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:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review 1999-09-16
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Z7751998-09-0808 September 1998 Rev 25 to McGuire Selected Licensee Commitment Manual, Consisting of Revised Pages 16.7-9 & 16.7-10 ML20236P8671998-07-0606 July 1998 Updated Pages to Catawba Nuclear Station Selected License Commitments Manual ML20249B6221998-06-11011 June 1998 Revised Table of Contents for Chapter 16 of Selected License Commitments Manual ML20249C2081998-06-0909 June 1998 Rev 24 to Selected License Commitments (SLC) Manual & SLC 16.10.1,dtd June 1998 ML20247Q9871998-05-11011 May 1998 Revised Chapter 16 to Selected License Commitment Manual ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20203J9391998-02-19019 February 1998 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20203E1911997-12-0101 December 1997 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20216A8691997-09-0101 September 1997 Rev 0 to QAM-2.0, Order Entry ML20141F1521997-06-25025 June 1997 Rev 4 to Nuclear Security Training & Qualification Plan ML20141D2721997-05-29029 May 1997 Chapter 16.8 to Electrical Power Sys, Chapter 16.10.1 to Steam Vent to Atmosphere & Revised Table of Contents ML20140D1361997-05-27027 May 1997 Rev 21 to McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20148G0251997-05-13013 May 1997 Revised Pages to Selected License Commitments Manual, Chapters 16.10.1 & 16.10.2 Re Steam Vent to Atmosphere & Condenser Circulating Water Sys,Respectively ML20148D5041997-05-0909 May 1997 Rev 19 to Selected Licensee Commitment Manual 16.5-4 ML20141B1371997-04-30030 April 1997 Chapter 16 to Table of Contents & Chapter 16.10.1 to Steam & Power Conversion Sys of Selected License Commitment Manual ML20137Q8351997-03-31031 March 1997 Revised Selected Licensee Commitments Manual ML20135A8581997-01-15015 January 1997 Revised Selected License Commitment Manual ML20133F9041996-12-26026 December 1996 Selected Licensee Commitments Manual, Rev 18 ML20134F8651996-10-21021 October 1996 Rev to Selected Licensee Commitments Manual ML20117K2851996-08-22022 August 1996 Rev 16 to Selected Licensee Commitments Manual ML20117M5901996-08-15015 August 1996 Loss of Electrical Power ML20115C9971996-06-25025 June 1996 Revised McGuire Nuclear Station Selected Licensee Commitiments Manual ML20115E8871996-06-18018 June 1996 Revised Pages to Selected Licensee Commitments Manual ML20112B7651996-05-13013 May 1996 Rev to Selected Licensee Commitments Manual ML20111B7401996-05-0202 May 1996 Revised Selected License Commitment Manual, New Selected License Commitment 1999-08-18
[Table view] |
Text
-
. (SAG 46)
McGuire Nuclear Station Catawba Nuclear Station Rod Swap Methodology Report for Startup Physics Testing DPC-NE-1003 REVISION 1 December 1986 J.H. Randles R.J. Tomonto Duke Power Company Design Engineering Department Nuclear Engineering 8612100472 861204 PDR P ADOCK 05000369 PDR
- 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, 3 and 4, and McGuire 2 Cycles 2 and 3.
In order to perform the " Control Rod Worth Measurement - Rod Swap Test 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 a'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 report presents the calculated procedures used to derive these parameters. The calculations as performed in this procedure utilize the approved physics codes and methodologies described in reference (1).
I 4
f i
--- - - - - - - - - - - - - - ~ ~ - ~
- 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.
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 P 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.
Heasured 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.
J 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:
WxI = W" ref
-a x (Ap)x where the above terms are defined in Section 2.0 of this report.
i I
e i
- 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 with the ff reference bank inserted, is referred to as the base Kdf) *
- 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 When K equals the base K ff. ff ff, 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 fromPh to the fully withdrawn position without bank x inserted in the core i
- - , , - - - - - - - _ , - _ - - . - - - - , . .- . - - , - - - - . , . . . - - -- .- . . - - - - - - - . . . - - . - , - - , , . ~ , - - . .
