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| | number = ML12341A129 | | | number = ML12341A129 |
| | issue date = 12/05/2012 | | | issue date = 12/05/2012 |
| | title = Palo Verde, Units 1, 2, and 3 - E-mail, Draft Request for Additional Information, Round 2, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160/ME81 | | | title = E-mail, Draft Request for Additional Information, Round 2, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160/ME8162) |
| | author name = Gibson L K | | | author name = Gibson L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Roehler R | | | addressee name = Roehler R |
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| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
| | license number = NPF-041, NPF-051, NPF-074 | | | license number = NPF-041, NPF-051, NPF-074 |
| | contact person = Gibson L K | | | contact person = Gibson L |
| | case reference number = TAC ME8160, TAC ME8161, TAC ME8162 | | | case reference number = TAC ME8160, TAC ME8161, TAC ME8162 |
| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
| | page count = 3 | | | page count = 3 |
| | project = TAC:ME8160, TAC:ME8160, TAC:ME8161, TAC:ME8162 | | | project = TAC:ME8160, TAC:ME8161, TAC:ME8162 |
| | stage = RAI | | | stage = Draft RAI |
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| =Text= | | =Text= |
| {{#Wiki_filter:Lent. Susan From: Gibson, Lauren Sent: Wednesday, December 05, 201211:13AM To: Robert. Roehler@aps.com Subject: Draft Request for Additional Information Related to LAR to remove the term CORE ALTERATION from Tech Specs (ME8160, ME8161, and ME8162) Attachments: Draft RAls ME8160, 1, 2.docx Rob, a dated March 8, 2012, and supplemented by letter dated October 11, 2012) Arizona Public Service Co, (APS. the licensee) submitted a license amendment (LAR) for Palo Verde Nuclear Generating Station (Agencywide Documents Access Management System (ADAMS) /"ccession No. ML 12076A045 and ML12286A330, respectively), The proposed amendment would the use of the term CORE ALTERATION from the technical specifications. The U.S, Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the additional information identified in the attachment is needed in order for the NRC staff to complete review. Please contact me jf you would like to have a clarifying conference call. Thank you, Lauren Lauren K Gibson Project Manager Columbia Generating Station Palo Verde Generating Station Nuclear of Operating Reactor 1 DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REMOVAL OF "CORE ALTERATION" FROM TECHNICAL SPECIFICATIONS (TSS) INCLUDING TS 3.9.2. "NUCLEAR INSTRUMENTATION" FOR PALO VERDE NUCLEAR GENERATING STATION (PVNGS), UNITS 1. 2. AND 3 DOCKET NOS. 50-528. 50-529 AND 50-530 Request for Additional Information By letter dated March 8, 2012, supplemented by a letter dated October 11,2012, Arizona Power Service Company (APS), the licensee for Palo Verde Nuclear Generating Station (PVNGS), Units 1,2, and 3, proposed to remove "CORE ALTERATION" from Technical Specifications (TSs) including TS 3.9.2, "Nuclear Instrumentation". The NRC staff has reviewed the submitted information and has determined that the following additional information is required to complete the review. For Palo Verde Nuclear Generating Station (PVNGS), current Technical Specification (TS) 3.9.2 (for Mode 6), "Nuclear Instrumentation", requires that (1) Core Alterations be suspended and (2) positive reactivity activities be terminated if the required source range nuclear instrumentation is determined to be inoperable. The licensee proposes to remove the required action of suspending Core Alterations from the TS 3.9.2 while maintaining the required action of suspending positive reactivity activities. At PVNGS, the source range monitors (SRMs) are used during refueling operations monitor the core reactivity conditions. The SRMs provide a signal to operator unexpected changes in core reactivity such as a boron dilution event and a fuel assembly event. These detectors are located external to the reactor vessel detect neutron leaking from the core. The licensee stated in References 1 and 2 that the conditions that one SMR is inoperable, the required action of suspending reactivity additions is sufficient to preclude an accident Based on the current definitions in TS 1.1, "CORE ALTERATION shall be the or manipulation of any fuel, sources, or