ML093130440

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GNF-0000-0100-8106, Gnf Additional Information Re Requested Changes to the Technical Specification SLMCPR, Vermont Yankee Cycle 28.
ML093130440
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 09/21/2009
From:
Global Nuclear Fuel - Americas
To:
Office of Nuclear Reactor Regulation
References
GNF-0000-0100-8106
Download: ML093130440 (24)
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{{#Wiki_filter:Docket No. 50-271 BVY 09-063 Attachment 6 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 287 GNF Summary of Technical Basis for SLMCPR Values (Non-Proprietary Version)Attachment 6 . Vermont Yankee Nuclear Power Station Docket No. 50-271 BVY 09-063 Proposed Techrlical Specification Change No. 287 GNF Summary of Technical Basis for SLMCPR Values (Non-Proprietary Version) GNF NON-PROPRIET, ARY [NFORMATION Class I GNF Attachment 9/21/2009 GNF-0000-0100-8106 eDRFSection: 0000-01.00-8106-RO GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Vermont Yankee Cycle 28 Vermont Yankee Cycle 28 Page I of 23 GNE" HORMA]10Nl CFass E GNP' AMaelilment 9/2.112009: GNF-OOOO-O 100-8 r 06 eDRFSection: 0000-0100-8106-RO GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Vermont Yankee Cycle 28 Vermont Yankee Cycle 28 Page 1 of23 GNF NON-PROPRIETARY JINFORMATION Class .GNF AttachmentPROPRIETARY INFORMATION NOTICE This document is the GNF non-proprietary version of the GNF proprietary report. From the GNFF proprietary version, the information denoted as GNIF proprietary (enclosed in double brackets) was deleted to generate this version,.. Important Notice Regarding Contents of this Report Please Read Carefully The only undertakings of Global Nuclear Fuel-Americas, LLC (GNF-A) with respect to information in this document are contained in contracts between GNF-A and its customers, and nothing contained in this document shall be construed as changing those contracts. The use of this information by anyone other than those participating entities and for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or warranty, and assumes no liability as to .the completeness, accuracy, or usefulness of the information contained in this document.Page 2 of 23 GrNFNON::'PRJi)17lmaTARY liNilFORMAlITONi Class: K GTNiFt AHadlment . P n'OpDTCT*/t DY* T/ii;,1lE:OD1'LIri/t'T'FO* il\,liN*O*TIC'C*

t ! Ji' 'll"l1 : 1, 'Ji:j, This: document is the GNP non-propri.etaJIy weliSion ofthe GNF proprietary report. From the GNF proprietaJIy version, the information denoted as: GNF proprietaJIy (endosed in double brackets) was deleted to generate this version .. Important Notice Regardi.ng Contents of this Report Please Read Carefully The only undertakings of Global Nuclear Fuel-Americas, .L.LC (GNF-A) with respect to information in this document are contained in contracts between GNF-A and its customers, and nothing contained in this document shall be construed as changing those contracts. The use of this information by anyone other than those participating entities and for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document. Page 2 of 23 GNF NON'-PROPRIEFTEY I FORMATION! Class I GN' Attachment Table of Contents 1.0 METHODOLOGY .................................................................................................................................... 4 2.0 DISCUSSION .............................. ................ ....................................................................... 4 2.1. MAJOR CONTRIBUTORS TO SLMCPR CHANGE .......................................................................................... 4 2.2. DEVIATIONS IN NRC-APPROVED UNCERTAINTIES .................................................................................... 5 2.2.1. R -Factor. ................................................................................................................................................ 5 2.2.2. Core Flow Rate and Random Effective TIP Reading .................................. 5 2.3. DEPARTURE FROM NRC-APPROVED METHODOLOGY .............................................................................. 5 2.4. FUEL AXIAL POWER SHAPE PENALTY ............................................................................. ........................ 6 2.5. METHODOLOGY RESTRICTIONS ...................................................................................................................... 7 2.6. MINIMUM CORE FLOW CONDITION ................................................................................................................ 7 2.7. LIMITING CONTROL ROD PATTERNS .............................................................................................................. 7 2.8. CORE MONITORING SYSTEM ....................... ! ................................................................................................. 7 2.9. PO W ER/F LOW M AP ......................................................................................................................................... 7 2.10. CoRE LOADING DIAGRAM ...................................................................................................................... 7 2.11. FIGURE REFERENCES ................................... ............................... ...................... ............ 7 2.12. ADDITIONAL SLMCPR LICENSING CONDITIONS ................................................................................ 7 2.13. SU M M AR Y .................................................................................................................................................. 8

