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| {{#Wiki_filter:From: William Orders Sent: Friday, May 1, 2024 To: Michael.Dilorenzo@aps.com | | {{#Wiki_filter:From: William Orders Sent: Friday, May 1, 2024 To: Michael.Dilorenzo@aps.com |
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| ==Subject:== | | ==Subject:== |
| 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, "Safety Injection Tanks (SIT) - Shutdown," LCO for TS 3.6.5, "Containment Air Temperature," and Surveillance Requirements (SRs) 3.5.1.2 and 3.5.2.2 for TS 3.5.1, "Safety Injection Tanks (SITs) - Operating," and TS 3.5.2, respectively. | | 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, "Safety Injection Tanks (SIT) - Shutdown," LCO for TS 3.6.5, "Containment Air Temperature," and Surveillance Requirements (SRs) 3.5.1.2 and 3.5.2.2 for TS 3.5.1, "Safety Injection Tanks (SITs) - Operating," and TS 3.5.2, respectively. |
| Mr. Dilorenzo, | | Mr. Dilorenzo, |
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| By {{letter dated|date=June 29, 2023|text=letter dated June 29, 2023}} (Reference 1), as supplemented by {{letter dated|date=March 6, 2024|text=letter dated March 6, 2024}} (Reference 2), Arizona Public Service Company (the licensee) submitted a license amendment request (LAR) to modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, "Safety Injection Tanks (SIT) - Shutdown," LCO for TS 3.6.5, "Containment Air Temperature," and Surveillance Requirements (SRs) 3.5.1.2 and 3.5.2.2 for TS 3.5.1, "Safety Injection Tanks (SITs) - Operating," and TS 3.5.2, respectively. The U.S. Nuclear Regulatory Commission (NRC) staff have reviewed the licensees submittals and concluded that additional information, as discussed below, is required to complete its review: | | By {{letter dated|date=June 29, 2023|text=letter dated June 29, 2023}} (Reference 1), as supplemented by {{letter dated|date=March 6, 2024|text=letter dated March 6, 2024}} (Reference 2), Arizona Public Service Company (the licensee) submitted a license amendment request (LAR) to modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, "Safety Injection Tanks (SIT) - Shutdown," LCO for TS 3.6.5, "Containment Air Temperature," and Surveillance Requirements (SRs) 3.5.1.2 and 3.5.2.2 for TS 3.5.1, "Safety Injection Tanks (SITs) - Operating," and TS 3.5.2, respectively. The U.S. Nuclear Regulatory Commission (NRC) staff have reviewed the licensees submittals and concluded that additional information, as discussed below, is required to complete its review: |
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| === | | === |
| Background=== | | Background=== |
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| Regulatory Basis: | | Regulatory Basis: |
| The following 10 CFR Part 50, Appendix A, General Design Criteria (GDC) are applicable: | | The following 10 CFR Part 50, Appendix A, General Design Criteria (GDC) are applicable: |
| * GDC 16, Containment design, as it relates to providing a reactor containm ent and associated systems to establish an essentially leak -tight barrier against the uncontroll ed release of radioactivity to the environment and to assure that the containment desi gn conditions important to safety are not exceeded for as long as postulated acci dent conditions require. | | * GDC 16, Containment design, as it relates to providing a reactor containm ent and associated systems to establish an essentially leak -tight barrier against the uncontroll ed release of radioactivity to the environment and to assure that the containment desi gn conditions important to safety are not exceeded for as long as postulated acci dent conditions require. |
| * GDC 38, Containment heat removal, as it relates to providing a system to remov e heat from the reactor containment whose safety function is to reduce rapidly, consistent wi th the functioning of other associated systems, the containment pressure and temperatur e following any loss-of- coolant accident and maintain them at acceptably low levels. | | * GDC 38, Containment heat removal, as it relates to providing a system to remov e heat from the reactor containment whose safety function is to reduce rapidly, consistent wi th the functioning of other associated systems, the containment pressure and temperatur e following any loss-of-coolant accident and maintain them at acceptably low levels. |
| * GDC 50, Containment design basis, as it relates to designing the reactor containm ent structure, including access openings, penetrations, and the containment heat removal system so that the containment structure and its internal compartments can accomm odate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss -of-coolant accident. | | * GDC 50, Containment design basis, as it relates to designing the reactor containm ent structure, including access openings, penetrations, and the containment heat removal system so that the containment structure and its internal compartments can accomm odate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss -of-coolant accident. |
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| Issue | | Issue |
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| Table 6.2.1- 3 of the Palo Verde Nuclear Generating Station (PVNGS) updated final safety analysis report (UFSAR) states the following principal containment design parameters (Reference 3): | | Table 6.2.1-3 of the Palo Verde Nuclear Generating Station (PVNGS) updated final safety analysis report (UFSAR) states the following principal containment design parameters (Reference 3): |
| * Internal Design Pressure, psig 60.0 | | * Internal Design Pressure, psig 60.0 |
| * Design temperature, °F | | * Design temperature, °F |
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| o High mean during normal operation 120.0 | | o High mean during normal operation 120.0 |
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| o Maximum, DBA 300.0 [containment wall design temperature] | | o Maximum, DBA 300.0 [containment wall design temperature] |
| UFSAR Table 6.2.1-9 summarizes the calculated temperatures and pressures as a result of a loss of coolant accident (LOCA) and main steam line break (MSLB) and states the peak pressure is 72.05 psia (57.85 psig) (based on LOCA), and a peak containment vapor temperature of 405.5°F (based on MSLB). | | UFSAR Table 6.2.1-9 summarizes the calculated temperatures and pressures as a result of a loss of coolant accident (LOCA) and main steam line break (MSLB) and states the peak pressure is 72.05 psia (57.85 psig) (based on LOCA), and a peak containment vapor temperature of 405.5°F (based on MSLB). |
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| The licensee proposes to change TS LCO 3.6.5 from its existing value of 117°F to the design analytical value of 120°F. To justify, in the {{letter dated|date=March 6, 2024|text=letter dated March 6, 2024}} (Reference 2), the licensee stated: | | The licensee proposes to change TS LCO 3.6.5 from its existing value of 117°F to the design analytical value of 120°F. To justify, in the {{letter dated|date=March 6, 2024|text=letter dated March 6, 2024}} (Reference 2), the licensee stated: |
| * PVNGS Technical Specifications contain both the LCO limit and Surveillanc e Requirement (SR) which is implemented by the Control Room Operators in accordanc e with surveillance testing (ST). The ST procedures reflect the total loop uncertainty calculations which specifies the indicated value to provide reasonable assurance that the analytical limit is not exceeded. Therefore, the TS value of 120°F does not account for instrument uncertainty and instead it is controlled within the licensee-controlled TS Bases and surveillance procedures, pursuant to 10 CFR 50.59. | | * PVNGS Technical Specifications contain both the LCO limit and Surveillanc e Requirement (SR) which is implemented by the Control Room Operators in accordanc e with surveillance testing (ST). The ST procedures reflect the total loop uncertainty calculations which specifies the indicated value to provide reasonable assurance that the analytical limit is not exceeded. Therefore, the TS value of 120°F does not account for instrument uncertainty and instead it is controlled within the licensee-controlled TS Bases and surveillance procedures, pursuant to 10 CFR 50.59. |
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| Requested Information | | Requested Information |
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| REFERENCES | | REFERENCES |
| : 1. Letter from APS to NRC, Palo Verde Nuclear Generating Station Units 1, 2, and 3, Dock et Nos. STN 50-528, 50-529, and 50-530, Renewed Operating License Number NPF- 41, NPF-51, and NPF-74 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (SITs) - Operating, TS 3.5.2, Safety Injection Tanks (SITs) - Shutdown, and TS 3.6.5, Containment Air Temperature. June 29, 2023, ADAMS Accession N o. | | : 1. Letter from APS to NRC, Palo Verde Nuclear Generating Station Units 1, 2, and 3, Dock et Nos. STN 50-528, 50-529, and 50-530, Renewed Operating License Number NPF-41, NPF-51, and NPF-74 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (SITs) - Operating, TS 3.5.2, Safety Injection Tanks (SITs) - Shutdown, and TS 3.6.5, Containment Air Temperature. June 29, 2023, ADAMS Accession N o. |
| ML23180A222 | | ML23180A222 |
| : 2. Letter from APS to NRC, Palo Verde Nuclear Generating Station Units 1, 2, and 3, Dock et Nos. STN 50-528, 50-529, and 50-530, Renewed Operating License Number NPF- 41, NPF-51, and NPF-74, Response to Request for Additional Information to Revis e Technical Specifications (TS) 3.5.1, Safety Injection Tanks (SITs) - Operating, TS 3.5.2, Safety Injection Tanks (SITs) - Shutdown, and TS 3.6.5, Containment Air Temperatur e, March 6, 2024, ADAMS Accession No. ML24066A047 | | : 2. Letter from APS to NRC, Palo Verde Nuclear Generating Station Units 1, 2, and 3, Dock et Nos. STN 50-528, 50-529, and 50-530, Renewed Operating License Number NPF-41, NPF-51, and NPF-74, Response to Request for Additional Information to Revis e Technical Specifications (TS) 3.5.1, Safety Injection Tanks (SITs) - Operating, TS 3.5.2, Safety Injection Tanks (SITs) - Shutdown, and TS 3.6.5, Containment Air Temperatur e, March 6, 2024, ADAMS Accession No. ML24066A047 |
