Letter Sequence RAI |
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Results
Other: ML071900365, ML11109A067, ML13043A527, ML13067A315, ML13077A284, ML14217A206, ML15007A430, ML15055A004, ML15055A014, ML15268A128, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application, NL-10-054, Correction to License Renewal Application, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A, NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A
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MONTHYEARNL-07-056, Supplement to License Renewal Application2007-05-0303 May 2007 Supplement to License Renewal Application Project stage: Supplement NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application2007-06-21021 June 2007 Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application Project stage: Other ML0719003652007-07-25025 July 2007 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Application from ENO, Inc. for Renewal of the Operating License for the Indian Point Nuclear Generating Unit Project stage: Other ML0727804392007-10-16016 October 2007 Summary of Telephone Conference Call with Entergy Nuclear Operations, Inc., Requests for Additional Information Project stage: RAI NL-10-054, Correction to License Renewal Application2010-05-27027 May 2010 Correction to License Renewal Application Project stage: Other ML11109A0672011-04-19019 April 2011 2011/04/19 Indian Point Lr Hearing - FW: OAR - Safety PM Change for the License Renewal Project for Indian Point...(Tac Nos. MD5407 & MD5408) Project stage: Other NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A2012-02-17017 February 2012 License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A Project stage: Other ML12223A3882012-09-10010 September 2012 RAI for the Review of the Indian Pont Nuclear Generating Unit Nos. 2 and 3, LRA Set 2012-02 Project stage: RAI ML12223A3672012-09-12012 September 2012 08/08/2012 Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning RAI Set 2012-02, Reactor Vessel Internals Program Pertaining to the Indian Point, Units 2 & 3, License Renewal Application Project stage: RAI ML12278A0772012-10-16016 October 2012 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application, Set 2012-03 (TAC Nos. MD5407 and MD5408) Project stage: RAI NL-12-140, Reply to Request for Additional Information Regarding the License Renewal Application2012-10-17017 October 2012 Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI NL-12-166, Reply to Request for Additional Information Regarding the License Renewal Application2012-11-20020 November 2012 Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI ML15334A2562013-02-0606 February 2013 Official Exhibit - ENT000660-00-BD01 - Letter from J. Daly, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 LRA, Set 2013-01 (TAC Nos. MD5407 and Project stage: Request ML15335A2722013-02-0606 February 2013 Official Exhibit - NRC000187-00-BD01 - Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and Project stage: RAI ML13015A1752013-02-0606 February 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA, Set 2013-01 Project stage: RAI ML15222A8962013-02-0606 February 2013 ENT000660 - Letter from J. Daly, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2013-01 (TAC Nos. MD54 Project stage: Request ML15223A2632013-02-0606 February 2013 NRC000187 - Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) Feb. 6, Project stage: RAI ML13043A5272013-02-26026 February 2013 PM Change Letter - February 2013 Project stage: Other ML13067A3152013-03-0808 March 2013 Correction to Project Manager Change for the License Renewal of Indian Point, Units 2 and 3 (TAC Nos. MD5407 & MD5408) Project stage: Other ML13077A2842013-03-0808 March 2013 Correction PM Letter Indian Point Project stage: Other NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application2013-05-0707 May 2013 Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI ML13162A6062013-06-12012 June 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-02 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML13186A1692013-07-17017 July 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013 03 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML15222A8982013-07-26026 July 2013 ENT000661 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2013-04 (TAC Nos. MD5 Project stage: Request ML15334A2572013-07-26026 July 2013 Official Exhibit - ENT000661-00-BD01 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 Lr Application, Set 2013-04 (TAC Nos Project stage: Request ML13204A1992013-07-26026 July 2013 RAI for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-04 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML13240A0762013-09-0303 September 2013 RAI Set 2013-5 follow-up RAI on CP Project stage: RAI ML13318A4502013-11-19019 November 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating, Units 2 and 3, License Renewal Application, Set 2013-06 