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MONTHYEARML15336A0832015-09-30030 September 2015 WCAP-18030-NP, Revision 0, Criticality Safety Analysis for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. Project stage: Request ML15336A0872015-11-25025 November 2015 License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Request ML16012A0032016-01-11011 January 2016 Draft Unacceptable with Opportunity to Supplement Requested Licensing Action Email, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Draft Other ML16014A0012016-01-15015 January 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Acceptance Review ML16043A3612016-01-29029 January 2016 Supplemental Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Supplement ML16043A3892016-02-18018 February 2016 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Acceptance Review ML16155A0752016-06-0202 June 2016 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Aphb and Esgb RAIs for Spent Fuel Pool Criticality Safety Analysis LAR Project stage: RAI ML16182A5192016-06-30030 June 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Critical Safety Analysis Project stage: Response to RAI ML16197A0062016-07-14014 July 2016 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs from Snpb for LAR That Requested Revision to TSs to Incorporate Updated Criticality Safety Analysis Project stage: RAI ML16286A2402016-10-0606 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Response to RAI ML16321A0022016-11-0909 November 2016 Response to RAI, Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised Technical Specifications and Bases and WCAP-18030, Revision 1 Project stage: Response to RAI ML17062B0362017-03-0303 March 2017 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Supplement ML17144A3762017-05-24024 May 2017 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Supplement ML17145A2732017-06-15015 June 2017 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2016-11-09
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Category:E-Mail
MONTHYEARML24221A2382024-08-0606 August 2024 Change in Estimated Review Schedule and Level of Effort for Palo Verde Units 1, 2, and 3 ML24143A1112024-05-20020 May 2024 Draft 2nd Round Request for RAIs Concerning LAR to Modify LCO for TS 3.5.2, LCO for TS 3.6.5, and Surveillance Requirements 3.5.1.2 and 3.5.2.2 for TS 3.5.1 and TS 3.5.2 ML24138A1112024-05-16016 May 2024 Draft 2nd Round Request for Additional Information (Rais) Concerning License Amendment Request (LAR) to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2 ML24120A2612024-05-0101 May 2024 Email Acceptance Review of Requested Licensing Action License Renewal Commitment 23A, Alloy 600 Management Program Plan ML24123A2002024-05-0101 May 2024 (E-Mail) Draft 2nd Round Request for Additional Information Concerning License Amendment Request to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, LCO for TS 3.6.5, 3.5.1.2 and 3.5.2.2 for TS 3.5.1, a ML24114A2812024-04-19019 April 2024 Request for Additional Information (RAI-10150-R1) ML24103A1222024-04-11011 April 2024 – Acceptance of Requested Licensing Action Re_ License Amendment Request to Revise Technical Specifications 3 ML24011A1002024-01-10010 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 2024-08-06
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Text
NRR-PMDAPEm Resource From: Lingam, Siva Sent: Thursday, July 14, 2016 4:27 PM To: Thomas.N.Weber@aps.com Cc: Pascarelli, Robert; Dean, Jeremy; Wood, Kent; Michael.Dilorenzo@aps.com; Carl.Stephenson@aps.com; Watford, Margaret
Subject:
Palo Verde 1, 2, and 3 - Official RAIs from SNPB for LAR that Requested Revision to TSs to Incorporate Updated Criticality Safety Analysis (CAC Nos. MF7138, MF7139, and MF7140)
By letter dated November 25, 2015 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML15336A087), as supplemented by letters dated January 29 and June 30, 2016 (ADAMS Accession Nos. ML16043A361 and ML16182A519, respectively), Arizona Public Service Company (APS, the licensee) requested a license amendment request (LAR) to amend Facility Operating License Nos. NPF-41, NPF-51, and NPF-74, and revise the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, Technical Specifications (TSs). The proposed amendment proposes to install the NETCO-SNAP-IN neutron absorbing rack inserts into some spent fuel pool (SFP) storage rack cells coupled with six classifications of fuel by initial enrichment, burnup, and decay time in six storage configurations for criticality control. Approval of this license amendment allows the licensee to meet the effective neutron multiplication factor (k-effective or keff) criticality control requirements. The U.S. Nuclear Regulatory Commission (NRC) Nuclear Performance and Code Review Branch (SNPB) has the following official requests for additional information (RAIs). We transmitted draft RAIs to you on June 20, 2016, and we had a clarification call on July 13, 2016. Please provide your RAI responses within 60 days from the date of this e-mail, and submit the revised Westinghouse report WCAP-18030-P/NP, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3, including the affidavit, along with TS revisions within 90 days from this e-mail (as notified by APS on July 14, 2016). Your timely responses will allow the NRC staff to complete its review on schedule.
- 1. WCAP-18030-P, Revision 0, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3 (Proprietary), dated September 2015, fuel assembly reconstitution as normal condition is described as follows, Fuel assembly reconstitution is defined as either pulling damaged fuel rods [pins] out of an assembly and reinserting intact rods with less reactivity than the damaged rod, or as removing undamaged rods from a damaged assembly for insertion in a new assembly. In most cases damaged rods will be replaced with stainless steel rods. Natural uranium rods may also be used. Additional information is provided in Section 5.4.2 of WCAP-18030-P. Please provide a full description of the fuel assembly reconstitution process, which includes at least the following:
- a. The description initially seems to be saying that damaged fuel pins could be replaced with fuel pins from another assembly, but then states that damaged fuel pins would only be replaced with either stainless steel or natural uranium pins. Provide clarification.
- b. If the intention is to allow damaged fuel pins to be replaced with intact fuel pins with less reactivity from another assembly, provide the methodology that will be used to identify the replacement fuel pins. Please clarify what will replace the intact fuel pins being moved.
- c. Please clarify where in the SFP does the fuel assembly reconstitution activity take place.
- d. What is the maximum number of fuel pins that can be missing for a given reconstituted assembly at one time? Please justify any limitation or lack thereof.
- e. Please clarify whether or not there is any limitation on the number of pins in any fuel assembly that are not part of its initial construction. Please justify any limitation or lack thereof.
- f. In WCAP-18030 Section 5.4.2 it states, If a fuel assembly has a rod removed and the lattice location is left empty, that fuel assembly shall be treated as fresh fuel until the location is filled or 1
analysis is performed demonstrating that the fuel assembly is bounded by the design basis assembly at the same burnup and initial enrichment levels. Please provide the methodology that will be used to perform the analysis. Please provide the analysis that demonstrates it is acceptable to store fuel with missing fuel pins as fresh. Please justify any limitations or lack thereof.
- g. Please provide a licensing commitment to incorporate requirements, resulting from reconstitution limitations, into the licensees procedures.
- 2. The burnup requirement coefficients given in WCAP-18030, Revision 0, Tables 6-2, 6-4, 6-6, and 6-8 are derived, by a curve fitting procedure, using the results from a series of depletion calculations that correspond to a specific average fuel assembly burnup and fuel enrichment. Please provide the burnup values used to define the burnup requirement coefficients given in WCAP-18030, Revision 0, Tables 6-2, 6-4, 6-6, and 6-8 so that the validity of the coefficients can be confirmed.
- 3. What isotopes were used in the nuclear criticality safety analysis? Please justify the use of any short lived or volatile isotopes.
- 4. Please describe how the licensee will ensure future cycles are bounded by the reactor operating parameters assumed in WCAP-18030-P. Please provide a commitment to incorporate that process into the licensees procedures.
- 5. WCAP-18030-P Section 5.4.1 states, The SFP as a single system is over moderated. A single fuel assembly however, is significantly under-moderated, and reducing the interstitial [heatup] H/U ratio has a negative impact on the system keff. With respect to these statements, please provide the following:
- a. The results of the SFP temperature bias sensitivity study mentioned in WCAP-18030-P Section 5.2.3.1.8 so that it can be confirmed that all proposed storage arrays for PVNGS are over moderated.
- i. If one or more proposed storage arrays for PVNGS are not over moderated adjust the analysis accordingly or justify not making any adjustments.
- b. If the second sentence in the above quote is accurate, then several aspects of the analysis are potentially non-conservative.
- i. Justify the assumptions and/or modeling simplifications that artificially reduce the interstitial H/U ratio.
ii. Justify bias and uncertainty determinations that only consider aspects that reduce the interstitial H/U ratio.
