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Category:Fuel Cycle Reload Report
MONTHYEARML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 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 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 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 ML22305A5362022-10-28028 October 2022 Core Operating Limits Report, Revision 30 ML22126A1262022-05-0606 May 2022 Unit 1 Core Operating Limits Report Revision 31 ML22301A2012022-04-30030 April 2022 Core Operating Limits Report, Revision 28 ML22026A2032022-01-26026 January 2022 Unit 1 Core Operating Limits Report Revision 30, Unit 2 Core Operating Limits Report Revision 24, Unit 3 Core Operating Limits Report Revision 29 ML21120A3272021-04-30030 April 2021 Unit 3 Core Operating Limits Report, Revision 28 ML20317A3302020-11-12012 November 2020 Core Operating Limits Report, Revision 29 ML20113F0352020-04-22022 April 2020 Unit 1 Core Operating Limits Report Revision 28 Unit 2 Core Operating Limits Report Revision 23 Unit 3 Core Operating Limits Report Revision 27 ML19297E7242019-10-24024 October 2019 Core Operating Limits Report, Revision 26 ML19204A1932019-07-22022 July 2019 Unit 1 Core Operating Limits Report Revision 27, Unit 2 Core Operating Limits Report Revision 22, Unit 3 Core Operating Limits Report Revision 25 ML19116A2682019-04-26026 April 2019 Core Operating Limits Report, Revision 26 ML18339A0302018-12-0505 December 2018 Current Core Operating Limits Report ML18102B6852018-04-12012 April 2018 Core Operating Limits Report (Colr), Revision 25, 21, and 24, Respectively ML16106A2502016-04-15015 April 2016 Current Core Operating Limits Report Revision ML16034A4682016-02-0202 February 2016 Current Core Operating Limits Report Revisions ML13114A2512013-04-17017 April 2013 Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2012 ML13108A1762013-04-11011 April 2013 Unit 1 Core Operating Limits Report (Colr), Revision 22, Unit 2 Core Operating Limits Report (Colr), Revision 18 and Unit 3 Core Operating Limits Report (Colr), Revision 21 ML11129A0312011-04-27027 April 2011 Unit 2 Core Operating Limits Report (Colr), Revision 17 ML1031300432010-10-29029 October 2010 Revised Core Operating Limits Report (COLR) ML1015304872010-05-21021 May 2010 Core Operating Limits Report - Revision 21 ML0932901072009-11-17017 November 2009 Submittal of Revised Core Operating Limits Reports (Colrs) ML0923702942009-08-0707 August 2009 Correction to Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report (COLR) ML0912703892009-04-29029 April 2009 Core Operating Limits Report (COLR) - Revision 18 ML0830908772008-10-24024 October 2008 Core Operating Limits Reports (COLR) - Revision 19 ML0825601772008-08-29029 August 2008 Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report (COLR) ML0733902822007-11-27027 November 2007 Core Operating Limits Reports (Colr), Unit 1 - Revision 18, Unit 2 - Revision 15, and Unit 3 - Revision 17 ML0617104592006-06-0909 June 2006 Units, 1, 2, & 3, Core Operating Limits Reports (Colr), Unit 1 - Revision 17, Unit 2 - Revision 14 and Unit 3 - Revision 16 ML0600903202005-12-27027 December 2005 Core Operating Limits Report (Colr), Revision 16 ML0507704192005-03-0707 March 2005 Cycle 12 Startup Report - Supplement 4 ML0505302362005-02-0404 February 2005 Cycle 12 Startup Report ML0432002272004-11-0303 November 2004 Core Operating Limits Report (Colr), Unit 3- Revision 14 ML0425301642004-08-31031 August 2004 Core Operating Limits Reports (Colr), Unit 1 - Revision 12, Unit 2 - Revision 11, and Unit 3 - Revision 13 ML0414602672004-05-13013 May 2004 Core Operating Limits Report (Colr), Unit 1- Revision 11 ML0411703932004-04-16016 April 2004 Core Operating Limits Reports (Colr), Unit 1- Revision 10, Unit 2- Revision 10, and Unit 3- Revision 12 ML0400606162003-12-23023 December 2003 Core Operating Limits Report: Unit 2 - Revision 9 ML0311404052003-04-17017 April 2003 Core Operating Limits Report, Unit 2-Revision 8 & Unit 3-Revision 11 ML0232303242002-11-0101 November 2002 Docket No.Stn 50-528, Core Operating Limits Report: Unit 1 - Revision 9 ML0230304272002-10-18018 October 2002 Core Operating Limits Reports: Unit 1 - Revision 8; Unit 2 - Revision 7; & Unit 3 - Revision 10 ML0226107122002-09-11011 September 2002 Special Report 2-SR-2002-001-01, Appendix D - G ML0226107102002-09-11011 September 2002 Special Report 2-SR-2002-001-01, Enclosure, Index - Appendix C 2024-04-19
[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
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LA P Scott A. Bauer Department Leader TRM T5.0.600.2 Regulatory Affairs Tel: 623/393-5978 Mail Station 7636 Palo Verde Nuclear Fax: 623/393-5442 P.O. Box 52034 Generating Station e-mail: sbauer~apsc.com Phoenix, AZ 85072-2034 102-05209-SAB/TNW/JAP February 4, 2005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. STN 50-530 Unit 3, Cycle 12 Startup Report In accordance with Technical Requirements Manual (TRM) section T5.0.600.2.a.(2),
Arizona Public Service Company (APS) is submitting this startup report for PVNGS Unit 3, Cycle 12.
The Unit 3 Cycle 12 core consists of 100 fresh assemblies (Improved Lattice) intermixed with 104 once and 37 twice-bumed irradiated assemblies. The fresh assemblies were designed utilizing a new three-enrichment assembly split. The utilization of a new three-enrichment assembly meets criteria (2) of TRM T5.0.600.2.a, requiring a startup report. Using three different fresh assembly enrichments versus only using two enrichments enhances the PVNGS Unit 3 core design by providing both improved power peaking control and lower predicted crud deposition.
No commitments are being made to the NRC by this letter.
If you have any questions, please contact Thomas N. Weber at (623) 393-5764.
Sincerely, SABfTNW/JAP/kg Enclosure cc: B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager G. G. Warnick NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
ENCLOSURE Unit 3, Cycle 12 Startup Report
Enclosure - Unit 3, Cycle 12 Startup Physics Testing Summary Introduction The Palo Verde Nuclear Generating Station (PVNGS) Unit 3 Cycle 12 core consists of 100 fresh assemblies (Improved Lattice) intermixed with 104 once and 37 twice-burned irradiated assemblies. The predicted cycle length is 496 EFPD. Reload analyses show that this core is typical of the most recent reload cores designed at PVNGS.
Cycle 12 initial criticality occurred at 2052 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.80786e-4 months <br /> on December 5, 2004. Low Power Physics Testing (LPPT) began immediately following criticality. Additionally, the resumption of commercial operations occurred on December 7, 2004. Power Ascension Testing followed and was completed without issues and the unit reached full power on December 12, 2004.
LPPT consisted of:
All Rods Out (ARO), Hot Zero Power (HZP), Critical Boron Concentration Isothermal Temperature Coefficient (ITC) Measurement Control Element Assembly (CEA) Worth Measurement Inverse Boron Worth Measurement Power Ascension Testing, for model verification, consisted of:
Radial Power Distribution - 20% Rated Thermal Power (RTP)
Radial Power Distribution - 70% RTP Axial Power Distribution - 70% RTP Radial Power Distribution - 100% RTP Axial Power Distribution - 100% RTP Verification of the Cycle Independent Shape Annealing Matrix (CISAM)
Hot Full Power (HFP), ARO, Critical Boron Concentration.
Test Acceptance Criteria The following acceptance criteria apply to each of the tests performed during LPPT and Power Ascension Testing:
Critical Boron Concentration (HZP) +/- 50 ppm of predicted ITC Measurement LPPT +/- 3 pcmI0 F of predicted CEA Testing Reference Group +/- 10% of predicted Test Group(s) +/- 15% of predicted Total Worth +/- 10% of predicted Inverse Boron Worth (IBW) +/- 15 ppm/% AK/K of predicted 1
Enclosure - Unit 3, Cycle 12 Startup Physics Testing Summary Test Acceptance Criteria (continued)
Radial Power Distribution -20% RTP +/- 10% of predicted for locations with a Relative Power Density (RPD) > 1.0 Flux Symmetry - 20% RTP < 10% of symmetric group average for instrumented locations with an RPD 2 1.0 and
+/- 0.1 RPD units for locations with an RPD < 1.0.
Radial Power Distribution -70% RTP +/- 0.1 RPD and Root Mean Square (RMS)
Axial Power Distribution -70% RTP +/- 0.1 RPD and RMS s 5%
Peaking Factors -70% RTP +/- 10% of predicted Radial Power Distribution -100% RTP +/- 0.1 RPD and RMS5s5%
Axial Power Distribution - 100% RTP +/- 0.1 RPD and RMS s 5%
Peaking Factors -100% RTP +/- 10% of predicted CISAM Verification Axial Shape RMS Error s 7.5%
Core Average Axial Shape Index 5 0.075 (ASI) Error (absolute value)
Axial Form Index Error (absolute value) 5 0.10 Critical Boron Concentration (HFP) +/- 50 ppm of predicted Low Power Physics Testing All Rods Out (ARO) Critical Boron Concentration (CBC)
This test is performed by obtaining a set of reactor coolant system (RCS) boron samples at equilibrium conditions near ARO (CEA Group 5 - 122 inches withdrawn) and adjusting this concentration for the Group 5 residual reactivity worth. The measured RCS concentration was 1973 ppm, which was adjusted for an ARO condition to 1979 ppm. The design HZP ARO CBC is 1979 ppm. The difference of 0 ppm is within the acceptance criterion.
