ML042520229
| ML042520229 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/21/2004 |
| From: | Yankee Atomic Electric Co |
| To: | NRC/FSME |
| References | |
| -RFPFR | |
| Download: ML042520229 (221) | |
Text
Building Historical Site Assessment and Classification Summary Survey Area Name: TK#1 Base and Pipe Chase Designator: NSY-12 Survey Area Description Survey Area NSY-12 consists of the reinforced concrete pad, pipe trench and subsurface structures that comprise the base Primary Water Storage Tank (TK-1) remaining after demolition of the tank and related system piping is complete. Although the tank is called "primary" it is designated as such because of the water grade, not for its connection with primary coolant system liquid inventories. This tank feeds make-up water to the Auxiliary Boilers and 'Steam Generators.
NSY-12 is located in the RCA yard area within the bounds of NOL.06.
Further division of this survey area into survey units as necessary is dependent upon the decommissioning end state configuration.
Page 1 of 4
t Building Historical Site Assessment and Classification Summary Survey Area Name: TK#1 Base and Pipe Chase Designator NSY-12
- )
Survey Area History NSY- 12, TK- 1,was of original plant construction and was used to store de- mineralized water. The de-mineralized water system potentially became contaminated as a result of a valve line-up error, which allowed reactor coolant to flow into the de-mineralized water header.
NSY- 12 is located within the RCA. There is no documented contamination of the NSY- 12 structures.
Scoping/Characterization Radiological contamination survey of the TK- 1 base is not routinely performed.
DecommissioningActivities Decommissioning activities performed in NSY- 12 have removed the TK- 1 and associated piping.
The remaining concrete tank base is presently the location of the temporary water storage tank that contains groundwater with tritium.
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Building Historical Site Assessment and Classification Summary Survey Area Name: TK#I Base and Pipe Chase -- Designator: NSY-12 Findings Survey area NSY-12 was impacted by plant operations. Access to NSY- 12 is through'a radiation' control area.
The radionuclide mix for the NSY-12 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref 2). The primary'radionuclides 'of concern for NSY-12 are'Co-60, Cs-137, Ag-108m, Sr-90, and tritium.
CurrentStatus The TK- 1 base is currently used as location for a water storage tank. No sampling was conducted in this area.
ClassificationStatement Based upon the radiological condition of area surrounding this survey area NSY- 12 is identified as a Class 1 Area.
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Building Historical Site Assessment and Classification Summary Survey Area Name: TK#I Base and Pipe Chase Designator NSY-12 Drawings 9699-FC-50 A References
., . . . . - . .,. I I.- Plant Information Report (PIR) 77-10, dated August 10, 1977.-
- 2. l"Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-l REPT-00-001-03 I Page 4 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: TK-39 Designator: NSY-13 Survey Area Description Survey Area NSY-13 consists of the reinforced concrete pad, pipe trench and subsurface structures that comprise the base De-mineralized Water Storage Tank (TK-39) remaining after demolition of the tank and related system piping is complete. Although the tank contained "primary" water it is designated as such because of the water grade, not for its connection with primary coolant system liquid inventories.
NSY-13 is located in the RCA yard area within the bounds of NOL402.
Further division of this survey area into survey units as necessary is dependent upon the decommissioning end state configuration.
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U Building Historical Site Assessment and Classification Summary Survey Area Name: TK-39 Designator: NSY-13 Survey Area History I NSY-13, TK-39 was of original plant construction and was used to store de-mineralized water. The de-mineralized water system became potentially contaminated as a result of backward flow through a check valve in the safety injection system (Ref 1).
NSY- 13 is located within the RCA. There is no documented contamination of the NSY- 13 structures.
Scoping/Characterization Radiological contamination survey of the TK-39 is not routinely performed.
DecommissioningActivities No decommissioning activities have been performed in NSY- 13.
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Building Historical Site Assessment and Classification Summary Survey Area Name: TK-39 Designator: NSY-13 Findings Survey area NSY-13 was impacted by plant operations. Access to NSY-13 is through a radiation control area.
The radionuclide mix for the NSY-13 includes all radionuclides identified in the reactor radioactive systems 6f the plant (Ref 2). The primary'radionhuclides of concern for NSY- 13'ar6 Co-60, Cs- 137, Ag-108m, Sr-90, and tritium. -
Current Status The TK-39 is currently still in service as a de-mineralized water storage tank. No sampling was conducted in this area.
Classification Statement Based upon the radiological condition of area surrounding this survey area NSY- 13 is identified as a Class 1 Area.
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M-Building Historical Site Assessment and Classification Summary Survey Area Name: TK-39 Designator: NSY-13 Drawings JU 9699 -FC-50 B References
- 1. Plant Information Report (PIR) 77-10, dated August 10, 1977..
- 2. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT-00-001-03 Page 4 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Screenwell and Pump House Designator: OMB-01 Survey Area Description Based upon the projected end-state of decommissioning activities,' Survey'Area OMB-01 will consist of the reinforced concrete structures, floors, and walls, pump wellsmintake structure and foundations of the Screenwell Pump House.:,
The footprint of OMB-01 is approximately 220 square meters. There are additional subsurface structures associated with the footprint of the OMB-01 that include walls, pump wells, foundation and the intake structure. (See drawings for details)
Survey area OMB-01 is bounded by survey area 001)03, a Class 3 land survey area.
The intake piping of the circulating water system connects to Sherman Reservoir via a 10' diameter corrugated steel pipe. The circulating water pumps discharged through a 7' diameter concrete pipe that connects to the condensers located in the turbine building.
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N-Building Historical Site Assessment and Classification Summary Survey Area Name: Screenwell and Pump House Designator: OMB-0 1 Survey Area History Survey Area OMB did not initially contain radioactive systems, was not used to store radioactive materials or package radioactive waste. Radioactive materials were not transported through or used in this area. Installation of the ASWS (Ref 1) return line channeled the monitored discharges of liquid radioactive wastes through OMB-01 on its way to OMB-06 (Seal Pit) where the wastes were discharged. This line is potentially internally contaminated but will be removed following the drain down of the spent fuel pit (SFP-01). f Radiological assessments of OMB-Ol performed on a routine basis did not identify the present of radioactive contamination within tle area.
Draft NUREG/CR-5849 based survey was performed in OMB-01, the results of which may be qualified as characterization data, if appropriate, in preparation of a characterization survey plan in accordance with the LTP (Ref 2).
Scoping/Characterization A pre-demolition survey plan is developed in accordance with AP-083 1 Administrative Program for Radiological and Non-Radiological Characterization Surveys prior to commencing demolition activities. The implementation of this plan creates a survey that will identify radiological contamination present within OMB-01. This survey also serves as the material survey for release in accordance with AP-0052 Radiation Protection Release of Equipment, Materials and Vehicles, if appropriate, for the OMB-01 demolition materials DecommissioningActivities Decommissioning Activities performed under Secondary Side Work Package (SSWP)
SWH-01 have removed circulating water system and service water system components and the components of the traveling-screen water filtration system from OMB-01.
The ASWS was installed in OMB-01 in support of decommissioning of the original service water system. The ASWS discharge line enters OMB-01 on the south and exits on the north. The discharge side of the ASWS is the monitored release pathway for radioactive liquids releases.
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Building Historical Site Assessment and Classification' Summary Survey Area Name: Screenwell and Pump House -Designator: OMB-01 Findings Survey area OMB-01 is a structure that is bounded by OOL,03 a Class 3 land survey area.
Survey area OMB-01 is minimally impacted by plant operations and is not likely to' contain residual radioactivity at levels greater than a small fraction of the DCGL.
If residual radioactivity is present, the radionuclide mix for the OMB-O1 includes all radionuclides identified as present in the radioactive systems of the plant (Ref 3). The primary radionuclides of concern for OMB-Ol are Co-60, Cs-137, Ag-108m, Sr-90, and tritium.
Current Status OMB-01 currently houses portions of the auxiliary, service water system and the electrically driven fire protection pumps'both of which are still in service. The 'discharge line of the ASWS is the monitored release pathway for radioactive liquid releases. No sampling was conducted in this area.
Classification Statement Based upon the historical use and radiological conditions associated with this survey area OMB-01 is identified as a Class 3 Area.
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a-Building Historical Site Assessment and Classification Summary Survey Area Name: Screenwell and Pump House Designator: OMB-01 Drawings 9699-FA- 13A 9699-FC-5 lA 9699-FC-51B 9699-FC-51 C 9699-FC-52A 9699-FC-52B 9699-FC-52C 9699-FC-52D 9699-FC-52E 9699-FC-52F 9699-FC-52G References
- 1. Engineering Design Change Request (EDCR)95-301, "Installation of Consolidated Spent Fuel Pool Cooling System," dated April 25, 1995.
- 2. "Radionuclides for Building Surfaces and Soil DCGL Determinations,"
YA-REPT-00-001-03 Page 4 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Security Gatehouse & Diesel Generator - Designator: OMB-02 Survey Area Description -
Based upon the projected end-state of decommissioning activities, Survey Area OMB-02 consists of the reinforced concrete and concrete block walls, reinforced concrete floors and foundations of the Security Diesel Building, Security Gatehouse and Control Room Complex. - I The footprint of OMB-02 is approximately 270 square meters.
Survey area OMB-02 is bounded by survey area OOL-02 and OOL-06, both of which are Class 3 land survey areas.
The west storm sewer system runs under the Security Gatehouse.
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X-Building Historical Site Assessment and Classification Summary Survey Area Name: Security Gatehouse & Diesel Generator Designator: OMB-02 Survey Area History The Security Gatehouse is an original- plant structure, which has been modified numerous times over the life of the plant. These modifications include additions that have expanded the footprint of the structure and reconfiguration of the internal arrangement of the .
original structure (Ref 1, Ref 2). The latest modifications being the control room addition and recent changes implemented to address heightened security concerns (Ref 3).
The security diesel generator building was constructed as part of and to support the site security upgrades'performed in the late 1970s that included replacement of the security boundary fence, installation of security cameras and improved site illumination. An addition attached to the security diesel building was constructed to house an uninterruptible power supply (UPS) to support the security system. This UPS was removed from service and the building now contains the diesel fuel storage tanks that supply the security diesel generator.
Survey Area OMB-02 did not contain radioactive systems, was not used to store radioactive materials or package radioactive waste. Radioactive materials in small packages ready for shipment may have been transported through OMB-02. Use of radioactive material in this area was limited to sealed check sources used for instrumentation operational checks.
The west storm sewer that runs under the security gatehouse portion of OMB-02 is known to have been contaminated (Ref 4) and will require further investigation.
Radiological assessments were performed on a routine basis in OMB-02. Radioactive contamination resulted from migration of contamination out of the RCA, when identified it was immediately cleaned-up.
Scoping/Characterization A pre-demolition survey developed in accordance with AP-0831 Administrative Program for Radiological and Non-Radiological Characterization Surveys is implemented prior to commencing demolition activities. The results of this survey will identify radiological contamination present within the bounds of OMB-02. This survey also serves as the material survey for release in accordance with AP-0052 Radiation Protection Release of Equipment, Materials and Vehicles, if appropriate, for the OMB-02 demolition materials DecommissioningActivities No decommissioning activities have been performed in OMB-02 Page 2 of 4
Building'Historical Site Assessment and Classification Summary Survey Area Name: Security Gatehouse & Diesel Generator Designator: OMB-02 Findings Survey area OMB-02 is a structure that is bounded by OOL-02 and OOL-06 Class 3 land survey areas.
Survey area OMB-02 was minimally impacted by plant operations and is not likely to contain residual radioactivity at levels'greater than a small fraction of the DCGL.
If residual radioactivity is present, the radionuclide mix for the OMB-02 includes all radionuclides identified as present in the radioactive systems of the plant (Ref 5). The primary radionuclides of concern for OMB-02 are Co-60, Cs- 137, Ag- 108m, Sr-90, and tritium.
CurrentStatus All structures that make up OMB-02 are still in service and will remain so. No sampling was conducted in this area.
ClassificationStatement Based upon the historical use and radiological conditions associated with this survey area OMB-02 is identified as a Class 3 Area.
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l-Building Historical Site Assessment and Classification Summary Survey Area Name: Security Gatehouse & Diesel Generator Designator: OMB-02
.. )
Drawings 9699-FA- 14A References
- 1. Plant Modification 75-46, "Gate House Addition," dated January 26, 1976.
- 3. Plant Design Change Request (PDCR) 91-06, "Gatehouse Access Modification,"
dated October 23, 1991.
- 4. Abnormal Occurrence Report (AOR) 66-08, "Abnormal Activity in Storm Drains,"
___ dated December 27, 1966.
- 5. "Radionuclides for Building Surfaces and Soil DCGL Determinations,"
YA-REPT-00-001-03
' /)
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Building Historical Site Assessment and Classification Summary Survey Area Name: Training Center Designator: OMB-03 Survey Area Description Survey Area OMB-03 consists of a metal frame and panel structure set on a reinforced concrete slab and foundations.,
The footprint of OMB-03 is approximately 890 square meters.
Survey area OMB-03 is bounded by OOL-06, a Class 3 kand survey area.
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a-Building Historical Site Assessment and Classification Summary Surve y Area Name: Training Center Designator: OMB-03 Survey Area History The OMB-03 structure has been subject to a variety of uses. Originally it functioned as a training center for plant personnel prior to start-up. For a time it served as the visitor and information center. It was later converted to office space to support the training organization. Today the OMB-03 structure functions as the YNPS Administration Office Building.
Radiological assessments performed in OMB-03 did not indicate the present of plant related radioactivity.
Draft NUREG/CR-5849 based survey was performed in OMB-03, the results of which may be qualified as characterization data, if appropriate, at the time of FSS (Ref 1).
Scoping/Characterization A pre-demolition survey developed in accordance with AP-0831 Administrative Program for Radiological and Non-Radiological Characterization Surveys is implemented prior to commencing demolition activities in OMB-03. The results of this survey will identify radiological contamination present within the bounds of OMB-03. This survey also serves as the material survey for release in accordance with AP-0052 Radiation Protection Release of Equipment, Materials and Vehicles, if appropriate, for the OMB-03 demolition materials DecommissioningActivities No decommissioning activities have been performed in OMB-03.
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Building Historical Site Assessment and Classification Summary Survey Area Name: Training Center Designator: OMB-03 Findings Survey area OMB-03 is a structure that is bounded by OOL-06, a Class 3 land survey area.
Survey area OMB-03 was minimally impacted by plant operations and is not likely to contain residual radioactivity at levels greater than a small fraction of the DCGL.
If present, the radionuclide mix for the OMB-03 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref 2). The primary-radionuclides of concerndfor OMB-03 are Co-60, Cs-137, Sr-90, and tritium.
CurrentStatus OMB-03 currently houses the administration offices for the YNPS site and will remain occupied for some period of time.
ClassificationStatement Based upon the historical use and radiological conditions associated with this survey area OMB-03 is identified as a Class 3 Area.
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Building Historical Site Assessment and Classification Summary Survey Area Name: Training Center Designator: OMB-03 Drawings No Plant Drawings Available FSS Map OB002A References
- 1. I "Radionuclides for Building Surfaces and Soil DCGL Determinations,"
I . YA-REPT-00-001-03 - I Page 4 of 4
Building Historical Site Assessment and Classification' Summary Survey Area Name: Warehouse and Loading Dock' Designator: OMB-04 Survey Area Description Survey Area OMB-04 consists of a concrete 'slab and foundations-and'the plant warehouse and loading dock structure.
The footprint of OMB-04 is approximately 625 square meters.
Survey area OMB-04 is bounded by survey area OOL-02, a Class 3 land survey area on'the north and east, OOL-12, a Class 1 land survey area on the south, SVC-02, a Class 2 structure survey area on the west and SVC-03, a Class 3 survey area also on the 'west.
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a Building Historical Site Assessment and Classification Summary Survey Area Name: Warehouse and Loading Dock Designator: OMB-04 Survey Area History The warehouse and loading dock are an original plant structure, which has been modified over the life of the plant. These modifications include additions that have expanded the footprint of the structure and reconfigured the internal arrangement of the original structure (Ref 1). A modification of particular interest was the raising of the height of the loading dock, which also resulted in application of two inches of concrete over the original concrete floor of the warehouse structure (Ref 2).
The most recent modification to OMB-04 was the installation of the auxiliary service water pipe under the west end of the warehouse floor slab (Ref 3). Soil samples collected along the line of excavation indicated no detectable plant related radioactivity.
Survey Area OMB-04 did not contain radioactive systems, was not used to store radioactive materials or to package radioactive waste. Radioactive materials package shipments may have been transported through OMB-04. Radioactive material packages were brought into the RCA prior to opening.
Radiological assessments were performed on a routine basis in OMB-04. Radioactive contamination of OMB-04 did occur, likely resulting from migration of contamination out of the RCA, when identified this contamination was immediately cleaned-up.
Scoping/Characterization A pre-demolition survey developed in accordance with AP-083 1 Administrative Program for Radiological and Non-Radiological Characterization Surveys was implemented prior to commencing demolition activities in OMB-04. The results of this survey identified no residual radiological contamination present within the bounds of OMB-04. This survey also serves as the material survey for release in accordance with AP-0052 Radiation Protection Release of Equipment, Materials and Vehicles, for the OMB-04 demolition materials DecommissioningActivities Decommissioning Activities performed DEM-TP-001 and 002 have removed the structure that was the original warehouse and the addition that connected the warehouse to the garage structure of OMB-04.
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Building Historical Site Assessment and Classification Summary Survey Area Name: Warehouse and Loading Dock ' 'Designator: OMB-04 Findings Survey area OMB-04 is bounded by survey area OOL-02, a Class 3 land survey area on the north and east, OOL-12, a Class 1 land survey area on the south, SVC-02, a Class 2 structure survey area on the west and SVC-03, a Class 3 survey area also on the west. Although OOL-12 is a Class 1 land survey area it is located down slope from OMB-04 making it unlikely that contamination would migrate 'into OMB-04. The radioactivity in OOL- 12 is embedded within the ties and ballast beneath the rail-bed that has been paved over. This embedded radioactivity is not likely to be trans-located to OMB-04.
Survey area OMB-04 was minimally impacted by plant operations and is not likely t6 contain residual radioactivity at levels greater than'a'small fraction of the DCGL.
If residual radioactivity is present, the radionuclide mix for the OMB-04 includes 'all radionuclides,-
identified as present in the radioactive systems of the plant (Ref 4). The primary radionuclides of concern for OMB-04 are Co-60, Cs-137, Ag-108m, Sr-90, and tritium.
Current Status Decommissioning activities have removed the warehouse structure down to the top of the second layer of concrete floor. Additional investigation will be necessary to evaluate the original warehouse floor surface. No sampling was conducted in this area.
Classification Statement Based upon the historical use and radiological conditions associated with this survey area OMB-04 is identified as a Class 3 Area.
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Building Historical Site Assessment and Classification Summary Survey Area Name: Warehouse and Loading Dock Designator: OMB-04 Drawings PDCR 86-009 Attachment Al-A13 References
- 2. Plant Design Change Request (PDCR)86-009, "Level 'B' Storage, Stores Warehouse," dated October 6, 1986.
- 3. Engineering Design Change Request (EDCR)95-301, "Installation of Consolidated Spent Fuel Pool Cooling System," dated April 25, 1995.
- 4. "Radionuclides for Building Surfaces and Soil DCGL Determinations,"
YA-REPT-00-001-03 Page 4 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Furlon a.k.a. Yankee House Designator: OMB-05 Survey Area Description Survey Area OMB-05 consists of a wood frame structure set on a foundation that is part reinforced concrete and part mortared rock. .
The footprint of OMB-05 is approximately 432 square meters.
OMB-05 is bounded on all sides by OOL-16, a Class 3 land survey area.
Pagel1 of 4
a-Building Historical Site Assessment and Classification Summary Survey Area Name: Furlon a.k.a. Yankee House Designator: OMB-05 Survey Area History The OMB-05 structure was, prior to purchase by YAEC, a private residence. It was purchased prior to construction of the YNPS facility. It has been subject to a variety of uses including storage of environmental sampling equipment and samples. It has been used to support emergency plan activities, which included storage of protective clothing, respirators, radiological survey and counting equipment. Although some of this emergency equipment had fixed contamination present, all contaminated equipment was stored in sealed storage containers.
Currently the OMB-05 functions as a visitor information center, office space and was established as the shipping and receiving point of contact for YNPS in response to heightened security concerns.
Radioactive material packages received at the YNPS site are brought into the YNPS RCA prior to opening they are not opened in OMB-05. Radioactive material shipments are package at the YNPS site and do not pass through OMB-05.
Radiological assessments were performed on a routine basis in OMB-05. No documentation of contamination within survey area OMB-05 was identified in YNPS historical documents reviewed.
Draft NUREG/CR-5849 based survey was performed in OMB-05 the results indicate no plant related residual radioactivity identified.
Scoping/Characterization Previously performed Draft NUREG/CR-5849 based surveys may subsequently be qualified as characterization surveys for OMB-05 as appropriate.
DecommissioningActivities No decommissioning activities are planned for OMB-05 Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Furlon a.k.a. Yankee House;' Designator: OMB-05 Findings Survey'area OMB-05 is a structure that is'bounded on all sides by 00- 16,'a Class 3 land survey area.
Survey area OMB-05 was minimally impacted by plant operations and is not likely to contain residual radioactivity at levels greater than a small fraction of the DCGL.
If present, the radionuclide mix for the OMB-05 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref 1). The primary radionuclides of concern for OMB-05 are Co-60, Cs-137,-Ag-108m and Sr-90.
CurrentStatus OMB-05 currently functions as the visitor information center, offices for YNPS staff and the shipping and receiving point of contact for the YNPS site. It is expected to remain occupied for some period of time.
ClassificationStatement Based upon the historical use and radiological conditions associated with this survey area OMB-05 is identified as a Class 3 Area.
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Building Historical Site Assessment and Classification Summary Survey Area Name: Furlon a.k.a. Yankee House Designator: OMB-05 Drawingsand References Due to the age of the structure and the fact that it was not constructed as part of the YNPS facility no drawings of the Furlon/Yankee House are available.
FSS OB003 A,B,C,D References
- 1. "Radionuclides for Building Surfaces and Soil DCGL Determinations,"
YA-REPT-00-001-03 l Page 4 of 4
Building'Historical Site Assessment and Classification Summary Survey Area Name: Seal Pit Designator: OMB-06 Survey Area Description Survey Area OMB-06 consists of the reinforced concrete structure located at the discharge'end of the circulating water system.
The footprint of OMB-06 is approximately 282 square meters.
Survey area OMB-06 is bounded by survey area OOL-01, a Class 3land survey area on the north and OOL-3, a Class 3 land survey area on east, south and west.
... .. I I..
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Building Historical Site Assessment and Classification Summary Survey Area Name: Seal Pit Designator: OMB-06 Survey Area History Survey Area OMB-06 is located outside of the security fence at the edge of Sherman Reservoir a short distance west ofthe Screenwell Pump House. OMB-06 received the discharge of the circulating water system. The circulating water system received the discharge of the service water system, which was a portion of monitored discharge pathway for radioactive liquid releases. The service water and circulating water systems were taken out of service after the ASWS installation was complete (Ref 1).
Consequently releases via this pathway were discontinued.
The ASWS discharge into the Seal Pit is currently the monitored discharge pathway for radioactive liquid releases Scoping/Characterization Radiological assessment of OMB-06 consists of a sediment sample collected from within the Seal Pit structure. Pipe scale and sediment samples were also collected from the circulating water system up-stream of the Seal Pit. The sediment sample from the Seal Pit and the pipe scale and sediment samples from the circulating water system piping identified low levels of residual radioactivity present.
DecommissioningActivities Decommissioning activities performed in OMB-06 installed the Auxiliary Service Water System (ASWS) the discharge. The ASWS is the current discharge pathway for monitored radioactive liquid releases.
The projected end state of OMB-06 in removal of the entire structure. A pre-demolition survey developed in accordance with AP-083 1 Administrative Program for Radiological and Non-Radiological Characterization Surveys is implemented prior to commencing demolition activities. The results of this survey will identify radiological contamination present within the bounds of OMB-06 and guide the demolition activities performed This survey also serves as the material survey for release in accordance with AP-0052 Radiation Protection Release of Equipment, Materials and Vehicles, if appropriate, for the OMB-06 demolition materials.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Aiea Name: Seal Pit Designator: OMB-06 Findings Survey area OMB-06 is bounded by survey area OOL-01, a Class 3 land survey area on the north and OOL-3, a Class 3 land survey area on east, south and west.
Survey area OMB-06 was impacted by the release of low levels of radioactivity through the ASWS monitored release pathway and the former service water system to circulating water system monitored release pathway. Survey area OMB-06 is likely to contain residual radioactivity at levels less the DCGL.
If residual radioactivity is'present, the radionuclide mix for the OMB-06 includes all radionuclides identified as present in the radioactive 'systems of the plant (Ref 2).r The primary radionuclides of concern to for OMB-06 include Co-60, Cs-137, Ag-108m, Sr-90 and tritium.
Current Status The ASWS is the monitored discharge pathway for release of liquid radioactivity and remains in service.
A soil sample location map (Figure 44) has been prepared to show the distribution of sampling locations in OMB-06. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented).
One survey media was assessed in OMB-06, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for OMB-06 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.642.
Maximum SOF for a single soil sample is 0.642. (key# 3122)
Minimum SOF for a single soil sample is 0.642. (key# 3122)
Classification Statement Based upon the historical use and radiological conditions associated with this survey area OMB-06 is identified as a Class 3 Area.
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- -- ~3-Building Historical Site Assessment and Classification Summary Survey Area Name: Seal Pit Designator: OMB-06 Drawings 9699-FC-53A 9699-FC-54A 9699-FC-54B 9699-FP- 12A References 1I Engineering Design Change Request (EDCR)95-301, "Installationof Consolidated Spent Fuel Pool Cooling System," dated April 25, 1995.
- 2. "Radionuclides for. Building Surfaces and Soil DCGL Determinations,"
YA-REPT-00-001-03 Page4of4
Page I Of I Table I Sum of Fractions OIB-06 -- Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 3122 SPOO1.1 SPOO1.1 0.642 Min 0.642 Max 0.642 Mean 0.642
Table 2 Page Ilo1 Statistical Data Summary - OMB-06 -Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Aledian Results Ac-228 pCi/g 1 1 2.563 2.563 2.563 2.563 Ag-108m pCi/g I 1 0.082 0.082 0.082 0.082 Ag-lOrm pCi/g 0 1 0.000 Am-241 pCi/g 0 1 0.000 Bi-212 pCi/g I 1 1.767 1.767 1.767 1.767 Bi-214 pCi/g I 1 0.634 0.634 0.634 0.634 Cc- 144 pCi/g 0 1 0.000 Co-58 pCi/g 0 1 0.000 Co-60 pCi/g I 1 2.958 2.958 2.958 2.958 Cs-134 pCi/g 0 1 0.000 Cs-137 pCi/g I 1 0.253 0.253 0.253 0.253 Fe-59 pCi/g 1 1 0.159 0.159 0.159 0.159 K-40 pCi/g I 1 1.566 1.566 1.566 1.566 Mn-54 pCi/g 0 1 0.000 Nb-95 pCi/g 0 1 0.000 Pb-212 pCi/g I 1 3.045 3.045 3.045 3.045 Pb-214 pCi/g I 1 0.784 0.784 0.784 0.784 Ra-226 pCi/g I 1 5.430 5.430 5.430 5.430 Ru-103 pCi/g 0 1 0.000 Ru- 106 pCi/g 0 1 0.000 Sb-124 pCi/g 0 1 0.000 TI-208 pCi/g I 1 2.611 2.611 2.611 2.611 Zn-65 pCi/g 0 1 0.000 Zr-95 pCi/g 0 1 0.000
( ((
Page I of I Table 3 Summary of Detected Results Above Criteria OMB.06 -- Soil:
Yankee Nuclear Power Station Rowe, MA DCGL_Soil
- Sample Criterion # Detects Above Maximum Parameter # Detects Results Concentration Units Criterion Detected Ac-228 I pCi/g 2.56 Ag-108m I U 8.52 pCi/g 0.08 Ag-i l Om I pCilg An-241 I 44.35 pCilg Bi-212 I pCilg 1.77 Bi-214 I pCi/g 0.63 Ce-144 1 pCilg Co-58 1 pCilg Co-60 I. 4.84 pCi/g 2.96 Cs-134 I 6.71 pCi/g Cs-137 I 12.24 pCi/g 0.25 Fe-59 I pCi/g 0.16 K-40 I, pCi/g 1.57 Mn-54 I 21.66 pCi/g Nb-95 1 pCi/g Pb-212 I pCi/g 3.05 Pb-214 1 pCi/g 0.78 Ra-226 I pCi/g 5A3 Ru-103 I pCi/g Ru- 106 I 68.21 pCi/g Sb-124 I pCi/g TI-208 I pCi/g 2.61 Zn-65 I pCi/g Zr-95 I pCi/g
Table 4 Page 1 of I Rad OMB-06 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) SPOO1.1 (3122)
Sample ID SPOO1.1 Date Sampled 9/1/1998 Ac-228 2.563 Ag-108m 0.08218 Ag-110m 0.0133 U Am-241 0U Bi-212 1.767 Bi-214 0.6339 Ce- 144 0.1326 U Co-58 -0.02371 U Co-60 2.958 Cs-134 -0.1582 U Cs-137 0.2525 Fe-59 0.1591 K-40 1.566 Mn-54 0.03527 U Nb-95 -0.0299 U Pb-212 3.045 Pb-214 0.7839 Ra-226 5.43 Ru-103 -0.05034 U Ru-106 -0.07772 U Sb-124 0.02847 U Tl-208 2.611 Zn-65 -0.2856 U Zr-95 0.06911 U SOF 0.642 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Building Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool . Designator: SFP-01 Information current as of October 31, 2003 Survey Area Description Survey Area SFP-O consists of the reinforced concrete floor, foundations and sub-grade structures of the Spent Fuel Pool expected to remain after demolition of the above-grade structure to elevation 1022' is complete. Survey area SFP-01 is located in the RCA and bounded by NOL01 on the north, SFP-02 on the east, NSY-02 on the south and NOL-01 and NSY-09 on the west. The footprint of SFP-01 'contains approximately 60 square meters.
Survey area SFP-01 includes the floor areas of varying elevations. (See referenced drawings). The operating floor area of SFP-01 consists of the floor area at elevation 1045' and the bottom of the SFP at elevation 1008'. The fuel transfer carriage follower ;'
pit extends down below elevation 1003'. The west exterior of the SFP includes the location of the spent fuel transfer chute and lower lock valve structure. The total surface area in square meters for SFP-01 may not be determined until demolition activities are complete. Survey Area SFP-01 will be divided into survey units as necessary.-'
The Spent Fuel Transfer Pit (SFP) was designed for the transfer of new fuel into the reactor and spent fuel out of the reactor. The spent fuel was then to remain in temporarily storage under water in the spent fuel pit. Routine shipments of fuel were intended to allow the SFP to be drained and decontaminated between re-fueling. In addition to spent fuel, the SFP was also used to store irradiated components such as control rods, shim rods and source vanes. The SFP annex was the location of the YNPS Special Nuclear Material storage area that was used to store sealed sources identified as Special Nuclear Material.
The SFP building was connected to the plant ventilation system tint discharged to the Primary Vent Stack. A negative pressure gradient relative to atmospheric pressure was maintained within the building. The SFP-01 room air was drawn from inlets on the north side of the building toward the south side where the exhaust passed through the charcoal and HEPA filter banks in the AUX-01 fan room to the Primary Vent Stack (PVS) monitored discharge.
The operating floor area around the edge of the SFP was typically controlled as a contaminated area when spent fuel was stored in the SFP.- The operating floor had a floor drain that ran to the gravity drain tank in AUX-0I for collection of radioactive liquids.
The soils present around and under the .SFP structure'include back fill;'overburden and lodgment till. The iodgment till is'relatively impermeable to groundwater flow. The overburden is more permeable. The backfill is the'most permeable media and i ;
consequently areas containing backfill are the likely pathways for subsurface migration of radioactivity. Backfill is present at the perimeter of the subsurface structures including the deepest portion of the SFP.
Page 1 of 8
Building Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool Designator: SFP-01 Information currentas of October 31, 2003 Survey Area History In November of 1961 a coating of phenolic resin was applied to the surface of the SFP in preparation for the first refueling outage. Operations Report #11 (Ref. 1)
A significant operational event that led to the contamination of survey area SFP-01 was AOR 66-07, Spent Fuel Pit Water Spill (Ref 2). About 33'gallons of the spent fuel pit water overflowed the edge of the pit and ran toward the northwest end of the building and!
down the exterior wall to earth. The event occurred as a fuel transfer cask was being removed from the pool which required water to be added to the pool.
In 1967 all of the spent fuel and irradiated components were shipped either for reprocessing or disposal and the spent fuel pit was drained and inspected. The inspection identified blisters in the phenolic coating on the walls of the SFP. Upon further inspection a crack was observed'in the concrete of the SFP. An evaluation of the crack determined it was caused by shrinkage. The phenolic coating was removed from the walls of the SFP using sandblasting and was replaced with an epoxy coating. (Ref 3)
Between uses the spent fuel pool was drained empty and inspected. The last spent fuel shipment was performed in 1971. A spent fuel shipment moratorium was instituted at that time.
In 1977 the plant experienced the first fuel cladding failures and fission products became a part of the radionuclide mixture in the SFP.
Between 1978 and 1980 EDCR 78-12 (Ref. 4) installed a stainless steel liner into the SFP, which facilitated the double stacking of spent fuel racks. The liner was installed in two sections with a temporary cofferdam used to facilitate the installation. The SFP Building annex was also constructed under EDCR 78-12. The annex is located on top of what was the roof of the New Fuel Storage Vault.
In 1992 all of the fuel was removed from the reactor and placed into storage in the SFP.
During the Control Rod disposal process, an abrasive saw and shear cutter were employed to cut the control elements into manageable sized pieces. As a result, Ag-108m was deposited among the other radionuclides in the Spent Fuel Pit. Ag- 108m has since been identified on a swipe taken from the surface of the SFP Liner.
In August of 2003 the transfer of all fuel to dry cask storage on the ISFSI pad was completed. In September of 2003, the bottom of the SFP was vacuumed and an underwater hydro- laser was applied for decontamination. In October of 2003 the final drain-down of the SFP was completed.
Page 2 of 8
Building Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool - Designator: SFP-01 TranslocationPathways During fuel transfer the water in the spent fuel pool would mix with the water in the shield tank cavity in the VC. The mixing of the waters resulted in radioactivity entering the water in the spent fuel pool.
In the colder months, condensation formed on the inside of the roof and un- insulated walls above the concrete portion of the structure due to evaporation from the liquid inventory, which was maintained at a temperature between 75 and 1000 F, and the cooler walls. This condensation would typically drip down the walls and pass onto the exterior concrete walls of the building. This condensation is expected to have contained tritium.
Potential pathways exist for-the liquid inventory to seep out of the pit directly to the exterior of the structure due to historically reported cracks during inspections between re-fueling in the early operational history prior to the lining of the pit. Careful monitoring of make-ups and additions of water to the pit did not identify a, significant leakage concern. (Ref. 5, 6, 7 & 8) This circumstance is on the list of areas targeted for subsurface investigational activities.
PotentialContaminants Contaminants pre~sent in SFP-Ol include all potential contaminants in the radionuclide mix identified in Radionuclides for Building Surfaces and Soil DCGL Determiniations, YA-REPT-' 00-001-03 (Ref. '9). Historical concentrations of key radionjuclides are shown on attached graphics (Ref. 10).
Scoping/CharacterizationSurveys (Historical)
Scoping surveys were performed and the data collected used to develop the YNPS Dec6imnissioning Plan (Ref. 11). Samples of residue on the bottom of the SFP and swipes of spent fuel racks were analyzed under Part 61 protocols for waste stream and site radionuclide mix characteriziation information.
An investigation well was drilled in the northwest corner outside the SFP to evaluate the possibility of radionuclide contamination at depth and of the groundwater surrounding and beneath the structure. Tritium was detected at levels above the MCL for tritium in the groundwater; however, no gamma emitting radionuclides were detected in the water or soil column in this location. An investigational scoping survey consisting of geo-probe borings to a depth near the bottom of the SFP slab is in progress. Preliminary results from the east side borings indicate the presence of Cs-137 above the soil DCGLs but an absence of Ag-108m and Co-60.
Page 3 of 8
Building Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool Designator: SFP-01 DecommissioningActivities Modifications performed to the SFP building since the shutdown of the YNPS and in support of decommissioning activities in other areas of the facility include:
- EDCR 92-303 SFP/Security Modifications
- EDCR 95-302 Installation of Consolidated SFP Cooling System,
- EDCR 95-303 Fuel Transfer Chute Isolation, NNS Mod 95-066 Construction Power Feed Installation SFP
- NNS Mod 96-003 Re-powering Electrical System from 13.8KV Mass Electric Line
- EDCR 96-304 and 304A SFP Building Modifications & Fuel Handing System Equipment Removals
- NNS98-004 SFP/Annex Building Interior Upgrades
- NNS98-004 A SFP/Annex Building Insulation
- NNS Mod 00-001 SFP Filter/Demineralizer Some decommissioning activities have been performed in survey area SFP-01 at the time of this assessment. At the conclusion of material transfer from the Shield Tank Cavity in the Vapor Container, the Fuel chute was isolated and the lower lock valve was encased in concrete. The fuel up-ender and follower carriage have been removed. The Spent Fuel Pit cooling system was removed during DWP-CCWS-01 (Ref. 12). An alternate cooling system was installed as part of the alternate liquid inventory clean-iup system installation.