- 5. Results Table l' presents a comparison between Duke's predicted and inferred bank worths. A review of the available data from McGuire 1 Cycles 2, 3, and 4, and McGuire 2 Cycles 2 and 3, identifies a mean difference of 5.27 pcm or 0.66% between Duke's predicted and inferred bank worths.
Table 2 identifies a comparison between measured and predicted total critical heights. The standard deviation of the differences between the measured critical heights and Duke's calculated critical heights is 12.63.
Table 3 presents some typical a values as calculated for McGuire 1, Cycle 3.
- 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 515%.
(b) The absolute value of the percent difference between the sum of the measured and predicted integral worth for all the banks is 510%.
(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 5 30%
EE (ii) lWf-Wl5200pcmforeachbank, whichever is greater.
These criteria were found acceptable using Duke's predicted values.
Based on the predicted and measured data presented in this report the rod swap method described has been verified to be accurate for use in startup physics testing.
,- ,e - -- ......n- - -,--- - - e - -- - --- --- ,n, .~ n- +-- - --- - - - - - - - ---
s J .
j Table 1 Duke Predicted and Inferred Bank Worth *
$ Duke Predicted Duke Inferred Difference
! Unit / Cycle Bank Worth (PCM) Worth (PCM) (PCM) (%)
l 1/2 CA 289 301 -12 -4.0 CB 557 606 -49 -8.1
, CC 786 788 -2 -0.3 j CD 616 566 50 8.8 i
l SA 473 546 -73 -13.4 i SB 443 479 -36 -7.5 SC 370 354 16 4.5 SD 362 374 -12 -3.2
, SE 223 237 -14 -5.9
.]
j Total 4119 4251 -132 -3.1
! Mean - -
-14.67 -3.17 j Standard Deviation - -
35.94 6.80 l
i i
j 1
i I
1 i
Table 1 (Cont.)
Duke Predicted Duke Inferred Difference
Unit / Cycle Bank Worth (PCM) Worth (PCM) (PCM) (%)
1/3 CA 311 305 6 2.0 CB 657 609 48 7.9 CC 789 745 44 5.9 CD 488 466 22 4.7 SA 269 303 -34 -11.2 SB 856 779 77 9.9 SC 394 373 21 5.6 SD 395 383 12 3.1 SE 429 392 37 9.4 Total 4588 4355 233 5.4 Mean - -
25.89 4.14 Standard Deviation - -
31.16 6.34
Table 1 (Cont.)
Duke Predicted Duke Inferred Difference
Unit / Cycle -Bank Worth (PCM) Worth (PCM) (PCM) (%)
1/4 CA 301 313 -12 -3.8 CB 656 677 -21 -3.1 CC 775 778 -3 -0.4 CD 581 556 25 4.5 SA 293 307 -14 -4.6 SB 746 750 -4 -0.5 SC 381 377 4 1.1 SD 382 314 68 21.7 SE 473 471 2 0.4 Total 4588 4543 45 1.0 Mean - -
5 1.7 Standard Deviation - -
27.04 8.0 l
Table 1 (Cont.)
Duke Predicted Duke Inferred Difference
Unit / Cycle Bank Worth (PCM) Worth (PCM) (PCM) (%)
t 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
-. - _ _ _ - - - - . . - - - - - . . - - . - - - . - - - . - - . .- - - .~ . . - - . - - - - - - _ - - . -
. - - . - _ _ ~ -
1 i
{ Table 1 (Cont.)
- Duke Predicted Duke Inferred Difference
Unit / Cycle Bank Worth (PCM) Worth (PCM) (PCM) (%)
i 2/3 CA 344 314 30 9.6 I l CB 698 '668 30 4.5 l
- CC 869 787 82 10.4 j CD 591 530 61 11.5 i
j SA 381 404 -23 -5.7 i SB 906 842 64 7.6 i SC 438 378 60 15.9 l SD 440 406 34 8.4 j SE 481 424 57 13.4 i
1 1 Total 5148 4753 395 8.3 Mean - -
43.89 8.40 Standard Deviation - -
30.70 6.23 1
4 1
1
- This was the reference bank used because vendor supplied data was used for the official rod snap l calculations.