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Enclosure - Unit 3, Cycle 12 Startup Physics Testing Summary Low Power Physics Testing (continued)
Isothermal Temperature Coefficient (OTC)
Raising and lowering the RCS Temperature and measuring the associated changes in core reactivity performs this test. The measured ITC with Group 5 at - 122" withdrawn was -1.887 pcm/lF. The predicted ITC was -1.560 pcmPF and was corrected to test conditions. The corrected ITC was -1.622 pcm/'F. The measured ITC met the acceptance criterion and satisfied the surveillance requirement of Technical Specification 3.1.4.1.
CEA Rod Worth Measurements Rod worth was measured using the Rod Swap method. The Reference Group (regulating groups (RGs) 2 + 3) was diluted into the core. The worth of the reference group was swapped with the worth of the test group. The results are summarized in the following Table:
CEA Group Measured Predicted % Difference Acceptance Worth (pcm) Worth (pcm) Criteria Reference Group (RG2 & RG3) -1295.9 -1318.5 1.74 s 10%
Test Groups:
SD (B6 & B16) -1202.1 -1203.7 0.13 s 15%
RG1 & RG4 -1041.4 -1052.3 1.05
SD (B7 & B10) -1159.1 -1178.9 1.71 s15%
RG5 & SD (A2 & A20) -1050.1 -1082.5 3.08 s15%
RG5 & SD (B9 & B16) -1242.2 -1235.8 -0.51 s 15%
RG5 & SD (A3 &A19) -1064.0 -1085.6 2.03 s 15%
Total CEA Worth -8054.8 -8157.3 1.27 s 10%
All test results met the acceptance criteria.
Inverse Boron Worth (IBW)
The IBW was determined by obtaining the measured worth of the CEA Reference Group and the change in the CBC from the dilution of the Reference Group to the control element assembly (CEA) lower electrical limit (LEL). The measured IBW was 136.0 ppm/% AK/K. The predicted IBW was 136.0 ppm/% AK/K. The acceptance criterion was met.
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Enclosure - Unit 3, Cycle 12 Startup Physics Testing Summary Power Ascension Testing Flux Symmetry Verification - 20% RTP Obtaining a flux map, by processing a CECOR snapshot and comparing symmetrical Relative Power Densities (RPD) performs this test. All deviations from the average of the instrumented powers were well within 10% or 0.1 relative power density (RPD) units.
Radial Power Distribution and Flux Symmetry - 20% RTP A comparison of predicted and measured RPD's was made using data from ROCS and CECOR at - 20% RTP. The maximum difference for assemblies with an RPD greater than or equal to 1.0 was less than the acceptance criterion of 10%. Measured powers in symmetric, instrumented assemblies were within 10% of the symmetric group average for assemblies with RPD's greater than 1.0 and within 0.1 RPD units for assemblies with an RPD less than 1.0.
Radial and Axial Power Distributions and Peaking Factor Comparisons - 70% RTP A comparison of predicted and measured RPD's was made using data from ROCS and CECOR at - 70% RTP. Measured versus predicted RPD's were within the requirement of +/- 0.1 RPD and a root mean square (RMS) of s 5% for both the radial and axial comparisons. Additionally, CECOR and ROCS comparisons of the Peaking Factors were made. The acceptance criterion of +/- 10% was also met.
Radial and Axial Power Distributions and Peakinq Factor Comparisons - 100% RTP A comparison of predicted and measured RPD's was made using data from ROCS and CECOR at - 100% RTP. Measured versus predicted RPD's were within the requirement of +/- 0.1 RPD and an RMS of 5 5% for both the Radial and Axial comparisons. Additionally, CECOR and ROCS comparisons of the Peaking Factors were made. The acceptance criterion of +/- 10% was also met.
Verification of the Cycle Independent Shape Annealing Matrix (CISAM)
Evaluation of the CEFAST output data was performed to validate the use of the CISAM in the plant Core Protection Calculator (CPC). The requirement that the axial shape index (ASI) RMS error be 5 7.5% for each CPC channel was met. Additionally, the absolute values of the Core Average ASI Error and the Axial Form AFM Error were s 0.075 and 50.10, respectively.
Critical Boron Concentration (Hot Full Power)
The requirement for the measured versus predicted CBC at HFP is +/- 50 ppm. This acceptance criterion was met for the Power Ascension Testing. The predicted HFP, equilibrium Xenon, CBC was 1393 ppm and the measured value was 1402 ppm.
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