| : 3. PVNGS UFSAR, Revision 22, ADAMS Accession No. ML23181A159 | | : 3. PVNGS UFSAR, Revision 22, ADAMS Accession No. ML23181A159 |
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| This draft RAI is provided to allow you the opportunity to request a clarification call. | | This draft RAI is provided to allow you the opportunity to request a clarification call. |
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| William Orders (301) 415-3329}} | | William Orders (301) 415-3329}} |
Letter Sequence Draft RAI |
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MONTHYEARML23180A2222023-06-29029 June 2023
Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature
Project stage: Request
ML23181A1662023-06-30030 June 2023
Enclosure 2 - Palo Verde Nuclear Generating Station Units 1, 2, and 3, Revision 22 to Updated Final Safety Analysis Report, Redacted Per RIS 2015-17
Project stage: Request
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
Project stage: Acceptance Review
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
Project stage: RAI
ML24066A0472024-03-0606 March 2024
Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS
Project stage: Response to RAI
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
Project stage: Draft RAI
ML24170A9962024-06-18018 June 2024
Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a
Project stage: Request
ML24221A2382024-08-0606 August 2024
Change in Estimated Review Schedule and Level of Effort for Palo Verde Units 1, 2, and 3
Project stage: Other
ML24208A0612024-08-20020 August 2024
Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5
Project stage: Approval
2024-03-06
[Table View] |
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Category:E-Mail
MONTHYEARML24297A6212024-10-22022 October 2024
Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300
ML24267A2172024-09-23023 September 2024
(E-Mail) Palo Verde Nuclear Generating Station Units 1, 2, and 3 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code
ML24257A1012024-09-11011 September 2024
Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components
ML24248A2632024-09-0404 September 2024
Acceptance Review of Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Relief Request (RR) No. 71: Re?Submittal of RR?30
ML24242A2812024-08-26026 August 2024
RR72 Acceptance 08/27/24 - La Jr
ML24221A2382024-08-0606 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
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
ML24120A2612024-05-0101 May 2024
Email Acceptance Review of Requested Licensing Action License Renewal Commitment 23A, Alloy 600 Management Program Plan
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
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24297A6212024-10-22022 October 2024
Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300
ML24257A1012024-09-11011 September 2024
Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components
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
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)
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
ML23031A3392023-01-31031 January 2023
In-service Inspection Request for Information
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
ML22272A3252022-09-29029 September 2022
Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information
ML22209A1752022-07-28028 July 2022
Inservice Inspection Request for Information
ML22187A2632022-07-0606 July 2022
Notification of Inspection (NRC IR 05000528/2022004, 05000529/2022004 and 05000530/2022004) and Request for Information
ML22067A2292022-03-0202 March 2022
Inservice Inspection Inspection PWR Request for Information
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
ML22035A3302022-02-10010 February 2022
Requests for Confirmation of Information for Exemption to Delete Diverse Auxiliary Feedwater Actuation System Based on Risk-Informed Process for Evaluations
ML22025A4012022-01-0303 January 2022
March 2022 Emergency Preparedness Program Inspection - Request for Information
ML21245A2222021-09-0101 September 2021
Request for Information
ML21200A2392021-07-20020 July 2021
Docs Request AC - AA August 2021
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)
ML21064A2372021-03-0303 March 2021
ISI Request for Information Rls
ML21042B9692021-02-18018 February 2021
Notification of NRC Design Bases Assurance Inspection and Initial Request for Information
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
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ML20227A0992020-08-14014 August 2020
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ML20118D1362020-04-28028 April 2020
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2024-09-11
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Text
From: William Orders Sent: Friday, May 1, 2024 To: Michael.Dilorenzo@aps.com
Subject:
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, "Safety Injection Tanks (SIT) - Shutdown," LCO for TS 3.6.5, "Containment Air Temperature," and Surveillance Requirements (SRs) 3.5.1.2 and 3.5.2.2 for TS 3.5.1, "Safety Injection Tanks (SITs) - Operating," and TS 3.5.2, respectively.