3.0 REFERENCES

................................................................................................................................................ 9 List of Figures FIGURE 1. CURRENT CYCLE CORE LOADING DIAGRAM ......................................................................................... 10 FIGURE 2. PREVIOUS CYCLE CORE LOADING DIAGRAM .............................................................................................. 11FIGURE 3. FIGURE 4.1 FROM NEDC-3260 I-P-A ..................................................................................................... 12 FIGURE 4. FIGURE 111.5-1 FROM NEDC-32601P-A ...................... ......................................................................... 13 FIGURE 5. FIGURE 111.5-2 FROM NEDC-32601P-A ................................................................................................ 14 List of Tables TABLE 1. DECIPIN FCOE.TA L .DESCRIPTION OF CORE ................................................................................................................................ a...15 TABLE 2. SLMCPR CALCULATION METHODOLOGIES ............................................................................................. 16 TABLE 3. MONTE CARLO CALCULATED SLMCPR vs. ESTIMATE .......................................................................... 17 TABLE 4. NON-POWERDISTRJB1ITION UNCERTAINTIES ............................................... 19 TABLE5. POWER DISTRIBUTION UNCERTAINTIES ...................... ......................... ........................... 21 TABLE 6. CRITICAL POWER UNCERTAINTIES ................... ....... ................ ......... .......................... 23 Table of Contents Page 3 of 23 GNFNON::"PROPruEll'ruty liNiIfOR:MA1i10N E GN!lF Att!aellmenF 1.0 METHODOLOGY .......................................................................................................................................... 4 2.0 DISCUSSION ................................................................................................................................................... 4 2.1. MAJOR CONTRIBUTORS TO SLMCPR CHANGE .............

................................................................................

4 2.2. DEVIATIONS IN NRC-ApPROVED UNCERTAINTIES ......................................................................................... 5 2.2.1. R-Factor .............................................. ................................................................................................... 5 2.2.2. Core How Rate and Random Effective TIP Reading ............................................................................. 5 2.3. DEPARlURE FROM NRC-ApPROVED METHODOLOGY .................................................................................... 5 2.4. FUEL AxIAL POWER SHAPE PENALTY ............................................................................................................ 6 2.5. METHoDOLOGY RESTRICTIONS ...................................................................................................................... 7 2.6. MINIMUM CORE FLOW CoNDITION ................................................................................................................ 7 2.7. LIMITING CONTROL ROD PATTERNS .............................................................................................................. 7 2.8. CORE MONITORING SySTEM ....................... , .................................................................................................. 7 2.9. POWERlFWW MAP .......................................................................................................................................... 7 2.10. CoRE LoADING DIAGRAM .......................................................................................................................... 7 2. L L. FIGURE REFERENCES .................................................................................................................................. 7 2.12. ADDITIONAL SLMCPR LICENSING CONDITIONS ....................................................................................... 7 2.13.

SUMMARY

...................................................................................................................................................

8

3.0 REFERENCES

................................................................................................................................................. 9 List of Figures FIGURE I. CURRENT CYCLE CORE LOADING DIAGRAM .............................................................................................. 10 FIGURE 2. PREVIOUS CYCLE CORE LoADING DIAGRAM .............................................................................................. 11 FIGURE 3. FIGURE 4.1 FROM NEDC-3260 I-P-A ......................................................................................................... 12 FIGURE 4. FIGUREIII.5-1 FROM NEDC-3260IP-A ...................... l, ............................................................................. 13 FIGURE 5. FIGURE Ill.5-2 FROM NEDC-3260IP-A ..................................................................................................... 14 List of Tables TABLE 1. DESCR1PTION OF CORE .............................................................................................................................. ?, .. 15 TABLE 2. SLMCPR CALCULATION METHODOLOGTES ................................................................................................ 16 TABLE 3. MONTE CARLo CALcULATED SLMCPR VS. ESTIMATE ..............................

...............................................

17 TABLE 4. NON-POWERDISTruBUTION UNCERTAINTIES .............................................................................................. 19 TABLE 5. POWER DISTRIBUTION UNCERTAINTIES ...................................

.....................................................................

21 TABLE 6.CRInCAL PO\VER UNCERTAINTIES .................................................................................................................. 23 Table of Contents Page 3 of23 GNF NON-PROPRIETARY INFORMATION Cl1ass I G NF Attachment 11.0 Methodology GNF performed the Vermont Yankee Cycle 28 Safety Limit Minimum Critical Power Ratio (SLMCPR) calculation in accordance to NEDE-240I1-P-A "General Electric Standard Application for Reactor Fuel" (Revision

16) using the following NRC-approved methodologies and uncertainties: " NEDC-32601P-A "Methodology and Uncertai nties for Safety Limit MCPR Evaluations" (August 1999)." NEDC-32694P-A "Power Distribution Uncertainties for Safety Limit MCPR Evaluations" (August 1999)." NEDC-32505P-A "R-Factor Calculation Method for GEl 1, GE12 and GE13 Fuel" (Revision 1, July 1999).* NEDO-10958-A "General ElectricBWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application" (January 1977).Table 2 identifies the actual methodologies used for the previous Cycle 27 and the current Cycle 28 SLMCPR calculations.

2.0 Discussion In this discussion, the TLO nomenclature is used for two recirculation loops in operation, and the SLO nomenclalure is used for one recirculation loop in operation. 2.1. Major Contributors to SLMCPR Change In general, the calculated safety limit is dominated by two key parameters: (1) flatness of the core bundle-by-bundle MCPR distribution, and (2) flatness of the bundle pin-by-pin power/R-factor distribution. Greater flatness in either parameter yields more rods susceptible to boilingtransition and thus a higher calculated SLMCPR. MIP (MCPR Importance Parameter) measures the core bundle-by-bundle MCPR distribution and RIP (R-factor Importance Parameter) measures the bundle pin-by-pin power/R-factor distribution. The impact of the fuel loading pattern on the calculated TLO SLMCPR using rated core power and rated core flow conditions has been correlated to the parameter MIPRIP, which combines the MIP and RIP values.Table 3 presents the MIP and RIP parameters for the previous cycle and the current cycle along with the TLO SLMCPR estimate using the MIPRIP correlation. If the minimum core flow caseis applicable, the TLO SLMCPR estimate is also provided for that case although the MIPRIP correlation is only applicable to the rated core flow case. This is done only to provide some reasonable assessment basis of the minimum core flow case trend. In addition, Table 3 presents estimated impacts on the TLO SLMCPR due to methodology deviations, penalities, and/or uncertainties deviations from approved values. Based on the MIPRIP correlation and any impacts due to deviations from approved values, a final estimated TLO SLMCPR is determined. Methodology Page 4 of 23 GNFNON:'PROPR.EIEIrMV IINlIFORMA1l10Nl Class: If G1NlF Ati1iachmmt 11.,0; . GNIF peri'mmed the Verm.ont Yankee C.ycle 28 Safety Umit .Minimum C.ritical, Power Ratio (SILMCPR) calculation in accordance to NEUB-24011l.-P:..A '"General Electri.c Standatrdi Application for Reactor Fuel" (Revision

16) using the following NRC-approved methodologies:

and uncertainties: .NEDC-32601P-A "Methodology and Uncertainties for Safety Limit MCPR Evaluations'" (August 1999).

  • NEDC-32694P-A "Power Distribution Uncertainties for Safety Limit MCPR Evaluations" (August 1999), .
  • NEDC-32505P-A "R-Factor Calculation Method for GEll, GEI2 and GE13 Fuel" (Revision 1, July 1999).
  • NEDO-10958-A "General Electric.BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application" (January 1977). Table 2 identifies the actual methodologies used for the previous Cycle 27 and the current Cycle 28 SLMCPR calculations.

