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{{#Wiki_filter:UNiTED STATES NUCLEAR REGULATORY COMMISSION ATOMIC: SAFETY, LICENSING BOARD DOCKETED USNRC May 22, 2008 (2:42pm)OFFICE OF. SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF-X In re: License Renewal Application Submitted by Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc.Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858.03.LR-BD01 DPR-26, DPR-64 May 22,2008-x NEW YORK STATE'S SUPPLEMENTAL CITATION IN SUPPORT OF ADMISSION OF CONTENTION-26A On May 14, 2008 -two weeks after the State of New York submitted its Reply to Entergy's Answer and NRC Staff's Response to New York's Supplemental Contention No.26-A (Metal Fatigue) -the NRC Staff posted on ADAMS a May 8, 2008 Summary of an April 3, 2008 telephone conference between Entergy and Staff regarding, inter alia, how much information NRC Staff would require Entergy to produce as part of its License Renewal Application.'
{{#Wiki_filter:DOCKETED USNRC UNiTED STATES                                       May 22, 2008 (2:42pm)
The Summary is contained in Attachment 1 to this Supplement, and is also available at ML081190059.
NUCLEAR REGULATORY COMMISSION                                      OFFICE OF. SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF ATOMIC: SAFETY, LICENSING BOARD
The May 8 Summary reveals that Entergy, with the acquiescence of Staff, does not intend to allow the details of how it will address metal fatigue issues to be made a part of this license renewal proceeding.
                                                      -X In re:                                                               Docket Nos. 50-247-LR and 50-286-LR License Renewal Application Submitted by                            ASLBP No. 07-858.03.LR-BD01 Entergy Nuclear Indian Point 2, LLC,                                DPR-26, DPR-64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc.                                    May 22,2008
Enclosure 1 to May 8, 2008 Summary of April 3, 2008 Telephone Conference, at pages 1 to 3.This newly-disclosed information supplements the statements made by New York State in its May 1, 2008 Reply at the end of the first full paragraph on page 10.IThe New York State Office of the Attorney General received a copy of the May 8, 2008 Summary via U.S.Mail on May 19, 2008.TE P, A 1FE Z) 3 9 S --ý) --)D Respectfiilly submitted, May 22, 2008 Janice A.: Dean Assistant Attorneys General Office of the Attorney General forthe State ofNew York The Capitol Albany, New York 12224 (518) 402-2251 john.sipos@oag.state.ny.us Joan Leary Matthews Senior Attomey!,forSpecial Projects NewYork State Department of Environmental Conservation 625 Broadway, 14th floor Albany;, New York 12233-5500 (518) 402-9190 jhlnatthe@gw.dec.state.ny.us John Louis Parker, Esq.Regional Attorney New York State Department of Environmental Conservation 21 South Putt Comers Rd New Paltz, NY 12561-1620 ATTACHMENT 1 NRC May 8,2008- Summary of an April 3, 2008 telephone conference between Entergy and NRC Staff also available at ML081190059 UNITED STATES NUCLFAR REGULATORY.COMMISSION May. 8, 2008 MA,-W, LICENSEE:
                                                      -x NEW YORK STATE'S SUPPLEMENTAL CITATION IN SUPPORT OF ADMISSION OF CONTENTION-26A On May 14, 2008 - two weeks after the State of New York submitted its Reply to Entergy's Answer and NRC Staff's Response to New York's Supplemental Contention No.26-A (Metal Fatigue) - the NRC Staff posted on ADAMS a May 8, 2008 Summary of an April 3, 2008 telephone conference between Entergy and Staff regarding, inter alia, how much information NRC Staff would require Entergy to produce as part of its License Renewal Application.' The Summary is contained in Attachment 1 to this Supplement, and is also available at ML081190059. The May 8 Summary reveals that Entergy, with the acquiescence of Staff, does not intend to allow the details of how it will address metal fatigue issues to be made a part of this license renewal proceeding. Enclosure 1 to May 8, 2008 Summary of April 3, 2008 Telephone Conference, at pages 1 to 3.
Ent'Ny Nulear Operations.
This newly-disclosed information supplements the statements made by New York State in its May 1, 2008 Reply at the end of the first full paragraph on page 10.
Inc.FAC(LITY: S UBJ.ECT: Indian Point Nuclear Generating
IThe New York State Office of the Attorney General received a copy of the May 8, 2008 Summary via U.S.
:Unit Nos. 2 and S3  
Mail on May 19, 2008.
TE P, A1FE                                Z)3 9                                                       D S --ý) --)
 
Respectfiilly submitted, May 22, 2008 Joan Leary Matthews Senior Attomey!,forSpecial Projects Janice A.: Dean                 NewYork State Department Assistant Attorneys General       of Environmental Conservation Office of the Attorney General 625 Broadway, 14th floor forthe State ofNew York       Albany;, New York 12233-5500 The Capitol                      (518) 402-9190 Albany, New York 12224          jhlnatthe@gw.dec.state.ny.us (518) 402-2251 john.sipos@oag.state.ny.us       John Louis Parker, Esq.
Regional Attorney New York State Department of Environmental Conservation 21 South Putt Comers Rd New Paltz, NY 12561-1620
 
ATTACHMENT 1 NRC May 8,2008-Summary of an April 3, 2008 telephone conference between Entergy and NRC Staff also available at ML081190059
 
UNITED STATES NUCLFAR REGULATORY.COMMISSION MA,-W, May. 8, 2008 LICENSEE: Ent'Ny Nulear Operations. Inc.
FAC(LITY:       Indian Point Nuclear Generating :Unit Nos. 2 and S3 SUBJ.ECT:     


==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE.CALL LHELD ON APRIL BETWEEN THE U.S. NUCLEAR AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS, 2 AND 3, LICENSERENEWAL APPLI.CA.TIO0N-METAL FATIGUE, BOLTED CONNECTIONS, AND BORAFLEXýThe U.-S. Nuclear Regulatory Commission (NRC or the staff) and. repre'sentatiVe6s" of Eintergy Nuclear Operatio'ns,-
OF TELEPHONE CONFERENCE.CALLLHELD ON APRIL *3,2008,,
Inc., held a telephone conference call on April 3, 2008, to discuss and clriy the staff's draft request for additional Information (0;i ocenn h Ida on Nuclear.Generating Unit Nos. 2 and 3, license renewal application.
BETWEEN THE U.S. NUCLEAR REGULATORY.COMI*MI.R1ON AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS, 2 AND 3, LICENSERENEWAL APPLI.CA.TIO0N-METAL FATIGUE, BOLTED CONNECTIONS, AND BORAFLEXý The U.-S. Nuclear Regulatory Commission (NRC or the staff) and. repre'sentatiVe6s" of Eintergy Nuclear Operatio'ns,- Inc., held a telephone conference call on April 3, 2008, to discuss and clriy the staff's draft request for additional Information (0;i     ocenn h Ida on Nuclear.Generating Unit Nos. 2 and 3, license renewal application. The telepihoeq"c'onfrec calwsuseful rin clarifyn thq intent of the staff's D-fRAl provides.:a isti ngof the participants and Enclosuire 2 conttalins-a listing of the D-RAI i.1em-s-disct s, wit th; appiat inluding a befdescrpin on th Pttsofteies Theappicnthad anooportunityito-commentntis s-ummay Kimberly Gre n, SafeyPojc Mange Projects Branch 2 Division of Liceinse Reeal:
The telepihoeq"c'onfrec calwsuseful rin clarifyn thq intent of the staff's D-fRAl Enclosure 1 provides.:a isti ngof the participants and Enclosuire 2 conttalins-a listing of the D-RAI i.1em-s-disct s, wit th; appiat inluding a befdescrpin on th Pttsofteies Theappicnthad ano oportunityito-commentntis s-ummay Kimberly Gre n, SafeyPojc Mange Projects Branch 2 Division of Liceinse Reeal: Office of'- ru'lear Reao Regu laton Do6kt Nos'. 50-247 and 50'28 Enclo~sures-1I, List of Participants 2.Summ~ary of Discussion..
Office of'- ru'lear Reao Regu laton Do6kt Nos'. 50-247 and 50'28 Enclo~sures-1I, List of Participants 2.Summ~ary of Discussion..
'cwencls.
      'cwencls.See next page
See next page Indianý Point Nuclear Generating Units. 2.and 3 cc: Senior Vice President Entergy, Nuclear Operations, Inc.P.'O.Box 31995 Jackson,.MS 39286-1995 Vice President Oversight Entergy Nuclear Operations, Inc.P.O.Box 31995 Jackson,.
 
