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Category:Report
MONTHYEARML24155A2222024-05-28028 May 2024 Methodology Evaluation Report for Elimination of Response Time Testing Prairie Island Reactor Trip System Rev. 1 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23075A3512022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 6 of 7) ML23075A3482022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 3 of 7) ML23075A3472022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 2 of 7) L-PI-23-002, WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7)2022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7) ML23075A3462022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 1 of 7) ML23075A3502022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 5 of 7) ML23075A3492022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 4 of 7) ML22003A1832022-01-0303 January 2022 Refueling Outage Unit 2 R32 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML21285A2812021-10-12012 October 2021 Revised Pressure and Temperature Limits Report ML20272A2932020-09-28028 September 2020 (PINGP) Unit 1 and 2 Revised Pressure and Temperature Limits Report ML20265A0892020-09-15015 September 2020 Draft License Conversation Record L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency ML17279A1242017-09-30030 September 2017 Enclosure 5 to L-PI-17-041, Westinghouse WCAP-17400-NP, Supplemental 1, Revision 2, Spent Fuel Pool Criticality Safety Analysis Supplemental Analysis Including the Storage of Ifba Bearing Fuel L-PI-16-058, Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation2016-07-22022 July 2016 Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation L-PI-16-054, Pressure and Temperature Limits Report, Revision 52016-06-22022 June 2016 Pressure and Temperature Limits Report, Revision 5 L-PI-16-051, 10 CFR 50.46 Emergency Core Cooling System Annual Report2016-06-22022 June 2016 10 CFR 50.46 Emergency Core Cooling System Annual Report L-PI-15-034, Pressure and Temperature Limits Report (PTLR) Revision 42015-05-14014 May 2015 Pressure and Temperature Limits Report (PTLR) Revision 4 ML15037A4582015-03-0606 March 2015 Staff Assessment of the Aging Management Program for Reactor Vessel Internal Components L-PI-14-131, Fifth Ten-Year Interval Snubbers Testing Program2014-12-18018 December 2014 Fifth Ten-Year Interval Snubbers Testing Program ML17297A3232014-11-14014 November 2014 Enclosure 2 (Redacted): Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal for Prairie Island Unit 1 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant ML14148A4772014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14120A1622014-05-0909 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident L-PI-14-045, Enclosure to L-PI-14-045, Transition Report, Revision 12014-04-30030 April 2014 Enclosure to L-PI-14-045, Transition Report, Revision 1 L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14030A5402014-02-27027 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14041A2042014-02-26026 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2, TAC Nos.: MF0834 and MF0835 L-PI-13-080, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-08-26026 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-PI-12-108, Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-PI-12-103, Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident ML12278A4052012-09-28028 September 2012 Prairie Island, Units 1 and 2, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors ML13133A0632012-06-27027 June 2012 H4, Rev. 27, Offsite Dose Calculation Manual (Odcm). ML12159A2562012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010 Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5 ML1021002592010-06-30030 June 2010 Seismic Fragilities for Unit #1 and Unit #2 Turbine Building Piping and Equipment ML1016901712010-06-11011 June 2010 Enclosure 6, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16275, Effects of Pipe Whip Interactions for Various Pipe Combinations for Internal Flooding Sdp. ML1016901702010-06-11011 June 2010 Enclosure 5, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16270, Screening of Pipe Whip Interactions for Sdp. ML1016901682010-06-11011 June 2010 Enclosure 3, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16090, Turbine Building Flooding SDP: Cl Turbine Building Pipe Break Analysis. ML1016901692010-06-10010 June 2010 Enclosure 4, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16154, Turbine Building Flooding SDP: Cl Turbine Building Seismic Pipe Break Analysis. L-PI-10-005, Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems2010-02-18018 February 2010 Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems ML1019703862009-12-31031 December 2009 Ground Water Investigation: an Improved Flow Net to Evaluate Pathways for a Potential Ground Water Release ML1002001312009-12-21021 December 2009 Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. ML1002001322009-12-18018 December 2009 Report 0900634.402, Revision 2, Updated Leak-Before-Break Report for Prairie Island Nuclear Generating Plant Unit 2 Pressurizer Surge Line Nozzle. L-PI-09-115, Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology ML1008406402009-09-11011 September 2009 Advisory Brief of Prairie Island Nuclear Generating Plant Study Group to State of Minnesota, Office of Administrative Hearings for the Public Utilities Commission, Sept. 11, 2009. Submitted with Comments on Draft Generic Environmental Impac L-PI-09-021, 2008 Unit 2 180-Day Steam Generator Tube Inspection Report2009-04-27027 April 2009 2008 Unit 2 180-Day Steam Generator Tube Inspection Report 2024-05-28
