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Category:Letter
MONTHYEARML24019A2012024-01-19019 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 ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] Category:Proprietary Information Review
MONTHYEARML18333A0712018-12-0404 December 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated May 16, 2018, Executed by Mr. Philip A. Opsal, from Framatome, Inc. ML18333A2272018-12-0404 December 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated October 18, 2018, Executed by Mr. Bruce Rash of APS ML17158B2012017-06-22022 June 2017 Palo Verde, Units 1, 2, and 3 - Request for Withholding Information from Public Disclosure, 6/1/17 affidavit Executed by J. Gresham, Westinghouse; Technical Analysis Next Generation Fuel Implementation Amendment Request (CAC MF8076-MF8081) ML17145A2732017-06-15015 June 2017 Request for Withholding Information from Public Disclosure ML17079A4462017-03-27027 March 2017 Request for Withholding Information from Public Disclosure ML16190A2272016-07-13013 July 2016 Request for Withholding Information from Public Disclosure, 6/30/16 Affidavit Executed by J. Gresham, Westinghouse; Technical Analysis Next Generation Fuel Implementation Amendment Request ML16014A0022016-01-14014 January 2016 Request for Withholding Information from Public Disclosure - 10/8/15 Affidavit Executed by J. Gresham, Westinghouse Electric Company LLC Re WCAP-18051-P Dated October 2015 ML15209A6662015-08-10010 August 2015 Request for Withholding Information from Public Disclosure - 7/10/15 Affidavit Executed by J. Gresham, Westinghouse, Re Five Proprietary Documents in Support of Relief Request 53 - Approval of an Alternative to Flaw Removal (TAC No ML15043A2232015-03-0909 March 2015 Request for Withholding Information from Public Disclosure, 1/15/2015 Affidavit Executed by P. Opsal, Areva, Inc. Response to Relief Request 52 Request for Additional Information ML14150A1692014-06-10010 June 2014 Request for Withholding Information from Public Disclosure, 4/18/14 Affidavit Executed by P. Opsal, Areva, Inc. and 4/29/14 Affidavit Executed by N. Hottle, Areva, Inc. Six Proprietary Documents ML14042A1822014-02-27027 February 2014 Request for Withholding Information from Public Disclosure - 1/10/14 Affidavit Executed by J. Gresham, Westinghouse WCAP-16011-P-A, Revision 0 ML14006A2242014-01-24024 January 2014 Request for Proprietary Withholding of Information - 9/25/13 Affidavit Executed by J. Gresham, Westinghouse WCAP-17787 ML0712401132007-05-0808 May 2007 Request for Withholding Information from Public Disclosure - Westinghouse LLC ML0624401622006-10-13013 October 2006 Request for Withholding Information from Public Disclosure (CAW-06-2137) ML0627900232006-10-12012 October 2006 Request for Withholding Information from Public Disclosure (CAW-05-1997) ML0525601382005-07-0505 July 2005 Redacted Version of Proprietary Submittal Dated February 15, 2005 Regarding Safety Significance Evaluation of ECCS Containment Sump Voided Piping ML0514702602005-05-26026 May 2005 Request for Withholding Information from Public Disclosure (Palo Verde Nuclear Generating Station, Docket Nos. 50-528, 50-529, 50-530) ML0414000502004-05-17017 May 2004 Withholding from Public Disclosure, WCAP-15817-P, Revision 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation... (CAW-04-1803) ML0329012052003-10-15015 October 2003 Palo Verde Ngs, Units 1, 2&3- Request for Withholding Information from Public Disclosure for Core Protection Calculator Upgrade Amend Request.(Tac. MB6726/MB6727/MB6728) ML0312602842003-05-0606 May 2003 Request for Withholding Information from Public Disclosure, Request for Relief from NRC Order EA-03-009 on Interim Requirements for Reactor Vessel Head Inspections ML0235002042002-12-16016 December 2002 Request for Withholding Info from Public Disclosure for Bulletin 2002-01 ML0228405102002-10-25025 October 2002 (Units 1, 2 &3), Withholding from Public Disclosure, Steam Generator Tube Inspection, TAC No. MB6378 2018-12-04
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May 26, 2005 Mr. Gregg R. Overbeck, Senior Vice President, Nuclear Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE (PALO VERDE NUCLEAR GENERATING STATION, DOCKET NOS. 50-528, 50-529, 50-530)
Dear Mr. Overbeck:
Arizona Public Service (APS) Companys letter (102-05195-GRO/DGM/RAS) and affidavit dated December 27, 2004, submitted information regarding recirculation sump void testing and preliminary results from a probabilistic risk assessment. In this letter, APS requested that the information in Enclosure 2 to the letter related to special pump tests and a risk evaluation based on the test results be withheld from public disclosure pursuant to 10 CFR 2.390. At the request of the NRC staff, APS provided a redacted version of this submittal (letter 102-5208-SAB/GAM) on February 4, 2005, that was suitable for public release. The redacted version of your submittal was subsequently posted on the NRCs public website (ADAMS accession number ML050450353).
Your affidavit that was enclosed with your letter of December 27, 2004, stated that the preliminary safety significance evaluation of emergency core cooling system containment sump voided piping constitutes proprietary commercial information that should be held in confidence from regulatory agencies of other countries and from the public by the NRC pursuant to the policy reflected in 10 CFR 2.390(a)(4) and 9.17(a)(4), because:
- 1. The information sought to be withheld from public disclosure is owned and has been held in confidence by APS and associated companies who participated in developing this information for APS.
- 2. This information is of a type that is customarily held in confidence by APS, and there is a rational basis for doing so because the information contains the proprietary confidential intellectual property of APS.
- 3. The information is being transmitted to the NRC in confidence.
- 4. The information is not available in public sources or available information has not been previously employed in the same original manner or method to the best of your knowledge and belief.
Arizona Public Service Company 5. Public disclosure of this information would create substantial harm to the competitive position of APS by disclosure of APS' proprietary confidential intellectual property.
Disclosure of this information to regulatory agencies in other countries would also create substantial harm to the competitive position of APS by disclosing information to governments with ownership and interest in competitors.
We have carefully reviewed both your original December 27, 2004, letter and the February 4, 2005, redacted letter and the information contained in your request. We have concluded that some of the material that was redacted may be withheld in accordance with 10 CFR 2.390, but that certain other material should be released and placed in the Public Document Room (PDR). to this letter details that information which we do not believe meets the criteria of 10 CFR 2.390(a) for public withholding. The attachment provides an explanation for each item that we believe should be released to the public that you originally characterized as proprietary and redacted from your February 4, 2005, submittal.
In accordance with 10 CFR 2.390(c)(2), this information is being forwarded to you as notice that the information will be placed in the Public Document Room fifteen (15) days from the date of this letter. If within fifteen (15) days of this letter, you provide additional reasons why this information should not be released, the NRC will withhold release pending review of your request. The NRC will consider your request in light of the applicable statues and regulations and will advise you prior to taking any further action.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the document. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
Sincerely,
/RA/
Troy Pruett, Chief Project Branch D Division of Reactor Projects Dockets: 50-528 50-529 50-530 Licenses: NPF-41 NPF-51 NPF-74
Arizona Public Service Company Electronic distribution by RIV:
Regional Administrator (BSM1)
DRP Director (ATH)
DRS Director (DDC)
DRS Deputy Director (KSW)
Senior Resident Inspector (GXW2)
Branch Chief, DRP/D (TWP)
Senior Project Engineer, DRP/D (GEW)
Team Leader, DRP/TSS (RLN1)
SISP Review Completed: _TWP___ ADAMS: / Yes G No Initials: __TWP_
/ Publicly Available G Non-Publicly Available G Sensitive / Non-Sensitive R:\_PV\2005\Proprietary Letter 12-27-04.wpd RIV:SPE:DRP/D D:DRP RC C:DRP/D GEWerner ATHowell KDFuller TWPruett
/RA/ AVegel for /RA/ /RA/
5/4/05 5/5/05 5/24/05 5/26/05 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
Attachment From Enclosure 2 - Information Listed as Proprietary Page 5:
A series of thermal hydraulic analyses of the Palo Verde Reactor Coolant System and Containment were performed using the Westinghouse CENTS code and the [ ] code. These analyses established the expected reactor coolant and containment environment conditions that would exist at the time of RAS for a spectrum of LOCA break sizes. Operator actions, as prescribed in the Palo Verde Emergency Operating Procedures (EOPs), to initiate a cool down and depressurize the RCS upon diagnoses of a LOCA were explicitly considered in the analyses. In this way, best-estimate parameters such as RCS and containment pressures at time of RAS were established.
With the exception of [ ], no proprietary information was found in this statement. This is a general description of the analysis and contains no specific information that would benefit a competitor.
Page 7:
....Dr. M. Ishii of Purdue University, an expert in two-phase modeling and experiments, This statement does not contain proprietary information and Dr. Ishiis background and his expertise were discussed at the Regulatory/Enforcement Conference attended by members of the public.
Page 9:
Figure and Figure 2-1 Phase 2 Test Arrangement This figure was shown during the Regulatory/Enforcement Conference in which members of the public attended.
Page 17:
....injected....
This one word in conjunction with what remains is not proprietary information.
Page 20 and 21:
The eight-stage HPSI pump demonstrated a very high tolerance for air ingestion. This is consistent with the limited data in the literature regarding multi-stage pumps under air ingestion conditions. The following figure (Figure 3-7) is a reproduction of Figure 3-8 from NUREG/CR-2792. As reported in the NUREG, performance degradation for a multi-stage pump is much less pronounced. The author of the test report cited in the NUREG (Reference 32 of the NUREG) attributes this to the fact that air is raised to a higher pressure (i.e. compressed) at each stage and has less effect on the performance of the next stage.
Figure and Figure 3-7 influence of Number of Stage on Performance Degradation (from NUREG/CR-2792)
The statement is not proprietary since it is based on publically available information, NUREG/CR-2792 is publically available.
Page 22:
....the Westinghouse CENTS code and the [ ] code.......the expected reactor coolant system and containment environment....such as RCS and containment pressures...
This information contained within the first paragraph described the general methodology for their analysis and contains no proprietary information. In addition, Figure 4-1, which is not marked as proprietary, on the same page, contains much of this information.
Page 23:
....construct system resistance curves and....
Considering the RCS pressure at RAS for the various break sizes described in Figure 4-1, system resistance curves can then be developed using the following relationship:
TDH = 144/(PRCS - PCONT) + (ZRCS - ZSUMP) + CsysQ2
[ ]. The elevation of the RCS is assumed to be the centerline of the cold legs at [ ]. The elevation of the sump is taken as the minimum flood level elevation of [ ]. Containment pressure is assumed to be equal to be [ ]. The system resistance curves are then developed as shown in Figure 4-2.
This information is general engineering knowledge and as such is not proprietary.
Page 24:
....and the system resistance curves developed above,...
This contains no proprietary information. The description of the test, contained on this page, describes the above statement and how pump performance was evaluated.