MS 39286A1995 Senior Manager, Nuclear Safety.&Licensing Entergy Nuclear Operations, Inc.P'O. Box 31995 Jackson, MS 39286-1995 Senior Vice President and COO Entergy Nuclear Operations, Inc.440 Hamilton Avenue White Plains, NY 10601 Assistant General Counsel Entergy Nuclear Operations, Inc.440 Hamilton Avenue White, Plains, NY 10601 Manager, Ucensing Entergy Nuclear Operations, Inc.Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Paul D. Tonko President and CEO New York State Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. John P. Spath New.York StateEnergy, Research.and.Development Authority 17 'Columbia-Circle Albany, NY 12203-6399 Mr. PaulEddy New. York State Department of Public Service 3 Empire StatePlaza Albany, NY 12223-1350 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector's Office Indian Point 2 U.S. Nuclear Regulatory Commission P.O. Box 59.Buchanan, NY 10511 Senior-Resident Inspector's Office Indian Point-3 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Indian Point Nuclear Generating Units 2and 3 cc: Mr. William DiProfio PWR SRC-Consultant 48 Bear. Hill Road Newton,.NH 03858 Mr. Garry Randolph PWR SRC Consultant 1,750, Ben Franklin Drive, 7E Sarasota,ý FL 34236 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Phillip Musegaas Riverkeeper, Inc.828 South Broadway Tarrytown, NY 10591 Mr. Mark Jacobs IPSEC 46 Highland Drive Garrison, NY 10524 Mr. R. M. Waters Technical Specialist Licensing 450 Broadway P.O. Box 0249 Buchanan, NY 10511-0249 Mr. Sherwood Martinelli 351 Dyckman -Peekskill, NY 10566 Ms. Susan Shapiro, Esq.21 Perlman Drive Spring Valley, NY 10977-2-John Sipos Assistant-Attorney-General NewYork State. Department of Law Environmental Protection Bureau The Capitol Albany, NY 12224 Robert Snook AssistantAttorney General Office of the Attorney General State of Connecticut 55 Elm Street P.O; Box120 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. O'Neill, 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 Joan Leary Matthews Senior Counsel for Special Projects Office of General Counsel NYS Department of Environmental Conservation 625 Broadway Albany, NY 12233-5500 TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS APRIL 3,2008 PARTICIPANTS Kim Green On Yee Peter Wen Jim Davis Bo Pham Jim Medhoff Mike Stroud Garry Young Alan Cox Ted Ivy Don Fronabarger Charlie Caputo John 'Curry Nelson Azevedo Charlie Jackson AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)NRC NRC NRC NRC NRC Entergy Nuclear Operations, Inc. (Entergy)Entergy Entergy Entergy Entergy Entergy Entergy Entergy Entergy ENCLOSURE I
Indianý Point Nuclear Generating Units. 2.and 3 cc:
DRAFT REQUEST FORADDITIONAL INFORMATION INDIAN POINT NUCLEAR GENERAT:ING UNIT NOS. 2AND 3 LICENSE RENEWAL :APPLICATION t 7METAL; FATIGUE April 3, 2008 The U.S.:Nuclear Regulatory Commission (NRC or, the staff)l and representatives of Entergy Nuclear Operations, Inc., held a telephone conferencecall on April 3, 2008, to discuss and clarifylthe following draft requests for additional information (D-RA.s) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 license renewal application (LRA).D-RAI 4.3.1.8-1 License, Renewal Application Section 4.3.1 states wCurrent design basis fatigue evaluations calculate cumulative usage factors (CUFs) forcomponents or-sub-components based on design transient cycles." For CU Fvalues listed in LRA Tables 4.3-13 and 4.3-14, please provide theT methodology used with sufficient results of the fatigue analysis such that the staff can make a determination based onithe guidance described inStandard Review Plan-License Renewal (SRP-LR) (NUREG-1 800). Specifically, please describe the details of how environmentally assisted fatigue (EAF) is factored into the calculation of the CUF using Fe values.Discussion:
Senior Vice President               Mr. John P. Spath Entergy, Nuclear Operations, Inc. New.York StateEnergy, Research.and P.'O.Box 31995                       .Development Authority Jackson,.MS 39286-1995               17 'Columbia-Circle Albany, NY 12203-6399 Vice President Oversight Entergy Nuclear Operations, Inc. Mr. PaulEddy P.O.Box 31995                       New. York State Department Jackson,. MS 39286A1995               of Public Service 3 Empire StatePlaza Senior Manager, Nuclear Safety.&   Albany, NY 12223-1350 Licensing Entergy Nuclear Operations, Inc. Regional Administrator, Region I P'O. Box 31995                       U.S. Nuclear Regulatory Commission Jackson, MS 39286-1995               475 Allendale Road King of Prussia, PA 19406 Senior Vice President and COO Entergy Nuclear Operations, Inc. Senior Resident Inspector's Office 440 Hamilton Avenue                 Indian Point 2 White Plains, NY 10601               U.S. Nuclear Regulatory Commission P.O. Box 59 Assistant General Counsel           .Buchanan, NY 10511 Entergy Nuclear Operations, Inc.
The applicant was uncertain as to whether the staff was requesting that they provide the evaluations or a description of evaluations.
440 Hamilton Avenue                 Senior-Resident Inspector's Office White, Plains, NY 10601             Indian Point-3 U.S. Nuclear Regulatory Commission Manager, Ucensing                   P.O. Box 59 Entergy Nuclear Operations, Inc. Buchanan, NY 10511 Indian Point Energy Center 450 Broadway, GSB                   Mr. Charles Donaldson, Esquire P.O. Box 249                       Assistant Attorney General Buchanan, NY 10511-0249             New York Department of Law 120 Broadway Mr. Paul D. Tonko                   New York, NY 10271 President and CEO New York State Energy Research and Mr. Raymond L. Albanese Development Authority             Four County Coordinator 17 Columbia Circle                 200 Bradhurst Avenue Albany, NY 12203-6399               Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511
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.License renewal application (LRA) Section 4.3.1 states "Current design basis fatigue evaluations calculate cumulative usage factors (CUFs) for components or sub-components based on design transient cycles." For CUF values listed in LRA Tables 4.3-13 and 4.3-14, please describe the details of how various environmental effects are factored into the calculation of the CUF using F,, 6 values.D.RAI 4.3.1.8-2 From the review of EAF analysis of other plants, it was found that the transfer function methodology used in the EAF analysis may not provide valid results, as it is dependent on the inputs. To assist the staff in its review, please provide the EAF analysis for all the NUREG/CR-6260 locations (components) at Indian Point unless it can be demonstrated that the CUF value is within the ASME Code limit of 1.0.by using the original 40-year analysis value adjusted for 60 years and multiplied by Fen, which is consistent with SRP-LR and ASME Code. This analysis should be completed by using NRC-approved fatigue software and the ASME Code, Section III, Subsection NB-3200 methodology (which defines the use of six stress components to determine the stress state and thereby calculates the principal stresses and stress, intensities).
 
