Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML070510476, ML073230158, ML073230169, ML073510242, ML081000213, ML082050406, ML082050433, ML082070154, ML083010366, ML083570153, ML091130122, ML092330075, NL-08-119, Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-02, NL-08-171, Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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MONTHYEARML0603800992006-02-0909 February 2006
Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors (TAC MC4689 & MC4690)
Project stage: RAI
ML0705104762007-02-0909 February 2007
Licensee Slides 2-9-07
Project stage: Other
ML0704701232007-02-26026 February 2007
Summary of February 9, 2007, Meeting with Entergy on the Response to Generic Letter 2004-02 for Indian Point Nuclear Generating Unit Nos. 2 and 3
Project stage: Meeting
ML0726808352007-09-17017 September 2007
Request for Extension of Completion Date for Corrective Actions and Modifications Required by GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML0730402912007-10-24024 October 2007
Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressu
Project stage: Request
ML0732301582007-11-20020 November 2007
Unit No.3 - Denial of Extension Request for Corrective Actions Required by Generic Letter 2004-02
Project stage: Other
ML0732301692007-11-20020 November 2007
Approval of Extension Request for Corrective Actions Required by Generic Letter 2004-02
Project stage: Other
ML0734600422007-12-0303 December 2007
Revised Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions & Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at
Project stage: Request
ML0733800442007-12-0303 December 2007
LB Order (Censure of Sherwood Martinelli)
Project stage: Request
NL-05-0133, Revised Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions & Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents a2007-12-0303 December 2007
Revised Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions & Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at
Project stage: Request
ML0735102422007-12-20020 December 2007
Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02
Project stage: Other
ML0802900972008-01-31031 January 2008
Draft Open Items from Staff Audit of Corrective Actions to Address Generic Letter 2004 02
Project stage: Draft Other
ML0806701352008-02-28028 February 2008
Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML0808801782008-03-27027 March 2008
Summary of February 28, 2008, Meeting with Entergy on the Response to Generic Letter 2004-02 for Indian Point Nuclear Generating Unit Nos. 2 and 3
Project stage: Meeting
NL-08-054, Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat2008-03-28028 March 2008
Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate
Project stage: Request
ML0809900852008-03-28028 March 2008
Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate
Project stage: Request
ML0810002132008-04-10010 April 2008
Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02
Project stage: Other
ML0820701542008-07-21021 July 2008
Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-02
Project stage: Other
05000003/LER-2008-001, Attempted Introduction of Contraband Into the Plant Protected Area Due to Personnel Error2008-07-21021 July 2008
Attempted Introduction of Contraband Into the Plant Protected Area Due to Personnel Error
Project stage: Request
NL-08-119, Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-022008-07-21021 July 2008
Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-02
Project stage: Other
ML0820504062008-07-29029 July 2008
Report on Results of Staff Audit of Corrective Actions Address Generic Letter 2004-02
Project stage: Other
ML0820504332008-07-29029 July 2008
Audit Report-Indian Point Nuclear Generating Unit Nos. 2 and 3 - Report on Result of Staff Audit of Corrective Actions to Address Generic Letter 2004-02
Project stage: Other
ML0825505742008-09-17017 September 2008
Summary of Telephone Conference Call Held on August 7, 2008, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Pertaining to the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3), License
Project stage: Request
ML0825902152008-09-17017 September 2008
Request for Additional Information Regarding Responses to Generic Letter 2004 - 02
Project stage: RAI
ML0829105722008-10-17017 October 2008
Lr Hearing - Draft Telecon Summary of September 15, 2008 Re Reactor Vessel Neutron Embrittlement
Project stage: Request
ML0830102392008-10-17017 October 2008
Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate
Project stage: Request
NL-08-153, Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat2008-10-17017 October 2008
Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate
Project stage: Request
ML0830103662008-10-30030 October 2008
Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02
Project stage: Other
ML0832300542008-11-19019 November 2008
Request for Additional Information Regarding Generic Letter 2004-02
Project stage: RAI
ML0835701532008-12-0101 December 2008
Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Other
NL-08-171, Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-12-0101 December 2008
Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Other
NL-09-021, Response to Request for Additional Information Regarding Generic Letter 2004-022009-02-0202 February 2009
Response to Request for Additional Information Regarding Generic Letter 2004-02
Project stage: Response to RAI
ML0911301222009-04-28028 April 2009
Telcom with Entergy on April 16, 2009, on Chemical Effects Testing for Generic Letter 2004-02
Project stage: Other
ML0921903102009-07-29029 July 2009
Request for Extension of Completion Dates for Indian Point, Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat
Project stage: Request
ML0923300752009-08-25025 August 2009
Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02
Project stage: Other
ML0926400612009-09-24024 September 2009
Summary of Conference Call with Entergy on Proposed Response to a Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML0932903162009-11-19019 November 2009
Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML1011702372010-04-29029 April 2010
Request for Additional Information Regarding Generic Letter 2004-02
Project stage: RAI
ML1016501692010-06-18018 June 2010
June 9, 2010 Summary of Conference Call with Entergy on Proposed Response to Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
2008-02-28
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 April 28, 2009 LICENSEE:
Entergy Nuclear Operations, Inc.
FACILITY:
Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
TELECON WITH ENTERGY ON APRIL 16, 2009, ON CHEMICAL EFFECTS TESTING FOR GENERIC LETTER 2004-02 (TAC NOS. MC4689 AND MC4690)
On April 16, 2009, a telephone call was held between the Nuclear Regulatory Commission (NRC) staff and representatives of Entergy Nuclear Operations, Inc. (Entergy or the licensee).
The purpose of the call was to discuss the licensee's plans to conduct chemical effects testing to support analyses required by NRC Generic Letter 2004-02, "Potentiallmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors."
The analyses are being performed for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3). See Enclosure 1 for a list of participants on the call, and Enclosure 2 for the handout provided by Entergy. The NRC staff generally agreed with the test protocol, but stressed two points: (1) that additional details (e.g., post-Ioss-of-coolant-accident pH range) would be needed for the NRC staff to assess the conservative nature of the IP test, and (2) the NRC staff's comments about the vendor's proposed test approach was unique to IP and that other licensee's tests would be evaluated on a case-by-case basis.
Please direct any inquiries to me at (301) 415-2901.
Sincerely,
..,....""1
(
r
- J.//) c.:<<:
..~H:-L:.
".Jbhn P. Boska, Senior Project Manager l/Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout cc w/encls: Distribution via Listserv
List of Attendees:
NRC J. Boska P. Klein M. Yoder S. Smith J. Lehning B. Bickett A. Ziedonis Entergy R. Walpole R. Waters V. Meyers J. Gehrlein E. Weinkam Alion R. Choromokos J. Furman Enercon K. Milliken K. Walker
HighTemperatureVerticalLoop Testing Indian Point Units 2 and 3 April 16th, 2009
HighTemperatureVerticalLoop Approach UsingtheHighTemperatureVerticalLoop(HTVL),IndianPoint2
&3(IP2&3)sumptemperature(below200°F)andchemistry willbesimulated Headlossismeasuredforthedurationofthetesttomeasure thetemperatureandtimefortheheadlossimpactofchemical precipitates HTVLresultswillbeusedtorefinetimingandtemperatureof chemicalprecipitateheadlossapplicationtolargescaletank testresults
HighTemperatureVerticalLoop Methodology UsesWCAP16530predicteddissolvedAl&Siconcentrations Sodiumtetraborate(NaTB)andboronsumpchemistryofIP2&
IP3 Simulatesworstcasetemperature,chemistryandpHfor precipitationatsumptemperaturesbelow200°F Determineswhenchemicalprecipitatescausesignificant increaseinheadlossinHTVL
HighTemperatureVerticalLoop EquipmentSpecifications Temperature:200° Fto65°F Pressure:atmosphericto5psig Volume:nominal60liters Screenapproachvelocities:
0.001 0.1ft/sec (IP2&3willuse0.013ft/s)
Maximumbeddifferential pressure:5 H2O(operational),
10 H2O(structural)
HighTemperatureVerticalLoop TestStrategy
- 1. Loopisfilledwithrecirculatingborated,bufferedwaterand heatedto200°F
- 2. TargetpHstomaximizeprecipitation a)
WCAP16530analysisconsideredpH4.62to7.4-maximumcorrosion willbeused b) 7.1pHusedinHTVL-Chosentomaximizeprecipitation c) pHismaintainedatorbelow7.1throughouttest
- 3. Thindebrisbedisestablished a)
NUKONfiber- ~1/2inchthickfiberbed b)
Siliconcarbide-5:1particulate/fiberratio
HighTemperatureVerticalLoop TestStrategy
- 4. Loopispressurizedwithnitrogengasorcompressedairas requiredtoensureadequateNPSHmargin
- 5. Whenheadlosshasstabilized,chemicalsareinjected
- Aluminum:2.9ppm(designvalue)
94.4ppm(designvalue)
- 6. Temperatureisreducedinstepscorrespondingwiththepost LOCAsumptemperaturesofinterest
- 7. Temperatureisheldateachstepforatleast6.5hours
- 8. Headlossismeasuredandthetimingandtemperatureof precipitateheadlossisdetermined
HighTemperatureVerticalLoop TestProfile Temperatureis adjustedtopoints ofinterest Durationsbound planttimingand addressreaction kinetics 0
50 100 150 200 250 0
20 40 60 80 100 120 Temperature(°F)
Time(h)
IP2&3HotLoopTemperatureProfilevs.MaximumSump Temperatures HTVLTemperature Curve ContainmentSump MaximumTemperature Curve 115°F 160°F 105°F 110°F 180°F 170°F 70°F 65°F AdditionalAl injected Actual temperatures and durations may vary pending approval of the Test Plan.
