Letter Sequence Response to RAI |
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MONTHYEARML0417401072004-06-21021 June 2004 Request for Additional Information Security Plan Sections 10-19 Project stage: RAI ML0419504002004-07-0909 July 2004 Request for Additional Information Training and Qualification Plan Project stage: RAI ML0421100872004-07-23023 July 2004 RAI, Safeguards Contingency Plan and Section 9.4.1 of the Physical Security Plan (TAC Nos. MC2950, MC2951, and MC2952) Project stage: RAI ML0423105032004-08-13013 August 2004 Response to Request for Additional Information Safeguards Contingency Plan, Section 9.4.1 of the Physical Security Plan and the July 8, 2004 NRC Letter to Power Reactor Security Work. Project stage: Response to RAI ML0425902352004-09-10010 September 2004 Implementation Status of Independent Spent Fuel Storage Installation Interim Compensatory Measures Project stage: Other ML0428703252004-10-0101 October 2004 Response to Security Plan Provisions for Enhanced Owner Controlled Area Surveillance and Response Project stage: Other ML0431800072004-10-28028 October 2004 Administrative Change to Facility Operating License in Conjunction with the Commission Order EA-03-086 Regarding Revised Design Basis Threat and Revisions to Physical Security Plan, Training and Qualification Plan. Project stage: Other ML0435802332004-12-16016 December 2004 APS Response to NRC Safety Evaluation of the PVNGS Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Project stage: Other 2004-06-21
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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 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
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"SAFEGUARDS INFORMATION" LWmp 10CFR73.45 Gregg R. Overbeck Mail Station 7602 Palo Verde Nuclear Senior Vice President TEL (623)393-5148 P.O. Box 52034 Generating Station Nuclear FAX (623) 393-6077 Phoenix, AZ 85072-2034 102-05138-GRO/SAB/DGM August 13, 2004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Reference:
- 1) Order dated April 29, 2003, Requiring Compliance with Revised Design Basis Threat ("Order EA-03-086" or "Order")
- 2) Letter dated 07/23/2004, NRC to G. R. Overbeck, Palo Verde Nuclear Generating Station, Units 1,2, and 3 - Request for Additional Information re: Safeguards Contingency Plan and Section 9.4.1 of the Physical Security Plan (TAC Nos. MC2950, MC2951, and MC2952)
- 3) Letter dated 07/08/2004, NRC to Power Reactor Security Working Group, NRC Staff Requests for Additional Information on Security Plans Submitted by Licensees Pursuant to the April 29, 2003, Design Basis Threat Order (Supplement)
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket No. STN 50-528; 50-529; 50-530 License No. NPF-41; NPF-51; NPF-74 Response to Request for Additional Information re: Safeguards Contingency Plan, Section 9.4.1 of the Physical Security Plan and the July 8, 2004 NRC Letter to Power Reactor Security Working Group (TAC Nos. MC2950, MC2951, and MC2952)
Dear Sirs:
The NRC issued an Order dated April 29, 2003, requiring compliance with revised Design Basis Threat ("Order EA-03-086" or "Order', Reference 1) and other security related Orders (collectively "Orders") for the Palo Verde Nuclear Generating Station.
Order EA-03-086 imposes license conditions on nuclear power plants licensed pursuant to the Atomic Energy Act of 1954 and Title 10 of the Code of Federal Regulations.
Section III.A of the Order requires licensees to revise their physical security plans and safeguards contingency plans to provide protection against the revised design basis threat (DBT) set forth in Attachment 2 to the Order. Section Il.A also requires licensees to revise the security force training and qualification plan to implement the revised DBT.
ENCLOSURE(S) CONTAIN(S)
SAFEGUARDS INFORMATION UPON SEPARATION THIS PAGE ISDECONTROLLED ZSPEBUtFARDS INFORMATION" 8 0o*
S eSAFEGUARDS INFORMATION J. S. Nuclear Regulatory Commission Response to Request for Additional Information re: Safeguards Contingency Plan, Section 9.4.1 of the Physical Security Plan and the July 8, 2004 NRC Letter to Power Reactor Security Working Group (TAC Nos. MC2950, MC2951, and MC2952)
Page 2 These revised plans, along with an implementation schedule, were required to be submitted to the Commission for review and approval no later than April 29, 2004.
In Reference 2, the NRC requested additional information, necessary in order to complete its evaluation based on its review of the Safeguards Contingency Plan and Section 9.4.1 of the PVNGS physical security plan. This information is contained in .
In Reference 3, the NRC requested additional information, necessary in order to complete its evaluation based on the information contained in its letter to the Power Reactor Security Working Group. PVNGS' response for that information is contained in .
If you have questions regarding this submittal, please contact Daniel G. Marks, Section Leader, Regulatory Affairs, at (623) 393-6492.
Arizona Public Service Company makes no commitments in this letter.
A telephone conversation was held with Messrs. B. J. Benney (NRC), D. G. Marks (APS) and E. E. Lumley (APS) on 07/28/2004. It was agreed in that conversation that submittal of this response on 08/13/2004 would be acceptable in order to incorporate the results of meetings between the NRC, NEI and the Power Reactor Security Working Group. APS appreciates the extension and resultant opportunity to include this consensus input.
The material enclosed herewith contains Safeguards Information as defined by 10 CFR 73.21 and its disclosure to unauthorized individuals Is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended.
Sincerely, 4
Nor 4;.R.'4xbeck GRO/SAB/DGM/dgm
Enclosures:
- 1) Response to the July 23, 2004 NRC Letter associated with Section 9.4.1 of the Physical Security Plan, Sections 1.1, 1.3, 2.2, Responsibility Matrix, Sections 3.5,4.5 and 7 of the Safeguards Contingency Plan
- 2) RAI Update to the NRC Letter dated July 8,2004 ENCLOSURE(S) CONTAIN(S)
SAFEGUARDS INFORMATION UPON SEPARATION THIS PAGE IS DECONTROLLED SAFEGUARDS INFORMATION