Justify the analysis method, the load (stress) combination, and the results of the ASME Code analysis if 2-D axis-symmetric modeling is used. In addition, the analysis should apply ASME code rules such as elastic-plastic correction factor, K, and stress intensities correction factor for modulus of elasticity.
Indian Point Nuclear Generating  Units 2and 3 cc:
This analysis should be performed without the use of the transfer function method.ENCLOSURE 2 Discussion:
Mr. William DiProfio                John Sipos PWR SRC-Consultant                  Assistant-Attorney-General 48 Bear. Hill Road                  NewYork State. Department of Law Newton,.NH 03858                    Environmental Protection Bureau The Capitol Mr. Garry Randolph                  Albany, NY 12224 PWR SRC Consultant 1,750, Ben Franklin Drive, 7E      Robert Snook Sarasota,ý FL 34236                AssistantAttorney General Office of the Attorney General Mr. William T. Russell              State of Connecticut PWR SRC Consultant                  55 Elm Street 400 Plantation Lane                P.O; Box120 Stevensville, MD 21666-3232        Hartford, CT 06141-0120 Mr. Jim Riccio                    Ms. Kathryn M. Sutton, Esq.
The applicant-wanted-clarification on the staff's request. The applicant pointed out thatthe requestis a new staff position and that forprevious plants, the staff hasnot requested the-,analyses.-to.be.provided and, has accepted a:commitmenttoperform 4the analyses two years prior to entering the period of extended operation as Part -6f the6 F atig ue Monitorng Program in accordance with. O CFR 54.21 (c)(1)(iii)..-
Greenpeace                        Morgan, Lewis & Bockius, LLP 702 H Street, NW                    1111 Pennsylvania Avenue, NW Suite 300                          Washington, DC 20004 Washington, DC 20001 Mr. Paul M. Bessette, Esq.
Subsequent to the telePhone conference, the staff determined that no additional information is needed atthis time. Therefore, a formal RAI will not be issued at this time.D-RAI 4.3.1.8ý3 SRP-LR Section 4.3.2.1.1.3 provides the basis for the staff acceptance of an aging management program to addessenvironmental-fatigue.
Mr. Phillip Musegaas              Morgan, Lewis & Bockius, LLP Riverkeeper, Inc.                  1111 Pennsylvania Avenue, NW 828 South Broadway                Washington, DC 20004 Tarrytown, NY 10591 Mr. Martin J. O'Neill, Esq.
lt states, -"[T]hestaff has evaluated-a program for monitoring and tracking the number of critical thermal and, pressure transients for the selected reactor coolant. system:components, Thestaff has determinedthatthis program is an acceptable aging managementeprogram to address metal fatigue of :the reactor coolant system components according to 10 CFR 54.21 (c)(1)(iii).":
Mr. Mark Jacobs                   Morgan, Lewis & Bockius, LLP IPSEC                               1111 Pennsylvania Avenue, NW 46 Highland Drive                 Washington, DC 20004 Garrison, NY 10524 The Honorable Nita Lowey Mr. R. M.Waters                   222 Mamaroneck Avenue, Suite 310 Technical Specialist Licensing     White Plains, NY 10605 450 Broadway P.O. Box 0249                     Joan Leary Matthews Buchanan, NY 10511-0249           Senior Counsel for Special Projects Office of General Counsel Mr. Sherwood Martinelli           NYS Department of Environmental 351 Dyckman       -                 Conservation Peekskill, NY 10566               625 Broadway Albany, NY 12233-5500 Ms. Susan Shapiro, Esq.
The staff is unable to determine if the Fatigue Monitoring Program-of lP2 andl1P3 contain-sufficient details to satisfy:this criterion, based on-the NAhitems listed i!n, LRA Tables 4.3-13 and 4.3-14. Please provide adequate details of the Fatigue Monitoring Program,'
21 Perlman Drive Spring Valley, NY 10977
specifically the fatigue analysis used in determining the CUF values for the NA locations and how IPEC plans to proceed in monitoring the locations of Tables 4.3-13 and 4.3-14 during the period of extended operation.
 
Discussion:
TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS APRIL 3,2008 PARTICIPANTS                            AFFILIATIONS Kim Green                                U.S. Nuclear Regulatory Commission (NRC)
The applicant wanted clarification on what the staff is requesting.
On Yee                                  NRC Peter Wen                                NRC Jim Davis                                NRC Bo Pham                                  NRC Jim Medhoff                              NRC Mike Stroud                              Entergy Nuclear Operations, Inc. (Entergy)
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 RAl, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 4.3.2.1.1.3 provides the basisfor the staff acceptance-of an aging management program to address environmental fatigue. It states, '[t]he staff has evaluated a program for monitoring and tracking the number of critical thermal and pressure transients for the selected reactor coolant system components.
Garry Young                              Entergy Alan Cox                                Entergy Ted Ivy                                  Entergy Don Fronabarger                          Entergy Charlie Caputo                          Entergy John 'Curry                              Entergy Nelson Azevedo                          Entergy Charlie Jackson                          Entergy ENCLOSURE I
The staff has determined that this program is an acceptable aging managembnt program to address metal fatigue of the reactor coolant system components according to 10 CFR 54.21 (c)(1 )(iii)." The staff is unable to determine if the Fatigue Monitoring Program for Indian Point 2 and Indian Point 3 contains sufficient details to satisfy this criterion.
 
Please provide adequate details of the Fatigue Monitoring Program such that the staff can make a determination based on the criterion set forth in SRP-LR Section 4.3.2.1.1.3.
DRAFT REQUEST FORADDITIONAL INFORMATION INDIAN POINT NUCLEAR GENERAT:ING UNIT NOS. 2AND 3 RENEWAL :APPLICATION LICENSEt7METAL; FATIGUE April 3, 2008 The U.S.:Nuclear Regulatory Commission (NRC or,the staff)l and representatives of Entergy Nuclear Operations, Inc., held a telephone conferencecall on April 3, 2008, to discuss and clarifylthe following draft requests for additional information (D-RA.s) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 license renewal application (LRA).
Also, please explain in detail the corrective actions and the frequency that such actions will be taken so that theacceptance criteria will not be exceeded in the period of extended operation. (This RAI will be renumbered as RAI 4.3.1.8-2.)
D-RAI 4.3.1.8-1 License, Renewal Application Section 4.3.1 states wCurrent design basis fatigue evaluations calculate cumulative usage factors (CUFs) forcomponents or-sub-components based on design transient cycles." For CU Fvalues listed in LRA Tables 4.3-13 and 4.3-14, please provide theT methodology used with sufficient results of the fatigue analysis such that the staff can make a determination based onithe guidance described inStandard Review Plan-License Renewal (SRP-LR) (NUREG-1 800). Specifically, please describe the details of how environmentally assisted fatigue (EAF) is factored into the calculation of the CUF using Fe values.
D-RAI 4.3.1.8-4 Section B. 1.12 of the LRA amendment, dated January 22, 2008, states, "If ongoing monitoring indicates the potential for a condition outside that analyzed above, IPEC may perform further reanalysis of the identified configuration using established configuration management processes as described above." Please explain in detail what is meant by the phrase musing established configuration management processes." Also, please explain in detail the corrective actions and the frequency that such actions will be taken so the acceptance criteria will not be exceeded in the period of extended operation. Discussion:
Discussion: The applicant was uncertain as to whether the staff was requesting that they provide the evaluations or a description of evaluations. 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.
The applicant stated that it was unclear-aboutlhe staff's request regarding ,configuration management processes." In a subsequent call, the applicant
License renewal application (LRA) Section 4.3.1 states "Current design basis fatigue evaluations calculate cumulative usage factors (CUFs) for components or sub-components based on design transient cycles." For CUF values listed in LRA Tables 4.3-13 and 4.3-14, please describe the details of how various environmental effects are factored into the calculation of the CUF using F,,
:explained that the'configuration managementprocesses referred to aret those govemed :byits 10 CFR Part 50, APppendix B,,Q u Quality ."Assuranceprogra m, and include design in p ut verification and independent reviews which ensure that valid assumptions, transients, cycles, externaoadingsanalysis methods, and environmental fatigue life correction factors will behusedý inthe fatigue analyses.Therefore, this portion of question is withdrawn and will not be sent asa formal RAI. The portion of.,the request that deals with corrective actions willhbe added to RAI 4.3.1.8-r2(as renumbered).
6 values.
Non-EQ Bolted Cable Connection AMP D-RAI 3.0.3.3.6-1 With regard to Indian Point Aging Management Program (AMP),B.1.22, "Non-EQ Bolted'Cable Connection Program," thellicense renewal applicationstates that inspection methods may include thermography, contact resistance testing, or otherappropriate methods including visual, based on plant configuration and industry guidance.
D.RAI 4.3.1.8-2 From the review of EAF analysis of other plants, it was found that the transfer function methodology used in the EAF analysis may not provide valid results, as it is dependent on the inputs. To assist the staff in its review, please provide the EAF analysis for all the NUREG/
In Generic Aging Lessons Learned (GALL)AMP XI.E6, the staff recommends thermography,, contact resistance testing, or other appropriate methods based on plant configuration and industry guidance for detecting loss of preload or bolt loosening.
CR-6260 locations (components) at Indian Point unless it can be demonstrated that the CUF value is within the ASME Code limit of 1.0.by using the original 40-year analysis value adjusted for 60 years and multiplied by Fen, which is consistent with SRP-LR and ASME Code. This analysis should be completed by using NRC-approved fatigue software and the ASME Code, Section III, Subsection NB-3200 methodology (which defines the use of six stress components to determine the stress state and thereby calculates the principal stresses and stress, intensities). Justify the analysis method, the load (stress) combination, and the results of the ASME Code analysis if 2-D axis-symmetric modeling is used. In addition, the analysis should apply ASME code rules such as elastic-plastic correction factor, K, and stress intensities correction factor for modulus of elasticity. This analysis should be performed without the use of the transfer function method.
In the case where visual inspection will- be the only method used, provide a technical basis of how this will be sufficient to detect loss of preloador loosening of bolted connections.
ENCLOSURE 2
Discussion:
 
