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| | number = ML12347A040 | | | number = ML12347A040 |
| | issue date = 12/19/2012 | | | issue date = 12/19/2012 |
| | title = Palo Verde, Units 1, 2 and 3 - 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) | | | title = 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 = Edington R K | | | addressee name = Edington R |
| | addressee affiliation = Arizona Public Service Co | | | addressee affiliation = Arizona Public Service Co |
| | 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 = Request for Additional Information (RAI), Letter | | | document type = Request for Additional Information (RAI), Letter |
| | page count = 5 | | | page count = 5 |
| | project = TAC:ME8160, TAC:ME8160, TAC:ME8161, TAC:ME8162 | | | project = TAC:ME8160, TAC:ME8161, TAC:ME8162 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 December 19, 2012 Mr. Randall K. Edington Executive Vice President Nuclearl Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ELIMINATE THE USE OF THE TERM CORE ALTERATION (TAC NOS. ME8160, ME8161, AND ME8162) Dear Mr. Edington: By letter dated March 8, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12076A045), as supplemented by letter dated October 11. 2012 (ADAMS Accession No. ML 12286A330). Arizona Public Service Company (APS, the licensee) submitted a license amendment (LAR) for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would eliminate 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 enclosure to this letter is needed in order for the NRC staff to complete its review. The draft copy of the request for additional information was provided in two parts to Mr. Robert Roehler of your staff via e-mail on December 5,2012. A clarifying conference call was held on December 13.2012. Mr. Roehler agreed to provide a response by January 31, 2013. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 19, 2012 Mr. Randall K. Edington Executive Vice President Nuclearl Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 |
| R. Edington -If you have any questions, please contact me at (301) 415-1056 or via e-mail at Lauren. Gibson@nrc.gov. Sincerely, Docket Nos. STN 50-528, STN and STN Enclosure: As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ELIMINATE THE USE OF THE TERM CORE ALTERATION IN THE TECHNICAL SPECIFICATIONS ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION. UNITS 1. 2. AND 3 DOCKET NOS. 50-528. 50-529. AND 50-530 By letter dated March 8, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12076A045), as supplemented by letter dated October 11, 2012 (ADAMS Accession No. ML 12286A330), Arizona Public Service Company (APS, the licensee) submitted a license amendment (LAR) in which it proposed to remove the use of the term CORE ALTERATION from the Technical Specifications (TSs) including TS 3.9.2, "Nuclear Instrumentation," for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS). The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submitted information and has determined that the following additional information is required to complete the review. 1. For PVNGS, current 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 proposed 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 its submittal that for the conditions that one SRM 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. Enclosure | | |
| -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. 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, please provide the rationale in support of the determination. If the SRM-neutron decouple is determined to be a credible phenomenon, please justify the proposed change to remove CORE ALTERATION from the TSs. The justification should include information addressing the compliance with: Acceptance criterion in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," (SRP) Section 15.6.4, "Radiological Consequences of Main Steam Line Failure Outside Containment (BWR)," 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 SRP Section 15.6.4, Revision 2, 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 determine whether shuffling an assembly (change the core geometry) causes a positive or negative reactivity change. By restricting core alteration, rather than 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. | | ==SUBJECT:== |
| R. Edington -2 If you have any questions, please contact me at (301) 415-1056 or via e-mail at Lauren.Gibson@nrc.gov. Docket Nos. STN 50-528, STN 50-529, and STN 50-530 Enclosure: As stated cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV r/f RidsAcrsAcnw _MaiICTR Resource RidsNrrDorlLpl4 Resource RidsNrrDssSrxb Resource RidsNrrLAJ Burkhardt Resource RidsNrrPMPaloVerde Resource RidsOgcRp Resource RidsRgn4MailCenter Resource SSun, NRRlDSS/SRXB Sincerely, IRA by Brian Benney forI Lauren K. Gibson, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ADAMS Accession No. ML 12347 A040 *b memo dated NRRlDORULPL4/PM NRRlDORULPL4/LA NRRlDSS/SRXBlBC LKGibson (BSingal for) 12/17112 JBurkhardt CJackson* 12/17/12 11/16/12 NRRlDORULPL4/BC NRRlDOR MMarkley 12/19/12 LKGibson (BBenney for) 12/19/12 OFFICIAL RECORD COpy | | PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ELIMINATE THE USE OF THE TERM CORE ALTERATION (TAC NOS. ME8160, ME8161, AND ME8162) |
| }} | | |
| | ==Dear Mr. Edington:== |
| | |
| | By letter dated March 8, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12076A045), as supplemented by letter dated October 11. 2012 (ADAMS Accession No. ML12286A330). Arizona Public Service Company (APS, the licensee) submitted a license amendment (LAR) for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would eliminate 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 enclosure to this letter is needed in order for the NRC staff to complete its review. The draft copy of the request for additional information was provided in two parts to Mr. Robert Roehler of your staff via e-mail on December 5,2012. A clarifying conference call was held on December 13.2012. |
| | Mr. Roehler agreed to provide a response by January 31, 2013. |
| | |
| | R. Edington - 2 If you have any questions, please contact me at (301) 415-1056 or via e-mail at Lauren. Gibson@nrc.gov. |