[Table view] Category:Miscellaneous
MONTHYEARML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML22003A1832022-01-0303 January 2022 Refueling Outage Unit 2 R32 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections L-PI-16-058, Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation2016-07-22022 July 2016 Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation L-PI-16-051, 10 CFR 50.46 Emergency Core Cooling System Annual Report2016-06-22022 June 2016 10 CFR 50.46 Emergency Core Cooling System Annual Report ML15037A4582015-03-0606 March 2015 Staff Assessment of the Aging Management Program for Reactor Vessel Internal Components L-PI-14-131, Fifth Ten-Year Interval Snubbers Testing Program2014-12-18018 December 2014 Fifth Ten-Year Interval Snubbers Testing Program ML14148A4772014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14120A1622014-05-0909 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident L-PI-13-080, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-08-26026 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-PI-12-108, Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-PI-12-103, Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident ML12278A4052012-09-28028 September 2012 Prairie Island, Units 1 and 2, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors ML12159A2562012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML1016901712010-06-11011 June 2010 Enclosure 6, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16275, Effects of Pipe Whip Interactions for Various Pipe Combinations for Internal Flooding Sdp. ML1016901702010-06-11011 June 2010 Enclosure 5, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16270, Screening of Pipe Whip Interactions for Sdp. ML1016901682010-06-11011 June 2010 Enclosure 3, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16090, Turbine Building Flooding SDP: Cl Turbine Building Pipe Break Analysis. ML1016901692010-06-10010 June 2010 Enclosure 4, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16154, Turbine Building Flooding SDP: Cl Turbine Building Seismic Pipe Break Analysis. L-PI-10-005, Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems2010-02-18018 February 2010 Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems ML1019703862009-12-31031 December 2009 Ground Water Investigation: an Improved Flow Net to Evaluate Pathways for a Potential Ground Water Release ML1002001312009-12-21021 December 2009 Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. ML1002001322009-12-18018 December 2009 Report 0900634.402, Revision 2, Updated Leak-Before-Break Report for Prairie Island Nuclear Generating Plant Unit 2 Pressurizer Surge Line Nozzle. L-PI-09-115, Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology ML1008406402009-09-11011 September 2009 Advisory Brief of Prairie Island Nuclear Generating Plant Study Group to State of Minnesota, Office of Administrative Hearings for the Public Utilities Commission, Sept. 11, 2009. Submitted with Comments on Draft Generic Environmental Impac L-PI-09-021, 2008 Unit 2 180-Day Steam Generator Tube Inspection Report2009-04-27027 April 2009 2008 Unit 2 180-Day Steam Generator Tube Inspection Report ML1020302362008-12-31031 December 2008 State of Wisconsin Prairie Island Environmental Radioactivity Survey ML0834701962008-11-21021 November 2008 PINGP - License Renewal; Radon Health Risks ML0834000702008-10-24024 October 2008 PINGP License Renewal: Wisconsin Department of Health Prairie Island Environmental Survey 2006. Reference 2008c L-PI-07-057, Corrections to Emergency Core Cooling System (ECCS) Evaluation Models2007-08-23023 August 2007 Corrections to Emergency Core Cooling System (ECCS) Evaluation Models IR 05000282/20053012005-09-30030 September 2005 Er 50-282-05-301 (DRS) and 50-306-05-301 (Drs), on 08/09-19/05, Nuclear Management Company, LLC, Prairie Island Nuclear Generating Plant. Initial License Examination Report ML0520901582005-08-0202 August 2005 2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment L-HU-05-012, Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 22005-06-0303 June 2005 Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 2 ML0522700732005-04-18018 April 2005 Event Notification Report for April 18, 2005 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0514604942004-04-0909 April 2004 Licensee Root Cause Report, CAP55527, Industrial Safety Issues and Poor Work Practices During Nozzle Dam Installation, with R. Alexander'S (Riii) Notes ML0318909462003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Duane Arnold, K ML0310401092003-04-0404 April 2003 Steam Generator (#22) & Pressurizer Flaw Evaluations ML0205206392002-01-25025 January 2002 Fqa Methodology & Shutdown Margin During Physics Tests Methodology 2023-09-29
[Table view] |
Text
-.9 PRAIRIE ISLAND NUCLEAR GENEkTING PLANT (P INGP). GROU,3ND WATER, INVESTIG-ATIONý:
AN IMPROVED FLOW NET TO EVALUATE PATHWAYS FOR A POTENTIAL GROUND WATER RELEASEt
/,
Prepared by:
tChuck Donke4Xce' Energy, December 2009
i PRAIRIE ISLAND NUCCLEAR GENERATING PLANT (GGP) GROUND WATER INVESTIGATI*iON:
AN IMPROVED FLOW NET TO EVALUATE PATHWAYS FOR,A POTENTIAL GROUND WATER RELEASE, BACKGROUNDz
,A,flow net 'is*one method to determine the groundwater path way between twoqpoints.
