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| | number = ML13231A128 | | | number = ML13231A128 |
| | issue date = 08/22/2013 | | | issue date = 08/22/2013 |
| | title = Nine Mile Point Unit 2 - Request for Additional Information Regarding the License Amendment Request for the Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report (TAC MF0345) | | | title = Request for Additional Information Regarding the License Amendment Request for the Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Costanzo C | | | addressee name = Costanzo C |
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| | docket = 05000410 | | | docket = 05000410 |
| | license number = | | | license number = |
| | contact person = Vaidya B K, NRR/DORL/LPL1-1, 415-3308 | | | contact person = Vaidya B, NRR/DORL/LPL1-1, 415-3308 |
| | case reference number = TAC MF0345 | | | case reference number = TAC MF0345 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 7 | | | page count = 7 |
| | project = TAC:MF0345, TAC:MF0345 | | | project = TAC:MF0345 |
| | stage = RAI | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:OFFIOIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August22,2013 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093 SUB..NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT (TAC NO. MF0345) Dear Mr. Costanzo: By letter dated ..Iuly 31, 2013, Nine Mile Point Nuclear Station, LLC (the licensee) submitted a response to request for additional information (RAI) regarding request for changes to the Nine Mile Point Unit No.2 (NMP2) Technical Specifications (TSs) pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90. The proposed amendment would revise the NMP2 TSs as necessary to relocate the pressure and temperature limit curves and associated references to a Pressure and Temperature Limits Report. The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review. NOTICE: Enclosure 2 to this letter contains sensitive security-related information. Upon separation from Enclosure 2, this letter is DECONTROLLED. OFFICIAL USE ONLY SENSITIVE PROPRIETARY OFFICIAL ldSE Ot.LY SENSITIVE PROPRIETARY INFORMATIOt. C. Costanzo The NRC staff's request for additional information (RAI) is provided in Enclosure 1. The RAI was discussed with your staff on August 19, 2013, and it was agreed that your response would be provided by close of business September 6, 2013. Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 Enclosure: 1. RAI with Proprietary Information Redacted 2. RAI with Proprietary Information cc w/encl 1 only: Distribution via Listserv -OFFICIAL USE ONLY SENSITIVE PROPRIETARY OFFICIAL USE ONLY SENSITIVE PROPRIETARY ENCLOSURE (WITH SENSITIVE PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL NINE MILE POINT NUCLEAR STATION, UNIT LICENSE AMENDMENT REQUEST THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT TO THE PRESSURE AND TEMPERA TRUE LIMITS DOCKET NUMBER: (TAC NUMBER OFFICIAL USE ONLY SENSITIVE PROPRIETARY OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL NINE MILE POINT NUCLEAR STATION, UNIT LICENSE AMENDMENT REQUEST THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT TO THE PRESSURE AND TEMPERATRUE LIMITS DOCKET NUMBER: (TAC NUMBER BACKGROUND Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements." states: "this appendix specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary (RCPB) oflight water nuclear power reactors to provide adequate margins of safety ... " In addition. 10 CFR Part 50. Appendix G. Paragraph IV.A states that: "the pressure-retaining components of the RCPB that are made of ferritic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), supplemented by the additional requirements set forlh in [paragraph IV.A.2. "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements"] ... " Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the entire RCPB, consisting of ferritic RCPB materials in the reactor pressure vessel (RPV) beltline (neutron fluence ;?: 1 x 1017 n/cm2, E > 1 MeV), as well as ferritic RCPB materials not in the RPV beltline (neutron fluence < 1 x 1017 n/cm2* E> 1 MeV). This request contains sensitive proprietary information which is indicated by double square brackets. RAI EVIB 3 The response to request for additional information (RAI) EVIB-1 states that Tables 4-4 and 4-5 of Reference 1 provide a list of all non-beltline vessel reactor coolant pressure boundary (RCPB) components included in the pressure-temperature (P-T) limit evaluation. It appears that all the listed components are non-beltline components in the RPV. OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION -2 Requested information: Are there any ferritic components in