reactivity control components [excluding assemblies (CEAs) withdrawal into the upper guide structure], within the reactor with vessel head removed and fuel in the vessel. Suspension of CORE shall not preclude completion of movement of a component to a safe With the removal of the TS required action of suspending CORE ALTERATION, the TS 3.9.2 restriction is the required action to suspend positive reactivity Since the withdrawal of fuel assemblies from the core may not contribute to the of positive reactivity to the core, it is not prohibited by the proposed TS The NRC staff is concerned that the SRM could be decoupled from the nuclear when the fuel assemblies are withdrawn out of the core. For example, the withdrawal fuel assemblies could result in a condition where fuel assemblies reside in a half of core opposite the operable SRM. Another example is removal of a source assembly from a decayed core. Under these conditions, the remaining operable SRM may not be able to effectively detect the neutron reactivity. Thus, there may not be an SRM to adequately detect the occurrence of the boron dilution or misloaded fuel assembly event, resulting in an unanalyzed condition. Please address whether the operable SRM could be decoupled from the neutron fluxes during a fuel assembly withdrawal in Mode 6. If the SRM-neutron decouple is determined to be a non-credible phenomenon, provide rationale in support of the determination. If the SRM-neutron decouple is determined to be a credible phenomenon, justify the proposed change to remove CORE ALTERATION from the TS. The justification should include information addressing the compliance with: Acceptance criterion in Standard Review Plan (SRP) 15.6.4 that requires that at least 30 minutes is available from the time the operator is made aware of the unplanned boron dilution event to the time a total loss of shutdown margin (criticality) occurs during refueling (Mode 6), and Guidance of Item 4 on page 15.4.6-8 of SPR 15.6.4 (Revision 2 dated March 2007) that specifies that redundant alarms should be available for the operator to identify and terminate the unplanned boron dilution within the required time The NRC staff is concerned that without a prior criticality analysis, it could be difficult to tell whether shuffling an assembly (change the core geometry) causes a positive or negative reactivity change. By restricting core alteration, rather just positive reactivity addition, current TS 3.9.2 explicitly delineates components that cannot be moved, and this TS restriction of core alteration could prevent the operator from misjudging the reactivity of the fuel assembly movement. Please describe how the licensee determines whether shuffling an assembly would cause a positive or negative reactivity change. | | {{#Wiki_filter:Lent. Susan From: Gibson, Lauren Sent: Wednesday, December 05, 201211:13AM To: Robert. Roehler@aps.com |
| }} | | |
| | ==Subject:== |
| | Draft Request for Additional Information Related to LAR to remove the term CORE ALTERATION from Tech Specs (ME8160, ME8161, and ME8162) |
| | Attachments: Draft RAls ME8160, 1, 2.docx |
| | : Rob, a dated March 8, 2012, and supplemented by letter dated October 11, 2012) Arizona Public Service Co, (APS. the licensee) submitted a license amendment (LAR) for Palo Verde Nuclear Generating Station (Agencywide Documents Access Management System (ADAMS) /"ccession No. ML12076A045 and ML12286A330, respectively), The proposed amendment would the use of the term CORE ALTERATION from the technical specifications. |
| | The U.S, Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the additional information identified in the attachment is needed in order for the NRC staff to complete review. |
| | Please contact me jf you would like to have a clarifying conference call. |
| | Thank you, Lauren Lauren K Gibson Project Manager Columbia Generating Station Palo Verde Generating Station of Operating Reactor Licensing Nuclear Commission 1 |
| | |
| | DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REMOVAL OF "CORE ALTERATION" FROM TECHNICAL SPECIFICATIONS (TSS) INCLUDING TS 3.9.2. "NUCLEAR INSTRUMENTATION" FOR PALO VERDE NUCLEAR GENERATING STATION (PVNGS), UNITS 1. 2. AND 3 DOCKET NOS. 50-528. 50-529 AND 50-530 Request for Additional Information By letter dated March 8, 2012, supplemented by a letter dated October 11,2012, Arizona Power Service Company (APS), the licensee for Palo Verde Nuclear Generating Station (PVNGS), |