This heat exchanger is supplied with cooling water by the installation of the Auxiliary Service Water (ASW) system. The ASW draws water from OMB-01 (screenwell house) and discharges to OMB-06 (seal pit).
Additional decommissioning activities to be performed will remove the pit liner and support systems associated with the structure. The lower lock valve and follower chute will be removed at a minimum with possible removal of the entire concrete mass. At a minimum, the above grade portions the structure will be removed.
Page4of8
Building Historical Site Assessment and Classificatio'n'Summary Survey Area Name: Spent Fuel Pool ; .; Designator: SFP-01 Information current as of October 31, 2003 Findings The history of SFP-0 1 indicates that this structure is radiologically impacted as a result of plant operations. The soils under and surrounding the footprint of SFP-O1 were impacted by plant operations.
No remediations have taken place within the footprint of the structure; however, some remediation activity has been conducted in the soils surrounding the structure. The remediations were associated with the installation of a security wall around the base of the above grade structure. The source of this activity is presumed to be related to the significant contaminating event AOR 66-07 described in the history section above. Soils in excess of the soil DCGLs were removed. 7 This remediation activity is documented under the NOL-Ol Survey Area.
The radionuclide mix for survey area AUX-01 includes all radionuclides identified in the radioactive systems of the plant (Ref 9). The primary radionuclides of concern for SFP-01 are Co-60, Cs-137, Ag-108m, Sr-90, and tritium.
ContaminatedMedia These radionuclides are distributed in media inciuding reiniforced concrete, the steel liner, the grout between the liner and the SFP concrete wall, epoxy paint and soils under and surrounding the footprint of SFP-01. The extent of contamination of the exterior surface of the PAB structure below grade and sub-foundation soil will require further investigation.
CurrentStatus Survey Area SFP-Ol is in an early stage of decommissioning with most associated systems still intact. Surface decontamination has been performed on the drained pit liner.
An assessment of core bores taken between the SFP and the IX pit obtained shortly after the pit was drained was conducted for the penetration depth of gamma emitters and tritium into the concrete. Both exterior ends of the cores contained activity; however, the central portion of the cores contained much less tritium and no gamma emitters. The exterior surface of sub-grade structures and foundation will be investigated for possible contamination. Continuing scoping/characterization surveys will be performed in support of further investigations of subsurface radioactivity if required.
Operational radiological surveys in this section represent the drained and decontaminated surface condition of the SFP liner inside the pit prior to removal. (Ref. 13)
Page 5 of 8
Building Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool Designator: SFP-01 Spent Fuel Pit Dose Rate & ContaminationSumnntary Operating Floor (as of 9/18/03):
Large Area Wipes - 300 ccpm to 6000 ccpm Smears - <50 dpm/100 enr? a
<1000 dpm/100 c to 18K dpm/100 cnH ,-y Dose Rates - <0.2 mr/hr to 16 mr/hr Pit:
Floor Contact Dose Rates (as of 9/15/03)
North 25% - 86 mr/hr to 6500 mr/hr Next 25%- 70 mr/hr to 3900 mr/hr Next 25% - 41 mr/hr to 10,000 mr/hr South 25% - 29 mr/hr to 171 mr/hr Floor Knee/Head Level (as of 9/23/03)
Northern third -' 200/100 mr/hr to 500/200 mr/hr Middle third - 40/42 mr/hr to 800/200 mr/hr Southern third - 12/18 mr/hr to 32/32 mr/hr Floor and Walls @1' North half - 75 mr/hr to 600 mr/hr y 0 mrad/hr to 500 mrad/hr J3 South half - 5 mr/hr to 30 mr/hr y 0 mrad/hr to 25 mrad/hr ,B Page 6 of 8
Building Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool Designator: SFP-O1 Information currentas of October 31, 2003 ClassificationStatement Based upon the radiological conditions identified in the operating history and as a result of the decommissioning activities performed to date, survey area SFP-O1 is identified as a Class 1 Survey Area.
Non-RadiologicalConcerns PCB Paint application.
Page 7 of 8
Historical Site Assessment and Classification Summary Survey Area Name: Spent Fuel Pool Designator: SFP-01 Drawings 9699-FA- 15A 9699-FA- 18A 9699-FC-45B 9699-FC-45C 9699-FC-45D 9699-FC-45E 9699-FC-45F 9699-FM-21A References
- 1. OPs Report #11 for the Month of November 1961, dated December 15, 1961.
- 2. Abnormal Occurrence Report (AOR) 66-07, "Spent Fuel Pit Water Spill," dated September 27, 1966.
- 3. Operations Report # 84 for the Month of December 1967, dated January 22, 1968.
- 4. OPs Report #85 for the Month of January 1968, dated February 26, 1968.
- 5. Engineering Design Change Request (EDCR) 78-12, "1978-1980 Spent Fuel Pit Liner Installation>" dated 1978.
- 6. Calculation YRC- 1060, Spent Fuel Pit Evaporation Rates, July 1994
- 7. OP 2189 - SFP Make-up Logsheets
- 8. CHM 01-012 "Spent Fuel Pit Wall Inspection and Calculated Through Wall Leakage," October 2001.
- 9. MRT Review Team, "Two Year Review of Spent Fuel Pool Make-ups," dated April 5, 2001.
- 10. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT- 00-001-03.
- 11. Annual Spent Fuel Chemistry Data Evaluations 1996, 1997-1999, 2000
- 12. Yankee Nuclear Power Station, Decommissioning Plan, Rev. 0.0, Section 3.
- 13. Operational Surveys September 2003 (see attachment to summary)
- 14. DWP-CCWS-01, "Component Cooling, Fuel Pit Cooling and Service Water (Primary Plant) Systems," dated September 5, 1995.
Page 8 of 8
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Building Historical Site Assessment and Classification Summary Survey Area Name: New Fuel Storage Vault Designator: SFP-02 Survey Area Description Survey Area SFP-02 consists of the reinforced concrete floor slab and subsurface structures remaining after the demolition of the New Fuel Storage Vault is complete. The footprint of survey area SFP-02 is approximately 95 square meters of concrete surface area. There are additional subsurface structures within the footprint of the SFP-02 that include grade beams, foundation and column supports. (See drawings for details)
SFP-02 is bounded on the north by NOL-01, on the east by NOL-Ol, on the south by NOL-02 and NSY-02 and on the west by SFP-01.
Page 1 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: New Fuel Storage Vault Designator: SFP-02 Survey Area History K-)
Survey area SFP-02 was used for the receipt and opening of new fuel transport containers. After opening the containers the new fuel assemblies were inspected and placed into the storage racks until transferred to the reactor. There is no documentation indicating contamination of SFP-02 resulting from handling and inspection of new fuel received at YNPS.
SFP-02 was also used as a radioactive material storage area for storage of operations department equipment. Survey area SFP-02 was generally maintained as a non-contaminated area. The contaminating events were associated with the handling and storage of contaminated operation's equipment. When contamination was identified the area was decontaminated.
After permanent shutdown of the YNPS the NFSV was used as a radioactive material storage area for components used during the reactor internal segmentation project that resulted in contamination of this area with the radionuclide mix resulting from that project. This material was later removed and dispositioned and the area was decontaminated Post shutdown modification to survey area SFP-02 include:
- NNS Mod 95-066 Construction Power Feed Installation SFP
- NNS Mod 96-003 Re-powering Electrical System from 13.8KV Mass Electric Line Survey area SFP-02 is the present location of the YNPS Special Nuclear Material storage area that contained sealed sources identified as Special Nuclear Material.
Scoping/Characterization Scoping surveys were performed and the data collected used to develop the YNPS Decommissioning Plan. (Ref 1)
DecommissioningActivities No decommissioning activities have been performed in survey area SFP-02.
Page 2 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: New Fuel Storage Vault Designator: SFP-02 Findings Survey area SFP-02 was impacted by plant operations and is likely to contain residual radioactivity at levels greater than the DCGL.
The radionuclide mix for the SFP-02 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref 2). The HSA for SFP-02 identifies the primary radionuclides of concern to be Co-60, Cs- 137, Ag- 108m, Sr-90, and tritium.
CurrentStatus SFP-02 currently houses the electrical systems and other support systems associated with the SFP.
The YNPS special Nuclear Material storage location remains in survey area SFP-02.
A soil sample location map (Figure 46) has been prepared to show the distribution of sampling locations in SFP-02. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented). One survey media were assessed in SFP-02, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for SFP-02 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.011.
Maximum SOF for a single soil sample is 0.030. (key# 3020)
Minimum SOF for a single soil sample is 0.004. (key# 3022)
SFP-02 continues to be impacted by decommissioning activities.
An investigation is underway as of November of 2003 to sample deep soils beneath SFP-02. The source of the potential activity in these deep soils is associated with potential leakage from SFP-01 and residue from the NSY-02 (IX-Pit) leakage in the 1960's. A sample location below SFP-02 has turned up Cesium-137 in concentrations greater than the DCGL. The sub-surface investigation is continuing.
Page 3 of 5
a-Building Historical Site Assessment and Classification Summary Survey Area Name: New Fuel Storage Vault Designator: SFP-02 Classification Statement Based upon the historical use and radiological conditions associated with this survey area SFP-02 is identified as a Class I Area.
Page 4 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: New Fuel Storage Vault Designator: SFP-02 Drawings 9699-FA- 15A 9699-FA-18A 9699-FC-45B 9699-FM-18A 9699-FM-21A References
- 1. YNPS Decommissioning Plan, Rev. 0.0.
- 2. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT- 00-001-03.
Page 5 of 5
3-Pagelof I Table I Sum of Fractions SFP-02 -- Soil Yankee Nuclear Power Station Rowe, MNIA J Station Key Station Sample ID Sum Of Fractions 3022 NFV001.3 NFV001.3C 0.004 3021 NFV001.2 NFV001.2B 0.005 3021 NFV001.2 NFV00l.2A 0.005 3020 NFVOOI.1 NFVOOI.IE 0.030 Min 0.004 Max 0.030 Alean 0.011
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Table 2 Page I of 1 Statistical Data Summary - SFP-02 -Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 PCilg 20 20 0.935 0.118 0.747 1.212 0.908 Ag-108m pCilg 2 20 0.146 0.160 0.032 0.259 0.146 Ag-I l Om 2 20 0.051 0.019 0.038 0.064 0.051 An-241 0 20 0.000 Bi-212 pCilg 19 19 0.905 0.253 0.547 1.372 0.879 Bi-214 20 20 0.462 0.047 0.367 0.534 . 0.459 Ce- 144 2 20 0.238 0.006 0.234 0.243 0.238 Co-58 pCi/g 2 20 0.033 0.004 0.031 0.036 0.033 Co-60 pCilg 0 20 0.000 Cs-134 pCi/g 0 20 0.000 Cs-137 pCilg 20 0.046 0.046 0.046 0.046 Eu- 152 pCi/g I 0.060 - 0.060 0.060 ; 0.060 Fe-59 pCilg 0 20 0.000 . . .
1-132 pCilg 0 I 0.000 K-40 PCi/g 20 20 16.885 1.265 14.870 19.110 16.660 Mn-54 pCilg 20 0.021 0.021 0.021 0.021 Mo-99 pCilg 0 I 0.000 Nb-94 0 2 0.000 Nb-95 pCilg 0 20 0.000 Np-239 pCi/g 1 3 5.204 5.204 5.204 5.204 Pb-212 pCi/g 20 20 ,- 0.891 0.115 0.740 1.238 0.890 Pb-214 pCi/g 20 20 0.503 0.056 0.401 0.608 0.504 Ra-226 pCilg 15 17 1.333 0.306 0.982 2.055 1.242 1
Ru-1 03 pCi/g 0 20 0.000 Ru-106 pCilg 0 20 0.000 Sb-124 pCilg 0 20 0.000 Sb-125 pCi/g 0 I 0.000 Tl-208 pCi/g 20 20 0.807 0.135 0.624 1.187 0.778 Zn-65 pCi/g 0 20 0.000 Zr-95 20 0.068 0.068 0.068 0.068
a-Page I of I Table 3 Summary of Detected Results Above Criteria SFP-02 -- Soil Yankee Nuclear Power Station Rowe, MIA -
DCGL_Soil
- Sample Criterion # Detects Above Maximum Parameter # Detects Results Concentration Units Criterion Detected Ac-228 20 20 pCilg 1.21 Ag-108m 2 20 8.52 pCilg 0.26 Ag- lOnm 2 20 pCilg 0.06 Am-241 0 20 44.35 pCilg Bi-212 19 19 pCilg 1.37 Bi-214 20 20 pCi/g 0.53 Ce- 144 2 20 pCi/g 0.24 Co-58 2 20 pCi/g 0.04 Co-60 0 20 4.84 Cs-134 0 20 6.71 Cs-137 I 20 12.24 pCi/g 0.05 Eu- 152 1 I 12.06 pCi/g 0.06 Fe-59 0 20 pCi/g 1-132 0 1 pCi/g K-40 20 20 pCi/g 19.11 Mn-54 I 20 21.66 pCi/g 0.02 Mo-99 0 I pCilg Nb-94 0 2 8.53 pCilg Nb-95 0 20 pCilg Np-239 1 3 pCilg 5.20 Pb-212 20 20 pCilg 1.24 Pb-214 20 20 pCi/g 0.61 Ra-226 15 17 pCilg 2.06 Ru- 103 0 20 pCi/g Ru- 106 0 20 68.21 pCilg Sb-124 0 20 pCilg Sb-125 0 1 37.73 PCi/g TI-208 20 20 pCi/g 1.19 Zn-65 0 20 pCi/g Zr-95 1* 20 pCi/g 0.07
Table 4 Page 1 of 4 Rad SFP-02 - Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) NFV001.1 (3020) NFVOO1.I (3020) NFVOO1.1 (3020) NFVOO1.1 (3020) NFV001.1 (3020)
Sample ID NFV001.1A -' NFVI001.B NFVOO.IC' NFVOO1.1D - NFVOO1.IE Date Sampled' 7/22/1998 7/22/1998 7/22/1998; Ac-228 1.212 0.968 0.7528 1.027 0.7466 Ag-108m : 0.002654 U -0.01661 U -0.009043 U 0.02637 U 0.259 Ag-110m 0.03802 0.02787 U 0.02987 U 0.006186 U -0.007354 U -
Am-241 OU 0U 0U 0U 0U Bi-212 0.755 0.6259 1.054 0.5474 0.5837 Bi-214 0.428 0.5198 0.4417 0.4622 0.4027 Ce-144 . -0.0459 U -0.1585 U 0.0906 U 0.1374 U 0.2092 U Co-58 -0.0168 U 0.02478 U 0.006433 U 0.01011 U -0.01891 U Co-60 0.0148 U 0.009515 U 0.03047 U 0.0004506 U 0.009234 U Cs-134 -0.111 U -0.1346U -0.05498 U -0.02748 U' 0.02518 U Cs-137 -0.01575 U -0.01412 U 0.008938 U -0.02173 U -0.0212 U Eu-152 Fe-59 0.005014 U 0.005714 U 0.01084 U -0.03163 U 0.01552 U 1-132 K-40 16.63 : 16 15.97 16.99 16.27 Mn-54 0.01448 U 0.01549 U -0.02827 U 0.01595 U 0.003929 U Mo-99 1.484 U Nb-94 0.02129 U Nb-95 -0.01174 U -0.000672 U 0.01072U 0.01026U -0.02144 U Np-239 5.204 -2.256 U Pb-212 1.238 0.9638 0.7738 0.8152 0.74 Pb-214 0.5431 0.6084 0.4962 0.5094 0.4245 Ra-226 1.077 1.242 1.258 Ru-103 0.006771 U -- 0.006238 U -0.01 193 U -0.006311 U - -0.02224 U Ru-106 -0.155 U -0.05913 U -0.03114 U -0.05643 U -0.0283 U Sb-124 0.01663 U - 0.002232 U -0.02329 U 0.007552 U -0.009586 U Sb-125 TI-208 1.187 0.8056 0.7988 0.8253 0.6237 Zn-65 0.017 U -0.04908 U -0.05776 U -0.01372 U 0.04671 U Zr-95 0.00815 U 0.0342 U -0.008111 U -0.02761 U -0.003864 U SOF ; 0.03 U-not detected (value is not greater than 2 sigma); UM-nondetect (value'is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate'chemical not analyzed'
Table 4 Page 2 of 4 Rad SFP-02 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) NFV001.2 (3021). NFVOO1.2 (3021) NFV001.2 (3021) NFV001.2 (3021) NFVOO1.2 (3021)
Sample ID NFVOOI.2A NFV001.2B NFV001.2C NFVOO1.2D NFV001.2E Date Sampled 7/23/1998 - 7/23/1998 7/23/1998 7/23/1998 7/28/1998 Ac-228 0.9231 0.8809 0.8667 0.8893 0.8604 Ag-108m 0.03246 0.003314 U -0.01624 U -0.0007483 U 0.004133 U Ag-110m -0.01232 U 0.02663 U 0.02522 U -0.001073 U 0.02669 U Am-241 0U 0U 0U 0U, OU Bi-212 0.6725 0.8605 0.8818 0.683 0.7319 Bi-214 0.4888 0.4151 0.3669 0.509 0.4559 Ce-144 -0.0107 U 0.2425 -0.1507 U 0.2339 0.0007655 U Co-58 0.003237 U 0.03597 -0.01998 U -0.001823 U -0.03732 U Co-60 0.006699 U -0.003825 U -0.00713 U 0.02837 U -0.006479 U Cs-134 -0.0002004 U -0.002962 U -0.0758 U 0.02684 U -0.1613 U Cs-137 -0.00412 U 0.00217 U 0.006216 U 0.01304 U -0.004173 U Eu-152 0.06015 Fe-59 -0.01477 U 0.02837 U 0.01486 U -0.0104 U . -0.01361 U 1-132 K-40 16.41 14.95 16.02 14.87 15.47 Mn-54 0.02115 -0.007577 U -0.001489 U -0.007138 U 0.005299 U Mo-99 Nb-94 Nb-95 -0.01815 U 0.02375 U 0.02325 U 0.01358 U 0.002188 U Np-239 Pb-212 0.899 0.8251 0.8077 0.7665 0.7627 Pb-214 0.517 0.5389 0.5489 0.5066 0.4111 Ra-226 1.851 1.172 1.211 1.393 1.627 Ru-103 0.008648 U 0.001095 U 0.006267 U -0.008999 U 0.01772 U Ru-106 -0.07234 U 0.1452 U -0.05371 U -0.1i72 U -0.06614 U Sb-124 -0.006757 U 0.002716 U -0.007772 U 0.008836 U 0.01449 U Sb-125 Tl-208 0.732 0.6746 0.7045 0.713 0.7426 Zn-65 -0.1672 U -0.03725 U -0.02049 U 0.01574 U 0.04589 U Zr-95 -0.0296 U -0.02529 U 0.02606 U -0.01954 U -0.003557 U SOF 0.005 0.005 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 3 of 4 Rad SFP-02 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) NFV001.3 (3022) NFV001.3 (3022) NFV0O1.3 (3022) NFVOO1.3 (3022) NFV0O1.4 (3023)
Sample ID NFV001.3A - NFV001.3B NFV001.3C NFVOO1.3D : NFV001.4A Date Sampled 7/27/1998 7/27/1998 7/27/1998 7/27/1998 7/27/1998.
Ac-228 1.09 1.065 . 0.9447 ' 0.9525 0.8035 Ag-108m 0.01356 U -0.02142 U -0.01737 U 0.008325 U 0.01486 U Ag-110m 0.02985 U 0.01135 U 0.03482 U 0.01722 U 0.01139 U Am-241 0U 0U 0U 0U 0U Bi-212 0.8787 0.8508 0.8988 1.112 1.166 Bi-214 0.4438 0.513 0.5337 0.4448 0.48 Ce-144 0.1112 U -0.1625 U 0.05423 U -0.0749 U 0.02887 U Co-58 -0.02091 U 0.02726 U -0.006684 U 0.0171 U 0.0305 Co-60 -0.02407 U 0.02159 U 0.0168 U -0.008261 U 0.002908 U Cs-134 0.04254 U -0.04814 U -0.008485 U 0.006389 U -0.117U Cs-137 -0.02951 U -0.02512 U 0.04564 -0.02109 U -0.02506 U :
Eu-152 Fe-59 0.02443 U -0.06202 U -0.01103 U -0.02345 U 0.01694 U 1-132 K-40 19.11 16.69 17.55 19.02 17.47 Mn-54 0.01355 U 0.007159 U -0.007006 U - 0.01584 U 0.005672 U Mo-99 Nb-94 0.03452 U Nb-95 0.03722 U -0.02531 U -0.001621 U 0.00582 U 0.02237 U Np-239 -0.5725 U Pb-212 0.9184 0.928 , 0.9816 0.8885 0.8916 Pb-214 0.5456 0.4754 ' 0.5735 0.4772 0.4493 Ra-226 1.486 1.164 1.059 2.055 1.087 Ru-103 -0.01258 U 0.005501 U -0.003038 U 0.002451 U 0.005307 U Ru-106 -0.08038 U -0.08862 U 0.04082 U -0.1301 U 0.0849 U Sb-124 0.04439 U 0.001124 U 0.005497 U 0.005065 U 0.022 U Sb-125 -0.1026 U Tl-208 0.7576 1.002 0.9024 1.003 0.8467 Zn-65 -0.09857 U 0.1264 U -0.01793 U -0.0259 U -0.04939 U Zr-95 0.05089 U 0.004321 U - -0.008452 U 0.02695 U 0.04337 U SOF _ 0.004 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 4 of 4 Rad SFP-02 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA
-jI Station (Key) NFVO0I.4 (3023) NFV001.4 (3023) NFV001.5 (3024) NFV001.5 (3024) NFV001.5 (3024)
Sample ID NFVOO1.4B NFVOO1.4C NFVOO1.5A NFV001.5B NFV0O1.5C Date Sampled 7/27/1998 7/27/1998 7/28/1998 7/28/1998 7/28/1998 Ac-228 0.8732 1.092 0.8769 0.8934 0.9782 Ag-108m -0.008744 U -0.005155 U 0.00547 U -0.006522 U -0.006211 U Ag-1 10m -0.04432 U 0.003654 U 0.06422 -0.01817 U 0.003998 U Am-241 0U 0U 0U 0U 0U Bi-212 1.322 1.372 1.3 0.9006 Bi-214 0.4947 0.4874 0.3886 0.5194 0.4496 Ce-144 -0.08103 U -0.02965 U -0.1243 U -0.2251 U 0.2178 U Co-58 0.01482 U 0.01783 U -0.004947 U -0.02131 U 0.01416 U Co-60 -0.02258 U -0.0132 U -0.0006695 U -0.01416 U 0.0187 U Cs-134 -0.1639 U -0.02612 U -0.03103 U -0.0533 U 0.004185 U Cs-137 -0.002597 U -0.02602 U 0.009408 U -0.004886 U -0.02311 U Eu- 152 Fe-59 0.06472 U -0.07319 U -0.03661 U -0.04706 U 0.005723 U 1-132 0.1931 U K-40 17.32 18.87 16.13 17.75 18.21 Mn-54 0U -0.005296 U 0.0241 U 0.02668 U 0.007831 U Mo-99 Nb-94 Nb-95 -0.005469 U 0.004204 U -0.0 1036 U -0.02803 U -0.006129 U Np-239 Pb-212 0.853 0.97 0.9262 0.8379 1.032 Pb-214 0.5018 0.4955 0.4006 0.4582 0.5732 Ra-226 0.8133 U 0.9823 1.336 0.9913 U Ru-103 0.006632 U -0.01039 U 0.01165 U -0.008546 U -0.02172 U Ru-106 0.03241 U -0.108 U 0.117 U 0U -0.3194 U Sb-124 0.008462 U -0.006988 U 0.01045 U 0.03349 U 0.006477 U Sb-125 TI-208 0.7306 0.8411 0.6831 0.723 0.8487 Zn-65 -0.05899 U -0.06986 U -0.1526 U 0.02765 U -0.104 U Zr-95 0U 0.06839 0.01768 U 0.01369 U -0.03076 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #1 -Designator SVC-01 Survey Area Description The Service' Building is a structure that, for the'purpose of this Historical Site Assessment (HSA) and Classification Summary, vill be'divided into three survey areas: SVC-01, SVC-02 and SVC-03. These survey areas are delineated based upon their'constriction, systems present and operating/use histories.'
Survey Area SVC-01 represents the original plant construction, non-Radiation Control Area (RCA) portion of the Service Building. Use of the spaces within the SVC-01 footprint includes the former location of the stockroom, small parcel shipping and receiving, and offices, which is now the maintenance department'shop' and'offices. The' current maintenance tool room was previously the Radiation Protecti6n (RP) offi6es and prior to that was the location of the Instrumentation and Controls (I&C) department shop:
The current RP whole body count room was formerly the plant break room located next to the plant locker room. The former location of the plant water treatment facility is now the temporary location'of the stockroom.
The SVC-01 portion of the Service Building is a structural steel frame and concrete block structure built on a reinforced concrete floor slab and foundation. The footprint of SVC-01 is approximately 921 square meters. There are additional subsurface structures associated with the footprint of the SVC-01 that include trenches, sumps, tank pits, grade beams foundation and 'column supports. (See drawings for details)
SVC-01 represents'that portion of the Service Building thit was not part of the Radiation' Control Area (RCA). SVC-01 is bounded on the noiith by'OOL-02, on'the east by'SVC-03, on the south by SVC-02 and on the west by TBN-01.
The sanitary sewer line that begins at the hot side lavatory runs under the floor of the SVC-0l, exiting the service building foundation on the north side.
Page 1 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #1 Designator: SVC-O1 Survey Area History The use of the Service Building spaces identified within survey area SVC-01 has changed over the life of the plant. The spaces identified as SCV-O1 have always been maintained as a clean area having experienced only minor contaminating events resulting from migration of radioactive contamination out of the RCA. When the routine radiological survey program identified such contaminating events the impacted area was decontaminated and maintained as a non-contaminated area.
The sanitary sewer system that runs under SVC-01 is potentially impacted. Radioactivity has been identified in the leaching field at the end of the sanitary sewer system. The likely input source of this radioactivity was operation of a hot side lavatory and the deposit of mop water derived from routine cleaning of the area just outside the RCA access point into the floor drains and sinks within the non-contaminated area.
Radiological assessments of SVC-Ol were performed on a routine basis. Surveys performed in July 1996 and in January, May and June 1998 did not identify radioactivity in excess of release criteria established at that time.
Scoping/Characterization Prior to commencing demolition activities in SVC-0 I a pre-demolition survey was developed in accordance with AP-083 1 Administrative Program for Radiological and Non-Radiological Characterization Surveys. The results of this survey identified no radiological contamination present within the bounds of SVC-0 1. This survey also serves as the survey for release for the demolition materials if appropriate.
DecommissioningActivities Decommissioning Activities performed in SVC-01 have removed the water treatment facility equipment, the secondary chemistry laboratory benches and equipment, and the equipment from mechanical operating equipment room.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building#1 Designator: SVC-O1 Findings Survey area SVC-01 was minimally impacted by plant operations and is not likely to contain residual radioactivity at levels greater than a small fraction of the DCGL.
The radionuclide mix for the SVC-01 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref. 1). The primary radionuclides of concern for SVC-01 are Co-60, Cs-137, Ag-108m, Sr-90, and tritium.
CurrentStatus SVC-01 currently is vacated and awaiting demolition. No sampling was conducted in this area.
ClassificationStatement Based upon the historical use and radiological conditions associated with this survey area SVC-01 is identified as a Class 3 Area.
Page 3 of 4
w-Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #1 Designator: SVC-O1 Drawings 9699-FB-05B 9699-FB-05C 9699-FC-22A 9699-FC-22B 9699-FC-22C 9699-FC-23A 9699-FC-23B 9699-FC-23C 9699-FC-23D References l1. I "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-l REPT- 00-001-03 Page 4 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #2 . Designator: SVC-02 Survey Area Description The Service Building is a structure that, for the purpose of this Historical Site Assessment (HSA) and Classification Summary, will be divided into three survey'areas: SVC-01, SVC-02 and SVC-03. These survey areas are delineated based upon their construction, systems present and operating/use histories.
Survey Area SVC-02 represents the original plant construction, Radiation Control Area (RCA) portion of the Service Building. Use of the spaces within the SVC-02 footprint includes the hot side machine shop and welding booth, the hot side lavatory (Out Of Service), RP count room, personnel decontamination showers, RP control point (from the clean side locker room access too to the female locker room) the female locker room, the primary side chemistry lab, the dress-out area and the RP instrument and equipment cage.
The hallway to the pass-through door and the hot side RP equipment shop and calibration facility in the service building annex.
Survey Area SVC-02 consists of the reinforced concrete floor slab and subsurface structures remaining after the demolition of the Service Building is complete. The footprint of SVC-02 is approximately 444 square meters of concrete surface area. There are additional subsurface structures associated with the footprint of the SVC-02 that include trenches, sumps, grade beams, foundation and column suppoits. (See drawings-for details) SVC-02 is bounded on the north by SVC-01, on the east by SVC-03 and OMB-04, on the south by NOLOl and OOI-12 and on the west by TBN-Ol.
Page I of 5.
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #2 Designator: SVC-02 Survey Area History Survey Area SVC-02 represents the original layout of the plant Radiation Control Area (RCA) portion of the Service Building. (Ref 1)
The hot side machine shop intermittently became contaminated as a result of maintenance work activities performed on contaminated plant equipment. The hot side machine shop area was maintained as a non-contaminated radioactive material area.-
The welding booth portion of the hot side machine shop was originally set-up as a decontamination room. It was later outfitted as a welding booth after Decontamination Pad #1 was converted from an out of doors pad to a building. (See NSY-01)
The hot side lavatory was originally set-up with two toilets, two urinals, and two hand wash stations. One of the hand wash stations was removed and replaced with a double deep sink. The toilets and urinal were removed from service although the plumbing still remains.
Plant Modification 76-28 rerouted the drain piping for the floor drains hand wash stations and the personnel decontamination shower from the sanitary sewer system to the liquid radioactive waste system.
The radiation control area (RCA) access control point is located in SVC-02. The current configuration of the control point is the result of Platt Alteration (PA)86-029. Prior to this the footprint of the control point consisted of the respirator storage room and the hot side locker room for plant personnel.
The female locker room was previously an RP storage room that contained supplies and surplus equipment, some of which was contaminated.
The present dress-out area was previously the contractor locker room. The RP instrument and equipment cage is the former location of the Protective Clothing (PC) storage area.
The primary chemistry lab is in its original location. It was surveyed on a routine basis when any portion of the primary chemistry lab was identified as contaminated and was decontaminated in order to maintain the area as a non- contaminated radioactive material area. The primary lab was renovated via PA 85-20; this replaced the laboratory benches, cabinets and flooring.
The RP instrument calibration lab and the hallway to the stockroom pass through window are located in the service building annex. The RP instrument calibration lab ws formerly occupied by the I&C department as the hot side instrument shop. The hallway was, as is now, used for storage of material and equipment.
Page 2 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #2 Designator: SVC-02 All portions of SVC-02 are surveyed on a routine basis. These surveys have identified radioactive contamination present; when contaminated the control point area was decontaminated.
The sanitary sewer system that runs under SVC-02 is potentially impacted. Radioactivity has been identified in the leaching field at the end of the sanitary sewer system. The - '
likely input source of this radioactivity was operation of a hot side'lavatory, resulting from deposition of mop water derived from routine cleaning of the area. Another likely input source of this radioactivity is the hot side lavatory.
Scoping/Characterization Prior to commencing demolition activities in SVC-02 a pre-demolition survey was developed in accordance with AP-0831 Administrative Program for Radiological and Non-Radiological Characterization Surveys.
DecommissioningActivities Decommissioning activities performed to date have removed the equipment from the hot side machine shop.
I . .-
,~- , . '
Page 3 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #2 Designator SVC-02 Findings Survey area SVC-02 was impacted by plant operations and is likely to contain residual radioactivity at levels greater than the DCGL.
The radionuclide mix for the SVC-02 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref 2). The primary radionuclides of concern for SVC-02 are Co-60, Cs-137, Ag-108m, Sr-90 and tritium.
Current Status SVC-02 currently continues to house the RP Control Point, Chemistry Laboratory, RP instrumentation storage and calibration facility and the hot side maintenance area. SVC-02 continues to be impacted by decommissioning activities.
A soil sample location map (Figure 48) has been prepared to show the distribution of sampling locations in SVC-02. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented). One survey media was assessed in SVC-02, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for SVC-02 is presented at the end of Table I for each survey medium. The results are summarized below.
Soil: Mean SOF is none detectable.
Maximum SOF for a single soil sample is rone detectable.
Minimum SOF for a single soil sample is none detectable.
Classiflcation Statement Based upon the historical use and radiological conditions associated with this survey area SVC-02 is identified as a Class I Area.
Page4of5
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #2 Designator: SVC-02 Drawings 9699-FB-05C 9699-FC-22A 9699-FC-22B 9699-FC-22C Service Building Addition, First Floor Plan + Details Drawing # A- 1, RJ Donovan Inc.
Service Building Addition, First Floor Plan + Details Drawing # S- 1, RJ Donovan Inc.
References Page 5 of 5
Pagelof I Table I Sum of Fractions SVC-02 -- Soil Yankee Nuclear Power Station Rowe, NIA Radionuclides for which SOF is calculated were not present in samples.
Table 2 - Page I orl Statistical Data Summary -SVC-02 -Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCi/g 4 4 0.970 0.054 0.890 1.007- 0.991 Ag-108m pCi/g 0 4 0.000 Ag- lOnm pCi/g 0 4 0.000 Am-241 pCi/g 0 4 0.000 Bi-212 pCi/g 4 4 0.758 0.180 0.610 1.013 0.704 Bi-214 pCi/g 4 4 0.514 0.040 0.456 0.549. 0.525 Ce-144 pCi/g 0 4 0.000 Co-58 pCi/g 0 4 0.000 Co-60 pCi/g 0 4 0.000 Cs-134 pCi/g 0 4 0.000 Cs-137 pCi/g 0 4 - 0.000 Eu-152 pCi/g 0 1 0.000 Fe-59 pCi/g 0 4 0.000 K-40 pCi/g 4 4 17.338 1.477 15.690 18.610 17.525 Mn-54 pCi/g 0 4 0.000 Nb-95 pCilg 0 4 0.000 Pb-212 pCi/g 4 4 0.919 0.083 0.819 1.008 0.924 Pb-214 pCi/g 4 4 0.525 0.040 0.502 0.585 0.505 Ra-226 pCi/g 3 4 2.215 0.743 1.651 3.057 1.937 Ru-103 pCi/g 0 4 0.000 Ru-106 pCi/g 0 4 0.000 Sb-124 pCi/g 0 4 0.000 TI-208 pCi/g 3 3 0.861 0.074 0.776 0.910 0.898 Zn-65 pCi/g 0 4 0.000 Zr-95 pCi/g 0 4 0.000
U Page I of I Table 3 Summary of Detected Results Above Criteria SVC-02 -- Soil Yankee Nuclear Power Station Rowe, MIA DCGL_Soil
- Sample Criterion # Detects Above Maximum Parameter # Detects Results Concentration Units Criterion Detected Ac-228 4 4 pCi/g 0 1.01 Ag-108m 0 4 8.52 pCi/g 0 Ag-lOrm 0 4 pCi/g 0 Am-241 0 4 44.35 pCi/g 0 Bi-212 4 4 pCi/g 0 1.01 Bi-214 4 4 pCi/g 0 0.55 Ce-144 0 4 pCi/g 0 Co-58 0 4 pCi/g 0 Co-60 0 4 4.84 pCi/g 0 Cs-134 0 4 6.71 pCi/g 0 Cs-137 0 4 12.24 pCi/g 0 Eu-152 0 1 12.06 pCi/g 0 Fe-59 0 4 pCi/g 0 K-40 4 4 pCi/g 0 18.61 Mn-54 0 4 21.66 pCilg 0 Nb-95 0 4 pCi/g 0 Pb-212 4 4 pCi/g 0 1.01 Pb-214 4 4 pCi/g 0 0.59 Ra-226 3 4 pCi/g 0 3.06 Ru- 103 0 4 pCi/g 0 Ru-106 0 4 68.21 pCi/g 0 Sb-124 0 4 pCi/g 0 TI-208 3 3 pCi/g 0 0.91 Zn-65 0 4 pCi/g 0 Zr-95 0 4 pCi/g 0
Table 4 Page I of I Rad SVC-02 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) SB003.1 (3062) SB003.2 (3063) SB003.2 (3063) SB003.2 (3063)
Sample ID SB003.1C SB003.2B SB003.2C SB003.2D Date Sampled 7/15/1998 7/14/1998 7/14/1998 7/14/1998 Ac-228 0.9947 0.9872 0.8903 1.007 Ag-108m -0.00268 U -0.01666 U 0.0 1372 U 0.01473 U Ag- lOnm -0.005703 U 0.02037 U -0.008758 U 0.00356 U Am-241 OU OU OU OU Bi-212 0.6569 0.61 1.013 0.7518 Bi-214 0.5275 0.5234 0.4557 0.5488 Ce-144 -0.02106 U -0.06196 U -0.01346 U 0.1135 U Co-58 0.009621 U 0.01401 U -0.000873 U 0.01461 U Co-60 0.02385 U -0.02135 U -0.01991 U -0.008059 U Cs-134 0.01293 U -0.01124 U 0.005807 U 0.0194 U Cs-137 -0.002596 U -0.02525 U -0.009319 U -0.02294 U Eu-152 0.2826 U Fe-59 0.04836 U 0.07071 U 0.04416 U -0.03279 U K-40 18.61 16.49 15.69 18.56 Mn-54 0.01244 U -0.004192 U 0.02977 U 0.01965 U Nb-95 -0.009507 U -0.08022 U 0.004885 U -0.0206 U Pb-212 1.008 0.8186 0.8895 0.959 Pb-214 0.5024 0.5052 0.5056 0.5851 Ra-226 3.057 1.937 1.23 U 1.651 Ru-103 -0.01511 U 0.02069 U -0.01397 U 0.00718 U Ru-106 -0.1346 U 0U 0.1438 U -0.09945 U Sb-124 -0.008862 U 0.01455 U -0.0188 U -0.0314 U TI-208 0.91 0.776 0.8981 Zn-65 0.02751 U 0.04574 U -0.08405 U -0.00731 U Zr-95 0.01679 U 0.03672 U 0.03558 U 0U U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #3 Designator: SVC-03 Survey Area Description The Service Building is a structure that, Tor the purpose of this Historical Site Assessment (HSA) and Classification Summary, will be divided into three'survey areas: SVC-O1,'
SVC-02 and SVC-03. These survey areas are delineated based upon their construction, systems present and operating/use histories.'