2.0 Discussion In this discussion, the TLO nomenclature is used for two recirculation loops in operation, and the SLO nomenclature is used for one recirculation loop in operation. 2.1. Major Contributors to SLMCPR Change In general, the calculated safety limit is dominated by two key parameters: (I) flatness of the core bundle-by-bundle MCPR distribution, and (2) flatness o( the bundle pin-by-pin factor distribution. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR MIP (MCPR Importance Parameter) measures the core bundle-by-bundle MCPR distribution and RIP (R-factor Importance Parameter) measures the bundle pin-by-pin power/R-factor distribution. The impact of the fuel loading pattern on the calculated TLO SLMCPR using rated core power and rated core flow conditions has been correlated to the parameter MIPRIP, which combines the MIP and RIP values. Table 3 presents the MIP and RIP parameters for the previous cycle and the current cycle along with the 11.0 SLMCPR estimate using the MIPRIP correlation. If the minimum core flow case is applicable, the TLO SLMCPR estimate is also provided for that case although the MIPRIP correlation is only applicable to the rated core flow case. This is done only to provide some reasonable assessment basis 'Of the minimum core flow case trend. In addition, Table 3 presents estimated impacts en the 11.0 SLMCPR due to methodology deviatiens, penalities,andior uncertainties deviations from approved values. Based on the MIPRIP ,correlation and any impacts due to deviations from approved values, a .final estimated TLO SLMCPR is determined. Methodology Page40f23 GNF NON-PROPRIETARY NFORMATION Class, [GN,, Attachment Table 3 also provides the actual calculated, M.'onte Carlo SLMCPRs. Given the bias and uncertainty in the MIPR[P correlation t3) and the inherent variation in the Monte: Carlo results 11 the. change in the Vermont Yankee Cycle 28calculated Monte Carlo TLO SLMCPR using rated core power and rated core flow conditions is consistent with the corresponding estimated TLO SLMICPR value.2.2. Deviations in NRC-Approved Uncertainties Tables 4 and 5 provide a list of NRC-approved uncertainties along with values actually used. A discussion of deviations from these NRC-approved values follows; all of which are conservative relative to NRC-approved values. Also, estimated impact on the SLMCPR is provided in Table'3 for each deviation. 2.2.1. R-Factor At this time, GNF has generically increased the GEXL R-Factor uncertainty from [[(3}]] to account for an increase in channel bow due to the emerging unforeseen phenomena called control blade shadow corrosion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the approved R-Factor uncertainty. The step "a RPEAK" in Figure 4.1 from NEDC-32601P-A, which has been provided for convenience in Figure 3 of this attachment, is affected byy this deviation. Reference 4 technically justifies that a GEXL R-Factor uncertainty of I accounts for a channel bow uncertainty of up to (3).Currently, Vermont Yankee has not experienced any control blade shadow corrosion-induced channel bow and is not expected to experience any in Cycle 28 to the extent that wouldinvalidate the approved R-Factor uncertainty. 2.2.2. Core Flow Rate and Random Effective TIP Reading At this time, GNF has not been able to show that the NRC-approved process to calculate the SLMCPR only at the rated core power and rated core flow condition is adequately bounding relative to the SLMCPR calculated at rated core power and minimum core flow, see Reference 5.The minimum core flow condition can be more limiting due to the control rod pattern used.GNF has modified the NRC-approved process for determining the SLMCPR to include analyses at the rated core power and minimum licensed core flow point in addition to analyses at the rated core power and rated core flow point. GNF believes this modification is conservative and may in the future provide justification that the original NRC-approved process is adequately bounding.The available flow range at rated power, 99% to 100% rated core flow, does not warrant analysis at the minimum core flow point.2.3. Departure from NRC-Approved Methodology No departures from NRC-approved methodologies were used in the Vermont Yankee Cycle 28 SLMCPR calculations. Discussion Page 5 of 23 GNF NOt'[ .. I!NJFORMAlITON Clasg, [ GNF Attacnme1i1t' 3 also provides the actual calculated. Monte SJLMCPRs. Given the bias and tlRcertainty in the MIPRIP correlation K[ {J}]] and the inherent vati'iation in the Monte Carlo results [[ the: change in the Vermont Yankee Cycle 28 calculated Monte Carlo TLO SLMCPR using rated COlle power and rated core flow conditions is: consistent with the corresponding estimated no SLMCPR value. 2.2. Deviations in NRC-Approved Uncertainties Tables 4 and 5 provide a list of NRC-approved uncertainties along with values actually used. A discussion of deviations from these NRC-approved values follows; all of which are conservative relative to NRC-approved values. Also, estimated impact on the SLMCPR is provided in Table '3 for each deviation. . 2.2.1. R-Factor At this time, GNF has generically increased the GEXL R-Factor uncertainty from [[ (3}]) to account for an increase in channel bow due to the emerging unforeseen phenomena called control blade shadow corrosion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the approved R-Factor uncertainty. The step "0 RPEAK" in Figure 4.1 from NEDC-3260IP-A, which has been provided for convenience in Figure 3 of this attachment, is affected b 6 this deviation. Reference 4 technically justifies that a GEXL Factor uncertainty of [[ 3}]] accounts for a channel bow uncertainty of up to [[ {3}]]. Currently, Vermont Yankee has not experienced any control blade shadow corrosion-induced channel bow and is not expected to experience any in Cycle 28 to the extent that would invalidate the approved R-Factor uncertainty. 2.2.2. Core Flow Rate and Random Effective TIP Reading At this time, GNF has not been able to show that the NRC-approved process to calculate the ' SLMCPR only at the rated core power and rated core flow condition is adequately bounding relative to the SLMCPR calculated at rated core power and minimum core flow, see Reference