| | Units 1,2, and 3, proposed to remove "CORE ALTERATION" from Technical Specifications (TSs) including TS 3.9.2, "Nuclear Instrumentation". |
| | The NRC staff has reviewed the submitted information and has determined that the following additional information is required to complete the review. |
| | : 1. For Palo Verde Nuclear Generating Station (PVNGS), current Technical Specification (TS) 3.9.2 (for Mode 6), "Nuclear Instrumentation", requires that (1) Core Alterations be suspended and (2) positive reactivity activities be terminated if the required source range nuclear instrumentation is determined to be inoperable. The licensee proposes to remove the required action of suspending Core Alterations from the TS 3.9.2 while maintaining the required action of suspending positive reactivity activities. |
| | At PVNGS, the source range monitors (SRMs) are used during refueling operations to monitor the core reactivity conditions. The SRMs provide a signal to operator of unexpected changes in core reactivity such as a boron dilution event and a misloaded fuel assembly event. These detectors are located external to the reactor vessel and detect neutron leaking from the core. The licensee stated in References 1 and 2 that for the conditions that one SMR is inoperable, the required action of suspending positive reactivity additions is sufficient to preclude an accident criticality. |
| | Based on the current definitions in TS 1.1, "CORE ALTERATION shall be the movement or manipulation of any fuel, sources, or reactivity control components [excluding control assemblies (CEAs) withdrawal into the upper guide structure], within the reactor vessel with vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position". |
| | With the removal of the TS required action of suspending CORE ALTERATION, the only TS 3.9.2 restriction is the required action to suspend positive reactivity operations. |
| | Since the withdrawal of fuel assemblies from the core may not contribute to the addition of positive reactivity to the core, it is not prohibited by the proposed TS 3.9.2. |
| | The NRC staff is concerned that the SRM could be decoupled from the nuclear response when the fuel assemblies are withdrawn out of the core. For example, the withdrawal of fuel assemblies could result in a condition where fuel assemblies reside in a half of the |
| | |
| | core opposite the operable SRM. Another example is removal of a source assembly from a decayed core. Under these conditions, the remaining operable SRM may not be able to effectively detect the neutron reactivity. Thus, there may not be an SRM to adequately detect the occurrence of the boron dilution or misloaded fuel assembly event, resulting in an unanalyzed condition. |
| | : a. Please address whether the operable SRM could be decoupled from the neutron fluxes during a fuel assembly withdrawal in Mode 6. |
| | : b. If the SRM-neutron decouple is determined to be a non-credible phenomenon, provide rationale in support of the determination. |
| | : c. If the SRM-neutron decouple is determined to be a credible phenomenon, justify the proposed change to remove CORE ALTERATION from the TS. The justification should include information addressing the compliance with: |
| | : i. Acceptance criterion in Standard Review Plan (SRP) 15.6.4 that requires that at least 30 minutes is available from the time the operator is made aware of the unplanned boron dilution event to the time a total loss of shutdown margin (criticality) occurs during refueling (Mode 6), and ii. Guidance of Item 4 on page 15.4.6-8 of SPR 15.6.4 (Revision 2 dated March 2007) that specifies that redundant alarms should be available for the operator to identify and terminate the unplanned boron dilution within the required time |
| | : 2. The NRC staff is concerned that without a prior criticality analysis, it could be difficult to tell whether shuffling an assembly (change the core geometry) causes a positive or negative reactivity change. By restricting core alteration, rather just positive reactivity addition, current TS 3.9.2 explicitly delineates components that cannot be moved, and this TS restriction of core alteration could prevent the operator from misjudging the reactivity of the fuel assembly movement. |
