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Category:Note to File incl Telcon Record
MONTHYEARML22264A0452022-09-20020 September 2022 Neutron Source Assembly Loading Clarification Call ML22172A1742022-06-17017 June 2022 Exemption Environmental Assessment Conversation Record (6-16-22) ML21221A3112021-07-29029 July 2021 Transcript for Public Meeting Held on July 29, 2021, in Tarrytown, New York Regarding Indian Point Energy Center Post-Shutdown Decommissioning Activities Report ML18204A1802018-07-23023 July 2018 Transcript of Annual Assessment Meeting for Indian Point Units 2 and 3 ML18046B4412018-02-23023 February 2018 Review of Updated Final Safety Analysis Report, Revision 7 ML17191A4562017-09-20020 September 2017 06/08/2017 Telecon Summary Related to Indian Point License Renewal RAIs Associated with ISG-2016-01 ML13354C0172014-01-0909 January 2014 Telecon Summary 12-18-13 Action Item 7 Alternative ML11215A0882011-08-30030 August 2011 July 25, 2011, Summary of Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Steam Generator Aging Management and Meal Fatigue Analysis for Indian Point Nuclear Generating Station, Unit ML0914200362009-06-11011 June 2009 Summary of Telephone Conference Call Held on May 11, 2009, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc,, Concerning Endangered Species Act Consultation Data ML0909705822009-04-0707 April 2009 Phone Call Summary with Licensees and Alion Science and Technology on April 2, 2009 to Address NRC Staff Position on Chemical Effects Refinements ML0905404262009-02-26026 February 2009 Summary of Teleconference Held on January 27, 2009, Between the USNRC Staff and Entergy Representatives to Discuss NRC Analysis of Aquatic Impacts in Supplement 38 NUREG-1437 ML0820506122008-07-25025 July 2008 07/08/2008 - Summary of Telephone Conference Call Held on July 8, 2008, Between the NRC & Entergy Nuclear Operations, Inc., Related to the Indian Point, Unit 2 & 3, License Renewal Application Reactor Vessel Neutron Embrittlement & Submerge ML0814008212008-05-23023 May 2008 05/07/2008 Summary of Telephone Conference Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Related to the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application - Status of Open I ML0801804202008-01-22022 January 2008 Summary of Telephone Conference Call Held on January 9, 2008, Between the Us NRC and Entergy Nuclear Operations, Inc., Draft RAI Pertaining to Indian Point, Units 2 & 3, License Renewal Application - Reactor Coolant System ML0727706052007-10-16016 October 2007 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Draft Requests for Additional Information Pertaining to Indian Point Generating Station. ML0713100432007-02-0808 February 2007 E-Mail from T. Rice of NYSDEC to Various, Regarding IPEC Fish Sampling ML0634603402006-12-0808 December 2006 Kld Associates, Appendix F, Telephone Survey ML0613202242006-03-0202 March 2006 E-mail from W. Axelson of Entergy to J. White of USNRC, Regarding Telephone Conversation.Doc ML0327316872003-09-26026 September 2003 Memo Record of Phone Call on September 17, 2003 - September 8, 2003, Riverkeeper and Union of Concerned Scientists (Ucs) 2.206 Petition (Tacs. MC0725/MC0726) ML17252A8731974-01-15015 January 1974 Letter Regarding Periodic Surveillance Test PT-M2, Reactor Coolant Temperature Analog Channel Functional Test - Delta T Overtemperature and Delta T Overpower in Cold Shutdown Condition -Indian Point Unit 2 ML17252A8751974-01-0808 January 1974 Letter Regarding Analysis of Results of Monthly Periodic Surveillance Test PT-M11 Indicated That the Setting of One of the Four Steam Line Pressure Bistables Was Below the Technical Specification - Indian Point Unit 2 ML17252A8911973-09-17017 September 1973 Letter Informing of 09/13/1973 Occurrence During Maintenance of the 80' Elevation Outer Door of the Vapor Container, the Inner Door Was Partially Opened for a Short Period - Indian Point Unit 2 2022-09-20
[Table view] Category:Verbal Comm