Survey Area SVC-03 represents the non-Radiation Control Area (RCA) portion of the Service Building Annex constructed in 1974. Use of the area within the SVC-03 footprint includes the stockroom, small parcel shipping and receiving and the Document Control Center (DCC). The double door at the southeast corner of the stockroom provided access to the warehouse and main loading dock area. The Radiation Protection instrument shop located at the south end of the service building addition and the hallway adjacent to it that leads to the stock room pass through window are part of the' RCA and are included in SVC-02.
Survey Area SVC-03 consists of the reinforced concrete floor and foundations that comprise the Service Building Addition expected to remain after demolition of the above-grade structures is complete. The SVC-03 footprint includes personnel access stairs and small loading dock combination located on the north side, the three bottom concrete steps of the exterior stairway that accesses the second floor and a concrete pad located at the double personnel door on the east side of SVC-03.
The Service Building Addition is a structural steel frame and concrete block structure built on a reinforced concrete floor slab and foundation. The footprint of SVC-03 is approximately 375 square meters. There are approximately 93 linear meters of foundation that extends to a depth of 1.35 meters associated with the footprint of the structure.
A portion of the sanitary sewer system and the east storm drain system run under the Service Building Addition.
Page 1 of 4
I-Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #3 Designator: SVC-03 Survey Area History The service building annex was constructed in 1974. It abuts the eastern end of the original service building and also connects the to the warehouse. The southwest corner of the service building addition was constructed on what had previously been a portion of the RCA that wrapped around the east end of the original service building (Ref 1). The footprint of this portion of the RCA under SVC-03 extends as far north as the former exterior door to the primary. chemistry lab. The present location of the nor-contaminated construction spoils generated during construction of the service building annex is thought to be within the SCF area (OOL.09) of the site. (Ref 2)
Radiological assessment of SVC-03 was performed on a routine basis. SVC-03 has always been maintained as a clean area having experienced only minor contaminating events resulting from migration of radioactive contamination out of the RCA. When contamination was identified the affected area was de-contaminated with a post decontamination survey performed and documented.
Radioactive material in the form of plant effluent samples sent offsite for analyses were normally shipped through the stockroom. These samples were packaged for shipment and surveyed prior to transfer to the stockroom for shipping. Packages of radioactive material received at the stockroom were surveyed upon receipt and then brought into the RCA prior to opening.
In 1977 a portion of the stockroom area of SVC-03 was designated as the location of Document Control Center. The DCC portion of SVC-03 was also surveyed on a routine.
basis and maintained as a clean area.
Scoping/Characterization Prior to commencing demolition activities in SVC-03 a pre-demolition survey was developed in accordance with AP-0831 Administrative Program for Radiological and Non-Radiological Characterization Surveys. The results of this survey identified no radiological contaminationpresent within the bounds of SVC-03. This survey also serves as the survey for release for the demolition materials.
DecommissioningActivities Demolition activities performed in SVC-03 were performed under DEM-TP-003 and 004.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #3 Designator: SVC-03 Findings Survey area SVC-03 was minimally impacted by plant operations and is not likely to contain residual radioactivity at levels greater than a small fraction of the DCGL.
The radionuclide mix for the SVC-03 includes all radionuclides identified in'the reactor radioactive systenis of the plant (Ref 3).'The primary radionuclides of concern for SVC-,
03 are Co-60, Cs-137, Sr-90 and tritium.
CurrentStatus Decommissioning activities in SVC-03 have removed the Service Building Aniex structure to elevation 1022'. No sampling'was conducted in this area.
ClassiflcationStatement -
Based upon the historical use and radiological conditions associated with this survey area SVC-03 is identified as a Class 3 Area.
Page 3 of 4
I-Building Historical Site Assessment and Classification Summary Survey Area Name: Service Building #3 Designator. SVC-03 Drawings 9699-FB-05C 9699-FC-22A 9699-FC-22B 9699-FC-22C Service Building Addition, First Floor Plan + Details Drawing # A- 1, RJ Donovan Inc.
Service Building Addition, First Floor Plan + Details Drawing # S- I, RJ Donovan Inc.
References
- 1. Radiation Protection Memorandum RP 98-23, "Overview of the YNPS Historical Material Release Evaluation," dated March 5, 1998.
- 2. "Summary of Excavation Volumes for YNPS Construction Performed During the Time Period of Plant Operation," dated October 1997.
- 3. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT- 00-001-03 Page 4 of 4
(.
Underground Systems SVC-03 Structure / System Component Description Location impacted?
Water from OOL-12 N to tee W8; E from W8 -40' to W8 - - Sand -1O E of NW hose house; from W8 N -50' corner of SB addition Abandoned Street electric cable -8' from east wall running N & S Lighting Page 1 of 1
Building Historical Site Assessment and Classification Summary Survey Area Name: Turbine Building #1 Designator: TBN-01 Survey Area Description Based upon the projected end-state of decommissioning activities,rSurvey Area TBN-01 will consist of the reinforced concrete floors and foundations of the Turbine and Administration Buildings, turbine support pedestal, and control room shield wall (reduced to grade level).,
The footprint of TBN-01 is approximately 1517 square meters of reinforced concrete floor slab minus that portion of the floor previously removed during demolition of the service water and floor drain systems. (See drawings for details of sections of the floor slab removed). ;
Survey area TBN-01 is bounded by survey area OOL-02, a Class 3 land survey area on the north, SVC-01 and SVC-02 on the east, NOL-06 on the south and OOLAO and OOL-02 on the west.
Systems that traverse or connect to TBN-01 include:
- Potable water,
- Fire protection water,
- Circulating water,
- Steam condensate,
- Feed water,
- De-mineralized water,
- Sanitary sewers,
- Fuel oil supply to the auxiliary boilers,
- Floor and equipment drains,
- Electrical duct trays Electrical conduits.
Page I of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Turbine Building #1 Designator: TBN-01 Survey Area History Radiological assessments of TBN-01 were performed on a routine basis.
Survey area TBN-01 has always been maintained as a clean area having experienced only.
minor contaminating events resulting from migration of radioactive contamination out of the RCA and through the service building. One significant contaminating event occurred in 1967 resulting from repair work performed on a reactor-cooling pump in a temporary radiation control area established on the turbine deck.
Structural modifications performed in TBN-01 include:
- Removal of the railroad spur line within the turbine building. (PA 19)
- Construction of a missile shield wall on the control room side of the turbine hall.'
- Reconfiguring of the auxiliary boiler room and turbine building floor drains and' trench. (PA-80-009)
Scoping/Characterization Scoping surveys were performed and the data collected used to develop the YNPS Decommissioning Plan. (Ref 1) Continuing characterization soil samples are also included in the TBN-01 soil sample data.
Remediations A soil remediation activity was conducted in subsurface locations of TBN-01 near support pedestal #4 around the time of floor drain and service water system piping removals. Since the source of this activity is uncharacteristic of the remainder of the building and at some depth, investigations will be performed in the most likely translocation pathway nearby. This is the backfill surrounding the Recirculation piping.
A summary of the results of "as found" soil sample data, results of samples taken during the progress of the remediation and results of "as left" soil sample data are included on the remediatedareas spreadsheet attached to this section. Details of some ofthe floor drain excavations are also included.
DecommissioningActivities A pre-demolition survey developed in accordance with AP-0831 Administrative Program for Radiological and Non-Radiological Characterization Surveys was implemented prior to commencing demolition activities in TBN-01. The results of this survey identified no residual radiological contamination present within the bounds of TBN-01. This survey also serves as the material survey for release in accordance with AP-0052 Radiation Protection Release of Equipment, Materials and Vehicles, for the TBN-01 demolition materials. Decommissioning Activities performed in TBN-01 have removed all operating systems Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Turbine Building #1 Designator: TBN-01 Findings Survey area TBN-01 was minimally impacted by plant operations and is not likely to':
contain residual radioactivity at levels greater than a small fraction of the DCGL.
The radionuclide mix for the TBN-01 includes all radionuclides identified in the reactor radioactive systems of the plant (Ref 2). The primary radionuclides of concern for TBN-01 are Co-60, Cs-137, Ag-108m, Sr-90, and tritium.
CurrentStatus TBN-01 currently is vacated and awaiting demolition.
A soil sample location map (Figure 50) has been prepared to show the distribution of sampling locations in TBN-01. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented). Two survey media were assessed in TBN-01, Asphalt and Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as ."key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL. There are separate sets of Tables 1-4 for each survey media. All are evaluated as fractions of the soil DCGL.'
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for TBN-01 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Asphalt: Mean SOF is 0.038.
Maximum SOF for a single asphalt sample is 0.038. (key# 270)
Minimum SOF for a single asphalt sample is 0.038. (key# 270)
Soil: Mean SOF is 0.087.
Maximum SOF for a single soil sample is 0.923. (key# 3137)
Minimum SOF for a single soil sample is 0.001. (key# 3325, 3346)
ClassificationStatement Based upon the historical use and radiological conditions associated with this survey area TBN-01 is identified as a Class 3 Area.
Page 3 of 4
a-Building Historical Site Assessment and Classification Summary Survey Area Name: Turbine Building #1 Designator: TBN-O1 Drawings 9699-FB-O&lA 9699-FB-05B 9699-FB-05C 9699-FB-05D 9699-FC-22A 9699-FC-22B 9699-FC-22C 9699-FC-23A 9699-FC-23B 9699-FC-23C 9699-FC-23D 9699-RC-7A References
- 1. YNPS Decommissioning Plarn Rev. 0.0.
- 2. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT- 00-001-03 Page4of4
Page I of I Table I Sum of Fractions TBN Asphalt Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 270 TBOOI-001 TBOOlBAFAOOl 0.038 Min 0.038 Max 0.038 Mean 0.038
Table 2 Page I of 1 Statistical Data Summary - TBN-O1 -- Asphalt Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCi/g 1 1 1.965 1.965 1.965 1.965 Ag-108m pCi/g 0 1 0.000 Ag-i lOm pCi/g 0 1 0.000 Bi-212 pCi/g 0 1 0.000 Bi-214 pCi/g I 1 1.503 1.503 1.503 1.503 Ce- 144 pCi/g 0 1 0.000 Co-58 pCi/g 0 1 0.000 Co-60 pCi/g I 1 0.183 0.183 0.183 0.183 Cs-134 pCi/g 0 1 0.000 Cs-137 pCi/g 0 1 0.000 Fc-59 pCi/g 0 1 0.000 K-40 pCi/g I 1 53.730 53.730 53.730 53.730 Kr-85 pCi/g 0 1 0.000 Mn-54 pCi/g 0 1 0.000 Nb-95 pCi/g 0 1 0.000 Pb-212 pCi/g I 1 2.513 2.513 2.513 2.513 Pb-214 pCi/g I 1 1.844 1.844 1.844 1.844 Ra-226 pCi/g 1 1 3.783 3.783 3.783 3.783 Ru-103 pCi/g 0 1 0.000 Ru-106 pCi/g 0 1 0.000 Sb-124 pCi/g 0 1 0.000 Sb-125 pCi/g 0 1 0.000 Se-75 pCi/g 0 1 0.000 TI-208 pCi/g 1 1 2.008 2.008 2.008 2.008 Zn-65 pCi/g 0 1 0.000 Zr-95 pCi/g 0 1 0.000 C ( ( IU
Page I of I Table 3 Summary of Detected Results Above Criteria I TBN-01 -Asphalt Yankee NuclearPower Station Rowe, MIA DCGLAAsphalt
- Sample Criterion # Detects Above Maximum Parameter # Detects Results _: Concentration Units Criterion Detected Ac-228 I pCi/g 1.97 Ag-108m 1 8.52 pCi/g Ag-i l Om I pCi/g Bi-212 I pCi/g Bi-214 I pCi/g 1.50 Ce- 144 I pCi/g Co-58 I pCi/g Co-60 I 4.84 pCi/g 0.18 Cs-134 1. . ' 6.71 pCi/g 1
Cs-137 12.24 pCi/g Fe-59 1 pCi/g K-40 pCi/g 53.73 Kr-85 I pCi/g Mn-54 I 21.66 pCi/g Nb-95 I pCi/g Pb-212 I pCi/g 2.51 Pb-214 I pCi/g 1.84 Ra-226 I pCi/g 3.78 Ru-103 I pCi/g
-__ Ru-106 I 68.21 pCi/g Sb-124 I pCi/g Sb-125 I 37.73 pCi/g Se-75 I pCilg TI-208 pCi/g 2.01 Zn-65 I pCi/g Zr-95 I pCi/g
a-Table 4 Page I of I Rad TBN-0O -Asphalt (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) TBOO1-001 (270)
Sample ID TBOOIBAFAOOI Date Sampled 12/18/1997 i Ac-228 1.965 Ag-108m -0.009932 U Ag-llOnm 0.05815 U Bi-212 1.619 U Bi-214 1.503 Ce-144 -0.0525 U Co-58 0.0007857 U Co-60 0.1829 Cs-134 -0.1523 U Cs-137 0.01338 U Fe-59 -0.02543 U K-40 53.73 Kr-85 32.19 U Mn-54 -0.02004 U Nb-95 -0.03846 U Pb-212 2.513 Pb-214 1.844 Ra-226 3.783 Ru-103 -0.01133 U Ru-106 -0.06281 U Sb-124 -0.03083 U Sb-125 -0.01128 U Se-75 0.0416 U TI-208 2.008 Zn-65 -0.09457 U Zr-95 0.0385 U SOF 0.038 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Asphalt Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Page I of 1 Table I Sum of Fractions TBN-OI - Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions
- 3315 TS99.16. TS99.16B- 0.004 3126 TB001.14 TB001.14 0.002 3133 TB001.25 TB001.25A 0.014 3135 TB001.27 TB001.27A 0.418 3135 TB001.27 .TB001.27B 0.008 3136 TB001.28 - TB001.28 0.832 3137 TB001.29 TB001.29 0.923 3138 TB001.3 TB001.3 0.062 3140 TB001.33 TB001.33 0.007 3305 TS99.02 TS99.02C 0.002 3306 TS99.07 TS99.07A 0.006 3306 TS99.07 TS99.07B 0.006 3124 TBOO1.I0 TBOO1.10 0.006 3310 TS99.11 TS99.IIC 0.007 3347 TS99.49 TS99.49A 0.003 3319 TS99.20 TS99.20B 0.003 3322 TS99.23 TS99.23A 0.009 3323 TS99.24 TS99.24A 0.004 3325 TS99.26 TS99.26B 0.001 3326 TS99.27 TS99.27A 0.003 3326 TS99.27 TS99.27B- 0.003 3338 TS99.39 TS99.39C 0.006 3339 TS99.40 TS99.40A 0.005 3342 TS99.43 TS99.43A 0.004 3343 TS99.44 TS99.44A 0.003 3346 TS99.48 TS99.48C 0.001 3309 TS99.10 TS99.1OB 0.002 Min 0.001 Max 0.923 Mean 0.087
Table 2 Page l of 2 Statistical Data Summary - TBN-01 -- Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCilg 138 138 0.805 0.134 0.312 1.131 0.814 Ag-108m pCilg 3 138 0.022 0.004 0.018 0.025 0.024 Ag- lOnm pCilg 3 138 0.045 0.007 0.037 0.049 0.048 Am-241 PCilg 0 138 0.000 Ba-133 pCilg 1 6 0.034 0.034 0.034 0.034 Ba- 140 PCilg 0 1 0.000 Bi-212 pCilg 105 119 1.459 6.316 0.507 65.520 0.796 Bi-214 pCilg 137 137 0.454 0.079 0.158 0.676 0.458 Cc- 141 pCilg 0 2 0.000 Ce- 144 pCilg 0 138 0.000 Co-58 pCilg 1 138 0.033 0.033 0.033 0.033 Co-60 pCilg 2 138 0.122 0.111 0.043 0.200 0.122 Cr-51 pCilg 0 1 0.000 Cs-134 pCilg 3 138 0.073 0.074 0.022 0.158 0.040 Cs-136 pCilg 2 5 0.444 0.176 0.319 0.569 0.444 Cs-137 pCilg 10 138 2.703 4.439 0.040 11.300 0.133 Eu- 152 pCilg 1 11 0.075 0.075 0.075 0.075 Fc-59 pCilg 3 138 0.068 0.009 0.060 0.078 0.067 1-131 pCilg 0 2 0.000 I-132 pCilg 1 2 1.447 1.447 1.447 1.447 K-40 pCilg 137 138 14.791 2.787 0.786 19.940 15.220 Kr-85 pCilg 3 8 8.601 3.247 4.902 10.980 9.921 La-140 pCilg 0 2 0.000 Mn-54 pCilg 6 138 0.036 0.007 0.028 0.046 0.036 Nb-94 pCilg 1 1 0.038 0.038 0.038 0.038 Nb-95 pCilg 5 138 0.044 0.013 0.033 0.065 0.043 Np-239 pCilg 0 18 0.000 Pb-212 pCilg 138 138 0.795 0.138 0.299 1.155 0.812 Pb-214 pCilg 138 138 0.492 0.081 0.212 0.687 0.491 Ra-226 pCilg 67 97 1.418 0.360 0.828 2.844 1.376 Ru- 103 pCilg 8 138 0.031 0.003 0.027 0.035 0.030 Ru- 106 vCilg 4 138 0.318 0.060 0.273 0.405 0.297
( (, I
(C C Table 2 Page 2 of 2 Statistical Data Summary - TBN-01 -- Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Sb-124 pCi/g 3 138 0.054 0.020 0.031 0.072 0.059 Sb-I 25 pCi/g I I1 0.261 0.261 0.261 0.261 Se-75 pCi/g 0 2 0.000 Sn-113 pCi/g 0 2 0.000 TI-202 pCi/g 0 3 0.000 TI-208 pCi/g -132 132 -0.739 0.141 0.339 1.165 0.745 Y-88 pCi/g 0 1 0.000 Zn-65 pCi/g 0 138 0.000 Zr-95 pCi/g 9 138 0.065 0.009 0.053 0.081 0.065
a-Page I of 2 Table 3 Summary of Detected Results Above Criteria TBN Soil Yankee Nuclear Power Station Rowe, MIA DCGL_Soil
- Sample Criterion # Detects Above Maximum Parameter # Detects Results Concentration Units Criterion Detected Ac-228 138 138 pCi/g 0 1.13 Ag-108m 3 138 8.52 pCi/g 0 0.02 Ag-lOrm 3 138 pCi/g 0 0.05 Am-241 0 138 44.35 pCi/g 0 Ba-133 1 6 pCi/g 0 0.03 Ba-140 0 1 pCi/g 0 Bi-212 105 119 pCi/g 0 65.52 Bi-214 137 137 pCi/g 0 0.68 Ce-141 0 2 pCi/g 0 Ce-144 0 138 pCi/g 0 Co-58 1 138 pCi/g 0 0.03 Co-60 2 138 4.84 pCi/g 0 0.20 Cr-51 0 1 pCi/g 0 Cs-134 3 138 6.71 pCi/g 0 0.16 Cs-136 2 5 pCi/g 0 0.57 Cs-137 10 138 12.24 pCi/g 0 11.30 Eu-152 1 11 12.06 pCi/g 0 0.08 Fe-59 3 138 pCi/g 0 0.08 1-131 0 2 pCi/g 0 1-132 1 2 pCi/g 0 1.45 K-40 137 138 pCi/g 0 19.94 Kr-85 3 8 pCi/g 0 10.98 La-140 0 2 pCi/g 0 Mn-54 6 138 21.66 pCi/g 0 0.05 Nb-94 1 1 8.53 pCi/g 0 0.04 Nb-95 5 138 pCi/g 0 0.06 Np-239 0 18 pCi/g 0 Pb-212 138 138 pCi/g 0 1.16 Pb-214 138 138 pCilg 0 0.69 Ra-226 67 97 pCi/g 0 2.84 Ru-103 8 138 pCi/g 0 0.04 Ru-106 4 138 68.21 pCi/g 0 0.41 Sb-124 3 138 pCi/g 0 0.07 Sb-125 1 11 37.73 pCi/g 0 0.26 Se-75 0 2 pCi/g 0 Sn-113 0 2 pCi/g 0 TI-202 0 3 pCi/g 0 TI-208 132 132 pCi/g 0 1.17
Page 2 of 2 Table 3 Summary of Detected Results Above Criteria TBN-0I-Soil 'I ; .
. Yankee Nuclear Power Station Rowe, MA
' DCGL_Soill -
- Ss imple' Criterion ,;', I # Detects 'Above Maximum Parameter .. # -Ri esults Concentration -Units - Criterion "' Detected I. .
Y-88 .I pCi/g -0 Zn-65 0, 138 I ' pCi/g . *0 Zr-95 9 138 - pCi/g 0 0.08
W-Table 4 Page I of 28 Rad TBN-01 -- Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) TB0OI.1O (3124) TBOOI.10 (3124) TB001.12 (3125) TBOO1.12 (3125) TB001.14 (3126)
Sample ID TBOOI.10 TB0O1.11 TBOOI.12 . TB001.13 TBOO1.14 Date Sampled 3/5/1998 3/5/1998 3/9/1998 . 3/9/1998 3/9/1998 Ac-228 0.8152 0.7455 0.6093 0.8566 0.6923 Ag-108m -0.0118 U 0.001634 U -0.006585 U -0.009356 U 0.01806 Ag-110mi 0.01477 U -0.01046 U -0.03285 U -0.009192 U -0.04117 U Am-241 0U 0U 0U OU OU Ba-133 Ba-140 Bi-212 0.5786 0.9687 0.7163 0.7833 0.6606 Bi-214 0.417 0.3843 0.3901 0.4258 0.3124 Ce-141 Ce-144 0.1074 U 0.003131 U 0.09727 U -0.06457 U 0.0852 U Co-58 -0.006393 U -0.0396 U -0.01238 U 0.00507 U -0.00795 U Co-60 0.01263 U 0.00306 U -0.01583 U -0.01822 U 0.006334 U Cr-51 Cs-134 -0.01331 U 0.01086 U 0.02789 U -0.1122 U 0.008909 U Cs-136 Cs-137 0.0261 U -0.01687 U -0.008738 U 0.03134 U -0.006554 U Eu-152 Fe-59 -0.01627 U -0.02018 U -0.0247 U -0.02844 U -0.03856 U 1-131 1-132 K-40 14.63 14.27 14.51 14.76 13.36 Kr-85 La-140 Mn-54 0.0231 U 0.01017 U 0.01491 U 0.002648 U 0.0143 U Nb-94 Nb-95 0.01978 U 0.01774 U 0.0003615 U 0.03268 U 0.001213 U Np-239 0.6014 U Pb-212 0.8039 0.8273 0.6043 0.7529 0.5193 Pb-214 0.4266 0.4371 0.35851 0.501 0.3731 Ra-226 1.175 1.328 0.8278 1.559 Ru-103 0.00279 U 0.007272 U 0.001468 U -0.007897 U 0.01943 U Ru-106 0.4051 0.08816 U -0.03629 U 0.1041 U 0.01814 U Sb-124 OU 0.007914 U 0.031451-0.01972 U 0.01619 U Sb-125 Se-75 Sn-113 Tl-202 TI-208 0.6728 0.7773 0.544 0.8472 0.5483 Y-88 Zn-65 0.06514 U 0.005085 U -0.1146 U 0.04999 U -0.009105 U Zr-95 0.03529 U 0.01782 U -0.003776 U 0.01552 U 0.008826 U SOF 0.006 1. 1 J.
0.002 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 2 of 28 Rad
- TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TB001.14 (3126) TBOO1.16 (3127) - TBOO1.16 (3127) TB001.18 (3128) TB001.18 (3128)
Sample ID TBOO1.15 TBOO1.16 TB001.17 TBOO1.18 TBOO1.19 Date Sampled 3/10/1998 3/10/1998 3/11/1998 3/11/1998 3/11/1998 Ac-228 - 0.8759 0.3122 0.8506 0.8903 0.7224 Ag-108m 0.007314 U 0.0002441 U -0.01569 U -0.01515 U -0.01244 U Ag-110m 0.02233 U -0.004701 U -0.01906 U -0.03157 U 0.002393 U Am-241 OU' OU OU OU OU Ba-133 Ba-140 Bi-212 0.7874 0.8814 0.6186 0.3494 U Bi-214 0.3049 0.1581 0.3765 0.4518 0.2916 Ce-141 Ce-144 -0.09412 U -0.03567 U 0.03146 U 0.0187 U 0.1305 U Co-58 -0.004 U -0.001785 U -0.00193 U 0.01581 U 0.005199 U Co-60 0.01 179 U 0.01116 U 0.01242 U -0.01255 U 0.008972 U Cr-51 Cs-134 -0.004974 U 0.003767 U -0.008034 U -0.1352 U 0.02567 U Cs-136 Cs-137 -0.02441 U -0.01386 U ' 0.00643 U 0.006358 U -0.01412 U Eu-152 Fe-59 OU 0.0173 U -0.01427 U -0.02072 U -0.04171 U 1-131 1-132 K-40 10.99 4.778 12.89 14.97 9.285 Kr-85 La-140 Mn-54 0.00455 U 0.0007837 U 0.009581 U 0.0006471 U 0.0003316 U Nb-94 Nb-95 0.007426 U 0.006869 U 0.01474 U 0.009869 U * -0.0002001 U Np-239 Pb-212 0.79 0.299 0.8523 0.7324 0.6093 Pb-214 0.4098 0.2123 0.513 0.4436 0.4437 Ra-226 0.6765 U 0.415 U - 0.6896 U Ru-103 -0.006158 U 0.00312 U -0.004966 U' -0.022 U 0.005976 U '
Ru-106 0.1888 U . I 0.03835 U 0.1099 U 0.05278 U ; 0.01713 U Sb-124 0.009057 U 0.003447 U 0.0252 U 0.02467 U 0U Sb-125 Se-75 Sn-113 Tl-202 TI-208 0.7505 0.8386 0.7534 0.4683 Y-88 Zn-65 -0.0262 U 0.02965 U 1-0.04278 U 0.08039 U -0.02598 U Zr-95 0.03291 U -0.00477 U , -0.01646 U 0.03064 U OU SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 3 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) ITB001.18 (3128) ITB001.1 (3123) TB001.20 (3130) TBOO1.20 (3130) TB001.23 (3131)
Sample ID TBO01.199 TBOOI.1A TB001.20 TBOOI.21 TB001.23A Date Sampled 3/11/1998 11/28/1998 3/12/1998 13/12/1998 8/13/1998 Ac-228 0.6801 0.859 0.7493 0.787 0.8846 Ag-108m -0.015 14 U 0.01241 U -0.01187 U 0.006994 U 0.001944 U Ag-110mi 0.008866 U 0.02082 U 0.02378 U 0.01484 U -0.01284 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 0.9534 12.63 U 0.6926 0.8143 0.9406 Bi-214 0.3249 0.3972 0.3669 0.4581 Ce-141 Ce-144 -0.006102 U -0.0157 U 0.003114 U -0.03321 U 0.05799 U Co-58 -0.008992 U -0.001234 U OU -0.02508 U -0.02333 U Co-60 -0.01804 U -0.01251 U -0.02766 U -0.0122 U 0.02181 U Cr-51 Cs-134 0.001473 U -0.007337 U -0.02153 U 0.009256 U 0.03623 U Cs-136 Cs-137 -0.02095 U 0.01351 U -0.03181 U OU -0.01799 U Eu-152 Fe-59 -0.02241 U 0.02996 U 0.0597710.0002229 U -0.0 1507 U 1-131 1-132 K-40 9.06410.1312 U 13.47 15.96 15.82 I
Kr-85 La-140 Mn-54 -0.001098 U 0.004827 U 0.009916 U 0.005346 U 0.002803 U Nb-94 Nb-95 0.0159 U -0.003223 U 0.001219 U 0.01169 U 0.01748 U Np-239 -0.3336 U -0.318 U Pb-212 0.6134 0.811 0.9416 0.7693 0.8785 Pb-214 0.4055 0.5689 0.446 0.4202 0.5177 Ra-226 1.227 0.9923 Ru-103 -0.004549 U -0.006255 U -0.01259 U 0.01596 U -0.001131 U Ru-106 -0.03444 U 0.01783 U 0.1407 U -0.02791 U -0.1455 U Sb-124 0.01858 U 0.02496 U 0.02404 U -0.005611 U 0.02671 U Sb-125 Se-75 Sn-113 TI-202 TI-208 0.5199 0.83 0.7582 0.7909 0.8601 Y-88 Zn-65 -0.03521 U 0U 0.01628 U -0.06904 U -0.1469 U Zr-95 0.0009521 U 0.001728 U 0.01595 U 0.01429 U 0.0398 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 4 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TB001.23 (3131) TB001.24 (3132) TB001.25 (3133) fTBOO1.25 (3133) TB001.26 (3134)
Sample ID -TBOOI.23B TB001.24A .TBO01.25A I TBOO1.25B - TBOO1.26B Date Sampled 8/13/1998 48t12/1998 18/13/1998 8/13/1998 1:8/13/1998 Ac-228 1.089 0.792 0.735 0.9504 0.6286 Ag-108Im 0.002577 U -0.00788 U -0.003188 U -0.01593 U -0.02081 U Ag-I lOin 0.01699 U 0.01396 U -0.006769 U 0.02718 U -0.0286 U Am-241 OU' 0U 0U 0U OU Ba-133 Ba-140 Bi-212 0.7284 0.7378 0.9867 0.5906 Bi-214 0.544 0.4522 0.5224 0.4321 0.4402 Ce-141 Ce-144 0.09416 U 0.09341 U 0.04368 U -0.04292 U ' -0.0368 U Co-58 0.00393 U -0.02405 U -0.02692 U 0.02378 U 0.005409 U Co-60 -0.01659 U -0.0007894 U 0.0000842 U 0.02398 U 0.003724 U Cr-51 Cs-134 -0.01196 U -0.07094 U 0.02585 U 0.0132 U 0.04761 U Cs-136 Cs-137 0.01847 U 0.01017 U 0.1692 10.002719 U 0.00257 U Eu-152 Fe-59 0.005816 U 0.004613 U 0.01177 U -0.006976 U -0.03433 U 1-131 1-132 K-40 16.85 16.88 14.75 14.81 16.36 Kr-85 I i
La-140 Mn-54 -0.01966 U 0.02341 U -0.006584 U -0.02321 U 0.009499 U Nb-94 Nb-95 0.006675 U 0.01623 U 0.02054 1 0.01729 U -0.007146 U Np-239 Pb-212 0.9643 0.7125 0.8899 0.8784 0.7759 Pb-214 0.5556 0.5062 0.4593 0.405 0.4397 Ra-226 1.121 0.6841 U 1.218 1.571 2.066 Ru-103 0.02291 U 0.01056 U 0.008402 0.00555 U 0.02669 Ru-106 -0.08682 U 0.02288 U 0.2631 U 0.1578 U 0.1159 U '
Sb-124 -0.005812 U 0.01079 U -0.05175 U 0.000805 U -0.009525 U Sb-125 Se-75 Sn-113 TI-202 0.02146 U TI-208 0.8054 0.7409 0.6393 0.8415 0.6538 Y-88 Zn-65 -0.1347 U -0.0413 U -0.002597 U I -0.1083 U ;:-; 0.01934 U Zr-95 0.005364 U 0.04018 U 0.03482 U ; 0.05572 10.02609 U SOF 0.014 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
a-Table 4 Page 5 of 28 Rad TBN-O1 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TB001.27 (3135). }TBOO1.27 (3135) TTB001.27 (3135) TB001.28 (3136) TBOOI.29 (3137)
Sample ID TB0OI.27A TB001.27B - TBOOI.27C TB0O1.28 TB001.29 Date Sampled 8/17/1998 8/1711998 8/17/1998 5/3/1999 5/4/1999 -
Ac-228 0.6856 1.031 0.9745 0.6804 0.9507 Ag-108m 0.03345 U -0.003498 U 0.006869 U 0.01094 U -0.03895 U Ag-1 10m. 0.006467 U -0.01939 U 0.005772 U -0.02716 U 0.02313 U Am-241 0U OU OU OU: OU Ba-133 Ba-140 Bi-212 1.117 0.7145
- 0.5956 0.5741 Bi-214 0.4532 0.5217 0.6596 0.4924 0.4407 Ce-141 Ce- 144 -0.05131 U -0.05939 U -0.2846 U 0.2653 U 0.04675 U Co-58 -0.03068 U -0.003207 U 0.00149 U -0.01918 U 0.00799 U Co-60 0.2003 -0.01064 U -0.008563 U -0.01073 U -0.01448 U Cr-51 Cs-134 0.15791-0.005698 U -0.1457 U -0.04668 U 0.09086 U Cs-136 Cs-137 4.295 0.097510.02926 U 10.18 11.3 Eu-152 Fe-59 -0.03986 U -0.01876 U 0.04863 U -0.023 U -0.03372 U 1-131 1-132 K-40, 15.67 17.12 18.58 16.23 16.27 Kr-85 La-140 Mn-54 0.0457210.009922 U 0.01624 U -0.007636 U -0.01523 U Nb-94 Nb-95 -0.009832 U 0.06451-0.0174 U -0.0188 U 0.03287 Np-239 Pb-212 0.7807 0.8655 0.8126 0.8136 0.9067 Pb-214 0.4323 0.6346 0.6236 0.4949 0.4771 Ra-226 2.844 2.263 Ru-103 -0.01449 U 0.01046 U -0.02803 U 0.0084 U -0.05644 U Ru-106 0.0632 U -0.02312 U 0.2452 U 0.02148 U 0.03157 U Sb-124 -0.006812 U 0.03839 U 0.05429 U 0.01954 U 0.02797 U Sb-125 Se-75 Sn-1 13 1.042 U TI-202 Tl-208 0.74 0.7086 0.8164 0.8019 0.63661.