| | Please describe how the licensee determines whether shuffling an assembly would cause a positive or negative reactivity change.}} |
Letter Sequence Draft RAI |
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TAC:ME8160, Eliminate Use of Term Core Alterations in Actions and Notes (Withdrawn, Closed) TAC:ME8161, Eliminate Use of Term Core Alterations in Actions and Notes (Withdrawn, Closed) TAC:ME8162, Eliminate Use of Term Core Alterations in Actions and Notes (Withdrawn, Closed) |
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MONTHYEARML12076A0452012-03-0808 March 2012 Request for Amendment to Eliminate the Use of the Term Core Alteration in the Technical Specifications Project stage: Request ML1213103802012-05-10010 May 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Revision 3 Project stage: Acceptance Review ML12248A1502012-09-0404 September 2012 E-mail Draft Request for Additional Information, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Revision 3 Project stage: Draft RAI ML12250A7202012-09-11011 September 2012 Request for Additional Information, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Revision 3 Project stage: RAI ML12286A3302012-10-11011 October 2012 Response to Request for Additional Information Regarding License Amendment Request to Eliminate the Use of the Term Core Alteration in the Technical Specifications Project stage: Response to RAI ML12341A1292012-12-0505 December 2012 E-mail, Draft Request for Additional Information, Round 2, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160/ME8162) Project stage: Draft RAI ML12347A0402012-12-19019 December 2012 Request for Additional Information, Round 2, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160-ME8162) Project stage: RAI ML12362A2922013-01-0303 January 2013 Request for Additional Information, Round 3, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160-ME8162) Project stage: RAI ML13039A0132013-01-31031 January 2013 Response to Request for Additional Information Regarding License Amendment Request to Eliminate the Use of the Term Core Alteration in the Technical Specifications Project stage: Response to RAI ML13072A1822013-03-13013 March 2013 Email, Draft Request for Additional Information, Round 4, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160-ME8162) Project stage: Draft RAI ML13127A2432013-05-0808 May 2013 5/29/13 Meeting Via Conference Call with Arizona Public Service Company to Discuss Palo Verde Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 (TAC ME8160-ME81 Project stage: Meeting ML13150A0812013-06-0303 June 2013 Request for Additional Information, Round 4, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 Project stage: RAI ML13154A4502013-06-26026 June 2013 Summary of Meeting Via Conference Call with Arizona Public Service Co. to Discuss Palo Verde Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 (TAC ME8160-ME816 Project stage: Meeting ML13210A2382013-07-25025 July 2013 Response to Request for Additional Information Regarding License Amendment Request to Eliminate the Use of the Term Core Alteration in the Technical Specifications Project stage: Response to RAI ML14051A1032014-02-13013 February 2014 Withdrawal of Request for Amendment to Eliminate the Use of the Term Core Aleration in the Technical Specifications Project stage: Request ML14059A1782014-03-0707 March 2014 Withdrawal of License Amendment Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 Project stage: Withdrawal ML14059A1812014-03-0707 March 2014 FRN - Withdrawal of License Amendment Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 Project stage: Withdrawal 2013-01-03
[Table View] |
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Category:E-Mail
MONTHYEARML24267A2172024-09-23023 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 ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA 2024-09-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24257A1012024-09-11011 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 PVNGS PI&R Request for Information RA ML21011A1972021-01-12012 January 2021 Unit 2, and Unit 3 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2021012, 05000529/2021012 and 05000530/2021012) and Request for Information ML20227A0992020-08-14014 August 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20118D1362020-04-28028 April 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20049A0992020-02-14014 February 2020 Notification of Cyber Security Inspection (NRC Inspection Report 05000528/2020401; 05000529/2020401; and 05000530/2020401) and Request for Information ML20049A0252020-02-12012 February 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for License Amendment Request Associated with Changes to Emergency Plan Staffing Requirements ML20021A3172020-01-21021 January 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for Relief Request 64, Impractical Examinations for the Third 10-Year ISI Interval ML19317D0782019-11-13013 November 2019 NRR E-mail Capture - Palo Verde 1 - Requests for Additional Information on Unit 1 21st Refueling Outage Steam Generator Tube Inspection Report ML19234A3202019-08-29029 August 2019 Redacted - Request for Additional Information for Amendment and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel (EPID L-2018-LLA-0194; EPID L-2018-LLE-0010) ML19155A1842019-05-30030 May 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mvib Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19095A6552019-04-0404 April 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mphb Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19044A7342019-02-13013 February 2019 NRR E-mail Capture - Palo Verde1, 2, and 3 - Official Requests for Additional Information for RR 62, Third and Fourth 10-Year ISI Intervals, Proposed Alternative - Pressurizer Heat Sleeve Repairs ML19008A3612019-01-0808 January 2019 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR Associated with Response Time Testing of Pressure Transmitters ML18341A0252018-12-0303 December 2018 Notification of NRC Design Bases Assurance Inspection (Teams)(05000528/2019011, 05000529/2019011, and 05000530/2019011) and Initial Request for Information ML18271A0392018-10-0202 October 2018 Non Proprietary - Supplemental Information Needed for Acceptance of Requested License Amendments and Exemptions Implementation of Framatome High Thermal Performance Fuel (Epids L-2018-LLA-0194 and L-2018-LLE-0010) ML18221A5102018-08-23023 August 2018 Request for Additional Information License Amendment Request to Adopt Risk-Informed Completion Times (CAC Nos. MF6576, MF6577, and MF6578; EPID: L-2015-LLA-0001) ML18229A3132018-08-17017 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 - Second Se ML18227A8672018-08-15015 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 ML18124A0112018-05-0303 May 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official Eeob RAIs for TSTF-505 (4b) LAR (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) ML18099A0072018-04-0606 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for 10 CFR 50.69 LAR (CAC Nos. MF9971, MF9972, and MF9973; EPID L-2017-LLA-0276) ML18094B1122018-04-0404 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAIs for TSTF-505 (Initiative 4b) LAR (CAC Nos. MF6576, MF6577, and MF6578: EPID L-2015-LLA-0001) ML18066A7032018-03-0707 March 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) 05000528/2018011, 05000529/2018011, and 05000530/2018011 Initial Request for Information ML17248A0162017-08-31031 August 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAI for RRs PRR-03, PRR-04 and PRR-05, Pump Testing ML17107A0052017-04-14014 April 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Ngf LAR and Exemption RAIs (CAC Nos. MF8076 to MF8081) ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 2024-09-11
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Text
Lent. Susan From: Gibson, Lauren Sent: Wednesday, December 05, 201211:13AM To: Robert. Roehler@aps.com
Subject:
Draft Request for Additional Information Related to LAR to remove the term CORE ALTERATION from Tech Specs (ME8160, ME8161, and ME8162)
Attachments: Draft RAls ME8160, 1, 2.docx
- Rob, a dated March 8, 2012, and supplemented by letter dated October 11, 2012) Arizona Public Service Co, (APS. the licensee) submitted a license amendment (LAR) for Palo Verde Nuclear Generating Station (Agencywide Documents Access Management System (ADAMS) /"ccession No. ML12076A045 and ML12286A330, respectively), The proposed amendment would the use of the term CORE ALTERATION from the technical specifications.
The U.S, Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the additional information identified in the attachment is needed in order for the NRC staff to complete review.
Please contact me jf you would like to have a clarifying conference call.
