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| | number = ML15016A184 | | | number = ML15016A184 |
| | issue date = 01/20/2015 | | | issue date = 01/20/2015 |
| | title = Palisades Nuclear Plant - Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a (TAC No. MF4528) | | | title = Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a |
| | author name = Rankin J K | | | author name = Rankin J |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = | | | addressee name = |
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| | docket = 05000255 | | | docket = 05000255 |
| | license number = DPR-020 | | | license number = DPR-020 |
| | contact person = Rankin J K | | | contact person = Rankin J |
| | case reference number = TAC MF4528 | | | case reference number = TAC MF4528 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 January 20, 2015 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 20, 2015 Vice President, Operations Entergy Nuclear Operations, Inc. |
| | Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PALISADES NUCLEAR PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61a (TAC NO. MF4528) | | PALISADES NUCLEAR PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61a (TAC NO. MF4528) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| By letter dated July 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14211A520), Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) for Palisades Nuclear Plant (PNP) to implement Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS)," also referred to as the alternate PTS rule. PNP is expected to exceed the screening criteria of the PTS rule (1 0 CFR 50.61) in August 2017, prior to the expiration of its extended operating license (2031). Compliance with the requirements of 10 CFR 50.61 a may be met as an alternative to 10 CFR 50.61. The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The draft questions were sent via electronic transmission on January 9, 2015, to Mr. Jeffrey Erickson, of your staff. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. A clarification telephone conference was held on January 16, 2015. As a result, modifications were made to RAI1a and 2c, as reflected in the enclosed RAI. Based on our discussions we understand that a response to the RAis will be provided by February 17, 2015. | | |
| If you have any questions, please contact me at Jennivine.Rankin@nrc.gov or (301) 415-1530. | | By letter dated July 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14211A520), Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) for Palisades Nuclear Plant (PNP) to implement Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS)," also referred to as the alternate PTS rule. PNP is expected to exceed the screening criteria of the PTS rule (1 0 CFR 50.61) in August 2017, prior to the expiration of its extended operating license (2031). |
| | Compliance with the requirements of 10 CFR 50.61 a may be met as an alternative to 10 CFR 50.61. |
| | The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The draft questions were sent via electronic transmission on January 9, 2015, to Mr. Jeffrey Erickson, of your staff. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. A clarification telephone conference was held on January 16, 2015. As a result, modifications were made to RAI1a and 2c, as reflected in the enclosed RAI. Based on our discussions we understand that a response to the RAis will be provided by February 17, 2015. |
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| | If you have any questions, please contact me at Jennivine.Rankin@nrc.gov or (301) 415-1530. |
| | Sincerely, nivine K. Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/encl: Distribution via ListServ Sincerely, nivine K. Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION ENTERGY NUCLEAR OPERATIONS. INC. PALISADES NUCLEAR PLANT LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61 a "ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS" DOCKET NO 50-255 By letter dated July 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14211A520), Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) for Palisades Nuclear Plant (PNP) to implement Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS}," also referred to as the alternate PTS rule. PNP is expected to exceed the screening criteria of the PTS rule (10 CFR 50.61) in August 2017, prior to the expiration of its extended operating license (2031). Compliance with the requirements of 10 CFR 50.61a may be met as an alternative to 10 CFR 50.61. Based on its review of the amendment request, the U.S. Nuclear Regulatory Commission staff has determined that additional information is required to complete the review. 10 CFR 50.61a(c)(2) states, in part, the following: Each licensee shall perform an examination and an assessment of flaws in the reactor vessel beltline as required by paragraph (e) of this section. The licensee shall verify that the requirements of paragraphs (e), (e)(1), (e)(2}, and (e)(3) of this section have been met. Issue 1 a There is no discussion of the proximity of the indications in weld 2-112B to each other. RAI1a Provide a discussion of the proximity of the indications, according to the directions in ASME Section XI, paragraph IWA-3300(b), to demonstrate how the indications in weld 2-112B were resolved. Issue 1b A plant-specific assessment of total plate flaws is shown in Table 8-11, "Alternate PTS Rule Allowable Number of Flaws in Plates and Forgings Scaled for Palisades" of the LAR enclosure.