MONTHYEARML22264A0452022-09-20020 September 2022 Neutron Source Assembly Loading Clarification Call ML22172A1742022-06-17017 June 2022 Exemption Environmental Assessment Conversation Record (6-16-22) ML21221A3112021-07-29029 July 2021 Transcript for Public Meeting Held on July 29, 2021, in Tarrytown, New York Regarding Indian Point Energy Center Post-Shutdown Decommissioning Activities Report ML18204A1802018-07-23023 July 2018 Transcript of Annual Assessment Meeting for Indian Point Units 2 and 3 ML18046B4412018-02-23023 February 2018 Review of Updated Final Safety Analysis Report, Revision 7 ML17191A4562017-09-20020 September 2017 06/08/2017 Telecon Summary Related to Indian Point License Renewal RAIs Associated with ISG-2016-01 ML13354C0172014-01-0909 January 2014 Telecon Summary 12-18-13 Action Item 7 Alternative ML11215A0882011-08-30030 August 2011 July 25, 2011, Summary of Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Steam Generator Aging Management and Meal Fatigue Analysis for Indian Point Nuclear Generating Station, Unit ML0914200362009-06-11011 June 2009 Summary of Telephone Conference Call Held on May 11, 2009, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc,, Concerning Endangered Species Act Consultation Data ML0909705822009-04-0707 April 2009 Phone Call Summary with Licensees and Alion Science and Technology on April 2, 2009 to Address NRC Staff Position on Chemical Effects Refinements ML0905404262009-02-26026 February 2009 Summary of Teleconference Held on January 27, 2009, Between the USNRC Staff and Entergy Representatives to Discuss NRC Analysis of Aquatic Impacts in Supplement 38 NUREG-1437 ML0820506122008-07-25025 July 2008 07/08/2008 - Summary of Telephone Conference Call Held on July 8, 2008, Between the NRC & Entergy Nuclear Operations, Inc., Related to the Indian Point, Unit 2 & 3, License Renewal Application Reactor Vessel Neutron Embrittlement & Submerge ML0814008212008-05-23023 May 2008 05/07/2008 Summary of Telephone Conference Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Related to the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application - Status of Open I ML0801804202008-01-22022 January 2008 Summary of Telephone Conference Call Held on January 9, 2008, Between the Us NRC and Entergy Nuclear Operations, Inc., Draft RAI Pertaining to Indian Point, Units 2 & 3, License Renewal Application - Reactor Coolant System ML0727706052007-10-16016 October 2007 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Draft Requests for Additional Information Pertaining to Indian Point Generating Station. ML0713100432007-02-0808 February 2007 E-Mail from T. Rice of NYSDEC to Various, Regarding IPEC Fish Sampling ML0634603402006-12-0808 December 2006 Kld Associates, Appendix F, Telephone Survey ML0613202242006-03-0202 March 2006 E-mail from W. Axelson of Entergy to J. White of USNRC, Regarding Telephone Conversation.Doc ML0327316872003-09-26026 September 2003 Memo Record of Phone Call on September 17, 2003 - September 8, 2003, Riverkeeper and Union of Concerned Scientists (Ucs) 2.206 Petition (Tacs. MC0725/MC0726) ML17252A8731974-01-15015 January 1974 Letter Regarding Periodic Surveillance Test PT-M2, Reactor Coolant Temperature Analog Channel Functional Test - Delta T Overtemperature and Delta T Overpower in Cold Shutdown Condition -Indian Point Unit 2 ML17252A8751974-01-0808 January 1974 Letter Regarding Analysis of Results of Monthly Periodic Surveillance Test PT-M11 Indicated That the Setting of One of the Four Steam Line Pressure Bistables Was Below the Technical Specification - Indian Point Unit 2 ML17252A8911973-09-17017 September 1973 Letter Informing of 09/13/1973 Occurrence During Maintenance of the 80' Elevation Outer Door of the Vapor Container, the Inner Door Was Partially Opened for a Short Period - Indian Point Unit 2 2022-09-20
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23171B0442023-06-23023 June 2023 Enclosure - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML22292A2402022-10-21021 October 2022 RAIs for Master Dtf Agreement on IP1 IP2 10 18 2022 ML22103A2442022-04-13013 April 2022 Attachment - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center ML22104A0352022-04-13013 April 2022 Request for Additional Information Related to Exemption Request from Emergency Planning Holtec Decommissioning International, LLC Indian Point Energy Center ML22006A0452022-01-0505 January 2022 PSDAR RAIs Final ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) ML21183A1602021-06-30030 June 2021 Update Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (06/30/2021 E-mail) ML21138A9412021-05-18018 May 2021 Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (05/18/2021 E-mail) ML21112A2672021-04-22022 April 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version) ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML21013A0152021-01-12012 January 2021 Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20268C2352020-09-24024 September 2020 Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20233B0152020-08-20020 August 2020 Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20190A2342020-07-0808 July 2020 Request for Additional Information - Application for Order Consenting to Transfers of Control of Licenses (07/08/2020 E-mail) ML20190A1502020-06-25025 June 2020 (06/25/2020 E-mail) Draft Request for Additional Information Application for Order Consenting to Transfers of Control of Licenses ML20106F2492020-04-15015 April 2020 E-mail (04/15/2020) Request for Additional Information Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic ML20070J7902020-03-10010 March 2020 Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012 ML19045A6252019-02-14014 February 2019 Request for Additional Information - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool - 2/14/19 E-mail from R.Guzman to M.Mirzai NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension2018-07-18018 July 2018 Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension ML18155A4842018-06-0404 June 2018 Request for Additional Information Regarding Relief Request IP3-ISI-RR-11, E-mail from R.Guzman to C.Mackaman ML18143B6792018-05-23023 May 2018 Request for Additional Information Regarding LAR for One-Time Extension of the Containment Leakage Rate Test - Email from R.Guzman to M.Mirzai ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML17296A2352017-10-23023 October 2017 Request for Additional Information -10/23/17 E-mail from R.Guzman to R.Louie Cyber Security Plan Milestone 8 Implementation Schedule (CAC Nos. MF9656, MF9657, MF9658; EPID: L-2017-LLA-0217) ML17277B5482017-10-0303 October 2017 Request for Additional Information - Relief Request IP2-ISI-RR-20 Regarding Weld Examination ML17219A1062017-08-10010 August 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information ML17200A0852017-07-19019 July 2017 Request for Additional Information Regarding the Connection of Non-Seismic Boric Acid Recovery System to RWST Seismic Piping ML17197A0002017-07-17017 July 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 ML17103A4182017-04-25025 April 2017 Baffle Bolt Rais. Requests for Additional Information for the Review of the Indian Point License Renewal Application (TAC Nos. MD5407 and MD5408) ML17088A4052017-04-20020 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 (CAC Nos. MD5407 and MD5408) ML17088A3272017-04-19019 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) ML17100A1282017-04-11011 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 ML16232A1192016-09-12012 September 2016 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units Nos. 2 and 3, License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives (CAC Nos. MD5411 and MD5412) ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 ML16139A0302016-06-10010 June 2016 Request for Additional Information Regarding Conditional Exemption from End-of-Line Moderator Temperature Coefficient Measurement ML16112A2262016-04-26026 April 2016 Request for Additional Information Regarding Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1 ML16041A5782016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Moderator Temperature Coefficient Measurement Change ML16005A6292016-01-14014 January 2016 Request for Additional Information Regarding Relief Request IP2-RR-19 ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15148A4032015-06-29029 June 2015 Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis ML15156B2742015-06-16016 June 2015 Request for Additional Information Regarding Request to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15125A0972015-05-0606 May 2015 Request for Additional Information Regarding License Amendment to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15071A1012015-05-0404 May 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408) ML15103A2592015-04-28028 April 2015 Request for Additional Information Regarding the Proposed License Amendment to Extend the Containment Type a Leak Rate Testing Frequency to 15 Years ML15104A5412015-04-22022 April 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) ML15072A4172015-03-17017 March 2015 Request for Additional Information Regarding Extension of the Containment Type a Leak Rate Testing Frequency to 15 Years ML14329B2452015-02-18018 February 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015 Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company 2023-06-23
