no unplanned releases of radioactive materials in effluents in 2009.

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Appendix D Off-site Dose Calculation Manual Changes There were no changes to the Off-site Dose Calculation Manual in 2009.

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