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Category:Fuel Cycle Reload Report
MONTHYEARRA-23-0021, Unit 2 Cycle 26 Core Operating Limits Report (COLR)2023-02-22022 February 2023 Unit 2 Cycle 26 Core Operating Limits Report (COLR) RA-22-0095, Unit 1 Cycle 24 Core Operating Limits Report (COLR)2022-03-29029 March 2022 Unit 1 Cycle 24 Core Operating Limits Report (COLR) RA-20-0296, Letter from Sabrina Salazar (Duke Energy) to NRC Document Control Desk, Cycle 23 Core Operating Limits Report (Colr), Revision 2, Dated June 19, 20202021-06-23023 June 2021 Letter from Sabrina Salazar (Duke Energy) to NRC Document Control Desk, Cycle 23 Core Operating Limits Report (Colr), Revision 2, Dated June 19, 2020 RA-21-0098, Unit 2 Cycle 25 Core Operating Limits Report (COLR) and Reload Safety Analysis Report (RSAR)2021-03-27027 March 2021 Unit 2 Cycle 25 Core Operating Limits Report (COLR) and Reload Safety Analysis Report (RSAR) RA-20-0217, Cycle 23 Startup Report2020-06-25025 June 2020 Cycle 23 Startup Report RA-20-0168, Cycle 23 Core Operating Limits Report (COLR) Revision 22020-06-19019 June 2020 Cycle 23 Core Operating Limits Report (COLR) Revision 2 RA-20-0118, Cycle 23 Operating Limits Report (COLR) Revision 12020-05-21021 May 2020 Cycle 23 Operating Limits Report (COLR) Revision 1 RA-20-0091, Unit 1 Cycle 23 Core Operating Limits Report (COLR2020-03-14014 March 2020 Unit 1 Cycle 23 Core Operating Limits Report (COLR RA-19-0162, Cycle 24 Core Operating Limits Report (COLR)2019-03-19019 March 2019 Cycle 24 Core Operating Limits Report (COLR) RA-18-0170, Unit 1 Cycle 22 and Unit 2 Cycle 23 Core Operating Limits Reports2018-10-0202 October 2018 Unit 1 Cycle 22 and Unit 2 Cycle 23 Core Operating Limits Reports RA-18-0101, Unit 1 Cycle 22 and Unit 2 Cycle 23 Reload Safety Analysis Reports2018-07-30030 July 2018 Unit 1 Cycle 22 and Unit 2 Cycle 23 Reload Safety Analysis Reports BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)2018-03-27027 March 2018 Cycle 22 Core Operating Limits Report (COLR) BSEP 17-0032, Cycle 23 Core Operating Limits Report (COLR)2017-04-0909 April 2017 Cycle 23 Core Operating Limits Report (COLR) BSEP 15-0048, Cycle 22 Startup Report2015-06-29029 June 2015 Cycle 22 Startup Report BSEP 15-0036, Submittal of Core Operating Limits Report (Colr), Revision 1 for Cycle 202015-05-13013 May 2015 Submittal of Core Operating Limits Report (Colr), Revision 1 for Cycle 20 BSEP 15-0022, Cycle 22 Core Operating Limits Report (COLR)2015-03-23023 March 2015 Cycle 22 Core Operating Limits Report (COLR) BSEP 14-0033, Cycle 20 Core Operating Limits Report (COLR)2014-04-0404 April 2014 Cycle 20 Core Operating Limits Report (COLR) BSEP 13-0039, Submittal of Cycle 21 Core Operating Limits Report (COLR)2013-04-23023 April 2013 Submittal of Cycle 21 Core Operating Limits Report (COLR) ML12100A0862012-03-26026 March 2012 Cycle 19, Core Operating Limits Report, March 2012 BSEP 12-0018, Submittal of Confirmatory Evaluation for Cycle 192012-01-26026 January 2012 Submittal of Confirmatory Evaluation for Cycle 19 BSEP 10-0050, Cycle 18 Core Operating Limits Report2010-04-0808 April 2010 Cycle 18 Core Operating Limits Report BSEP 09-0054, Core Operating Limits Report, Revision 2 for Unit 1 Cycle 172009-07-23023 July 2009 Core Operating Limits Report, Revision 2 for Unit 1 Cycle 17 ML0909702472009-04-0101 April 2009 Submittal of Cycle 19 Core Operating Limits Report BSEP 08-0097, Cycle 17 Core Operating Limits Report, Revision 12008-07-30030 July 2008 Cycle 17 Core Operating Limits Report, Revision 1 BSEP 08-0096, Cycle 17 Startup Report2008-07-28028 July 2008 Cycle 17 Startup Report BSEP 08-0093, Cycle 18 Core Operating Limits Report, Revision 12008-07-17017 July 2008 Cycle 18 Core Operating Limits Report, Revision 1 BSEP 08-0047, Cycle 17 Core Operating Limits Report2008-04-22022 April 2008 Cycle 17 Core Operating Limits Report ML0729503692007-09-30030 September 2007 Areva Report, ANP-2674(NP), Revision 0, Brunswick, Unit 1, Cycle 17 Reload Safety Analysis, September 2007 BSEP 07-0034, Core Operating Limits Report, Revision 