[Table view] |
Text
January 22, 2008 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 9, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION - REACTOR COOLANT SYSTEM The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on January 9, 2008, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAI. provides a listing of the participants; and Enclosure 2 contains a listing of the D-RAI items discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Kimberly Green, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
As stated cc w/encls: See next page
ML080180420 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME SFigueroa KGreen RFranovich DATE 01/22/08 01/22/08 01/22/08
TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JANUARY 9, 2008 PARTICIPANTS AFFILIATIONS Kim Green U.S. Nuclear Regulatory Commission (NRC)
Benjamin Parks NRC Mike Stroud Entergy Nuclear Operations, Inc. (Entergy)
Ted Ivy Entergy Ron Finnin Entergy Stan Batch Entergy ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION REACTOR COOLANT SYSTEM JANUARY 9, 2008 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on January 9, 2008, to discuss and clarify the following draft request for additional information (D-RAI) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 license renewal application (LRA).
D-RAI 2.3A.1.2-1 Reactor Vessel Internals If failure of the following reactor vessel internals could potentially inhibit core coolability in an accident scenario, they would be subject to the requirement in 10 CFR 54.4(a)(2). Justify the exclusion of these components from the scope of license renewal:
a) rectangular sample tubing, b) sample tubing springs, and c) core energy absorber Discussion: The applicant stated that the components identified in (a) and (b) are referred to as holder and holder closures (ref. WCAP-14577-A), and that the component (c) is referred to as a secondary core support (ref. LRA, pp 3.1-80 and 3.1-99). Upon further review by the staff, component (c) will be eliminated from the question. The revised question will be sent as a formal RAI.
If failure of the following reactor vessel internals could potentially inhibit core coolability in an accident scenario, they would be subject to the requirement in 10 CFR 54.4(a)(2). Justify the exclusion of these components from the scope of license renewal:
a) rectangular sample tubing and b) sample tubing springs D-RAI 2.3A.1.3-2 Reactor Coolant Pressure Boundary Manway covers and insert plates (see LRA Table 2.3.1-3-IP2 and 2.3.1-3-IP3) have been identified as within the scope of license renewal and subject to an aging management review (AMR) in the LRA. Please clarify whether the manways themselves are within the scope of license renewal and subject to an AMR.
Discussion: Based on the discussion with the applicant, the staff agreed to revise this question as follows. The revised question will be sent as a formal RAI.
Pressurizer manway covers and insert plates (see LRA Tables 2.3.1-3-IP2 and 2.3.1-3-IP3) have been identified as within the scope of license renewal and subject to an aging management review (AMR) in the LRA. Please clarify whether the pressurizer manways themselves are within the scope of license renewal and subject to an AMR.
D-RAI 2.3A.1.3-3 Level sensor housing/vents in the reactor vessel level indication system are not highlighted as components that are subject to an AMR (ref: license renewal drawing LRA-208798). The sensor housing/vents appear to provide a reactor coolant pressure boundary. Please clarify whether these components are subject to an AMR, and if not, justify their exclusion.
Discussion: The applicant stated that the sensors are active components; therefore, they are not subject to an AMR. The staff clarified its question to say that it is specifically asking about the vent portion of the sensor shown on the drawing and questions whether the vent has a pressure boundary function. The staff will revise this question as follows. The revised question will be sent as a formal RAI.
Level sensor vents in the reactor vessel level indication system are not highlighted as components that are subject to an AMR (ref: license renewal drawing LRA-208798-0). The sensor vents appear to provide a reactor coolant pressure boundary. Please state whether the vents associated with the level sensors, as shown on license renewal drawing LRA-208798-0 have a pressure boundary function and, therefore, should be subject to an AMR. If not, justify their exclusion.
D-RAI 2.3B.1.3-1 High volume sensor housings in the reactor vessel level indication system are not highlighted as components that are subject to an AMR (ref: license renewal drawing LRA-9321-72043, Sht. 5).
The sensor housings appear to provide a reactor coolant pressure boundary. Please clarify whether these components are subject to an AMR, and if not, justify their exclusion.
Discussion: The applicant stated that sensors are active; therefore, the sensors are not subject to an AMR. Therefore, this question is withdrawn and will not be sent as a formal RAI.
D-RAI 2.3B.1.3-2 The auxiliary pressurizer spray has a function identified within the chemical volume and control system for 10 CFR 54.4(a)(3) to provide RCS reactivity, inventory, and pressure control during an Appendix R event. Please explain whether the auxiliary pressurizer spray components that perform the above-intended function are within the scope of license renewal.
Discussion: The applicant referred the staff to license renewal drawings LRA-9321-27363 and LRA-9321-37473 which show the auxiliary pressurizer spray components that have an Appendix R intended function. After further review by the staff, it determined that the auxiliary pressurizer spray components are highlighted on the stated drawings as subject to an AMR.
Therefore, this question is withdrawn and will not be sent as a formal RAI.
D-RAI 2.3A.2.4-1 Safety Injection System The safety injection accumulators are highlighted on license renewal drawings LRA-235296-0 and LRA-27353-0 as subject to an AMR; however, LRA Tables 2.3.2-4-IP2 and 2.3.2-4-IP3 do not include them as component types subject to an AMR. Please clarify whether the accumulators are subject to an AMR.
Discussion: The applicant stated that the accumulators are referred to as component type tank. The staff confirmed that LRA Tables 2.3.2-4-IP2 and 2.3.2-4-IP3 include the component type tank as subject to an AMR. Therefore, this question is withdrawn and will not be sent as a formal RAI.
D-RAI 2.3A.4.5-2 IP2 AFW Pump Room Fire Event Please provide a separate listing of those auxiliary steam system components subject to an AMR that support the refueling water storage tank pressure boundary.
Discussion: The applicant referred the staff to license renewal drawing LRA-9321-2735. After further review by the staff, it determined that the auxiliary steam system components are highlighted on the stated drawing as subject to an AMR. Therefore, this question is withdrawn and will not be sent as a formal RAI.
Letter to Michael Balduzzi from Kimberly Green, dated January 22, 2008 DISTRIBUTION:
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 9, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION - REACTOR COOLANT SYSTEM HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr RidsNrrDlrRpb1 RidsNrrDlrRpb2 RidsNrrDlrRer1 RidsNrrDlrRer2 RidsNrrDlrRerb RidsNrrDlrRpob RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDraAplb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSbwb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter
RFranovich BPham GMeyer, RI KGreen MMcLaughlin, RI JCaverly NMcNamara, RI RAuluck DScrenci, RI OPA KChang NSheehan, RI OPA MKowal MCox, RI JBoska PCataldo, RI STurk, OGC CHott, RI LSubin, OGC DJackson, RI BMizuno, OGC BWelling, RI SBurnell, OPA DMcIntyre, OPA EDacus, OCA TMensah, OEDO RConte, RI ECobey, RI
Indian Point Nuclear Generating Units 2 and 3 cc:
Mr. Michael R. Kansler Mr. John A. Ventosa President & CEO / CNO GM, Engineering Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Mr. John F. McCann Senior Vice President Director, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Sr. Vice President Ms. Charlene D. Faison Engineering & Technical Services Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Fred R. Dacimo Mr. Ernest J. Harkness Site Vice President Director, Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Indian Point Energy Center 1340 Echelon Parkway 450 Broadway, GSB Jackson, MS 39213 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric W. Conroy Director, Nuclear Safety Assurance Mr. Anthony Vitale - Acting Entergy Nuclear Operations, Inc.