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| In this table, all of the flaws detected during the February 2014 inservice inspection at PNP have been included, reflecting the assumption made by the licensee that all detected flaws lie in the plate rather than in the weld. The exact procedure used to determine the total plate area included in the inspection is not given. Specifically, it is not clear if the area of the weld has been included or excluded from the total plate area. RA11b Augment Table 8-10, "Inspection Length and Area for Palisades," or otherwise revise the documentation provided in the submittal, to clarify how the total plate area was calculated and whether it includes the area of the weld. 10 CFR 50.61 a(c)(1) states, in part, the following: Each licensee shall have projected values of RT MAx-x for each reactor vessel beltline material for the EOL fluence of the material. The assessment of RT MAx-x values must use the calculation procedures given in paragraphs (f) and (g) of this section. The assessment must specify the bases for the projected value of RT MAx-x for each reactor vessel beltline material, including the assumptions regarding future plant operation (e.g., core loading patterns, projected capacity factors); the copper (Cu), phosphorus (P), manganese (Mn), and nickel (Ni) contents; the reactor cold leg temperature (T c); and the neutron flux and fluence values used in the calculation for each beltline material. Issue 2a Section 4, "Plant-Specific RV Material Properties and Dimensions" of the LAR enclosure states the following: Table 4-1 summarizes the best estimate copper, manganese, phosphorus, and nickel contents and RT NDT(U) values of the beltline and extended beltline materials for the Palisades RV. RT NDT(U) values for the Palisades RV plate materials were determined in accordance with the fracture toughness requirements in NUREG-0800, Revision 2, Branch Technical Position MTEB 5-3 (Reference 6); and the requirements of Subparagraph NB-2331 of Section Ill of the ASME B&PV Code (Reference 7). RT NDT(U) values for the weld materials are generic values for Linde 1 092 and 124 weld fluxes per Reference 1. Table 4-1, "Details of RT MAx-x Calculation Inputs for Palisades" of the LAR does not clearly identify which plates used the methods of the Branch Technical Position (BTP) 5-3 and which plates followed the requirements of 10 CFR Part 50, Appendix G, as augmented by the criteria in Section Ill of the ASME Code. RA12a Document which method was used for each RT NDT(u) value in Table 4-1. Provide data demonstrating how each value of RT NDT(ul was calculated when a provision of BTP 5-3 was used.
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| Issue 2b Table 5-1, "Maximum Neutron Fluence on the RV Clad-to-Base Metal Interface for Palisades at 42.1 EFPY" of the LAR, lists that the values for the intermediate and lower longitudinal (axial) welds in the vessel are the same, 2.161 x 1 0+19 neutron/cm2 (E >1.0 MeV), which is 63% of the peak values for the adjacent intermediate and lower shell plates. The methodology for determining the maximum fluence at the axial welds relative to the maximum fluence in the adjacent plates is not discussed in the LAR. RAI2b Provide a discussion of how the maximum fluence for each region and component in Table 5-1 was determined from the detailed fluence information contained in References 8 and 13 listed in Section 10 of the LAR enclosure. For clarity, illustrate the axial position of the active fuel and the azimuthal position of the peak fluence values for the adjacent intermediate and lower shell plates on Figure 4-1, "Identification and Location of Beltline Region Materials for the Palisades Reactor Vessel." Issue 2c Equations 5, 6, and 7 in 10 CFR 50.61a estimate flT3o as a function of various input values, including neutron flux. The licensee has provided most of these input values in Tables 4-1, 5-1 and Table 5-2, "RV Cold Leg Temperature per Operating Cycle for Palisades" of the LAR enclosure. The LAR lacks neutron flux values in Table 8-1, "RT WIAX-Aw Calculation Results for Palisades at 42.1 EFPY," Table 8-2, "RT WIAX-PL Calculation Results for Palisades at 42.1 EFPY," and Table 8-3, "RT W1Ax-cw Calculation Results for Palisades at 42.1 EFPY" for the calculation of RT WIAX-x for the materials listed in Table 4-1. RAI2c Provide neutron flux values on a per cycle basis for the limiting material/region (W5214 intermediate shell longitudinal weld). Section 3.0, "Background" of the LAR indicates that PNP reactor vessel fluence was recalculated based on actual reactor operation through fuel Cycle 22 and expected fluence based on projected operations through Cycle 26. This evaluation was documented in WCAP-15353-Supplement 3-NP, Revision 0, dated June 2013. The PNP alternate PTS rule evaluation is documented in WCAP-17628-NP, Revision 1, "Alternate Pressurized Thermal Shock (PTS) Rule Evaluation for Palisades," dated June 2014. WCAP-17628-NP, Revision 1, for its reactor vessel neutron fluence values references WCAP-15353-Supplement 2-NP, Revision 0, "Palisades Reactor Pressure Vessel Fluence Evaluation," dated July 2011. Please provide clarification for which supplement of WCAP-15353-NP is used in evaluating PNP's alternate fracture toughness requirements for protection against PTS.
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| If you have any questions, please contact me at Jennivine.Rankin@nrc.gov or (301) 415-1530.
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| ==Enclosure:==
| | Request for Additional Information cc w/encl: Distribution via ListServ |
| Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION: Sincerely, IRA/ Jennivine K. Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC LPL3-1 r/f RidsNrrPMPalisades Resource RidsRgn3Mai1Center Resource RidsNrrLAMHenderson Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl3-1 Resource RidsNrrDeEvib Resource PPurtscher, NRR/DE/EVIB Jlindell, OGC ADAMS Accession No* ML15016A184 .. **via email *via memo OFFICE NRR/DORLILPL3-1/PM NRR/DORLILPL3-1/LA NRR/DE/EVIB/BC NAME JRankin MHenderson** SRosenburg | | |
| * DATE 01/20/2015 01/16/2015 1/07/2015 OFFICE NRR/DSS/SRXB NRR/DORLILPL3-1/BC NRR/DORLILPL3-1/PM NAME CJackson | | REQUEST FOR ADDITIONAL INFORMATION ENTERGY NUCLEAR OPERATIONS. INC. |
| * DPelton JRankin DATE 11/18/2014 01/20/2015 01/20/2015 OFFICIAL RECORD COPY | | PALISADES NUCLEAR PLANT LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61 a "ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS" DOCKET NO 50-255 By letter dated July 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14211A520), Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) for Palisades Nuclear Plant (PNP) to implement Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS}," also referred to as the alternate PTS rule. PNP is expected to exceed the screening criteria of the PTS rule (10 CFR 50.61) in August 2017, prior to the expiration of its extended operating license (2031). |
| }} | | Compliance with the requirements of 10 CFR 50.61a may be met as an alternative to 10 CFR 50.61. |
| | Based on its review of the amendment request, the U.S. Nuclear Regulatory Commission staff has determined that additional information is required to complete the review. |
| | 10 CFR 50.61a(c)(2) states, in part, the following: |
| | Each licensee shall perform an examination and an assessment of flaws in the reactor vessel beltline as required by paragraph (e) of this section. The licensee shall verify that the requirements of paragraphs (e), (e)(1), (e)(2}, and (e)(3) of this section have been met. |
| | Issue 1a There is no discussion of the proximity of the indications in weld 2-112B to each other. |
| | RAI1a Provide a discussion of the proximity of the indications, according to the directions in ASME Section XI, paragraph IWA-3300(b), to demonstrate how the indications in weld 2-112B were resolved. |
| | Issue 1b A plant-specific assessment of total plate flaws is shown in Table 8-11, "Alternate PTS Rule Allowable Number of Flaws in Plates and Forgings Scaled for Palisades" of the LAR enclosure. |
| | |
| | In this table, all of the flaws detected during the February 2014 inservice inspection at PNP have been included, reflecting the assumption made by the licensee that all detected flaws lie in the plate rather than in the weld. The exact procedure used to determine the total plate area included in the inspection is not given. Specifically, it is not clear if the area of the weld has been included or excluded from the total plate area. |
| | RA11b Augment Table 8-10, "Inspection Length and Area for Palisades," or otherwise revise the documentation provided in the submittal, to clarify how the total plate area was calculated and whether it includes the area of the weld. |
| | 10 CFR 50.61 a(c)(1) states, in part, the following: |
| | Each licensee shall have projected values of RTMAx-x for each reactor vessel beltline material for the EOL fluence of the material. The assessment of RTMAx-x values must use the calculation procedures given in paragraphs (f) and (g) of this section. The assessment must specify the bases for the projected value of RTMAx-x for each reactor vessel beltline material, including the assumptions regarding future plant operation (e.g., core loading patterns, projected capacity factors); the copper (Cu), phosphorus (P), manganese (Mn), and nickel (Ni) contents; the reactor cold leg temperature (Tc); and the neutron flux and fluence values used in the calculation for each beltline material. |
| | Issue 2a Section 4, "Plant-Specific RV Material Properties and Dimensions" of the LAR enclosure states the following: |
| | Table 4-1 summarizes the best estimate copper, manganese, phosphorus, and nickel contents and RT NDT(U) values of the beltline and extended beltline materials for the Palisades RV. RT NDT(U) values for the Palisades RV plate materials were determined in accordance with the fracture toughness requirements in NUREG-0800, Revision 2, Branch Technical Position MTEB 5-3 (Reference 6); and the requirements of Subparagraph NB-2331 of Section Ill of the ASME B&PV Code (Reference 7). RTNDT(U) values for the weld materials are generic values for Linde 1092 and 124 weld fluxes per Reference 1. |
| | Table 4-1, "Details of RTMAx-x Calculation Inputs for Palisades" of the LAR does not clearly identify which plates used the methods of the Branch Technical Position (BTP) 5-3 and which plates followed the requirements of 10 CFR Part 50, Appendix G, as augmented by the criteria in Section Ill of the ASME Code. |
| | RA12a Document which method was used for each RT NDT(u) value in Table 4-1. Provide data demonstrating how each value of RT NDT(ul was calculated when a provision of BTP 5-3 was used. |
| | |
| | Issue 2b Table 5-1, "Maximum Neutron Fluence on the RV Clad-to-Base Metal Interface for Palisades at 42.1 EFPY" of the LAR, lists that the values for the intermediate and lower longitudinal (axial) welds in the vessel are the same, 2.161 x 10+ 19 neutron/cm 2 (E >1.0 MeV), which is 63% of the peak values for the adjacent intermediate and lower shell plates. The methodology for determining the maximum fluence at the axial welds relative to the maximum fluence in the adjacent plates is not discussed in the LAR. |
| | RAI2b Provide a discussion of how the maximum fluence for each region and component in Table 5-1 was determined from the detailed fluence information contained in References 8 and 13 listed in Section 10 of the LAR enclosure. For clarity, illustrate the axial position of the active fuel and the azimuthal position of the peak fluence values for the adjacent intermediate and lower shell plates on Figure 4-1, "Identification and Location of Beltline Region Materials for the Palisades Reactor Vessel." |
| | Issue 2c Equations 5, 6, and 7 in 10 CFR 50.61a estimate flT 3o as a function of various input values, including neutron flux. The licensee has provided most of these input values in Tables 4-1, 5-1 and Table 5-2, "RV Cold Leg Temperature per Operating Cycle for Palisades" of the LAR enclosure. The LAR lacks neutron flux values in Table 8-1, "RTWIAX-Aw Calculation Results for Palisades at 42.1 EFPY," Table 8-2, "RTWIAX-PL Calculation Results for Palisades at 42.1 EFPY," |
| | and Table 8-3, "RT W1Ax-cw Calculation Results for Palisades at 42.1 EFPY" for the calculation of RT WIAX-x for the materials listed in Table 4-1. |
| | RAI2c Provide neutron flux values on a per cycle basis for the limiting material/region (W5214 intermediate shell longitudinal weld). |
| | Section 3.0, "Background" of the LAR indicates that PNP reactor vessel fluence was recalculated based on actual reactor operation through fuel Cycle 22 and expected fluence based on projected operations through Cycle 26. This evaluation was documented in WCAP-15353- Supplement 3- NP, Revision 0, dated June 2013. The PNP alternate PTS rule evaluation is documented in WCAP-17628- NP, Revision 1, "Alternate Pressurized Thermal Shock (PTS) Rule Evaluation for Palisades," dated June 2014. WCAP-17628-NP, Revision 1, for its reactor vessel neutron fluence values references WCAP-15353- Supplement 2- NP, Revision 0, "Palisades Reactor Pressure Vessel Fluence Evaluation," dated July 2011. |
| | Please provide clarification for which supplement of WCAP-15353-NP is used in evaluating PNP's alternate fracture toughness requirements for protection against PTS. |
| | * ML15016A184 **via email *via memo OFFICE NRR/DORLILPL3-1/PM NRR/DORLILPL3-1/LA NRR/DE/EVIB/BC NAME JRankin MHenderson** SRosenburg |
| | * DATE 01/20/2015 01/16/2015 1/07/2015 OFFICE NRR/DSS/SRXB NRR/DORLILPL3-1/BC NRR/DORLILPL3-1/PM NAME CJackson |
| | * DPelton JRankin DATE 11/18/2014 01/20/2015 01/20/2015}} |
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Tribal Letter - Menominee Indian Tribe of Wisconsin
ML24183A1502024-07-0101 July 2024
Tribal Letter - Prarie Band Potawatomi Nation
ML24183A1452024-07-0101 July 2024
Tribal Letter - Miami Tribe of Oklahoma
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24263A1712024-09-20020 September 2024
Environmental Request for Additional Information
ML24192A0012024-07-0606 July 2024
(E-Mail) Palisades Nuclear Plant - Plant - Draft Request for Additional Information: Palisades Operating TS License Amendment Request - June 6, 2024
ML24192A1672024-06-28028 June 2024
Restart - NRC Request for Additional Information - EP ORO Coordination - June 28, 2024
ML24192A1472024-06-28028 June 2024
Email - Palisades Nuclear Plant - Draft Request for Additional Information: Palisades Administrative TS License Amendment Request - June 28, 2024
ML23354A2602023-12-21021 December 2023
Reference Simulator Inspection Request for Information
ML23055A1542023-02-24024 February 2023
Attachment: Request for Additional Information on the Palisades PSDAR
ML22292A2582022-10-31031 October 2022
PDEP-EAL Amendment RAI
ML22102A2482022-04-14014 April 2022
Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications
ML21274A4172021-10-0505 October 2021
Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information Inspection Report 05000255/2021004
ML21028A4092021-01-27027 January 2021
NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv)
ML21028A0552021-01-27027 January 2021
NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application
ML20272A0112020-09-26026 September 2020
Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs
ML20133K0562020-05-14014 May 2020
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML19357A2752019-12-23023 December 2019
