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Category:Code Relief or Alternative
MONTHYEARML24297A6212024-10-22022 October 2024 Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300 ML22124A2412022-05-12012 May 2022 Relief Request 67 for an Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML22049A0572022-02-23023 February 2022 Relief Request 69 to Extend Inservice Inspection of Containment Tendon by Four Months Due to the Covid 19 Pandemic (EPID L 2022 Llr 0011 (Covid 19)) ML21278B0912021-10-0606 October 2021 Presubmittal Meeting with Arizona Public Service Company Regarding Relief Request No. 68 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (EPID L-2021-LRM-0104) (Slides) ML21228A1042021-08-12012 August 2021 RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (EPID L-2021-LLR-0050) (Email) ML21089A0102021-04-0202 April 2021 Relief Request 66 to Defer Inservice Inspection of Containment Tendon by One Year Due to Covid-19 Pandemic ML20088A5332020-03-27027 March 2020 Relief Request 65 - Unit 2, COVID-19, Request for Relief from Bottom Mounted Instrumentation Nozzles and a Pressurizer Nozzle to Surge Line Weld Overlay Examination ML19263F8752019-09-20020 September 2019 Relief Request VRR-01: Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)C3)(xi) ML19107A3722019-04-19019 April 2019 Relief Request 62 Regarding Proposed Alternative Pressurizer Heater Sleeve Repairs ML19044A6412019-02-19019 February 2019 Relief Request No. 58 for the Third 10-Year Inservice Inspection Interval, Request for Relief from the American Society of Mechanical Engineers for Certain Class 1 and Class 2 Welds ML18285A0292018-10-19019 October 2018 Relief Request 59 for the Deferral of Reactor Vessel Beltline Region Interior Attachment Examinations ML18079A7252018-03-17017 March 2018 Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML18016A1722018-01-12012 January 2018 Relief Request 50 - Request for Alternative to American Society of Mechanical Engineers Section XI Requirements for Pressure Retaining Boundary During System Leakage Tests ML17074A2092017-03-16016 March 2017 Relief Request GRR-01 to ASME Code Case OMN-20 for Third 10-Year Interval Pump and Valve Inservice Testing Program ML16172A0382016-06-23023 June 2016 Relief Request 54 to Approve an Alternative to Flaw Removal for Reactor Coolant Pump 2A Suction Pressure Instrument Nozzle, for the Third 10-Year Inservice Inspection Interval ML15238B6612015-09-15015 September 2015 Relief Request 53, Alternative to ASME Code Section XI Requirements Related to Flaw Removal ML15079A0062015-03-30030 March 2015 Relief Request 52 - Request for Approval of Alternate to Flaw Removal, Flaw Characterization and Successive Examinations, for the Remainder of Its Useful Life ML14093A4072014-04-10010 April 2014 Relief Request 51, Alternative to ASME Code for Flaw Removal, Reactor Vessel Bottom-mounted Instrumentation Nozzle, Third 10-Year ISI Interval ML13091A1772013-04-12012 April 2013 Relief Request 48 - Alternative to ASME Section III, Phased Array Ultrasonic Exam Techniques in Lieu of Radiography for Remainder of Third 10-Year Inservice Inspection Interval ML13085A2542013-04-0404 April 2013 Relief Request 49, Alternative to ASME Code, Section XI, for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval ML12257A1412012-09-18018 September 2012 Request for Relief to Use Subsequent Edition and Addenda of ASME Code, Section XI, for Examination Categories B-L-1, B-M-1, and C-G, for the Third 10-Year Inservice Inspection Interval ML1026700802010-10-14014 October 2010 Relief Request No. 47, from Certain ASME Code Requirements for Reactor Vessel Nozzle to Vessel Welds for Second 10-Year Inservice Inspection Interval ML1025001432010-09-21021 September 2010 Relief Request No. 45 from Certain ASME Code Class 1 Weld and Component Volumetric Exams of Reactor Vessel Outlet Nozzles for Second 10-Year Inservice Inspection Interval ML1021604872010-08-27027 August 2010 Relief Request No. RR-44, Reactor Vessel Weld Visual Examination Interval Extension for Third 10-Year Inservice Inspection Interval ML0921603982009-07-17017 July 2009 Submittal of Relief Request from the American Society of Mechanical Engineers (ASME) Code, Section XI - Relief Request No. 46 ML0917001972009-07-0202 July 2009 Relief Request No. 39, Alternative to Repair Weld Methods, ASME Code, Section XI for Remainder of Operating License ML0916304492009-06-0202 June 2009 Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Pump Relief Request PRR-08, Revision 1 ML0905801992009-02-17017 February 2009 Relief Request 41, to Use Appendix I of ASME Code Case N-729-1 ML0830105722008-11-10010 November 2008 Relief Request Nos. 18 and 36, Proposed Alternatives for the Third Interval 10-Year Inservice Inspection Program Interval ML0825905562008-10-0202 October 