- 6. WCAP-18030-P Section 5.4.1 also states, It has been shown in WCAP- 16541-NP, "Point Beach Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis" (Reference 13) that even storage of fuel pins in
[guide tubes] GTs has a negative reactivity impact. Similar calculations have been performed for Palo Verde previously which resulted in the same conclusion as the Point Beach study. These studies demonstrate that individual fuel assembly lattices are significantly under moderated in the SFP environment and further reducing the H/U ratio will decrease reactivity. With respect to these statements:
- a. Please provide the calculations that were performed for PVNGS.
2
- b. Point Beach uses a [Westinghouse Electric Company LLC] WEC 14x14 fuel design whereas Palo Verde uses a [Combustion Engineering] CE 16x16 fuel design. Please provide justification as to why Point Beach a valid precedent for Palo Verde?
- c. Please clarify whether or not storage of fuel pins in instrument tubes is being requested as part of this LAR.
- d. The Point Beach WCAP-16541 was not a bounding analysis for all fuel pins stored in Point Beachs WEC 14x14 guide tubes. Please describe any limitations on storing fuel pins in PVNGSs CE 16x16 guide tubes and the justification for those limitations.
- 7. In Section 5.5 of WCAP-18030-P, it is not clear how k-effective for the soluble boron cases was calculated. The limiting accident isnt necessarily the one with the largest reactivity increase, but rather the one which requires the most soluble boron to offset the reactivity increase. A storage array with a lower soluble boron worth could take more soluble boron to offset the reactivity increase, even with a smaller reactivity increase. Please demonstrate that the array configuration selected in determining the minimum soluble boron requirements corresponds to the limiting configuration.
- a. The values in Note 2 of Table 5-12 and Section 5.2.3.1.9 do not agree. Please provide clarification on this apparent discrepancy.
- 8. Section 5.2.3.2 of WCAP-18030-P makes reference to a study that Westinghouse performed to support its treatment of biases and uncertainties. Please provide the study or reference where the study has previously been submitted to the NRC.
- 9. The uncertainty in the SCALE 6.1.2 validation was performed on the uncertainty of the mean instead of the uncertainty of the population, which is inconsistent with NUREG/CR-6698, Guide for Validation of Nuclear Criticality Safety Calculated Methodology, as referenced. Please revise the SCALE 6.1.2 validation to include the uncertainty of the population.
- a. Please provide Tables A-3, A-4, A-5, A-6, and A-7 in spreadsheet format so that the NRC can perform confirmatory analysis.
- 10. Do the fuel assembly grids expand over the course of their utilization in the reactor? If they do expand, how does this affect the nuclear criticality safety analysis for the SFP?
- 11. Section 5.2.3.1.1 of WCAP-18030-P discusses the manufacturing tolerances. The information provided in Figures 5-2 and 5-3 appears to be too limited to support the conclusions drawn from them. With respect to Figures 5-2 and 5-3, please provide the following:
- a. What is the source of the information presented in Figures 5-2 and 5-3? Please justify its applicability for PVNGS.
- b. Please justify the use of the information under full and optimum moderation scenarios for new fuel storage.
- c. Please justify not applying an instrument tube uncertainty.
Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL4-1)
Palo Verde Nuclear Generating Station 3
Location: O8-D5; Mail Stop: O8-B3 Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov 4
Hearing Identifier: NRR_PMDA Email Number: 2945 Mail Envelope Properties (Siva.Lingam@nrc.gov20160714162600)
Subject:
Palo Verde 1, 2, and 3 - Official RAIs from SNPB for LAR that Requested Revision to TSs to Incorporate Updated Criticality Safety Analysis (CAC Nos. MF7138, MF7139, and MF7140)
Sent Date: 7/14/2016 4:26:54 PM Received Date: 7/14/2016 4:26:00 PM From: Lingam, Siva Created By: Siva.Lingam@nrc.gov Recipients:
"Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>
Tracking Status: None "Dean, Jeremy" <Jeremy.Dean@nrc.gov>
Tracking Status: None "Wood, Kent" <Kent.Wood@nrc.gov>
Tracking Status: None "Michael.Dilorenzo@aps.com" <Michael.Dilorenzo@aps.com>
Tracking Status: None "Carl.Stephenson@aps.com" <Carl.Stephenson@aps.com>
Tracking Status: None "Watford, Margaret" <Margaret.Watford@nrc.gov>
Tracking Status: None "Thomas.N.Weber@aps.com" <Thomas.N.Weber@aps.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 10296 7/14/2016 4:26:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: