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Category:E-Mail
MONTHYEARML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23243B0082023-08-31031 August 2023 NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX) ML23233A0132023-08-18018 August 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23220A0512023-08-0303 August 2023 NRR E-mail Capture - Re Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 22 ML23202A0162023-07-20020 July 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Revise TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23143A1332023-05-23023 May 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Revising TS 3.3.11 to Adopt TSTF-266-A, Rev. 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls ML23130A0132023-05-10010 May 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Authorized Use of Mururoa Supplied Air Suits (Models V4F1 and MTH2) Pursuant to 10 CFR 20.1703 and 10 CFR 20.1705 ML23017A0932023-01-17017 January 2023 NRR E-mail Capture - Palo Verde - Acceptance of License Amendment Request Regarding Adoption of TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable (L-2022-LLA-0181) ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22173A0682022-06-17017 June 2022 Email Concurrence on SE Input for Columbia Pltr LAR ML22167A1872022-06-16016 June 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Revised Acceptance Review of LAR to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues ML22136A0922022-05-16016 May 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Adopt TSTF-487-A, Revision 1, Relocate DNB Parameters to the COLR ML22075A1902022-03-16016 March 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues ML22055A5842022-02-24024 February 2022 NRR E-mail Capture - Palo Verde, Unit 3 - Final RAIs for 22nd Refueling Outage (Spring 2021) Steam Generator Tube Inservice Inspection Report ML22034A0132022-02-0202 February 2022 NRR E-mail Capture - Palo Verde, Unit 2 - Verbal Approval of RR-69 to Extend Containment Tendon Inspection from 2/8/22 to 6/8/22 ML22032A0312022-01-31031 January 2022 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for an Exemption Regarding Elimination of Dafas Using RIPE Process ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information ML21333A1982021-11-19019 November 2021 NRC Review of PVNGS Training Needs Analysis and Training Required by Condition I of the Confirmatory Order EA-20-054 ML21306A1882021-10-18018 October 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Second Pre-submittal Meeting for the Proposed Exemption to Eliminate Dafas Using RIPE Process ML21272A0592021-09-28028 September 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 21 ML21264A1352021-09-17017 September 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Acceptance Review of LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21237A0762021-08-25025 August 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML21228A0082021-08-16016 August 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of an LAR for Administrative Changes to Technical Specifications ML21228A1042021-08-12012 August 2021 RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (EPID L-2021-LLR-0050) (Email) ML21237A5172021-08-10010 August 2021 Email to PV Licensee and Palo Verde Nuclear Generating Station, Units 1, 2 and 3 - Notification of Inspection of the Licensees Implementation Industry Initiative Associated with the Open Phase Condition (NRC Bulletin 2012-01) and Request Fo ML21160A1442021-06-0909 June 2021 NRR E-mail Capture - Palo Verde 1 and, 2 - Acceptance Review for Order Approving Transfers of Control of Licenses for Minority Interests Subject to Expiring Leases ML21154A0082021-05-26026 May 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Official RAIs for LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21146A3342021-05-14014 May 2021 ISFSI - Final Package for an Order Associated with Indirect Transfers of Control of Licenses from Pnm to Avangrid ML21132A2372021-05-12012 May 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3, and ISFSI - Final Package for an Order Associated with Indirect Transfers of Control of Licenses from Pnm to Avangrid ML21103A3632021-04-13013 April 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Indirect Transfer of Control of Licenses Pursuant to 10 CFR 50.80 and 10 CFR 72.50 ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21053A0262021-02-22022 February 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Acceptance Review of LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21043A1462021-02-11011 February 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAI for an Order Associated