2008 Relief Request No. 34 for Second 10-Year Inservice Inspection Interval ML0822506752008-07-11011 July 2008 American Society of Mechanical Engineers (ASME) Code, Section XI, Request for Approval of an Alternative Repair Method - Relief Request No. 39 ML0817002812008-06-0606 June 2008 Request for Extension to Complete the Final Confirmatory Analysis and Validation of Containment Sump Strainers Associated with NRC GL-04-002 ML0715600082007-06-21021 June 2007 Relief Request Nos. 36 and 37 Alternatives to Weld Overlay Requirements for Inservice Inspection ML0711400332007-05-16016 May 2007 Supplement to Relief Request No. 34 Request to Extend the Second 10-Year Inservice Inspection Program Interval for Reactor Vessel Weld Examinations ML0629302082006-11-0303 November 2006 Relief Request No. 32, Risk-Informed Inservice Inspection Program ML0626401992006-10-0404 October 2006 Relief Request No. 35 Request to Extend the Second 10-Year Inservice Inspection Program Interval for Reactor Vessel Visual Examinations ML0624905132006-09-20020 September 2006 Relief, Request to Extend the Second 10-Year Inservice Inspection Program Interval ML0623003332006-09-12012 September 2006 Relief Request No. 31, Revision 1, Proposed Alternative Repair for Reactor Coolant System Hot Leg Alloy 600 Small-Bore Nozzles ML0615702092006-05-26026 May 2006 Additional Information to Support the Request to Extend the Second 10-Year, American Society of Mechanical Engineers Section IX, Inservice Inspection Program Interval for Reactor Vessel Weld Examinations - Relief Request No. 34 ML0610803942006-04-0707 April 2006 Relief, Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities at PVNGS in Accordance with 10 CFR 50.55a(g)(4)(iv) ML0518901452005-06-28028 June 2005 Revision 1 to 10 CFR 50.55a(a)(3)(i) Request for Alternatives to 10 CFR 50.55a(c) Requirement to Comply with ASME Section III, Subsection NB-1120, Temperature Limits, for a Portion of the Plant Pressurizer That Was Subjected To. ML0512901232005-05-0505 May 2005 Relief, Relief Request No. 31 Proposed Alternative Repair for Reactor Coolant System Hot Leg Alloy 600 Small-Bore Nozzles ML0434201672004-11-24024 November 2004 Relief Request No. 25 for Palo Verde, Unit 2 - Relaxation from First Revised NRC Order EA-03-009 - Additional Analysis Information for Control Element Drive Mechanism (CEDM) Nozzles ML0432706262004-11-19019 November 2004 Palo Verde - Correction to Approval Letter for Relief Request No. 30 ML0328705392003-10-0909 October 2003 Relief, Inservice Inspection Program Surface Examination Requirements, (TACs MC0830, MC0831, and MC0832) ML0321105422003-07-30030 July 2003 Relief Request 23 Alternative to Temper Bead Welding Requirements for Inservice Inspection Program (Tac. MB8973, MB8974 and MB8975) ML0314000512003-05-15015 May 2003 CFR 50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Inspection Program: Relief Request 23, Pressurizer Heater Sleeves ML0302902122003-01-27027 January 2003 Relief, Requirements of American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code) Concerning Use of Electrical Discharge Machining (Edm), MB6439, MB6440 & MB6441 ML0302801692003-01-24024 January 2003 Mechanical Nozzle Seal Assembly Type 2 Code Replacement Request for Relief from 10 CFR 50.55a ML0235200682002-12-11011 December 2002 Resubmittal of 10 CFR 50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Inspection Program (Relief Request 18) 2024-10-22
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 2R24 ML23013A0912023-01-13013 January 2023 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R23 ML22189A1432022-07-0808 July 2022 Fourth 10-Year Interval, First Period Owners Activity Report Number 1R23 ML22018A2022022-01-18018 January 2022 Fourth 10-Year Interval, First Period Owners Activity Report Number 2R23 ML21341A5522021-12-0303 December 2021 Snubber Program for the Fourth 10-Year Testing Interval ML21292A1842021-10-19019 October 2021 Nd Refueling Outage Steam Generator Tube Inspection Report ML21197A2052021-07-16016 July 2021 Fourth 10-Year Interval, First Period Owners Activity Report Number 3R22 ML21047A4972021-02-16016 February 2021 Twenty-Second Refueling Outage Owners Activity, Report 1R22 ML20288A2982020-10-13013 October 2020 Refueling Outage 22 Steam Generator Inspection Report ML20203M2042020-07-17017 July 2020 Fourth 10-Year Interval, First Period Owner'S Activity Report Number 2R22 ML20054A2692020-02-19019 February 2020 Response to Request for Additional Information - Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML20028D5402020-01-24024 January 2020 Owner'S Activity Report Number U3R21 ML19291F5762019-10-18018 October 2019 Generator (Pvggs), Unit 1 - Steam Generataor Tube Inspection Ruport ML19205A2642019-07-24024 July 2019 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U1R21 