| | Sincerely, Docket Nos. STN 50-528, STN 50-529, and STN 50-530 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ELIMINATE THE USE OF THE TERM CORE ALTERATION IN THE TECHNICAL SPECIFICATIONS ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION. UNITS 1. 2. AND 3 DOCKET NOS. 50-528. 50-529. AND 50-530 By letter dated March 8, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12076A045), as supplemented by letter dated October 11, 2012 (ADAMS Accession No. ML12286A330), Arizona Public Service Company (APS, the licensee) submitted a license amendment (LAR) in which it proposed to remove the use of the term CORE ALTERATION from the Technical Specifications (TSs) including TS 3.9.2, "Nuclear Instrumentation," for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS). |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submitted information and has determined that the following additional information is required to complete the review. |
| | : 1. For PVNGS, current 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 proposed 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 its submittal that for the conditions that one SRM 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. |
| | Enclosure |
| | |
| | - 2 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, please provide the rationale in support of the determination. |
| | : c. If the SRM-neutron decouple is determined to be a credible phenomenon, please justify the proposed change to remove CORE ALTERATION from the TSs. The justification should include information addressing the compliance with: |
| | : i. Acceptance criterion in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," (SRP) Section 15.6.4, "Radiological Consequences of Main Steam Line Failure Outside Containment (BWR)," 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 SRP Section 15.6.4, Revision 2, 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 determine whether shuffling an assembly (change the core geometry) causes a positive or negative reactivity change. By restricting core alteration, rather than 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. |
| | |
| | R. Edington -2 If you have any questions, please contact me at (301) 415-1056 or via e-mail at Lauren.Gibson@nrc.gov. |
| | Sincerely, IRA by Brian Benney forI Lauren K. Gibson, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPLIV r/f RidsAcrsAcnw_MaiICTR Resource RidsNrrDorlLpl4 Resource RidsNrrDssSrxb Resource RidsNrrLAJ Burkhardt Resource RidsNrrPMPaloVerde Resource RidsOgcRp Resource RidsRgn4MailCenter Resource SSun, NRRlDSS/SRXB ADAMS Accession No. ML12347A040 *b memo dated NRRlDORULPL4/PM NRRlDORULPL4/LA NRRlDSS/SRXBlBC NRRlDORULPL4/BC NRRlDOR LKGibson (BSingal LKGibson (BBenney for) JBurkhardt CJackson* MMarkley for) 12/17112 12/17/12 11/16/12 12/19/12 12/19/12 OFFICIAL RECORD COpy}} |
Letter Sequence 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
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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
[Table view] Category:Letter
MONTHYEARML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24241A2782024-08-28028 August 2024 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 ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation 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 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu 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 IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24157A3392024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24144A2772024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations 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 IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 1R24 2024-09-23
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 19, 2012 Mr. Randall K. Edington Executive Vice President Nuclearl Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ELIMINATE THE USE OF THE TERM CORE ALTERATION (TAC NOS. ME8160, ME8161, AND ME8162)
Dear Mr. Edington:
By letter dated March 8, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12076A045), as supplemented by letter dated October 11. 2012 (ADAMS Accession No. ML12286A330). Arizona Public Service Company (APS, the licensee) submitted a license amendment (LAR) for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would eliminate 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 enclosure to this letter is needed in order for the NRC staff to complete its review. The draft copy of the request for additional information was provided in two parts to Mr. Robert Roehler of your staff via e-mail on December 5,2012. A clarifying conference call was held on December 13.2012.
Mr. Roehler agreed to provide a response by January 31, 2013.
R. Edington - 2 If you have any questions, please contact me at (301) 415-1056 or via e-mail at Lauren. Gibson@nrc.gov.
Sincerely, Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ELIMINATE THE USE OF THE TERM CORE ALTERATION IN THE TECHNICAL SPECIFICATIONS ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION. UNITS 1. 2. AND 3 DOCKET NOS. 50-528. 50-529. AND 50-530 By letter dated March 8, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12076A045), as supplemented by letter dated October 11, 2012 (ADAMS Accession No. ML12286A330), Arizona Public Service Company (APS, the licensee) submitted a license amendment (LAR) in which it proposed to remove the use of the term CORE ALTERATION from the Technical Specifications (TSs) including TS 3.9.2, "Nuclear Instrumentation," for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submitted information and has determined that the following additional information is required to complete the review.
- 1. For PVNGS, current 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 proposed 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 its submittal that for the conditions that one SRM 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.
Enclosure
- 2 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, please provide the rationale in support of the determination.
- c. If the SRM-neutron decouple is determined to be a credible phenomenon, please justify the proposed change to remove CORE ALTERATION from the TSs. The justification should include information addressing the compliance with:
- i. Acceptance criterion in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," (SRP) Section 15.6.4, "Radiological Consequences of Main Steam Line Failure Outside Containment (BWR)," 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 SRP Section 15.6.4, Revision 2, 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 determine whether shuffling an assembly (change the core geometry) causes a positive or negative reactivity change. By restricting core alteration, rather than 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.
R. Edington -2 If you have any questions, please contact me at (301) 415-1056 or via e-mail at Lauren.Gibson@nrc.gov.
Sincerely, IRA by Brian Benney forI Lauren K. Gibson, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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