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| | number = ML14076A074 | | | number = ML14076A074 |
| | issue date = 03/10/2014 | | | issue date = 03/10/2014 |
| | title = Palo Verde, Units 1, 2 and 3 - APS Extension Request for Flooding Hazard Reevaluation Submittal | | | title = APS Extension Request for Flooding Hazard Reevaluation Submittal |
| | author name = Mims D C | | | author name = Mims D C |
| | author affiliation = Arizona Public Service Co | | | author affiliation = Arizona Public Service Co |
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MONTHYEARML14076A0742014-03-10010 March 2014 APS Extension Request for Flooding Hazard Reevaluation Submittal Project stage: Request ML14118A3642014-04-24024 April 2014 Response to Request for Additional Information Regarding Recommendation 2.1 Flood Hazard Reevaluation Extension Request Project stage: Response to RAI ML14156A4062014-05-30030 May 2014 Flooding Hazard Re-Evaluation Extension - Public Meeting Clarification Items Project stage: Request ML14136A0582014-06-0202 June 2014 5/14/2014 Summary of Meeting with Arizona Public Service Company to Discuss Flooding Hazard Reevaluation Extension Request for Palo Verde, Units 1, 2, and 3; Near-Term Task Force Recommendation 2.1 Project stage: Meeting ML14162A4652014-07-29029 July 2014 Relaxation of Response Due Dates Regarding Near-Term Task Force Recommendation 2.1, Flood Hazard Reevaluation Report Project stage: Other 2014-05-30
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Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24285A2562024-10-11011 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) 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-2024-001-01, 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 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator 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 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 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 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 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 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 ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes 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) 2024-09-27
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10 CFR 50.54(f)DWIGHT C. MIMS Senior Vice President, Nuclear Regulatory
& Oversight Palo Verde Nuclear Generating Station aps P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623 393 5403 102-06850-DCM/MAM/PJH March 10, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 2. NRC Letter, Prioritization of Response Due Dates for Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated May 11, 2012 3. NRC Letter, Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 1, 2013
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 APS Extension Request for Flooding Hazard Reevaluation Submittal On March 12, 2012, the U. S. Nuclear Regulatory Commission (NRC) issued Reference 1 to request information associated with Near-Term Task Force (NTTF)Recommendation 2.1 for flooding, including a reevaluation of licensees' flooding hazards. The NRC subsequently identified in Reference 2 the submittal date to report the results of the flooding hazard reevaluation for the Palo Verde Nuclear Generating Station (PVNGS), a Category 2 plant, as March 12, 2014. Reference 3 provides guidance regarding request for extensions of the hazard reevaluation submittal dates.A member of the STARS (strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak -Diablo Canyon
- Palo Verde -Wolf CreekA I 102-06850-DCM/MAM/PJH ATTN: Document Control Desk U.S. Nuclear Regulatory Commission APS Extension Request for Flooding Hazard Reevaluation Submittal Page 2 Arizona Public Service Company (APS) requests an extension of the scheduled submittal date for the flooding hazard reevaluation report to December 12, 2014. In accordance with Reference 3, the following information is provided as requested:
Reason for the extension:
Reference 1, Enclosure 2, Flooding, Request 1, Hazard Reevaluation Report, Item 1.b requires evaluation of the flooding hazard for each flood causing mechanism, based on present-day methodologies and regulatory guidance of each flood causing mechanism that may impact the site.Reference 1, Enclosure 2, Item 1.d, also requires the flooding hazard reevaluation report to include interim evaluations and actions taken or planned to address any higher flooding hazards relative to the design basis, prior to completion of an integrated assessment, if the assessment is required.APS requires additional time to complete review and validation of the flooding hazard reevaluation results by independent consultants.
These reviews are necessary to ensure further interim evaluations or actions are prescribed, if needed, to provide the complete flooding hazard reevaluation report. Reference 3 emphasizes that incomplete hazard reports would not be of substantive benefit for staff review and would not be acceptable.
Therefore, APS concludes the continuing external validation and review of the current results are necessary to provide a complete flooding hazard reevaluation report that affords the maximum safety and regulatory benefit.This extension is justified on the following basis: a. The cover letter of Reference 1 states that the current regulatory approach and the resultant plant capabilities provide confidence that an accident with consequences similar to the Fukushima accident is unlikely to occur in the United States. Reference 1 concludes that continued plant operation and the continuation of licensing activities do not pose an imminent risk to public health and safety.b. APS has completed walkdowns of the PVNGS site which verified the current flooding licensing basis is being met. Therefore, PVNGS is protected from current design basis flood events.c. The events being analyzed in the flooding hazard reevaluation are beyond the plant's design and licensing basis. The reevaluation results do not, therefore, constitute an operability concern.d. The current licensing bases and the previously submitted flooding hazard walkdown report, dated November 27, 2012, screened out flood hazards for probable maximum storm surge and seiche, probable maximum tsunami flooding, ice effects, and channel diversions because these hazards are not 102-06850-DCM/MAM/PJH ATTN: Document Control Desk U.S. Nuclear Regulatory Commission APS Extension Request for Flooding Hazard Reevaluation Submittal Page 3 credible at PVNGS. The remaining reevaluated flooding hazards, local intense precipitation (LIP) and probable maximum flood (PMF) are very low probability events. The time frame of the submittal extension is short, relative to the probability of occurrence of the flood events being evaluated, and would result in an insignificant contribution to overall risk.e. The flooding hazard reevaluation report would be issued prior to the submittal date for Category 3 plants, identified in Reference 2, as March 12, 2015.Those plants were assigned that due date partially based on their susceptibility to the hazards that were screened out by the PVNGS flooding hazard evaluation.
Since the submittal date extension, is prior to the Category 3 plant submittal date, the extended due date provides the requested information within the established priority scheme established in Reference 2.For these reasons the duration of the extension request is reasonable and will not impact safe plant operation.
APS will submit the flooding hazard reevaluation to the NRC by December 12, 2014.No commitments are being made to the NRC by this letter.Should you have any questions concerning the content of this letter, please contact Mark McGhee, Department Leader, Regulatory Affairs, at (623) 393-4972.I declare under penalty of perjury that the foregoing is true and correct.Executed on (Date)Sincerely, DCM/MAM/PJ H cc: E. J. Leeds M. L. Dapas J. K. Rankin A. E. George M. A. Brown L. M. Regner NRC Director, Office of Nuclear Reactor Regulation NRC Region IV Regional Administrator NRC NRR Project Manager NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS NRC NRR/JLD/JPMB Project Manager