Mr. Dilorenzo,
By letter dated June 29, 2023 (Reference 1), as supplemented by letter dated March 6, 2024 (Reference 2), Arizona Public Service Company (the licensee) submitted a license amendment request (LAR) to modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, "Safety Injection Tanks (SIT) - Shutdown," LCO for TS 3.6.5, "Containment Air Temperature," and Surveillance Requirements (SRs) 3.5.1.2 and 3.5.2.2 for TS 3.5.1, "Safety Injection Tanks (SITs) - Operating," and TS 3.5.2, respectively. The U.S. Nuclear Regulatory Commission (NRC) staff have reviewed the licensees submittals and concluded that additional information, as discussed below, is required to complete its review:
=
Background===
Regulatory Basis:
The following 10 CFR Part 50, Appendix A, General Design Criteria (GDC) are applicable:
- GDC 16, Containment design, as it relates to providing a reactor containm ent and associated systems to establish an essentially leak -tight barrier against the uncontroll ed release of radioactivity to the environment and to assure that the containment desi gn conditions important to safety are not exceeded for as long as postulated acci dent conditions require.
- GDC 38, Containment heat removal, as it relates to providing a system to remov e heat from the reactor containment whose safety function is to reduce rapidly, consistent wi th the functioning of other associated systems, the containment pressure and temperatur e following any loss-of-coolant accident and maintain them at acceptably low levels.
- GDC 50, Containment design basis, as it relates to designing the reactor containm ent structure, including access openings, penetrations, and the containment heat removal system so that the containment structure and its internal compartments can accomm odate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss -of-coolant accident.
Issue
Table 6.2.1-3 of the Palo Verde Nuclear Generating Station (PVNGS) updated final safety analysis report (UFSAR) states the following principal containment design parameters (Reference 3):
- Internal Design Pressure, psig 60.0
o High mean during normal operation 120.0
o Maximum, DBA 300.0 [containment wall design temperature]
UFSAR Table 6.2.1-9 summarizes the calculated temperatures and pressures as a result of a loss of coolant accident (LOCA) and main steam line break (MSLB) and states the peak pressure is 72.05 psia (57.85 psig) (based on LOCA), and a peak containment vapor temperature of 405.5°F (based on MSLB).
TS, Section 5.5.16 states the containment integrated leak rate test (ILRT) pressure Pa as 58 psig.
The licensee proposes to change TS LCO 3.6.5 from its existing value of 117°F to the design analytical value of 120°F. To justify, in the letter dated March 6, 2024 (Reference 2), the licensee stated:
- PVNGS Technical Specifications contain both the LCO limit and Surveillanc e Requirement (SR) which is implemented by the Control Room Operators in accordanc e with surveillance testing (ST). The ST procedures reflect the total loop uncertainty calculations which specifies the indicated value to provide reasonable assurance that the analytical limit is not exceeded. Therefore, the TS value of 120°F does not account for instrument uncertainty and instead it is controlled within the licensee-controlled TS Bases and surveillance procedures, pursuant to 10 CFR 50.59.
Requested Information
Provide the results of a sensitivity analysis based on an initial containment temperature of 120°F (plus instrument uncertainty) while the other input parameters and assumptions remain the same as in the analysis of record to demonstrate the impact that variations in instrument uncertainty assumptions have on the ability of containment to perform as designed during a LOCA and MSLB. Include the impact on the following:
- Maximum containment vapor temperature
- Maximum containment pressure
- Maximum containment wall temperature
REFERENCES
- 1. Letter from APS to NRC, Palo Verde Nuclear Generating Station Units 1, 2, and 3, Dock et Nos. STN 50-528, 50-529, and 50-530, Renewed Operating License Number NPF-41, NPF-51, and NPF-74 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (SITs) - Operating, TS 3.5.2, Safety Injection Tanks (SITs) - Shutdown, and TS 3.6.5, Containment Air Temperature. June 29, 2023, ADAMS Accession N o.
ML23180A222
- 2. Letter from APS to NRC, Palo Verde Nuclear Generating Station Units 1, 2, and 3, Dock et Nos. STN 50-528, 50-529, and 50-530, Renewed Operating License Number NPF-41, NPF-51, and NPF-74, Response to Request for Additional Information to Revis e Technical Specifications (TS) 3.5.1, Safety Injection Tanks (SITs) - Operating, TS 3.5.2, Safety Injection Tanks (SITs) - Shutdown, and TS 3.6.5, Containment Air Temperatur e, March 6, 2024, ADAMS Accession No. ML24066A047
- 3. PVNGS UFSAR, Revision 22, ADAMS Accession No. ML23181A159
This draft RAI is provided to allow you the opportunity to request a clarification call.
William Orders (301) 415-3329