ML19198A3402019-07-17017 July 2019 Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19179A3312019-06-28028 June 2019 Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19017A3452019-01-17017 January 2019 Fourth 10-Year Interval Pump and Valve Inservice Testing Program ML19010A3072019-01-10010 January 2019 Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML18306A9992018-11-0202 November 2018 Steam Generator Tube Inspection Report ML18277A2972018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 1 of 7 ML18277A3192018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 5 of 7 ML18277A3032018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 2 of 7 ML18277A3102018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update. (Part 3 of 7) ML18277A3122018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 4 of 7 ML18277A3232018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 7 of 7 ML18277A3212018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 6 of 7 ML18102B6842018-04-12012 April 2018 Third 10-Year Interval, Third Period: Owner'S Activity Report Number 1R20 Correction ML18093A3352018-03-30030 March 2018 Palo Verde, Units 1, 2 and 3 - Fourth 10-Year Interval Pump and Valve Inservice Testing Program ML18030B1382018-01-26026 January 2018 Third 10-Year Interval, Third Period: Owner'S Activity Report Number 1R20 ML17270A4242017-09-26026 September 2017 Transmittal of 20th Refueling Outage Steam Generator Tube Inspection Report ML17181A5202017-06-30030 June 2017 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R20 ML17248A5232017-05-30030 May 2017 3INT-ISI-1, Revision 5, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 1, Enclosure 1 to 102-07551-MDD/MSC ML17248A5252017-05-26026 May 2017 3INT-ISI-2, Revision 6, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 2, Enclosure 2 to 102-07551-MDD/MSC ML17054D6872017-02-23023 February 2017 Fourth 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests GRR-01, GRR-02, PRR-01, PRR-02, PRR-03, PRR-04, PRR-05, and PRR-06 ML16308A2322016-10-26026 October 2016 Steam Generator Tube Inspection Report - Refueling Outage 19 ML16180A4462016-06-24024 June 2016 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U1R19 ML16015A4542016-01-15015 January 2016 Submittal of Owner'S Activity Report (Form OAR-1) Refueling Outage 19 (U2R19) ML15267A2692015-09-23023 September 2015 Steam Generator Tube Inspection Report ML14035A4042013-08-29029 August 2013 3INT-ISI-3, Rev. 3, Palo Verde, Unit 3, 3rd Interval: Inservice Inspection Program Summary Manual ML14035A4022013-08-28028 August 2013 3INT-ISI-2, Rev. 4, Palo Verde, Unit 2, 3rd Interval: Inservice Inspection Program Summary Manual ML14035A4002013-08-22022 August 2013 INT-ISI-1, Rev. 3, 3rd Interval, Inservice Inspection Program Summary Manual ML13182A0152013-06-26026 June 2013 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R17 ML14035A3992013-05-31031 May 2013 INT-ISI-1, Rev. 2, 3rd Inspection Interval, Inservice Inspection Program Summary Manual ML14035A4012013-05-31031 May 2013 INT-ISI-2, Rev. 3, 3rd Inspection Interval, Inservice Inspection Program Summary Manual ML14035A4032013-05-31031 May 2013 3INT-ISI-3, Rev. 2, Palo Verde, Unit 3, 3rd Interval: Inservice Inspection Program Summary Manual ML12242A2492012-08-0707 August 2012 Steam Generator Tube Inspection Report ML11287A0142011-10-0404 October 2011 Revised Third 10 Year Interval Inservice Inspection Plans ML11136A1062011-05-0505 May 2011 Submittal of Steam Generator Tube Inspection Report 2024-07-11
[Table view] Category:Letter
MONTHYEARML24312A3152024-11-0505 November 2024 Independent Spent Fuel Storage Installation - Updated Annual Radioactive Effluent Release Report 2023 ML24295A0362024-10-23023 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 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 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 ML24177A3222024-06-25025 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 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 2024-09-27
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10 CFR 50.55a jAI A subsidiaryof Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06013-DCM/RJR June 02, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Reference:
APS letter 102-06009, dated May 22, 2009,
Subject:
Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Pump Relief Request PRR-08
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. STN 50-530 Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Pump Relief Request PRR-08, Revision I This correspondence revises the referenced Arizona Public Service Company (APS) request for relief from the comprehensive full flow pump testing requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance
.of Nuclear Power Plants (OM) Code 2001 Edition, 2003 Addenda.
Specifically, on May 22, 2009, APS requested and was granted verbal authorization for this relief request. The enclosure, "Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Relief Request PRR-08, Revision 1," incorporates the additional information requested by the NRC staff during the teleconference on May 22, 2009. APS requests approval of the proposed alternative for the duration of the fifteenth operating cycle of Unit 3.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance A 1U 17 Callaway - Comanche Peak
- Palo Verde - San Onofre - South Texas
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Revision 1 to Relief Request PRR-08 Page 2 No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
Sincerely, DCM/TNW/RJR/gat
Enclosure:
Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Relief Request PRR-08, Revision 1 cc: E. E. Collins Jr. NRC Region IV Regional Administrator J. R. Hall NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector
Enclosure Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing Relief Request PRR-08, Revision I
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
Relief Request PRR-08, Revision 1
Background
During the Palo Verde Unit 3 fourteenth refueling outage (U3R1 4), the High Pressure
.Safety Injection (HPSI) B pump outboard mechanical seal was replaced, which required the removal of the outboard bearing. A comprehensive full flow test was satisfactorily performed following that maintenance with the reactor vessel head removed and the reactor defueled. Approximately 2 weeks later on May 20, 2009, during preparation to enter Mode 4 and while using the pump to fill the Safety Injection Tanks, excessive leakage was observed which subsequently subsided. An investigation identified a misalignment of the mechanical seal. At the recommendation of the vendor, a new' mechanical seal and outboard bearing were installed. The scope of work performed was reviewed and Arizona Public Service Company (APS) engineering determined that a comprehensive full flow test was necessary and that the test procedure could not be performed in the current plant configuration.
Due to circumstances that would delay the timely resumption of Palo Verde Unit 3 operation, APS requested, and was granted, verbal authorization for ayrelief request to test the HPSI B pump using the recirculation line back to the Refueling Water Tank (RWT) in lieu of performing the comprehensive full flow test into the reactor Vessel.
During the verbal authorization of Relief Request PRR-08, the NRC asked that APS revise the relief request to include the following additional information discussed during the teleconference:
- Why it would be acceptable to test the Unit 3 HPSI B pump at flow rates lower than the comprehensive full flow test flow rates.
- Why it would be acceptable to test the Unit 3 HPSI B pump using instrument uncertainties greater than allowed by the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM) Code 2001 Edition, 2003 Addenda. It was requested that this include a discussion of the existing relief request that Palo Verde has for instrument uncertainty on the miniflow line.
- A discussion on the use of spectrum analysis for the vibration measurements.
The revised portions of the May 22, 2009, Relief Request have been identified by revision bars.
- 1. ASME Code Component(s) Affected Pump 3MSIBPO2 is the train B HPSI pump in Palo Verde Nuclear Generating Page 1
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
Relief Request PRR-08, Revision I Station (PVNGS) Unit 3. This is a safety-related centrifugal pump model 4X11CA-8 manufactured by Ingersol-Rand.
2. Applicable Code Edition and Addenda
ASME OM Code 2001 Edition, 2003 Addenda.
- 3. Applicable Code Requirements ASME OM Code Subsection ISTB, /nservice Testing of Pumps in Light-Water Reactor NuclearPower Plants ISTB-3310 Effect of Pump Replacement, Repair, and Maintenance on Reference Values. When a reference value or set of values may have been affected by repair, replacement, or routine servicing of a pump, a new reference value or set of values shall be determined in accordance with ISTB-3300, or the previous value reconfirmed by a comprehensive or Group A test run before declaring the pump operable. The Owner shall determine whether the requirements of ISTB-3100, to reestablish reference values, apply. Deviations between the previous and new set of reference values shall be evaluated, and verification that the new values represent acceptable pump operation shall be placed in the record of tests (see ISTB-9000).
ISTB-3510 General (a) Accuracy - Instrument accuracyshall be within the limits of Table ISTB-3500-1. If a parameter is determined by analytical methods instead of measurement, then the determination shall meet the parameter accuracy requirement of Table ISTB-3500-1 (e.g., flow rate determination shall be accurate to within +/- 2% of actual). For individual analog instruments, the required accuracy is percent of fullscale. For digital instruments, the required accuracy is over the calibrated range. For a combination of instruments, the required accuracy is loop accuracy.
Table ISTB-3500-1 Required InstrumentAccuracy - Flow Rate for Comprehensive and Preservice Tests, +/- 2%.
4. Reason for Request
The Unit 3 HPSI B pump falls under the Group B categorization in the applicable ASME OM Code. The ASME OM Code ISTB-3310 requires that a comprehensive or Group A pump test be performed when a reference value may have been affected by repair, replacement, or routine servicing of a pump. The HPSI pump comprehensive full flow test would necessitate the removal of the reactor head to create an adequate flow path to achieve the required test flow rate. This test is normally performed with the reactor defueled. To perform the Page 2
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
Relief Request PRR-08, Revision I comprehensive full flow test in the plant conditions existing on May 22, 2009, would require a temporary procedure change with associated training to enable the test to be performed without removing the reactor head and defueling the reactor. The test would require a unique alignment and the control room operators would be required to react quickly in the event of a flow imbalance in the Reactor Coolant System (RCS).
The risk imposed by performing the comprehensive full flow test in strict accordance with the ASME OM Code would not provide an increase in the level of quality and safety over the proposed test method and is therefore not warranted.
- 5. Proposed Alternative and Basis for Use Proposed Alternative The proposed alternative is to test the Unit 3 HPSI B pump on the larger (non-orifice) recirculation line to the Refueling Water Tank (RWT), which can be performed safely in Mode 5 in lieu of the comprehensive full flow test which requires flow back to the reactor vessel. Running the pump on the larger recirculation line produces a flow (at least 750 gpm) close to the comprehensive full flow of 1040 gpm. The proposed alternative is applicable until the comprehensive full flow test can be performed during the next refueling outage.
Basis for Use The maintenance performed on the pump for the additional seal replacement activities would not adversely impact the hydraulic characteristics of the pump due to the limited scope of work and the controls used during the maintenance.
The controls included maintaining the pump shaft in place during the pump seal and outboard bearing replacement. The purpose of performing the comprehensive full flow pump test following maintenance is to determine if the vibration reference value was impacted to the degree that would require the acceptance criteria to be adjusted. As discussed below, this determination can be made from the results of testing at flow rates lower than the comprehensive full flow test.
The ASME OM Code ISTB 3300(e)(1) states that reference values shall be established within +/- 20% of pump design flow for the comprehensive full flow test. The design flow for the PVNGS HPSI pumps is 1040 gpm. The flow rate during the performance of this alternative is expected to be at least 750 gpm which would be greater than 70% of the comprehensive full flow test point.
Performing the alternative testing at flow rates that are 70% of the Page 3
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
Relief Request PRR-08, Revision 1 comprehensive full flow test point provides sufficient vibration data to assess HPSI pump operation. Performing the test at flow rates greater than the 750 gpm anticipated during the alternative testing would not provide any additional information that would improve the assessment capability since pumps operate more efficiently at flow rates closer to the design point.
The flowmeter on the larger (non-orifice) recirculation line to the RWT has an accuracy of +/- 5.0% and is a digital flow measuring device. While this does not meet the +/- 2% accuracy requirements of the ASME OM Code, it is the optimal accuracy that can presently be achieved given the piping geometry and technological limitations of the equipment available. The flowmeter utilizes ultrasonic technology to monitor flow and can be unfavorably influenced by turbulent conditions, similar to other flow measuring devices commercially available. The purpose of the flow measurement is to ensure there is adequate flow in order to obtain representative vibration data to assess HPSI pump operation. The comprehensive full flow pump test value is 1040 gpm, which is the design flow rate necessary for accident mitigation. The alternative test proposed in this relief request will be performed to measure vibration at flow rates near the comprehensive full flow value to support confidence of operational capability for the duration of the operating cycle. Due to the limited scope of work and the controls used during maintenance, the hydraulic characteristics (including flow rate) were not adversely impacted. On this basis, the ultrasonic flowmeter is sufficiently accurate for the purposes of the alternative test.
