Committed to Nuclear Excellence Nuclear Management Company, LLC 

July 31,2006 

Mr. Stuart A. Richards, Deputy Director 

Division of Inspection and Regional Support 

Office of Nuclear Reactor Regulation 

U.S. Nuclear Regulatory Commission 

Washington DC 20555-0001 

Prairie Island Nuclear Generating Plant Point Beach Nuclear Plant 

Units 1 and 2 Units 1 and 2 

Dockets 50-282 and 50-306 Dockets 50-266 and 50-301 

License Nos. DPR-40 and DPR-60 License Nos. DPR-24 and DPR-27 

Monticello Nuclear Generating Plant Palisades Nuclear Plant 

Docket 50-263 Docket 50-255 

License No. DPR-22 License No. DPR-20 

Groundwater Protection - Data Collection Questionnaire 

The nuclear industry, in conjunction with the Nuclear Energy Institute, has developed a 

questionnaire to facilitate the collection of groundwater data at commercial nuclear 

reactor sites. The objective of the questionnaire is to compile baseline information 

about the current status of site programs for monitoring and protecting groundwater and 

to share that information with NRC. The completed questionnaires for the above listed 

sites operated by Nuclear Management Company, LLC are enclosed. 

This submittal contains no new regulatory commitments. 

A 

~irectorclear Licensing and Regulatory Services 

Nuclear Management Company, LLC 

Enclosures 

700 First St Hudson, Wisconsin 54016 

Telephone: 71 5-377-3300 
Document Control Desk 

Page 2 

cc: Document Control Desk 

Administrator, Region III, USNRC 

Project Managers (Monticello Nuclear Generating Plant, Palisades 

Nuclear Plant, Point Beach Nuclear Plant, Prairie Island 

Nuclear Generating Plant), USNRC 

Resident Inspectors (Monticello Nuclear Generating Plant, Palisades 

Nuclear Plant, Point Beach Nuclear Plant, Prairie Island Nuclear 

Generating Plant), USNRC

Ralph Andersen, Nuclear Energy Institute 

Lou Brandon, NFU/HWRS/WHMD, Minnesota Department of Commerce 

Daniel Ebert, Public Service Commission of Wisconsin 

Michigan Public Service Commission 
Page 1 of 3 

ENCLOSURE 1 

INDUSTRY GROUNDWATER PROTECTION INITIATIVE 

VOLUNTARY DATA COLLECTION QUESTIONNAIRE 

PRAIRIE ISLAND NUCLEAR GENERATING PLANT 

The Nuclear Energy Institute has developed a questionnaire to facilitate the collection of 

groundwater data at commercial nuclear reactor sites. The objective of the 

questionnaire is to compile baseline information about the current status of site 

programs for monitoring and protecting groundwater and to share that information with 

the NRC. The completed questionnaire for Prairie Island Nuclear Generating Plant 

(PINGP) follows. 

1. Briefly describe the program and/or methods used for detection of leakage or spills 

from plant systems, structures, and components that have a potential for an 

inadvertent release of radioactivity from plant operations into groundwater. 

• The PINGP has a leakage detection system installed in the annulus of the 

double-walled liquid radioactive waste discharge line. Leaks into the annulus are 

detected and location identified using this system. 

• The PINGP has a Spent Fuel Leakage Detection system which is used to 

monitor for leakage from the spent fuel pool. 

• Engineers perform periodic walkdowns of the systems for which they are 

responsible. These walkdowns include the requirement to identify and report 

leaks and spills. Leaks and spills are addressed through any of the following: 

decontamination, notifying supervision for assistance, writing a work request or 

initiating a Corrective Action Report. 

• Operations personnel conduct shiftly walkdowns of plant systems and are 

required to identify and report leaks and spills. Leaks and spills are addressed 

through any of the following: decontamination, notifying supervision for 

assistance, writing a work request or initiating a Corrective Action Report. 

• The site corrective action program is used for reporting and trending leaks and 

spills. The process facilitates anonymous reporting. 

2. Briefly describe the program and/or methods for monitoring onsite groundwater for 

the presence of radioactivity released from plant operations. 