with Indirect License Transfer from Public Service Company of New Mexico to Avangrid, Inc ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA ML20366A1682020-12-31031 December 2020 NRR E-mail Capture - Palo Verde 1, 2, and 3, and ISFSI - Acceptance Review of an Order Associated with Indirect Transfers of Control of Licenses ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML20325A0392020-11-19019 November 2020 NRR E-mail Capture - Palo Verde 2 - Verbal Authorization of RR 66 to Extend Containment Tendon Inspection by One Year Based on 10 CFR 50.55a(Z)(2) ML20316A0162020-11-0909 November 2020 NRR E-mail Capture - Palo Verde 2 - Acceptance Review of RR 66, Request Containment Post-Tensioning System Inspection One-Time by One Year Due to COVID-19 Pandemic ML20295A4912020-10-21021 October 2020 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Associated with Adopting TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control ML20265A0982020-09-21021 September 2020 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Amendment Associated with Making Necessary Administrative Changes to Technical Specifications ML20108E9462020-04-16016 April 2020 NRR E-mail Capture - (External_Sender) Clarification to PVNGS Part 26 Exemption Request (ML20105A481) ML20091K0752020-03-31031 March 2020 NRR E-mail Capture - Palo Verde 2 - Acceptance Review of RR 65, Request for Relief from RPV Bottom Mounted Instrumentation Nozzles and a Pressurizer Surge Line Weld Overlay Examination ML20091M1992020-03-31031 March 2020 NRR E-mail Capture - Palo Verde 2 - Verbal Authorization of RR 65, Request for Relief from RPV Bottom Mounted Instrumentation Nozzles and a Pressurizer Surge Line Weld Overlay ISI Examinations ML20050C9742020-02-19019 February 2020 NRR E-mail Capture - Palo Verde 1,2, and 3 - Framatome Htp Fuel LAR and Exemption Third Audit Summary (EPIDs L-2018-LLA-0194 and L-2018-LLE-0010) 2024-01-10
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Text
NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Friday, November 15, 2013 2:47 PM To: Robert.Roehler@aps.com Cc: Thomas.N.Weber@aps.com; Ronald.Barnes@aps.com; Burkhardt, Janet
Subject:
Request for Additional Information: Relief Request regarding axial flaw indications (MF3051)
Attachments: Palo Verde 3 BMI RAI final.docx Mr. Roehler, By letter dated November 8, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13317A070), Arizona Public Service Company (APS, the licensee) submitted for U.S.
Nuclear Regulatory Commission (NRC) approval a relief request pursuant to Title 10 of the Code of Federal Regulations (CFR) 50.55a(a)(3)(i). This relief request proposes an alternative to the ASME Code requirements of Section XI related to axial flaw indications identified in the Unit 3 reactor vessel bottom mounted instrumentation nozzle.
Based on a review of the submittal, the NRC staff has determined that the following request for additional information (RAI) is required in order to complete its review. The RAIs were discussed with you on November 15, 2013. It was agreed that a response to these RAIs would be provided by November 18, 2013. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1530 or via email at jennivine.rankin@nrc.gov.
Thank you, Jennie Rankin Division of Operating Reactor Licensing 1
Hearing Identifier: NRR_PMDA Email Number: 924 Mail Envelope Properties (E85CAE0ED2FC5449B808712D77E97576B55986241C)
Subject:
Request for Additional Information: Relief Request regarding axial flaw indications (MF3051)
Sent Date: 11/15/2013 2:46:33 PM Received Date: 11/15/2013 2:46:00 PM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:
"Thomas.N.Weber@aps.com" <Thomas.N.Weber@aps.com>
Tracking Status: None "Ronald.Barnes@aps.com" <Ronald.Barnes@aps.com>
Tracking Status: None "Burkhardt, Janet" <Janet.Burkhardt@nrc.gov>
Tracking Status: None "Robert.Roehler@aps.com" <Robert.Roehler@aps.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 1160 11/15/2013 2:46:00 PM Palo Verde 3 BMI RAI final.docx 30621 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING ATTACHMENT 2, FLAW FRACTURE MECHANICS EVALUATION TO SUPPORT RESTART TO RELIEF REQUEST 51 FOR THE REMNANT FLAW IN THE J-GROOVE WELD IN THE BOTTOM MOUNTED INSTRUMENT NOZZLE NO. 3 PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 ARIZONA PUBLIC SERVICE COMPANY DOCKET NO. 50-530
RAI-1
Section 4.1 of Attachment 2 reported that the nil-ductility reference temperature (RTNDT) of -60 °F for the RPV bottom head is from Reference 1 of this Attachment. Please confirm that this value is from the Certified Material Test Report for the RPV bottom head. If not, please justify the use of this RTNDT value in this application.