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000255/2020011
ML19226A2932019-08-14014 August 2019
NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant
ML19226A2922019-08-0505 August 2019
NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425
ML19122A4852019-04-29029 April 2019
NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications
ML19009A5392019-01-0909 January 2019
NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a
ML19009A5382018-12-12012 December 2018
NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a
ML18337A1382018-11-30030 November 2018
NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7
ML18337A1402018-11-29029 November 2018
NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7
ML18309A1342018-11-0808 November 2018
Supplemental Information Needed for Acceptance or Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-425, Revision 3
ML18094B0922018-04-0505 April 2018
Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59)
ML18081A2962018-03-22022 March 2018
NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305)
ML18059A8202018-02-28028 February 2018
NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition
ML17335A1042017-11-30030 November 2017
NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266)
ML17118A3342017-04-18018 April 2017
E-Mailed Request for Information Dated 04/18/2017 for Palisades Nuclear Power Station, Unit 1, Inservice Inspection - Part B Items (Exf)
ML17118A3312017-04-18018 April 2017
E-Mailed Request for Information Dated 04/18/17 for Palisades Nuclear Power Station, Unit 1, Inservice Inspection - Part a Items
ML17072A2752017-03-10010 March 2017
NRR E-mail Capture - Palisades Nuclear Plant - Final Request for Additional Information Regarding Relief Request No. RR 4-25
ML16238A0302016-08-29029 August 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action Control Rod Drive Exercise Surveillance
ML16130A0762016-05-11011 May 2016
Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternative Repair Criterion on the Steam Generator Tubes
ML16013A0642016-01-13013 January 2016
NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097)
ML15341A1662015-12-0707 December 2015
NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349)
ML15258A2432015-09-0101 September 2015
NRC Supplement to NRC Letter - Notification of NRC Inspection and Request for Information Dated May 1, 2015 - Palisades Nuclear Plant
ML15149A2462015-05-28028 May 2015
Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg)
ML15072A2542015-03-19019 March 2015
Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a
CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015
Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company
ML15022A1382015-01-22022 January 2015
E-Mail - Palisades Request for Information
ML15016A1842015-01-20020 January 2015
Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a
ML15012A3052015-01-15015 January 2015
Request for Additional Information Regarding the License Amendment Request for an Equivalent Margin Analysis Completed in Accordance with 10 CFR 50, Appendix G
ML14318A4002014-12-17017 December 2014
Vermont Yankee Nuclear and Big Rock Point - Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company (Tac Nos. MF3218 - MF3221)
ML14157A3642014-06-0505 June 2014
CDBI Request for Information
ML13353A0422013-12-16016 December 2013
NRR E-mail Capture - Request for Additional Information - Palisades - Proposed Revision to Palisades Site Emergency Plan (SEP) Emergency Response Organization (ERO) MF2321
ML13312A4232013-11-26026 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
ML13179A4622013-07-0505 July 2013
Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report
ML13051A7772013-02-19019 February 2013
Request for Additional Information, 2012 SG Inspection Report
ML12314A4222012-11-0808 November 2012
ME8074 - Request for Additional Information Regarding Replacement of Spent Fuel Pool Region I Storage Racks
ML12278A3862012-10-0404 October 2012
ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford, Request for Additional Information, Round 2, Amendment Request to Revise QA Program Manual and Staff Qualification TSs
ML12206A4042012-07-24024 July 2012
Request for Additional Information (Revised) - Palisades - SFP Rerack LAR - ME8074
ML12206A3322012-07-19019 July 2012
E-mail Combined Request for Additional Information for Several Branches of NRR for the Submittal on Palisades re-sack LAR
2024-09-20
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 20, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530
SUBJECT:
PALISADES NUCLEAR PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61a (TAC NO. MF4528)
Dear Sir or Madam:
By letter dated July 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14211A520), Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) for Palisades Nuclear Plant (PNP) to implement Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS)," also referred to as the alternate PTS rule. PNP is expected to exceed the screening criteria of the PTS rule (1 0 CFR 50.61) in August 2017, prior to the expiration of its extended operating license (2031).
Compliance with the requirements of 10 CFR 50.61 a may be met as an alternative to 10 CFR 50.61.
The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The draft questions were sent via electronic transmission on January 9, 2015, to Mr. Jeffrey Erickson, of your staff. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. A clarification telephone conference was held on January 16, 2015. As a result, modifications were made to RAI1a and 2c, as reflected in the enclosed RAI. Based on our discussions we understand that a response to the RAis will be provided by February 17, 2015.
If you have any questions, please contact me at Jennivine.Rankin@nrc.gov or (301) 415-1530.
Sincerely, nivine K. Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION ENTERGY NUCLEAR OPERATIONS. INC.
PALISADES NUCLEAR PLANT LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61 a "ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS" DOCKET NO 50-255 By letter dated July 29, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14211A520), Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) for Palisades Nuclear Plant (PNP) to implement Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS}," also referred to as the alternate PTS rule. PNP is expected to exceed the screening criteria of the PTS rule (10 CFR 50.61) in August 2017, prior to the expiration of its extended operating license (2031).
Compliance with the requirements of 10 CFR 50.61a may be met as an alternative to 10 CFR 50.61.
Based on its review of the amendment request, the U.S. Nuclear Regulatory Commission staff has determined that additional information is required to complete the review.
10 CFR 50.61a(c)(2) states, in part, the following:
Each licensee shall perform an examination and an assessment of flaws in the reactor vessel beltline as required by paragraph (e) of this section. The licensee shall verify that the requirements of paragraphs (e), (e)(1), (e)(2}, and (e)(3) of this section have been met.
Issue 1a There is no discussion of the proximity of the indications in weld 2-112B to each other.
RAI1a Provide a discussion of the proximity of the indications, according to the directions in ASME Section XI, paragraph IWA-3300(b), to demonstrate how the indications in weld 2-112B were resolved.
Issue 1b A plant-specific assessment of total plate flaws is shown in Table 8-11, "Alternate PTS Rule Allowable Number of Flaws in Plates and Forgings Scaled for Palisades" of the LAR enclosure.
In this table, all of the flaws detected during the February 2014 inservice inspection at PNP have been included, reflecting the assumption made by the licensee that all detected flaws lie in the plate rather than in the weld. The exact procedure used to determine the total plate area included in the inspection is not given. Specifically, it is not clear if the area of the weld has been included or excluded from the total plate area.
RA11b Augment Table 8-10, "Inspection Length and Area for Palisades," or otherwise revise the documentation provided in the submittal, to clarify how the total plate area was calculated and whether it includes the area of the weld.
10 CFR 50.61 a(c)(1) states, in part, the following:
Each licensee shall have projected values of RTMAx-x for each reactor vessel beltline material for the EOL fluence of the material. The assessment of RTMAx-x values must use the calculation procedures given in paragraphs (f) and (g) of this section. The assessment must specify the bases for the projected value of RTMAx-x for each reactor vessel beltline material, including the assumptions regarding future plant operation (e.g., core loading patterns, projected capacity factors); the copper (Cu), phosphorus (P), manganese (Mn), and nickel (Ni) contents; the reactor cold leg temperature (Tc); and the neutron flux and fluence values used in the calculation for each beltline material.
Issue 2a Section 4, "Plant-Specific RV Material Properties and Dimensions" of the LAR enclosure states the following:
Table 4-1 summarizes the best estimate copper, manganese, phosphorus, and nickel contents and RT NDT(U) values of the beltline and extended beltline materials for the Palisades RV. RT NDT(U) values for the Palisades RV plate materials were determined in accordance with the fracture toughness requirements in NUREG-0800, Revision 2, Branch Technical Position MTEB 5-3 (Reference 6); and the requirements of Subparagraph NB-2331 of Section Ill of the ASME B&PV Code (Reference 7). RTNDT(U) values for the weld materials are generic values for Linde 1092 and 124 weld fluxes per Reference 1.
Table 4-1, "Details of RTMAx-x Calculation Inputs for Palisades" of the LAR does not clearly identify which plates used the methods of the Branch Technical Position (BTP) 5-3 and which plates followed the requirements of 10 CFR Part 50, Appendix G, as augmented by the criteria in Section Ill of the ASME Code.
RA12a Document which method was used for each RT NDT(u) value in Table 4-1. Provide data demonstrating how each value of RT NDT(ul was calculated when a provision of BTP 5-3 was used.
Issue 2b Table 5-1, "Maximum Neutron Fluence on the RV Clad-to-Base Metal Interface for Palisades at 42.1 EFPY" of the LAR, lists that the values for the intermediate and lower longitudinal (axial) welds in the vessel are the same, 2.161 x 10+ 19 neutron/cm 2 (E >1.0 MeV), which is 63% of the peak values for the adjacent intermediate and lower shell plates. The methodology for determining the maximum fluence at the axial welds relative to the maximum fluence in the adjacent plates is not discussed in the LAR.
RAI2b Provide a discussion of how the maximum fluence for each region and component in Table 5-1 was determined from the detailed fluence information contained in References 8 and 13 listed in Section 10 of the LAR enclosure. For clarity, illustrate the axial position of the active fuel and the azimuthal position of the peak fluence values for the adjacent intermediate and lower shell plates on Figure 4-1, "Identification and Location of Beltline Region Materials for the Palisades Reactor Vessel."
Issue 2c Equations 5, 6, and 7 in 10 CFR 50.61a estimate flT 3o as a function of various input values, including neutron flux. The licensee has provided most of these input values in Tables 4-1, 5-1 and Table 5-2, "RV Cold Leg Temperature per Operating Cycle for Palisades" of the LAR enclosure. The LAR lacks neutron flux values in Table 8-1, "RTWIAX-Aw Calculation Results for Palisades at 42.1 EFPY," Table 8-2, "RTWIAX-PL Calculation Results for Palisades at 42.1 EFPY,"
and Table 8-3, "RT W1Ax-cw Calculation Results for Palisades at 42.1 EFPY" for the calculation of RT WIAX-x for the materials listed in Table 4-1.
RAI2c Provide neutron flux values on a per cycle basis for the limiting material/region (W5214 intermediate shell longitudinal weld).
Section 3.0, "Background" of the LAR indicates that PNP reactor vessel fluence was recalculated based on actual reactor operation through fuel Cycle 22 and expected fluence based on projected operations through Cycle 26. This evaluation was documented in WCAP-15353- Supplement 3- NP, Revision 0, dated June 2013. The PNP alternate PTS rule evaluation is documented in WCAP-17628- NP, Revision 1, "Alternate Pressurized Thermal Shock (PTS) Rule Evaluation for Palisades," dated June 2014. WCAP-17628-NP, Revision 1, for its reactor vessel neutron fluence values references WCAP-15353- Supplement 2- NP, Revision 0, "Palisades Reactor Pressure Vessel Fluence Evaluation," dated July 2011.
Please provide clarification for which supplement of WCAP-15353-NP is used in evaluating PNP's alternate fracture toughness requirements for protection against PTS.
- ML15016A184 **via email *via memo OFFICE NRR/DORLILPL3-1/PM NRR/DORLILPL3-1/LA NRR/DE/EVIB/BC NAME JRankin MHenderson** SRosenburg
- DATE 01/20/2015 01/16/2015 1/07/2015 OFFICE NRR/DSS/SRXB NRR/DORLILPL3-1/BC NRR/DORLILPL3-1/PM NAME CJackson
- DPelton JRankin DATE 11/18/2014 01/20/2015 01/20/2015