1 for Unit 1 Cycle 162007-05-15015 May 2007 Core Operating Limits Report, Revision 1 for Unit 1 Cycle 16 BSEP 07-0026, Enclosure 1 - Design Calc. 21321-1267, Revision 0, Brunswick, Unit 2, Cycle 18 Core Operating Limits Report March 2007.2007-03-31031 March 2007 Enclosure 1 - Design Calc. 21321-1267, Revision 0, Brunswick, Unit 2, Cycle 18 Core Operating Limits Report March 2007. BSEP-06-0061, Core Operating Limits Report (Colr), Revision 2 for Plant Cycle 172006-05-26026 May 2006 Core Operating Limits Report (Colr), Revision 2 for Plant Cycle 17 ML0609501212006-03-22022 March 2006 Brunswick, Unit 1 Cycle 16 Core Operating Limits Report, March 2006 BSEP 06-0034, Supplemental Reload Licensing Report for Brunswick, Unit 1, Reload 15 Cycle 16, December 20052005-12-31031 December 2005 Supplemental Reload Licensing Report for Brunswick, Unit 1, Reload 15 Cycle 16, December 2005 BSEP-05-0139, Core Operating Limits Report (Colr), Revision 1 for Unit 2, Cycle 172005-11-21021 November 2005 Core Operating Limits Report (Colr), Revision 1 for Unit 2, Cycle 17 BSEP 05-0087, Core Operating Limits Report (COLR) for Unit 1 Cycle 15, Revision 12005-06-29029 June 2005 Core Operating Limits Report (COLR) for Unit 1 Cycle 15, Revision 1 BSEP-05-0024, Design Calculation No. 2821-1064, Rev 0, Brunswick Unit 2, Cycle 17 Core Operating Limits Report, February 2005.2005-03-0303 March 2005 Design Calculation No. 2821-1064, Rev 0, Brunswick Unit 2, Cycle 17 Core Operating Limits Report, February 2005. ML0409600822004-03-0101 March 2004 to 1B21-0625, Brunswick, Unit 1, Cycle 15, Core Operating Limits Report. BSEP 04-0012, Cycle 16 Core Operating Limits Report2004-01-29029 January 2004 Cycle 16 Core Operating Limits Report BSEP 03-0168, Cycle 14 Core Operating Limits Report2003-12-17017 December 2003 Cycle 14 Core Operating Limits Report BSEP 02-0108, Cycle 14 Core Operating Limits Report, Supplemental Reload Licensing Report & Loss-Of-Coolant Accident Analysis Report for Operation with Extended Power Uprate2002-05-31031 May 2002 Cycle 14 Core Operating Limits Report, Supplemental Reload Licensing Report & Loss-Of-Coolant Accident Analysis Report for Operation with Extended Power Uprate BSEP 02-0059, Unit 1 Cycle 14 Core Operating Limit Report, Supplemental Reload Licensing Report, Loss-of-Coolant Accident Analysis Report & Plant-Specific Emergency Core Cooling System (ECCS) Evaluation2002-03-22022 March 2002 Unit 1 Cycle 14 Core Operating Limit Report, Supplemental Reload Licensing Report, Loss-of-Coolant Accident Analysis Report & Plant-Specific Emergency Core Cooling System (ECCS) Evaluation 2023-02-22
[Table view] Category:Letter
MONTHYEARIR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20243012023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) ML22230D0692022-08-22022 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident IR 05000324/20220022022-08-0505 August 2022 Integrated Inspection Report 05000324/2022002 and 05000325/2022002 IR 05000324/20220102022-06-27027 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000324 2022010 and 05000325 2022010 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 IR 05000324/20220012022-05-10010 May 2022 Integrated Inspection Report 05000324/2022001 and 05000325/2022001 ML22119A1352022-05-0909 May 2022 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000325/2022403; 05000324/2022403 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22102A0502022-04-11011 April 2022 301 Corporate Notification Letter IR 05000324/20224012022-03-16016 March 2022 Security Baseline Inspection Report 05000324/2022401 and 05000325/2022401 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications IR 05000324/20210062022-03-0202 March 2022 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 (Reports No. 05000324/2021006 and 05000325/2021006) IR 05000324/20210042022-02-14014 February 2022 Integrated Inspection Report 05000324/2021004 and 05000325/2021004 ML22035A1262022-02-0909 February 2022 Withdrawal of Exemption Request from the Requirements of 10 CFR Part 50, Appendix E, Section IV.F.2.d (EPID L-2021-LLE-0055 (COVID-19)) ML21354A5032022-01-24024 January 2022 Requested Exemption from 10 CFR 50, Appendix E, Section IV.F.2.D Not Required (EPID L-2021-LLE-0055 (COVID-19)) ML22018A1842022-01-18018 January 2022 Notification of Brunswick Steam Electric Plant, Units 1 & 2 - Design Bases Assurance Inspection - U.S. Nuclear Regulatory Inspection Report 05000324/2022010 and 05000325/2022010 ML21348A7192021-12-21021 December 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times 2023-09-25
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Progress Energy JUL 28 2008 SERIAL: BSEP 08-0096 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No.; 1 Docket No. 50-325/License No. DPR-7, Cycle 17 Startup Report Ladies and Gentlemen:
In accordance with the Brunswick Steam Electric Plant (BSEP) Updated Final Safety Analysis Report (UFSAR), Section 13.4.2.1, "Startup Report," Carolina Power &Light (CP&L) Company, now doing business as Progress Energy Carolinas, Inc., submits the enclosed BSEP Unit 1, Cycle 17 Startup Report. The report is required as a result of installation of fuel that was manufactured by a different fuel supplier (i.e., the AREVA ATRIUM- 10 fuel type) during the spring 2008 refueling, outage.No regulatory commitments are contained in this letter., Please refer any questions regarding this submittal to Mr. Gene Atkinson, Supervisor
-Licensing/Regulatory Programs, at (910) 457-2056.Sincerely, Philip A. Leich Manager -Support Services Brunswick Steam Electric Plant MAT/mat
Enclosure:
Brunswick Unit 1, Cycle 17 Startup Report Progress Energy Carolinas, Inc.Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 Document Control Desk BSEP 08-0096 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A)11555 Rockville Pike Rockville, MD 20852-2738 Chair -North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 BSEP 08-0096 Enclosure Brunswick Unit 1 Cycle 17 Startup Report BRUNSWICK UNIT 1, CYCLE 17 STARTUP REPORT July 2008 Prepared by: Reviewed by: Reviewed by: Approved by: Cahill, Thomas 2008.07.23)12.22:20
-04'00'Tom Cahill (NFM&SA)Alford, Mike.4 2008.07.23 12:43:47 -04'00a Mike Alford (BNP Reactor Engineering) r g ySIglt, by M( ThtQi Mark ca /I,,41 ~ ~ 0 /l124,J 1-Sev e 17 Mark Turkal (Regulatory Affairs)Westmoreland, Gregory for Michael Blom 2008.07.23 15:59:12',04'00' Michael Blom Supervisor, BWR Fuel Engineering Progress Energy Nuclear Fuels Management
& Safety Analysis Section B 1C17 Startup Report Page 2 of 8, Revision 0 1.0 Introduction This report summarizes observed data from the initial Brunswick Steam Electric plant (BSEP) Unit 1, Cycle 17 (B1C17) startup tests. The Cycle 17 core represents the first loading of the AREVA ATRIUM- 10 fuel type in Unit 1. 248 ATRIUM- 10 fuel assemblies have been loaded.Pursuant to the requirements of Section 13.4.2.1 of the BSEP 1 & 2 Updated Final Safety Analysis Report (UFSAR), a summary report of plant startup and power escalation testing shall be submitted to the NRC should any one of four conditions occur. Condition (3) applies: (3): "installation of fuel that has a different design or has been manufactured by a different fuel supplier." This report shall include results of neutronics related startup tests following core reloading as described in the UFSAR.2.0 References 2.1 BSEP UFSAR 2.2 BSEP Technical Specifications 2.3 NGGS-NFP-0002, "Guidelines for BWR Cycle Management Calculations" 2.4 OENP-24.13, "Core Verification" 2.5 OFH-1 1, "Refueling" 2.6 OPT-14.2.1, "Single Rod Scram Insertion Times Test" 2.7 OPT- 14.3.1, "Insequence Critical Shutdown Margin Calculation" 2.8 OPT-14.5.2, "Reactivity Anomaly Check" 2.9 OPT-50.0, "Reactor Engineering Refueling Outage Testing" 2.10 OPT-50.3, "TIP Reproducibility And Uncertainty Determination" 2.11 OPT-90.2, "Friction Testing of Control Rods" 3.0 UFSAR Section 14.4.1, Item 1: Core Loading Verification A Core Loading Pattern Verification was performed per BSEP Engineering Procedure OENP-24.13, "Core Verification." The core was verified to be loaded in accordance with the analyzed B 1 C 17 core design.