The applicant stated that this question is similar to an audit question that has been answered and subsequently discussed during two telephone conferences.
Discussion: The applicant-wanted-clarification on the staff's request. The applicant pointed out thatthe requestis a new staff position and that forprevious plants, the staff hasnot requested the-,analyses.-to.be.provided and, has accepted a:commitmenttoperform 4the analyses two years prior to entering the period of extended operation as Part -6f the6 Fatig ue Monitorng Program in accordance with. OCFR 54.21 (c)(1)(iii)..- Subsequent to the telePhone conference, the staff determined that no additional information is needed atthis time. Therefore, a formal RAI will not be issued at this time.
This issue is being reviewed by the Division of Engineering and, therefore, is withdrawn at this time. However, when the staff has: reached a determination, a formal RAI may be issued at such time.Boraflex AMP D-RAi 3.0.3.2.3-1 Indian Point 2 Updated Final Safety Analysis Report, Revision 20, dated 2006, Section 14.2.1 on page 55 of 218, states in -part that: "Northeast Technology Corporation report NET-173-01 and NET-171-02 are based on conservative projections of amount of boraflex absorber panel degradation assumed in each sub-region.
D-RAI 4.3.1.8ý3 SRP-LR Section 4.3.2.1.1.3 provides the basis for the staff acceptance of an aging management program to addessenvironmental-fatigue. lt states, -"[T]hestaff has evaluated-a program for monitoring and tracking the number of critical thermal and, pressure transients for the selected reactor coolant. system:components, Thestaff has determinedthatthis program is an acceptable aging managementeprogram to address metal fatigue of:the reactor coolant system components according to 10 CFR 54.21 (c)(1)(iii).": The staff is unable to determine if the Fatigue Monitoring Program-of lP2 andl1P3 contain-sufficient details to satisfy:this criterion, based on-the NAhitems listed i!n, LRA Tables 4.3-13 and 4.3-14. Please provide adequate details of the Fatigue Monitoring Program,' specifically the fatigue analysis used in determining the CUF values for the NA locations and how IPEC plans to proceed in monitoring the locations of Tables 4.3-13 and 4.3-14 during the period of extended operation.
These projections are valid through the end of the year 2006." Please confirm that the Boraflex neutron absorber panels in the Indian Point Unit 2 spent fuel pool have been re-evaluated for service through the end of the current licensing period. Also, please discuss the plans for updating the Boraflex analysis during the period of extended operation.
Discussion: The applicant wanted clarification on what the staff is requesting. 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 RAl, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 4.3.2.1.1.3 provides the basisfor the staff acceptance
Discussion:
        -of an aging management program to address environmental fatigue. It states, '[t]he staff has evaluated a program for monitoring and tracking the number of critical thermal and pressure transients for the selected reactor coolant system components.
The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.  
The staff has determined that this program is an acceptable aging managembnt program to address metal fatigue of the reactor coolant system components according to 10 CFR 54.21 (c)(1 )(iii)." The staff is unable to determine if the Fatigue Monitoring Program for Indian Point 2 and Indian Point 3 contains sufficient details to satisfy this criterion. Please provide adequate details of the Fatigue Monitoring Program such that the staff can make a determination based on the criterion set forth in SRP-LR Section 4.3.2.1.1.3. Also, please explain in detail the corrective actions and the frequency that such actions will be taken so that theacceptance criteria will not be exceeded in the period of extended operation. (This RAI will be renumbered as RAI 4.3.1.8-2.)
.,UNITED ,STATES OEAMERICAK NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY LICENSINGBOARD
D-RAI 4.3.1.8-4 Section B. 1.12 of the LRA amendment, dated January 22, 2008, states, "Ifongoing monitoring indicates the potential for a condition outside that analyzed above, IPEC may perform further reanalysis of the identified configuration using established configuration management processes as described above." Please explain in detail what is meant by the phrase musing established configuration management processes." Also, please explain in detail the corrective actions and the frequency that such actions will be taken so the acceptance criteria will not be exceeded in the period of extended operation.
---------------
 
---------x In re: LicenseRenewal Application Submitted by Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc.Docket Nos. 50-247-LR and 50-286-LR-ASLBP No. 07-858-03-LR-BD01 DPR-26, DPR-64-x CERTIFICATE OF SERVICE Pursuant to 28 U.S.C. § 1746 Teresa Fountain hereby declares: I am over 18 years old and am an employee in the New York State Office of the Attorney General.I hereby certify that on May 22, 2008, copies of "The State of New York's Supplemental Citation In Support of Contention 26A" were served upon the following persons via electronic mail and by deposit in the U.S. Postal Service with first class postage: LawrenceG.
Discussion: The applicant stated that it was unclear-aboutlhe staff's request regarding
McDade, Chair Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Lawrence.McDade@nrc.gov Richard E. Wardwell Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Richard.Wardwell@nrc.gov Kaye D. Lathrop Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission 190 Cedar Lane E.Ridgway, CO 81432 Kaye.Lathrop@nrc.gov Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Zachary S. Kahn, Esq.Law Clerk Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Zachary.Kahn@nrc.gov Marcia Carpentier Law'Cleik-Atomic Safety andLicensing Board Panel U.S. Nuclear.Regulatory Commission Mailstop 3 E2B Two White Flint North 11545 Rockville Pike.Rockville, MD 20852-2738 Marcia.Carpentier@nrc.gov Office of Commission Appellate.
,configuration management processes." In a subsequent call, the applicant :explained that the
Adjudication, U.S. NNuclear Regulatory Commission Mailstop 16 G4 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738.ocaamail@nrc.gov Office of the Secretary Attn: Rulemaking and Adjudications Staff U.S. Nuclear Regulatory Commission Mailstop 3F23 Two White'Flint North 11545 Rockville Pike Rockville, MD 20852-2738 hearingdocket@nrc.gov Sherwin E. .Turk, Esq.David E. Roth, Esq.Marcia J. Simon, Esq.Beth N. Mizuno, Esq.Jessica A. Bielecki, Esq.Officeof the General Counsel U.S. Nuclear Regulatory Commission Mailstop 15 D21 One White Flint North 11555 Rockville Pike'Rockville, MD 20852-2738 set@nrc.gov der@nrc.gov jessica.bielecki@nrc.gov bnml@nrc.gov marcia.simon@nrc.gov Kathryn M. Sutton, Esq.Paul M. Bessette, Esq.Martin J. O'Neill, Esq.'Mauri T. Lemoncelli, Esq.Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 ksutton@morganlewis.com pbessette@morganlewis.com martin.o'neill@morganlewis.com mlemoncelli@morganlewis.com cadams@morganlewis.com Elise N. Zoli, E~sq.zGoodvvnPr ,octer, LL IP Exchange Place 53.State Street Boston, MA 02109 ezoli@goodwinprocter~com William C. Dennis, Esq.Assistant General Counsel*Entergy Nuclear Operations, Inc.440 Hamilton7Avenue White'Plains, NY 10601 wdennis@entergy.com Robert D.. Snook!,Esq.
'configuration managementprocesses referred to aret those govemed :byits 10 CFR Part 50, APppendix B,,QQuality u    ."Assuranceprogram, and include design in put verification and independent reviews which ensure that valid assumptions, transients, cycles, externaoadingsanalysis methods, and environmental fatigue life correction factors will behusedý inthe fatigue analyses.
Assistant Attorney General Office of the Attorney General State of Connecticut 55'Elm Street P.O. Box 120 Hartford, CT 06141-0120 robert.snook@po.state.ct.us Justin D. Pruyne, Esq.Assistant County Attorney Office of the Westchester County Attorney Michaelian
Therefore, this portion of question is withdrawn and will not be sent asa formal RAI. The portion of.,the request that deals with corrective actions willhbe added to RAI 4.3.1.8-r2(as renumbered).
:Office Building 148 Martine Avenue, 6th.Floor White Plains, NY 10601 jdp3@westchestergov.com Daniel E. O'Neill,, Mayor James Seirmarco, M.S.Village of Buchanan Municipal Building 236 Tate Avenue Buchanan, NY 10511-1298 vob@bestweb.net Daniel Riesel, Esq.Thomas F. Wood, Esq.Jessica Steinberg, J.D.Sive, Paget &Riesel, P.C.460 Park Avenue New York, NY 10022 driesel@sprlaw.com jsteinberg@sprlaw.com Michael J. Delaney, Esq.Vice President
Non-EQ Bolted Cable Connection AMP D-RAI 3.0.3.3.6-1 With regard to Indian Point Aging Management Program (AMP),B.1.22, "Non-EQ Bolted'Cable Connection Program," thellicense renewal applicationstates that inspection methods may include thermography, contact resistance testing, or otherappropriate methods including visual, based on plant configuration and industry guidance. In Generic Aging Lessons Learned (GALL)
-Energy Department New York City Economic Development Corporation (NYCEDC)110 William Street New York, NY 10038 mdelaney@nycedc.com (Arthur J. Kremer, Chairman.*New York~Afifoidable:
AMP XI.E6, the staff recommends thermography,, contact resistance testing, or other appropriate methods based on plant configuration and industry guidance for detecting loss of preload or bolt loosening. In the case where visual inspection will- be the only method used, provide a technical basis of how this will be sufficient to detect loss of preloador loosening of bolted connections.
Relabl'eElectric'ity Allianric'e
Discussion: The applicant stated that this question is similar to an audit question that has been answered and subsequently discussed during two telephone conferences. This issue is being reviewed by the Division of Engineering and, therefore, is withdrawn at this time. However, when the staff has: reached a determination, a formal RAI may be issued at such time.
,(AREA)347 Fifth.Avenue, Suite 508 New York, NY 10016ýkremer@area-alliance.org ajkremef@rnfpc.com Manna Jo Greene, Director Hudson River Sloop Clearwater, Inc.'112 Little Market'.St.
Boraflex AMP D-RAi 3.0.3.2.3-1 Indian Point 2 Updated Final Safety Analysis Report, Revision 20, dated 2006, Section 14.2.1 on page 55 of 218, states in-part that:
Poughkeepsie; NY.-.12601 Mannajo@clearwater.org Stephen Filler, Esq.Board Member'Hudson River. Sloop Clearwater, Inc.-Suite 222 303 South Broadway Tarrytown, NY. 10591 sfiller@nylawline.com Susan H. Shapiro,.
          "Northeast Technology Corporation report NET-173-01 and NET-171-02 are based on conservative projections of amount of boraflex absorber panel degradation assumed in each sub-region. These projections are valid through the end of the year 2006."
Esq.Weschester Citizen's Awareness Network (WestCan), Citizens Awareness Network (CAN),etc.
Please confirm that the Boraflex neutron absorber panels in the Indian Point Unit 2 spent fuel pool have been re-evaluated for service through the end of the current licensing period. Also, please discuss the plans for updating the Boraflex analysis during the period of extended operation.
21 Perlman Drive Spring Valley, NY 10977 mbs@ourrocklandoffice.com, NancyBurton 147 Cross Highway Redding Ridge, CT 06876 NancyBurtonCT@aol.com-Richard L-.Brodsky,gEsq.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Assehib yman, SuiteW205 5 West Main Street Elmsford,,NY
 