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML14027A4152014-01-16016 January 2014 Enclosure 2 to NL-14-010, Attachment 2, Final Response to U.S. NRC RAI 6-A Items 1 and 2 on the Rvi Program and Rvi Inspection Plan Project stage: Request NL-14-010, Units, 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application2014-01-16016 January 2014 Units, 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A2014-01-28028 January 2014 Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A Project stage: Other ML14084A3872014-04-0101 April 2014 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2014-01 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML15334A2582014-04-0909 April 2014 Official Exhibit - ENT000662-00-BD01 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 LRA, Set 2014-02 (TAC Nos. MD5407 and Project stage: Request ML15222A9012014-04-0909 April 2014 ENT000662 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2014-02 (TAC Nos. MD5 Project stage: Request ML14094A1732014-04-0909 April 2014 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2014-02 Project stage: RAI NL-14-093, Reply to Request for Additional Information Regarding License Renewal Application2014-08-0505 August 2014 Reply to Request for Additional Information Regarding License Renewal Application Project stage: Response to RAI ML14217A2062014-08-14014 August 2014 Respect for Withholding Information from Public Disclosure Project stage: Other ML14206B1742014-08-14014 August 2014 Review of Draft Audit Report Regarding Indian Point Nuclear Generating Unit Nos 2 and 3, License Renewal Application Project stage: Draft Approval ML14259A1152014-09-0909 September 2014 Submittal of Westinghouse Review of Draft NRC Audit Report Regarding Indian Point Nuclear Generating Units Nos. 2 and 3 Project stage: Request ML14265A2262014-09-25025 September 2014 Request for Withholding Information from Public Disclosure Regarding the Aging Management Audit Report Associated with Indian Point, Units 2 and 3 License Renewal Application (TACs MD5407 and MD5408) Project stage: Withholding Request Acceptance ML15007A4302015-01-0909 January 2015 Project Manager Change for the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. MD5407 and MD5408) Project stage: Other ML15055A0042015-02-17017 February 2015 Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA Project stage: Other ML15055A0142015-02-18018 February 2015 Lr Hearing - Reissue of RAI 3.0.3-2 from Set 2014-01 for Review of Indian Point, Units 2 and 3, LRA Project stage: Other ML15055A0082015-02-18018 February 2015 Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA Project stage: RAI ML15055A0122015-02-18018 February 2015 Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA (Tac Nos. MD5407 and MD5408) Project stage: RAI NL-15-019, Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application2015-03-10010 March 2015 Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application Project stage: Response to RAI 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) Project stage: RAI ML15170A4562015-07-0707 July 2015 RAI for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-02 Project stage: RAI ML15190A2912015-07-22022 July 2015 070115, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review Project stage: RAI NL-15-092, Reply to 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)2015-08-18018 August 2015 Reply to 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) Project stage: Response to RAI 2013-07-17
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Category:Legal-Pre-Filed Exhibits
MONTHYEARML16081A3252016-03-21021 March 2016 NRCR12001 - NRC Staff Prefiled Hearing Exhibit List (Revised) ML16078A4172016-03-18018 March 2016 ENTR20726 - Entergy Track 2 Exhibit List ML16078A4122016-03-18018 March 2016 NRC000236 - Crack Growth Rate Comparison - Eason Pathania Model to MRP Model- Excel Spreadsheet ML16078A4132016-03-18018 March 2016 NRCR11001 - Exhibt List NRC Staff Prefiled Hearing Exhibit List (Revised) ML15321A0352015-11-17017 November 2015 NYS000582 - Diagram of Strength Vs Amplitude by Dr. Richard T. Lahey ML15315A0132015-11-11011 November 2015 ENTR00726 - Track 2 Hearing Exhibit List ML15309A1292015-11-0505 November 2015 ENT000726 - Entergy Track 2 Hearing Exhibit List ML15309A1712015-11-0505 November 2015 RIVR14001 - Riverkeeper Tailored Track 2 Exhibit List ML15309A2212015-11-0505 November 2015 NRCR10001 - NRC Staff Track 2 Exhibit List ML15309A1552015-11-0404 November 2015 NYSR25001 - NYS Revised Tailored Exhibits List Relevant to Track 2 Contentions ML15313A4602015-11-0404 November 2015 NYSR25001 - Corrected Page 24 to Exhibits List Relevant to Track 2 Contentions ML15307A1152015-11-0303 November 2015 NYSR24001 - State of Ny Revised Hearing Exhibits List ML15307A8112015-11-0303 November 2015 NRC000230 - Corrections to Prefiled Testimony NRC000168 and NRC000197 ML15302A4672015-10-29029 October 2015 ENTR16001 - Entergy Revised Exhibit List ML15252A4442015-09-0909 September 2015 NYS000563 - Pressurized Water Reactor (PWR) Systems, USNRC Technical Training Center, Reactor Concepts Manual, Pages 4-1 to 4-28 ML15252A4432015-09-0909 September 2015 NYS000566 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey ML15252A5042015-09-0909 September 2015 NYS000568 - Supplemental Reply Statement of Position of the State of New York in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15252A5062015-09-0909 September 2015 NYS000570 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15252A5092015-09-0909 September 2015 RIV000164 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001) ML15252A5112015-09-0909 September 2015 RIVR13001 - Riverkeeper Updated Exhibit List ML15252A5752015-09-0909 September 2015 NYS000573 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15252A5792015-09-0909 September 2015 NYS Updated Exhibit List ML15261A8302015-09-0404 September 2015 ENTR00615 - Entergy'S Statement of Position Re Contention NYS-25 (Embrittlement) - Redacted ML15222A9152015-08-10010 August 2015 ENT000648 - M. Mitchell, Chief, Vessels and Internals Integrity Branch, Response to Non-Concurrence Regarding Safety Evaluation for Topical Report MRP-227, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (Undated) ML15223A4512015-08-10010 August 2015 NRC000206 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014) ML15223A4542015-08-10010 August 2015 NRC000207 - Regulatory Information Conference Presentation Slides, Recent Materials Inspections of PWR Reactor Internals (Mar. 2015) ML15223A4502015-08-10010 August 2015 NRC000205 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 3 - Reactor (2014) ML15223A3932015-08-10010 August 2015 NRCR00104 - on Yee Statement of Professional Qualifications (Revised) ML15223A3912015-08-10010 August 2015 NRCR00105 - Ching Ng Statement of Professional Qualifications (Revised) ML15222A8212015-08-10010 August 2015 ENT000617 - Curriculum Vitae of Timothy J. Griesbach ML15223A6712015-08-10010 August 2015 NRCR00147- NRC Staff'S Revised Statement of Position on State of New York and Riverkeeper'S Joint Contention NYS-38/RK-TC5 (Revised) ML15223A6752015-08-10010 August 2015 NRC000227 - Gary Stevens Statement of Professional Qualifications ML15222A8222015-08-10010 August 2015 ENT000618 - Curriculum Vitae of Randy G. Lott ML15223A7022015-08-10010 August 2015 NRCR900001 - NRC Staff Pre-filed Hearing Exhibit List (Revised) ML15222A8252015-08-10010 August 2015 ENT000629 - Letter from C. Grimes, NRC, to D. Walters, NEI, License Renewal Issue No. 98-0030 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components (May 19, 2000) ML15222A8302015-08-10010 August 2015 ENT000634 - Entergy, IP2, FSAR Update, Revision 25 (2014) (Excerpts) ML15223A7792015-08-10010 August 2015 NRC000224 - IP3 FSAR Rev. 04 Chapter 16 ML15223A7812015-08-10010 August 2015 NRC000226 - Jeffrey C. Poehler Statement of Professional Qualifications ML15223A7832015-08-10010 August 2015 NRC000228 - Indian Point Unit 2 Technical Specifications 3.1.4 ML15223A7852015-08-10010 August 2015 NRC000229 - Indian Point, Unit 3 Technical Specifications 3.1.4 ML15223A7872015-08-10010 August 2015 NRC000196 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) ML15223A3872015-08-10010 August 2015 NRCR00118 - Indian Point Unit 3 Technical Specifications (Excerpt) (Revised) ML15222A8352015-08-10010 August 2015 ENT000621 - Westinghouse, WCAP-17894-NP, Rev. 0, Component Inspection Details Supporting Aging Management of Reactor Internals at Indian Point Unit 2 (Sept. 2014) ML15223A8052015-08-10010 August 2015 NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt) ML15223A9452015-08-10010 August 2015 NRC000223 - IP3 FSAR Rev. 04 Chapter 14 (2011) ML15223A3862015-08-10010 August 2015 NRC000222 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt) ML15222B1242015-08-10010 August 2015 ENT000680 - Curriculum Vitae of Barry M. Gordon ML15222B1262015-08-10010 August 2015 ENT000687 - NRC, Safety Evaluation Report, Topical Report on ASME Section III Piping and Component Fatigue Analysis Utilizing the Westems Computer Code (WCAP-17577, Revision 2) (Undated) ML15222B1612015-08-10010 August 2015 ENTR00186 - Curriculum Vitae of Mark A. Gray ML15222A8482015-08-10010 August 2015 ENT000637 - NUREG-1874, Recommended Screening Limits for Pressurized Thermal Shock (PTS) (March 2010) 2016-03-21
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NRC000187 Submitted: August 10, 2015 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 6, 2013 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUB~IECT: REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2013-01 (TAC NOS. MD5407 AND MD5408)
Dear Sir or Madam:
By letter dated April 23,2007, as supplemented by letters dated May 3,2007, and June 21, 2007, Entergy Nuclear Operations, Inc. (Entergy or the applicant), submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3, for review by the U.S.
