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MONTHYEARML1021503522010-07-22022 July 2010 Request for Amendment to Change an Element of Methodology Used in Evaluating the Radiological Consequences of Design Basis Steam, Generator Tube Rupture (SGTR) Accidents Project stage: Request ML1104105432011-02-10010 February 2011 Draft Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report to Change Methodology for Steam Generator Tube Rupture Accidents Project stage: Draft RAI ML11111A0632011-04-0808 April 2011 Response to Request for Additional Information Regarding License Amendment Request to Revise an Element of Methodology Used in Evaluating the Radiological Consequences of Design Basis Steam Generator Tube Rupture Accidents Project stage: Response to RAI ML1118103382011-07-28028 July 2011 Issuance of Amendment Nos. 186, 186, and 186, Revise Updated Final Safety Analysis Report to Change Methodology for Steam Generator Tube Rupture Accidents Project stage: Approval ML1121401572011-08-0303 August 2011 Correction of Typographical Error in Cover Letter to Amendment Nos. 186, 186, and 186 Issued July 28, 2011 Project stage: Other 2011-04-08
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Category:Request for Additional Information (RAI)
MONTHYEARML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle 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 ML17003A0182017-01-0202 January 2017 NRR E-mail Capture - Palo Verde, Unit 3 - Draft RAIs for the Second Emergency LAR Associated with EDG 3B Failure ML16258A0312016-09-14014 September 2016 PVNGS Units 1-3 - Notif of NRC Insp of the Implementation of Mitigation Strategies and Spent Fuel Pool Instr. Orders and Emer. Prep. Comm./Staffing/Multi-Unit Dose Assessment Plns(05000528/ 2016009;05000529/2016009;and 05000530/2016009) and ML16111B3312016-04-20020 April 2016 Notification of NRC Component Design Bases Inspection (05000528/2016007; 05000529/2016007; 05000530/2016007) and Initial Request for Information ML16083A2502016-03-23023 March 2016 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Official RAIs for EAL LAR 2024-01-10
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DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO REVISE THE STEAM GENERATOR TUBE RUPTURE ACCIDENT ANALYSIS PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN-50-528, STN-50-529, AND STN-50-530 ARIZONA PUBLIC SERVICE COMPANY By letter dated July 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102150352), Arizona Public Service Company (the licensee), submitted a license amendment request (LAR) to revise an element of the methodology used in evaluating the radiological consequences of design basis Steam Generator Tube Rupture (SGTR) accidents at the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, as described in the Updated Final Safety Analysis Report (UFSAR). The revision would revise the iodine spiking factor used for a coincident event-generated iodine spike (GIS) from a value of 500 to a value of 335.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the following additional information is needed to complete the review: 1. In Enclosure 1, page 2, the LAR proposes to change an element of methodology (assumption) used in evaluating the radiological consequences of design basis SGTR accidents. Specifically, this proposed change would revise the iodine spiking factor used for a coincident event-Generated Iodine Spike (GIS) from a value of 500 to 335. For the GIS spiking factor of 500 currently used in the dose analysis of record (AOR), a 2-hour thyroid dose value of 182 rem at the exclusion area boundary (EAB), and an 8-hour thyroid dose value of 125 rem at the low population zone (LPZ) were determined as presented in Table 15.6.3-5 of the PVNGS UFSAR. The LAR asserts that use of the newly proposed GIS spiking factor of 335 would result in the 2-hour thyroid dose at the EAB to be reduced to approximately 124 rem. The LAR also asserts that the 8-hour thyroid dose at the LPZ would be reduced to approximately 84 rem.
The LAR further asserts that the current Pre-Accident Iodine Spike (PIS) values would not be affected by the proposed methodology change. The LAR also states, "The NRC acceptance criterion previously specified on the PVNGS licensing docket for both GIS and PIS cases is 100% of the 10 CFR Part 100 guideline values which allowed a maximum thyroid dose of 300 rem. The results of this proposed change still remain within these acceptance criteria."
Title 10 of the Code of Federal Regulations (10 CFR), Section 100.11 sets the regulatory limits for offsite radiological dose consequences at both the EAB and LPZ at 25 rem whole body and/or 300 rem thyroid. Further, acceptance criteria provided in Revision 2 of the Standard Review Plan (NUREG-0800), Section 15.6.3, "Radiological Consequences of Steam Generator Tube Failure (PWR)," provides applicable guidelines which state, "-for the postulated accident with the equilibrium iodine concentration for continued full power operation in combination with an assumed accident initiated iodine spike, the calculated doses should not exceed a small fraction of the above [10 CFR Part 100] guideline values, i.e., 10 percent or 2.5 rem and 30 rem, respectively, for the whole-body and thyroid doses."
Therefore, Revision 2 of NUREG-0800 has effectively established guidance that offsite radiological dose consequences are limited to a small fraction, or 10% of the 10 CFR Section 100.11 guideline values.
In regard to the offsite radiological dose consequences for the SGTR with an assumed accident-initiated iodine spike, please provide justification as to why the proposed 2-hour thyroid dose value of 124 rem at the EAB, and 8-hour thyroid dose value of 84 rem at the LPZ are appropriate, considering that each exceeds the current NRC staff review criterion of 30 rem to the thyroid for offsite dose. Please also provide all pertinent analyses and/or radiological dose calculations that support the justification to allow the staff to conduct an independent evaluation.
Please also verify that the proposed change would not result in a control room (CR) dose above the 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 19 limit of 5 rem. Please provide all pertinent radiological analyses, calculations, or documentation needed in order for the NRC staff to conduct an independent evaluation. As it pertains to the PVNGS's current AOR, please also specify where the current CR radiological dose consequence values for the SGTR accident are located.