.10523 ,brtdskr@assembly.state*.ny.us-richardbrodsky@msnicom Sarah L. Wagner, Esq.Room 422 Legislative Office:Building
                                  .,UNITED ,STATES OEAMERICAK NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY LICENSINGBOARD
* Albany, NY.'12248 sarahwagneresq@gmail.com John LeKay FUSE USA 35.1 DyckmanStreet Peekskill' ,NY 10566 fuse usa@yahoo.com Diane Curran, Esq.Harmon, Curran, Spielberg
                      ---------------  --------- x In re:
& Eisenberg, LLP Suite 600 1726 M Street, NW Washington, DC 20036 dcurran@harmoncurran.com Phillip Musegaas, Esq.Victor Tafur, Esq.Riverkeeper, Inc.828 South Broadway Tarrytown, NY 10591 phillip@riverkeeper.org vtafur@riverkeeper.org I declare under penalty of perjury that the foregoing is true and correct.Executed on: this 22nd day of May 2008 Albany, New York/I Teresa Fountain-3-}}
Docket Nos. 50-247-LR and 50-286-LR LicenseRenewal Application Submitted by
                                                          -ASLBPNo. 07-858-03-LR-BD01 Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, and                  DPR-26, DPR-64 Entergy Nuclear Operations, Inc.
                                                  -x CERTIFICATE OF SERVICE Pursuant to 28 U.S.C. § 1746 Teresa Fountain hereby declares:
I am over 18 years old and am an employee in the New York State Office of the Attorney General.
I hereby certify that on May 22, 2008, copies of "The State of New York's Supplemental Citation In Support of Contention 26A" were served upon the following persons via electronic mail and by deposit in the U.S. Postal Service with first class postage:
LawrenceG. McDade, Chair                              Kaye D. Lathrop Administrative Judge                                  Administrative Judge Atomic Safety and Licensing Board Panel              Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission                    U.S. Nuclear Regulatory Commission Mailstop 3 F23                                       190 Cedar Lane E.
Two White Flint North                                 Ridgway, CO 81432 11545 Rockville Pike                                 Kaye.Lathrop@nrc.gov Rockville, MD 20852-2738 Lawrence.McDade@nrc.gov                               Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Richard E. Wardwell                                   Mailstop 3 F23 Administrative Judge                                 Two White Flint North Atomic Safety and Licensing Board Panel               11545 Rockville Pike U.S. Nuclear Regulatory Commission                   Rockville, MD 20852-2738 Mailstop 3 F23 Two White Flint North                                 Zachary S. Kahn, Esq.
11545 Rockville Pike                                 Law Clerk Rockville, MD 20852-2738                             Atomic Safety and Licensing Board Panel Richard.Wardwell@nrc.gov                             U.S. Nuclear Regulatory Commission Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Zachary.Kahn@nrc.gov
 
Marcia Carpentier                                Elise N. Zoli, E~sq.
Law'Cleik-                                        zGoodvvnPr ,octer,LL IP Atomic Safety andLicensing Board Panel           Exchange Place U.S. Nuclear.Regulatory Commission                 53.State Street Mailstop 3 E2B                                    Boston, MA 02109 Two White Flint North                             ezoli@goodwinprocter~com 11545 Rockville Pike.
Rockville, MD 20852-2738                           William C. Dennis, Esq.
Marcia.Carpentier@nrc.gov                         Assistant General Counsel
                                                  *EntergyNuclear Operations, Inc.
Office of Commission Appellate. Adjudication,      440 Hamilton7Avenue U.S. NNuclear Regulatory Commission               White'Plains, NY 10601 Mailstop 16 G4                                    wdennis@entergy.com One White Flint North 11555 Rockville Pike                             Robert D.. Snook!,Esq.
Rockville, MD 20852-2738                           Assistant Attorney General
.ocaamail@nrc.gov                                 Office of the Attorney General State of Connecticut Office of the Secretary                            55'Elm Street Attn: Rulemaking and Adjudications Staff          P.O. Box 120 U.S. Nuclear Regulatory Commission                 Hartford, CT 06141-0120 Mailstop 3F23                                      robert.snook@po.state.ct.us Two White'Flint North 11545 Rockville Pike                             Justin D. Pruyne, Esq.
Rockville, MD 20852-2738                           Assistant County Attorney hearingdocket@nrc.gov                             Office of the Westchester County Attorney Michaelian :Office Building Sherwin E. .Turk, Esq.                             148 Martine Avenue, 6th.Floor David E. Roth, Esq.                               White Plains, NY 10601 Marcia J. Simon, Esq.                             jdp3@westchestergov.com Beth N. Mizuno, Esq.
Jessica A. Bielecki, Esq.                         Daniel E. O'Neill,, Mayor Officeof the General Counsel                     James Seirmarco, M.S.
U.S. Nuclear Regulatory Commission               Village of Buchanan Mailstop 15 D21                                   Municipal Building One White Flint North                             236 Tate Avenue 11555 Rockville Pike                             Buchanan, NY 10511-1298
'Rockville, MD 20852-2738                           vob@bestweb.net set@nrc.gov der@nrc.gov                                       Daniel Riesel, Esq.
jessica.bielecki@nrc.gov                           Thomas F. Wood, Esq.
bnml@nrc.gov                                       Jessica Steinberg, J.D.
marcia.simon@nrc.gov                               Sive, Paget &Riesel, P.C.
460 Park Avenue Kathryn M. Sutton, Esq.                           New York, NY 10022 Paul M. Bessette, Esq.                             driesel@sprlaw.com Martin J. O'Neill, Esq.'                         jsteinberg@sprlaw.com Mauri T. Lemoncelli, Esq.
Morgan, Lewis & Bockius LLP                       Michael J. Delaney, Esq.
1111 Pennsylvania Avenue, NW                     Vice President - Energy Department Washington, DC 20004                             New York City Economic Development Corporation ksutton@morganlewis.com                           (NYCEDC) pbessette@morganlewis.com                         110 William Street martin.o'neill@morganlewis.com                   New York, NY 10038 mlemoncelli@morganlewis.com                       mdelaney@nycedc.com cadams@morganlewis.com
 