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& Safety Analysis Section B 1C 17 Startup Report Page 3 of 8, Revision 0 4.0 UFSAR Section 14.4.1, Item 4A: TIP Operability and Bundle Power Evaluation*
- a. TIP Measurement Uncertainty Radial (bundle or 2D) and nodal (3D) gamma TIP measurement uncertainties were determined in accordance with BSEP Periodic Test Procedure OPT-50.3, "TIP Uncertainty Determination." Total radial TIP measurement uncertainty at high core thermal power (CTP) (>80% CTP) was 0.912% and total nodal TIP measurement uncertainty was 1.555%. These radial and nodal uncertainties were also determined at medium core thermal power (40% to 80% CTP) and were 1.599% and 2.140%, respectively.
All results met the test acceptance criteria.b. Measured and Calculated TIP Comparison Radial and.nodal deviations between measured and calculated TIP data were determined in accordance with BSEP Periodic Test Procedure OPT-50.3, "TIP Uncertainty Determination." The radial deviation at high core thermal power (>80% CTP) was 2.364% and the nodal deviation was 3.989%. These radial and nodal deviations were also determined at medium core thermal power (40% to 80% CTP) and were 2.700% and 5.144%, respectively.
All results met the test acceptance criteria.c. Monitored Power Uncertainty Radial and nodal monitored power uncertainties were determined in accordance with BSEP Periodic Test Procedure OPT-50.3, "TIP Uncertainty Determination." The radial monitored power uncertainty at high core thermal power (>80% CTP) was 3.216% and the nodal monitored power uncertainty was 3.851%. These radial and nodal uncertainties were also determined at medium core thermal power (40% to 80% CTP) and were 3.278% and 4.182%, respectively.
All results met the test acceptance criteria.d. Bundle Powers This analysis compares the MICROBURN-B2 predictions of bundle powers to the plant process computer's measured bundle powers in accordance with BSEP Periodic Test procedure OPT-50.0, "Reactor Engineering Refueling Outage Testing." Bundles located in peripheral control cells or uncontrolled peripheral locations are excluded.
The maximum radial difference was calculated to be 3.14% at medium power (40% to 80%CTP). All results met the test acceptance criteria.
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& Safety Analysis Section B 1 C 17 Startup Report Page 4 of 8, Revision 0 5.0 UFSAR Section 14.4.1, Item 2: Control Rod Mobility Control rod mobility is verified by two tests: friction testing and scram timing. The results of these tests and their acceptance criteria are described below.a. Friction Testing Friction Testing was performed prior to startup per BSEP Periodic Test Procedure 0PT-90.2, "Friction Testing of Control Rods." Control rods were verified to complete full travel without excessive binding or friction.
In a pre-requisite to 0PT-90.2, the reactor was observed to remain subcritical during the withdrawal of the most reactive rod in BSEP Fuel Handling Procedure 0FH-1 1, "Refueling." b. Scram Time Testing Scram Time Testing was performed for each control rod prior to exceeding 40% power per BSEP Periodic Test Procedure OPT-14.2.1, "Single Rod Scram Insertion Times Test." The acceptance criteria for this test are found in Technical Specification 3.1.4. All control rods had a scram time of 7.0 seconds and thus were considered operable in accordance with Technical Specification 3.1.3. The maximum measured 5%, 20%, 50%, and 90% insertion times are given in Attachment 1 of this report.The average 20% insertion time measured from the low power testing was 0.789 seconds which is faster than the. analyzed nominal speed limit of < 0.822 seconds.6.0 UFSAR Section 14.4.1, Item 3: Reactivity Testing Reactivity Testing consists of a shutdown margin (SDM) measurement, reactivity anomaly check, and measured critical k~ff comparison to predicted values. The results of these tests are provided below with the acceptance criteria.a. Shutdown Margin SDM measurements were performed per BSEP Periodic Test Procedure OPT-14.3.1,"Insequence Critical Shutdown Margin Calculation." The cycle minimum SDM was determined to be 0.893% Ak/k compared to a predicted cycle minimum SDM value of 0.977% Ak/k, an absolute difference of 0.084% Ak/k. The cycle minimum SDM is..determined by subtracting the maximum decrease in SDM which occurs at 20.43 GWD/MTU cycle exposure (R = 0.249% Ak/k) from the SDM at beginning-of-cycle (BOC). The acceptance criterion for minimum SDM is defined in Technical Specification 3.1.1.1, which requires the SDM be > 0.38% Ak/k during the entire cycle.
