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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
[Table view] |
Text
NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Wednesday, November 20, 2013 12:47 PM To: Robert.Roehler@aps.com Cc: Thomas.N.Weber@aps.com; Burkhardt, Janet; George, Andrea; Ronald.Barnes@aps.com
Subject:
Request for Additional Information #2: Relief Request regarding axial flaw indications (MF3051)
Attachments: Palo Verde 3 BMI RAI#2.docx Mr. Roehler, By letter dated November 8, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13317A070), as supplemented November 18, 2013 (ADAMS Accession No. ML13323A763),
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 20, 2013. It was agreed that a response to these RAIs would be provided by November 20, 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.
- Thanks, Jennie Jennie Rankin, Project Manager Palo Verde Nuclear Generating Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1
Hearing Identifier: NRR_PMDA Email Number: 927 Mail Envelope Properties (Jennivine.Rankin@nrc.gov20131120124600)
Subject:
Request for Additional Information #2: Relief Request regarding axial flaw indications (MF3051)
Sent Date: 11/20/2013 12:46:35 PM Received Date: 11/20/2013 12:46:00 PM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:
"Thomas.N.Weber@aps.com" <Thomas.N.Weber@aps.com>
Tracking Status: None "Burkhardt, Janet" <Janet.Burkhardt@nrc.gov>
Tracking Status: None "George, Andrea" <Andrea.George@nrc.gov>
Tracking Status: None "Ronald.Barnes@aps.com" <Ronald.Barnes@aps.com>
Tracking Status: None "Robert.Roehler@aps.com" <Robert.Roehler@aps.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1371 11/20/2013 12:46:00 PM Palo Verde 3 BMI RAI#2.docx 31001 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION #2 THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RAI RESPONSES FOR 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
Your response to RAI-2 dated November 18, 2013, stated that, The maximum faulted condition, Loss of Secondary Pressure [LSP] stresses, derived in Attachment 1 to this enclosure, occur at about 118 seconds into the transient (at the maximum through-wall temperature gradient) when the cold leg temperature is 344 °F and the pressure is less than 300 psia. It is therefore conservative to add the maximum thermal stresses for this transient to the SS [steady state]
pressure stresses. Please confirm that by adding the stresses under the SS condition to the stresses under the LSP condition for the SS + LSP condition, you basically assumed that the pressure will be at 2235 psig at any time during the LSP and this is the source of conservatism that you mentioned above in the quote. Please clarify whether there is any other conservatism in the stresses under the SS + LSP condition.
RAI-2
Reference 7 of Attachment 2 to Relief Request 51 dated November 8, 2013, was provided as part of your response to RAI-4 dated November 18, 2013. However, it is not clear which stresses in Reference 7 were used in this application. Please indicate the Table number in Reference 7 from which the stresses were used to calculate the stress coefficients under the SS condition in Table 6-1 of Attachment 2 to Relief Request 51.
RAI-3
Your response to RAI-5 dated November 18, 2013, stated that, The parameters used to calculate the CD [cooldown] condition used the same total stresses as defined for the SS condition above and included a cooldown transient of 100°F/hour. Considering that the stresses under the CD condition in Table 4-3 of Attachment 2 to Relief Request 51 are much less than the stresses under the SS condition, the NRC staff still thinks that the CD condition are for thermal stresses only.
1
Please confirm that by adding the stresses under the SS condition to the stresses under the CD condition for the SS + CD condition, you basically assumed that the pressure will be at 2235 psig at any time during CD and this is one source of extra conservatism. Please clarify whether there is any other conservatism in the stresses under the SS + CD condition.
RAI-4
Your response to RAI-6 dated November 18, 2013, indicated that the J-R curve based on NUREG-0744, Volume 2, Revision 1, Resolution of the Task A-11 Reactor Vessel Materials Toughness Safety Issue, is significantly different from that based on Regulatory Guide (RG) 1.161, Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 FT-LB. As a result, you used the safety factors associated with RG 1.161 to perform the elastic plastic fracture mechanics (EPFM) analysis. The required safety factors for detected flaws (ASME Code) are different from those for postulated flaws (RG 1.161). To avoid identifying the causes for the significant difference between the J-R curves based on the two sources, which may be time consuming, please take out the extra conservatism associated with the stresses under the SS + CD condition (RAI-3) and perform the EPFM analysis using the safety factors for detected flaws.
2