• PINGP has a special tritium sampling program in addition to that of the 

Radiological Environmental Monitoring Program (REMP) and consists of the 

following: 
Page 2 of 3 

o Twenty-two onsite groundwater monitoring wells surrounding the plant 

o Seven offsite residential groundwater wells 

o Five surface water sample locations 

o All samples analyzed to a Minimum Detectable Activity (MDA) of 19 pCi/L 

o All locations sampled annually and four locations sampled quarterly 

• PINGP has a water sampling program as part of the REMP that consists of the 

following: 

o Six onsite and offsite drinking water wells 

o Two surface water sample locations 

o The surface water locations and one drinking water well are sampled weekly, 

the other five wells are sampled quarterly 

o All samples are analyzed for radionuclides with the following MDAs. 

Nuclide Typical MDA (pCi/l) 

3

H 

54Mn 

59Fe 

58Co 

60Co 

65Zn 

95Zr-Nb 

134Cs 

137Cs 

140Ba-La 

144Ce 

500 

10 

30 

10 

30 

10 

15 

10 

10 

15 

40 

3. If applicable, briefly summarize any occurrences of inadvertent releases of 

radioactive liquids that had the potential to reach groundwater and have been 

documented in accordance with 10 CFR 50.75(g). 

• Elevated levels of tritium, which were below U.S. EPA drinking water limits, were 

detected in a nearby residence well in 1989. Evaluation of this incident indicated 

that the source of the groundwater tritium was from planned discharges of liquid 

radioactive waste that seeped from the discharge canal and possibly leaked from 

the liquid radioactive waste discharge piping. 

• Low levels of Co-60, Cs-134, and Cs-137 were found in 1992 when sampling an 

area where high turbidity water is discharged from the turbine building sump. 

The contaminated area was inside the owner controlled area. 

4. If applicable, briefly summarize the circumstances associated with any onsite or 

offsite groundwater monitoring result indicating a concentration in groundwater of 
Page 3 of 3 

radioactivity released from plant operations that exceeds the maximum contaminant 

level (MCL) established by the U.S. EPA for drinking water. 

Not applicable. No groundwater monitoring results have exceeded the maximum 

contaminant levels established by the U.S. EPA for drinking water. 

5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate 

levels of radioactivity resulting from plant operations in soil or groundwater onsite or 

offsite. 

• The 1989 discharge canal and liquid radioactive seepage was remediated in 

1991 by installing a double-walled discharge pipe. The pipe extended the 

discharge of liquid radioactive waste near the outfall of the discharge canal to 

reduce the residence time of the tritium in the discharge canal and minimize any 

underground leakage from the discharge piping. A special groundwater 

monitoring program was initiated after the repairs. Regular samplings of 

groundwater on and off the site are significantly below the limit established by the 

U.S. EPA for drinking water. 

• In 1998, contaminated soil from the turbine building sump discharge area event 

of 1992 was removed and shipped for radioactive disposal. 
Page 1 of 3 

ENCLOSURE 2 

INDUSTRY GROUNDWATER PROTECTION INITIATIVE 

VOLUNTARY DATA COLLECTION QUESTIONNAIRE 

POINT BEACH NUCLEAR PLANT 

The Nuclear Energy Institute has developed a questionnaire to facilitate the collection of 

groundwater data at commercial nuclear reactor sites. The objective of the 

questionnaire is to compile baseline information about the current status of site 

programs for monitoring and protecting groundwater and to share that information with 

the NRC. The completed questionnaire for Point Beach Nuclear Plant (PBNP) follows. 

1. Briefly describe the program and/or methods used for detection of leakage or spills 

from plant systems, structures, and components that have a potential for an 

inadvertent release of radioactivity from plant operations into groundwater. 

• Storm drains are sampled monthly as part of the Radiological Effluent Control 

Program (RECP). 

• Lake water and well water samples and vegetation samples are obtained within 

the owner controlled area as part of the Radiological Effluent Monitoring Program 

(REMP). 

• Engineers perform periodic walk downs of the systems for which they are 

responsible. These walkdowns include the requirement to identify and report 

leaks and spills. Leaks and spills are addressed through any of the following: 

decontamination, notifying supervision for assistance, writing a work request or 

initiating a Corrective Action Report. 

• Operations personnel conduct shiftly walkdowns of plant systems and are 

required to identify and report leaks and spills. Leaks and spills are addressed 

through any of the following: decontamination, notifying supervision for 

assistance, writing a work request or initiating a Corrective Action Report. 

• Chemistry and Radiation Protection (RP) personnel perform on the job 

observations and are trained to report spills. 

• PBNP has a Spent Fuel Leakage Detection system which is used to monitor for 

leakage from the spent fuel pool. 

• Tanks that contain radionuclides have level monitoring gauges and alarms. This 

would provide indication of leakage from the tank. 
Page 2 of 3 

• Tanks containing radioactive liquids at PBNP are located within the plant; there 

are no outside radioactive liquid storage tanks. The former retention pond has 

been remediated as described in Item 5 and monitoring continues as described 

in Item 2. 

• The site corrective action program is used for reporting and trending leaks and 

spills. The process facilitates anonymous reporting. 

2. Briefly describe the program and/or methods for monitoring onsite groundwater for 

the presence of radioactivity released from plant operations. 

• Intermittent streams are sampled monthly for tritium to monitor the status of 

existing groundwater tritium concentrations associated with the remediated 

retention pond. 

• Three onsite potable wells are periodically sampled. The Energy Information 

Center well is sampled monthly; the others are sampled quarterly. 

• Tritium lower limits of detection (LLDs) are set at a fraction of the U.S. 

Environmental Protection Agency (EPA) drinking water standard. 

• Typical LLDs for well and stream samples are listed below. 

Nuclide Typical LLD (pCi/l) 

3

H 

54Mn 

59Fe 

58Co/60Co 

65Zn 

95Zr-Nb 

131I 

134Cs 

137Cs 

140Ba-La 

89Sr 

90Sr 

200 

15 

30 

15 

30 

15 

 2 

15 

18 

15 

10 

2 

3. If applicable, briefly summarize any occurrences of inadvertent releases of 

radioactive liquids that had the potential to reach groundwater and have been 

documented in accordance with 10 CFR 50.75(g). 

• During 1975, a steam generator tube rupture resulted in a release of about 

10,000 gallons of low level contaminated water, which included tritium, to the 

onsite retention pond. Some of this leaked into the upper surface aquifer through 
Page 3 of 3 

the earthen pond sides before the pond was remediated. Also, some of this 

water was released via the approved effluent discharge pathway. 

• In 1997, the buried discharge line to the retention pond developed a leak sending 

sewage treatment plant and secondary side sump water into the ground, where it 

welled up to the surface. This water contained slight amounts of radioactivity. 

Most of this water ran into the intermittent stream on the east side of the sewage 

treatment plant and then into Lake Michigan. 

4. If applicable, briefly summarize the circumstances associated with any onsite or 

offsite groundwater monitoring result indicating a concentration in groundwater of 

radioactivity released from plant operations that exceeds the maximum contaminant 

level (MCL) established by the U.S. EPA for drinking water. 

Not applicable. No groundwater monitoring results have exceeded the maximum 

contaminant levels established by the U.S. EPA for drinking water. 

5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate 

levels of radioactivity resulting from plant operations in soil or groundwater onsite or 

offsite. 

The retention pond was closed and remediated to a fraction of the NRC unrestricted 

access dose guideline of 25 mrem/year. All Cs-137 contaminated soil outside the 

pond was remediated to produce residual Cs-137 levels below the NRC generic 

decommissioning screening level for unrestricted access. 

A large segment of the buried discharge line to the retention pond that leaked in 

1997 was replaced. The stream is now sampled monthly and tritium levels are 

significantly below the limit established by the U.S. EPA for drinking water. 
Page 1 of 3 

ENCLOSURE 3 

INDUSTRY GROUNDWATER PROTECTION INITIATIVE 

VOLUNTARY DATA COLLECTION QUESTIONNAIRE 

MONTICELLO NUCLEAR GENERATING PLANT 

The Nuclear Energy Institute has developed a questionnaire to facilitate the collection of 

groundwater data at commercial nuclear reactor sites. The objective of the 

questionnaire is to compile baseline information about the current status of site 

programs for monitoring and protecting groundwater and to share that information with 

NRC. The completed questionnaire for Monticello Nuclear Generating Plant (MNGP) 

follows. 

1. Briefly describe the program and/or methods used for detection of leakage or spills 

from plant systems, structures, and components that have a potential for an 

inadvertent release of radioactivity from plant operations into groundwater. 

• Permanent outdoor radioactive water storage tanks at MNGP (condensate water) 

are located within a basin designed to contain leakage. Leakage from the tanks 

would be detected either visually or during routine sampling and analysis, which 

is performed prior to periodic removal of accumulated precipitation. 

• The MNGP spent fuel pool has a leak detection system that includes a skimmer 

surge tank low level alarm, a fuel pool low level alarm, and an inspection of the 

fuel pool liner drains once per shift. 

• Engineers perform periodic walk downs of the systems for which they are 

responsible. These walkdowns include the requirement to identify and report 

leaks and spills. Leaks and spills are addressed through any of the following: 

decontamination, notifying supervision for assistance, writing a work request or 

initiating a Corrective Action Report. 

• Operations personnel conduct shiftly walkdowns of plant systems and are 

required to identify and report leaks and spills. Leaks and spills are addressed 

through any of the following: decontamination, notifying supervision for 

assistance, writing a work request or initiating a Corrective Action Report. 

• The site corrective action program is used for reporting and trending leaks and 

spills. The process facilitates anonymous reporting. 

• The Radiological Environmental Monitoring Program (REMP) includes periodic 

sampling and analysis of onsite and offsite groundwater wells. 
Page 2 of 3 

2. Briefly describe the program and/or methods for monitoring onsite groundwater for 

the presence of radioactivity released from plant operations. 

• MNGP has one onsite groundwater monitoring well, which is sampled as part of 

the REMP. This well is one of several that supply water for employee 

consumption. 

• In addition, MNGP samples two offsite groundwater wells (one residential and 

one public) as part of the REMP. 

• The wells are sampled quarterly and analyzed for gamma-emitting radionuclides 

and tritium. 

• The samples are analyzed to the site’s REMP criteria. 

• Typical sample Minimum Detectable Activities (MDAs) are as follows. 

Nuclide Typical MDA (pCi/l) 

3

H 

54Mn 

59Fe 

58Co/60Co 

65Zn 

95Zr-Nb 

131I 

134Cs/137Cs 

140Ba-La 

500 

10 

30 

10 

30 

15 

1 

10 

15 

3. If applicable, briefly summarize any occurrences of inadvertent releases of 

radioactive liquids that had the potential to reach groundwater and have been 

documented in accordance with 10 CFR 50.75(g). 

Not applicable. There are no inadvertent releases of radioactive liquids documented 

in accordance with 10 CFR 50.75(g). 

4. If applicable, briefly summarize the circumstances associated with any onsite or 

offsite groundwater monitoring result indicating a concentration in groundwater of 

radioactivity released from plant operations that exceeds the maximum contaminant 

level (MCL) established by the U.S. EPA for drinking water. 

Not applicable. No groundwater monitoring results have exceeded the maximum 

contaminant levels established by the U.S. EPA for drinking water. 

5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate 

levels of radioactivity resulting from plant operations in soil or groundwater onsite or 

offsite. 
Page 3 of 3 

Not applicable. No remediation efforts have been planned or undertaken to reduce 

or eliminate levels of radioactivity resulting from plant operations in soil or 

groundwater onsite or offsite. 
Page 1 of 3 

ENCLOSURE 4 

INDUSTRY GROUNDWATER PROTECTION INITIATIVE 

VOLUNTARY DATA COLLECTION QUESTIONNAIRE 

PALISADES NUCLEAR PLANT 

The Nuclear Energy Institute has developed a questionnaire to facilitate the collection of 

groundwater data at commercial nuclear reactor sites. The objective of the 

questionnaire is to compile baseline information about the current status of site 

programs for monitoring and protecting groundwater and to share that information with 

the NRC. The completed questionnaire for Palisades Nuclear Plant (PNP) follows. 

