Letter Sequence Acceptance Review |
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EPID:L-2018-LLA-0194, License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel (Approved, Closed) EPID:L-2018-LLE-0010, Response to NRC Staff Request for Additional Information from Reactor Assessment and Human Performance Branch Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome High Thermal (Open) |
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MONTHYEARML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel Project stage: Request 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) Project stage: Acceptance Review ML18296A4662018-10-18018 October 2018 Supplemental Information Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel Project stage: Supplement ML18312A3322018-11-13013 November 2018 Acceptance Review for License Amendment and Exemption Requests Regarding the Implementation of Framatome High Thermal Performance Fuel Project stage: Acceptance Review ML18333A2272018-12-0404 December 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated October 18, 2018, Executed by Mr. Bruce Rash of APS Project stage: Withholding Request Acceptance ML18333A1632018-12-0404 December 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated July 6, 2018, Executed by Mr. Bruce Rash of APS Project stage: Withholding Request Acceptance ML18333A0712018-12-0404 December 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated May 16, 2018, Executed by Mr. Philip A. Opsal, from Framatome, Inc. Project stage: Withholding Request Acceptance ML18333A0592018-12-0404 December 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated March 9, 2018, Executed by Mr. Philip A. Opsal, from Framatome, Inc. Project stage: Withholding Request Acceptance ML19011A1082019-01-15015 January 2019 First Regulatory Audit Plan for January 22-23, 2019, in Support of Framatome (EPID L-2018-LLA-0194 and EPID L-2018-LLE-0010) Project stage: Other ML19060A2982019-03-0101 March 2019 Transmittal of Audit Presentation Slides Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome CE16HTP Fuel Project stage: Request ML19065A2212019-03-18018 March 2019 Request for Withholding Information from Public Disclosure, Affidavit Dated February 22, 2019, Executed by Mr Philip A. Opsal, Framatome, Inc. Project stage: Withholding Request Acceptance ML19065A2542019-03-18018 March 2019 Request for Withholding Information from Public Disclosure, Affidavit Dated February 28, 2019, Executed by Mr. Bruce Rash, Arizona Public Service Company Project stage: Withholding Request Acceptance ML19098A1872019-04-0505 April 2019 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs from Irab for Framatome Htp Fuel LAR and Exemption (EPIDs L-2018-LLA-0194 and L-2018-LLE-0010) Project stage: RAI ML19137A1182019-05-17017 May 2019 Response to NRC Staff Request for Additional Information from Reactor Assessment and Human Performance Branch Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome High Thermal Project stage: Request ML19154A4692019-06-0404 June 2019 Second Regulatory Audit Plan for June 17-20, 2019, in Support of Framatome High Thermal Performance Fuel License Amendment Request and Exemption Project stage: Other ML19218A2932019-08-13013 August 2019 Regulatory Audit Report for the January 22-23, 2019, Audit for the License Amendment and Exemption Requests Assoc. W/Framatome High Thermal Performance Fuel (EPID L-2018-LLA-0194; EPID L-2018-LLE-0010) Project stage: Other 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) Project stage: RAI ML19235A2562019-09-0909 September 2019 Regulatory Audit Summary for the June 17-20, 2019, Audit for the License Amendment and Exemption Requests Associated with Framatome High Thermal Performance Fuel Project stage: Other ML19277J4572019-10-0404 October 2019 Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel Project stage: Response to RAI ML19331A3612019-11-26026 November 2019 Supplemental Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel Project stage: Supplement ML19353C0382019-12-19019 December 2019 Supplemental Information Related to Framatome CE16HTP Fuel LAR Requests for Additional Information Bhtp RAl-05 and Bhtp RAl-06 Project stage: Supplement ML20031D6012020-02-13013 February 2020 Audit Summary for the Nov. 7-8, 2019, Audit for the License Amendment and Exemption Requests Associated with Framatome High Thermal Performance Fuel (EPID L-2018-LLA-0194 & EPID L-2018-LLE-0010) Project stage: Other ML20050C9742020-02-19019 February 2020 NRR E-mail Capture - Palo Verde 1,2, and 3 - Framatome Htp Fuel LAR and Exemption Third Audit Summary (EPIDs L-2018-LLA-0194 and L-2018-LLE-0010) Project stage: Other ML20031C9472020-03-0404 March 2020 Nonproprietary, Issuance of Amendment Nos. 212, 212, and 212 to Revise Technical Specifications to Support the Implementation of Framatome High Thermal Performance Fuel Project stage: Approval 2019-03-01
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Category:Letter
MONTHYEARML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) 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 ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information 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-2024-001-01, 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 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 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) 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 ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator 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 2024-09-27
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24297A6212024-10-22022 October 2024 Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300 ML24257A1012024-09-11011 September 2024 Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components ML24143A1112024-05-20020 May 2024 Draft 2nd Round Request for RAIs Concerning LAR to Modify LCO for TS 3.5.2, LCO for TS 3.6.5, and Surveillance Requirements 3.5.1.2 and 3.5.2.2 for TS 3.5.1 and TS 3.5.2 ML24123A2002024-05-0101 May 2024 (E-Mail) Draft 2nd Round Request for Additional Information Concerning License Amendment Request to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, LCO for TS 3.6.5, 3.5.1.2 and 3.5.2.2 for TS 3.5.1, a ML24114A2812024-04-19019 April 2024 Request for Additional Information (RAI-10150-R1) ML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23031A3392023-01-31031 January 2023 In-service Inspection Request for Information ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22272A3252022-09-29029 September 2022 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML22209A1752022-07-28028 July 2022 Inservice Inspection Request for Information ML22187A2632022-07-0606 July 2022 Notification of Inspection (NRC IR 05000528/2022004, 05000529/2022004 and 05000530/2022004) and Request for Information ML22067A2292022-03-0202 March 2022 Inservice Inspection Inspection PWR Request for Information ML22055A5842022-02-24024 February 2022 NRR E-mail Capture - Palo Verde, Unit 3 - Final RAIs for 22nd Refueling Outage (Spring 2021) Steam Generator Tube Inservice Inspection Report ML22035A3302022-02-10010 February 2022 Requests for Confirmation of Information for Exemption to Delete Diverse Auxiliary Feedwater Actuation System Based on Risk-Informed Process for Evaluations ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information ML21245A2222021-09-0101 September 2021 Request for Information ML21200A2392021-07-20020 July 2021 Docs Request AC - AA August 2021 ML21154A0082021-05-26026 May 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Official RAIs for LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21042B9692021-02-18018 February 2021 Notification of NRC Design Bases Assurance Inspection and Initial Request for Information ML21043A1462021-02-11011 February 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAI for an Order Associated with Indirect License Transfer from Public Service Company of New Mexico to Avangrid, Inc ML21023A0212021-01-13013 January 2021 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) 2024-09-11
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OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 2, 2018 Mr. Robert S. Bement Executive Vice President Nuclear/Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 -
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSE AMENDMENTS AND EXEMPTIONS RE:
IMPLEMENTATION OF FRAMATOME HIGH THERMAL PERFORMANCE FUEL (EPID L-2018-LLA-0194 AND EPID L-2018-LLE-0010)
Dear Mr. Bement:
By letter dated July 6, 2018, Arizona Public Service Company (APS) submitted license amendment and exemption requests for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendments and exemptions would support the implementation of Framatome High Thermal Performance Fuel.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these amendment and exemption requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the license amendment and exemption applications have any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics unusual or novel design features, and principal safety considerations.
Enclosure 1 to this document contains Proprietary Information. When separated from Enclosure 1, this letter is DECONTROLLED.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION R. Bement Consistent with Section 50.12 of 10 CFR, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of the regulations of this part, which are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The Commission will not consider granting an exemption unless special circumstances are present, as specified in Section 50.12(a)(2).
The NRC staff has reviewed your license amendment and exemption applications and concluded that the information delineated in the enclosure 'to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendments and exemptions in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the license amendment and exemption applications complete, the NRC staff requests that APS supplement the application to address the information requested in the enclosure by October 22, 2018. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the license amendment and exemption applications will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the applications. If the applications are subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with Mr. Tom Weber of your staff on September 27, 2018.
If you have any questions, please contact me at (301) 415-3229 or via e-mail at Michael. Orenak@nrc.gov.
Sincerely, IRA Margaret W. O'Banion for/
Michael D. Orenak, 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:
- 1. Supplemental Information Needed (Proprietary version)
- 2. Supplemental Information Needed (Non Proprietary version) cc: w/o Enclosure 1: Listerv OFFICIAL USE ONLY PROPRIETARY INFORMATION
Enclosure 2 REQUESTED SUPPLEMENTAL INFORMATION LICENSE AMENDMENT AND EXEMPTION REQUESTS REGARDING IMPLEMENTATION OF FRAMATOME HIGH THERMAL PERFORMANCE FUEL ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530 (NON-PROPRIETARY)
Proprietary information pursuant to Section 2.390 of Title 1O of the Code of Federal Regulations has been redacted from this document.
Redacted information is identified by blank space enclosed within double brackets.
OFFICIAL USE ONLY PROPRIETARY INFORMATION SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT AND EXEMPTION REQUESTS REGARDING IMPLEMENTATION OF FRAMATOME HIGH THERMAL PERFORMANCE FUEL ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530 By letter dated July 6, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18187A417), Arizona Public Service Company (APS, the licensee) submitted license amendment and exemption requests for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Palo Verde). The proposed amendments and exemptions would support the implementation of Framatome High Thermal Performance Fuel.
During the acceptance review of the license amendment and exemption applications (together, the application), the U.S. Nuclear Regulatory Commission (NRC) staff identified the following information needed before the application can be accepted by the NRC for review.
- 1. In Section 5.4.1.1, of Attachment 10 of the application, APS discusses its use of the VIPRE-01 computer code. VIPRE-01 has been previously reviewed and approved by the NRC staff. However, as noted by the NRC staff in its safety evaluation, "Each organization using VIPRE-01 for licensing calculations should submit separate documentation describing how they intend to use VIPRE-01 and providing justification for their specific modeling assumptions, choice of particular two-phase flow models and correlations, heat transfer correlations, CHF [critical heat flux] correlation and DNBR
[departure from nucleate boiling ratio] limit, input values of plant specific data such as turbulent mixing coefficient, slip ratio, grid loss coefficient, etc., including defaults."
In Section 5 of Enclosure 10 of the application, APS did not provide the details necessary for the NRC staff to approve the use of VIPRE-01. Please submit the information that describes how APS intends to use VIPRE-01.
- 2. Since the publication of Regulatory Guide (RG) 1. 77, "Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors" (ADAMS Accession No. ML003740279), the acceptance criteria of 280 calories per gram of deposited enthalpy has been found inadequate to ensure fuel rod geometry and long-term coolability. The NRC staff documented its position on RG 1. 77 in a letter dated April 3, 2015, "Results of Periodic Review of Regulatory Guide 1.77" (ADAMS Accession No. ML15075A311 ). The position is supported by a guidance document dated January 19, 2007, titled "Technical and Regulatory Basis for the Reactivity-Initiated Accident Interim Acceptance Criteria and Guidance" (ADAMS Accession No. ML070220400).
Please demonstrate that the control element assembly ejection transient analysis results meet General Design Criterion 28, "Reactivity Limits," of Title 10 of the Code of Federal OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Regulations Part 50, Appendix A, by showing that fuel rod geometry and long-term coolability is maintained and that the effects of burn-up are considered in the analysis.
- 3. Attachment 4 of the application, Insert "A" to 8.2.1.1, indicates that there will be three fuel types which will be used at Palo Verde (CE16STD, CE16NGF and CE16HTP).
However, in Section 5.5 of Attachment 10 of the application, APS seems to limit the mixed core assessment to (1) the inlet flow distribution, and (2) crossflow velocity analysis for mechanical calculations. Provide a summary of the analysis that describes how mixed cores are treated from a thermal-hydraulic standpoint, especially noting any DNBR penalties which are needed due to the different fuel types. This should be provided for both the VIPRE-W and VIPRE-01 methodologies.
- 4. Pages 12 and 13 of Attachment 5 of the application discuss the use of Topical Report CENPD-183-A, "C-E methods for Loss of Flow Analysis" (ADAMS Accession No. ML16224A358) for loss of flow analysis using several codes, such as COAST, QUIX, COSMO/W3, TORC/CE1 and CESEC. The methodology and codes are approved for Combustion Engineering (CE) or Westinghouse type of fuels. Please provide a detailed justification as to how these codes can be applied to the Palo Verde mixed core with Framatome CE 16x16 high thermal performance (HTP) fuel design.
- 5. Section 5.4.3 of Attachment 10 of the application discusses the proposed implementation of the BHTP (designation for a Framatome CHF Correlation) CHF correlation with the VIPRE-01 and VIPRE-W thermal-hydraulic codes and with several other thermal-hydraulics codes at Palo Verde. The examples cited are:
- Implementing the ABB-NV or WSSV CHF correlations, which the NRC has previously approved for use with the VIPRE-W code, for use with the VIPRE-01 code;
- Implementing the CE-1 CHF correlation, which the NRC has previously approved for use with the VIPRE-W, CETOP-D, and TORC codes, for use with the VIPRE-01 code;
- Implementing the BHTP CHF correlation, which is anticipated to be approved for use with the VIPRE-01 and VIPRE-W code as described in this license amendment request, with the CETOP-D code and/or the TORC code.
Please provide detailed explanations for inserting the different correlations into the above codes with respect to validation, verification, and sensitivity studies.
- 6. Section 1.3 of Attachment 10 of the application states, in part, The current APS Core Thermal Hydraulic Analysis scope will be modified to the extent that ((
]) for compliance with Technical Specification limits on DNBR.
OFFICIAL USE ONLY PROPRIETARY INFORMATION The specifics of this modification process in Section 5 of Attachment 1O do not appear to be provided. Please provide a detailed explanation of which computer codes were needed to be modified by the addition of BHTP and how that modification took place.
- 7. Section 11 of Attachment 10 provides a short summary of Core Operating Limits Supervisory System/Core Protection Calculator System (COLSS/CPCS) setpoints analysis that is unique for some CE plants. This section provides a very limited description of the setpoints analysis for Palo Verde cores which use Framatome CE 16x16 HTP fuel.
- a. Please provide justification for the CE setpoints methodology applicability to Framatome fuel.
- b. Please provide details of how the CE setpoints methodology is applied to the cores with Framatome fuel design.
PKG ML18271A037 Proprietary ML18271A035 Non-Proprietary ML18271A039 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/SNPB/BC NAME MOrenak PBlechman Rlukes DATE 9/28/18 9/28/18 8/31/18 OFFICE NRR/DSS/SRXB/BC NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME JWhitman RPascarelli MOrenak (MO'Banion for)
DATE 8/24/18 10/01/18 10/2/18