Nuclear Regulatory Commission (NRC or the staff). The staff documented its findings in the Safety Evaluation Report (SER) related to the license renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, which was issued August 2009 and supplemented August 3D, 2011 (SER Supplement 1).
As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," the staff has identified the need for additional information with respect to this plan and the associated Reactor Vessel Internals Inspection Program as described in the enclosure.
This request for additional information was discussed with Mr. Roger Waters, and a mutually agreeable date for Entergy's response is within 90 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or bye-mail at John. Daily@nrc.gov.
Sincerely, John Daily, Sr. Project M nager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
As stated cc w/encl: Listserv
ML13015A175 *concurred via email I
iloFFICE LA: RPB2:DLR* PM: DLR/RPB1 BC:DLR/RPB1 PM: DLR/RPB1 II NAME IKing JDaily DMorey JDaily II DATE 1/18/13 2/4113 2/5113 2/6/13
REQUESTS FOR ADDITIONAL INFORMATION, SET 2013-01 RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3, LICENSE RENEWAL APPLICATION REACTOR VESSEL INTERNALS PROGRAM DOCKET NOS. 50-247 AND 50-286 (Set 2013-01 )
RAI11a (RVI Program and combined effects of embrittlement)
Background
In request for additional information (RAI) 11, the staff requested additional information on the approach to be used for the plant-specific evaluation of the cast austenitic stainless steel (CASS) lower support column bodies. The applicant's response indicates it plans to use a screening approach using the screening criteria for thermal aging embrittlement susceptibility from the Nuclear Regulatory Commission (NRC) staff's May 19, 2000, letter (Reference 1). The applicant provided a table of the screening criteria based on chemistry, casting method, and delta ferrite content identical to Table 2 of Reference 1.
Issue However, Reference 1 also recommends that to account for a potential synergistic effect on loss of fracture toughness due to the combined effects of thermal embrittlement (TE) and neutron irradiation embrittlement (IE), a component-specific assessment should be performed for components that will experience neutron f1uence of 1x1011 neutrons per square centimeter (n/cm 2) or greater. Supplemental inspections would be recommended for those components that are potentially susceptible to TE and IE, that are also subject to significant tensile loadings under any normal operating or design basis condition. Per Table 4-6 of MRP-191 (Reference 2), the screening value of the neutron fluence for the lower support column bodies for Westinghouse-design reactor vessel internals (RVI) is 1x1 0 22 to 5x1022 n/cm 2
- This is significantly greater than the 1x1011 n/cm 2 threshold value provided in Reference 1.
Request Describe how the effects of neutron fluence, with respect to a potential synergistic effect of TE and IE, will be addressed in the plant-specific evaluation of the lower support column bodies.
The applicant should propose modifications of the aging management requirements for the lower support column bodies as necessary to address the concern with a potential synergistic effect.
The staff notes that for CASS, different neutron fluence thresholds, above which the synergistic effect of TE and IE must be considered, have been proposed in various industry documents. If a threshold value greater than 1x1011 n/cm 2 is used in the applicant's evaluation ofthe potential synergistic effect, a technical justification should be included for the threshold value chosen.
The technical justification should include a description of the material test data used as the basis for the threshold including material type(s), thermal aging time and temperature, neutron fluence, type of reactor in which the irradiation was conducted, and relevant mechanical testing results.
ENCLOSURE
-2 RAI15a (RVI program and Fatigue)
Background
In its response to RAI 15, Question 1, by letter dated October 17, 2012 (Reference 3), the applicant revised its response to RAI 12 to indicate that it intends to use the RVI Program to manage the cracking-fatigue aging effect for RVI components that have a time-limited aging analysis (TLAA) that determined a cumulative usage factor (CUF). The applicant provided a list of the RVI components that have a CUF analysis, a table cross-indexing these components with the equivalent component name in MRP-227 -A, along with the inspection requirements, and a justification for each component with a CUF that the inspection requirements are adequate to manage the cumulative fatigue damage aging effect.
Part 5 of Action Item 8 of the staff's final safety evaluation (SE) of MRP-227 -A contains two requirements that must be fulfilled by licensees that intend to use the RVI Program to manage the cracking-fatigue aging effect for components with a TLAA for fatigue:
- 1. For those CUF analyses that are TLAAs, the applicant may use the pressurized-water reactor (PWR) Vessel Internals Program as the basis for accepting these CUF analyses in accordance with 10 CFR 54.21 (c)(1)(iii) only if the RVI components in the CUF analyses are periodically inspected for fatigue-induced cracking in the components during the period of extended operation.