1. Briefly describe the program and/or methods used for detection of leakage or spills 

from plant systems, structures, and components that have a potential for an 

inadvertent release of radioactivity from plant operations into groundwater. 

• The PNP spent fuel pool (SFP) consists of a stainless steel liner surrounded by 

several feet of concrete. Leak chases are located between the stainless steel 

liner and the concrete. The leak chases route any leakage past the liner to a 

monitored drain system (commonly referred to as tell tale drains). If the SFP 

were to leak past the concrete liner, leakage should be contained in the auxiliary 

building. 

• Engineers perform periodic walk downs of the systems for which they are 

responsible. These walkdowns include the requirement to identify and report 

leaks and spills. Leaks and spills are addressed through any of the following: 

decontamination, notifying supervision for assistance, writing a work request or 

initiating a Corrective Action Report. 

• Operations personnel conduct shiftly walkdowns of plant systems and are 

required to identify and report leaks and spills. Leaks and spills are addressed 

through any of the following: decontamination, notifying supervision for 

assistance, writing a work request or initiating a Corrective Action Report. 

• Other periodic inspections and walk downs include personnel from Engineering, 

Chemistry and Radiological Protection and Security Departments. 

• Tanks that contain radionuclides have continuous level monitoring and recording 

capabilities. 

• The site corrective action program is used for reporting and trending leaks and 

spills. The process facilitates anonymous reporting. 
Page 2 of 3 

2. Briefly describe the program and/or methods for monitoring onsite groundwater for 

the presence of radioactivity released from plant operations. 

• There are three monitoring wells located around the interim steam generator 

building, which houses two steam generators, and are sampled quarterly per the 

Radiological Effluent Monitoring Program (REMP). 

• The table below lists the required lower limit of detection (LLD) that the vendor 

will achieve for liquid environmental samples. 

Nuclide Typical LLD (pCi/l) 

3

H 

Gross Beta 

89Sr 

90Sr 

131I 

134Cs 

137Cs 

140Ba-La 

500 

4 

5 

1 

1 

15 

18 

15 

3. If applicable, briefly summarize any occurrences of inadvertent releases of 

radioactive liquids that had the potential to reach groundwater and have been 

documented in accordance with 10 CFR 50.75(g). 

• The utility water storage tank (T-91) leaked 2,790 gallons of processed liquid 

radioactive waste from a flange onto the ground, with some seepage through the 

wall of the vault below ground level. This event is documented in the 10 CFR 

50.75(g) file. 

• The 10 CFR 50.75(g) file also contains reports that describe historical cooling 

tower overflow incidents. The non-radioactive circulating water subsequently 

flowed through the south storage building, which contained radiologically 

contaminated equipment. Surveys confirmed that the surface contamination was 

to a depth of approximately six inches. The soils in the affected area were 

retained in accordance with approval from the NRC per 10 CFR 20.302. 

4. If applicable, briefly summarize the circumstances associated with any onsite or 

offsite groundwater monitoring result indicating a concentration in groundwater of 

radioactivity released from plant operations that exceeds the maximum contaminant 

level (MCL) established by the U.S. EPA for drinking water. 

Not applicable. No groundwater monitoring results have exceeded the maximum 

contaminant levels established by the U.S. EPA for drinking water. 
Page 3 of 3 

5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate 

levels of radioactivity resulting from plant operations in soil or groundwater onsite or 

offsite. 

• The utility water storage tank release summarized in question 3, and referenced 

in the 10 CFR 50.75 (g) file, was remediated by removing approximately six 

inches of soil from the surface. Approval was obtained for disposal per 10 CFR 

20.2002. 

• The cooling tower overflow incidents, which flooded the south storage building 

containing radiologically contaminated equipment, was remediated by retaining 

the majority of the 4,200 cubic feet of affected soil in accordance with 

10 CFR 20.302.