Additionally, sufficient test trend data exists at full flow conditions and at mini-flow conditions to allow a comparison of vibration data taken during the alternative test.
The testing will be performed by running the pump for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at normal recirculation flow (approximately 150 gpm) to verify acceptable seal and bearing operation. The oil will be changed and the pump run for another 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on the larger recirculation flow path. The oil will be changed a second time and the pump run for another 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on the larger recirculation flow path. Vibration data will be collected at initial pump start-up after stable flow conditions. are achieved.
During the subsequent pump runs vibration data will be collected in a similar manner.
Vibration frequency analysis will be conducted to ensure there are no indications of unacceptable pump performance and that the performance data is within the expected range. Vibration frequency spectrum analysis ensures that the maintenance performed does not result in a condition that is detrimental to pump health.
During the next Unit 3 refueling outage, the comprehensive full flow pump test Page 4
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
Relief Request PRR-08, Revision 1 will be performed in accordance with ISTB-3310. During the fifteenth operating cycle, the quarterly Group B surveillance tests will be performed. Vibration data will be collected during these Group B surveillance tests and analyzed to provide assurance of acceptable HPSI pump operation.
Relief Request PRR-04, approved on April 24, 2008, (Agencywide Documents Access and Management System (ADAMS) No. ML081050003) discusses the accuracy limitation of the same flow measuring instrument which will be used for the proposed alternative test. However, the flow path discussed in PRR-04 uses the minimum flow recirculation line that includes a flow limiting orifice for Group B testing. Repeatability of the Group B testing is assured by using the installed orifice to establish the flow. The purpose of using the installed ultrasonic flow measurement device during the alternative test for PRR-08 is to establish a flow rate close to the comprehensive full flow test value to ensure representative vibration data can be obtained in order to assess HPSI pump operation. It is not anticipated that APS will perform routine tests at this same flow rate and compare test data. Therefore, there is no need to adhere to the instrument uncertainty requirements specified in the ASME OM Code for this alternative test.
Vibration readings will be taken during the alternative testing and analyzed using vibration frequency spectrum analysis. Vibration frequency spectrum analysis is superior at detecting pump problems when compared to the simple overall measurement of vibration displacement or velocity. The spectrum analysis method utilizes a Fast Fourier Transform to convert accelerometer information from the time domain to the frequency domain. The information is collected using a hand-held data acquisition system that is later downloaded into a computer. The vibration data is then compared in the frequency domain to identify increasing trends at specific frequencies that would otherwise be undetected by evaluating the simple value of overall vibration. Vibration spectrum analysis is a proven technology for determining the health of rotating equipment.
In conclusion, the alternate testing proposed in this relief request to demonstrate the acceptable operation of the Unit 3 HPSI B pump is:
- Vibration can be measured at a comparable flow rate to the comprehensive full flow point which provides an acceptable condition for assessment of pump vibration.
- The flowmeter is sufficiently accurate to ensure there is adequate flow to obtain representative vibration data to assess HPSI pump operation.
" Vibration frequency spectrum analysis is superior to the method of simple overall vibration value measurement required by the ASME OM Code.
This provides the capability to detect degradation in pump performance through identification of increases in vibration amplitudes at specific Page 5
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
Relief Request PRR-08, Revision 1 frequencies which enables early detection of problems in rotating equipment.
The performance of this test and quarterly Group B tests will provide additional assurance of acceptable HPSI pump operation until the comprehensive full flow test can be performed at the next available opportunity to meet the requirements of ASME OM Code ISTB-3310. During the quarterly Group B surveillance tests, vibration data will be collected and spectrum analyses will be performed to provide assurance of continued pump operability.
- 6. Duration of Proposed Alternative The duration of the proposed alternative will be for the fifteenth operating cycle of PVNGS Unit 3.
'7. Update of Test Results Due to the unique nature of this situation, revision 1 to Pump Relief Request PRR-08 is being provided subsequent to the performance of the alternative test, such that the results are available. The actual flow rate achieved by the HPSI B pump on the larger recirculation line was approximately 840 gpm. In addition, the data obtained from the Unit 3 HPSI B pump vibration spectrum analysis was well within the expected range and was acceptable.
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