the RCPB that are not part of the RPV that must be considered in the development of the P-T limits, such as piping components or other pressure vessels? If so, describe how these components were considered in the development of the P-T limits, for example through consideration of the lowest service temperature as defined in the ASME Code, Section III. RAI EVIB4 The response to RAI EVIB-1 indicates that all RCPB materials met the applicable ASME Code requirements for fracture toughness, but also states that the Pressure Integrity Specification for the RCPB materials has the following requirement: "For ferritic RCPB materials ordered where the service temperature is less than 250°F when the system is pressurized to more than 20% of the design pressure, impact tests in accordance with the ASME Code were required to demonstrate adequate fracture toughness properties. For RCPB materials having a minimum service temperature of 250°F or more when the system is pressurized to more than 20% of the design pressure, impact testing was not required. Further, impact testing was not required on components or equipment whose rupture could not result in a loss of coolant exceeding the capability of the normal makeup system to maintain adequate core cooling for the duration of reactor shutdown and orderly cooldown." The above requirement of the Pressure Integrity Specification appears inconsistent with the requirements of the ASME Code, Section III, NB-2300, "Fracture Toughness Requirements for Material." Requested Information: Discuss how the impact testing requirements of the Pressure Integrity Specification are consistent with ASME Code, Section III, NB-2300 requirements for fracture toughness of material. RAI EVIB 5 The response to RAI EVIB-2, Item 1, Water Level Instrumentation (WLI) Nozzle states that the General Electric-Hitachi (GEH) methodology is that any partial penetration nozzle that is located in the beltline region is evaluated using the [[ ]] methodology as defined in Appendix F of Reference 1. The calculation provided for the pressure-temperature relationship of the WLI nozzle appears to follow the methodology of Appendix F. However, the calculation uses the [[ ]] from Appendix J of Reference 1. OFFICIAL USE ONLY SENSITIVE PROPRIETARY OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION Requested Information: Clarify whether the NMP2 WLI nozzle is a partial penetration or full penetration nozzle and whether the methodology of Appendix F or Appendix J was used to calculate the P-T limits required for the WLI nozzle. If the NMP2 WLI nozzle is a full-penetration nozzle, justify the use of the [[ ]] values from Appendix J for evaluating the P-T limits for this nozzle, since the Appendix J methodology is for a partial penetration welded nozzle. Provide the inputs and the calculation of References: NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves," Enclosure 1 to MFN 09-506, June 30, 2009 (ADAMS Accession No. ML092370488) OFFICIAL USE ONLY SENSITIVE PROPRIETARY UBi OtJL:':' BIiJJBITIYE PROPRIIi ..... RY IJiFORM ....ION C. Costanzo The NRC staff's request for additional information (RAI) is provided in Enclosure 1. The RAI was discussed with your staff on August 19, 2013, and it was agreed that your response would be provided by close of business September 6, 2013. Sincerely, Ira! Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 Enclosure: 1. RAI with Proprietary Information Redacted 2. RAI with Proprietary Information cc w/encl 1 only: Distribution via Listserv. DISTRIBUTION: PUBLIC LPL1-1 R/F RidsNrrPMNineMilePoint RidsNrrDeEvib RidsAcrsAcnw_MailCTR RidsNrrLAKGoldstein RidsNrrDssSrxb RidsRgn1 MailCenter TMcLellan, NRRlEVIB JPoehler, NRRlEVIB ADAMS ACCESSION NUMBERS: Package: ML13232A145 Cover Letter & Enclosure 1: M L 13231 A 128 Enclosure 2: ML13231A131 RAJs transml'ttedblY memo dated 08/08/13 NRRO41-OFFICE ILPL 1-1\PM llPL1-1\LA EVIB/BC (*) LPL 1-1\BC (A) LPL1-1\PM NAME BVaidya KGoldstein SRosenberg RBeall (DPickett for) BVaidya DATE 08/22/13 08/22/13 08/08/13 08/22/13 08/22/13 OFFICIAL RECORD COPY OFFICIAL USE ONLY SENSITI'JE PROPRIETARY INFORMATION | | {{#Wiki_filter:OFFIOIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August22,2013 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093 SUB..IECT: NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT (TAC NO. MF0345) |
| }} | | |
| | ==Dear Mr. Costanzo:== |
| | |