Y-88 Zn-65 -0.2792 U -0.05704 U -0.1201 U 0.03237 U 0.008341 U Zr-95 0.009601 U 0.05725 U 0.05954 U -0.04067 U 0.06006 SOF 0.418 0.008 0.832 0.923 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 6 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) JTBOOI.2 (3129) JTBOO1.3 (3138) fTBOO1.31 (3139) TBOO1.33 (3140) TB0O1.35 (3141)'
Sample ID TB001.2A . TBOO1.3 - TBOO1.31 TBOO1.33 .:- : TBOO1.35 Date Sampled 1/28/1998 .5/4/1999 I.5/4/1999 , 5/4/1999 5/11/1999 Ac-228 0.7552 0.778 0.8154 0.9433 -I 0.675 Ag-108Im 0.002859 U -0.0007865 U -0.0221 U 0.008861 U -0.01451 U Ag-110n -0.0007583 U 0.01672 U -0.00865 U 0.00748 U' -0.01611 U Am-241 0U OU OU ' OU OU Ba-133 Ba-140 Bi-212 0.4266 U 0.5282 0.6797 0.6311 1.254 Bi-214 0.3797 0.4693 0.4726 0.4217 0 .4727 Ce-141 Ce-144 -0.1347 U -0.03524 U 0.1132 U -0.03753 U -0.004756 U Co-58 0.008297 U -0.002298 U 0.01698 U 0.0006861 U 0.01223 U Co-60 -0.00408 U -0.01655 U -0.008207 U 0.0194 U -0.01234 U Cr-51 Cs-134 -0.02367 U -0.04601 U -0.05275 U -0.06305 U 0.02323 U Cs-136 Cs-137 -0.0 1867 U 0.762610.01222 U 0.07033 10.01296 U Eu-152 Fe-59 -0.0184 U -0.005119 U 0.0001523 U -0.02039 U -0.04604 U 1-131 1-132 K-40 0.7857 15.76 16.73 17.38 ,15.18 Kr-85 La-140 Mn-54 0.002436 U 0.03159 U 0.02263 U 0.03671 0.01896 U Nb-94 Nb-95 -0.03207 U t 0.006773 U 0.02957 U -0.005356 U -0.002477 U Np-239 -0.1461 U Pb-212 0.6608 0.8265 0.8179 0.8162 0.8185 Pb-214 0.4388 0.5019 0.5287 0.4769 0.3926 Ra-226 0.887 1.254 0.8948 U 1.076 0.8318 U Ru-103 0.01409 U 0.002014 U1 ., . 1.. 0.0004669 U -0.002487 U 0.006808 U Ru-106 -0.1376 U -0.05684 U -0.01503 U : 0.147 U 0.1719 U Sb-124 -0.01932 U -0.02143 U OU, 0.002032 U -0.02819 U Sb-125 Se-75 Sn-113 TI-202 TI-208 0.5862 0.7885 0.6811 0.7975 0.7401 Y-88 Zn-65 -0.02874 U -0.04802 U -0.008134 U - 0.05519 U -0.07894 U Zr-95 -0.01062 U 0.03178 U 0.04159 U 0.04764 U 0.009733 U SOF I 0.062J. 0.007 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 7 of 28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TBOO1.3 (3138) TBOO1.4 (3142) TB001.4 (3142) TB001.6 (3143) TB001.6 (3143)
Sample ID 1 TBOO1.3A TBOO1.4 TBOO1.5 TB001.6 TBOO1.7 Date Sampled 1/29/1998 [3/5/1998 3/5/1998 3/5/1998 ' 3/5/1998 -
Ac-228 0.5406 0.8955 0.9148 0.6848 0.8396 Ag-108m -0.01073 U -0.00908 U 0.005003 U -0.01189 U -0.01346 U Ag-1 10m -0.008436 U 0.01077 U -0.0154 U 0.01186 U -0.02279 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 0.6688 0.3265 U 0.6464 0.6747 0.7517 Bi-214 0.5542 0.5066 0.5216 0.3956 0.4063 Ce-141 Ce-144 -0.2439 U 0.09456 U -0.09464 U 0.001843 U -0.002607 U Co-58 -0.01108 U -0.01637 U 0.02187 U 0.006781 U -0.009736 U Co-60 0.01242 U -0.01743 U -0.0303 U -0.001455 U -0.0028 U Cr-51 Cs-134 0.03261 U -0.09678 U -0.05972 U -0.04679 U -0.05231 U Cs-136 Cs-137 0.01616 U -0.004908 U 10.004647 U -0.01665 U -0.004902 U Eu-152 Fe-59 -0.01664 U 0.01089 U 0.01031 U 0.03343 U -0.01579 U 1-131 1-132 K-40 10.49 13.94 14.48 16.57 15.07 Kr-85 La- 140 Mn-54 -0.01079 U -0.00374 U -0.01818 U 0.02015 U 0.02092 U Nb-94 Nb-95 0.01162 U -0.01812 U -0.004345 U -0.03261 U -0.006421 U Np-239 Pb-212 0.6555 0.631 0.8074 0.6864 C1.9064 Pb-214 0.4664 0.4416 0.4875 0.4557 C1.4392 Ra-226 0.7157 U 1.118 0.8869 U Ru-103 -0.01301 U -0.00815 U -0.002153 U -0.0009693 U 0.006958 U Ru- 106 -0.1148 U 0.08137 U 0.01926 U 0.06244 U 0.1374 U Sb-124 -0.003584 U 0.02106 U 0.0189 U 0.01894 U 0.01788 U Sb-125 Se-75 Sn-113 Tl-202 TI-208 0.5784 0.6966 0.7036 0.6863 0.8426 Y-88 Zn-65 -0.05785 U 0.1496 U 0.08427 U 0.07289 U 0.06947 U Zr-95 0.03082 U 0.02726 U 0.02973 U -0.007283 U 0.005441 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 8 of 28 Rad TBN-01 -- Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) TB0O1.8 (3144) TBOO1.8 (3144) TS99.02 (3305) TS99.02 (3305) TS99.02 (3305)
Sample ID TBOO1.8 TBOO1.9 TS99.02A TS99.02B TS99.02C Date Sampled 13/5/1998 3/5/1998 4/1/1999 1411i1999 4/1/1999 Ac-228' 0.6398 0.7675 0.7422 0.9171 0.8865 Ag-108m -0.02068 U -0.004355 U: 0.01268 U -0.01951 U -0.005294 U Ag-lOmrn -0.02305 U 0.03078 U ; -0.005418 U 0.004821 U 0.00172 U Amn-241 OU 0U OU OU OU Ba-133 Ba-140 Bi-212 0.6976 0.798 1.445 0.9874 0.5795 Bi-214 0.3744 *0.4199 0.5083 0.5705 0.5307 Cc-141 Ce-144 -0.08672 U 0.1381 U -0.1968 U 0.03521 U -0.05174 U Co-58 -0.004623 U -0.01501 U -0.01385 U 0.01859 U -0.001696 U Co-60 -0.003198 U -0.002966 U 0.01054 U 0.004057 U 0.02421 U, Cr-51 Cs-134 -0.008334 U -0.08663 U 0.01605 U -0.1814 U 0.006853 U -
Cs-136 Cs-137 -0.003041 U 0.004381 U 0.01389 U 0.01678 U -0.008383 U Eu-152 Fe-59 -0.006856 U 0.009784 U -0.0129 U -0.000000006284 U 0.06707 1-131 1-132 K-40 14.21 14.7 17.31 15.311 15.71 Kr-85 La-140 Mn-54 -0.009051 U 0.003777 U 0.02626 U 0.01318 1U 0.04279 Nb-94 Nb-95 -0.01795 U 0.01913 U -0.01224 U -0.00570:3U 0.01139U Np-239 0.3123 U Pb-212 0.6987 0.8582 !09319 0.9233 0.8205 Pb-214 0.3124 0.5173 0.5763 0.6091 0.4973 Ra-226 0.8178 U 1.747 1.488 ()77RQ1 1T Ru-103 0.03355 -0.01599 U -0.02323 U -0.002542 U 0.01648 U Ru-106 0.03686 U -0.01709 U 0.05227 U 0.1167 U 0.1122 U --
Sb-124 0.02027 U -0.01534 U OU -0.03372 U 0.03206 U Sb-125 Se-75 Sn-113 TI-202 TI-208 0.6613 0.7965 0.6738 0.9343 0.7287 Y-88 Zn-65 -0.08874 U 0.141 U 0.07141 U -0.04694 U -0.05109 U Zr-95 0.07411 -0.0002557 U 0.0622 U 0.0587 U 0.02766 U SOF 0.002 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
I!
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 9 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.07 (3306) TS99.07 (3306) TS99.08 (3307) TS99.08 (3307) TS99.09 (3308)
Sample ID - TS99.07A TS99.07B TS99.08A j TS99.08B TS99.09A Date Sampled 4/7/1999 4/8/1999 4/8/1999 j4/8/1999 4/8/1999 Ac-228 0.7459 0.8615 0.8245 0.8862 0.7413 Ag-108m -0.0 1656 U -0.0007065 U -0.03572 U -0.006612 U 0.0145 U Ag-110mI -0.03461 U -0.004998 U -0.0 1296 U 0.04782 0.0009566 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 1.225 0.9419 0.776 0.8645 1.211 Bi-214 0.4542 0.6079 0.5861 0.6057 0.5232 Ce-141 Ce-144 -0.1085 U 0.02709 U 0.04568 U 0.01846 U -0.03074 U Co-58 -0.003787 U 0.006573 U -0.002307 U 0.02726 U -0.01731 U Co-60 -0.02936 U -0.01981 U -0.01156 U -0.02672 U 0.008303 U Cr-51 Cs-134 0.0401 -0.02907 U -0.009425 U -0.02349 U -0.1054 U Cs-136 Cs-137 0.01157 U -0.03828 U -0.02658 U -0.0283 U -0.03472 U Eu-152 1.013 U 0.07504 Fe-59 -0.01297 U 0.04291 U -0.04153 U -0.01764 U -0.04725 U 1-131 1-132 6.784 U K-40 17.36 16.45 17.34 18.27 18.33 Kr-85 La-140 Mn-54 -0.007654 U -0.0464 U -0.002972 U -0.01228 U -0.01818 U Nb-94 Nb-95 0.03051 U 0.01028 U 0.01 12 U -0.02234 U 0.01406 U Np-239 0.1597 U -0.2362 U Pb-212 0.9324 0.8237 0.9118 0.9051 0.9129 Pb-214 0.632 0.6844 0.6874 0.6244 0.5478 Ra-226 0.9969 U 0.9654 U 1.423 0.9562 U Ru-103 0.004973 U -0.01352 U -0.01385 U -0.009412 U 0.006867 U Ru-106 -0.1201 U -0.0544 U -0.05387 U -0.02274 U 0.09556 U Sb-124 -0.06339 U -0.007284 U 0.02894 U 0.008228 U 0.01262 U Sb-125 -0.1132 U Se-75 Sn-113 TI-202 Tl-208 0.7566 0.8128 0.6876 0.9139 0.6367 Y-88 Zn-65 0.008144 U -0.1212 U 0.01789 U 0.02548 U 0.07564 U Zr-95 0.03133 U 0.01097 U 0.0386 U 0.008136 U -0.02089 U SOF 0.006 I 0.006 5 1. .5.
U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 10 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA' Station (Key) -TS99.09 (3308) TS99.09 (3308) TS99.10 (3309) (3309) (3309) TS99.10 (3309)
Sample ID TS99.09B TS99.09C ! -.TS99.lOA I TS99.lOB r i X TS99.lOC Date Sampled 4/8/1999 ; 4/8/1999 - 4/19/1999 - 4/19/1999 j4/19/1999 Ac-228 - 0.7808 0.7679 0.7396 0.7716 0.5574 Ag-108m 0.003746 U : -0.005347 U - 0.003099 U' 0.004183 U ; 0.00638 U Ag- lOnm -0.01005 U -0.01205 U -; 0.04911 0.0271 U 0.007292 U Am-241 oU OU OU OU OU - I Ba-133 Ba-140 Bi-212 0.9166 1.031 1.11310.384 U Bi-214 0.4695 0.4184 0.4069 0.4164 0.3589 Ce-141 Ce-144 -0.07197 U -0.06376 U -0.04361 U 0.02533 U 0.02136 U Co-58 -0.02175 U -0.004692 U -0.005038 U -0.008184 U 0.03337 Co-60 -0.004207 U 0.004094 U 0.01498 U 0.0177 U -0.01027 U ' -
Cr-5I Cs-134 -0.02499 U -0.04921 U - -0.07113 U 0.03988 U 0.006407 U Cs-136 Cs-137 0.0001547 U 0.03669 U 0.02091 U OU -0.0296 U Eu-152 Fe-59 0.006841 U 0.01996 U -0.02293 U 0.03136 U -0.005879 U 1-131 1-132 K-40 18.49 16.89 17.38 15.93 16.11 Kr-85 9.921 La-140 Mn-54 -0.001783 U 0.0133 U 0.02467 U 0.034331-0.01613 U Nb-94 Nb-95 0.001818 U 0.03319 U 0.01119 U 0.0105 U -0.01392 U.
Np-239 Pb-212 0.7424 0.7439 0.4923 0.6842 0.5737 Pb-214 0.6694 0.5156 - 0.4176 0.4758 0.4945 Ra-226 1.436 1.805 Ru-103 0.00048 U 0.01419 U -0.006581 U 0.01365 U -0.001131 U Ru-106 -0.3147 U -0.1 178 U 0.1071 U 0.1271 U 0.1097 U Sb-124 0.02639 U -0.006548 1 0.01032 U 0.005673 U -0.007637 U Sb-125 Se-75 Sn-113 TI-202 TI-208 0.7074 0.5989 0.5689 ": 0.7583 0.6224 Y-88 Zn-65 0.01947 U -0.01947 U 0.001663 U -0.1675 U 0.02993 U Zr-95 -0.0315 U 0.02813 U 0.02953 U 0.01658 U 0.009488 U SOF I 1. _________________________
0.002 1 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
a-Table 4 Page 11 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.11 (3310) TS99.11 (3310) TS99.11 (3310) TS99.12 (3311) TS99.12 (3311)
Sample ID TS99.11A - TS99.111B TS99.11 C TS99.12A - TS99.12B Date Sampled 4/19/1999 4/19/1999 4/19/1999 14/19/1999 4/19/1999 Ac-228 0.93 1.131 0.981 0.8999 0.7974 Ag-108m -0.006647 U 0.00755 U -0.007248 U -0.02183 U -0.01315 U Ag-10m 0.0148 U 0.0128 U -0.02005 U 0.01321 U -0.002996 U Am-241 0U OU OU OU OU Ba-133 0.03212 U Ba-140 Bi-212 1.089 1.216 0.9788 1.309 1.187 Bi-214 0.6757 0.5322 0.5247 0.5015 0.3514 Ce-141 Ce-144 0.1246 U -0.02555 U -0.04752 U 0.03672 U -0.1573 U Co-58 -0.03244 U 0.006452 U 0.006713 U -0.02444 U -0.01182 U Co-60 -0.01997 U -0.01121 U -0.01 173 U 0.01463 U -0.01513 U Cr-51 Cs-134 -0.07354 U -0.0514 U -0.1589 U -0.02823 U -0.1374 U Cs-136 Cs-137 0.002572 U -0.03941 U 0.01888 U -0.0132 U -0.009916 U Eu-152 Fe-59 0.04001 U 0.02292 U -0.04837 U -0.005914 U 0.01005 U 1-131 1-132 K40 17.61 19.94 18.07 14.46 13.46 Kr-85 La-140 Mn-54 0.004966 U 0.01703 U -0.006579 U 0.001343 U 0.02342 U Nb-94 Nb-95 0.01334 U -0.006905 U 0.03454 U 0.01684 U 0.006875 U Np-239 -0.4582 U 0.1262 U Pb-212 1.044 1.025 1.071 0.8766 0.7861 Pb-214 0.5729 0.4941 0.5417 0.6013 0.4816 Ra-226 1.376 1.711 1.53 1.616 Ru-103 -0.01195 U -0.02492 U 0.006677 U 0.02369 U 0.01707 U Ru-106 0.1279 U 0.0855 U 0.00342 U -0.03067 U -0.08082 U Sb-124 -0.01828 U -0.01832 U 0.00719 U -0.002359 U 0.009764 U Sb-125 0.2607 Se-75 0.06131 U Sn-113 TI-202 TI-208 1.077 0.9693 0.8845 0.8519 0.8097 Y-88 Zn-65 -0.122 U -0.1271 U 0.06829 U -0.09236 U -0.03657 U Zr-95 -0.01558 U 0.04804 U 0.03229 U 0.01496 U -0.00344 U SOF 0.007 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 12 of 28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.12 (3311) ITS99.13 (3312) TS99.14 (3313) TS99.14 (3313) TS99.14 (3313)
Sample ID - TS99.12C TS99.13A TS99.14A TS99.14B TS99.14C Date Sampled 4/20/1999 14/20/1999 - 4/22/199 /26/1999 4127/1999 Ac-228 0.9516 0.7541 0.774 0.8856 0.833 Ag-108m -0.004279 U -0.007813 U 0.001828 U -0.01421 U 0.01015 U Ag-1 lOn -; 0.01311 U -0.005738 U -0.02612 U -0.003471 U 0.03071 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 0.50710.4011 U 0.5775 0.4472 U Bi-214 0.5065 0.5598 0.4225 0.443 0.5143 Ce-141 Ce-144 0.08203 U -0.1423 U 0.06678 U 0.09302 U ' 0.1789 U Co-58' -0.009658 U -0.01715 U 0.001357 U 0.001718 U 0.002467 U Co-60 0.003688 U -0.05608 U 0.003849 U 0.008244 U OU Cr-51 Cs-134 -0.01835 U -0.1086 U -0.01688 U -0.1235 U 0.03604 U Cs-136 I
Cs-137 0.006047 U 0.01658 U -0.01857 U -0.01706 U -0.02581 U Eu-152 0.4449 U Fe-59 -0.02448 U -0.03728 U -0.0374 U OU -0.02982 U I
1-131 1-132 1.447 K40 17.77 15.66 13.56 15.41 18.83 Kr-85 La-140 Mn-54 0.003365 U 0.02166 U -0.00163 U -0.03646 U 0.003897 U Nb-94 Nb-95 -0.0192 U 0.008049 U 0.03324 U 0.01403 U - 0.03298 U Np-239 -0.3019 U Pb-212 0.9509 0.7823 0.7592 0.8598 0.911 Pb-214 0.5227 0.506 0.5082 0.5708 0.4166 Ra-226 0.885 U 1.401 1.149 - 1.436 Ru-103 -0.003808 U 0.0327 -0.001748 U -0.003776 U -0.006349 U Ru-106 0.02288 U -0.06883 U ' -0.02214 U 0.0708 U 0.06911 U Sb-124 -0.002448 U 0.03368 U 0.05894 -0.01398 U -0.008511 U :
Sb-125 -0.05709 U Se-75 Sn-113 TI-202 TI-208 1.08 0.7916 0.6114 0.7479 0.7286 Y-88 Zn-65 0.01951 U 0.04394 U 0.008155 U -0.01029 U -0.05468 U Zr-95 -0.03591 U 0.02855 U 0.0537 U 0.04007 U -0.003741 U SOF I .L .L _________________________
U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 13 of 28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.15 (3314) TS99.15 (3314) TS99.15 (3314) TS99.16 (3315) TS99.16 (3315)
Sample ID TS99.15A : TS99.15B TS99.15C -TS99.16A TS99.16B Date Sampled 4/27/1999 4/27/1999 4/27/1999 - 4/27/1999 4/27/1999 Ac-228 . 0.9722 0.9014 0.8578 1.014 D.8494 Ag-108m -0.01 119 U 0.004243 U 0.009166 U 0.01434 U -0.01478 U Ag-IlOrn -0.03258 U 0.02255 U -0.02871 U 0.01866 U -0.01005 U Am-241 0U OU OU OU OU Ba-133 -0.02221 U Ba-140 Bi-212 0.9404 0.8276 0.7204 0.7958 0.6919 Bi-214 0.4608 0.5035 0.5164 0.5737 0.5318 Ce-141 Ce-144 0.07918 U 0.08939 U -0.009937 U -0.1375 U 0.1172 U Co-58 -0.02932 U -0.009195 U -0.03042 U -0.03246 U -0.0005492 U Co-60 0.01 158 U 0.01 19 U -0.02354 U -0.02374 U -0.01912 U Cr-51 0.2559 U Cs-134 -0.0127 U -0.00894 U -0.1005 U -0.02655 U -0.1758 U Cs-136 0.2064 U Cs-137 -0.01066 U -0.008989 U -0.002482 U -0.008189 U -0.0109 U Eu-152 Fe-59 -0.06984 U -0.01216 U 0.007269 U 0.04905 U -0.04284 U 1-131 1-132 K-40 17.96 16.82 17.7 17.17 18.09 Kr-85 4.902 La-140 Mn-54 -0.02544 U 0.004171 U -0.003301 U 0.00 1389 U 0.0305 U Nb-94 Nb-95 0.02291 U 0.02459 U 0.02227 U 0.0155 U -0.0 1982 U Np-239 0.2171 U Pb-212 0.8348 0.8682 0.9063 0.856 0.8503 Pb-214 0.5059 0.5852 0.5686 0.6723 0.5006 Ra-226 1.45310.9663 U 0.9852 U 1.057 Ru-103 0.0004445 U 0.01206 U -0.01361 U 0.01453 U -0.01 133 U Ru-106 0.1767 U 0.0825 U 0.08978 U 0.02719 U 0.2725 Sb-124 0.00946 U -0.009113 U 0.02365 U 0.01222 U -0.008539 U Sb-125 -0.11I U Se-75 Sn-113 Tl-202 TI-208 1.056 0.7994 0.6972 0.8608 0.8848 Y-88 Zn-65 -0.03116 U -0.04339 U -0.006756 U -0.08186 U 0.1571 U Zr-95 0.05184 U -0.02149 U 0.02034 U -0.04321 U -0.001765 U SOF 0.004 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 14 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe; MA Station'(Key) TS99.16 (3315) - TS99.17 (3316) - TS99.17 (3316) TS99.17 (3316) JTS99.18 (3317)
Sample ID TS99.16C TS99.17A TS99.17B i' TS99.17C ' TS99.18A Date Sampled 4/27/1999 4/27/1999 ; '4/27/1999 4/27/1999 14/27/1999 Ac-228 - 0.7593 : 0.8493 0.842 ,: - ,0.7683 0.7959 Ag-108m -0.008612 U -0.01 104 U 0.004121 U -0.01893 U -0.007541 U Ag-1 lOrn -0.04037 U -0.02102 U - -0.01581 U 0.01842 U ; ' -0.02413 U Am-241 0U OU OU OU OU Ba-133 -0.06773 U Ba-140 Bi-212 ' 1.16 0.6808 0.5385 Bi-214 0.4067 0.5394 0.5264 0.5116 0.5093 Ce-141 Ce-144 0.1215 U k -0.04184 U -0.1687 U 0.1074 U j- 0.04025 U
Co-58 -0.0178 U 0.02744 U -0.02528 U -0.0278 U -0.001347 U Co-60 0.01097 U -0.04023 U -0.008159 U -0.004033 U , -0.01548 U Cr-51 Cs-134 -0.02962 U -0.07194 U -0.05784 U -0.04822 U -0.01444 U Cs-136 0.5687 Cs-137 OU 0.02446 U 0.002815 U OU OU Eu-152 Fe-59 0.00677 U 0.04626 U -0.005567 U 0.006264 U -0.05951 U 1-131 0.04122 U 1-132 K-40 15.95 17.58 17.54 16.65 17.07 Kr-85 La-140 Mn-54 -0.01592 U 0.01582 U 0.03553 U -0.007486 U -0.00462 U Nb-94 Nb-95 0.02154 U 0.006445 U 0.02494 U -0.008606 U 0.02753 U Np-239 Pb-212 0.66631 0.8237 0.9875 0.9669 0.7723 Pb-214 0.4641 0.5227 0.4905 0.5867 0.616 Ra-226 1.408 1.671 2.073 1.124 Ru-103 0.002173 U 0.003918 U 0.02849 U 0.02944 -0.007543 U Ru-106 -0.176 U 0.1613 U -0.02337 U -0.06931 U 0.1995 U Sb-124 0.00113 U 0.001866 U 0.001262 U 0.03057 U -0.01556 U Sb-125 Se-75 Sn-113 T1-202 TI-208 - 0.5873 0.8013 ' 0.7678 0.9891 0.786 Y-88 Zn-65 -0.04876 U t 0.01988 U ; -0.1328 U 0.1094 U 0.1335 U Zr-95 -0.04473 U -0.02414 U 0.02716 U -0.001247 U 0.05453 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
a-Table 4 Page 15 of 28 Rad TBN Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key)' TS99.18 (3317) TS99.19 (3318) TS99.19 (3318) TS99.19 (3318) TS99.20 (3319)
Sample ID TS99.18B TS99.19A TS99.19B TS99.19C TS99.20A t Date Sampled 4/27/1999 . 4/27/1999 4/27/1999 {4/27/1999 J4/28/1999 Ac-228 0.97451 0.9112 0).8171 0.7015 0.9184 Ag-108m 0.01392 U 0.0004868 U -0.009815 U 0.005119 U. 0.0007164 U Ag-110m -0.02049 U -0.03073 U -0.03284 U 0.01461 U 0.0003387 U Am-241 0U OU OU OU OU Ba- 133 -0.04861 U Ba-140 Bi-212 0.9027 65.52 0.67151 0.5775 U 1.006 Bi-214 0.4561 0.5954 0.444 0.4745 0.5249 Ce-141 Ce-144 0.184 U 0.09043 U -0.02149 U -0. 1429 U -0.1662 U Co-58 0.01084 U -0.001141 U 0.01711 U -0.01335 U -0.01512 U Co-60 0.00835 U -0.03687 U 0.02118 U 0.008654 U -0.01206 U Cr-51 Cs-134 0.0584 U -0.06164 U -0.2605 U -0.01705 U -0.02122 U Cs-136 Cs-137 -0.03299 U -0.01978 U -0.002922 U -0.01367 U -0.02912 U Eu-152 Fe-59 -0.02477 U 0.01459 U 0.04605 U -0.02436 U -0.01249 U 1-131 0.01456 U 1-132 K-40 17.14 16.13 16.43 16.25 14.3 Kr-85 2.803 U 0.2984 U La-140 Mn-54 1-0.01036 U 0.01755 U -0.005355 U -0.005337 U -0.004517 U Nb-94 Nb-95 0.03131 U 0.01063 U 0.02956 U -0.03388 U -0.006476 U Np-239 -0.5138 U Pb-212 0.8467 0.8495 0.8301 0.7886 0.8168 Pb-214 0.4175 0.5834 0.5091 0.4688 0.5728 Ra-226 0.7937 U 1.451 Ru-103 -0.002375 U 0.00451 U 0.02867 0.002373 U 0.01154 U Ru-106 0.09132 U 0.04693 U 0.09705 U -0.07982 U -0.03881 U Sb-124 -0.0259 U OU -0.02097 U OU 0.006841 U Sb-125 Se-75 Sn- 113 TI-202 TI-208 0.8508 0.7876 0.6869 0.6769 Y-88 Zn-65 -0.09327 U 0.06273 U 10.06865 U -0.07622 U -0.006006 U Zr-95 0.05601 U 0.0645810.02619 U -0.03267 U 0.00717 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 16 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.20 (3319) -TS99.20 (3319) TS99.21 (3320) TS99.21 (3320) TS99.21 (3320)
Sample ID TS99.20B : TS99.20C' TS99.21A ' - TS99.21B - : TS99.21C Date Sampled 4/28/1999 4/28/1999 4/28/1999 4/2811999 4/28/1999 Ac-228 0.8755 0.9164 0.9454 0.9007 0.9333 Ag-108m 0.0226 U -0.006829 U -0.009065 U 0.00486 U 0.002567 U Ag-1 10m -0.01374 U -0.003494 U -0.01117 U -0.01482 U -0.03089 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 0.6283 1.005 0.4436 U 0.7393 Bi-214 0.5039 0.5374 0.5756 0.5902 0.4806 Ce-141 Ce-144 0.07879 U 0.06738 U 0.002037 U 0.01972 U 0.1032 U Co-58 0.03244 U -0.01297 U -0.03156 U 0.01481 U' -0.007576 U Co-60 -0.007763 U -0.03567 U 0.00803 U 0.008179 U 0.004027 U Cr-51 Cs-134 0.01092 U 0.006689 U 0.004517 U 0.009203 U -0.01359 U Cs-136 Cs-137 0.040171-0.01367 U -0.03047 U -0.03104 U -0.01627 U Eu-152 Fe-59 0.0005027 U 0.01231 U -0.03743 U -0.04447 U -0.02504 U 1-131 1-132 K-40 14.31 15.93 15.17 15.08 16.63 Kr-85 4.813 U -4.081 U -2.064 U La-140 Mn-54 0.02181 U 0.01222 U: -0.00423 U 0.0339 U 0.03055 U Nb-94 )
Nb-95 -0.006478 U -0.01436 U -0.01891 U 0.01592 U -0.02029 U Np-239 -0.5165 U -0.5587 U I Pb-212 0.69 0.7456 t 0.8445 0.942 0.931 Pb-214 0.6048 0.549 - ' 0.6161 0.4127 0.5572 Ra-226 , 1.27 0.8674 U 1.28 Ru-103 -0.02944 U 0.02919 0.006741 U ' 0.008195 U -0.01884 U Ru-106 0.04447 U 0.1362 U 0.138 U 0.2811 U -0.04522 U Sb-124 -0.01081 U 0.02882 U -0.007454 U 0.0715 0.0346 U Sb-125 -0.1303 U Se-75 Sn-I 13 Tl-202 T1-208 0.7009 0.7665 0.8217 0.8775 0.8178 Y-88 Zn-65 -0.1519 U -0.08208 U -0.07028 U -0.05831 U -0.03313 U Zr-95 0.05402 U -0.005656 U 0.04488 U 0.02174 U 0.06708 SOF 0.003 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 17 of28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.22 (3321) TS99.22 (3321) TS99.22 (3321) TS99.23 (3322) TS99.23 (3322)
Sample ID TS99.22A . TS99.22B TS99.22C .. TS99.23A TS99.23B Date Sampled 4/28/1999 4/28/1999 4/28/1999 - 4/28/1999 14/28/1999 Ac-228 0.8148 0.841 0.8728 1.046 1.011 Ag-108m -0.001111 U 0.0006497 U 0.009781 U 0.006314 U 0.01893 U Ag-I 10mi -0.00126 U -0.02014 U -0.01248 U 0.001985 U -0.0287 U Am-241 OU 0U OU OU 0U Ba-133 Ba-140 0.07874 U Bi-212 1.248 0.6754 0.8852 0.9709 0.8925 Bi-214 0.4673 0.4715 0.4602 0.5427 0.4547 Ce-141 Ce-144 0.1489 U -0.1331 U -0.04732 U -0.1165 U -0.06632 U Co-58 -0.00468 U -0.02585 U -0.01068 U 0.006828 U -0.02425 U Co-60 -0.002885 U -0.02112 U -0.0003135 U 0.04319 0.003961 U Cr-51 Cs-134 -0.01052 U 0.01266 U 0.004115 U -0.008834 U 0.002228 U Cs-136 Cs-137 0.00258 U -0.01933 U 0.003161 U -0.01845 U 0.01913 U Eu-152 0.05679 U 0.2922 U Fe-59 -0.06954 U -0.03852 U OU -0.06089 U 0.04915 U 1-131 1-132 K-40 15.03 16.74 15.33 16.84 15.68 Kr-85 La-140 Mn-54 0.01536 U 0.03045 U -0.002055 U 0.02178 U -0.01197 U Nb-94 Nb-95 -0.01451 U -0.02682 U -0.01983 U -0.009466 U -0.009233 U Np-239 Pb-212 0.9531 0.9521 0.862 1.097 0.9497 Pb-214 0.585 0.5496 0.4851 0.5608 0.5757 Ra-226 2.142 1.843 1.497 1.87 0.7665 U Ru-103 -0.01535 U -0.002952 U 0.003953 U 0.008701 U -0.009422 U Ru-106 0.06576 U 0.03713 U 0.0419 U 0.1799 U 0.04538 U Sb-124 -0.008085 U 0.02223 U 0.01 13 U -0.02184 U -0.07285 U Sb-125 0.105 U Se-75 Sn-113 TI-202 TI-208 0.8808 0.8367 0.8132 1.165 0.8955 Y-88 Zn-65 0.1223 U 0.07755 U 0.02203 U 0.1351 U -0.05307 U Zr-95 0.05327 0.01788 U 0.01591 U -0.004197 U 0.01929 U SOF £ ______________ J. .L .1 0.009 £ U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 18 of28 Rad TBN Soil (pCitg)
Yankee Nuclear Power Station Rowe, MA Station (Key) }TS99.23 (3322) TS99.24 (3323) TS99.24 (3323) TS99.24 (3323) TS99.25 (3324)'
Sample ID TS99.23C TS99.24A TS99.24B TS99.24C TS99.25A Date Sampled 4/28/1999 - ;[._ 4129/1999 14/29/1999 - 4/29/1999 ' 14/29/1999 Ac-228 0.915 0.811 0.8509 * . 0.8341 0.4971 Ag-108m 0.01294 U 0.02558 U -0.001113 U -0.01515 U 0.01601 U Ag-110m -0.01012 U 0.01316 U f: 0.03295 U ' 0.0151 U 0.003419 U Am-241 0U 0U OU OU OU Ba-133 Ba-140 Bi-212 0.5819 1.448 0.4999 U , 0.7153 0.8389 Bi-214 0.4673 0.4847 f 0.4662 * - 0.4686 0.4108 Ce-141 Ce-144 -0.07638 U 0.116 U -0.01532 U -0.1984 U 0.108 U :
Co-58 0.02388 U : -0.02704 U 0.009411 U 0.004992 U 0.002887 U Co-60 0.003879 U 0.01154 U -0.002785 U -0.003867 U -0.02818 U Cr-5I Cs-134 1-0.07215 U -0.04819 U ' 0.04507 U -0.08573 U 0.05107 U Cs-136 Cs-137 -0.02139 U -0.00282 U -0.005074 U -0.02932 U -0.0111 U ' '
Eu-152 Fe-59 -0.0168 U -0.006267 U -0.02879 U 0.002422 U -0.03934 U 1-131 1-132 K-40 11.83 15.18 12.53 13.5 10.26 Kr-85 La-140 Mn-54 0.01854 U -0.02447 U' 0.01086 U 0.01721 U -0.02219 U Nb-94 Nb-95 -0.03975 U 0.02195 U -0.01684 U -0.01489 U 0.0002871 U Np-239 Pb-212 0.8332 0.823 I- I 0.8507 0.7785 0.5881 Pb-214 0.4387 0.5762 :' 0.5424 0.5384 I0.3966 Ra-226 1.41 . 1.094 1.297 0.8917 U 1;393 Ru-103 0.002017 U. , 0.007036 U -0.012 U : 0.003978 U ' 0.009663 U Ru-106 -0.02235 U 0.2821 0.1079 U O.033 U -' -0.06257 U Sb-124 0.009699 U OU 0.007207 U -0.0223 U -0.02709 U Sb-125 : .
Se-75 Sn-113 TI-202 0.01681 U TI-208 0.704 0.6853 i 0.7011 . 0.8109 ).3389 Y-88 Zn-65 -0.02003 U 0.1058 U -0.08957 U -' 0.09884 U -0.0385 U Zr-95 0.01055 U i ' 0.002364 U 9 ; -0.0281 U -0.006176 U -0.009398 U SOF 0.004 i U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 19of28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA K.-,
Station (Key) TS99.25 (3324) TS99.25 (3324) TS99.26 (3325) TS99.26 (3325) TS99.26 (3325)
Sample ID TS99.25B : TS99.25C TS99.26A TS99.26B TS99.26C Date Sampled 4/29/1999 4/29/1999 4/29/1999 . l 4/29/1999 4/29/1999 1 Ac-228 - 10.7127 0.7959 0.6659 0.6593 0.654 Ag-108m -0.0009218 U -0.002082 U -0.01288 U 0.005393 U -0.008407 U Ag-110mi -0.008572 U -0.0192 U 0.002958 U -0.007872 U -0.01875 U Am-241 0U 0U OU OU OU Ba-133 Ba-140 Bi-212 0.4207 U 0.5359 0.8526 Bi-214 0.4124 0.4377 0.3617 0.3547 0.3685 Ce- 141 Ce- 144 -0.05949 U 0.05638 U 0.04721 U -0.05114 U 0.004026 U Co-58 -0.00891 U -0.00915 U -0.01557 U 0.01235 U 0.008529 U Co-60 0.01165 U 0.01 169 U 0.0154 U 0.01278 U -0.04329 U Cr-51 Cs-134 0.02523 U -0.05887 U -0.05357 U 0.009018 U -0.0464 U Cs-136 Cs-137 -0.01873 U -0.0188 U -0.00554 U 0.01654 U -0.008136 U Eu-152 0.3966 U Fe-59 -0.03794 U -0.03969 U 0.02267 U -0.05923 U 0.04524 U 1-131 1-132 K-40 11.26 11.97 10.97 11.76 11.49 Kr-85 La-140 Mn-54 0.01125 U -0.007985 U 0.007382 U 0.027581-0.000174 U Nb-94 Nb-95 -0.02574 U 0.02163 U 0.043471-0.01065 U 0.001412 U Np-239 Pb-212 0.6967 0.636 0.6261 0.6533 0.6836 Pb-214 0.4149 0.4232 0.4923 0.4248 0.4702 Ra-226 1.199 1.143 0.7118 U Ru-103 -0.0005481 U -0.02605 U 0.006204 U 0.01272 U -0.003419 U Ru-106 -0.02235 U 0.2243 U 0.0643 U -0.1613 U 0.1587 U Sb- 124 0.02767 U 0.009992 U OU OU -0.008902 U Sb-125 -0.1016 U Se-75 0.0437 U Sn-113 1.057 U TI-202 Tl-208 0.4174 0.5524 0.5566 Y-88 Zn-65 -0.08778 U 0. 106 U 0.04016 U 0.006932 U -0.048 U Zr-95 -0.04198 U -0.02539 U 0.03408 U 0.03959 U 0.01998 U SOF I I I .5.
0.001 .5.
