ML13231A128

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)

ML13231A128
Person / Time
Site:	Nine Mile Point
Issue date:	08/22/2013
From:	Bhalchandra Vaidya Plant Licensing Branch 1
To:	Costanzo C Nine Mile Point
Vaidya B K, NRR/DORL/LPL1-1, 415-3308
References
TAC MF0345
Download: ML13231A128 (7)

Text

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