Letter Sequence Request |
---|
|
|
MONTHYEARML20105A4812020-04-14014 April 2020 Independent Spent Fuel Storage Installation (ISFSI) - Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs Project stage: Request ML20105A4362020-04-14014 April 2020 2019 Annual Environmental Operating Report Project stage: Request ML20356A2922020-12-21021 December 2020 Independent Spent Fuel Storage Installation (ISFSI) - Subsequent Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs Project stage: Request ML20357A0552020-12-23023 December 2020 Subsequent Request for Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0238 (COVID-19)) Project stage: Approval 2020-12-23
[Table View] |
|
---|
Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 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 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 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 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 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 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 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 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 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 ML24109A0712024-04-22022 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) 2024-09-27
[Table view] |
Text
10 CFR 26.9 BRUCE J. RASH Vice President, Nuclear 102-08094-BJR/SPD Engineering/Regulatory April 14, 2020 Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7602 Tel 623.393.5102 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
NRC Letter from H. Nieh to NEI dated March 28, 2020, U.S. NUCLEAR REGULATORY COMMISSION PLANNED ACTIONS RELATED TO THE REQUIREMENTS FOR WORK HOUR CONTROLS DURING THE CORONAVIRUS DISEASE 2019 PUBLIC HEALTH EMERGENCY, [Agencywide Document Access and Management System (ADAMS) Accession Number ML20087P237]
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 and Independent Spent Fuel Storage Installation (ISFSI)
Docket Nos. STN 50-528/529/530 and 72.44 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs As a result of the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE)
Arizona Public Service Company (APS) has proactively determined that PVNGS can no longer meet the work-hour controls of 10 CFR 26.205(d) for the covered workers noted below. By implementing the alternative work-hour controls, APS is proactively taking steps to complete necessary work, testing, and inspections in a manner that supports both worker and neighboring community safety to limit the spread of COVID-19.
This request is being made in support of the efforts to maintain the recommendations made by the Centers for Disease Control and Prevention (CDC) related to social distancing, worker screening, and limiting close-proximity work. Particularly given the challenges that COVID-19 could present in the immediate community surrounding PVNGS, leveraging the alternative work-hour controls will assist in facilitating further worker and community protection as APS continues the current Unit 2 refueling outage and daily operation of Units 1 and 3.
As the U.S. Departments of Homeland Security and Energy have stated in their guidance, the electric grid and nuclear plant operation make up the nation's critical infrastructure similar to the medical, food, communications, and other critical industries. The PVNGS daily operation of Units 1 and 3 and the current Unit 2 refueling outage must be conducted such that all three units are available when needed, including during the critical peak summer loads.
A member of the STARS Alliance LLC Callaway
102-08094-BJR/SPD ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Part 26 Exemption Request Page 2 In accordance with the Reference, the following information is provided in the table below:
- Positions (as described in § 26.4(a)(1) - (5)) for which either current work-hour controls will be maintained, or for which alternative controls will be required as a preventive measure.
- The date and time for which alternative controls (if necessary) will be implemented for the listed positions.
Positions Compliance Begin Implementation 26.4(a)(1) Operators Will phase in site-specific Upon NRC Approval alternative work-hour controls as defined in the Reference, as necessary, to minimize transition issues.
26.4(a)(2) Health Physics and Will phase in site-specific Upon NRC Approval Chemistry alternative work-hour controls as defined in the Reference, as necessary, to minimize transition issues.
26.4(a)(3) PVNGS Fire Will phase in site-specific Upon NRC Approval Department alternative work-hour controls as defined in the Reference, as necessary, to minimize transition issues.
26.4(a)(4) Maintenance Will phase in site-specific Upon NRC Approval alternative work-hour controls as defined in the Reference, as necessary, to minimize transition issues.
26.4(a)(5) Security Will phase in site-specific Upon NRC Approval alternative work-hour controls as defined in the Reference, as necessary, to minimize transition issues.
The PVNGS site-specific COVID-19 PHE fatigue-management controls are consistent with the constraints outlined in the Reference and its attachment.
APS will continue to follow the fatigue-management controls, behavioral observation requirements, and self-declaration allowances in accordance with the current work-hour control program and station Procedure 01DP-0AP17, Managing Personnel Fatigue.
Upon NRC approval, APS will implement the alternative controls described below, consistent with the Reference for the management of fatigue during the period of the exemption.
These controls ensure that covered workers are subjected to the following minimum controls:
(1) not more than 16 work-hours in any 24-hour period and not more than 86 work-hours in any 7-day period, excluding shift turnover;
102-08094-BJR/SPD ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Part 26 Exemption Request Page 3 (2) a minimum 10-hour break is provided between successive work periods; (3) 12-hour shifts are limited to not more than 14 consecutive days; (4) a minimum of 6 days off are provided in any 30-day period; and (5) requirements are established for behavioral observation and self-declaration during the period of the exemption.
The requirements of 10 CFR 26.33, Behavioral observation; 10 CFR 26.209, Self-declarations; and 10 CFR 26.211, Fatigue assessments, remain in effect during the period of the exemption. These requirements provide reasonable assurance that should personnel become impaired due to fatigue, requirements and processes are in place to identify the impairment through observation by plant staff or by worker self-declaration, and to assess and address instances of impairment through fatigue assessments.
Upon NRC approval, APS will implement the alternative controls described in the Reference for the management of fatigue during the initial period of 60 days. Near the end of the 60-day period, if the COVID-19 conditions persist at the site affecting staffing requirements and the efforts to maintain CDC, state, and local recommendations related to social distancing, worker screening, and limiting close-proximity work, as well as the particular concern of the COVID-19 challenge in the immediate community of PVNGS, an additional email supplement request may be submitted to extend the 60-day implementation period exemption.
APS requests NRC approval by no later than April 17, 2020, to expedite implementation of the safety benefits of the alternative controls.
APS makes no commitments in this letter. Should you need further information regarding this exemption request, please contact Matthew Kura, Department Leader, Nuclear Regulatory Affairs, at (623) 393-5379.
Sincerely, Rash, Bruce Digitally signed by Rash, Bruce (Z77439)
(Z77439) DN: cn=Rash, Bruce (Z77439)
Date: 2020.04.14 12:51:44 -07'00' BJR/SPD cc: S. A. Morris NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS J. L. Dixon NRC Branch Chief for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS