Letter Sequence Other |
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Results
Other: ML20135D986, ML20207R745, ML20210D696, ML20210T949, ML20210T980, ML20210U020, ML20210U168, ML20211G851, ML20214W928, ML20214W946, ML20215C373, ML20215C402, ML20215C422
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MONTHYEARML20210U1681984-04-0404 April 1984 Changes 0 to 0 of PT/0/A/4150/11A, Control Rod Worth Measurement:Rod Swap Project stage: Other ML20210T9801984-04-26026 April 1984 Changes 0 to 3 of PT/0/A/4150/11, Control Rod Worth Measurement Project stage: Other ML20215C4021985-08-28028 August 1985 Forwards DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20215C4221985-08-31031 August 1985 Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20135D9861985-09-10010 September 1985 Forwards Summary of Review Criteria Evaluations,Per WCAP-9863-A, Rod Bank Worth Measurement Utilizing Bank Exchange & Ser.On 850626,measured 12.5% Below Predicted Value.No Safety Analysis Input Assumptions Effected Project stage: Other ML20210D6961986-09-15015 September 1986 Informs of Results of Cycle 3 Startup Physics Tests Conducted Using Method Described in, Rod Bank Worth Measurement Utilizing Bank Exchange. Ref Bank,Shutdown C, Worth Measured 14% Below Predicted Value Project stage: Other ML20215C3731986-10-0101 October 1986 Forwards Forwarding Rept Re Rod Swap Methodology, Which Was Never Docketed.Info Not Revised in Any Way, Submitted for Docketing Purposes Only Project stage: Other ML20214W9281986-12-0404 December 1986 Forwards Rev 1 to DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20214W9461986-12-31031 December 1986 Rev 1 to DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20207N2931987-01-12012 January 1987 Forwards Request for Addl Info to Complete Review of DPC-NE-1103, Rod Swap Methodology Rept for Startup Physics Testing. Info Required within 30 Days to Meet Review Completion Prior to Approval of Plant Reloads Project stage: RAI ML20213A5551987-01-28028 January 1987 Requests Remittance of Application Fee for Review of Rod Swap Methodology Rept for Startup Physics Testing Project stage: Approval ML20210U0201987-01-29029 January 1987 Changes 0 to 5 of PT/0/A/4150/11A, Control Rod Worth Measurement:Rod Swap Project stage: Other ML20210T9491987-01-29029 January 1987 Changes 0 to 31 of PT/0/A/4150/21, Post-Refueling Controlling Procedure for Criticality,Zero Power Physics & Power Escalation Testing Project stage: Other ML20210T8691987-02-11011 February 1987 Forwards Response to NRC 870112 Request for Addl Info Re Determination of Rod Worth Using Rod Swap Methodology. Methodology Described in 861204 Submittal Will Be Used for 870501 Reloads of Plants Project stage: Request ML20211G8511987-02-16016 February 1987 Comments on D Hood Re 14.5% Discrepancy Between Predicted & Measured Worths of Ref Bank of Unit 2,Cycle 3. Caused by Shortcomings in Measurement Technique.Procedure Used to Measure Rod Worths Will Be Revised Project stage: Other ML20207R7451987-03-11011 March 1987 Forwards Revised Responses to Questions 6 & 7 Re Determination of Rod Worth Using Rod Swap Methodology,Per Ds Hood 870112 Request & 870219 & 0310 Telcons Between Ds Hood & SA Gewehr Project stage: Other ML20214M3101987-05-22022 May 1987 Forwards SER Based on Review of Rod Swap Methodology Rept for Startup Physics Testing & 870211 & 0311 Supplemental Info.Rod Swap Methodology Acceptable for Rod Worth Measurement of Reload Cores for Plants Project stage: Approval ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Approval 1986-12-04
[Table View] |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20203J8581998-01-31031 January 1998 Rev 2 to Catawba Nuclear Station PRA Summary Rept, for Jan 1998.W/one Diskette ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20094N0751995-10-31031 October 1995 Validation of Crest, Interim Rept ML20094N0641995-07-31031 July 1995 Computer Program for Coupled Response Spectrum Analysis of Secondary Sys ML20117M8021995-07-31031 July 1995 CNS Standby Nuclear SW Pond Analysis ML20086F4711995-06-30030 June 1995 Interim Plugging Criteria 90 Day Rept ML20098A4511995-04-30030 April 1995 Stations Replacement SG Topical Rept ML20083N7541995-04-24024 April 1995 Rn Sys Corrosion in Stainless Steel Welds Metallurgical Analysis Rept ML20117M7911995-02-28028 February 1995 Standby Nuclear SW Pond Physical Testing Conducted During Feb 1995 ML20077S6091994-12-31031 December 1994 1994 Annual Insp of Snsw Dam & Wwcb Dikes ML20077R7101994-12-20020 December 1994 CNS Units 1 & 2 10CFR50.59 Evaluation of FSAR Change Related Edsfi Deviation 50413,414/92-01-02 (IEEE 308-1974) ML20077C5771994-11-0303 November 1994 1 Cycle 7 Interim Plugging Criteria Assessment & Projected EOC-8 Slb Leakage ML20072T4441994-08-31031 August 1994 Selected Licensee Commitments ML20063E2801994-01-31031 January 1994 Duke Power Co Catawba Nuclear Station Special Rept RHR Pump Vibration ML20071A9291994-01-25025 January 1994 Nonproprietary McGuire Units 1 & 2 Kinetic Sleeve Evaluation ML20059J2771994-01-18018 January 1994 Non-proprietary Document 51-1228707-01, Evaluation of Bwnt Kinetic Sleeving Process ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20126A0671992-12-0909 December 1992 Snubber Elimination at McGuire Nuclear Station Using Limit Stops, Interim Rept ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20101F1811991-11-18018 November 1991 Rev 0 to Overtemp Delta Temp Scaling,Westinghouse NSSS Process Control Sys ML20079N4011991-11-11011 November 1991 Mixed Waste Characterization & Processing ML20062G7271990-11-19019 November 1990 Eddy Current Exam Rept Catawba Unit 2 June 1990 Refueling Outage 3 ML20043E8101990-02-28028 February 1990 Rev 0 to Catawba Unit 1 Cycle 5 Core Operating Limits Rept. ML20043E7701990-02-28028 February 1990 Rev 0 to Catawba Unit 2 Cycle 3 Core Operating Limits Rept. ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML20011E2531989-07-31031 July 1989 Arrotta Validation & Verification - Std Benchmarks Set. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML20246A6791989-06-30030 June 1989 Description of Additions to & Deviations from Generic Emergency Response Guidelines ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20246J3571989-05-31031 May 1989 Evaluation of Degradation of Tube R18C25 & Justification for Return to Power ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML20244B3341989-05-12012 May 1989 Rev 3 to Final Design Description of ATWS Mitigation Sys Actuation Circuitry ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 1999-09-07
[Table view] |
Text
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4 4 1
I McGuire Nuclear Station Catawba Nuclear Station i
Rod Swap Methodology Report for Startup Physics Testing DPC-NE-1003 August 1985 a f
J. H. Randles R. J. Tomonto t
Duke Power Company Nuclear Production Department Nuclear Engineering f
i I 8610100274 861001
. PDR ADOCK 05000369 p PDR l
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- 1. Introduction This report describes the calculational procedures used to develop the rod swap constants and describes the measurement procedure used to deter =
mine the inferred bank worths. This paper also presents a comparison between the calculated and inferred bank worths for McGuire 1 Cycles 2 and 3, and McGuire 2 Cycle 2. g Inorodetoperfersthe"ControlRodWorthMeasurement-RedSwapTest Procedure" (2), the following information must be provided to the station.
This information shall include the bank worths, critical heights and a's.
The critical heights and o's are used to calculate the inferred bank worth of each control and shutdown bank, as reduced from information following the iso-reactivity interchange with the reference bank.
This r2 port presents the calculated procedures used to derive these parameters. The calculations as performed in this pcocedure utilize the approved physics codes and methodologies described in reference (1).
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- 2. Definitions The following is a list of the constants needed by the plant, to perform the rod swap procedure. These include:
Predicted reactivity worth of each control and shutdown bank, when inserted individually into an otherwise unrodded core.
- h - Predicted critical position of the' reference bank after interchange with bank x, starting with the reference bank at 0 steps and bank x fully withdrawn.
A correction factor which accounts for the effect of bank x on the partial integral worth of the reference bank, equal to the ratio of the integral worth of the reference bank from h to the fully withdrawn position with and without x in the core.
In addition, included is a list of constants and their definitions as used in this report.
- W - Measured rod bank worth of bank x from rod exchange
- (g - Measured rod bank worth of reference bank
- (Ap), - The measured integral worth of the reference bank from the measured critical position (h") to the fully withdrawn position.
- h"* - The measured critical position of the reference bank after interchange with bank x.
- 3. Measurement Procedure With an initial configuration of all rods out, hot zero power, the integral worth of the reference bank is measured using the standard boration/ dilution technique. The reference bank is the bank that is predicted to have the highest integral worth. All other banks are then individually exchanged with the reference bank at constant boron conditions.