An ithrove&*.fiwnetwas sýUght to identify potential receptors in the everit'that a hypothetical ground water release were to occur at-the Prairie'island'Nuclear Generating'Plant (PINGP)., Aflow net is a static
'snap siioofia dynfamoit 9st'em. It is'constructed pti grii&Ot Ibations collected frm Wste wells: for a.specific date. To improve upoh the currenit flow riet, perspeitiv6e wbs fieedId'How:
rep~resentative is the "sna sht ohe entirey kecentstudies (ULiSG1997) suggested large rain events could causeshortiterm deviaitionsfrom the existiig~fowt Inliigiht ofthisibnformation, Xcel Energy developed a stdy to identipft he magnitude and quantifythe duration of such changeS:inflowdirectibn.
PROJEC-& OSIGN The tprei.seofthiso ivestigation was to identify short term cha0nges in"flow direction duetoJthe influence of floodingorlarge rain events. Seven (7) wells were edqluilped.with water le6el tiransducers and d*at !oggers. Hourly ground water elevations were collected 'inthese seven weIls from:Mar.ch30, 2009 thre Dece6mber:16, 2009. Using methodology develbped by"Pinder(Velocity ClcdulationFrom RandomjtyLocated Heads, Pihder et aL 1981), hourly flow directionsn werIe calulated "for pre-de6finhed 9areas.
To *improv~e the PINGs flow net,two methods were~employed. Surfer, a commerially available jinterp.latiof p .rogrIamwasus Ied to produce a m -r cIccurate pred*ctioh of ground water flowvpaths but Aitdoes not lend itself-to processing large amounts of time varialle da1ta. Theieth6dIlogýy.de.veloped by Pinder lends itself to processing large volUmesof data, and huius dentifying shott*m .upsets; howeverP it is less accurate than other ijiethods. The~two methods comopkinen-t each other byOutting the more
,accurate "snap shot" in to perspective for-the fullyear.
R;EsULTS.
'Figuree1 depicts the PINGP site, and identifiesýwhich Wells werejequipp-ed with datalIoggers, Figure 2 presents the hydrographs for the hourly data,from seven wells plusississippi River and'VAermillion Riv6erCeevationis. -Figures3 thru 6 depict ground water elevation contours for the site when aliwelIs
,were sampled and the approximate no-flow bounidary. The no-f66w bouindaryis:the approximate
i northen and western lim~it of flow originating fr'm thePlNQP. Figqre 7 illustrates the indild .alflow
_elements(areas)'that were used to calculate the hourly flow directibns. Figdie 8ilustrates flow vs. time for each area. Figure 9 is a delineation of groundwaier whichfis down gradient fIDom odirectin Athe PINGP using a compilation of'all data generated in this, investigation0.
Hy~dro_gph Aspects5
- As~shlown*on Figure 2, the study period extended from March 30, 2009 thru December 16, 2009. Stage Adata-from bthe Mississippi and Vermillion RiVerS-Were avadiable startilng~on Februalry 6,2009.. As,
- intend'edthis period included several significant events including the spring flood, and several large, ra.ihn evenrts in Jiui'Vand August. The-following. observations were ma~de:ý o' Typical.(non-food) flowisfrom MississippiRiver (highest head) to the groundwater under the Prairie Island Plant tO theyVermillionh(ilowest head). This con diltion occur o6verabout 90% of the study period.
TThe i*y*crographs indicate g*round water 'e!vationsdo respond':to spring' flooding. There is a short lag time between flooding and the rise in ground water elevations. 'Ground water elevations are also slower to recede.
w, Groundiwater'elevations were higheerthan th6 Mississippi Riverand the Vermillion River for about f6Ourweek's duringthe. spring flood periob. Thlis suggests that a brief reversal of flow (firdr groundwater'towafrd the rivers bccurs overaboOt 1:,,o%6f the study priod., 'Grbundwater flow:duringtthis period would likely be: radially.outward, from groundwater to surface water.
SSeveral large'raineVents0(1" to-2"/da) occurredin* August. Ground water elevations rose several inches.:in response to this. pretpitation. However.all wells responded in a similar fashion, suggesting no moundingof ground'water.
ýGround water Elevation contour Maps Ground water elevations were interpolated using Surfer for four sampling events. Mississippi River and Viermillion*River elevations were included in the surfer applications; the inclusion of these data. resulted in the depiction, of a strong southwesterly flowdirection.. Because water flows frfmornreas. of higher head to areassoflower head elevationthis southwesterly flow direction appears to be areasonable charactetizatin of actua flow conditiocns throughout.henmajority ofthe study period. This
.characterization is also supported by the hydr6gfaph data and the apparent higher:head in the ississippi River relative to the Vermillion River duringsthemajority of the study period. The following observations were made:
o GroundWater flow paths (flow dire~ction.his*pierpiiduilar to eleVation contou*s) generallytrend
,southwest~as described above 0 Radial flowis exhibited near P-bfdue tolocalized moxnIirg ofIthe water table., The mounding influence may be due the presence of severalwate r features suchlas thecooling tower canalsi a
,sur.fbce.draihage-ditch and septic drainrfidlds. The observedm6uiridihib*i dimniishis withiiva
~ho*distan~ce ~from rthe wejl,zreiurningtjothle predminant.souihweeser!y.w direction.
- Gýoiud Watgr.gradients are. depicted in Figtir&s 3--6. The legth* of*thector irrw tails are proportionalto the:gradiqot; thp longerthe tail, the steeper the gradient. Assuming similar geology, this generallyindictates ffaster'travel velocities.
Hourly Flow Directions Fowdirections were, calulated'hourly; for foura reas FigUrege7 Illustrate the are*s*represented by
'theses hourly. directidt'ns Figure 8d .istratesfl'6wdirectimns 0 *Ihefllo ig obserattionswere made!ý the predominantiflow direction, spatiallyand in-termsof duration.is~sotithwest (2,25 deg from T
rbth4). The greatest deviation from this predominhant trend occuprreýdwfithin 4-.8weeks after the Duriing the months of April andqMay, Area
- nd Area 4 reportetd westerly flows. however gfound wat*,gradients were.sigriificantiy less during these`,tirmes anditheduration of timeVwas, short. Therefore the.actual distance traveled, in awesterly direction, issmalldue to lower gradients and the short duration of the deviation.
The four static flow nets depicted ihn figures 3-6 correspond to stable flowiconditions, observed:
T forihemajotity of the year. Theseflow netsiareirep.esentative;for tse throughout-the year Wkith~ thei possible exception of 4-6 We~eksjafter the sPriflood.
ýCONCCUSIONS*.
- No~eIdence of ground water mod ppd.gWas bbserved whith orreiate~d to. a.rge rain events.
- Mounding was.observed near O.40. .Radial ground water flowwas'noted. The numerous infiltration sources, (septic drain fi6lds, drainage ditc', aand c-liigtower canals)ýare believed to contribute to the mounding effect..
- The inclusion of river elevations wi~th- wte elevations im~pre theinterpolated-grgund din water contours.-and hence the flowhnet!
S'Thespring flood demonstrated tte largest influence uponEgrudwater flowdirections. Flood influences extend 4-6 weeks after the*flo*d recedes.
- With the e~xceptipn of the 4-6 weeks~a*.er spri.ng fooodjground water flowssouthwest t.'Wards the.VrmJllion River.
o "e.liow n~ets presented in this report (~iiur's 3-6) represent,f lwpath's for approximately 10 idfhtihs dout of the yeat.
o iven theishortduration and limitediarealextent of the flow reversals. a hypothetical release froM the Prairie Island Plant could move only a relatively'ýshbrt distarcite feromthe plant~during a spring flood event before it would be'redirected to the predominant:flow direction (to the so uthwest).
- The data collected duringithis investigapion suggestthat there is no direct ground water Vpathway connec.ting the IjNGP and neighbo~s t~o the north and westi ofthe plant..
SCalculatih*ig hourly fWirte-ti~n~s1'entified the montbs ,of,AprilV4nd May as h'avin"the gteatest potential fbrwesterlyflow. Although.the significance of these%.westerty'flows, istconsidered mlitire~mm d t costiruct additional flow nets, .Using,!,aliIws, during thiS period of flux.
Figur~e L.
+ PINGP Grouncl \Vrter Monitoaring System.
~
V~,U ~by
__ Pipe Efev..
,59228 2355090: 93ý02-MW- "3592201 5858668 88.83
-71 M". t.591842' 2357597. 82M3 MW. ' 593885 23557,14 .M95.S4 MW-8 59944; 235654; 697,47
.pZ*.4 P-10, 5 23497, 69316
. R255297 898.19 J& J 594449 *,O42' 69,72 P- 592998 2353997 899;19.
P-S 594002 2354501 69551 P6 595250 2354802, 893 P-7 594449 2355235 697.97 J96790,. 2354934 882.9Z
ýPZ-21 59%743 25259, 889.05 PZ-4 5942n2 2352598 688.5 P . *591502 2358299 %95.93 PZ-74 L594469 2356158. 97.85.
PZ :595471 2353662, 96.652
~,Wetequii~edj %with'a' d t~ ogger
/0> k t7; -007
Figure 2. PINGP 2009 Hydog-raphs 680.,00 14 678&00 12, U- 676.00 - PZ-2 i0: - P-iTO w
toC PZ-4
!PZA-:
' 674.'00
- P-2!
'2 o 677200 6
4 -Vermiiiion R
> 670.00 4-¢-
.- precip-2
&666&00 0;
a) C LL 0' (0 co An.
Figure ý3,f Ground' V/oter- Ele vat Icnrs bflG
- Fow Vectors For 7/11/2006,,
ý6( L... tý.-
.... NtU' Ea&t i1 eoE MW%4 .592236 2355090 69102 MW., 59220i 2356568 686.83 MW4 59164Z f2357597 682.3 MW.7, 593685 235S7,14, 695.54
, 593944 2355654- 69Z7
.P 59338 SlO ;2355497k 69315 P-11 594949 2355297 5:98.19 P4 59444. 2354002: 697,72 P.,3 5929 2353997, 69819 P-5 594002 .:235450f 695.51 P.- 595250 2354802 6W3-P7 . 594449. 2355235 697.97 PZA1 595790 2354934: 6829.
PZ-2 596743 2352589".. 6 5 PZ.4 594252 235598. 696.
5*9PZ02 2356299 695.93 PZ-7 594469, 2356150I 697.5 PZ,8 595471 . :2353662 696.52 Np-ftow boounldary; The~
_________ pproxirýAte norther-r
ýmd. southern limits. of
,Ftow Or'iginc6tirg ;A
?1NGP F~or a specific dAky.
AWeL. gqufped, withý .(rdcita 'logg~er g
"0
FigOr'el 4 Grourd Water'- E~.evc~tiohns O R~ow, Vectors iLorw 7/9/2008 SMIL.Yd~ by Top of Riser
'VI ori 'Eait Pipe ELev MW-4 :592236A 1355M90 ý83.O2.
MW.5 59220 23586566: W68.83
.7 MW46 591842 123575971 W82.33 MW-7 -593885' .2365714. 695.54 MW.8.' 593944.., 2356854 697A7
- 1o. 593538- .-23-59 693.16 P-lI 594949,: 2355297ý 69819a P-2 !59444T 2354002 697,72*
P43 :592998 2353997 698.t9 P-5 594002 2354501 89551 P46 595250 12354802. 699;3,1 697.97
.23652351; P2-2 94449
'596743 2352569: 6W905 P2.4ý 594262 2352598 .696.53 P75; 5915602, 2358299 '695.93'
ýPZ-7 594489 2356,158. ý697.85 P2-a .595471 2353862 ,696.52 No-f ow boundlary;. The ckpproxilmcae n~orthern and -sout'herri Limits OF P.I..P .o.speciric drqye.