| | By letter dated ..Iuly 31, 2013, Nine Mile Point Nuclear Station, LLC (the licensee) submitted a response to request for additional information (RAI) regarding request for changes to the Nine Mile Point Unit No.2 (NMP2) Technical Specifications (TSs) pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90. The proposed amendment would revise the NMP2 TSs as necessary to relocate the pressure and temperature limit curves and associated references to a Pressure and Temperature Limits Report. |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review. |
| | NOTICE: Enclosure 2 to this letter contains sensitive security-related information. |
| | Upon separation from Enclosure 2, this letter is DECONTROLLED. |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | |
| | OFFICIAL ldSE Ot.LY SENSITIVE PROPRIETARY INFORMATIOt. |
| | C. Costanzo -2 The NRC staff's request for additional information (RAI) is provided in Enclosure 1. The RAI was discussed with your staff on August 19, 2013, and it was agreed that your response would be provided by close of business September 6, 2013. |
| | Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
| | |
| | ==Enclosure:== |
| | : 1. RAI with Proprietary Information Redacted |
| | : 2. RAI with Proprietary Information cc w/encl 1 only: Distribution via Listserv |
| | - OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION ENCLOSURE 1 (WITH SENSITIVE PROPRIETARY INFORMATION REDACTED) |
| | REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.2 LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT DOCKET NUMBER: 50-410 (TAC NUMBER MF0345) |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.2 LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT DOCKET NUMBER: 50-410 (TAC NUMBER MF0345) |
| | BACKGROUND Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements." states: |
| | "this appendix specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary (RCPB) of light water nuclear power reactors to provide adequate margins of safety ... " |
| | In addition. 10 CFR Part 50. Appendix G. Paragraph IV.A states that: |
| | "the pressure-retaining components of the RCPB that are made of ferritic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), supplemented by the additional requirements set forlh in [paragraph IV.A.2. "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements"] ... " |
| | Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the entire RCPB, consisting of ferritic RCPB materials in the reactor pressure vessel (RPV) beltline (neutron fluence ;?: 1 x 10 17 n/cm 2 , E > 1 MeV), as well as ferritic RCPB materials not in the RPV beltline (neutron fluence < 1 x 1017 n/cm 2 |
| | * E> 1 MeV). This request contains sensitive proprietary information which is indicated by double square brackets. |
| | RAI EVIB 3 The response to request for additional information (RAI) EVIB-1 states that Tables 4-4 and 4-5 of Reference 1 provide a list of all non-beltline vessel reactor coolant pressure boundary (RCPB) components included in the pressure-temperature (P-T) limit evaluation. It appears that all the listed components are non-beltline components in the RPV. |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | -2 Requested information: |
| | Are there any ferritic components in the RCPB that are not part of the RPV that must be considered in the development of the P-T limits, such as piping components or other pressure vessels? If so, describe how these components were considered in the development of the P-T limits, for example through consideration of the lowest service temperature as defined in the ASME Code, Section III. |
| | RAI EVIB4 The response to RAI EVIB-1 indicates that all RCPB materials met the applicable ASME Code requirements for fracture toughness, but also states that the Pressure Integrity Specification for the RCPB materials has the following requirement: |
| | "For ferritic RCPB materials ordered where the service temperature is less than 250°F when the system is pressurized to more than 20% of the design pressure, impact tests in accordance with the ASME Code were required to demonstrate adequate fracture toughness properties. For RCPB materials having a minimum service temperature of 250°F or more when the system is pressurized to more than 20% of the design pressure, impact testing was not required. Further, impact testing was not required on components or equipment whose rupture could not result in a loss of coolant exceeding the capability of the normal makeup system to maintain adequate core cooling for the duration of reactor shutdown and orderly cooldown." |
| | The above requirement of the Pressure Integrity Specification appears inconsistent with the requirements of the ASME Code, Section III, NB-2300, "Fracture Toughness Requirements for Material." |
| | Requested Information: |
| | Discuss how the impact testing requirements of the Pressure Integrity Specification are consistent with ASME Code, Section III, NB-2300 requirements for fracture toughness of material. |
| | RAI EVIB 5 The response to RAI EVIB-2, Item 1, Water Level Instrumentation (WLI) Nozzle states that the General Electric-Hitachi (GEH) methodology is that any partial penetration nozzle that is located in the beltline region is evaluated using the (( )) methodology as defined in Appendix F of Reference 1. The calculation provided for the pressure-temperature relationship of the WLI nozzle appears to follow the methodology of Appendix F. However, the calculation uses the (( )) from Appendix J of Reference 1. |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | -3 Requested Information: |
| | : 1. Clarify whether the NMP2 WLI nozzle is a partial penetration or full penetration nozzle and whether the methodology of Appendix F or Appendix J was used to calculate the P-T limits required for the WLI nozzle. |
| | : 2. If the NMP2 WLI nozzle is a full-penetration nozzle, justify the use of the (( )) values from Appendix J for evaluating the P-T limits for this nozzle, since the Appendix J methodology is for a partial penetration welded nozzle. |
| | : 3. Provide the inputs and the calculation of (( |
| | )) |
| | |
| | ==References:== |
| | : 1. NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves," Enclosure 1 to MFN 09-506, June 30, 2009 (ADAMS Accession No. ML092370488) |
| | OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION |
| | |
| | Package: ML13232A145 Cover Letter & Enclosure 1: M L 13231 A 128 : ML13231A131 RAJ s transml'ttedblY memo d ated 08/08/13 NRRO41 OFFICE ILPL 1-1\PM llPL1-1\LA EVIB/BC (*) LPL 1-1\BC (A) LPL1-1\PM RBeall (DPickett NAME BVaidya KGoldstein SRosenberg BVaidya for) |
| | DATE 08/22/13 08/22/13 08/08/13 08/22/13 08/22/13}} |
Letter Sequence RAI |
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TAC:MF0345, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR (Approved, Closed) |
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MONTHYEARML1233803362012-11-21021 November 2012 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report Project stage: Request ML13022A3252013-01-22022 January 2013 MF0345 - Acceptance of Requested Licensing Action License Amendment Request- Relocation of PT Limit Curves to PTLR Project stage: Acceptance Review ML13091A0402013-03-25025 March 2013 Supplement to License Amendment Request to Relocate, the Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report Project stage: Supplement ML13086A0342013-04-16016 April 2013 MF0345-Proprietary Information Determination Letter to Licensee Submission Dated November 21, 2012 (Proprietary Information Determination Letter) Project stage: Other ML13172A1392013-06-20020 June 2013 Draft Rais, MF0345, LAR Revising and Relocating PT Limit Curves to Prlr Project stage: Draft RAI ML13214A3882013-07-31031 July 2013 License Amendment Request to Relocate the Pressure & Temperature Limit Curves to the Pressure & Temperature Limits Report - Supplemental Information in Response to NRC Request for Additional Information Project stage: Supplement ML13224A2652013-08-12012 August 2013 MF0345, Draft Follow-Up RAIs (Redacted), MF0345, LAR Revising and Relocating PT Limit Curves to PTLR Project stage: Draft RAI ML13231A1282013-08-22022 August 2013 Request for Additional Information Regarding the License Amendment Request for the Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report Project stage: RAI ML13254A1552013-09-0606 September 2013 Amendment Request to Relocate the Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report - Supplemental Information in Response to NRC Request for Additional Information Project stage: Supplement ML13217A0442013-09-12012 September 2013 Request for Withholding Information from Public Disclosure Responses to Requests for Additional Information Dated July 31, 2013 Project stage: RAI ML13256A3952013-09-13013 September 2013 Revised Draft Follow-Up Rais, MF0345, LAR Revising and Relocating PT Limit Curves to PTLR Project stage: Draft RAI ML13268A5582013-09-25025 September 2013 MF0345, Additional Draft Rais, MF0345, LAR Revising and Relocating PT Limit Curves to PTLR Project stage: Draft RAI ML13270A2772013-09-27027 September 2013 MF0345, Revised Additional Rais, MF0345, LAR Revising and Relocating PT Limit Curves to PTLR Project stage: RAI ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 Project stage: Other ML13256A0132013-10-0909 October 2013 Request for Withholding Information from Public Disclosure Responses to Requests for Additional Information Dated July 31, 2013 Project stage: RAI ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) Project stage: Draft Other ML13311A0532013-11-0404 