5. The minimum core flow condition can be more limiting due to the control rod pattern used. GNF has modified the NRC-approved process for determining the SLMCPR to include analyses at the rated core power and minimum licensed core flow point in addition to analyses at the rated core power and rated core flow point. GNF believes this modification is conservative and may in the future provide justification that the original NRC-approved process is adequately bounding.

The available flow range at rated power, 99% to 100% rated core flow, does not warrant analysis at the minimum core flow point. 2.3. Departure from NRC-Approved Methodology No departures from NRC-:approved methodologies were used in the Vermont Yankee Cycle 28 SLMCPR calculations. Discussion Page 5 of 23 GN NON-PROPR[ETARY IFORMATION Class f GNIF Attachment-2.4. Fuel Axial Power Shape Penalty At this time, GNF has determined that higher uncertainties and non-conservative biases in the GEXL correlations for the various types of axial power shapes (i.e_, inlet, cosine, outlet and double hump) could potentially exist relative to the, NRC-approved methodology values, see References 3, 6, 7 and 8. The folowing table identifies, by marking with an, "X", this potential for each GNF product line currently being offered:[[Axial bundle power shapes corresponding to the limiting SLMCPR control blade patterns are determined using the PANACEA 3D core simulator. These axial power shapes are classified in accordance to the following table: If the limiting bundles in the SLMCPR calculation exhibit an axial power shape identified by this table, GNF penalizes the GEXL critical power uncertainties to conservatively account for the impact of the axial power shape. Table 6 provides a list of the GEXL critical power uncertainties determined in accordance to the NRC-approved methodology contained in NEDE-2401 1-P-A along with values actually used.For the limiting bundles, the fuel axial power shapes in the SLMCPR analysis were examined to determine the presence of axial power shapes identified in the above table. These power shapes were not found; therefore, no power shape penalties were applied to the calculated Vermont Yankee Cycle ý28 SLMCPR values.Discussion Page 6 of 23 GNf IITNilFORMlAll0N Class: I GlNiF Amiadmr*:1ilit F'uel, Axial Power Shape' Penalty At mils time, GNF has detetmined that highetr utlcel11arnmt1es: and mOl1-conservative biases: Ln tlte; GEXIL correlations for the various: types. of aoo:i:aI! power shapes (i.e .* inlet, cosine, oudet and[ double hllmp) could potentially exist relative to tlte NRC'-appFOved. methodology see References 6, 7 and 8. The foHowing tab;le identifies, by marking with an <<X", this potential! for each GNF pFOduct line currently being offered:. [[ {3}1 ]] Axial bundle power shapes corresponding to the limiting SLMCPR control blade patterns are determined using the PANACEA 3D core simulator. These axial power shapes are classified in accordance to the following table: [[ I . \ l3}]] If the limiting bundles in the SLMCPR calculation exhibit an axial power shape identified by this table. GNF penalizes: the GEXL critical power uncertainties to conservatively account for the impact of the axial power shape. Table 6 provides a list of the GEXL critical power uncertainties determined in accordance to the NRC-approved methodology contained in NEDE-24011-P-A along with values actually used. For the limiting the fuel axial power shapes in the SLMCPR analysis were examined to determine the presence of axial power shapes identified in the above table. These power shapes were not found; no power shape penalties were applied to the calculated Vermont Yankee Cycle.28 SLMCPR values. Discussion Page*60f23 GNF NON-PROPRETiARY mORMATION Class, I GNF, Attachment-2.56. Methodology Restrictions The, four restrictions identified on Page. 3 of NRC's Safety Evaluation relating to the General Electric Licensing Topical Reports NEDC-32601 P. NEDC-32694P, and Amendment. 25 to NEDE-2401 1-P-A (March 11, 1999) are addressed in References t, 2, 3, and 9.No new GNF fuel designs are being introduced in Vermont Yankee Cycle 28; therefore, the: NEDC-32505-P-A statement "... if new fuel is introducted, GENE must confirm that the revised R-Factor method is still valid based on new test data" is not applicable. The GNF2 product line is not considered a new fuel design relative to the GEl4 product line, as both consist of 10 x 10 lattice designs.2.6. Minimum Core Flow Condition The available flow range at rated power, 99% to 100% rated core flow, does not warrant analysis at the minimum core flow point. 2.7. Limiting Control Rod Patterns The limiting control rod patterns used to calculate the SLMCPR reasonably assures that at least 99.9% of the fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences during the operation of Vermont Yankee Cycle 28.2.8. Core Monitoring System For Vermont Yankee Cycle 28, the 3D Monicore system will be used as the core monitoring system.2.9. PowerlFlow Map The utility has provided the current and previous cycle power/flow map in a separate attachment. 2.10. Core Loading Diagram Figures I and 2 provide the core loading diagram for the current and previous cycle respectively, which are the Reference Loading Pattern as defined by NEDE-2401 1-P-A. Table 1 provides a description of the core.2.11. Figure References Figure 3 is Figure 4-1 from NEDC-32601-P-A. Figure 4 is Figure II.5-1 from NEDC-32601P-A. Figure 5 is Figure -1.5-2 from NEDC-32601P-A. 2.12. Additional SLMCPR Licensing Conditions For Vermont Yankee Cycle 28, the additional SLMCPR licensing condition (Reference

10) that the SLMCPR shall be established by adding 0.02 to the cycle-specific TLO SLMCPR value Discussion Page 7 of 23 GNP JiN!JFORMAlITONl E GNF A1it!aemment 2.5., M'ethodology Restrictions The; four restrictions identified on 3 of lNlRC"s Safety Evaluation relating to the Genefal: Efectric Licensing Topical Reports NEDC-32694P, and Amendment 25 to NEDE-24011-P-A (March 11, 1999) are addressed En References 1,2,3, and 9. No new GNF fuel designs are being intmduced In Vermont Yankee Cycle therefore, the NEDG-32505-P-A statement" ... if new fuet is introducted, GENE must confirm that the revised R-Factor method is still valid based on new test data n is not applicable.

The GNF2 product line is not considered a new fuel design relative to the GE14 product line, as both consist of 10 x 10 lattice designs. 2.6. Minimum Core Flow Condition The available flow range at rated power, 99% to 100% rated core flow, does not warrant analysis at the minimum core flow point. 2.7. Limiting Control Rod Patterns The limiting control rod patterns used to calculate the SLMCPR reasonably assures that at least 99.9% of the fuel rods in the core would not be expected to experience boiling transition during operation or anticipated operational occurrences during the operation of Vermont Yankee Cycle 28. 2.8. Core Monitoring System For Vermont Yankee Cycle 28, the 3D Monicore system will be used as the core monitoring system. 2.9. Power/Flow Map . The utility has provided the current and previous cycle power/flow map in a separate attachment. 2.10. Core Loading Diagram Figures 1 and 2 provide the core loading diagram for the current and previous cycle respectively, which are the Reference Loading Pattern as defined by NEDE-24011-P-A Table 1 provides a description of the core. 2.11. Figure References Figure 3 is Figure 4.1 from NEDC-3260l-P-A Figure 4 is Figure ID.S-l from A. Figure 5 is Figure ID.S-2 from NEDC-32601P-A. 2.12. Additional SLMCPRLicensing Conditions For Vermont Yankee Cycle 28, the additional SLMCPR licensing condition (Reference