(
Arthur J. Kremer, Chairman.                              -Richard L-.Brodsky,gEsq.
*NewYork~Afifoidable: Relabl'eElectric'ity Allianric'e      Assehib yman,
,(AREA)                                                    SuiteW205 347 Fifth.Avenue, Suite 508                                5 West Main Street New York, NY 10016                                        Elmsford,,NY .10523
ýkremer@area-alliance.org                                ,brtdskr@assembly.state*.ny.us ajkremef@rnfpc.com                                        -richardbrodsky@msnicom Manna Jo Greene, Director                                  Sarah L. Wagner, Esq.
Hudson River Sloop Clearwater, Inc.                        Room 422
  '112 Little Market'.St.                                  Legislative Office:Building Poughkeepsie; NY.-.12601                                  *Albany, NY.'12248 Mannajo@clearwater.org                                    sarahwagneresq@gmail.com Stephen Filler, Esq.                                     John LeKay Board Member'                                            FUSE USA Hudson River. Sloop Clearwater, Inc.                      35.1 DyckmanStreet
-Suite 222                                                Peekskill',NY 10566 303 South Broadway                                        fuse usa@yahoo.com Tarrytown, NY. 10591 sfiller@nylawline.com                                   Diane Curran, Esq.
Harmon, Curran, Spielberg & Eisenberg, LLP Susan H. Shapiro,. Esq.                                   Suite 600 Weschester Citizen's Awareness Network                    1726 M Street, NW (WestCan), Citizens Awareness Network (CAN),etc.         Washington, DC 20036 21 Perlman Drive                                          dcurran@harmoncurran.com Spring Valley, NY 10977 mbs@ourrocklandoffice.com,                                Phillip Musegaas, Esq.
Victor Tafur, Esq.
NancyBurton                                              Riverkeeper, Inc.
147 Cross Highway                                        828 South Broadway Redding Ridge, CT 06876                                  Tarrytown, NY 10591 NancyBurtonCT@aol.com                                     phillip@riverkeeper.org vtafur@riverkeeper.org I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
this 22nd day of May 2008
                                                                      /
I Albany, New York Teresa Fountain
                                                      }}

Revision as of 16:12, 14 November 2019

2008/05/22-New York State'S Supplemental Citation in Support of Admission of Contention 26A
ML081500530
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 05/22/2008
From: Jeremy Dean, Sipos J
State of NY, Office of the Attorney General
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, RAS E-105
Download: ML081500530 (13)


Text

DOCKETED USNRC UNiTED STATES May 22, 2008 (2:42pm)

NUCLEAR REGULATORY COMMISSION OFFICE OF. SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF ATOMIC: SAFETY, LICENSING BOARD

-X In re: Docket Nos. 50-247-LR and 50-286-LR License Renewal Application Submitted by ASLBP No.07-858.03.LR-BD01 Entergy Nuclear Indian Point 2, LLC, DPR-26, DPR-64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc. May 22,2008

-x NEW YORK STATE'S SUPPLEMENTAL CITATION IN SUPPORT OF ADMISSION OF CONTENTION-26A On May 14, 2008 - two weeks after the State of New York submitted its Reply to Entergy's Answer and NRC Staff's Response to New York's Supplemental Contention No.26-A (Metal Fatigue) - the NRC Staff posted on ADAMS a May 8, 2008 Summary of an April 3, 2008 telephone conference between Entergy and Staff regarding, inter alia, how much information NRC Staff would require Entergy to produce as part of its License Renewal Application.' The Summary is contained in Attachment 1 to this Supplement, and is also available at ML081190059. The May 8 Summary reveals that Entergy, with the acquiescence of Staff, does not intend to allow the details of how it will address metal fatigue issues to be made a part of this license renewal proceeding. Enclosure 1 to May 8, 2008 Summary of April 3, 2008 Telephone Conference, at pages 1 to 3.

This newly-disclosed information supplements the statements made by New York State in its May 1, 2008 Reply at the end of the first full paragraph on page 10.

IThe New York State Office of the Attorney General received a copy of the May 8, 2008 Summary via U.S.

Mail on May 19, 2008.

TE P, A1FE Z)3 9 D S --ý) --)

Respectfiilly submitted, May 22, 2008 Joan Leary Matthews Senior Attomey!,forSpecial Projects Janice A.: Dean NewYork State Department Assistant Attorneys General of Environmental Conservation Office of the Attorney General 625 Broadway, 14th floor forthe State ofNew York Albany;, New York 12233-5500 The Capitol (518) 402-9190 Albany, New York 12224 jhlnatthe@gw.dec.state.ny.us (518) 402-2251 john.sipos@oag.state.ny.us John Louis Parker, Esq.

Regional Attorney New York State Department of Environmental Conservation 21 South Putt Comers Rd New Paltz, NY 12561-1620

ATTACHMENT 1 NRC May 8,2008-Summary of an April 3, 2008 telephone conference between Entergy and NRC Staff also available at ML081190059

UNITED STATES NUCLFAR REGULATORY.COMMISSION MA,-W, May. 8, 2008 LICENSEE: Ent'Ny Nulear Operations. Inc.

FAC(LITY: Indian Point Nuclear Generating :Unit Nos. 2 and S3 SUBJ.ECT:

SUMMARY

OF TELEPHONE CONFERENCE.CALLLHELD ON APRIL *3,2008,,

BETWEEN THE U.S. NUCLEAR REGULATORY.COMI*MI.R1ON AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS, 2 AND 3, LICENSERENEWAL APPLI.CA.TIO0N-METAL FATIGUE, BOLTED CONNECTIONS, AND BORAFLEXý The U.-S. Nuclear Regulatory Commission (NRC or the staff) and. repre'sentatiVe6s" of Eintergy Nuclear Operatio'ns,- Inc., held a telephone conference call on April 3, 2008, to discuss and clriy the staff's draft request for additional Information (0;i ocenn h Ida on Nuclear.Generating Unit Nos. 2 and 3, license renewal application. The telepihoeq"c'onfrec calwsuseful rin clarifyn thq intent of the staff's D-fRAl provides.:a isti ngof the participants and Enclosuire 2 conttalins-a listing of the D-RAI i.1em-s-disct s, wit th; appiat inluding a befdescrpin on th Pttsofteies Theappicnthad anooportunityito-commentntis s-ummay Kimberly Gre n, SafeyPojc Mange Projects Branch 2 Division of Liceinse Reeal:

Office of'- ru'lear Reao Regu laton Do6kt Nos'. 50-247 and 50'28 Enclo~sures-1I, List of Participants 2.Summ~ary of Discussion..

'cwencls.See next page

Indianý Point Nuclear Generating Units. 2.and 3 cc:

Senior Vice President Mr. John P. Spath Entergy, Nuclear Operations, Inc. New.York StateEnergy, Research.and P.'O.Box 31995 .Development Authority Jackson,.MS 39286-1995 17 'Columbia-Circle Albany, NY 12203-6399 Vice President Oversight Entergy Nuclear Operations, Inc. Mr. PaulEddy P.O.Box 31995 New. York State Department Jackson,. MS 39286A1995 of Public Service 3 Empire StatePlaza Senior Manager, Nuclear Safety.& Albany, NY 12223-1350 Licensing Entergy Nuclear Operations, Inc. Regional Administrator, Region I P'O. Box 31995 U.S. Nuclear Regulatory Commission Jackson, MS 39286-1995 475 Allendale Road King of Prussia, PA 19406 Senior Vice President and COO Entergy Nuclear Operations, Inc. Senior Resident Inspector's Office 440 Hamilton Avenue Indian Point 2 White Plains, NY 10601 U.S. Nuclear Regulatory Commission P.O. Box 59 Assistant General Counsel .Buchanan, NY 10511 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue Senior-Resident Inspector's Office White, Plains, NY 10601 Indian Point-3 U.S. Nuclear Regulatory Commission Manager, Ucensing P.O. Box 59 Entergy Nuclear Operations, Inc. Buchanan, NY 10511 Indian Point Energy Center 450 Broadway, GSB Mr. Charles Donaldson, Esquire P.O. Box 249 Assistant Attorney General Buchanan, NY 10511-0249 New York Department of Law 120 Broadway Mr. Paul D. Tonko New York, NY 10271 President and CEO New York State Energy Research and Mr. Raymond L. Albanese Development Authority Four County Coordinator 17 Columbia Circle 200 Bradhurst Avenue Albany, NY 12203-6399 Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511

Indian Point Nuclear Generating Units 2and 3 cc:

Mr. William DiProfio John Sipos PWR SRC-Consultant Assistant-Attorney-General 48 Bear. Hill Road NewYork State. Department of Law Newton,.NH 03858 Environmental Protection Bureau The Capitol Mr. Garry Randolph Albany, NY 12224 PWR SRC Consultant 1,750, Ben Franklin Drive, 7E Robert Snook Sarasota,ý FL 34236 AssistantAttorney General Office of the Attorney General Mr. William T. Russell State of Connecticut PWR SRC Consultant 55 Elm Street 400 Plantation Lane P.O; Box120 Stevensville, MD 21666-3232 Hartford, CT 06141-0120 Mr. Jim Riccio Ms. Kathryn M. Sutton, Esq.