RAI-2
A typical flaw evaluation in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requires consideration of emergency and faulted conditions in addition to the normal condition (e.g., Appendix A of the ASME Code,Section XI). The applied stresses for the flaw evaluation in Section 4.4 of Attachment 2 to Relief Request 51 are for the normal conditions only. Please address the flaw evaluation under the emergency and faulted conditions.
RAI-3
Appendix A to Attachment 2 documented the thermal stresses during cooldown which were obtained using a 2-dimensional axisymmetric finite element model (FEM). The NRC staff needs further clarification regarding the FEM results to gain confidence in the FEM model:
- Please confirm that the results shown in Figures A-1 to A-5 and Table A-3 are 1-dimensional, i.e., the results (temperature and stresses) are the same for all points at inner diameter (ID), outer diameter (OD), or any surface that is defined by a specific depth of the bottom head. Demonstrate that the 1-dimensional results are realistic in this application.
1
- Please confirm that the temperature difference-time plot (right figure) in Figure A-2 is a plot of the maximum thermal gradient mentioned in Paragraph A.2 Item 4. If it is not, explain the significance of this parameter. Regardless of the confirmation, please identify the location (depth) where this temperature difference-time plot was obtained and explain the physical meaning of such a unique shape of the temperature difference-time plot.
RAI-4
Section 4.4 of Attachment 2 states, Residual plus operating stresses are obtained from Reference [7]. Demonstrate that the residual stresses used in the flaw evaluation are consistent with what were approved by the NRC staff in published safety evaluations (SEs), NUREGs, or other NRC documents. If this cannot be demonstrated, please provide Reference 7 to support this review.
RAI-5
Table 4-3 of Attachment 2 presents the hoop stresses at different depths of the RPV wall for the steady state (SS), cooldown (CD), and their combined effect. The NRC staff has the following requests:
- Identify the loads that were considered in the SS condition (i.e., any of the three: pressure, steady state thermal load, and residual stresses). Repeat the similar identification for the CD condition.
- Confirm that the thermal state associated with the SS condition is the starting point of the CD condition.
- The stress pattern for the SS condition (Column 2 of Table 4-3 under SS) is very unusual.
Please provide the corresponding stress components due to pressure, thermal, and residual stresses for each position (or depth) in Table 4-3. Explain the unusual zigzag stress pattern to demonstrate that it is not caused by modeling errors.
- If residual stresses are not included in the SS condition, confirm that residual stresses are considered in the subsequent applied stress intensity factor (K) or applied J calculations (Tables 6-1 and 6-2 do not show explicitly the contribution due to residual stresses).
RAI-6
Section 4.1.4 of Attachment 2 presents the generic J-R curve used in the elastic plastic fracture mechanics (EPFM) evaluation. This J-R curve is based on the J model from Appendix D to NUREG-0744, Vol. 2, Rev. 1, Resolution of the Task A-11 Reactor Vessel Materials Toughness Safety Issue, 1982. The generic J-R curve models for various low upper-shelf RPV materials are presented in RG 1.161, Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 FT-LB, 1995. Please provide J-R curves based on both approaches to demonstrate that your J-R curve based on NUREG-0744, Vol. 2, Rev. 1 is not significantly different from the RG 1.161 model. Provide correction and reassess your final conclusion if the 2
difference is significant. Please note that the database underlying the J-R model for RPV base metals in RG 1.161 contains not just low upper-shelf energy materials.
RAI-7
Table 6-2 of Attachment 2 provides results for a number of parameters which were calculated during the EPFM evaluation. Please provide the flow stress f at the operating temperature of 565 °F and a sample calculation for the applied tearing modulus Tapp appeared in Column 9 of this table.
Note: There are no RAIs regarding Attachment 1. If there are any RAIs related to Relief Request 51 (i.e., not Attachment 1 or Attachment 2), it will be provided to the licensee on Monday, November 18, 2013.
3