General Manager, Plant Operations Indian Point Energy Center Entergy Nuclear Operations, Inc. 450 Broadway, GSB Indian Point Energy Center P.O. Box 249 450 Broadway, GSB Buchanan, NY 10511-0249 P.O. Box 249 Buchanan, NY 10511-0249 Mr. T.R. Jones - Acting Manager, Licensing Mr. Oscar Limpias Entergy Nuclear Operations, Inc.
Vice President Engineering Indian Point Energy Center Entergy Nuclear Operations, Inc. 450 Broadway, GSB 1340 Echelon Parkway P.O. Box 249 Jackson, MS 39213 Buchanan, NY 10511-0249 Mr. Joseph P. DeRoy Mr. William C. Dennis Vice President, Operations Support Assistant General Counsel Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601
Indian Point Nuclear Generating Units 2 and 3 cc:
Mr. Paul D. Tonko President and CEO Mr. Raymond L. Albanese New York State Energy Research and Four County Coordinator Development Authority 200 Bradhurst Avenue 17 Columbia Circle Unit 4 Westchester County Albany, NY 12203-6399 Hawthorne, NY 10532 Mr. John P. Spath Mr. William DiProfio New York State Energy, Research and PWR SRC Consultant Development Authority 48 Bear Hill Road 17 Columbia Circle Newton, NH 03858 Albany, NY 12203-6399 Mr. Garry Randolph Mr. Paul Eddy PWR SRC Consultant New York State Department 1750 Ben Franklin Drive, 7E of Public Service Sarasota, FL 34236 3 Empire State Plaza Albany, NY 12223-1350 Mr. William T. Russell PWR SRC Consultant Regional Administrator, Region I 400 Plantation Lane U.S. Nuclear Regulatory Commission Stevensville, MD 21666-3232 475 Allendale Road King of Prussia, PA 19406 Mr. Jim Riccio Greenpeace Senior Resident Inspectors Office 702 H Street, NW Indian Point 2 Suite 300 U.S. Nuclear Regulatory Commission Washington, DC 20001 P.O. Box 59 Buchanan, NY 10511 Mr. Phillip Musegaas Riverkeeper, Inc.
Senior Resident Inspectors Office 828 South Broadway Indian Point 3 Tarrytown, NY 10591 U.S. Nuclear Regulatory Commission P.O. Box 59 Mr. Mark Jacobs Buchanan, NY 10511 IPSEC 46 Highland Drive Mr. Charles Donaldson, Esquire Garrison, NY 10524 Assistant Attorney General New York Department of Law Mr. R. M. Waters 120 Broadway Technical Specialist Licensing New York, NY 10271 450 Broadway P.O. Box 0249 Mayor, Village of Buchanan Buchanan, NY 10511-0249 236 Tate Avenue Buchanan, NY 10511
Indian Point Nuclear Generating Units 2 and 3 cc:
Mr. Sherwood Martinelli 351 Dyckman Peekskill, NY 10566 Ms. Susan Shapiro, Esq.
21 Perlman Drive Spring Valley, NY 10977 John Sipos Assistant Attorney General New York State Department of Law Environmental Protection Bureau The Capitol Albany, NY 12224 Robert Snook Assistant Attorney General Office of the Attorney General State of Connecticut 55 Elm Street P.O. Box 120 Hartford, CT 06141-0120 Ms. Kathryn M. Sutton, Esq.
Morgan, Lewis & Bockius, LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Mr. Paul M. Bessette, Esq.
Morgan, Lewis & Bockius, LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Mr. Martin J. ONeill, Esq.
Morgan, Lewis & Bockius, LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 The Honorable Nita Lowey 222 Mamaroneck Avenue, Suite 310 White Plains, NY 10605