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Category:Letter
MONTHYEARML24241A2542024-08-28028 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) 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 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 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 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 ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 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 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) 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 Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 2024-08-08
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARML19116A2462019-04-26026 April 2019 SR-2019-001-00 for Palo Verde Nuclear Generating Station (PVNGS) Unit 1, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML18306A7622018-11-0101 November 2018 Special Report 2-SR-2018-001-00 for Palo Verde Nuclear Generating Station (Pvngs), Unit 2, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML1109701512011-04-0101 April 2011 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML1000400662009-12-22022 December 2009 30-Day Report Pursuant to 10 CFR 50.46(a)(3)(ii) and Submittal of Large Break Loss of Coolant Accident Reanalysis Results ML0907005532009-02-24024 February 2009 LER for Palo Verde, Units 1 and 3, Regarding Special Reports 1-SR-2009-001-00, 3-SR-2009-001-00 on Fuel Building Ventilation System High Range, Radioactive Gaseous Effluent Monitor Inoperable ML0524307122005-08-23023 August 2005 Special Report 3-SR-2005-002, Report of Boron Deposit at Control Element Drive Mechanism Vent ML0511601862005-04-14014 April 2005 Special Report 1-SR-2005-001 of Boron Deposit at Control Element Drive Mechanism Vent ML0433402652004-11-19019 November 2004 Special Report 3-SR-2004-003 Re Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable ML0423005132004-08-0606 August 2004 Special Report 3-SR-2004-001 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0423005092004-08-0606 August 2004 Unit I, Special Report 1-SR-2004-003 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0429603932004-07-0505 July 2004 Draft Preliminary Root Cause of Failure Analysis 13.8kV Breaker Failures During Losss of Switchyard Event ML0328804092003-10-0101 October 2003 Special Report 3-SR-2003-04 Regarding Boron Deposit at Control Element Drive Mechanism Vents ML0328703072003-10-0101 October 2003 Special Report 1-SR-2003-002 Re Boron Deposit at Control Element Drive Mechanism Vent ML0204202202002-01-0303 January 2002 Special Report 2-SR-2001-001 Regarding Post Accident Sampling System Being Inoperable 2019-04-26
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ODCM 2.1 MARIA L. LACAL Se ni or Vice President Nu clea r Reg ul atory and Ove rsight Palo Verde Nuclear Generati ng Station P.O. Box 52034 Phoe nix, AZ 85072 Mai l Station 7605 Tel 623 393 649 1 102-07910-M LL/SPD April 26, 2019 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 1 Docket No. STN 50-528 /License No. NPF 51 Special Report 1-SR-2019-001-00 Enclosed please find Special Report 1-SR-2019-001-00, wh ich is prepared and submitted pursuant to PVNGS Offsite Dose Calculation Manual requirements . This report discusses the nonfunctionality of a fuel building ventilation system high range radioactive gaseous effluent monitor for more than 7 days.
Copies of this Special Report are being forwarded to the Nuclear Regulatory Commission (NRC), NRC Region IV, and the Senior Resident Inspector.
Arizona Public Service Company makes no commitments in this letter. If you have questions regarding this submittal, please contact Matthew Kura, Department Leader, Nuclear Regulatory Affairs, at (623) 393-5379 .
Sincerely, MLL/SPD
Enclosure:
Special Report 1-SR-2019-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional cc: S. A. Morris NRC Reg ion I V Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector PVNGS A member of the STARS Alliance LLC Callaway
Enclosure Special Report 1-SR-2019-001-00 Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional
Palo Verde Nuclear Generating Station Special Report 1-SR-2019-001-00 Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional Docket No. STN 50-528, Unit 1 Reporting Requirement:
The Palo Verde Nuclear Generating Station Offsite Dose Calculation Manual revision 27 (ODCM) includes functionality requirements for radioactive gaseous effluent monitoring instrumentation. Action 42 of Table 2-1, specifies the following: "With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- a. Either restore the nonfunctional channel(s) to FUNCTIONAL status within 7 days of the event, or
- b. Prepare and submit a Special Report to the Commission within 14 days following the event outlining the action(s) taken, the cause of the nonfunctionality, and the plans and schedule for restoring the system to FUNCTIONAL status."
Initial Conditions:
At 0427 Mountain Standard Time (MST) on April 13, 2019, Unit 1 was in a refueling outage. The fuel building ventilation system high range radioactive gaseous effluent monitor (RU-146) was declared nonfunctional when its 120 VAC Class 1E power supply was removed from service in support of a unit modification.
The monitor RU-146 was not restored to FUNCTIONAL status within 7 days.
Actions Taken:
The Preplanned Alternate Sampling Program was initiated to "monitor appropriate parameters" pursuant to ODCM Requirement ACTION 42 of Table 2-1 on April 12, 2019, at 0840 MST in anticipation of the planned 120 VAC Class 1E power supply outage.
Portable area monitors were placed on the roof to measure dose rates in the event of an accident. The parameters being monitored were post accident high range conditions, specifically dose rates due to gases. On April 21, 2019, at 1314 MST, RU-146 was declared FUNCTIONAL after restoration of power and completion of the channel check surveillance test.
Cause of the Nonfunctionality:
There was no monitor malfunction associated with the nonfunctionality of RU-146. The cause for exceeding the 7 days allowed by ODCM Action 42 of Table 2-1 was removal of its associated 120 VAC Class 1E power.
Plans and Schedule for Restoring the System to FUNCTIONAL Status:
The monitor was restored to a functional status as described above.
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