HighTemperatureVerticalLoop IncrementalElementalAddition Corrosion/dissolutionisarelativelyslowprocess IncrementalElementalAdditionaccountsforgradualcorrosionand dissolution ElementsareinjectedintotheHTVLatWCAP16530plantcorrosionand dissolutionrates
- NRCStaffguidancerelativetodoublingaluminumcorrosionrateisconsideredandapplied InjectionquantitiescorrespondWCAP16530analysisatmaximum temperature Injectiontimingcorrespondswithminimumplanttemperatureprofileto maximizeprecipitation TimingprovidesconservativesimulationofWCAP16530 dissolution/corrosionphenomena
HighTemperatureVerticalLoop Conclusions MethodologyforIP2&3isdesignedtomeasurewhenchemicalprecipitates willhaveanimpactonstrainerheadlossbymeasuringthetimingand temperatureoftheonsetofprecipitateheadloss ProvidesIP2&3representativeandconservativeplantsumpchemistryand headlossdatawithouttheneedforextrapolation
- HTVLtestingisusedforprecipitateheadlosstiming/temperatureevaluation
- Largescaletestingisusedforplantstrainerheadlossprediction Dualtestingmethodsareintegratedwithtime/temperaturedependent acceptableheadlossestoresolveGSI191forIP2&3
AcceptanceCriteria
- GreaterthanStructuralat~160°F
- MinimumFlowPerformance(TIMEBASED)
- Strainerheadlosslimitationfortherecirculationpumpsto ensureadequateflow
- Sprayssecuredwithin6.5hours
- Applicableatalltimesandtemperatures
- Anticipatedgoverningcriteriaafter6.5hours
MaximumCoolingCalculation
- Previouscontainmentanalysistemperaturecurvesuse assumptionstomaximizetemperature
- Newcalculationisbeingdevelopedtoestimateaconservative minimumtemperatureat6.5hours
- Preliminaryanalysisshowsminimumsumptemperature
- IP2~110°F
- IP3~115°F
ExpectedVerticalLoopResults
- Littleornoheadlosseffectfrom3ppmAlat6.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />sand65°F
- Resultsinatemperaturemarginof~45°F (65°F+45°F=110°F)
- Intentistodemonstratethatchemicalsdonot precipitatebefore6.5hours
- Structuralbecomesonlycriteria
ApplicationofResults
- Above160°F:Applytoconventionaldebrisheadlossvaluesonly
- Below160°F:Applytoconventionaldebrisplus100%WCAPchemical headlossvalues
- MinimumFlowPerformanceCriteria(<6.5hours)
- Applytoconventionaldebrisheadlossvalues
- Applytoconventionaldebrisplus100%WCAPchemicalheadloss values
April 28, 2009 LICENSEE:
Entergy Nuclear Operations, Inc.
FACILITY:
Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
TELECON WITH ENTERGY ON APRIL 16, 2009, ON CHEMICAL EFFECTS TESTING FOR GENERIC LETTER 2004-02 (TAC NOS. MC4689 AND MC4690)
On April 16, 2009, a telephone call was held between the Nuclear Regulatory Commission (NRC) staff and representatives of Entergy Nuclear Operations, Inc. (Entergy or the licensee).
The purpose of the call was to discuss the licensee's plans to conduct chemical effects testing to support analyses required by NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors."
The analyses are being performed for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3). See Enclosure 1 for a list of participants on the call, and Enclosure 2 for the handout provided by Entergy. The NRC staff generally agreed with the test protocol, but stressed two points: (1) that additional details (e.g., post-Ioss-of-coolant-accident pH range) would be needed for the NRC staff to assess the conservative nature of the IP test, and (2) the NRC staff's comments about the vendor's proposed test approach was unique to IP and that other licensee's tests would be evaluated on a case-by-case basis.
Please direct any inquiries to me at (301) 415-2901.
Sincerely, Ira!
John P. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-1 RidsNrrPM~IBoska RidsOGCRp LPL1-1 Reading File RidsNrrLASLittle RidsAcrsAcnw_MailCTR RidsNrrDssSsib RidsNrrDorlDpr RidsRgn1 MailCenter RidsNrrDciCsgb PKlein BBickett ADAMS ACCESSION NO.: ML091130122 OFFICE LPL1-1/PM LPL1-1/LA CSGB LPL 1-1/BC(A)
NAME JBoska SLittie PKlein RGuzman DATE 4/27/09 4/27/09 4/27/09 4/28/09 OFFICIAL RECORD COPY