U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 20 of 28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.27 (3326) TS99.27 (3326) TS99.27 (3326) TS99.28 (3327) TS99.28 (3327)
Sample ID TS99.27A TS99.27B TS99.27C TS99.28A TS99.28B - -
Date Sampled 4t29/1999 - 4/29/1999 . 4129/1999 -55/1999 5/5/1999 Ac-228 0.6291 0.6623 -- 0.646 . 0.4483 0.5864 Ag-108m 0.001088 U 0.02458 -0.02484 U -0.01875 U 0.01172 U Ag-110mn -0.003879 U OU -0.005098 U -0.01757 U -0.02176 U -
Am-241 OU OU OU OU OU Ba-133 0.03402 0.02241 U Ba-140 Bi-212 0.8287 0.5582 0.6656 0.4114 U Bi-214 0.3504 0.3354 0.3376 0.38 0.3391 Ce-141 Ce-144 0.1059 U -0.003025 U 0.08584 U 0.06952 U 0.07346 U Co-58 -0.002879 U 0.003258 U -0.008563 U" -0.006222 U -0.001984 U Co-60 -0.003979 U -0.00319 U -0.01997 U -0.01132 U -0.01291 U Cr-51 ,
Cs-134 0.021831-0.03053 U -0.02183 U 0.002304 U -0.04463 U Cs-136 0.133 U Cs-137 -0.005483 U 0.007733 U -0.01 101 U -0.01697 U 0.002834 U Eu-152 Fe-59 -0.09862 U 0.07809 0.006596 U 0.01274 U 0.02515 U 1-131 1-132 K-40 12.53 10.04 I ,: 11.14 7.537 9.412 Kr-85 La-140 0.8634 U Mn-54 -0.01605 U 0.01478 U 0.02578 U 0.005631 U 0.005183 U Nb-94 Nb-95 0.02899 U 0.04541 0.002319 U 0.002699 U 0.01 136 U Np-239 3.353 U Pb-212 0.5385 0.4458 0.5921 0.5882 0.4552 Pb-214 0.4031 0.3884 0.4936 0.3401 0.3819 Ra-226 1.482 0.703 U 1.363 Ru-103 0.02959 -0.00183 U OU 0.01201 U 0.009188 U Ru-106 0.2016 U ' ' 0.04542 U -0.02302 U -0.06973 U 0.1175 U Sb-124 -0.009018 U 0.01 148 U 0.0181 U 0.008781 U 0.03458 U Sb-125 I 0.04729 U Se-75 Sn-113 TI-202 0.009738 U Tl-208 ! 1:- 0.479 , .* 0.5066 0.3833 Y-88 Zn-65 -0.05069 U -0.006308 U: 0.01042 U 0.0453 U 0.09833 U Zr-95 0.007368 U 0.03479 U ~ - 0.02312 U -0.01868 U 0.01823 U SOF 0.003 0.003 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed I
Table 4 Page 21 of 28 Rad TBN-01 -- Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.29 (3328) TS99.29 (3328) TS99.29 (3328) TS99.30 (3329) TS99.30 (3329)
Sample ID TS99.29A TS99.29B TS99.29C TS99.30A TS99.30B Date Sampled 5/10/1999 - 5/10/1999 5/10/1999 5/10/1999 5/10/1999 Ac-228 0.6523 0.6513 0.715 0.7831 0.6425 Ag-108m 0.004878 U 0.005792 U 0.001404 U -0.003403 U -0.01 151 U Ag- 10m -0.01511 U -0.01026 U 0.008486 U 0.000321 U 0.03256 U Am-241 OU OU OU OU OU Ba-133 Ba-140 Bi-212 0.7433 0.4137 U 0.8735 1.194 0.3802 U Bi-214 0.3855 0.4156 0.4772 0.4145 0.3211 Ce-141 Ce-144 0.04849 U -0.04925 U -0.07288 U -0.1668 U -0.04902 U Co-58 -0.004854 U -0.01422 U -0.03096 U -0.01528 U -0.01336 U Co-60 -0.007195 U 0.01265 U 0.01495 U -0.006334 U 0.003007 U Cr-51 Cs-134 0.001686 U -0.09396 U 0.05276 U -0.05219 U -0.1709 U Cs-136 Cs-137 -0.0006742 U 0.008011 U 0.007738 U -0.03425 U -0.01572 U Eu-152 Fe-59 0.03004 U 0.04674 U 0.01717 U -0.01225 U -0.005814 U 1-131 1-132 K-40 11.04 13.07 12.58 14.69 14.84 Kr-85 La-140 Mn-54 -0.02329 U -0.003476 U -0.002359 U 0.02085 U -0.001863 U Nb-94 Nb-95 0.02538 U -0.00176 U -0.001 109 U 0.01046 U 0 .03278 Np-239 Pb-212 0.693 0.69 0.7072 0.692 0.7308 Pb-214 0.408 0.3096 0.4218 0.4896 0.4206 Ra-226 1.615 1.373 Ru-103 0.00562 U -0.009495 U 0.002938 U 0.01221 U -0.01 173 U Ru-106 0.06705 U 0.02617 U -0.0955 U -0.1092 U -0.1772 U Sb- 124 0.001794 U 0.004672 U -0.03434 U 0.01286 U 0.01279 U Sb-125 Se-75 Sn-113 Tl-202 TI-208 0.5639 0.6326 0.5145 0.6939 0.6565 Y-88 Zn-65 0.08342 U 0.03569 U -0.148 U 0.1187 U -0.09284 U Zr-95 0.04601 U 0.0256 U -0.03829 U -0.02967 U 0.01341 U SOF .I. .L 1 1 1 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 22 of 28 Rad TBN-01 - Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.30 (3329) 1TS99.31 (3330) TS99.31 (3330)' TS99.32 (3331) TS99.37 (3336).
Sample ID TS99.30C TS99.31A - TS99.31 B : 1TS99.32A TS99.37A Date Sampled 5/10/1999 ! 5/10/1999 ' 5/1011999 /51i0/1999 . 5/17/1999 Ac-228 0.7457 0.8241 0.7868 0.5128 1.075 Ag-108m -0.028 U 0.003819 U - 0.01714 U 0.00167 U 0.006132 U Ag-110m -0.009905 U 0.001261 U -0.01471 U 0.006412 U 0.005512 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 1.062 1.108 1.213 Bi-214 0.3752 0.3643 0.3587 0.3399 0.56 Ce-141 0.02263 U 0.03263 U Ce-144 0.0943 U 0.04745 U -0.001925 U 0.007129 U -0.1435 U Co-58 -0.01832 U. 0.005463 U -0.01443 U: 0.002929 U. 0.006657 U Co-60 -0.0114 U -0.02108 U -0.01518 U -0.01054 U -0.02314 U -
Cr-51 Cs-134 -0.1128U 0.01052 U 0.006405 U 0.008644 U -0.01443 U Cs-136 0.3193 Cs-137 0.005244 U 0.002582 U : -0.01571 U -0.002425 U 0.01597 U Eu-152 0.5628 U Fe-59 . I -0.01165 U -0.005798 U 0.02354 U: -0.05437 U -0.04728 U I-131 1-132 K-40 14.74 16.54 15.83 13.77 16.94 Kr-85 10.98 La-140 Mn-54 0.02035 U -0.01445 U -0.006662 U 0.001233 U 0.01893 U Nb-94 Nb-95 0.007768 U -0.01101 U -0.009908 U -0.009386 U -0.0234 U Np-239 -0.5268 U Pb-212 0.7937 0.912 0.8453 0.5636 1.155 Pb-214 0.4044 -~ 0.5014 0.4717 0.3947 i 0.5099 Ra-226 1.571 1.92 1.097 1.281 Ru-103 -0.0002026 U 0.01616 U - -0.01353 U 0.002084 U -0.008431 U Ru-106 0.08694 U 0.2571 U -0.1299 U -0.002841 U 0.1 166 U Sb-124 0.009312 U 0.02119 U 7 OU -0.002168 U 0.02126 U Sb-125 Se-75 Sn-113 i TI-202 TI-208 0.7623 0.9264 0.7844 0.6459 0.7804 Y-88 Zn-65 -0.09896 U -0.05164 U -I0.01042 U -0.01818 U . -0.1289 U Zr-95 0.03133 U 0.01 164 U ; ; 0.003606 U 0.01584 U : - 0.04089 U l
SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 23 of 28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.37 (3336) -TS99.37 (3336) TS99.38 (3337) TS99.39 (3338) TS99.39 (3338)
Sample ID TS99.37B TS99.37C TS99.38A TS99.39A TS99.39B Date Sampled 5/17/1999 15/17/1999 5/17/1999 5/18/1999 . 5/18/1999 Ac-228 0.8528 1.064 1.103 0.8441 0.8507 Ag-108m -0.02329 U -0.00205 U 0.008281 U -0.01376 U 0.00264 U Ag-110m 0.01005 U 0.01901 U 0.03462 U -0.006733 U 0.0186 U Am-241 0U 0U OU OU OU Ba-133 Ba-140 Bi-212 1.09 0.8364 1.123 0.8507 0.9269 Bi-214 0.4376 0.4964 0.5509 0.504 0.427 Ce-141 Ce-144 0.2148 U -0.07527 U -0.365 U -0.1447 U -0.01639 U Co-58 0.01573 U 0.0007939 U -0.004247 U -0.007284 U -0.009254 U Co-60 -0.00942 U -0.009237 U -0.003842 U 0.02912 U 0.02814 U Cr-5I Cs-134 0.006297 U 0.02053 U -0.03515 U -0.1075 U -0.162 U Cs-136 Cs-137 0.002655 U 0.0238 U 0.02917 U 0.02763 U -0.005273 U Eu-152 0.2914 U Fe-59 -0.04581 U -0.01175 U 0.005893 U -0.06501 U 0.001 145 U 1-131 1-132 K-40 16.92 17.37 18.11 13.76 17.15 Kr-85 La-140 Mn-54 0.01361 U 0.01422 U 0.007006 U 0.006423 U -0.01014 U Nb-94 Nb-95 0.02625 U 0.01593 U -0.008625 U 0.01017 U 0.01877 U Np-239 Pb-212 0.9953 0.9345 1.004 0.9706 0.9012 Pb-214 0.5116 0.4821 0.6133 0.4665 0.5577 Ra-226 0.9927 U 0.764 U 1.362 0.9667 0.9897 Ru-103 -0.00 1594 U -0.01133 U -0.002871 U 0.006785 U 0.03549 Ru-106 -0.04057 U -0.06576 U 0.2858 U -0.1457 U -0.0212 U Sb-124 -0.001907 U 0.01409 U 0.001767 U 0.005571 U -0.01655 U Sb-125 -0.105 U Se-75 Sn-113 TI-202 TI-208 0.7895 1.007 0.951 0.6582 0.7708 Y-88 Zn-65 0.001 191 U -0.1386 U -0.06915 U -0.1125 U -0.1213 U Zr-95 0.01538 U 0.05883 0.05234 U 0.01457 U 0.02852 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 24 of 28 Rad TBN Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) 1TS99.39 (3338) ; TS99.40 (3339) TS99.40 (3339) . *1TS99.40 (3339) TS99.41 (3340)
Sample ID _ TS99.39C TS99.40A TS99.40B - TS99.40C TS99.41A Date Sampled 5/18/1999 5/27/1999 15/27/1999 5/27/1999 , 5/26/1999 Ac-228 - 0.8271 0.9368 - 10.8375 7 - 0.7442 0.7802 Ag-108m -0.00817 U - - -0.007878 U -0.01656 U 0.01344 U 0.01766 U Ag-110m - -0.05226 U 0.002296 U ; 0.03929 U -0.01275 U 0.004943 U Am-241 0U 0U OU OU OU Ba-133 Ba-140 Bi-212 0.6233 0.6878 0.7906 0.9341 Bi-214 0.4794 0.4097 0.5133 0.5057 0.398 Ce-141 Ce-144 -0.06218 U -0.02765 U 0.06761 U -0.1547 U - -0.2378 U Co-58 -0.01035 U -0.0213 U : -0.0216 U -0.01252 U 0.005347 U Co-60 0.04087 U 0.007798 U -0.000000001871 U -0.01131 U ! -0.01547 U Cr-51 Cs-134 0.02856 U 0.004789 U -0.1321 U -0.154 U a . : -0.0913 U Cs-136 0.03941 U Cs-137 0.071791-0.0101 U 0.002708 U 0.0156 U 0.01326 U Eu-152 Fe-59 -0.01 149 U -0.008649 U -0.04828 U 0.005795 U -0.03869 U 1-131 1-132 K-40 15.83 15.2 I, 16.25 15.22 15.67 Kr-85 La-140 Mn-54 -0.01252 U 0.001 094 U 0.01156 U .10.008459 U 0.001096 U Nb-94 Nb-95 0.007723 U -0.0098 U 0.007279 U 0.01679 U 0.009662 U Np-239 0.1639 U Pb-212 0.8802 0.9325 0.9028 0.739 0.6788 Pb-214 0.4377 - 0.65 0.5953 0.4914 0.4772 Ra-226 1.628 0.9801 U 1.045 U I 1.115 1.238 Ru-103 -0.003604 U 0.006878 U - -0.02302 U -0.02934 U - 0.00908 U Ru-106 -0.3191 U 0.3123 -0.04491 U 0.0207 U 0.1785 U Sb-124 -0.004584 U 0.0323 U I OU!' 0.02963 U ; -0.005042 U Sb-125 0.3107 U Se-75 Sn-1 13 TI-202 TI-208 0.7515 .0.7401 0.9036 . 0.9776 0.681 Y-88 Zn-65 -0.07475 U . 0.03311 U 0.1554 U -0.05194 U. -0.03151 U Zr-95 0.03039 U 0. -0.04232 U 0.0 0.01205 U 0.05073 U 0.08112 SOF 0.06 0.005 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 25 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.41 (3340) TS99.41 (3340) TS99.42 (3341) TS99.43 (3342) - T99.43 (3342)
Sample ID TS99.41B TS99.41C TS99.42A TS99.43A TS99.43B Date Sampled 5/26/1999 5/27/1999 5/26/1999 512711999 15/27/1999 Ac-228 0.8127 0.7755 0.8125 0.742 0.6352 Ag-108m 0.006014 U 0.0004455 U -0.002617 U 0.007253 U 0.001635 U Ag-1 10m 0.03395 U -0.02492 U -0.003092 U -0.006176 U 0.01055 U Am-241 OU OU OU OU 0U Ba-133 Ba-140 Bi-212 0.9241 0.6881 0.7258 Bi-214 0.4681 0.403 ).4188 0.4758 0.4599 Ce-141 Ce- 144 -0.07841 U -0.02978 U -0.1303 U 0.01075 U -0.1067 U Co-58 -0.00964 U 0.001901 U 0.004492 U 0.003591 U 0.01536 U Co-60 0.003947 U -0.01126 U 0.00734 U -0.000000003643 U -0.03006 U Cr-51 Cs-134 -0.1349 U -0.2246 U -0.02289 U 0.0118 U 0.05654 U Cs-136 Cs-137 -0.002636 U -0.02302 U -0.007596 U 0.02743 U 0.007768 U Eu- 152 0.2051 U Fe-59 -0.01915 U 0.03101 U -0.07396 U -0.03i53 U -0.006204 U 1-131 1-132 K-40 16.54 14.24 13.98 11.34 9.1611 Kr-85 La-140 1.402 U Mn-54 -0.009683 U -0.009298 U -0.0134 U 0.001081 U 0.007481 U Nb-94 0.03751 Nb-95 -0.01153 U 10.005723 U 0.01279 U 0.01302 U 0.01472 U Np-239 Pb-212 0.7502 0.7391 0.7949 0.6693 0.6593 Pb-214 0.4928 0.4398 0.5363 0.416 0D.4592 Ra-226 0.956 0.9009 1.341 Ru-103 -0.03123 U -0.01177 U -0.004758 U -0.0164 U 0.005235 U Ru-106 0.1324 U 0.2596 U 0.1471 U -0.03704 U -0.06497 U Sb-124 0.01 123 U 0.02248 U 0.02721 U 0.02423 U 0.008512 U Sb-125 Se-75 Sn-113 TI-202 TI-208 0.6535 0.7421 0.6972 0.5384 0.6451 Y-88 Zn-65 0.07816 U -0.1374 U -0.007442 U 0.01298 U -0.1255 U Zr-95 -0.008124 U -0.01025 U 0.04271 U 0.0189 U 0.01305 U SOF - I I 0.004 I U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 26 of 28 Rad TBN-01 - Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.43 (3342) i TS99.44 (3343) TS99.44(3343) TS99.44 (3343) TS99.47 (3345)
Sample ID TS99.43C TS99.44A , TS99.44B '; TS99.44C TS99.47A Date Sampled 5/27/1999 J6/i/1999 - 61 61l/1999 ' 611/1999 6/2/1999 Ac-228 , 0.9596 0.6795 . \ 0.8018 0.7001 0.8486 Ag-108m 0.01001 U 0.007983 U -0.005732 U ' ' -0.00361 U 0.00798 U Ag-IlOin 0.03148 U, 0.03712 -0.01038 U 0.01469 U -0.008066 U Am-241 0U OU OU 0U 0U Ba-133 Ba-140 Bi-212 0.7728 0.7804 Bi-214 0.5119 0.4831 ! , 0.483 0.4059 0.4306 Ce-141 ;
Ce-144 0.04346 U -0.07485 U 0.0684 U 0.1914 U 0.1244 U Co-58 -0.00874 U -0.005 835 U 0.0002666 U : -0.006113 U -0.01325 U Co-60 -0.03594 U -0.003837 U -0.01569 U -0.006327 U -0.02012 U Cr-51 i Cs-134 -0.1696 U -0.001222 U -0.09466 U 0.05626 U 0.02572 U Cs-136 Cs-137 0.002601 U 0.04237 0.01864 U 0.0131 U -0.01588 U*'
i Eu-152 0.1519 U Fe-59 -0.1 179 U 0.01767 U -0.00296 U -0.05248 U -0.01176 U -
1-131 1-132 K-40 15.83 15.58 15.94 14.69 13.84 Kr-85 La-140 Mn-54 0.02831 U -0.0298 U -0.001623 U 0.009519 U 0.001076 U Nb-94 Nb-95 -0.00466 U -0.01395 U. 0.02065 U 0.007184 U 0.02051 U Np-239 Pb-212 1.028 0.704 0.7936 0.7439 0.7956 Pb-214 0.4957 0.4246 0.5316 0.4507 0.4559 Ra-226 1.531 Ru-103 0.01491 U 0.006149 U 0.002433 U -0.01507 U 0.01555 U Ru-106 -0.1523 U 0.1149 U -0.00302 U 0.0252 U OU Sb-124 0.01466 U 0.003531 U 0.02839 U 0.01544 U OU Sb-125 -0.02469 U Se-75 Sn-113 TI-202 Tl-208 0.8577 0.6569 0.7118 0.5869 0.823 Y-88 Zn-65 0.1088 U -0.04354 U -0.06644 U -0.1372 U' -0.05038 U Zr-95 -0.003747 U 0.01629 U 0. 0 0.01911 U . -0.002688 U -0.02125 U SOF 0.003 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 27 of 28 Rad TBN-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) TS99.47 (3345) TS99.47 (3345) TS99.48 (3346) TS99.48 (3346) TS99.48 (3346) 1 Sample ID TS99.47B TS99.47C TS99.48A TS99.48B TS99.48C Date Sampled 6/2/1999 6/2/1999 6/2/1999 6/3/1999 6/3/1999 Ac-228 0.737 0.7763 0.6536 0.8907 0.61 Ag-108m -0.01235 U 0.001992 U 0.008457 U 0.02188 U -0.004379 U Ag-i 1Orn 0.01615 U -0.01535 U -0.01541 U -0.0006766 U -0.02576 U Am-241 0U OU OU OU OU Ba-133 Ba-140 Bi-212 1.104 0.5905 0.5608 1.041 0.712 Bi-214 0.4702 0.3688 0.383 0.3881 0.4174 Ce-141 Ce-144 -0.135 U -0.03773 U -0.06718 U 0.1039 U -0.0009818 U Co-58 0.01039 U 0.01431 U 0.003678 U 0.002468 U 0.000669 U Co-60 0.01968 U -0.02653 U 0.007906 U -0.003664 U 0.01103 U Cr-51 Cs-134 0.01976 U -0.02578 U 0.005192 U -0.05167 U -0.0507 U Cs-136 Cs-137 -0.01737 U OU 0.005455 U -0.01052 U 0.01873 U Eu-152 -0.05783 U Fe-59 0.03005 U 0.02285 U 0.03062 U -0.01848 U -0.01781 U 1-131 1-132 K-40 13.63 13.62 10.88 13.55 12 . ,
Kr-85 La-140 Mn-54 0.006597 U -0.001492 U 0.02554 U -0.002398 U 0.03072 Nb-94 Nb-95 0.00552 U 0.01549 U 0.006873 U 0.0228 U -0.00562 U Np-239 Pb-212 ).7477 0.7936 0.6657 0.8767 0.762 Pb-214 ).4244 0.3976 0.4761 0.4787 0.5022 Ra-226 0.7153 U 0.9203 U 0.8011 U Ru-103 0.002301 U 0.004657 U -0.006402 U -0.009645 U -0.0002066 U Ru-106 -0.1345 U OU -0.1494 U -0.06904 U -0.1109 U Sb-124 -0.01201 U 0.002664 U 0.007934 U 0.0193 U -0.05698 U Sb-125 Se-75 Sn-113 TI-202 TI-208 ).8209 0.6891 0.5371 0.8663 0.5605 Y-88 0.02016 U Zn-65 -0.01841 U -0.00578 U 0.09767 U -0.0303 U -0.1194 U Zr-95 -0.00693 U -0.03029 U 0.0183 U 0.07447 0.02054 U SOF I ________________ .L I 0.001 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 28 of 28 Rad TBN-01 -- Soil (pCi/g) -,
- Yankee Nuclear Power Station Rowe, MA
. -i . I Station (Key) TS99.49 (3347) TS99.49 (3347) TS99.49 (3347) . .
I Sample ID TS99.49A ; TS99.49B 1TS99.49C Date Sampled 66/3/1999 9/3/1999 i Ac-228 0.8877 l:; 0.8251 0.9346 Ag-108m I 0.02402 -0.005608 U : -0.0006752 U Ag- lOnm -0.02278 U 0.02681U t -0.02863 U Am-241 OU ' OUI .. OU _
, -, ,; A Ba-133 Ba-140 I
- n. uII .
Bi-212 0.7311 0.6321 Bi-214 0.4685 0.4932 0.4459 I Ce-141 I I I
I Ce-144 0.04331 U 0.03011U. 0.05528 U Co-58 -0.02357 U -0.03709 U -0.02678 U Co-60 -0.003938 U -0.00293 U 0.01138 U Cr-51 ! f Cs-134 -0.002002 U 0.04558 U' 0.03033 U Cs-136 i I Cs-137 -0.01375 U -0.02356- UU -0.04705 U Eu-152 Fe-59 -0.05189 U -0.02207 U 0.04366 U 1-131 1-132 K-40 13.95 14.56 13.43 Kr-85 , .
La-140 Mn-54 -0.01135 U -0.004638 U 0.004122 U Nb-94 Nb-95 0.003418 U 0.01837 U , 0.02574 U Np-239 -1.014 U Pb-212 0.6506 ).7138 0.8803 Pb-214 0.5429 .. .( : aI).4612 0.4663 Ra-226 1.189 1.792 0.7628 U Ru-103 -0.01277 U 0.005474 U 0.006794 U Ru-106 0.04539 U 0.1313 U -0.1748 U.
Sb-124 0.006361';U 0.01961 U: -0.007343 U Sb-125 Se-75 Sn-1 13 TI-202 11-208 0.6176 0.7757 0.7409 Y-88 Zn-65 -0.08759 U 0.01163 U -0.1513 U:
Zr-95 0.05071 U- -0.02537 U 0.01267 U SOF 0.003 t
t : .
I . i .- , . .
U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
TBN-01 Remediated Areas Location Sample Date GLV Disposition Nuclide Conc. Fraction of DCGLSOF
___________________________________ SOF DsoionNcde (pCilgm) DCGL _____
TB Floor Drain Excavation TBOOI.4 5-Mar-98 ND AB TB Floor Drain Excavation TBOO1.5 5-Mar-98 ND AB TB Floor Drain Excavation TBOOI.6 5-Mar-98 ND AB TB Floor Drain Excavation TBOO1.7 5-Mar-98 ND AB TB Floor Drain Excavation TBOO1.8 5-Mar-98 ND AB TB Floor Drain Excavation TBOO1.88 5-Mar-98 ND AB TB Floor Drain Excavation TB0OI.9 5-Mar-98 ND AB - _____
TB Floor Drain Excavation TB001.10 5-Mar-98 ND AB .
TB Floor Drain Excavation TBOO1;1 I 5-Mar-98 ND AB- - . .
TB Floor Drain Excavation TBO01.12 9-Mar ND-- AB - -
TB Floor Drain Excavation TB0O1.13 9-Mar-98 ND AB TB Floor Drain Excavation TBOO1.14 9-Mar-98 ND AB TB Floor Drain Excavation TBOO1.15 9-Mar-98 ND AB TB Floor Drain Excavation TBOOI.16 10-Mar-98 ND AB,,
TB Floor Drain Excavation TBOO1.17 10-Mar-98 ND AB TB Floor Drain Excavation TBOOI.18 11-Mar-98 ND AB _ _
TB Floor Drain Excavation TBOO1.19 11-Mar-98 ND AB TB Floor Drain Excavation TBOO1.199 11-Mar-98 ND AB TB Floor Drain Excavation TBOO1.20 12-Mar-98 ND AB TB Floor Drain Excavation TBOO1.21 12-Mar-98 ND AB TB Pedestal #4 TBOOI.22A 12-Aug-98 Co-60 1.43E 0.030
. . ..- . _ 25.740 FR Cs-134 3.20E-01 0.048 16.417 Cs-137 2.OOE+02 16.340 TB Pedestal #4 TBOO1.22B 12-Aug-98 4.640 FR Cs-I 37 3.62E+01 2.958 3.061 TBOO1.22B 12-Aug-98 Sr-90 2.76E-01 0.103 TB Pedestal #4 TBOO1.23A 13-Aug-98 ND AL _
TB Pedestal #4 TBOO1.23B 13-Aug-98 ND AL TB Pedestal #4 TBOOI.24A 12-Aug-98 ND AL TB Pedestal #4 TBOO1.25A 13-Aug-98 0.022 AL Cs-1 37 1.692E-01 0.014 0.014 TB Pedestal #4 TBOO1.25B 13-Aug-98 ND AL TB Pedestal #4 TBOO1.26B 13-Aug-98 ND AL TB Col #4 steam cut area comp o"- 14" TBOOI.28 3-May-99 1.305 Cs-137 1.018E+01 0.832 0.832 TB Col #4 steam cut area comp 0" - 14" TBOOI.29 4-May-99 1.449 Cs-137 I1.130E+01 0.923 0.923
. Page 1 of 2
( (,
(7 TBN-01
(
TB Col #4 steam cut area S comp TBOO1.31 4-May-99 ND TB Col #4 steam cut area E comp TBO01.32 4-May-99 3.925 Cs-134 7.456E-02 0.011 2.500
. Cs-137 3.046E+01 2.489 TB Col #4 steam cut area W comp TBOO1.33 4-May-99 0.009 Cs-1 37 7.033E-02 0.006 0.006 TB Col #4 steam cut area NE comp o0 - 14" TB0OI.34 11-May-99 Co-60 1.522E-01 0.031 23.390 Cs-134 1.690E-01 0.025 14.893 Cs-137 1.816E+02 14.837 TB Col #4 steam cut area SE comp o0 - 14" TB001.35 11-May-99 ND TB Col #4 steam cut area N comp o" - 30" UG005DUFC 17-May-99 ND TB Heating & Boiler Room TBOO1.27A 17-Aug-98 Co-60 2.000E-01 0.041 0.670 AL Cs-134 1.580E-01 0.024 0.415 Cs-1 37 4.290E+00 0.350 TB Heating & Boiler Room TBOOI.27B 17-Aug-98 0.013 AL Cs-137 9.750E-02 0.008 0.008 TB Heating & Boiler Room TBOO1.27C 17-Aug-98 ND AL UNK - unknown DCGL (pCi/g m)
AB - as area backfill Nuclide l 25 mrem/yr 10 mrem/yr ABC - ABC storage area Ag-108m I 8.521E+00 3.408E+00 AL - as left Co-60 I 4.838E+00 1.935E+00 ALAR - as left after remediation Cs-1 34 6.706E+00 2.682E+00 FR - further remediation Cs-1 37 1.224E+01 4.896E+00 RD - rad disposal Sr-90 2.68E+00 1.072E+00 TS - temporary storage tk Page 2 of 2
Building Historical Site Assessment and Classification Summary Survey Area Name: Old PCA Storage Building Designator: WST-01 Survey Area Description Survey Area WST-01 consists of the reinforced concrete pad, pipe trench and subsurface structures that comprise the Old PCA Storage Building remaining after demolition of the structure is complete.
WST-01 is located in the RCA yard area and bounded by NOL-03 on the north, east, and south and by NOL-04.and WST-02 on the west. - .
- . . .... I; i-. -
Further division of this survey area into survey units as necessary is dependent upon the decommissioning end state configuration.
Page 1 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Old PCA Storage Building Designator: WST-01 Survey Area History WST-O 1 was constructed for use as an equipment decontamination and storage facility. (Ref 1) It was subsequently converted to a contaminated area used for radioactive'material storage only after it was determined that the drain line from the decon area was leaking. The building was later decontaminated and is now used as a hazardous and mixed waste storage location.
While it was used as a decontamination facility it was generally used for items considered heavily contaminated. These items include control rod drive shafts and dash-pots and other components of moderate size from the primary systems.
In 1984 construction of the RCA warehouse exposed the failed drain line where it crossed the RCA to the waste disposal building. An examination of the drain line identified leakage at each pipe joint indicating that the joints had failed. (Ref 2) The drain line, where it was exposed, was removed along with a volume of soil prior to construction of the warehouse. The drain line not removed during construction of the warehouse remains in place under the WST-O1 structure.
Scoping/Characterization Scoping surveys were performed and the data collected used to develop the YNPS Decommissioning Plan. (Ref 3)
DecommissioningActivities No decommissioning activities have been performed for survey area WST-O1.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Old PCA Storage Building Designator: WST-O1 Findings Survey area WST-01 was impacted by plant operations. Access to WST-01 is through a radiation control area.
The radionuclide mix likely to be present in WST-01 includes all radionuclides identified in the radioactive.systems of~the plant (Ref 4). The primary radionuclides of concern for survey area WST-01 are Co-60, Cs-137, Ag-108m, Sr-90 and tritium' ;
Current Status Survey area WST-01 remains in use as a material storage area and potentially may be impacted by ongoing decommissioning activities.
A soil sample location map (Figure 51) has been prepared to show the distribution of sampling locations in WST-01. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented).
One survey media was assessed in WST-01, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does mt include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for WST-01 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.022.
Maximum SOF for a single soil sample is 0.03 1. (key# 3358)
Minimum SOF for a single soil sample is 0.017. (key# 3359)
ClassificationStatement Based upon the historical use of survey area WST-01 and tl- radiological condition of area surrounding this survey area WST-01 is identified as a Class 1 Area.
Page 3 of 4
N-Building Historical Site Assessment and Classification Summary Survey Area Name: Old PCA Storage Building Designator: WST-O1 E
Drawings YB-H-1-0 YR-C-1 0-008 References
- 1. "Summary of Excavation Volumes for YNPS Construction Performed During the Time Period of Plant Operation," dated October 1997.
- 2. Plant Information Report (PIR) 84-16, "Drain Pipe Failure," dated December 5, 1984.
- 3. YNPS Decommissioning Plan, Rev. 0.0.
- 4. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT-00-00 1-03.
'II_
Page 4 of 4
Page I Of I Table I Sum of Fractions WST-O1 -- Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 3359 UG004.5 UG004.5B 0.017 3359 UG004.5 UG004.5A 0.020 3358 UG004.4 UG004.4B 0.031 3358 UG004.4 - UG004.4A 0.024 3357 UG004.3 UG004.3B 0.019 Min 0.017 Max 0.031 Mean 0.022
Table 2 Pagelof I Statistical Data Summary - WST-01 -- Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Mledian Results Ac-228 PCi/g 6 6 0.785 0.130 0.598 0.942 0.794 Ag-108m pCilg 0 6 0.000 Ag-i lOim PCi/g 0 6 0.000 Am-241 PCi/g 0 6 0.000 Bi-212 pCi/g 5 5 0.986 0.169 0.833 1.270 0.920 Bi-214 pCi/g 6 6 0.424 0.034 0.394 0.489 0.413 Ce-144 PCi/g 0 6 0.000 Co-58 PCi/g 1 6 0.028 0.028 0.028 0.028 Co-60 pCi/g 4 6 0.110 0.029 0.081 0.148 0.105 Cs-134 pCi/g 1 6 0.094 0.094 0.094 0.094 Cs-137 pCi/g 1 6 0.039 0.039 0.039 0.039 Fc-59 pCi/g 1 6 0.099 0.099 0.099 0.099 1-131 pCi/g 0 l 0.000 1-133 pCilg 0 1 0.000 K-40 pCi/g 6 6 14.747 1.819 11.530 16.790 14.940 Mn-54 pCi/g 1 6 0.042 0.042 0.042 0.042 Nb-95 pCi/g 0 6 0.000 Np-239 PCi/g 0 1 0.000 Pb-212 pCi/g 6 6 0.761 0.096 0.620 0.855 0.770 Pb-214 PCi/g 6 6 0.423 0.024 0.384 0.455 0.422 Ra-226 pCi/g 2 3 1.128 0.213 0.978 1.279 1.128 Ru- 103 PCi/g 0 6 0.000 Ru- 106 pCi/g 0 6 0.000 Sb-124 pCi/g 6 0.038 0.038 0.038 0.038 Sb-125 pCi/g 0 1 0.000 TI-208 pCi/g 6 6 0.719 0.085 0.586 0.817 0.733 Zn-65 PCi/g 0 6 0.000 Zr-95 PCilg 1 6 0.049 0.049 0.049 0.049
(' K-
Page 1 Of I Table 3 Summary of Detected Results-Above Criteria WST-0I -- Soil Yankee Nuclear.Power Station Rowe, MA
, DCGL_.Soil .
- Sample Criterion # Detects Above ' Maximum Parameter' # Detects Results Concentration Units Criterion. Detected Ac-228 6 6 pCi/g 0 I0.94 Ag-108m'. 0 6 8.52 pCi/g 0 Ag-I lOm 0 6 pCi/g 0
'Am-241 0 6 44.35 pCi/g 0
,Bi-212 5 5 - pCi/g I0 1.27 Bi-214 6 6 pCi/g 0 0.49
- Ce-144 0 6 pCi/g 0
'Co-58 1 6 pCi/g 0 0.03 lCo-60 4 6, 4.84 pCi/g 0 0.15 Cs-134 1 6 , 6.71 pCi/g 0 0.09 Cs-137 I 6 ;.12.24 pCi/g , 0 0.04 Fe-59 1 6 pCilg 0 0.10 1-131 0 1. pCi/g 0
,1-133 0 1 pCi/g 0 K-40 6 6 , pCi/g 0 16.79 Mn-54 1 6 21.66 pCi/g 0 0.04 Nb-95 0 6 'pCi/g ~0 Np-239 0 1 pCi/g 0 Pb-212 6 6 pCi/g' 0 0.86 Pb-214 6 6 pCi/g 0 0.45 Ra-226 2 3 pCi/g 0 - 1.28 Ru- 103 0 , 6,.,; pCi/g.
- , 0 Ru-106 0 6 68.21 pCi/g
' 0 Sb-I 24 1 6 pCi/g 0.04
. 0 Sb-125 0 1 37.73 pCi/g TI-208 6 6 pCi/g 0 0.82 Zn-65 0 6 pCi/g 0 0 Zr-95 .1. 6 pCi/g ..0 - ~0.05
0 Table 4 Page I of 2 Rad WST-01 --Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) UG004.3 (3357) UG004.3 (3357) UG004.4 (3358) UG004.4 (3358) UG004.5 (3359)
Sample ID UG004.3A UG004.3B UG004.4A UG004.4B UG004.5A Date Sampled 2/3/1998 2/3/1998 2/4/1998 2/4/1998 2/3/1998:
Ac-228 0.5981 0.8869 0.6951 0.9415 0.8511 Ag-108m -0.01228 U -0.006096 U 0.0109 U -0.007517 U -0.018 U Ag-110m 0.008035 U -0.01224 U 0.0205 U -0.01484 U -0.01044 U Am-241 0U 0U 0U 0U' 0U Bi-212 1.27 0.9977 0.833 0.9098 Bi-214 0.3937 0.4886 0.4085 0.4085 0.4295 Ce-144 -0.1788 U -0.03435 U 0.1158 U 0.1847 U -0.0069 U Co-58 0.02786 0.006088 U -0.008392 U -0.02824 U 0.0008359 U' Co-60 0.008896 U 0.02765 U 0.1143 0.1483 0.09508 Cs-134 0.04698 U 0.09385 -0.03193 U -0.1625 U -0.02057 U Cs-137 0.0234 U 0.03882 -0.01031 U 0.01218 U 0.01323 U Fe-59 0.02831 U 0.09927 0.01372 U -0.03865 U -0.02333 U 1-131 -0.1181 U 1-133 0.02041 U K-40 11.53 16.79 16.01 15.19 14.27 Mn-54 -0.001297 U 0.04175 -0.007542 U 0.003775 U -0.01804 U Nb-95 0.0109 U -0.01059 U 0.01378 U 0.01532 U 0.02813 U Np-239 -0.003568 U Pb-212 0.6196 0.8121 0.855 0.8552 0.7269 Pb-214 0.4175 0.4243 0.4188 0.4549 0.3838 Ra-226 0.9777 1.279 Ru-103 -0.003611 U 0.01216 U 0.001273 U 0.01072 U 0.01532 U Ru-106 0.03526 U -0.2548 U -0.06381 U -0.08412 U 0.1833 U Sb-124 0.03774 0.01722 U -0.01189 U -0.004502 U -0.00927 U Sb-125 0.2584 U TI-208 0.6608 0.7865 0.8174 0.7472 0.7182 Zn-65 -0.1008 U 0.0412 U -0.002027 U 0.03038 U 0.04317 U Zr-95 0.03265 U 0.02697 U 0.01016 U -0.01039 U 0.00713 U SOF 0.019 0.024 0.031 0.02 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 2 of 2 Rad WST-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) UG004.5 (3359)
Sample ID UG004.5B Date Sampled 2/3/1998 Ac-228 0.7361 Ag-108m -0.01011 U Ag- 10m 0.02019 U Am-241 0U Bi-212 0.9196 Bi-214 0.417 Ce-144 0.1208 U Co-58 -0.002097 U Co-60 0.08105 Cs-134 -0.01738 U Cs-137 0.01468 U Fe-59 0U 1-131 1-133 K40 14.69 Mn-54 -0.001278 U Nb-95 0.008008 U Np-239 Pb-212 0.6954 Pb-214 0.4373 Ra-226 0.7175 U Ru-103 0.00345 U Ru-106 -0.1043 U Sb-124 0.03881 U Sb-125 TI-208 0.5857 Zn-65 -0.03021 U Zr-95 0.04854 SOF 0.017 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Building Historical Site Assessment and Classification Summary Survey Area Name: Plant Warehouse RCA Designator: WST-02 Survey Area Description Survey Area WST-02 consists of the reinforced concrete pad and subsurface structures that comprise the RCA warehouse building remaining after demolition of the structure is complete.
WST-02 is located in the RCA yard area and is bounded by WST-03 and WST-04 on the north, NSY-7, NOL,03 and WST-01 on the east, NOL-04 on the south and NOL,05 on the west.
Further division of this survey area into survey units as necessary is dependent upon the decommissioning end state configuration Page 1 of 4
S *-
Building Historical Site Assessment and Classification Summary Survey Area Name: Plant Warehouse RCA Designator: WST-02 Survey Area History WST-02, RCA Warehouse was constructed under Plant Alteration (PA) #84-017 in 1984.
The RCA Warehouse was primarily used to store packaged radioactive material. The survey history of survey area WST-02 documents conditions of loose contamination present. When identified as contaminated the survey area WST-02 was decontaminated.
During various phases of the YNPS decommissioning WST-02 was used as a contaminated work area.
Contaminated soil was identified, excavated and disposed of as radioactive waste during construction of the RCA warehouse (Ref 1). Residual radioactivity remains in the soils under a portion of the RCA warehouse structure.
The present location of the non-contaminated construction spoils generated during construction of the RCA Warehouse is thought to be within the SCF area (OOL.09) of the site. (Ref 2)
Scoping/Characterization Scoping surveys were performed and the data collected used to develop the YNPS Decommissioning Plan. (Ref 3)
Decommissioning Activities No decommissioning activities have been performed for survey area WST-02.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Plant Warehouse RCA Designator: WST-02 Findings Survey area WST-02 was impacted by plant operations. Access to WST-02 is through the RCA.
The radionuclide mix likely to be present in WST-02 includes all radionuclides identified in the radioactive systems of the plant (Ref 4). The primary radionuclides of concern for survey area WST-02 are Co-60, Cs-137, Ag-108m, Sr-90 and tritium.
Current Status Survey area WST-02 remains in use as a material storage~area and potentially may be-impacted by ongoing decommissioning activities.
A soil sample location map (Figure 52) has been prepared to show the distribution of sampling locations in WST-02. Only samples representative of soils still present are included on tlr map (samples of soils representative of soils removed during remediation activities are not presented).
One survey media was assessed in WST-02, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for WST-02 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.147.
Maximum SOF for a single soil sample is 0.798. (key# 3361)
Minimum SOF for a single soil sample is 0.009. (key# 3362)
ClassificationStatement Based upon the historical use of survey area WST-02 and the radiological condition of area surrounding this survey area WST-02 is identified as a Class 1 Area.
Page 3 of 4
a-Building Historical Site Assessment and Classification Summary Survey Area Name: Plant Warehouse RCA Designator WST-02 Drawings KJ H Loney Construction. Co. A- I H Loney Construction. Co. S- I References
- 1. Plant Information Report (PIR) 84-16, "Drain Pipe Failure," dated December 5,1984.
- 2. "Summary of Excavation Volumes for YNPS Construction Performed During the Time Period of Plant Operation," dated October 1997.
- 3. YNPS Decommissioning Plan, Rev. 0.0.
4 "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT-00-001-03.
Page 4 of 4
Pagel of I Table 1 Sum of Fractions WST-02 -- Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 3363 WD002.2 WD002.2A '0.052 3362 WD002.1 WD002.lE 0.013 3362 WD002.1 WD002.1 D 0.009 3362 WD002.1 WD002.1C 0.063 3362 WD002.1 WD002.1B 0.061 3362 - WD002.1 WD002.1A 0.344 3361 WD001.2 WD001.2B 0.012 3361 WD001.2 WD001.2A 0.798 3360 WDOOI.1 WDOO1.1C 0.110 3360 WD001.1 WD001.11B 0.074.
3360 WDOOl.1 WDOOI.IA 0.082 Min 0.009 Max 0.798 Mean 0.147
Table 2 Page I of 1 Statistical Data Summary - WST-02 -- Soil Yankee Nuclear Power Station Rowe, MIA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCi/g 17 17 0.786 0.140 0.415 0.969 0.796 Ag-i 08m pCi/g 0 17 0.000 Ag- lOnm pCi/g 0 17 0.000 Am-241 pCi/g 0 17 0.000 Bi-212 pCi/g 15 16 0.872 0.194 0.481 1.213 0.857 Bi-214 pCi/g 17 17 0.444 0.080 0.290 0.583 0.446 Cc-144 pCi/g 0 17 0.000 Co-58 pCi/g 0 17 0.000 Co-60 pCi/g 11 17 0.686 1.094 0.046 3.712 0.284 Cs-134 pCi/g 0 17 0.000 Cs-137 pCi/g 5 17 0.133 0.141 0.041 0.378 0.064 Fe-59 pCi/g 0 17 0.000 K-40 pCi/g 17 17 17.561 1.485 14.470 19.380 18.040 Mn-54 pCilg 0 17 0.000 Mo-99 pCi/g 0 1 0.000 Nb-95 pCi/g 0 17 0.000 Np-239 pCi/g 0 4 0.000 Pb-212 pCi/g 17 17 0.786 0.156 0.327 0.926 0.844 Pb-214 pCi/g 17 17 0.468 0.096 0.290 0.657 0.470 Ra-226 pCi/g 11 13 1.334 0.183 1.057 1.690 1.384 Ru-103 pCi/g 0 17 0.000 Ru-106 pCi/g 1 17 0.317 0.317 0.317 0.317 Sb-124 pCi/g 1 17 0.048 0.048 0.048 0.048 Sb-125 pCi/g 0 3 0.000 TI-208 pCi/g 16 16 0.707 0.134 0.443 0.882 0.714 Zn-65 pCi/g 0 17 0.000 Zr-95 pCi/g I 17 0.069 0.069 0.069 0.069 (Q (.
Page lof I Table 3 Summary of Detected Results Above Criteria WST Soil Yankee Nuclear Power Station Rowe, MA DCGL_Soil
- Sample Criterion # Detects Above Maximum Parameter , #Detects Results 'Concentration Units ,_ Criterion Detected Ac-228 - 17 17 pCi/g 0 0.97 Ag-108m 0 17 8.52 pCi/g 0 Ag-lOrm 0 17 pCi/g 0 Am-241 0 17 44.35 pCi/g 0 Bi-212 - 15 16 pCi/g. 0 1.21 Bi-214 . 17 17 pCi/g 0 0.58 Ce-144 0 17 pCi/g 0 Co-58 0 17 -- pCi/g - 0 Co-60 11 17 4.84 pCilg 0 3.71 Cs-134 0 17 6.71 pCi/g 0 Cs-137 5 17 '12.24 pCi/g 0 0.38 Fe-59 0 17 pCi/g 0 K-40 17 17 pCi/g 0 19.38 Mn-54' 0 17 21.66 pCi/g 0 Mo-99 0 1 pCi/g 0 Nb-95 0 17 pCi/g 0 Np-239 0 4 pCi/g 0 Pb-212 17 17 pCi/g 0 0.93 Pb-214 - 17 17 pCi/g; 0 0.66 Ra-226 11 13 pCi/g 0 1.69 Ru-103 0 17' pCi/g 0 Ru-106 1 17 68.21 pCi/g 0 0.32 Sb-124 1 17 pCi/g 0 0.05 Sb-125 0 3 37.73 pCi/g 0 TI-208 16 16 pCi/g 0 0.88 Zn-65 0 17 pCilg' 0 Zr-95 1 17 '0 0.07
Table 4 Pagel1 of 4 Rad WST-02 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD001.1 (3360) WD001.L (3360) WDOO1.1 (3360) WDOO1.2 (3361) WD001.2 (3361)
Sample ID WD001.IA , WDOO1.1B WDOO1.1C WD001.2A WDOOI.2B Date Sampled 6/16/1998 6/16/1998 6/16/1998 6/16/1998 6/16/1998 Ac-228 0.4153 0.9693 0.8029 0.8349 0.9558 Ag-108m -0.009578 U 0.0002772 U -0.0293 U 0.01594 U -0.01841 U' Ag-110in 0.008587 U -0.03729 U -0.02706 U -0.03959 U 0.007855 U Am-241 0U 0U 0U 0U 0U Bi-212 0.7602 1.08 0.701 0.648 U 1.076 Bi-214 0.3656 0.4455 0.4296 0.5605 0.4463 Ce-144 0.0811 U -0.0668 U 0.06482 U -0.04391 U -0.09914 U Co-58 -0.01922 U -0.02612 U -0.01475 U 0.04212 U -0.02558 U Co-60 0.3797 0.3573 0.5111 3.712 0.05834 Cs-134 0.003946 U -0.03927 U 0.00734 U -0.06965 U 0.03743 U Cs-137 0.0411 0.03622 U 0.0504 0.3775 0.03461 U Fe-59 -0.01637 U -0.05544 U -0.02258 U 0.09902 U -0.0335 U K-40 14.47 19.02 19.38 18.55 18.04 Mn-54 -0.004193 U 0.02687 U 0.02974 U 0.03076 U -0.02039 U Mo-99 0.4584 U Nb-95 -0.02589 U -0.001204 U 0.01851 U -0.0003425 U -0.01164 U Np-239 Pb-212 0.3268 0.8547 0.8586 0.7434 0.8891 Pb-214 0.2898 0.4668 0.4807 0.4461 0.4785 Ra-226 1.057 1.302 0.9223 U Ru-103 -0.01371 U -0.01279 U 0.01003 U -0.02091 U 0.002921 U Ru-106 -0.02011 U 0.08037 U 0.04182 U 0.08092 U 0.2258 U Sb-124 0.04788 -0.02527 U -0.03772 U 0.003284 U -0.01445 U Sb-125 TI-208 0.4428 0.5763 0.8764 0.6976 0.806 Zn-65 0.03008 U -0.0002911 U -0.1412 U -0.1829 U -0.0242 U Zr-95 0.03203 U -0.001688 U 0.06925 -0.02104 U -0.002033 U SOF 0.082 0.074 0.11 0.798 0.012 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 2 of 4 Rad WST-02-- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key). WD1OO.2 (3361) WD001.2 (3361) WD002.1 (3362) WD002.1 (3362) WD002.1 (3362)
Sample ID - WDOO1.2C WDOO1.2D WD002.1A WD002.1B VWD002.1C Date Sampled 6/16/1998 6/16/1998 6/11/1998 6/1i/1998 6/1i/1998 Ac-228 - 0.8762 . 0.7408 0.6149 0.7723 0.9444 Ag-108m . 0.004496 U . -0.003647 U - 0.01586 U 0.02485 U -0.0137 U Ag-110mn 0.02677 U -0.01194 U . 0.008631 U 0.008507 U -0.004646 U Am-241 0U 0U 0U 0U 0U Bi-212 1.01 1.06 0.8033 1.213 Bi-214 0.467 0.3818 0.3531 0.4824 0.5827 Ce-144 -0.002879 U 0.02932 U - -0.03758 U -0.1148 U 0.1028 U Co-58 -0.01386 U 0.006446 U - -0.006073 U -0.02552 U -0.0288 U 0.007222 U -0.01494 U 1.614 0.2691 0.2841 Co-60 Cs-134 -0.06081 U -0.00326 U -0.01108 U 0.006273 U -0.01501 U Cs-137 0.01827 U 0.01289U 0.1325 0.06388 0.03775 U Fe-59 0.04554 U 0U -0.07511 U -0.03069 U - 0.006336 U K-40 17.41 ; 17.98 15.65 18.45 18.41 Mn-54 -0.01237 U -0.004976 U -0.00495 U 0.01155 U -0.01822 U Mo-99 Nb-95 -0.02761 U 0.02017 U 0.02387 U 0.005399 U 0.006957 U Np-239 1.048 U -0.837 U Pb-212 0.8683 0.8295 0.5136 0.8654 0.9154 Pb-214 0.4432 0.3713 0.4698 0.4945 0.6027 Ra-226 1.407 1.075 1.384 1.441 - 1.198 Ru-103 -0.03639 U -0.005772 U - -0.001625 U -0.0009761 U 0.006078 U Ru-106 -0.1517 U 0.1709 U -0.1008 U 0.1562 U 0.3172 Sb-124 -0.00789 U 0U 0.009624 U -0.01623 U -0.01248 U Sb-125 -0.1103 U -0.1055 U TI-208 0.8089 0.8107 0.5483 0.8819 Zn-65 0.04687 U -0.03648 U - -0.06858 U -0.1334 U 0.05615 U Zr-95 -0.07638 U 0.001822 U 0.04773 U 0.03686 U 0.02873 U SOF . i 0.344 0.061 0.063 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
a-Table 4 Page 3 of 4 Rad WST Soil (pCilg)
Yankee Nuclear Powver Station Rowe, MA Station (Key) WD002.1 (3362) WVD002.1 (3362) WD002.2 (3363) WD002.2 (3363)' WD002.2 (3363)-
Sample ID WD002.11D WD002.1 E WD002.2A WD002.2B - WD002.2C Date Sampled 6/11/1998 6111/1998 6/15/1998 6/15/1998 6/15/1998 r Ac-228 0.8933 0.7963 0.6449 0.7582 0.7174 Ag-108m -0.008961 U 0.01863 U 0.007614 U -0.009366 U 0.01766 U Ag-110mI 0.02697 U 0.03183 U 0.0045 U -0.008542 U 0.008109 U Am-241 0U 0U 0U 0U 0U Bi-212 0.7979 0.4812 0.8613 0.9282 0.6289 Bi-214 0.4597 0.5806 0.4451 0.4491 0.2896 Ce-144 0.03771 U 0:1338 U -0.2186 U 0.03459 U -0.0745 U Co-58 0.001067 U -0.0394 U -0.005908 U -0.02281 U -0.01438 U Co-60 0.04555 0.06125 0.2512 0.03002 U -0.005101 U Cs-134 -0.008308 U -0.08126 U -0.1333 U -0.1592 U -0.1204 U Cs-137 -0.02284 U -0.02111 U 0.01965 U 0.03625 U -0.0059 U Fe-59 0.01136 U -0.02481 U -0.02353 U 0.02924 U -0.03702 U K-40 18.44 18.87 15.99 17.16 14.71 Mn-54 0.004721 U -0.01239 U -0.00108 U 0.008964 U 0.01387 U Mo-99 Nb-95 -0.01082 U 0.01654 U -0.009331 U 0.01135 U 0.01707 U Np-239 -1.711 U -0.9905 U Pb-212 0.9255 0.8378 0.6661 0.7948 0.7474 Pb-214 0.479 0.6574 0.3834 0.4097 0.3377 Ra-226 0.8871 U 1.437 1.427 Ru-103 0.02251 U -0.01653 U -0.006747 U -0.03291 U 0.0071 U Ru-106 -0.1118 U -0.2636 U -0.02039 U -0.001843 U 0.02273 U Sb-124 -0.00836 U 0.02077 U 0U -0.004649 U 0.01044 U Sb-125 0.07983 U TI-208 0.6554 0.8569 0.5785 0.6423 0.5942 Zn-65 0.04536 U -0.009466 U -0.1167 U -0.04535 U -0.05478 U Zr-95 0.03041 U 0.03749 U -0.004236 U 0.004467 U 0.009443 U SOF 0.009 0.013 0.052 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 4 of 4 Rad WST-02 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD002.2 (3363) WD002.2 (3363)
Sample ID WD002.2D WD002.2E Date Sampled 6/15/1998 6/15/1998 Ac-228 0.8767 0.7554 Ag-108m -0.0 1802 U -0.005004 U Ag-1 10m -0.02626 U 0.02252 U Am-241 0U 0U Bi-212 0.8571 0.825 Bi-214 0.4482 0.36 Ce-144 0.1005 U -0.03251 U Co-58 0.006905 U -0.007645 U Co-60 0.03441 U -0.01099 U Cs-134 0.009073 U -0.06512 U Cs-137 0.002531 U 0.01768 U Fe-59 -0.02854 U 0.005682 U K-40 17.8 18.21 Mn-54 -0.0 1624 U -0.0144 U Mo-99 Nb-95 0.02393 U 0.002209 U Np-239 Pb-212 0.8774 0.8435 Pb-214 0.5757 0.577 Ra-226 1.259 1.69 Ru-103 0.009448 U -0.009902 U Ru-106 0.08407 U 0.1468 U Sb-124 -0.01648 U -0.004528 U Sb-125 T1-208 0.73 0.7996 Zn-65 -0.07422 U 0.01082 U Zr-95 0U 0.0351 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Underground Systems WST-02 Structure / System component Description Location Impacted?
Abandoned Street electric cable from -35' N of SW comer of PCA warehouse Lighting going E to opposite side of bIdg Page 1 of 1 K (
Building Historical Site Assessment and Classification Summary Survey Area Name: Waste Disposal Building Designator: WST-03 Survey Area Description Survey Area WST-03 consists of reinforced concrete floor, foundations and sub-grade structures of the Waste Disposal Building expected to remain after demolition of the above-grade structure is complete.
The floor area of WST-03 is at elevation 1035'and includes the waste gas compressor room, the liquid waste transfer pump room, the drum drying area and the operator's station and motor control center. The WST-03 footprint includes the following below, grade structures: the evaporator cubicle, drumming pit and three pipe chases.
The soils present within and under and around the Waste Disposal Building structure' include back fill, overburden and lodgment till. The lodgment till is relatively impermeable to groundwater flow. The overburden is more permeable. The backfill is the most permeable media and consequently areas containing backfill are the likely pathways for subsurface migration of radioactivity.
The structures and systems present in WST-03 include:
- The electrical conduit duct tray
- Drumming area floor drain sump pit
- Floor drain piping,
- Service water piping, Page 1 of 5
a-Building Historical Site Assessment and Classification Summary Survey Area Name: Waste Disposal Building Designator: WST-03 Survey Area History WST-03 was designed to contain radioactive operating systems and the leakage of radioactivity associated with such systems. WST-03 was specifically designed and constructed to contain and conduct radioactive liquid spills to waste collection tanks.
Survey area WST-03 spaces were connected to the primary plant ventilation system that discharged to the Primary Vent Stack. The negative pressure maintained within the spaces channeled the release of airborne radioactivity through a monitored discharge to the environment.
This structure was subject to contaminating events involving leakage of radioactive liquids from pump seals, liquid waste spills and the general spread of contamination by operations and maintenance activities.
An incinerator used to dispose of combustible radioactive waste was located on an elevated platform at the west end of the drumming pit. The discharge of combustion gases was filtered and monitored via batch sampling. Operation of the incinerator continued through the mid 1970's when it was removed from service.
For the most part with the exclusion of the drum drying area, the 1035' elevation of the WST-03 was maintained as a non-contaminated area. The cubicles and pipe chases were, for much of the plant history, contaminated areas. Migration of contamination out of posted contaminated areas resulted in the occasional contamination of the 1035' elevation of WST-03. This area was decontaminated when contamination was identified in these areas.
Scoping/Characterization Scoping surveys were performed and the data collected used to develop the YNPS Decommissioning Plan. (Ref 1)
DecommissioningActivities Decommissioning Work Plans (DWP) activities performed in the WST-03 survey area included the following:
- WDBA-01 Removal of WD Building MCC5.
- WDBA-02Waste Disposal Bldg Area Clean Out.
- WDSR-01 Waste Disposal System Removal.
- WG-01 Removal of Waste Gas System.
The decommissioning activities performed have removed all radioactively contaminated piping, pumps, tanks, and other system components from WST-03. In addition reinforced concrete surfaces have been de-contaminated via surface removal techniques.
Page 2 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: Waste Disposal Building : .:- Designator: WST-03 Removal of the floor drain system piping and sump pit also required removal of portion of the floor and sub-floor soils.
Page 3 of 5
- a3 Building Historical Site Assessment and Classification Summary Survey Area Name: Waste Disposal Building Designator: WST-03 Findings The history of the WST-03 indicates that this structure is impacted as a result of plant operations.
The radionuclide mix likely to be present in WST-03 includes all radionuclides identified in the radioactive systems of the plant (Ref 2). The primary radionuclides of concern for survey area WST-03 are Co-60, Cs-137, Ag-108m, Sr-90 and tritium.
CurrentStatus Survey area WST-03 remains in use as a material storage area and potentially may be impacted by ongoing decommissioning activities.
A soil sample location map (Figure 53) has been prepared to show the distribution of sampling locations in WST-03. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented). One survey media was assessed in WST-03, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for WST-03 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.206.
Maximum SOF for a single soil sample is 3.526. (key# 3064)
Minimum SOF for a single soil sample is 0.002. (key# 3364)
ClassificationStatement Based upon the historical use of survey area WST-03 and the radiological condition of area surrounding this survey area WST-03 is identified as a Class I Area.
Page 4 of 5
Building Historical Site Assessment and Classification Summary Survey Area Name: Waste Disposal Building Designator: WST-03 Drawings 9699-FA-17A 9699-FA- 17B . I 9699-FA-17C 9699-FB-5 F 9699-FC-36A 9699-FC-36B 9699-RC-36C References
- 1. YNPS Decommissioning Plan, Revision 0.0.
- 2. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-REPT-00-001-03. I Page 5 of 5
a-Pagel of 2 Table 1 Sum of Fractions WST-03 -- Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 3068 SB9A SB9A3 0.010
- 3002 CB12 CB12A 0.177 3367 WD004.3 WD004.3A 0.075 3366 WD004.2 WD004.2D 0.090 3366 WD004.2 WD004.2C 0.014 3366 WD004.2 WD004.2B 0.017 3366 WD004.2 WD004.2A 0.094 3365 WD004.1 WD004.1 D 0.147 3365 WD004.1 WD004.1 C 0.043 3365 WD004.1 WD004. 1 B 0.160 3368 WD004.4 WD004.4C 0.165 3364 WD003.1 WD003.1A 0.002 3368 WD004.4 WD004.4D 0.415 3064 SB110 SBIOF 0.022 3064 SB1O SBIOE 0.068 3064 SBIO SBIOD 0.217 3064 SBIO SBIOC 0.197 3064 SBIO SB1OB 0.350 3064 SBIO SBIOA 3.526 3002 CB12 CB12E 0.553 3002 CB12 CB12D 0.306 3002 CB12 CB12C 0.566 3002 CB12 CB12B 0.432 3365 WD004.1 WD004.1A 0.558 3385 WD008.1 WD008.11B 0.003 3400 WD011.6 WD011.6B 0.018 3400 WD011.6 WDOI1.6A 0.024
Page2of 2 Table I Sum of Fractions WST-03 -- Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 3398 WD011.4 WD011.4A 0.007 3397 WDO1I.3 WD011.3A 0.044 3396 WD011.2 WD011.2B 0.005 3396 WD011.2 WD011.2A 0.005 3394 WD010.3 WD010.3C 0.258 3393 WD010.2 - WD010.2B 0.019 3393 WD010.2 WVD010.2A 0.058 3368 WD004.4 W1D004.4B 0.205 3389 WD008.5 WD008.5A 0.016 3401 WD012 WD012A 0.004 3384 WD007.9 WD007.9A 0.021 3383 WD007.8 WD007.8B 0.003 3380 WD007.3 WD007.3D 0.010 3380 WD007.3 WD007.3C 0.003 3372 WD005.3 W1D005.3D 0.009 3372 WD005.3 WD005.3A 0.392 3371 WD005.2 WD005.2A 0.019 3370 WD005.1 WD005.1B 0.080 3370 WD005.1 WD005.1A 0.087 3369 WD004.5 WD004.5A 0.376 3391 WD008.7 WD008.7A 0.016 Min 0.002 Max 3.526 Mean 0.206
Table 2 Page I of I Statistical Data Summary - WST-03 -- Soil Yankee Nuclear Power Station Rowe, MA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCi/g 85 85 1.018 0.512 0.216 2.633 0.850 Ag-108m PCi/g 1 85 0.040 0.040 0.040 0.040 Ag- lOm pCilg 2 85 0.053 0.002 0.052 0.054 0.053 Am-241 pCi/g 0 59 0.000 Ba-133 pCi/g o 1 0.000 Bi-212 pCilg 56 72 3.005 14.368 0.256 108.500 0.900 Bi-214 pCi/g 81 81 0.616 0.337 0.150 1.667 0.480 Cc-144 pCilg 5 85 0.578 0.541 0.243 1.512 0.288 Co-58 pCilg 1 85 0.037 0.037 0.037 0.037 Co-60 pCilg 34 85 0.735 1.063 0.040 4.928 0.281 Cr-51 pCilg o 1 0.000 Cs-134 pCi/g 9 85 0.171 0.214 0.034 0.722 0.103 Cs-137 pCi/g 29 85 1.889 5.437 0.037 29.370 0.524 Fe-59 pCilg 0 85 0.000 1-131 pCilg o ' 0.000 1-132 pCilg 0 5 0.000 1-133 pCilg 0 2 0.000 1-135 PCilg o 1 0.000 K-40 pCilg 82 85 20.637 11.297 0.428 52.870 17.035 Mn-54 pCi/g 1 85 0.035 0.035 0.035 0.035 Mo-99 pCilg o 1 0.000 Nb-95 pCilg 6 85 0.060 0.034 0.033 0.119 0.049 Np-239 pCilg 0 14 0.000 Pb-212 pCi/g 85 85 1.072 0.619 0.224 3.082 0.845 Pb-214 pCi/g 85 85 0.701 0.423 0.151 2.163 0.540 Ra-226 pCilg 45 57 2.047 1.581 0.525 9.892 1.587 Ru-103 pCilg 1 85 0.114 0.114 0.114 0.114 Ru-106 pCilg 3 85 0.289 0.069 0.235 0.366 0.265 Sb-124 2 85 0.047 0.032 0.024 0.070 0.047 Sb-125 PCilg 0 7 0.000 Te-129m pCilg 1 1 1.656 1.656 1.656 1.656 TI-208 pCi/g 78 78 0.967 0.527 0.223 2.731 0.789 Zn-65 pCi/g 0 85 0.000 Zr-95 vCilg 4 85 0.105 0.073 0.057 0.213 0.074
( ( ( II
Page I of i Table 3 Summary of Detected Results Above Criteria WST-03 -- Soil Yankee Nuclear Power Station Rowe, MIA
.' , . , DCGL_Soil' ' i * ^,
- Sample Criterion # Detects Above Maximum Parameter # Detects Results Concentration Units Criterion - Detected Ac-228; 85 '85; pCi/g . 0 2.63 Ag-108m 1 *85. 8.52 pCi/g . 0 0.04 Ag-i lOm 2 85 pCi/g 0 0.05 Am-241 0 59 44.35 pCi/g 0 Ba-133 0 1 ; I pCi/g 0 Bi-212 56 72 pCi/g 0 108.50 Bi-214 81 81 pCilg 0 1.67 Ce-144 5 85 pCi/g . I 0 1.51 Co-58 1 85 pCi/g 0 0.04 Co-60 34 85 4.84 pCi/g 1 4.93 Cr-51 '0 1 6pCi/g .i 0 Cs-134 9. 85 6.71 ,pCi/g '0 0.72 Cs-137 29 85 , 12.24 pCi/g 1 29.37 Fe-59 0 85 pCi/g 0 1-131 0 1 pCi/g 0 1-132 0 5 pCi/g I 0 1-133 0 2 pCi/g ; 0 1-135 0 1 pCi/g 0 K-40 82 85 _ pCi/g 0 '52.87 Mn-54 1 85 '21.66 ' pCi/g 0 0.04 Mo-99 O 1 pCi/g 0 Nb-95 6 85 pCi/g 0 0.12 Np-239 0 14 pCi/g 0 Pb-212 85 85 pCi/g 0 3.08 Pb-214 85 85, pCi/g 2.16 0
Ra-226 45 57 pCi/g 9.89 0
Ru-103 1 85. pCi/g 0.11 0
Ru-106 3 , 85 ;68.21 pCi/g 0.37 0
Sb-i 24 2 85 pCi/g 0 0.07 Sb-125 :0 7 37.73, pCi/g Te-129m 1 1. pCi/g 0 1.66 TI-208 78 78 pCi/g 0 2.73 Zn-65 0 85 pcilg Zr-95 4 .85 pCi/g 0 .0.21 I, .
Table 4 Page I of 17 Rad WST Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) CB12 (3002) CB12 (3002) CB12 (3002) CB12 (3002) CB12 (3002) SB10 (3064)
Sample ID CB12A CB12B CB12C CB12D CB12E SBIOA Date Sampled 12/10/1997 12/10/1997 12/10/1997 12/10/1997 12/10/1997 12/10/1997 4 . . . .
. . AU Ac-228 2.532 2.102 2.203 1.842 1.14 2.633 Ag-108m 0.01043 U 0.05048 U 0.005961 U 0.02403 U -0.01549 U 0.02604 U Ag-110m 0.09367 U 0.06108 U -0.003996 U 0.05304 U -0.0207 U 0.08436 U Am-241 0U OU OU OU OU OU Ba-133 Bi-212 2.898 1.457 U 1.704 U 1.754 Bi-214 1.667 1.171 1.234 1.339 1.074 1.483 Ce-144 0.05261 U -0.1912 U -0.5167 U 0.447 U -0.2801 U 1.512 Co-58 0.0007895 U -0.04502 U 0.05962 U 0.04979 U 1-0.01212 U -0.06082 U Co-60 0.8561 ' 2.089 2.74 1.481 2.674 4.928 Cr-51 Cs-134 -0.06274 U -0.1184 U -0.3517 U -0.1196 U -0.05063 U 0.7223 Cs-137 0.03999 U 0.007131 U -0.0373 U -0.05616 U 0.02586 U 29.37 Fe-59 0.06865 U 0.107 U -0.04232 U -0.01304 U 0.05544 U -0.1803 U 1-131 1-132 1-133 1-135 K40 41.18 39.77 49.33 38.781 33.64 46.41 Mn-54 0.0208 U 0.04779 U -0.0597 U -0.06204 U -0.02974 U 0.07454 U Mo-99 Nb-95 -0.01449 U 0.008763 U -0.01046 U 0.1194 -0.003667 U -0.1202 U Np-239 -0.2584 U Pb-212 3.026 2.464 2.296 2.024 1.025 2.479 Pb-214 1.997 1.473 1.539 1.32 1.287 2.163 Ra-226 4.283 2.355 U 2.285 U 3.386 9.892 Ru-103 -0.06171 U -0.03457 U 0.114 0.0287 U -0.02491 U 0.07716 U Ru-106 -0.06657 U 0.05935 U 0.1242 U -0.1012 U 0.7486 U 0.4663 U Sb-124 0.05553 U 0.1039 U 0.006213 U -0.05316 U 0.01749 U -0.02528 U Sb-125 Te-129m Tl-208 2.731 2.393 2.232 2.07 Zn-65 0.1264 U -0.1431 U 0.2272 U 0.03351 U 0.01073 U -0.3036 U Zr-95 -0.01026 U 0.0434 U 0.1981 U 0.01851 U 0.0623 U -0.2795 U SOF 0.177 0.432 0.566 0.306 0.553 3.526 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 2 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) ' SBIO (3064) ISB10 (3064) I-SBIO (3064) SBIO (3064) - SBIO (3064) SBIO (3064)
Sample ID - SBIOB SB1OC I SBIOD ;:SBIOE SBIOF SBIOG Date Sampled 12/101997 . 12/10/1997 j12/10/1997' 112/10/1997 .{12/11/1997 112/11/1997 .
Ac-228 1.758 : 1.445 . 1.218 2.001 C, 1.76 1.332 Ag-108m 0.05377 U 0.05483 U -0.001209 U 0.005217 U 0.006135 U 0.04901 U Ag-I lOm 0.04576 U 0.03841 U -0.06725 U -0.02729 U -0.02116 U 0.03704 U Am-241 OU OU OU OU OU OU Ba-133 Bi-212 1.41 U .. , 1.339 U Bi-214 0.9218 ! - .1.248 0.8588 ! I1.136 - 1.023 1.021 Ce-144 -0.00267 U 0.3867 U 0.481 U ': -0.4446 U -0.2839 U -0.09492 U Co-58 -0.1137 U -0.03792 U -0.0317 U -0.04941 U -0.04244 U. 0.02425 U Co-60 1.531 0.745 0.741 0.3311 0.1049 0.01768 U Cr-5I Cs-134 -0.01484 U -0.0223 U 0.01765 U -0.2123 U -0.3942 U 0.1021 U Cs-137
- 0,4141 0.5242 0.7853 0.007367 U -0.03163 U -0.02694 U Fe-59 -0.2368 U -0.1349 U -0.05866 U 0.01579 U -0.03905 U 0.01003 U 1-131 1-132 1-133 1-135 K-40 35.35 52.871 29.79 38.14 36.5 27.79 Mn-54 0.004833 U 0.06991 U -0.0205 U 0.06189 U -0.06264 U 10.03776 U Mo-99 Nb-95 0.01104 U 0.04229 U -0.0537.U -0.049 U 0.0317 U 0.07609 Np-239 0.2017 U Pb-212 1.888 1.97 1.527 2.114 1.631 1.315 Pb-214 1.197 1.444 1.083 1.638 1.633 0.9288 Ra-226 2.201 U 2.865 2.491 3.522 2.161 U 2.865 Ru-103 -0.008574 U -0.0 1924 U -0.03803 U 0.005792 U 0.005474 U -0.01138 U Ru-106 -0.3447 U -0.01286 U -0.5173 U' 0.4905 U -0.05265 U -0.2056 U Sb-124 0.02874 U OU 0.03131 U 0.02146 U 0.0856 U 0.002618 U Sb-125 0.05144 U Te-129m TI-208 1.638 1.9371 , 7! 2.166 1.484 1.193 Zn-65 0.09684 U -0.1535 U -0.1705 U 0.02072 U 0.07561 U . -0.285 U Zr-95 -0.02918 U 0.2127 0.0272 U 0.08717 U 0.1227 U 0.08082 U SOF 0.35 ,. 0.197 i 0.217 0.068 0.022 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed I.
a-Table 4 Page 3 of 17 Rad WST Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) SB8 (3066)
- SB9 (3067) 1SB9A (3068) ISB9A (3068) SB9A (3068) -J WDOO3.1 (3364)
Sample ID SB8 SB9 j SB9A2 SB9A3 !' SB9A4 WD003.1A;. ;
Date Sampled 12/12/1997 > 12/12/1997 12/12/1997 12/12/1997 112/12/1997 10/2/1997 ___
Ac-228 2.017 2.392 2.245 1.934 - 0.2164 0.8521 Ag-108m -0.01161 U 0.0552 U 0.01121 U 0.001619 U -0.0009126 U -0.01095 U Ag-I lOm- 0.02031 U -0.05413 U -0.03814 U 0.005875 U -0.001077 U -0.001739 U Am-241 0U OU OU OU OU OU Ba-133 Bi-212 1.144 3.546 2.882 1.866 0.2561 0.4758 U Bi-214 1.226 1.565 1.416 0.9929 0.1497 0.368 Ce-144 0.5885 0.2718 U 0.5794 U 0.2067 U : 0.002947 U -0.02354 U Co-58 0.03267 U 0.003407 U -0.0193 U -0.07122 U 0.001257 U -0.01413 U Co-60 -0.01756 U 0.02783 U -0.02628 U 0.05153 U 0.0007471 U -0.02617 U Cr-51 Cs-134 0.1513 U -0.05293 U -0.1794 U -0.0213 U -0.01745 U 0.01979 U Cs-137 0.05079 U 0.04793 U 0.06854 U 0.1219 -0.004124 U 0.03315 U Fe-59 -0.04263 U 0.1189 U 0.1138 U -0.02318 U -0.006299 U 0.02707 U 1-131 1-132 1-133 1-135 K-40 32.42 36.19 43.44 42.151 3.899 15.65 Mn-54 0.02811 U -0.0074 U 0.01849 U -0.01473 U -0.006575 U 0.03504 Mo-99 Nb-95 -0.03361 U -0.05116 U -0.05718 U -0.009787 U 0.0007201 U 0.02678 U '-1 Np-239 Pb-212 2.145 3.056 3..082 2.304 0.2241 0.7332 Pb-214 1.373 1.595 1.648 1.182 0.1514 0.4514 Ra-226 3.051 3.704 2.936 0.5251 1.38 Ru-103 -0.02862 U 0.01977 U -0.04044 U -0.05663 U 0.002111 U -0.005244 U Ru-106 -0.2124 U 0.5051 U 0.05299 U 0.5612 U -0.005753 U 0.222 U Sb-124 0.02456 U -0.0318 U -0.02638 U -0.06831 U -0.001926 U -0.004207 U Sb-125 Te-129m TI-208 1.595 2.522 2.171 1.843 0.2229 0.7043 Zn-65 -0.1874 U 0.1203 U -0.1999 U 0.09325 U -0.004227 U -0. 1163 U Zr-95 0.06747 U -0.008201 U -0.02433 U 0.0291 U' 0.001537 U 0.0184 U SOF 0.01 0.002 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 4 of 17 Rad WST Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD003.1 (3364) WD004.1 (3365) WD004.1 (3365) IWD004.1 (3365) WD004.1 (3365)
Sample ID WD003.1B - WD004.IA WD004.1B:.. IWD004.1C WD004.1D' Date Sampled 1012/1997 -9/29/1997 rI 9/29/1997 ; 9/29/1997 19/29/1997 Ac-228 - 0.8292 1.054 1.045 1.124 0.9313 Ag-108m -0.02221 U -0.04466 U 0.02739 U -0.01838 U 0.01858 U Ag-I 10m -0.003664 U -0.05054 U 0.01166 U 0.00436 U -0.001477 U Am-241 OU OU OU OU OU Ba-133 Bi-212 0.5997 U 1.267 0.976 2.064 Bi-214 0.4871 0.5565 0.4478 0.4191 Ce-144 -0.07102 U 0.1799 U -0.1404 U -0.02769 U 0.004725 U Co-58 -0.02404 U -0.01319 U -0.0315 U -0.02393 U -0.01 159 U Co-60 0.01919 U 0.2695 0.3949 0.1672 0.3094 Cr-51 0.298 U Cs-134 0.01351 U 0.1528 0.0321 U 0.01789 U 0.04872 U Cs-137 0.002645 U 5.871 0.9597 0.1067 1.017 Fe-59 -0.03045 U 0.03303 U 0.01247 U -0.0173 U 0.02388 U 1-131 I-132 1-133 1-135 K-40 18.15 0.6408 0.6558 0.9098 0.6565 Mn-54 -0.01186 U -0.008376 U 0.02992 U 0.01401 U 0.04579 U Mo-99 Nb-95 0.0247 U 0.01409 U 0.04024 U 0.04956 U -0.01075 U Np-239 Pb-212 0.956 0.9154 0.8937 1.034 '1.09 Pb-214 - 0.5675 0.516 :: 0.5486 0.5436 0.6261 Ra-226 1.914 1.641 2.064 Ru-103 0.03061 U 0.01333 U -0.001736 U -0.005602 U 0.007945 U Ru-106 -0.1932 U 0.1563 U -0.2099 U -0.04314 U -0.43 U Sb-124 -0.009203 U 0.03518 U -0.01622 U , 0.01327 U -0.003331 U '
Sb-125 Te-129m Tl-208 0.7938 0.7305 0.8205 0.8321 Zn-65 0.01859 U OU, -0.0702 U -0.1104 U 0.03691 U Zr-95 0.06118 0.03269 U 0. 5 -0.06716 U 0.05546 U -0.02583 U SOF J .... i ... 0.558 0.16 0.043 0.147 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
W-Table 4 Page 5 of 17 Rad WST Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD004.2 (3366) WD004.2 (3366) -WD004.2 (3366) WD004.2 (3366) WD004.3 (3367)
Sample ID WD004.2A WD004.2B WD004.2C WD004.2D WD004.3A Date Sampled 9/29/1997 9/29/1997 9/29/1997 49/29/1997 9/22/1997 Ac-228 1.068 0.8499 1.005 0.9186 0.584 Ag-108m 0.0125 U -0.02577 U -0.0273 U -0.01387 U -0.00671 U Ag-I 10m -0.02163 U -0.02177 U 0.0523 0.01498 U 0.007733 U Am-241 OU OU 0U OU OU Ba-133 Bi-212 0.4672 U 1.33210.09758 U 0.6742 Bi-214 0.4654 0.4677 0.4505 Ce-144 0.03115 U -0.1818 U -0.01402 U 0.1203 U 0.258 Co-58 0.01828 U 0.01 177 U 0.0197 U -0.02136 U -0.0148 U Co-60 i 0.04023 0.03175 U -0.01704 U 0.1895 0.1138 Cr-51 Cs-134 -6.002 U 0.00511 U 0.09472 C0.03715 0.03437 Cs-137 1.052 0.2038 0.03568 U 0.5504 0.5701 Fe-59 0.004554 U 0.0278 U -0.0717 U -0.006275 U -0.005686 U 1-131 1-132 1.352 U 1-133 1-135 0.8997 U K-40 0.3192 U 0.09135 U 0.4283 18.93 14.54 Mn-54 0.03896 U 0.009238 U 0.00926 U 0.01071 U -0.01504 U Mo-99 Nb-95 0.02142 U -0.009565 U 0.01542 U -0.02653 U 0.01603 U Np-239 0.1333 U 1.345 U Pb-212 0.7705 0.8664 0.9219 0.9726 0.708 Pb-214 0.5028 0.5924 0.5429 0.5235 0.5443 Ra-226 2.137 1.822 2.315 1.092 Ru-103 0.008073 U 0.001209 U -0.01 12 U -0.007452 U -0.0007379 U Ru-106 0.1816 U 0.02426 U -0.3158 U 0.1213 U 0.08412 U Sb-124 0.02423 0.01251 U 0.06974 0.01525 U -0.03174 U Sb-125 0.05304 U Te-129m 1.656 TI-208 0.7916 0.7864 0.9131 0.9041 0.813 Zn-65 0.06833 U -0.007822 U -0.03709 U -0.02695 U 0.04479 U Zr-95 0.03409 U 0.05488 U -0.01805 U 0.08747 0.03094 U SOF 0.094 I.
0.017 I 0.014 .
0.09 0.075 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 6 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD004.4 (3368) WD004.4 (3368) - WD004.4 (3368) WD004.5 (3369) WD005.1 (3370)
Sample ID WD004.4B -- WD004.4C ,WD004.4D - WD004.5A . - WD005.IA Date Sampled 9/22/1997 - .- 9/18/1997 r 9/18/1997 : 9/23/1997 8/21/1997 Ac-228 0.617 0.9122 2.052 0.6869 0.7655 Ag-108m -0.01554 U -0.007436 U : -0.00239 U 0.02225 U -0.01406 U Ag-110m 0.05443 -0.0439 U -; 0.001613 U 0.02972 U -0.06148 U Am-241 OU CU OU OU Ba-133 0.06187 U Bi-212 0.6666 0.9362 1.896 0.9174 0.3027 U ' -
Bi-214 0.3626 0.5306 1.286 0.4969 0.4193 Ce-144 -0.163 U -0.07975 U -0.3787 U -0.2144 U -0.1296 U Co-58 -0.007061 U -0.01728 U 0.00997 U -0.01598 U -0.03372 UJI Co-60 0.06536 0.7453 1.908 0.9228 ).06233 Cr-51 Cs-134 0.1029 -0.0589 U -0.4087 U 0.078161-0.174 U Cs-137 2.157 0.1369 0.2565 2.1241 0.9084 Fe-59 0.02808 U 0.05615 U 0.01449 U 0.03182 U 0.007737 U 1-131 1-132 1.686 U 1-133 1-135 K-40 16.71 19.12 44.45 13.91 16.73 Mn-54 -0.01478 U 0.04014 U -0.08104 U -0.00787 U 0.01448 U Mo-99 Nb-95 0.01338 U -0.00313 U -0.012 14 U 0.0357810.02095 U Np-239 Pb-212 0.6516 1.191 2.359 ; 0.694 0.9127 Pb-214 0.3157 0.5969 1.603 0.5462 0.4362 Ra-226 5.615 0.8982 U 1.618 Ru-103 -0.01135 U 0.0299 U -0.009035 U 0.01 123 U -0.000229 U Ru-106 -0.1871 U 0.1749 U 0.3933 U -0.1529 U OU Sb-124 0.00504 U -0.03899 U -0.03656 U 0.01788 U 0.03291 U Sb-125 Te-129m
' ; 1,. .'
T1-208 0.6281 0.9517 1.878 0.7025 0.7383 Zn-65 -0.0141 U 0.07554 U -0.3i232 U -0.1114 U 0.1087 U Zr-95 0.002583 U 0.0498 U -0.00571 U , 15..0.03458 U -0.0008437 U SOF' 0.205 ,. 0.165 0.415 0.376 0.087 U-not detected (value is not greater than 2 sigma); UM-nondetect (value' is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 7 of 17 Rad WST Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD005.1 (3370). 1lWD005.1 (3370) WD005.2 (3371) WD005.2 (3371)' WD005.3 (3372)
Sample ID WD005.1B ' jWD005.IE WD005.2A WD005.2B - WD005.3A Date Sampled 8/28/1997 - 10/1/1997 10/23/1997 10/23/1997 8/21/1997 Ac-228 0.79971 0.8684 0.6431 0.7629 0.7882 Ag-108m. -0.02443 U 0.01185 U 0.007073 U 0.01703 U -0.02171 U Ag-110mI -0.006707 U 0.0129 U -0.01534 U 0.02344 U 0.03317 U Am-241 OU OU OU Ba-133 Bi-212 -0.00000006048 U 1.11 0.7927 0.9581 0.6403 Bi-214 0.2881 0.3659 0.5751 0.6726 0.4007 Ce-144 0.06733 U -0.06407 U -0.02411 U -0.2954 U -0.04902 U Co-58 0.0152 U 0.009278 U 0.01026 U 0.001702 U -0.008821 U Co-60 0.04803 0.02491 U 0.04121 U -0.01429 U 0.2801 Cr-51 Cs-134 -0.02692 U -0.002494 U -0.09733 U 0.01666 U 0.2089 Cs-137 0.852 0.02447 U 0.2379 0.03284 U 3.703 Fe-59 0.001939 U 0.01791 U 0.02925 U -0.00771 U OU 1-131 0.04257 U 1-132 12.379 U 1-133 1.728 U 1-135 K-40 18.25 18.66 16.54 15.16 15.02 Mn-54 -0.01248 U 0.004046 U -0.004061 U 0.005044 U -0.02228 U Mo-99 K'
Nb95 -0.01051 U -0.03373 U 0.01221 U 0.0155 U 0.01371 U Np-239 -0.07726 U Pb-212 0.7752 0.777 0.7016 0.8683 0.7571 Pb-214 0.5403 0.4461 0.5033 0.7095 0.5272 Ra-226 1.85 0.9221 U Ru-103 0.00344 U -0.001741 U -0.01819 U 0.001788 U -0.02762 U Ru-106 -0.01716 U -0.05077 U -0.1468 U -0.118 U 0.02089 U Sb-124 0.01977 U 0.00547 U -0.007863 U -0.01519 U 0.008943 U Sb-I125 Te-129m Tl-208 0.6405 0.5858 0.6381 0.8723 Zn-65 -0.01 16 U 0.01529 U -0.1086 U -0.04883 U -0.09433 U Zr-95 0.05724 -0.02628 U -0.02865 U 0.02214 U -0.004299 U SOF 0.08 0.019 0.392 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 8 of 17 Rad WST-03 -- Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD005.3 (3372) WD007.1 V (3378) WD007.2 (3379) WD007.3 (3380) WD007.3 (3380)
Sample ID WD005.3D - WDOO7.1 WDO07.2 . WD007.3A - WD007.3B:
Date Sampled 10/1/1997 , 8/4/1997 . . 8/4/1997 8/5/1997 8/5/1997 -
Ac-228 0.6549 0.5274 0.7427 0.6272 0.7187 Ag-108m 0.0178 U -0.008532 U -0.004328 U 0.004457 U -0.01345 U Ag-110m -0.009557 U ' ' -0.03192 U 0.01301 U 0.01076 U 0.01755 U.
Am-241 OU Ba-133 Bi-212 0.9076 0.7138 . 0.6974 0.8136 0.7614 Bi-214 0.4638 0.2998 0.4522 0.4348 0.4526 Ce-144 0.06954 U 0.09067 U 0.0622 U -0.003809 U 0.2434 Co-58 -0.008476 U 0.01211 U 0.005266 U 0.003668 U 0.01801 U Co-60 0.03783 U 0.02756 U 0.03953 U -0.02559 U 0.00365 U Cr-51 Cs-134 0.007979 U -0.07215 U -0.08148 U -0.08698 U -0.06079 U Cs-137 0.1109 -0.004216 U -0.01091 U 0.007762 U 0.007555 U Fe-59 0.00731 U -0.04264 U -0.02627 U -0.05765 U 0.009666 U 1-131 1-132 1-133 2.386 U 1-135 K-40 20.15 13.17 15.64 15.19 15.26 Mn-54 0.004824 U 0.005363 U 0.01473 U -0.02963 U 0.01591 U Mo-99 1 Nb-95 0.007884 U 0.001637 U -0.00269 U 0.03166 U 0.02576 U Np-239 -0.1 124 U -0.3922 U Pb-212 0.6634 0.5756 0.7272 0.7114 0.6327 Pb-214 0.5685 0.3952 0.5044 0.412 0.3613 Ra-226 0.8411 1.127 0.925 1.009 U Ru-103 0.01977 U -0.00644 U 0.002168 U 0.0004085 U 0.0003976 U Ru-106 0.08122 U 0.1243 U 0.06007 U 0.02272 U 0.1883 U Sb-124 -0.002916 U -0.00 1888 U 0.001233 U 0.03727 U 0.01247 U Sb-125 0.008522 U Te-129m TI-208 0.866 0.5175 0.7808 0.6683 0.7079 Zn-65 0.004035 U -0.05045 U 0.06434 U : -0.02819 U -0.02142 U Zr-95 0.03673 U vvvsv UT 0.001814 -0.002692 U -0.02014 U -0.02178 U SOF 0.009 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 9 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD007.3 (3380) WD007.3 (3380) WD007.5 (3381) - WD007.5 (3381) WD007.5 (3381)
Sample ID WD007.3C WD007.3D WD007.5A - WD007.5B - WD007.5C Date Sampled 8/5/1997 8/6/1997 8/6/1997 - 8/6/1997 8/6/1997 ;
Ac-228 0.7799 0.7628 0.9806 0.7867 0.7448 Ag-108m -0.002985 U -0.003149 U 0.0175 U 0.00632 U -0.003089 U Ag-110mn -0.006282 U -0.002428 U -0.0006044 U 0.007367 U -0.01096 U Am-241 Ba-133 Bi-212 0.8684 1.655 1.078 0.8676 Bi-214 0.4036 0.4377 0.4981 0.4197 0.3959 Ce-144 -0.1166 U 0.06701 U -0.00728 U 0.04436 U -0.07272 U Co-58 -0.01454 U -0.001117 U 0.0242 U 0.009542 U 0.01451 U Co-60 0.0009789 U 0.04865 -0.000000003425 U' 0.009769 U OU Cr-51 Cs-134 -0.1006 U 0.01164 U 0.06683 U -0.1556 U 0.01188 U Cs-137 0.03714 0.002759 U 0.009913 U -0.02853 U -0.01793 U Fe-59 -0.02802 U 0.006234 U -0.01413 U 0.006138 U -0.00926 U 1-131 1-132 1-133 I-135 K40 14.64 17.64 15.92 17.02 17.05 Mn-54 0.008324 U -0.005996 U -0.00907 U -0.0003337 U 0.008872 U Mo-99 0.02784 U Nb-95 0.008023 U 0.01186 U -0.001536 U 0.002503 U Np-239 -0.3223 U Pb-212 0.7224 0.7618 0.8644 0.7989 0.7136 Pb-214 0.3824 0.5259 0.4492 0.4738 0.375 Ra-226 0.6707 1.911 0.9925 Ru-103 -0.008799 U 0.00336 U -0.004807 U 0.0004129 U -0.01574 U Ru-106 -0.003756 U -0.06876 U 0.2261 U 0.0653 U 0.1277 U Sb-124 0U 0.01241 U OU 0.0106 U 0.005759 U Sb-125 Te-129m TI-208 0.6458 0.6555 0.919 0.6367 0.6954 Zn-65 -0.1736 U -0.04049 U -0.1058 U -0.09704 U -0.08231 U Zr-95 -0.002998 U -0.01764 U 0.03736 U 0.04753 U -0.00177 U SOF 0.003 0.01 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 10 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD007.5 (3381) -WD007.7 (3382) WD007.8 (3383) J WD007.8 (3383) WD007.8 (3383) -
Sample ID. WD007.5D WD007.7 j WD007.8A WD007.8B - WD007.8C ;
Date Sampled 8/6/1997 8/111/1997 {-8/12/1 997 : j 8/12/1997 j8/12997 Ac-228 0.6672 0.6812 0.9371 0.8306 1.026 Ag-108m. 0.001858 U 0.00336 U -0.008745 U 0.001014 U -0.00 1008 U Ag-1 10m -0.002344 U 0.01039 U 0.02482 U -0.04411 U 0.04113 U I I Am-241 !
Ba-133 Bi-212 0.4994 0.5459 0.8127 0.598 1.585 Bi-214 0.3338 0.4495 0.4456 0.5083 0.4762 Ce-144 -0.04498 U 0.06734 U 0.01651 U -0.2157 U -0.07406 U Co-58 -0.01306 U -0.02381 1U 0.001671 U -0.04143 U -0.03243 U Co-60 -0.01042 U 0.02321 U -0.02396 U -0.003413 U 0.03054 U Cr-51 Cs-134 -0.0176 U -0.01479 U -0.02244 U 0.001793 U 0.005239 U Cs-137 -0.008483 U 0.02835 U 0.01653 U -0.008285 U -0.0117 U Fe-59 -0.01051 U -0.02224 U 0.02133 U -0.002954 U -0.0427 U 1-131 1-132 1-133 1-135 K-40 16.55 9.714 14.48 16.8 17.9 Mn-54 -0.002197 U -0.0015 U 0.01467 U -0.03333 U 0.007867 U Mo-99 Nb-95 -0.002257 U 0.02559 U 0.03712 -0.0223 U 0.006807 U Np-239 0.1773 U Pb-212 0.7876 0.6445
- 0.935 0.8097 0.8861 Pb-214 0.4249 0.4876 0.477 0.5505 0.5693 Ra-226 1.* 14 1.248 '1.064 Ru-103 0.008121 U 0.01222 U -0.002789 U -0.02708 U -0.004978 U Ru-106 0.1195 U 0U -0.06709 U 0.2347 -0.2916 U Sb-124 -0.02371 U -0.007782 U -0.05731 U 0.01693 U OU, Sb-125 Te-129m Tl-208 0.6797 0.8989 0.8678 0.9053 Zn-65 -0.02483 U -0.08131 U -0.03446 U -0.1034 U 0.08943 U Zr-95 0.02609 U -0.03335 U 0.03548 U -0.01974 U 0.03315 U SOF 0.003 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 11 of 17 Rad WST-03 -- Soil (pCilg)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD007.9 (3384) WD007.9 (3384) WD007.9 (3384) WD008.1 (3385) WD008.1 (3385)
Sample ID - WD007.9 WD007.9A WD007.9B WDOO8.IA WD008.1B :
Date Sampled 8/21/1997 r 8/14/1997 8114/1997 8/1811997 8/18/1997 -
Ac-228 0.7708 0.7998 ).5341 ; 0.6395 0.7361 Ag-108m 0.01855 U -0.009285 U 0.0001915 U -0.007723 U 0.002939 U Ag-i lOm -0.007496 U 0.01313 U -0.002741 U 0U -0.03202 U Am-241 Ba-133 Bi-212 0.9921 0.695410.00000005131 U 0.8545 1.035 Bi-214 0.6498 0.3552 0.3325 0.333 0.3379 Ce-144 0.1317 U 0.04483 U 0.05385 U 0.0002496 U -0.1551 U Co-58 0.006155 U -0.02035 U 0.002584 U -0.01106 U 0.03689 Co-60 0.01857 U 0.1007 0.0254 U 0.003938 U 0.03557 U Cr-51 .
Cs-134 -0.1018 U 0.01952 U 0.01268 U -0.02829 U -0.02383 U Cs-137 -0.00769 U 0.04312 U 0.01334 U -0.01902 U 0.0414 Fe-59 -0.08434 U -0.01062 U -0.009861 U 0.01823 U -0.03085 U 1-131 1-132 1.662 U 1-133 1-135 K-40 16.84 14.34 14.38 16.26 15.27 Mn-54 0.01432 U 0.001095 U 0.007681 U 0.01935 U -0.01993 U Mo-99 Nb-95 0.005623 U 0.0007311 U 0.02237 U -0.0234 U -0.004524 U Np-239 Pb-212 1.044 0.7021 0.6772 0.8012 0.6022 Pb-214 0.7124 0.3531 0.3755 ' 0.4342 0.4516 Ra-226 1.042 1.139 0.8602 U Ru-103 0.01485 U -0.002217 U -0.0063 U 0.005079 U 0.0008597 U Ru-106 -0.2573 U -0.139 U -0.105 U 0.1578 U -0.1145 U Sb-124 0.01024 U 0.007081 U 0.007888 U 0.03001 U -0.04433 U Sb-125 0.01045 U Te-129m TI-208 0.8289 0.5364 0.5113 0.6115 0.6162 Zn-65 -0.1062 U 0.05825 U -0.0421 U 0.00423 U -0.03371 U Zr-95 0.03281 U 0.03676 U 0.03678 U -0.01398 U 0.03484 U SOF 0.021 0.003 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 12 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station R6we, MA Station (Key) WD008.2 (3386) , WD008.3 (3387) WD008.3 (3387) WD008.4 (3388) WD008.5 (3389)
Sample ID. WD008.2C - WD008.3A WDO08.3B *YD008.4 WDOO8.5A Date Sampled 8/18/1997 8/18/1997 8/18/1997 8/21/1997 . 8/24/1998 Ac-228 0.6285 0.7707 0.5884 0.6229 0.8078 Ag-108m 0.009831 U -0.012 U -0.01623 U -0.004923 U 0.002586 U Ag-110m -0.009945 U -0.01508 U 0.03103 U -0.002322 U -0.006479 U Am-241 I1' OU Ba-133 Bi-212 0.4969 0.6657 0.8923 0.4609 0.7922 Bi-214 0.4081 0.4427 0.4982 0.4 155 0.4621 Ce-144 0.003993 U -0.0266 U 0.09625 U -0.1573 U 0.06214 U Co-58 0.001638 U 0.002618 U -0.01645 U -0.0251 U -0.01013 U Co-60 0.02276 U 0.008396 U -0.02475 U -0.01906 U 0.03164 U Cr-51 Cs-134 -0.05486 U 0.02244 U -0.05721 U -0.04237 U 0.1072 Cs-137 0.01018 U -0.01738 U -0.02798 U -0.00007328 U -0.04367 U Fe-59 -0.06151 U 0U -0.0353 U -0.05963 U -0.02435 U 1-131 I-132 1-133 I-135 K-40 16.66 15.69 15.01 1.3 20.99 Mn-54 0.01517 U -0.02053 U -0.01811 U -0.000242 U 0.02137 U Mo-99 K> Nb-95 0.02502 U -0.0002789 U -0.02646 U 0.01 137 U -0.009183 U Np-239 -0.2233 U Pb-212 0.7881 0.7652 0.6829 0.6577 0.8121 Pb-214 0.4307 0.5263 0.3852 0.3943 0.5822 Ra-226 0.7377 U 1.172 0.9372 U Ru-103 -0.005823 U -0.0004507 U -0.02494 U -0.01398 U 0.01569 U Ru-106 0.1131 U 0.1442 U -0.04891 U 0.03838 U OU Sb-124 0.02504 U 0.02066 U I I -0.006239 U 0.00687 U - OU Sb-125 Te-129m TI-208 0.6741 0.7185 0.8197 ' 0.6523 0.8445 Zn-65 -0.1339 U -0.02314 U 0.01864 U -0.07725 U -0.1227 U Zr-95 0.03833 U -0.04171 U -0.02922 U 0.0004064 U 0.01215 U SOF 0.016 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
a-Table 4 Page 13 of 17 Rad WST Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD008.5 (3389)i WD008.6 (3390) WD008.7 (3391) IWDO1O.1 (3392) WDO1O.2 (3393)
WD008.6A 1WD008.7A - - WD010.1 B WDOIO.2A Sample ID WD008.5B Date Sampled 8/24/1998 10/1/1997 8/24/1998 . 10/2/1997 :410/6/1997 Ac-228 0.9456 0.6703 0.8513 0.9334 0.8082 Ag-108m -0.03495 U -0.005635 U 0.02323 U 0.002836 U 0.003022 U Ag-110m -0.04107 U -0.0 1659 U -0.0241 U -0.02217 U -0.01107 U Am-241 OU OU OU OU OU Ba-133 Bi-212 108.5 0.716 0.5141 U 1.231 0.5381 U Bi-214 0.4988 0.4112 0.431 0.5716 0.4339 Ce-144 -0.0365 U 0.2309 U -0.06927 U 0.03437 U -0.1935 U Co-58 0.001108 U -0.003736 U -0.01422 U -0.0122 U 0.02943 U Co-60 0.012 U -0.01297 U 0.07779 0.02606 U 0.2809 Cr-51 i Cs-134 0.02475 U 0.002538 U -0.0797 U 0.01313 U -0.05178 U Cs-137 -0.002761 U -0.01246 U -0.002656 U -0.008721 U 0.03554 U Fe-59 -0.03694 U 0.04143 U -0.04874 U 0.0141 U -0.007335 U 1-131 1-132 13.63 U 1-133 1-135 K-40 20.71 18.29 19.5 21.58 14.48 Mn-54 0.01291 U -0.02089 U -0.008292 U -0.00427 U -0.001636 U Mo-99 Nb-95 0.06066 -0.03742 U -0.01916 U 0.0006169 U 0.03031 U Np-239 -0.3821 U 0.0231 U 0.3038 U Pb-212 1.014 0.8453 0.8074 1.013 0.8197 Pb-214 0.5533 0.485 0.5351 0.6654 0.521 Ra-226 1.055 1.466 Ru-103 0.01 144 U -0.0197 U -0.00289 U 0.002721 U -0.01601 U Ru-106 0.0229 U -0.02582 U 0.02203 U 0.08705 U 0.09707 U Sb-124 -0.02213 U 0.01427 U -0.008285 U -0.04026 U 0.004579 U Sb-125 -0.05039 U Te-129m Tl-208 0.9797 0.5717 0.591 0.7661 0.6879 Zn-65 0.06572 U -0.07771 U 0.05759 U -0.151 U 0.1255 U Zr-95 -0.02505 U -0.04898 U 0.01775 U -0.0213 U -0.01509 U SOF .I. I £ _________________ 0.016 I I 0.058 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 14 of 17 Rad WST-03 -- Soil (pCitg)
Yankee Nuclear Power Station Rowe;MA Station (Key) WD010.2 (3393). VWD010.3 (3394) : WD010.3 (3394) WD010.3 (3394) WDOII.1 (3395)
Sample ID.' WD010.2B - WD010.3A ' WD010.3B - WDO1O.3C - WDOIl.IA Date Sampled 10/6/1997 110/6/1997 . 10/6/1997 .- 10/6/1997 9/30/1997 Ac-228 1.04 0.6848 0.7054 0.8598 0.8578 OU Ag-108m 0.003292 U 0.01049 U 0.004372 U 0.0151 U Ag-llOm' -0.01561 U -0.02377 U -0.01165 U -0.01 145 U -0.01713 U Am-241 OU 0U OU OU OU Ba-133 Bi-212 1.991 1.144 0.7037 1.134 Bi-214 0.581 0.5193 0.5995 0.6116 0.4936 Ce-144 -0.04323 U -0.028 8U - -0.005479 U -0.167 U -0.07954 U Co-58 -0.004588 U -0.00725U 0.01052 U -0.01124 U 0.008784 U Co-60 0.
.06589 1-0.00533 U 0.03974 U , 0.4081 0.02722 U Cr-5I Cs-134 0.02876 U -0.01698 U 0.04731 U 0.005042 U 0.004774 U Cs-137 0.02646 U 0.006264 U -0.0 1788 U 2.131 0.01 154 U Fe-59 0.02637 U -0.05148 U -0.01389 U 0.05564 U -0.01299 U 1-131 1-132 1-133 1-135 K-40 19.53 15.44 20.091 36.78 19.29 Mn-54 -0.01244 U -0.008716 U -0.02875 U 0.0004054 1L -0.01786 U Mo-99 0.1663 U Nb-95 -0.01163 U -0.005403 U -0.01427 U 0.05139 U 0.01864 U Np-239 0.06431 U Pb-212 0.8998 0.7868
- 0.7749 ,1 0.9361 0.8739 Pb-214 0.5115 0.5145 0.5992 0.6792 0.4915 Ra-226 1.203 1.41 .1.471 Ru-103 0.005053 U 0.002308 U -0.0004673 U -0.006238 U -0.01107 U Ru-106 0.366 0.07503 U -0.04948 U 0.1984 U 0.09712 U Sb-124 -0.01052 U 0.01318 U 0.01202 U 0.03 U -0.01905 U Sb-125 -0.1292 U Te-129m TI-208 0.7636 0.7759 0.7544 0.8877 0.7157 Zn-65 -0.1932 U -0.0387 U .: i, ~0.04471 U 0.1312 U -0.1535 U Zr-95 -0.001011 U . 0.03989 U 0.04106 U -0.006856 U 0.03496 U SOF 0.019 0.258 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 15 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) - WDO11.2 (3396) WD011.2 (3396) WD011.3 (3397) WD011.3 (3397) WDO1 .3 (3397)
Sample ID IWD011.2A WDO1I.2B WD011.3A - WDO1I.3B WD011.3C - -
Date Sampled 10/2/1997 10/2/1997 9/30/1997 19/30/1997 9/30/1997 Ac-228 0.93591 0.89541 1.001 0.8902 0.8778 Ag-108m 0.0101 U 0.04012 0.01471 U 0.002754 U 0.000613 U Ag-110m 0.01526 U 0.01935 U 0.00749 U 0.00949 U -0.01212 U Am-241 0U 0U 0U OU 0U Ba-133 Bi-212 1.443 0.8603 1.02 0.5776 U Bi-214 0.4648 0.6051 0.4802 0.5619 0.5292 Ce-144 -0.1747 U -0.068 U -0.03744 U 0.0931 U -0.03549 U Co-58 0.02248 U 0.008879 U -0.02442 U 0.0277 U 0.006947 U Co-60 0.01908 U 0.03065 U 0.09028 0.005169 U 0.002855 U Cr-51 Cs-134 -0.02618 U -0.06244 U 0.005112 U -0.08312 U -0.01864 U ;
Cs-137 0.06404 0.0204 U i 0.3092 -0.0108 U -0.005665 U Fe-59 -0.04805 U 0.02404 U 0.01371 U -0.0008547 U -0.006192 U 1-131 1-132 1-133 1-135 K-40 18.4 21.68 16.8 20.01 19.36 Mn-54 0.01849 U 0.004528 U 0.003598 U 0.008638 U 0.01572 U Mo-99 Nb-95 0.009711 U 0.008411 U -0.006782 U 0.032941-0.008553 U Np-239 Pb-212 0.9136 1.003 0.7884 0.9011 1.054 Pb-214 0.6305 0.7953 0.5971 0.5536 0.4601 Ra-226 1.556 2.006 1.788 0.9214 U Ru-103 0.006742 U -0.02677 U 0.01025 U -0.008533 U -0.005286 U Ru-106 0.1458 U -0.08514 U 0.1025 U 0.1588 U -0.1602 U Sb-124 -0.008781 U 0.02681 U -0.01097 U 0.02114 U 0.004937 U Sb-125 Te-129m TI-208 1.028 0.765 0.88 0.9372 0.8192 Zn-65 -0.1048 U 0.01715 U -0.08574 U 0.02359 U -0.02578 U Zr-95 -0.01036 U 0.07218 U 0.005272 U 0.02761 U 0.03795 U SOF 0.005 0.005 0.044 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 16 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD011.4 (3398) WD011.5 (3399) IWD011.6 (3400) WDO11.6 (3400) WD012 (3401)
Sample ID WDO11.4A WDO11.5A, WDO11.6A ; - WD011.6B WD012A Date Sampled 3/31/1998 3/31/1998 j3/31/1998' 3131/1998 9/23/1997 Ac-228 0.694 !0.5532 0.6871 0.8357 0.8234 Ag-108m -0.01666 U -0.01003 U OU OU 0.02377 U Ag-110m 0.001741 U 0.006752 U -0.01868 U 0.02351 U -0.003835 U Am-241 0U 0U OU OU 0U Ba-133 Bi-212 0.4218 : 0.6572 0.614510.531 U Bi-214 0.4189 0.5159 0.4199 0.5855 Ce-144 -0.03445 U 0.01089 U - - -0.1909 U 0.07973 U -0.008082 U Co-58 0.01787 U 0.003785 U -0.01056 U -0.01773 U 0.007629 U Co-60 0.03542 U 0.01717 U 0.1163 0.05418 0.01364 U Cr-51 Cs-134 -0.06322 U -0.2665 U -0.1234 U OU -0.05856 U Cs-137 0.08757 0.02369 U 0.03824 U. 0.08598 -0.01568 U Fe-59 0.004582 U -0.004442 U, -0.06338 U -0.02523 U -0.007109 U 1-131 1-132 1-133 1-135 K-40 13.97 13.54 14.65 -0.1089 U 16.58 Mn-54 -0.0313 U 0.009646 U 0.01001 U 0.01522 U 0.01822 U Mo-99 Nb-95 0.002969 U 0.01497 U 0.01757 U 0.02162 U -0.01169 U Np-239 Pb-212 0.6353 0.5606 0.5751 0.728 0.6576 Pb-214 0.5174 0.4756 0.464 0.4272 0.5731 Ra-226 0.7252 U 1.372 0.9864 Ru-103 -0.00346 U 0.002478 U 0.01001 U. -0.02162 U 0.0191 U Ru-106 -0.01691 U -0.01639 U -0.01176 U 0.09191 U 0.2652 Sb-124 -0.01278 U 0.03186 U 0.02165 U 0.002514 U 0.007068 U Sb-125 Te-129m I. . I Tl-208 0.6226 ; 0.5918 0.76 0.6897 Zn-65 0.07209 U -0.05925 U 0.006013 U -0.0374 U -0.07069 U Zr-95 0.01283 U 0.0295 U 0.006933 U 0.008243 U -0.01688 U SOF 0.007 I _________________________
i 0.024 0.018 I _________________________ I 0.004 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 17 of 17 Rad WST-03 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD012 (3401) WD012 (3401)
Sample ID WD012B WD012C Date Sampled 9/23/1997 9/23/1997 Ac-228 0.724 0.9622 Ag-108m 0.004696 U -0.007911 U Ag-I lOin -0.01825 U 0.01057 U Am-241 0U OU Ba-133 Bi-212 0.4165 U Bi-214 0.5125 0.3885 Ce-144 0.2884 0.05171 U Co-58 -0.01367 U -0.003833 U Co-60 -0.02496 U 0.003916 U Cr-51 Cs- 134 -0.01154 U -0.02225 U Cs- 137 -0.02649 U 0.01351 U Fe-59 -0.05739 U -0.07031 U 1-131 1-132 1-133 1-135 K-40 18.22 16.68 Mn-54 -0.0 1082 U 0.02367 U Mo-99' -'-V Nb-95 0.001408 U 0.03974 U Np-239 Pb-212 0.7159 0.897 Pb-214 0.5573 0.5281 Ra-226 1.587 Ru-103 -0.009306 U 0.001614 U Ru-106 -0.07154 U -0.01771 U Sb-124 0.008408 U 0.02952 U Sb-125 0.08193 U Te-129m TI-208 0.8253 0.8258 Zn-65 -0.03554 U -0.00598 U Zr-95 -0.003072 U -0.02264 U SOF U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Building Historical Site Assessment and Classification Summary Survey Area Name: Radioactive Waste Compactor Building Designator: WST-04 Survey Area Description Survey Area WST-04 consists of the reinforced concrete pad and subsurface structures that comprise the radioactive waste compactor building remaining after demolition of the structure is complete.
WST-04 is located in the RCA yard area and is bounded by NOL-05 on the north, WST-03 on the east, WST-02 on the south and NOL-05 on the west.
Further division of this survey area into survey units as necessary is dependent upon the decommissioning end state configuration.
Page 1 of 4
a-Building Historical Site Assessment and Classification Summary Survey Area Name: Radioactive Waste Compactor Building Designator: WST-04 Survey Area History Survey area WST-04 was constructed under Plant Alteration (PA) #83-30 in 1983.
Survey area WST-04 was used to process (compact) and package radioactive waste. The survey history of the survey area WST-04 documents conditions of loose contamination present. When identified as contaminated survey area WST-04 was decontaminated.
The present location of the construction spoils generated by the Compactor Building is thought to be within the SCF area (OOL-09) of the sit. (Ref 1)
Scoping/Characterization Scoping surveys were performed and the data collected used to develop the YNPS Decommissioning Plan. (Ref 2)
DecommissioningActivities No decommissioning activities associated with the Compactor Building have been performed.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Radioactive Waste Compactor Building Designator WST-04 Findings The history of the WST-04 indicates that this structure is radiologically impacted as a result of plant operations.
The radionuclide mix likely to be present in WST-04 includes all radionuclides identified in the radioactive systems of the plant (Ref 3). The primary radionuclides of concern for survey area WST-04 are Co-60, Cs-137, Ag-108m, Sr-90 and tritium.
Current Status Survey area WST-04 remains in use as a material storage area and potentially may be impacted by ongoing decommissioning activities.
A soil sample location map (Figure 54) has been prepared to show the distribution of sampling locations in WST-04. Only samples representative of soils still present are included on the map (samples of soils representative of soils removed during remediation activities are not presented).
One survey media was assessed in WST-04, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling (a period spanning several years) as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substances of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for WST-04 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.011.
Maximum SOF for a single soil sample is 0.024. (key# 3377)
Minimum SOF for a single soil sample is 0.002. (key# 3374)
ClassificationStatement Based upon the historical use of survey area WST-04 and the radiological condition of area surrounding this survey area WST-04 is identified as a Class 1 Area.
Page 3 of 4:
0 Building Historical Site Assessment and Classification Summary Survey Area Name: Radioactive Waste Compactor Building Designator: WST-04 I'
Drawings 9699-FB-02 A.
9699-FC-36 C References
- 1. "Summary of Excavation Volumes for YNPS Construction Performed During the Time Period of Plant Operation," dated October 1997.
- 2. YNPS Decommissioning Plan, Rev. 0.0.
- 3. "Radionuclides for Building Surfaces and Soil DCGL Determinations," YA-
_ I REPT-00-001-03. I Page 4 of 4
Page l o I Table 1
- Sum of Fractions WST-04 -- Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 3377 WD00O5.6 WD006.6A 0.024 3376 WD00O6.5 WD006.5B 0.006 3376 WD0OO 5.5 WD006.5A : 0.004 3375 WD00O5.4 WD006.4C 0.017 3375 WD00O6.4 WD006.4B 0.022 3375 WD00O6.4 WD006.4A 0.007 3374 WDOO( 6.3 ~ WD006.3C 0.020 3374 WD00O6.3 WD006.3B 0.002-3374 WD0065 WD006.3A 0.006 3373 WD0OO WD006.1A 0.003 Min 0.002 Max 0.024 Mean 0.011
Table 2 Pagclof 1 Statistical Data Summary - WST-04 -- Soil Yankee Nuclear Power Station Rowe, MIA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCi/g 12 12 0.854 0.127 0.627 1.001 0.862 Ag-108m pCi/g 1 12 0.023 0.023 0.023 0.023 Ag-I 11m pCi/g 1 12 0.039 0.039 0.039 0.039 Am-241 pCi/g 0 12 0.000 Bi-212 pCi/g 9 11 1.022 0.210 0.764 1.390 0.975 Bi-214 PCi/g 12 12 0.437 0.054 0.334 0.532 0.452 Ce-144 pCi/g 0 12 0.000 Co-58 pCi/g 0 12 0.000 Co-60 pCilg 4 12 0.061 0.003 0.057 0.063 0.062 Cs-134 PCi/g 0 12 0.000 Cs-137 pCi/g 8 12 0.083 0.035 0.049 0.151 0.076 Fc-59 pCi/g 0 12 0.000 K-40 PCilg 12 12 17.212 1.981 14.020 20.020 17.570 Mn-54 pCi/g 2 12 0.041 0.009 0.035 0.048 0.041 Nb-95 pCi/g 0 12 0.000 Np-239 pCi/g 0 1 0.000 Pb-212 pCi/g 12 12 0.841 0.117 0.627 0.995 0.858 Pb-214 pCi/g 12 12 0.486 0.063 0.378 0.583 0.490 Ra-226 pCi/g 6 6 1.187 0.088 1.070 1.298 1.203 Ru- 103 pCi/g 0 12 0.000 Ru-106 PCi/g 0 12 0.000 Sb-124 pCi/g 0 12 0.000 TI-208. pCi/g 11 11 0.806 0.126 -0.618 1.028 0.792 Zn-65 pCilg 1 12 0.174 0.174 0.174 0.174 Zr-95 IDci/[! 1 12 0.068 0.068 0.068 0.068
(. (.,
Page of 1 Table 3 Summary of Detected Results Above Criteria WST-04 -- Soil
..Yankee Nuclear Power Station Rowe, MA DCGL_Soil
- Sample Criterion # Detects Above Maximum Parameter # Detects - Results: 4Concentration Units Criterion Detected
- Ac-228 12 12 pcilg 1.00 0
Ag-108m 1 12 * - 8.52 pCi/g 0.02 0
Ag-i lOim 1 12 pCi/g ..0 0.04 Am-241 0 12 44.35 pCi/g 0
Bi-212 9 11 pCi/g 1.39 0
Bi-214 12 12 pCi/g 0.53 0
Ce-144 0 12 pCi/g Co-58 0 12 pCi/g 0 Co-60 4 12 4.84 pCi/g 0.06 Cs-134 0 12 6.71 pCi/g 0 O
Cs-137 8 12 12.24 pCi/g 0 0.15 Fe-59 0 12 pCi/g 0 K-40 12 12 pCi/g 0 20.02 Mn-54 2 12 21.66 pCi/g' 0 0.05 Nb-95 0 12 pCi/g 0 Np-239 0 1 pCi/g 0 Pb-212 12 12 pCi/g 0 1.00 Pb-214 12 12 pCi/g 0 0.58 Ra-226 6 6 pCi/g 0 1.30 Ru-103 0 12 pCi/g 0 Ru-106 0 12 68.21 pCi/g 0 Sb-124 0 12 pCi/g TI-208 11 11 pCi/g 0 1.03 Zn-65 1' 12 pCi/g 0 0.17 Zr-95 1 12 pCi/g 0 0.07
a-Table 4 Page 1 of3 Rad WST-04N - Soil (peCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD006.1 (3373) WD006.1 (3373) WD006.1 (3373) WD006.3 (3374) WD006.3 (3374)
Sample ID WD006.1A WD006.IB WD006.1C WD006.3A WD006.3B Date Sampled 6/8/1998 6/8/1998 6/8/1998.. 6/9/1998 6/9/1998 .
Ac-228 0.6773 0.7814 0.9728 0.6267 0.9201 Ag-108m 0.02342 -0.01321 U 0.0004407 U -0.001038 U 0.001821 U Ag-110m 0.03934 0.02997 U 0.005778 U -0.004543 U 0.02609 U Am-241 0U OU OU OU OU Bi-212 0.9587 1.273 0.3186 U 1.1 Bi-214 0.334 - 0.4571 0.4617 0.3823 0.4382 Ce-144 -0.07113 U 0.05921 U -0.05643 U -0.04661 U 0.03432 U, Co-58 0.004872 U -0.0002575 U -0.004897 U -0.01571 U -0.01061 U Co-60 0.01081 U 0.0336 U 0.007323 U 0.02699 U -0.007401 U Cs-134 -0.05145 U -0.01226 U 0.01031 U 0.009758 U -0.03375 U Cs-137 0.03796 U 0.005114 U -0.008494 U 0.05268 0.009836 U Fe-59 0U 0.06312 U 0.005743 U -0.03741 U -0.05379 U K-40 14.31 15.3 18.96 14.02 20.02 Mn-54 -0.01762 U -0.01821 U 0.0328 U 0.03545 0.0475 Nb-95 -0.0005752 U -0.003564 U 0.0004958 U 0.01359 U 0.01656 U Np-239 Pb-212 0.6573 0.8424 0.7966 0.6274 0.7496 Pb-214 0.3778 0.4479 0.4787 0.3969 0.4369 Ra-226 1.07 1.185 Ru-103 -0.01294 U -0.03199 U 0.0157 U 0.005582 U -0.004395 U; Ru-106 -0.07185 U 0.09373 U 0.1062 U 0.01986 U -0.1636 U Sb-124 0.001139 U -0.02059 U -0.005724 U 0U -0.00767 U K>
TI-208 0.6181 , 0.9405 1.028 0.6992 0.6906 Zn-65 -0.1082 U -0.03196 U 0.1744 0.01387 U -0.0001786 U Zr-95 -0.0526 U 0.004397 U -0.0352 U -0.02461 U 0.06806 SOF 0.003 0.006 0.002 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 2 of 3 Rad WST-04 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD006.3 (3374). WD006.4 (3375) WD006.4 (3375) WD006.4 (3375) WD006.5 (3376)
Sample ID WD006.3C WD006.4A WD006.4B WD006.4C WD006.5A Date Sampled 6/9/1998 6/8/1998 - 6/8/1998
- 6/8/1998 6/4/1998 Ac-228 0.9755 1.001 0.8183 1 0.7551 Ag-108m -0.001301 U 0.003777 U 0.00445 U 0.01014 U -0.004911 U Ag-110m -0.009827 U -0.03714 U- -0.04891 U -0.01708 U 0.00003945 U Am-241 0U 0U 0U 0U 0U Bi-212 0.9746 0.5574 U 0.9152 1.39 1.051 Bi-214 0.4649 0.4663 0.4618 0.5323 0.4407 Ce-144 0.0185 U 0.1999 U 0.0009948 U 0.08567 U -0.02016 U Co-58 0.008339 U 0.002957 U -0.002895 U 0.002776 U -0.01766 U Co-60 0.06195 0.02219 U 0.06268 . 0.06124 0.03547 U Cs-134 -0.01847 U -0.06223 U 0.01764 U. 0U -0.03833 U Cs-137 0.09317 0.08064 0.1108 0.04927 0.05432 Fe-59 0.003121 U 0.04588 U -0.0717 U -0.01881 U -0.03249 U K-40 16.21 17.03 18.62 18.74 16.29 Mn-54 0.008193 U -0.02268 U -0.01475 U 0.01283 U 0.002204 U Nb-95 -0.01961 U 0.01878 U 0.02862 U 0.02636 U 0.0234 U Np-239 -0.7086 U Pb-212 0.8989 0.8692 0.9551 0.9835 0.8535 Pb-214 0.5709 0.5004 0.5828 0.5204 0.4798 Ra-226 1.099 1.221 Ru-103 -0.007433 U 0.007437 U 0.02554 U 0.009317 U -0.0137 U Ru-106 0.05295 U -0.04467 U -0.04491 U. -0.09842 U 0.2347 U Sb-124 0.02094 U -0.009285 U 0.003247 U -0.003703 U -0.002229 U TI-208 0.7857 0.921 0.8915 0.7009 Zn-65 -0.06637 U 0.09656 U -0.08121 U -0.1059 U 0.03434 U Zr-95 -0.01725 U 0.04721 U 0.01872 U 0.04743 U 0.02957 U SOF ! 0.02 0.007 0.022 0.017 0.004 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 3 of 3 Rad WST-04 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) WD006.5 (3376) - WD006.6 (3377)
Sample ID WD006.5B WD006.6A Date Sampled 6/4/1998 6/8/1998 Ac-228 0.8323 0.891 Ag-108m 0.01521 U 0.002957 U Ag-i 1Om 0.002978 U -0.004772 U Am-241 0U 0U Bi-212 0.7708 0.7638 Bi-214 0.363 0.4459 Ce-144 0.08324 U -0.2174 U Co-58 0.006368 U 0.00 1582 U Co-60 0.003827 U 0.05657 Cs-134 0.05101 U 0.006366U Cs-137 0.07121 0.1509 Fe-59 -0.04425 U -0.01769 U K-40 18.93 18.11 Mn-54 -0.002519 U 0.009278 U Nb-95 -0.01356 U 0.02884 U Np-239 Pb-212 0.8629 0.995 Pb-214 0.5362 0.5002 Ra-226 1.247 1.298 Ru-103; 0.001111 U 0.01184 U Ru-106 0.04412 U 0.06485 U Sb-124 0.001239 U -0.01583 U TI-208 0.7952 0.7916 Zn-65 -0.06607 U -0.05863 U Zr-95 -0.009496 U 0.01437 U SOF 0.006 0.024 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
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Building Historical Site Assessment and Classification Summary Survey Area Name: Vapor Container & Reactor Support Structures Designator: BRT-01 Survey Area Description Survey Area BRT-Ol consists of the reinforced concrete structures that comprise the foundations and support pedestals of the sixteen Vapor Container (VC) supports and the eight Reactor Support Structure (RSS) remaining after demolition of the VC and RSS is complete.
BRT-01 is located in the RCA yard area within the bounds of survey areas NOL01 and NOL-06.
Further division of this survey area into survey units as necessary is dependent upon the decommissioning end state configuration.
Page 1 of 4
I-Building Historical Site Assessment and Classification Summary Survey Area Name: Vapor Container & Reactor Support Structures Designator: BRT-01 Survey Area History Survey area BRT-0l includes all concrete structures associated with the sixteen VC supports and eight RSS foundations. It also includes the concrete supports f6r the non-return valve house, the lower pipe chase support and the fuel transfer chute support. The structures have exterior surfaces only. There are no sources of radioactivity directly associated with the support structures. The primary mode of contamination of these structures is as a result of contamination spread within the RCA yard.
Scoping/Clharacterization No scoping/characterization data is available for the anticipated end state of survey area BRT-O 1.
DecommissioningActivities Decommissioning activities performed in BRT-01 have removed the non-retum valve house and associated piping and secondary vent stack.
Planned decommissioning activities will removed all structures above grade 1022'.
Page 2 of 4
Building Historical Site Assessment and Classification Summary Survey Area Name: Vapor Container & Reactor Support Structures Designator: BRT-01 Findings Survey area BRT-01 was impacted by contamination spread within the RCA resulting from plant operations.
The radionuclide mix likely to be present in BRT-01 includes all radionuclides identified in the radioactive systems of the plant (Ref 1.). The primary radionuclides of concern for survey area NOL-06 are Co-60, Cs-137, Ag-108m, Sr-90 and tritium.
CurrentStatuts Survey area BRT-01 potentially may be impacted by ongoing decommissioning activities.
ClassificationStatement Based upon the historical use of survey area BRT-01 and the radiological condition of area surrounding this survey area BRT-01 is identified as a Class 1 Area.
Page 3 of 4
a-Building Historical Site Assessment and Classification Summary Survey Area Name: Vapor Container & Reactor Support Structures Designator: BRT-O1 Drawings 9699-FC-50 D 9699-FC-59 A 9699-FC-59 B References
- 1. "Radionuclides for Building Surfaces and Soil DCGL Determination," YA-REPT-00-001-13.
Page 4 of 4
Historical Site Assessment and Classification Summary Area Name: Non-Impacted Area Designator: NIA-O 1 Area Description The data evaluation presented below represents samples taken in the non- impacted area.
The locations of these samples are presented in Figure 7-5.
A soil sample location map (Figure 7-5) has been prepared to show the distribution of sampling locations in NIA-01. One survey media was assessed in NIA-01, Soil. The results and analyses (Tables 1-4 in this section) of the samples plotted as "key numbers" on the map represent the radiological status at the time of sampling as sums of fractions of the soil DCGL.
Only those samples with detectable results of the radionuclides of concern appear in Table 1. For this reason the number listed as minimum does not include samples that did not have detectable quantities of the radiological substaires of concern. An assessment of the maximum, minimum and mean sum of fractions (SOF) for NIA-01 is presented at the end of Table 1 for each survey medium. The results are summarized below.
Soil: Mean SOF is 0.060.
Maximum SOF for a single soil sample is 0.134. (key# 341)
Minimum SOF for a single soil sample is 0.012. (key# 340)
ClassificationStatement Based on the information evaluated in section 7.2.2 (Non-Impacted Area Justification) this area is classified as Non-Impacted Page 1 of I
p Page I of 2 Table I Sum of Fractions NIA Soil I Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions 328 PROOI 4017 PROOIGUFU017 0.042 314 PROOI 4003 PROOIGUFDO03 0.025 315 PROOI -4004 PROOIGUFU004 0.015 316 PROOI-( 005 PROOIGUFU005 0.024 PRO .- 1 317 PROOI -(006 PROOIGUFU006 0.068 318 007 PROOIGUFU007 0.035 319 PROOI -()08 PROOIGUFU008 0.020 320 PROOI -009 PROO I GUFU009 0.076 321 PROOI -010 PROOIGUFUOIO 0.060 322 PROO1-O I I PROOIGUFUOI I 0.051 323 PROOI -012 PROOIGUFU012 0.043 324 PROOI -013 PROOIGUFU013 0.047 325 PROOI -014 PROOIGUFU014 0.059 313 PROOI -001 PROOIGUFUOOI 0.070 327 PROO I-016 PROOIGUFU016 0.075 342 PROOI -032 PROOIGUFU032 0.059 329 PROOI -018 PROOIGUFU018 0.098 330 PROOI -019 PROOIGUFU019 0.058 331 PROOI -020 PROO IGUFU020 0.131 332 PROOI -021 PROOIGUFU021 0.041 333 PROOI -022 PROOIGUFU022 0.069 334 PROOI -023 PROOIGUFU023 0.019 335 PROOI -024 PROOI GUFU024 0.089 337 PROOI -026 PROOI GUFU026 0.096 338 PROOI -027 PROOIGUFU027 0.085 339 PROOI-028 PROOIGUFU028 0.102 340 PROOI -029 PROO I GUFU029 0.012
Page 2 of 2 Table I:
- : Sum of Fractions NIA-O1 - Soil Yankee Nuclear Power Station Rowe, MA Station Key Station Sample ID Sum Of Fractions
- 341 PROOW - 030 PROOIGUFU030 0.134 326 PROOI - 015 PROOIGUFU015 0.037 Min 0.012 Max 0.134 Mean 0.060
Table 2 Page I of 1 Statistical Data Summary - NIA-01 -- Soil Yankee Nuclear Power Station Rowe, MIA Parameter Units # Detects # Sample Mean Std. Dev Minimum Maximum Median Results Ac-228 pCi/g 28 0.678 0.217 0.354 1.203 0.640 Ag-108m pCilg 30 0.000 Ag-I1 Om pCilg 30 0.000 An-241 pCilg 30 0.000 Bi-212 pCilg 16 0.978 0.715 0.517 3.140 0.741 Bi-214 pCilg 24 0.444 0.072 0.343 0.559 0.444 Ce-144 pCilg 30 0.267 0.030 0.246 0.289 0.267 Co-58 pCilg 30 0.000 Co-60 pCi/g 30 0.000 Cs--134 pCilg 30 0.179 0.179 0.179 0.179 Cs-137 pCilg 30 0.718 0.397 0.148 1.643 0.709 Fe-59 pCi/g 30 0.113 0.113 0.113 0.113 1-133 pCilg 0.000 K-40 pCilg 30 13.986 4.132 1.715 22.380 13.540 Kr-85 pCilg 0.000 La-140 pCilg 1 0.000 Mn-54 PCi/g 30 0.043 0.011 0.036 0.051 0.043 Mo-99 pCilg l 0.000 Nb-94 pCi/g 0.051 0.051 0.051 0.051 Nb-95 pCilg 30 0.000 Np-239 pCilg 2 0.000 Pb-212 pCilg 29 0.580 0.263 0.208 1.302 0.587 Pb-214 pCilg 29 0.447 0.082 0.275 0.640 0.461 Ra-226 pCilg 17 1.687 0.291 1.374 2.229 1.583 Ru- 103 pCilg 30 0.000 Ru-106 pCi/g 30 0.000 Sb-124 pCilg 30 0.063 0.063 0.063 0.063 Sb-125 pCilg 5 0.000 Sn-113 pCilg 0.000 TI-208 pCilg 18 0.658 0.217 0.326 1.261 0.605 Zn-65 pCilg 30 0.000 Zr-95 D~ci/L2 30 0.074 0.015 0.063 0.084 0.074
(: ( U
Page I of 1 Table'3 Summary of Detected Results Above Criteria NIA Soil Yankee Nuclear Power Station Rowe, MIA DCGL_Soil'"'
Sample' Criterion # Detects Above Maxim umr Parameter # Detects Results 'Concentration 'Units Criterion Detected Ac-228 27 28 pCi/g 0; 1.20 Ag-108m 0 30 8.52 pCi/g 0 Ag-i 1lm 0 30 pci/g 0, Am-241 0 30 44.35> pCilg 0 Bi-212 12 .16 pCi/g 0 '3.14 Bi-214 24 24 pCilg 0 0.56 O'
Ce-144 2 30 pci/g 0 0.29
.I I. 4. 8 Co-58 0 30 pCi/g 0 Co-60 0 30 ,4.84 pCi/g O0 Cs-134 i 30 6.71 pci/g 0 0.18 Cs-137 29 30 12.24 pPi/g 0' 1.64 Fe-59 i 30 pCi/g 0 0.11 1-133 0 1 ?. I pCi/g 0
K-40 30 30 pCi/g 22.38 0
Kr-85 0 pCi/g 0
La-140 0 pCi/g 11 0 Mn-54 2 21.66 pCi/g 0.05 1I 0 Mo-99 0 pci/g 30 30 0 Nb-94 1 I 8.53 pCi/g 0.05 0
Nb-95 0 Np-239 0 2 0 Pb-212 29 29 pCi/g 0 1.30 Pb-214 29 29 pCi/g 0 '0.64 Ra-226 11 17 pCi/g 0 2.23 Ru-103 0 30 pCilg 0 Ru- 106 0 30 68.21 pCi/g 0 Sb-124 i 30 pCi/g *0 0.06 Sb-125 0 5 37.73 pCi/g 0 Sn-I13 0 I pCi/g 0 TI-208 18 18 . pCi/g 0 1.26 Zn-65 0 30, pCi/g 0 Zr-95 2 30 pCi/g 0 0.08
Table 4 Page I of 6 Rad i ., NIA-Ol -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) PROO1-003 (314) PROO1-001 (313): PROOI-004 (315) PROO1-005 (316) PROOI-006 (317)
Sample ID PR001GUFDO03 PRO01GUFUOOI PRO01GUFU004 PR001GUFU005 PROOIGUFU006 Date Sampled 8/24/1998 8/24/1998 8/25/1998 8/24/1998 8/24/1998 Ac-228 0.5894 0.6403 0.786 0.3984 0.6449 Ag-108m -0.02681 U -0.03076 U -0.0043 U 0.01296 U -0.02624 U Ag-1 10m 0.02602 U. 0.04414 U 0.01956 U 0.009628 U -0.01776 U Am-241 0U 0U 0U 0U 0U Bi-212 1.117 0.5169 0.5835 Bi-214 0.515 0.3712 0.5048 0.4587 0.4417 Ce-144 -0.135 U -0.04514 U 0.08899 U 0.07789 U 0.105 U Co-58 -0.007514 U 0.002696 U 0.02782 U 0.03958 U 0.02287 U Co-60 0.007521 U -0.009002 U -0.05305 U -0.02841 U -0.0674 U Cs-134 -0.04433 U -0.04639 U -0.03978 U 0.016 U -0.01687 U Cs-137 0.3018 0.8549 0.1782 0.289 0.7539 Fe-59 -0.001637 U -0.01421 U -0.0592 U 0.1134 0.01201 U 1-133 K-40 14.66 14.45 18.65 18.26 11.88 Kr-85 La-140 Mn-54 0.02042 U -0.005933 U -0.007164 U 0.01803 U -0.01531 U Mo-99 Nb-94 0.05059 Nb-95 0.007381 U 0.01233 U -0.02259 U 0.0332 U -0.04397 U Np-239 Pb-212 0.6791 0.6425 0.835 0.3631 0.52 Pb-214 0.4836 0.4341 0.5255 0.5337 0.4644 Ra-226 1.543 1.823 Ru-103 0.01676 U -0.01492 U 0.007747 U -0.02633 U -0.0185 U Ru-106 0.00000002524 U -0.05089 U -0.1236 U 0U -0.02071 U Sb-124 -0.01019 U 0.03086 U 0U 0.018 U 0.03795 U Sb-125 0.01547 U Sn-113 TI-208 0.5761 0.7972 0.3256 Zn-65 -0.015 14 U -0.07885 U -0.06477 U -0.03422 U 0.04617 U Zr-95 0.07164 U 0.02584 U 0.05728 U 0.03486 U 0.009103 U SOF 0.025 0.07 0.015 0.024 0.068 k'
U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 2 of 6 Rad NIA-OI -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) PRO01-007 (318) (PRO01-008 (319) ,' PROOI-009 (320) PRO0I-010 (321) PROOI-OII (322)
Sample ID : PROO1GUFU007 PRO01GUFU008 PROOIGUFUOO9 ; PROOIGUFUOIO PROOIGUFUOIlI Date Sampled 8/2411998 '18124/1998 8/24/1998 - 8/24il998 8/24/1998 Ac-228 1.063 , 0.7188 0.5197 1.203 ().7853 Ag-108m 0.0002096 U -0.002759 U 0.003541 U -0.0 1396 U 0.02559 U Ag-I lOIm -0.0002988 U -0.01575 U -0.0i628 U -0.02202 U 0.03384 U Am-241 OU 0U Ou, OU OU Bi-212 0.618 5.815 U 0.7289 U Bi-214 0.5456 - 0.4984 0.35051 ).4032 Ce-144 -0.08908 U -0.1 132 U -0.03716 U 0.0471 U ).2885 Co-58 -0.04205 U 0.01468 U 0.031 U OU, 0.002213 U Co-60 0.02823 U 0.00378 U -0.02651 U -0.003418 U -0.05621 U Cs-134 0.01988 U -0.1071 U 0.0224 U -0.1493 U -0.01972 U Cs-137 . 0.4259 0.2492 0.9047 0.7287 ).6201 Fe-59 -0.0494 U -0.04735 U 0.1064 U -0.1506 U 0.01906 U 1-133 K-40 18.39 13.63 12.84 16.12 12.48 Kr-85 La-140 - .i Mn-54 0.02911 U 0.02294 U .,
0.0359910.02322 U 0.003681 U Mo-99 0.4452 U Nb-94 Nb-95 0.0007378 U 0.03288 U -0.05519 U 10.01818 U -0.0008109 U Np-239 Pb-212 0.9382 0.7492 n 2nA1 1.302 ).7028 j V.JU -
Pb-214 0.5174 0.5164 0.4584 0.5176 ).4331 Ra-226 1.421 1.376 1.11 13 1.583 1.848 Ru-103 -0.0096831U -0.005804 U -0.01341 U -0.004219 U 0.0004988 U Ru-106 0.2028 U 0.08902 U 0.3471 U 0.1304 U 0.229 U Sb-124 -0.04129 U 0.01309 U 0.004201 U 0.05857 U -0.01282 U Sb-125 -0.1618 U Sn-113 TI-208 0.9667 0.5916 1.261 ).6717 Zn-65 0.1097 U -0.1 138 U -0.09199 U -0.1002 U 0.05538 U Zr-95 0.005996 t 0.02072 U -0.03385 U 0.0551 U 0.0265 U SOF 0.035 1 ..- ,', 0.02 : f .- 0.076 0.06 0.051 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
M-Table 4 Page 3 of 6 Rad NIA-0 I -Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) PR001-012 (323) PRO0I-013 (324) PR001-014 (325) PROOl-OIs (326) PR001-016 (327)
Sample ID PRO01GUFU012 PROOIGUFU013 PROOIGUFUO14; PROOIGUFU015 PROOIGUFU016 Date Sampled 8/24/1998 8/24/1998 8/25/1998 8/25/1998 8/25/1998 Ac-228 0.6126 0.1735 U 0.6461 0.4495 0.5528 Ag-108m 0.01365 U -0.002616 U 0.01008 U 0.006894 U 0.01 177 U Ag-i lOm 0.02237 U -0.05268 U 0.01316 U 0.03643 U 0.005292 U Am-241 OU OU OU OU OU Bi-212 0.9166 0.6004 0.461 U 1.175 Bi-214 0.3537 0.3769 0.343 Ce-144 -0.2007 U -0.02332 U -0.1618 U 0.2165 U -0.09754 U Co-58 -0.004918 U -0.03607 U 0.02161 U 0.008687 U -0.03509 U Co-60 -0.02498 U -0.02752 U 0.0168 U -0.01776 U -0.03129 U Cs-134 0.007604 U -0.01033 U 0.006173 U 0.009674 U 0.1792 Cs-137 0.5237 0.5758 0.7261 0.4536 0.5935 Fe-59 -0.007883 U -0.01444 U 0U 0.05239 U -0.0124 U 1-133 K-40 22.38 8.201 16.36 13.71 9.9 Kr-85 La-140 Mn-54 -0.001758 U -0.02323 U 0.002434 U -0.02334 U -0.04682 U Mo-99 Nb-94 Nb-95 -0.00171 U -0.001252 U 0.04442 U -0.01933 U -0.03915 U Np-239 0.1537 U Pb-212 0.5626 0.3808 0.3112 0.6167 Pb-214 0.3328 0.3624 0.4085 0.3351 0.4024 Ra-226 0.8272 U 1.374 1.122 U Ru-103 0U 0.03469 U -0.02058 U -0.009459 U 0.02817 U Ru-106 0.02866 U -0.07367 U -0.04695 U -0.08562 U -0.01257 U Sb-124 0.007818 U 0.06879 U OU OU OU Sb-125 0.04495 U Sn- 13 TI-208 0.6189 0.5657 Zn-65 -0.1609 U -0.006346 U -0.04015 U 0.01991 U -0.08128 U Zr-95 0.04804 U -0.001101 U 0.02374 U 0U 0.009434 U SOF 0.043 0.047 0.059 0.037 0.075 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 4 of 6 Rad NIA-01 -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key): PRO01-017 (328) PR001-018 (329) -PR00I-019 (330) IPROOI-020 (331) PROOI-021 (332)
Sample ID PROOIGUFU017:- PROOIGUFU018- PROO1GUFU019 -PROO1GUFU020 PROO1GUFU021 Date Sampled' 8/24tl998 - 8/24/1998 ; 8/24/1998 - 8/24/1998 - 8/24/1998 Ac-228 0.4307 0.9353 0.3544 0.4121 0.5315 Ag-108m 0.004206 U -0.007407 U 0.02988 U 0.004631 U -0.0 1937 U Ag-110m -0.01795 U 0.0193 U 0.0395 U 0.0406 U 0.02421 U Am-241 OU. oUt Ou 0U OU Bi-212 0.6496 Bi-214 0.4013 0.4365 0.5556 Ce-144 0.2456 -0.1887 U -0.1207 U 0.2424 U 0.07019 U Co-58 -0.02283 U -0.0594 U -0.02945 U -0.03302 U -0.0i59 U Co-60 -0.02575 U Ou -0.007929 U -0.0401 U -0.03636 U Cs-134 -0.2912 U -0.1069 U -0.01667 U -0.02344 U -0.09664 U Cs-137 0.5106 1.204 0.7093 1.605 i 0.505 Fe-59 0.01017 U 0.01525 U -0.00132 U -0.01204 U 0.04862 U 1-133 22.64 U K-40 13.45 1.715 9.733 13.3 12.2 Kr-85 La-140 0.1917 U Mn-54 0.02039 U 0.02767 U 0.01357 U -0.03168 U -0.02308 U Mo-99 Nb-94 Nb-95 -0.01589 U -0.01596 U 0.03366 U -0.02048 U -0.0361 U Np-239 Pb-212 0.3706 0.6056 0.2083 0.4073 0.5003 Pb-214 0.3949 0.3537 0.4758 0.64 Ra-226 0.9109 U Ru-103 0.017 U 0.05607 U 0.01539 U 0.005903 U 0.001415 U Ru-106 -0.03694 U -0.4801 U 0.07656 U 0.1893 U -0.2687 U Sb- 124 0.002016 U 0.01204 U -0.01173 U OU -0.03134 U Sb-125 Sn-113 0.03977 U Tl-208 0.3695 0.5769 Zn-65 -0.1448 U 0.05308 U -0.07704 U 0.02515 U 0.02918 U Zr-95 -0.008517 U 0.0955 U 0.06301 0.02461 U 0.003164 U SOF 0.042 0.098 0.058 'l ~. 0.131 0.041 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
3L-Table 4 Page 5 of 6 Rad NIA-Ol -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) PROO1-022 (333) PR0O1-023 (334) PROOI-024 (335) PROO1-025 (336) PROOI-026 (337)
Sample ID PROO1GUFU022 PROO1GUFU023 PROO1GUFU024 PROOIGUFU025 PROO1GUFU026 Date Sampled 8/24/1998 8/24/1998 8/24/1998 8/24/1998 8/24/1998 Ac-228 0.8117 0.6694 0.7645 1.028 Ag-108m -0.006974 U 0.00688 U 0.01022 U -0.01008 U -0.002721 U Ag-lO0m 0.009898U 0.02471 U -0.01831 U -0.05412U 0.01574U Am-241 OU 0U OU OU OU Bi-212 3.14 0.9569 0.8324 Bi-214 0.4642 0.3588 0.5585 0.5078 0.3527 Ce-144 0.1146 U -0.1277 U -0.05024 U 0.0241 U -0.3766 U Co-58 0U -0.003107 U 0.01075 U -0.01614 U -0.02755 U Co-60 0.005842 U -0.008143 U 0.005853 U -0.02495 U -0.007636 U Cs-134 -0.06158 U - 0.009315 U -0.04735 U -0.08943 U -0.02149 U Cs-137 0.8418 0.2321 1.09 0.006883 U 1.169 Fe-59 0.04689 U -0.00872 U -0.04021 U -0.03148 U 0.0843 U 1-133 K-40 12.61 12.58 11.27 15.23 13.42 Kr-85 5.63 U La-140 Mn-54 0.03296 U -0.01915 U 0.01704 U -0.02036 U 0.02579 U Mo-99 Nb-94 Nb-95 0.007016 U -0.00454 U 0.01701 U 0.01 193 U 0.03821 U Np-239 1.466 U Pb-212 0.7275 0.5867 0.849 0.9443 0.2293 Pb-214 0.5 0.3709 0.4819 0.5259 0.3079 Ra-226 1.156 U 1.103 U 1.464 Ru-103 0.01806 U 0.002307 U 0.0003512 U 0.02173 U -0.01253 U Ru-106 0.1343 U 0.1782 U 0.2278 U -0.08587 U -0.07593 U Sb-124 -0.05463 U 0.006916 U 0.01197 U 0.02904 U 0.01911 U Sb-125 -0.00008087 U Sn-113 TI-208 0.6385 0.4651 0.6857 0.826 Zn-65 0.01459 U -0.1021 U -0.06383 U -0.01635 U -0.1266 U Zr-95 0.004264 U 0U 0.04596 U 0.08445 0.01285 U SOF 0.069 0.019 0.089 0.096 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed
Table 4 Page 6 of 6 Rad NIA-OI -- Soil (pCi/g)
Yankee Nuclear Power Station Rowe, MA Station (Key) PRO01-027 (338) PR001-028 (339) PRO01-029 (340) PR001-030 (341) PROO1-032 (342)
Sample ID PROOIGUFU027 PROOI GUFU028 PROO GUFU029 PROOI GUFU030 PROOI GUFU032 Date Sampled 8/24/1998 8/24/1998 8/25/1998 8/25/1998 8/24/1998 Ac-228 0.5575 0.6359_ 0.5826 0.9825 Ag-108m -0.01494 U -0.062 U -0.006781 U -0.01584 U -0.01114 U Ag-I 1m -0.04133 U 0.009048 U -0.002056 U -0.06035 U -0.01767 U Am-241 OU 0U OU 0U 0U Bi-212 40.87 U 0.6257 Bi-214 0.4006 0.4468 0.4769 0.5418 Ce-144 -0.2015 U -0.06533 U -0.004842 U -0.3158 U -0.1335 U Co-58 -0.009833 U 0.003544 U -0.0104 U -0.01314 U 0.01056 U Co-60 0.009316 U -0.0168 U 0.004757 U 0.0257 U 0.02084 U Cs-134 -0.02622 U -0.1576 U -0.02923 U -0.2166 U -0.07742 U Cs-137 1.041 1.222 0.1476 1.643 0.7272 Fe-59 0.03581 U 0.03314 U -0.02263 U -0.004549 U 0.03575 U 1-133 K-40 9.356 19.23 21.07 15.64 16.87 Kr-85 La-140 Mn-54 0.02054 U 0.05093 0.01943 U -0.001821 U 0.01848 U Mo-99 Nb-94 Nb-95 0.01661 U 0.002301 U 0.01508 U 0.0004285 U 0.02996 U Np-239 Pb-212 0.2331 0.3573 0.3393 0.6443 0.9209 Pb-214 0.2749 0.5023 0.4467 0.4874 0.4614 Ra-226 1.832 2.064 2.229 Ru-103 -0.01902 U 0.03196 U -0.01029 U -0.004199 U 0.004117 U Ru-106 0.07483 U 0.1446 U 0.06247 U 0.1781 U 0.02391 U Sb-124 OU 0.03024 U OU 0.03253 U 0.06322 Sb-125 -0.002423 U Sn-113 Tl-208 0.5446 0.5789 0.7893 Zn-65 -0.03224 U 0.03322 U -0.0001651 U 0.1246 U 0.03826 U Zr-95 0.03362 U 0.02525 U 0.04074 U 0.06431 U -0.002005 U SOF 0.085 0.102 0.012 0.134 0.059 U-not detected (value is not greater than 2 sigma); UM-nondetect (value is equal to MDA)
Soil Basic Data 12/15/2003 Blank results indicate chemical not analyzed