Thank you, Lauren Lauren K Gibson Project Manager Columbia Generating Station Palo Verde Generating Station of Operating Reactor Licensing Nuclear Commission 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REMOVAL OF "CORE ALTERATION" FROM TECHNICAL SPECIFICATIONS (TSS) INCLUDING TS 3.9.2. "NUCLEAR INSTRUMENTATION" FOR PALO VERDE NUCLEAR GENERATING STATION (PVNGS), UNITS 1. 2. AND 3 DOCKET NOS. 50-528. 50-529 AND 50-530 Request for Additional Information By letter dated March 8, 2012, supplemented by a letter dated October 11,2012, Arizona Power Service Company (APS), the licensee for Palo Verde Nuclear Generating Station (PVNGS),
Units 1,2, and 3, proposed to remove "CORE ALTERATION" from Technical Specifications (TSs) including TS 3.9.2, "Nuclear Instrumentation".
The NRC staff has reviewed the submitted information and has determined that the following additional information is required to complete the review.
- 1. For Palo Verde Nuclear Generating Station (PVNGS), current Technical Specification (TS) 3.9.2 (for Mode 6), "Nuclear Instrumentation", requires that (1) Core Alterations be suspended and (2) positive reactivity activities be terminated if the required source range nuclear instrumentation is determined to be inoperable. The licensee proposes to remove the required action of suspending Core Alterations from the TS 3.9.2 while maintaining the required action of suspending positive reactivity activities.
At PVNGS, the source range monitors (SRMs) are used during refueling operations to monitor the core reactivity conditions. The SRMs provide a signal to operator of unexpected changes in core reactivity such as a boron dilution event and a misloaded fuel assembly event. These detectors are located external to the reactor vessel and detect neutron leaking from the core. The licensee stated in References 1 and 2 that for the conditions that one SMR is inoperable, the required action of suspending positive reactivity additions is sufficient to preclude an accident criticality.
Based on the current definitions in TS 1.1, "CORE ALTERATION shall be the movement or manipulation of any fuel, sources, or reactivity control components [excluding control assemblies (CEAs) withdrawal into the upper guide structure], within the reactor vessel with vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position".
With the removal of the TS required action of suspending CORE ALTERATION, the only TS 3.9.2 restriction is the required action to suspend positive reactivity operations.
Since the withdrawal of fuel assemblies from the core may not contribute to the addition of positive reactivity to the core, it is not prohibited by the proposed TS 3.9.2.
The NRC staff is concerned that the SRM could be decoupled from the nuclear response when the fuel assemblies are withdrawn out of the core. For example, the withdrawal of fuel assemblies could result in a condition where fuel assemblies reside in a half of the
core opposite the operable SRM. Another example is removal of a source assembly from a decayed core. Under these conditions, the remaining operable SRM may not be able to effectively detect the neutron reactivity. Thus, there may not be an SRM to adequately detect the occurrence of the boron dilution or misloaded fuel assembly event, resulting in an unanalyzed condition.
- a. Please address whether the operable SRM could be decoupled from the neutron fluxes during a fuel assembly withdrawal in Mode 6.
- b. If the SRM-neutron decouple is determined to be a non-credible phenomenon, provide rationale in support of the determination.
- c. If the SRM-neutron decouple is determined to be a credible phenomenon, justify the proposed change to remove CORE ALTERATION from the TS. The justification should include information addressing the compliance with:
- i. Acceptance criterion in Standard Review Plan (SRP) 15.6.4 that requires that at least 30 minutes is available from the time the operator is made aware of the unplanned boron dilution event to the time a total loss of shutdown margin (criticality) occurs during refueling (Mode 6), and ii. Guidance of Item 4 on page 15.4.6-8 of SPR 15.6.4 (Revision 2 dated March 2007) that specifies that redundant alarms should be available for the operator to identify and terminate the unplanned boron dilution within the required time
- 2. The NRC staff is concerned that without a prior criticality analysis, it could be difficult to tell whether shuffling an assembly (change the core geometry) causes a positive or negative reactivity change. By restricting core alteration, rather just positive reactivity addition, current TS 3.9.2 explicitly delineates components that cannot be moved, and this TS restriction of core alteration could prevent the operator from misjudging the reactivity of the fuel assembly movement.
Please describe how the licensee determines whether shuffling an assembly would cause a positive or negative reactivity change.