The worth of each bank is then the amount of reactivity change caused by the withdrawal of the reference bank to its new critical height.
The rod bank worth is inferred from the measured reference bank worth and the measured reference bank height using the following equation:
W[=W"f, - a, M ,
where the above terms are defined in Section 2.0 of this report.
This test procedure was performed consistent with the approved Westinghouse Rod Swap Methodology.
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- 4. Calculational Procedure This calculation is performed using EPRI-NODE-P to model core conditions during the rod swap procedure. The following procedure describes the method of data generation:
- 1. Calculate the integral bank worth at HZP, ARO critical boron. Insert one bank at a time with no overlap and calculate the bank worth as the difference between ARO and the bank fully inserted condition.
(The calculated highest worth bank will be considered the reference bank.)
- 2. With the reference bank fully inserted, calculate the critical boron concentration. (The reference bank in boron concentration is used in predicting the predicted rod worth - )
- 3. Using the above calculated critical boron concentration for the reference bank, the new integral bank worths at HZP are determined.
. These values correspond to the predicted worth for each bank ( ).
The reference bank should be inserted in approximately six (6) step increments such that a plot of the integral worth of the reference bank can be obtained. (As should be noted, the K,gg with the reference bank inserted, is referred to as the base K,gg).
- 4. In order to calculate the critical height, the. core is modeled with the measured bank fully inserted. The reference, bank is then inserted in approximately six (6) step increments. The critical height (h ) of the reference bank is then calculated by plotting the steps inserted versus K,gg. When K,ff equals the base K,gg, the critical height is found. (This can also be done by linear interpolation between two data points.)
- 5. In order to calculate a for each bank position, the following expression is used:
Integral Worth of the reference bank from h to the fully withdrawn position with bank x inserted in the core a=
Integral worth of the reference bank from h to the fully
, withdrawn position without bank x inserted in the core
- 5. Results Table 1 presents a comparison between Duke's predicted and inferred bank worths. A review of the available data from McGuire 1 Cycles 2 and 3, and McGuire 2 Cycle 2, identifies a mean difference of -7.52 pcm or
-2.27% between Duke's predicted and inferred bank worths. A similar comparison using Westinghouse's predicted and inferred bank worths [
identifies a mean difference of 34.63 pcm or 7.32%.
Table 2 presents a comparison between Duke's and Westinghouse's predicted minus inferred total bank worth difference. In reviewing this information, Westinghouse appears to overpredict on the predicted worth, while Duke's trend appears more evenly scattered.
Table 3 identifies a comparison between Duke and Westinghouse measured minus predicted total critical heights. When evaluating the sum of the absolute value of the differences, Duke was 110 steps closer to the measured critical heights than Westinghouse. When considering the sum of the differences, Duke was 146 steps c.'.eser to the measured critical heights than Westinghouse. The standard deviation of the differences between the measured critical heights and Duke's calculated critical
, heights is 8.82. The standard deviation of the differences between the measured critical heights and Westinghouse's calculated critical heights is 10.46. Duke's predictions appear to be more consistent than Westing-house's prediction.
Table 4 presents some typical a values as calculated for McGuire 1, Cycle 3. ,
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- 6. Conclusion Reference to the Rod Swap Test Procedure (2) identifies the specific
. acceptance criteria. In order to satisfy this procedure the following conditions must be met:
(a) The absolute value of the percent difference between the measured and predicted integral worth for the reference bank is 1 15%.
(b) The absolute,,value of the percent difference between the sum of the measured and predicted integral worth for all the banks is 110%.
(c) For all RCC banks other than the reference bank, either:
(i) the percent difference between the inferred and predicted worth for each individual bank is 1 30%
EE (ii) lW - W l 5 200 pcm for each bank, whichever is greater.
These criterias were found acceptable using both Duke's and Westinghouse's predicted values.
Based upon these measurements, the procedure developed to predict critical heights, a's and bank worths for rod swap yielded respits that were as good as the results obtained using Westinghouse critical heights, a's and bank worths.
Table 1 Duke Predicted and Inferred Bank Worth Duke Predicted Duke Inferred Difference
Unit / Cycle Bank Worth (PCH) Worth (PCM) (PCM) (%) _
1/2 CA 289 301 -12 -4.0 CB 557 606 -49 -8.1 CC 786 788 -2 0.3 CD 616 566 50 8.8 SA 473 546 -73 -13.4 SB 443 479 -36 -7.5 SC 370 354 16 4.5 SD 362 . 374 -12 -3.2 SE 223 237 -14 -5.9 4
Total 4119 4251 -132 -3.1 4
Hean - -
-14.67 -3.17 Standard Deviation - -
35.94 6.80
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Duke Predicted Duke Inferred Difference
Unit / Cycle Bank Worth (PCH) Worth (PCH) (PCH) (%)
1/3 CA 311 305 6 2.0 CB 657 609 48 7.9 CC 789 745 44 5.9 4 CD 488 466 22 4.7 SA 269 303 -34 -11.2 l SB 856 779 77 9.9 l SC 394 373 21 5.6 SD 395 383 12 3.1 SE 429 392 37 9.4 1
! Total 4588 4355 233 5.4 Hean - -
25.89 4.14 Standard Deviation - -
31.16 6.34
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1 Table 1 (Cont.)
4 Duke Predicted Duke Inferred Difference
Unit / Cycle Bank Worth (PCM) Worth (PCM) (PCM) (%)
2/2 CA 437 459 -22 -4.8 CB 413 452 -39 -8.6 CC 858 871 -13 -1.5 CD 654 664 -10 -1.5 SA 327 430 -103 -24.0 SB 425 480 -55 -11.5 SC 354 375 -21 -5.6 SD 355 374 -19 -5.1 SE 270 292 -22 -7.5 Total 4093 4397 -304 -6.9 Mean - -
-33.78 -7.79 Standard Deviation - -
29.42 6.87 i
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Table 1 (Cont.)
Evaluation of All Available Data Duke Calculated Westinghouse Calculated Difference Differences Difference Differences
/
(PCH) (%) (PCM) (%)
Hean -7.52 -2.27 34.63 7.32 l Standard Deviation 40.07 8.13 43.81 8.59 NOTE:
1- Di f ference = Predicted - Infer:cd P - I x 00
> s
Table 2 Comparison of Differences Between Duke and Westinghouse Predicted and Inferred Bank Worth Duke Westinghouse Total Rod Worth Total Rod Worth Difference -
Difference '
Unit / Cycle (PCM) (%) (PCM) (%)
1/2 -132 -3.1 220 5.1 1/3 233 5.4 473 10.8 2/2 -304 -6.9 242 5.5 NOTE:
- Difference = Predicted - Inferred x 100
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E b Table 3 Duke Predicted and Measured Critical Heights Critical lieight (Steps) Duke Calculated Westinghouse Calculated Unit / Cycle Bank Measured Predicted Difference (Steps) Difference (Steps) 1/2 CA 83 88 -5 -14 CB 197 195 2 +15 CD 183 196 -13 -5 SA 191 187 4 14 SB 156 157 -1 3 SC 144 158 -14 3 SD 147 156 -9 4 SE 86 92 -6 -11 I - -
-42 9 I of absolute value - -
54 69 Standard Deviation - -
6.63 10.60
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Table 3 (Cont.)
Critical lleight (Steps) Duke Calculated Westinghouse Calculated Unit / Cycle Bank Heasured Predicted Difference (Steps) Difference (Steps) 127 117 10 9 1/3 CA CB 180 172 8 23 CC 224 201 23 -4 CD 163 156 7 18 SA 127 111 16 21 SC 139 133 6 21 SD 141 133 8 23 SE 132 126 6 12 1 - - 84 123
- - 84 131 I of absolute value Standard Deviation - - 6.00 9.36 a . >
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Table 3 (Cont.)
Critical IIcight (Steps) Duke Calculated Westinghouse Calculated Unit / Cycle Bank Measured Predicted Difference (Steps) Difference (Steps) i 2/2 CA 153 146 7 13 CB 190 191 -1 4 CD 202 205 -3 2 SA 198 186 12 16 SB 194 183 11 15 SC 185 182 3 14 SD 184 182 2 13 SE 149 141 8 18 I - -
39 95 I of absolute value - -
47 95 Standard Deviation - -
5.49 5.74
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I Table 3 (Cont.)
- Evaluation of All Available Data Duke Calculated Westinahouse Calculated i I (Differences) 81 227 1
3 j I (Absolute Value of Differences) 185 295 i ,
i j Standard Deviation 8.82 10.46 l (of the Differences) 4 l
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NOTE:
- Difference = Measured - Predicted ,
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Table 4 a's Unit / Cycle Bank Duke Calculated 1/3 CA 1.042 CB O.877 CC 0.870 CD 1.161 SA 1.060 SC 1.052 SD 1.050 SE 0.903 a
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-. g Reference
- 1. Duke Power Company, " Nuclear Physics Methodology for Reload Design",
DPC-NF-2010A, June 1985.
- 2. Duke Power Company, McGuire Nuclear Station, " Control Rod Worth Measurement: Rod Swap Test Procedure", PT/0/A/4150/11A, April 1984.
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