Greenpeace Morgan, Lewis & Bockius, LLP 702 H Street, NW 1111 Pennsylvania Avenue, NW Suite 300 Washington, DC 20004 Washington, DC 20001 Mr. Paul M. Bessette, Esq.

Mr. Phillip Musegaas Morgan, Lewis & Bockius, LLP Riverkeeper, Inc. 1111 Pennsylvania Avenue, NW 828 South Broadway Washington, DC 20004 Tarrytown, NY 10591 Mr. Martin J. O'Neill, Esq.

Mr. Mark Jacobs Morgan, Lewis & Bockius, LLP IPSEC 1111 Pennsylvania Avenue, NW 46 Highland Drive Washington, DC 20004 Garrison, NY 10524 The Honorable Nita Lowey Mr. R. M.Waters 222 Mamaroneck Avenue, Suite 310 Technical Specialist Licensing White Plains, NY 10605 450 Broadway P.O. Box 0249 Joan Leary Matthews Buchanan, NY 10511-0249 Senior Counsel for Special Projects Office of General Counsel Mr. Sherwood Martinelli NYS Department of Environmental 351 Dyckman - Conservation Peekskill, NY 10566 625 Broadway Albany, NY 12233-5500 Ms. Susan Shapiro, Esq.

21 Perlman Drive Spring Valley, NY 10977

TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS APRIL 3,2008 PARTICIPANTS AFFILIATIONS Kim Green U.S. Nuclear Regulatory Commission (NRC)

On Yee NRC Peter Wen NRC Jim Davis NRC Bo Pham NRC Jim Medhoff NRC Mike Stroud Entergy Nuclear Operations, Inc. (Entergy)

Garry Young Entergy Alan Cox Entergy Ted Ivy Entergy Don Fronabarger Entergy Charlie Caputo Entergy John 'Curry Entergy Nelson Azevedo Entergy Charlie Jackson Entergy ENCLOSURE I

DRAFT REQUEST FORADDITIONAL INFORMATION INDIAN POINT NUCLEAR GENERAT:ING UNIT NOS. 2AND 3 RENEWAL :APPLICATION LICENSEt7METAL; FATIGUE April 3, 2008 The U.S.:Nuclear Regulatory Commission (NRC or,the staff)l and representatives of Entergy Nuclear Operations, Inc., held a telephone conferencecall on April 3, 2008, to discuss and clarifylthe following draft requests for additional information (D-RA.s) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 license renewal application (LRA).

D-RAI 4.3.1.8-1 License, Renewal Application Section 4.3.1 states wCurrent design basis fatigue evaluations calculate cumulative usage factors (CUFs) forcomponents or-sub-components based on design transient cycles." For CU Fvalues listed in LRA Tables 4.3-13 and 4.3-14, please provide theT methodology used with sufficient results of the fatigue analysis such that the staff can make a determination based onithe guidance described inStandard Review Plan-License Renewal (SRP-LR) (NUREG-1 800). Specifically, please describe the details of how environmentally assisted fatigue (EAF) is factored into the calculation of the CUF using Fe values.

Discussion: The applicant was uncertain as to whether the staff was requesting that they provide the evaluations or a description of evaluations. 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.

License renewal application (LRA) Section 4.3.1 states "Current design basis fatigue evaluations calculate cumulative usage factors (CUFs) for components or sub-components based on design transient cycles." For CUF values listed in LRA Tables 4.3-13 and 4.3-14, please describe the details of how various environmental effects are factored into the calculation of the CUF using F,,

6 values.

D.RAI 4.3.1.8-2 From the review of EAF analysis of other plants, it was found that the transfer function methodology used in the EAF analysis may not provide valid results, as it is dependent on the inputs. To assist the staff in its review, please provide the EAF analysis for all the NUREG/

CR-6260 locations (components) at Indian Point unless it can be demonstrated that the CUF value is within the ASME Code limit of 1.0.by using the original 40-year analysis value adjusted for 60 years and multiplied by Fen, which is consistent with SRP-LR and ASME Code. This analysis should be completed by using NRC-approved fatigue software and the ASME Code,Section III, Subsection NB-3200 methodology (which defines the use of six stress components to determine the stress state and thereby calculates the principal stresses and stress, intensities). Justify the analysis method, the load (stress) combination, and the results of the ASME Code analysis if 2-D axis-symmetric modeling is used. In addition, the analysis should apply ASME code rules such as elastic-plastic correction factor, K, and stress intensities correction factor for modulus of elasticity. This analysis should be performed without the use of the transfer function method.

ENCLOSURE 2

Discussion: The applicant-wanted-clarification on the staff's request. The applicant pointed out thatthe requestis a new staff position and that forprevious plants, the staff hasnot requested the-,analyses.-to.be.provided and, has accepted a:commitmenttoperform 4the analyses two years prior to entering the period of extended operation as Part -6f the6 Fatig ue Monitorng Program in accordance with. OCFR 54.21 (c)(1)(iii)..- Subsequent to the telePhone conference, the staff determined that no additional information is needed atthis time. Therefore, a formal RAI will not be issued at this time.

D-RAI 4.3.1.8ý3 SRP-LR Section 4.3.2.1.1.3 provides the basis for the staff acceptance of an aging management program to addessenvironmental-fatigue. lt states, -"[T]hestaff has evaluated-a program for monitoring and tracking the number of critical thermal and, pressure transients for the selected reactor coolant. system:components, Thestaff has determinedthatthis program is an acceptable aging managementeprogram to address metal fatigue of:the reactor coolant system components according to 10 CFR 54.21 (c)(1)(iii).": The staff is unable to determine if the Fatigue Monitoring Program-of lP2 andl1P3 contain-sufficient details to satisfy:this criterion, based on-the NAhitems listed i!n, LRA Tables 4.3-13 and 4.3-14. Please provide adequate details of the Fatigue Monitoring Program,' specifically the fatigue analysis used in determining the CUF values for the NA locations and how IPEC plans to proceed in monitoring the locations of Tables 4.3-13 and 4.3-14 during the period of extended operation.

Discussion: The applicant wanted clarification on what the staff is requesting. 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 RAl, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 4.3.2.1.1.3 provides the basisfor the staff acceptance

-of an aging management program to address environmental fatigue. It states, '[t]he staff has evaluated a program for monitoring and tracking the number of critical thermal and pressure transients for the selected reactor coolant system components.

The staff has determined that this program is an acceptable aging managembnt program to address metal fatigue of the reactor coolant system components according to 10 CFR 54.21 (c)(1 )(iii)." The staff is unable to determine if the Fatigue Monitoring Program for Indian Point 2 and Indian Point 3 contains sufficient details to satisfy this criterion. Please provide adequate details of the Fatigue Monitoring Program such that the staff can make a determination based on the criterion set forth in SRP-LR Section 4.3.2.1.1.3. Also, please explain in detail the corrective actions and the frequency that such actions will be taken so that theacceptance criteria will not be exceeded in the period of extended operation. (This RAI will be renumbered as RAI 4.3.1.8-2.)

D-RAI 4.3.1.8-4 Section B. 1.12 of the LRA amendment, dated January 22, 2008, states, "Ifongoing monitoring indicates the potential for a condition outside that analyzed above, IPEC may perform further reanalysis of the identified configuration using established configuration management processes as described above." Please explain in detail what is meant by the phrase musing established configuration management processes." Also, please explain in detail the corrective actions and the frequency that such actions will be taken so the acceptance criteria will not be exceeded in the period of extended operation.

Discussion: The applicant stated that it was unclear-aboutlhe staff's request regarding

,configuration management processes." In a subsequent call, the applicant :explained that the

'configuration managementprocesses referred to aret those govemed :byits 10 CFR Part 50, APppendix B,,QQuality u ."Assuranceprogram, and include design in put verification and independent reviews which ensure that valid assumptions, transients, cycles, externaoadingsanalysis methods, and environmental fatigue life correction factors will behusedý inthe fatigue analyses.

Therefore, this portion of question is withdrawn and will not be sent asa formal RAI. The portion of.,the request that deals with corrective actions willhbe added to RAI 4.3.1.8-r2(as renumbered).

Non-EQ Bolted Cable Connection AMP D-RAI 3.0.3.3.6-1 With regard to Indian Point Aging Management Program (AMP),B.1.22, "Non-EQ Bolted'Cable Connection Program," thellicense renewal applicationstates that inspection methods may include thermography, contact resistance testing, or otherappropriate methods including visual, based on plant configuration and industry guidance. In Generic Aging Lessons Learned (GALL)

AMP XI.E6, the staff recommends thermography,, contact resistance testing, or other appropriate methods based on plant configuration and industry guidance for detecting loss of preload or bolt loosening. In the case where visual inspection will- be the only method used, provide a technical basis of how this will be sufficient to detect loss of preloador loosening of bolted connections.

Discussion: The applicant stated that this question is similar to an audit question that has been answered and subsequently discussed during two telephone conferences. This issue is being reviewed by the Division of Engineering and, therefore, is withdrawn at this time. However, when the staff has: reached a determination, a formal RAI may be issued at such time.

Boraflex AMP D-RAi 3.0.3.2.3-1 Indian Point 2 Updated Final Safety Analysis Report, Revision 20, dated 2006, Section 14.2.1 on page 55 of 218, states in-part that:

"Northeast Technology Corporation report NET-173-01 and NET-171-02 are based on conservative projections of amount of boraflex absorber panel degradation assumed in each sub-region. These projections are valid through the end of the year 2006."

Please confirm that the Boraflex neutron absorber panels in the Indian Point Unit 2 spent fuel pool have been re-evaluated for service through the end of the current licensing period. Also, please discuss the plans for updating the Boraflex analysis during the period of extended operation.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

.,UNITED ,STATES OEAMERICAK NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY LICENSINGBOARD


--------- x In re:

Docket Nos. 50-247-LR and 50-286-LR LicenseRenewal Application Submitted by

-ASLBPNo. 07-858-03-LR-BD01 Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, and DPR-26, DPR-64 Entergy Nuclear Operations, Inc.

-x CERTIFICATE OF SERVICE Pursuant to 28 U.S.C. § 1746 Teresa Fountain hereby declares:

I am over 18 years old and am an employee in the New York State Office of the Attorney General.

I hereby certify that on May 22, 2008, copies of "The State of New York's Supplemental Citation In Support of Contention 26A" were served upon the following persons via electronic mail and by deposit in the U.S. Postal Service with first class postage:

LawrenceG. McDade, Chair Kaye D. Lathrop Administrative Judge Administrative Judge Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Mailstop 3 F23 190 Cedar Lane E.

Two White Flint North Ridgway, CO 81432 11545 Rockville Pike Kaye.Lathrop@nrc.gov Rockville, MD 20852-2738 Lawrence.McDade@nrc.gov Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Richard E. Wardwell Mailstop 3 F23 Administrative Judge Two White Flint North Atomic Safety and Licensing Board Panel 11545 Rockville Pike U.S. Nuclear Regulatory Commission Rockville, MD 20852-2738 Mailstop 3 F23 Two White Flint North Zachary S. Kahn, Esq.

11545 Rockville Pike Law Clerk Rockville, MD 20852-2738 Atomic Safety and Licensing Board Panel Richard.Wardwell@nrc.gov U.S. Nuclear Regulatory Commission Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Zachary.Kahn@nrc.gov

Marcia Carpentier Elise N. Zoli, E~sq.

Law'Cleik- zGoodvvnPr ,octer,LL IP Atomic Safety andLicensing Board Panel Exchange Place U.S. Nuclear.Regulatory Commission 53.State Street Mailstop 3 E2B Boston, MA 02109 Two White Flint North ezoli@goodwinprocter~com 11545 Rockville Pike.

Rockville, MD 20852-2738 William C. Dennis, Esq.

Marcia.Carpentier@nrc.gov Assistant General Counsel

  • EntergyNuclear Operations, Inc.

Office of Commission Appellate. Adjudication, 440 Hamilton7Avenue U.S. NNuclear Regulatory Commission White'Plains, NY 10601 Mailstop 16 G4 wdennis@entergy.com One White Flint North 11555 Rockville Pike Robert D.. Snook!,Esq.

Rockville, MD 20852-2738 Assistant Attorney General

.ocaamail@nrc.gov Office of the Attorney General State of Connecticut Office of the Secretary 55'Elm Street Attn: Rulemaking and Adjudications Staff P.O. Box 120 U.S. Nuclear Regulatory Commission Hartford, CT 06141-0120 Mailstop 3F23 robert.snook@po.state.ct.us Two White'Flint North 11545 Rockville Pike Justin D. Pruyne, Esq.

Rockville, MD 20852-2738 Assistant County Attorney hearingdocket@nrc.gov Office of the Westchester County Attorney Michaelian :Office Building Sherwin E. .Turk, Esq. 148 Martine Avenue, 6th.Floor David E. Roth, Esq. White Plains, NY 10601 Marcia J. Simon, Esq. jdp3@westchestergov.com Beth N. Mizuno, Esq.

Jessica A. Bielecki, Esq. Daniel E. O'Neill,, Mayor Officeof the General Counsel James Seirmarco, M.S.

U.S. Nuclear Regulatory Commission Village of Buchanan Mailstop 15 D21 Municipal Building One White Flint North 236 Tate Avenue 11555 Rockville Pike Buchanan, NY 10511-1298

'Rockville, MD 20852-2738 vob@bestweb.net set@nrc.gov der@nrc.gov Daniel Riesel, Esq.

jessica.bielecki@nrc.gov Thomas F. Wood, Esq.

bnml@nrc.gov Jessica Steinberg, J.D.

marcia.simon@nrc.gov Sive, Paget &Riesel, P.C.

460 Park Avenue Kathryn M. Sutton, Esq. New York, NY 10022 Paul M. Bessette, Esq. driesel@sprlaw.com Martin J. O'Neill, Esq.' jsteinberg@sprlaw.com Mauri T. Lemoncelli, Esq.

Morgan, Lewis & Bockius LLP Michael J. Delaney, Esq.

1111 Pennsylvania Avenue, NW Vice President - Energy Department Washington, DC 20004 New York City Economic Development Corporation ksutton@morganlewis.com (NYCEDC) pbessette@morganlewis.com 110 William Street martin.o'neill@morganlewis.com New York, NY 10038 mlemoncelli@morganlewis.com mdelaney@nycedc.com cadams@morganlewis.com

(

Arthur J. Kremer, Chairman. -Richard L-.Brodsky,gEsq.

  • NewYork~Afifoidable: Relabl'eElectric'ity Allianric'e Assehib yman,

,(AREA) SuiteW205 347 Fifth.Avenue, Suite 508 5 West Main Street New York, NY 10016 Elmsford,,NY .10523

ýkremer@area-alliance.org ,brtdskr@assembly.state*.ny.us ajkremef@rnfpc.com -richardbrodsky@msnicom Manna Jo Greene, Director Sarah L. Wagner, Esq.

Hudson River Sloop Clearwater, Inc. Room 422

'112 Little Market'.St. Legislative Office:Building Poughkeepsie; NY.-.12601 *Albany, NY.'12248 Mannajo@clearwater.org sarahwagneresq@gmail.com Stephen Filler, Esq. John LeKay Board Member' FUSE USA Hudson River. Sloop Clearwater, Inc. 35.1 DyckmanStreet

-Suite 222 Peekskill',NY 10566 303 South Broadway fuse usa@yahoo.com Tarrytown, NY. 10591 sfiller@nylawline.com Diane Curran, Esq.

Harmon, Curran, Spielberg & Eisenberg, LLP Susan H. Shapiro,. Esq. Suite 600 Weschester Citizen's Awareness Network 1726 M Street, NW (WestCan), Citizens Awareness Network (CAN),etc. Washington, DC 20036 21 Perlman Drive dcurran@harmoncurran.com Spring Valley, NY 10977 mbs@ourrocklandoffice.com, Phillip Musegaas, Esq.

Victor Tafur, Esq.

NancyBurton Riverkeeper, Inc.

147 Cross Highway 828 South Broadway Redding Ridge, CT 06876 Tarrytown, NY 10591 NancyBurtonCT@aol.com phillip@riverkeeper.org vtafur@riverkeeper.org I declare under penalty of perjury that the foregoing is true and correct.

Executed on:

this 22nd day of May 2008

/

I Albany, New York Teresa Fountain