4 wie~tt eqipd wtbo da~tq, iogger' C
Fig u r E 5:
Grourd Water ELevqt.!ons o*ncl Flo~w Veact*ors For 7/8/2009 V1( - S.-yr{
6- i V~e Noilh Siit pipefREer 592236 :2355090 695.02
~MW-S 592201 2356566 666,83
~MW "6591642 2357597 682.33 MW.7 59368 ý-2355714' 695.54 MY", 593944 2355654 697.47 P-10 5S93538 2355497 693.16 P4 I "594949 2355297 P;2 594449 1354002, 697-72 P 592998 2353997 698:19 P-S5 594002 23501 695.5 P.ý6ý 595250 '255402 699.3 P.ý7g. 594449, 235235 697-97 K.PZ.1 596790 2354934 682.91 PZ-2 596743 235259 669.05 PZ-4 594262 2352596 696,53 PZ5 ,,591V50 2356299 695.93 PZ_71594469, 235615 69'785 PZ.8-. .- 595471-, 2353W2 69652
_______No-r~ov boundary, The aproximate northern and southern Uinits of
,flow. originating at PIGP' for . ;sPecifjc 4 de equipe.4 ait oatLog
'6 G
- Figu:re GCround Wote- Elevaotions andc FLWw Vettors Por, 12:/16/-`200'9
-ti Nd.i-b 21, 20l07, wd. NOMi EWs PipeElev MV"4 592236 2355090. 693.02 MW.5- 59220 2356566 W6.683
ýMW.6 591642 2357597 682.33 MW-7 593M'5 :23557,14 69.54
.MW-6 '593944 2355654 697.47 P140 ý59353O 2355497 69:16 P-I. '594949ý 235297 698,19 N.2 594449, 2354002 897.72 P.3 5692998 2353997 698.19 P-6 594002, 2354501 W&SI5 P-6 5920 23S4802. 699.3 P-7 '594449ýA..2355235 697.97, PZ-1 596790' ý'2354934 .682;91--
PZ-2, 596743ý 2352589 6M89:05
- PZ-4 594262ý 2352596: 696.53 PZ-5' 591502 2356299ý 695.93 PZi7, '594469, -2356158 6971.85 V:W 5195471 - 2353682z ,696.52 NO-4loiv~bounciryý THO' ro~xfima e nor'therrý c~nd jsouthern Limit~s of
';~*ow &iginating i at day;fr~ p'cf Welt equiped with a data Logger A
I
Figure 7.T-PINGRi Ground Wvoter Monitoring, Systemn
+ Areias Haurly Flow, Oire*Ction is.
CseeF1~ure8 for resu,[to)*
lm%*ý L S-fiýLli qo 21. 207 Top ofRizer MIE Namh Et PieEe hM44 sg2236 2355090 89302 MW-S 592201 2358568, 86.83 fW.6 591642 2357597 882-33 M 593685 : 695.54
ýMW-S- 593944.: 2356654 6974
- f, N10", 593538 :2355497 83.18 P'14 594949 1355297 69.19 N. 594449, 2354002, 697.72 P3 6592998: ý23597 698.19 P4. '594002 235501 895.51 P-6 595250 23402 89.
P-7,. 59,49. F 2M235 697.0-A 596790 -23549034 ,q62:r PZ-1 ,
PZ-Z. $ 9W43-,1-2352589 .689.0,5.
PZ.4.594262S..23525S& '696.53 PZ-6' S91502ý 2356299 -895.91 PZ-7< 594469: 2358158 697;85 Z595471 .235366 6M52 4~ Wett eqviped withý ia d to 'logger
'C
4 Figure 8. P1NGP, Flow Direction vs Time
,(See Figure 7 For Area Locati"ns)
'270 225 0
z
-Area 1 E 180 0 -Area 2 135 -Area 3
-Area 4
ý90 45 0
(000N 1,*- CO~ -MO MO C4CC -~
Composite oF PI'iNGP No-Ftow BoundIary Clondili "Ois',&
Arawhich is down
- gradient of~ the, PIN4GP 4