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& Safety Analysis Section B1C17 Startup Report Page 5 of 8, Revision 0 Since for B1C17 the cycle minimum SDM was determined to be 0.893% Ak/k, the acceptance criterion is met.b. Reactivity Anomaly A reactivity anomaly test was performed at near rated conditions (2904.9 MWt or 99.4%)per BSEP Periodic Test Procedure OPT-14.5.2, "Reactivity Anomaly Check." The acceptance criterion is defined by Technical Specification 3.1.2, which requires that the reactivity difference between monitored and predicted core kff be within +/-1% Ak. The measured and predicted values for keff were 1.0006 and 1.0025, respectively, a difference of 0.19% Ak/k. This is within the +/-1% Ak requirement.
- c. Cold Critical Eigenvalue (kff)The measured BOC cold critical keff per BSEP Periodic Test Procedure OPT-14.3.1,"Insequence Critical Shutdown Margin Calculation" was inferred as 0.99516 by nodal simulator code calculations with actual critical conditions as input (including period correction).
The predicted BOC cold critical k~ff was 0.99600 resulting in a measured to predicted difference of 0.084% Ak/k. Therefore, per Technical Specification 3.1.2, the acceptance criterion requiring agreement within +/-1% Ak/k is met.7.0 Additional Testing Results As a matter of course, key testing and checks beyond those specified in the UFSAR are performed during initial startup and power ascension.
These "standard" tests are described in items (a) and (b) below.a. Core Monitoring Software Comparisons to Predictions Thermal limits calculated by the online POWERPLEX Core Monitoring Software System were compared to those calculated by MICROBURN-B2 predictions at medium and high power levels. The results of these comparisons and the POWERPLEX statepoints are provided as Attachment
- 2. All results met the test acceptance criteria.b. Hot Full Power Eigenvalue After establishing a sustained period of full power equilibrium operation at 203.8 MWD/MTU on 6/05/2008, the predicted and core follow Hot Full Power Eigenvalues (kff) are compared.
The core follow klff was calculated as 1.000 14 and the predicted klff was 1.00010. The difference between the predicted and core follow values is 0.004% Ak/k which is within the +/-1% Ak/k reactivity anomaly requirements.
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& Safety Analysis Section B 1 C17 Startup Report Page 6 of 8, Revision 0 8.0 Summary Evaluation of the BSEP Unit 1, Cycle 17 startup data concludes the core has been loaded properly and is operating as expected.
The startup and initial operating conditions and parameters compare well to predictions.
Core thermal peaking design predictions and measured peaking comparisons met the startup acceptance criteria.
The BOC SDM demonstration indicates adequate SDM will exist throughout B 1C 17. All UFSAR prescribed and additional tests met their acceptance criteria.
Progress Energy Nuclear Fuels Management
& Safety Analysis Section B1C17 Startup Report Attachment 1 to the B1C17 Startup Report Results of Control Rod Scram Time Testing Page 7 of 8, Revision 0 Maximum Measured Scram Insertion Time Technical Specification
3.1.4 Insertion
Position/Notch Tech Spec Maximum Average"Slow" Limit Measured Insertion Time*(seconds) (seconds)5% 46 0.440 0.295 20% 36 1.080 0.848 50% 26 1.830 1.405 90% 06 3.350 2.503* Average of the scram insertion times for the three fastest control rods in a 2x2 array Progress Energy Nuclear Fuels Management
& Safety Analysis Section B1C17 Startup Report Page 8 of 8, Revision 0 Attachment 2 to the B1C17 Startup Report Core Monitoring Software Comparisons to Predictions Medium Power Testing Plateau 67.7% CMWT, 08MAY01, 12.40.39 Thermal Limit POWERPLEX MICROBURN-B2 Absolute On-Line Predicted Difference Monitoring CMFLCPR 0.839 0.834 0.005 CMARAT 0.734 0.742 0.008 CMFDLRX 0.673 0.683 0.010 CMFLPD 0.529 0.533 0.004 High Power Testing Plateau 99.7% CMWT, 08MAY03, 22.08.40 Thermal Limit POWERPLEX MICROBURN-B2 Absolute On-Line Predicted Difference Monitoring CMFLCPR 0.909 0.897 0.012 CMAPRAT 0.808 0.822 0.014 CMFDLRX 0.859 0.874 0.015 CMFLPD 0.713 0.722 0.009