- 2. The periodicity of the inspections of these components shall be justified to be adequate to resolve the TLAA.
Many of the RVI components with TLAA analyses for both Indian Point (IP) Units 2 and 3 (IP2 and IP3) are either "existing programs" or "no additional measures" components under MRP 227-A, which are inspected under the ASME Section XI, Inservice Inspection Program and are thus only subject to a VT-3 visual examination. Those components categorized as "expansion" mayor may not be inspected under the RVI Program based on the findings of the RVI Inspection Program examinations of the linked "primary" component(s). Additionally, a VT-3 visual examination may not be adequate for a" components for detecting fatigue cracking prior to the occurrence of structurally significant cracking, although the staff notes that VT-3 examination is used for some components that were determined to be primary components for fatigue (such as thermal shield flexures and baffle-edge bolts).
In general, a justification for the inspection periodicity was not provided in the response to RAI
- 15. The default inspection periodicity for most "primary" inspection category components in MRP-227-A is every ten years following the initial inspection.
All of the CUFs for RVI components provided in Tables 4.3-5 and 4.3-6 of the IP2 & IP3 license renewal application (LRA) are less than 1.0. However, these CUFs were determined without the application of an environmental correction factor (Fen) to account for the effects of the reactor coolant environment. However, it is reasonable to conclude that if the reactor coolant environment affects the fatigue usage of other components in the reactor coolant system and reactor pressure vessel, then it would affect the RVI components similarly. The Fen for the reactor pressure vessel (RPV) components and reactor coolant system given in Section 4.3.4 of the LRA range from 2.45 to 15.35. Application of Fen in this range could cause the CUF of some RVI components to exceed 1.0. This would affect the required periodicity of inspection. For a very high environmentally-adjusted CUF, even a 10-year inspection interval may not be adequate.
- 3 Issue
- 1. Most of the RVI components with a fatigue TLAA analysis are not "Primary" inspection category components under the RVI Program, thus may be subject to no inspection other than a Vf-3 visual examination under the ASME Section XI, Inservice Inspection Program, since "Expansion" category component inspections are only triggered in the event of degradation of the linked "Primary" inspection category component(s).
- 2. The licensee did not justify the adequacy of the periodicity of the RVI Program inspections performed on RVI components that have fatigue TLAA analyses.
- 3. The staff considers the inspection techniques required by MRP-227 -A for components in the "Primary," "Expansion," or "Existing Programs" categories, for which fatigue is a screened-in aging mechanism, adequate to detect cracking due to fatigue if the RVI Program is credited for managing a fatigue TLAA. However, those components that fall into the "No Additional Measures" category under MRP-227 -A have no specified examination techniques, periodicity, coverage, and acceptance criteria in MRP-227-A Requested Information
- 1. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, but which are classified as "Expansion," "Existing Programs," or "No Additional Measures" inspection category components, provide a modification to the RVllnspection Program to re-categorize these components as "Primary" inspection category components. If any such components are to remain in the "Expansion" category, provide a technical justification for potentially never inspecting these components. Discuss your plans to re-categorize these components as "Primary" inspection category components.
- 2. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, provide a quantitative justification that the periodicity of inspections for fatigue is adequate, either in terms of the calculated CUF (considering the effects of the environment on the CUF analysis), or by using a flaw tolerance approach.
- 3. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVI Inspection Program and which are classified as "No Additional Measures" components under MRP-227 -A, identify the examination technique, coverage, periodicity, and acceptance criteria (i.e., provide the equivalent information to that provided in Tables 4-3 and 5-3 of MRP-227-A). In addition, provide the information requested in Parts 1 and 2 of this RAI for these components.
References
- 1. U.S. Nuclear Regulatory Commission Letter, "License Renewal Issue No. 98-0030, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components," May 19, 2000 (NRC ADAMS Accession No. ML003717179)
- 2. MRP-191 Revision 0, "Materials Reliability Program: Screening, Categorization and Ranking of Reactor Internals of Westinghouse and Combustion Engineering PWR Designs," ADAMS Accession Number ML091910130
- 3. Letter from F. Dacimo to NRC dated October 17,2012,
Subject:
Indian Point Nuclear Generating Unit Nos. 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application. (ADAMS Accession No. ML12300A391)
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-03 (TAC NOS. MD5407 AND MD5408)
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