November 2013 License Amendment Request to Relocate the Pressure & Temperature Limit Curves to the Pressure and Temperature Limits Report - Supplemental Information in Response to NRC Request for Additional Information Project stage: Supplement ML13310C0632013-11-0606 November 2013 MF0345, Additional FOLLOW-UP RAI, MF0345, LAR Revising and Relocating PT Limit Curves to PTLR Project stage: RAI ML13353A3052013-12-13013 December 2013 License Amendment Request to Relocate the Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report - Supplemental Information in Response to NRC Request for Additional Information and Clarification.. Project stage: Supplement ML14003A0052014-01-15015 January 2014 Request for Withholding Information from Public Disclosure Responses to Requests for Additional Information Dated November 4, and December 13, 2013 Project stage: RAI ML14063A4742014-02-25025 February 2014 License Amendment Request to Relocate the Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report - Supplement to Revise Implementation Date Project stage: Supplement ML14057A5542014-05-29029 May 2014 Issuance of Amendment Regarding Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report Project stage: Approval 2013-08-12
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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21320A3472021-11-16016 November 2021 Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0 ML21306A3312021-11-0202 November 2021 Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21125A1282021-05-0404 May 2021 OPC Document Request - Feb 2021 ML21110A5112021-04-20020 April 2021 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582 ML21088A2682021-03-30030 March 2021 Notification of Conduct of a Fire Protection Team Inspection ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20212L8702020-07-30030 July 2020 Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290) ML20213A9352020-07-30030 July 2020 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20045E3582020-02-14014 February 2020 Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates ML19296A1862019-10-23023 October 2019 Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19151A8132019-05-31031 May 2019 Licensed Operator Positive Fitness-For-Duty Test ML19025A1572019-01-25025 January 2019 Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18341A2212018-12-0707 December 2018 Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491) ML18228A6932018-08-15015 August 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18205A3922018-07-24024 July 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18184A2882018-07-0303 July 2018 Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039) ML18102A2372018-04-12012 April 2018 NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control ML17234A3592017-08-30030 August 2017 Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 ML17241A2752017-08-29029 August 2017 Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment ML17240A3102017-08-15015 August 2017 NRR E-mail Capture - Nine Mile Point MSA and FE RAI ML17172A0842017-06-27027 June 2017 Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702 ML17065A1622017-03-14014 March 2017 Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J 2023-09-21
[Table view] |
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OFFIOIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August22,2013 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093 SUB..IECT: NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT (TAC NO. MF0345)
Dear Mr. Costanzo:
By letter dated ..Iuly 31, 2013, Nine Mile Point Nuclear Station, LLC (the licensee) submitted a response to request for additional information (RAI) regarding request for changes to the Nine Mile Point Unit No.2 (NMP2) Technical Specifications (TSs) pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90. The proposed amendment would revise the NMP2 TSs as necessary to relocate the pressure and temperature limit curves and associated references to a Pressure and Temperature Limits Report.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional information is needed to complete its review.
NOTICE: Enclosure 2 to this letter contains sensitive security-related information.
Upon separation from Enclosure 2, this letter is DECONTROLLED.
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
OFFICIAL ldSE Ot.LY SENSITIVE PROPRIETARY INFORMATIOt.
C. Costanzo -2 The NRC staff's request for additional information (RAI) is provided in Enclosure 1. The RAI was discussed with your staff on August 19, 2013, and it was agreed that your response would be provided by close of business September 6, 2013.
Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
- 1. RAI with Proprietary Information Redacted
- 2. RAI with Proprietary Information cc w/encl 1 only: Distribution via Listserv
- OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION ENCLOSURE 1 (WITH SENSITIVE PROPRIETARY INFORMATION REDACTED)
REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.2 LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT DOCKET NUMBER: 50-410 (TAC NUMBER MF0345)
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.2 LICENSE AMENDMENT REQUEST FOR THE RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATRUE LIMITS REPORT DOCKET NUMBER: 50-410 (TAC NUMBER MF0345)
BACKGROUND Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements." states:
"this appendix specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary (RCPB) of light water nuclear power reactors to provide adequate margins of safety ... "
In addition. 10 CFR Part 50. Appendix G. Paragraph IV.A states that:
"the pressure-retaining components of the RCPB that are made of ferritic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), supplemented by the additional requirements set forlh in [paragraph IV.A.2. "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements"] ... "
Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the entire RCPB, consisting of ferritic RCPB materials in the reactor pressure vessel (RPV) beltline (neutron fluence ;?: 1 x 10 17 n/cm 2 , E > 1 MeV), as well as ferritic RCPB materials not in the RPV beltline (neutron fluence < 1 x 1017 n/cm 2
- E> 1 MeV). This request contains sensitive proprietary information which is indicated by double square brackets.
RAI EVIB 3 The response to request for additional information (RAI) EVIB-1 states that Tables 4-4 and 4-5 of Reference 1 provide a list of all non-beltline vessel reactor coolant pressure boundary (RCPB) components included in the pressure-temperature (P-T) limit evaluation. It appears that all the listed components are non-beltline components in the RPV.
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
-2 Requested information:
Are there any ferritic components in the RCPB that are not part of the RPV that must be considered in the development of the P-T limits, such as piping components or other pressure vessels? If so, describe how these components were considered in the development of the P-T limits, for example through consideration of the lowest service temperature as defined in the ASME Code,Section III.
RAI EVIB4 The response to RAI EVIB-1 indicates that all RCPB materials met the applicable ASME Code requirements for fracture toughness, but also states that the Pressure Integrity Specification for the RCPB materials has the following requirement:
"For ferritic RCPB materials ordered where the service temperature is less than 250°F when the system is pressurized to more than 20% of the design pressure, impact tests in accordance with the ASME Code were required to demonstrate adequate fracture toughness properties. For RCPB materials having a minimum service temperature of 250°F or more when the system is pressurized to more than 20% of the design pressure, impact testing was not required. Further, impact testing was not required on components or equipment whose rupture could not result in a loss of coolant exceeding the capability of the normal makeup system to maintain adequate core cooling for the duration of reactor shutdown and orderly cooldown."
The above requirement of the Pressure Integrity Specification appears inconsistent with the requirements of the ASME Code,Section III, NB-2300, "Fracture Toughness Requirements for Material."
Requested Information:
Discuss how the impact testing requirements of the Pressure Integrity Specification are consistent with ASME Code,Section III, NB-2300 requirements for fracture toughness of material.
RAI EVIB 5 The response to RAI EVIB-2, Item 1, Water Level Instrumentation (WLI) Nozzle states that the General Electric-Hitachi (GEH) methodology is that any partial penetration nozzle that is located in the beltline region is evaluated using the (( )) methodology as defined in Appendix F of Reference 1. The calculation provided for the pressure-temperature relationship of the WLI nozzle appears to follow the methodology of Appendix F. However, the calculation uses the (( )) from Appendix J of Reference 1.
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
-3 Requested Information:
- 1. Clarify whether the NMP2 WLI nozzle is a partial penetration or full penetration nozzle and whether the methodology of Appendix F or Appendix J was used to calculate the P-T limits required for the WLI nozzle.
- 2. If the NMP2 WLI nozzle is a full-penetration nozzle, justify the use of the (( )) values from Appendix J for evaluating the P-T limits for this nozzle, since the Appendix J methodology is for a partial penetration welded nozzle.
- 3. Provide the inputs and the calculation of ((
))
References:
- 1. NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves," Enclosure 1 to MFN 09-506, June 30, 2009 (ADAMS Accession No. ML092370488)
OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
Package: ML13232A145 Cover Letter & Enclosure 1: M L 13231 A 128 : ML13231A131 RAJ s transml'ttedblY memo d ated 08/08/13 NRRO41 OFFICE ILPL 1-1\PM llPL1-1\LA EVIB/BC (*) LPL 1-1\BC (A) LPL1-1\PM RBeall (DPickett NAME BVaidya KGoldstein SRosenberg BVaidya for)
DATE 08/22/13 08/22/13 08/08/13 08/22/13 08/22/13