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Table 1 (Cont.)
Evaluation of All Available Data Duke Calculated Difference Differences (PCH) (%)
Mean 5.27 .66 Standard Deviation 40.72 8.69 NOTE:
- Difference = Predicted - Inferred
l .- -
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L Table 2
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- Duke Predicted and ifcisured Critical Heights * '5 "
'i
., s <
'-0i 3x.. p. "., .,4 --
1
\ . . ., ~
4 Critical Height (Steps) , .'s ,
l Unit / Cycle Bank Measured , Predicted ' hDifference (Steps) >
\-, g s - ', , .., - r,., e
'1/2 a' '. ~g 1
~'
, CA 83 A', 88 ..~ -5 .
f . ' s[ ,>6s CB 197 -\ 195 2 4 m --
2 s
CD 183 196 -13 -
i < 4
, r , *.
j r. SA.> v 191 i N '187 ^; '
4 i 4 ,
SB' l .-
' 15b~ ' '\ 157 -
-1 a Y 1 - SC x-144 158' -14 i s
-._ ' SD .'
S 747 156 -9
'T '
' SE i ~
. % 86' w 92 -6
,s 4 I s
42 _
}
- r Y
jE,of absolute vaiue i
.s i - -
54 , {.
]
s E
, Standard Deviation .
t; 6.63 s4 % 'N - * .
4 +
y 3 f 'k i
's ,' %' ,
! h e ,
y k \ % > w.
v_. i '
i
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s, j *%
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Table 2 (Cont.)
Critical Height (Steps)
Unit / Cycle Itank Measured Predicted Difference (Steps) 1/3 CA 127 117 10 CB 180 172 8 CC 224 201 23 CD 163 156 7 SA 127 111 16 SC 139 133 6 SD 141 133 8 SE 132 126 6 I - -
84 I of absolute value - -
84 Standard Deviation - -
6.00 i
_ r '
Table 2 (Cont.)
Critical Height (Steps-)
Unit / Cycle Bank Measured Predicted Difference (Steps) 1/4 CA 108 121 -13 CB 201 203 -2 CD 179 191 -12 SA 136 149 -13 SB 218 216 2 SC 147 161 -14 SD 136 161 -25 SE 151 163 -12 I - -
-89 I of absolute value - -
93 Standard Deviation- - -
8.15 I
i l
Table 2 (Coat.)
Critical Height (Steps)
Unit / Cycle Bank Measured Predicted Difference (Steps) 2/2 CA 153 146 7 CB 190 191 -1 CD 202 205 -3 SA 198 186 12 SB 194 183 11 SC 185 182 3 SD 184 182 2 SE 149 141 8 I - -
39 I of absolute value - -
47 Standard Deviation - -
5.49 6
l 4
I
- - - - - - - . ~ ~ . . .. . - . -- ~. . .- _ __. .
1 Table 2 (Cont.)
j Critical Height (Steps)
Unit / Cycle Bank Measured Predicted Difference (Steps) 2/3 .CA 99 112 -13 CB 173 191 -18 CD 158 179 -21 i SA 123 145 -22 SB 228 228 0 SC 130 159 -29 SD 131 159 -28 SE 131 147 -16 I - -
-147
! I of absolute value - -
147 Standard Deviation - -
9.24 i
)
i 1
l 1
I l
l J
1 ,
Table 2 (Cont.)
Evaluation of All Available Data Duke Calculated I (Differences) -155 t I (Absolute Value of Differences) 425 Standard Deviation 12.63 (of the Differences) i 2
4 e
P NOTE:
t
- Difference = Measured - Predicted l I
J i
[ e .
Table 3 O'S Unit / Cycle Bank Calculated 1/3 CA 1.042 CB 0.877 CC 0.870 CD 1.161 SA 1.060 SC 1.052 SD 1.050 SE 0.903 1
l t
l r
I l-
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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