10) that the SLMCPR shaU be established iby adding 0.02 to the cycle-specific TLO SLMCPR value Discussion , \ Page 7 of 23 GNF NON-PROPRIETARY IN FORMATION Class T G-NF Attachment calculated using the NRC-approved methodolofies docume nted in NEDE-240 11-P-A has been applied, (see Table 3). This adder does not apply to the, cyle- specific SLO SLMCPR, because such, peration would by Technical Specification be limited to less than the 1593 MNWt power, threshold specified in Reference 10.2.13. Summary The requested changes to the Technical Specification SL-MCPR values are 1.09 for TLO and 1.10 for SLO for Vermont Yankee Cycle 28.Discussion Page 8 of 23 GNFNOWr:'PROPmE1fARll'mIFORMAlITON .

GNlF Atrnadlmem1t calealatedi uSIng the. NRC-applTOved doeamented in NEDE-24011-P-A has beetil! applied (see TaMe J). This adder does: not: appUy tEl> the: c:yde,..speciifi.c SLO SLMCPR,. because; s1![ch operation. would by Technical \be Diimilted t<!l' less than. the t 593 MWt llowelr tmreslit<!lld specifi.ed in Reference ]Oi. 2.,13 .. Summary The requested changes to the Technical Specification SLMCPR values are 1.09 for TLO and 1.10 for SLO for Vermont Yankee Cyde 28. Discussion Page 8 of23 GNF NON-PROPRIETARY INFORMATION' Class, [GNF Attachment-3.0 References 1 Letter, Glen A. Watford (GNF-A) to ýU.S_ Nuclear Regulatory Commission Document Control Desk with attention to R. Pulsifer (.NRC), "Confirmation of 10x 10 Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies", FLN-2001-016, September 24, 2001-2. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), "Confirmation of the Applicability of the GEXL 14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Fuel", FLN-2001-017, October 1, 2001.3. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to Joseph E. Donoghue (NRC), "Final Presentation Material for GEXL Presentation -February 11, 2002", FLN-2002-004, February 12, 2002.4. Letter, John F. Schardt (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to Mel B. Fields (NRC), "Shadow Corrosion Effects on SLMCPR Channel Bow Uncertainty", FLN-2004-030, November 10, 2004.5. Letter, Jason S. Post (GENE) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to Chief, Information Management Branch, et al. (NRC), "Part 21 Final Report: Non-Conservative SLMCPR", MFN 04-108, September 29, 2004.6. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to Alan Wang (NRC), "NRC Technology Update -Proprietary Slides- July 31 -August 1, 2002", FLN-2002-015, October.31, 2002.7. Letter, Jens G. Munthe Andersen (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to Alan Wang (NRC), "GEXL Correlation for IOXI0 Fuel", FLN-2003-005, May 31, 2003.8. Letter, Andrew A. Lingenfelter (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with cc to MC Honcharik (NRC), "Removal of Penalty Being Applied to GE14 Critical Power Correlation for Outlet Peaked Axial Power Shapes", FLN-2007-03 1, September 18,2007.9. Letter, Andrew A. Lingenfelter (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with cc to MC Honcharik (NRC), "GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR I1), NEDC-33270P, Revision 2, June 2009 and GEXL Correlation for GNF2 Fuel, NEDC-33292P, Revision 3, June 2009", MFN 09-436, June 30, 2009.10. Letter, Richard B. Ennis (NRC) to Michael Kansler (Entergy Nuclear Operations, Inc.),"Vermont Yankee Nuclear Power Station -Issuance of Amendment Re: Extended Power Uprate (TAC No. MC0761)"m March 2, 2006.References RPage 9 of 23 3'.,0 References INiFORMAlITONi CFas$ [ G'NlF Attaellrn:ent 1.. Letter, Glen A. Watford (GNP-A) to U. S. Nudeali Regulatory Commission Document Control Desk with attention to R. Pu]siJfetr (NlRC)" '"Continnati on of lOx lO Fuel Design Applicability to Improved SLMCPR" Power Distribution and. R-Factor Methodologies, FLN-2001-016, September 24, 200L , 2. Letter, Glen A. Watford (GNP-A) to US. Nuclear Regulatory Commission Document Control Desk with attention toJ. Donoghue (NRC), "Confirmation of the Applicability of the GEXL 14 Correlation and Associated R-F actor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Fuel", FLN-2001-017, October 1,2001. 3. Letter, Glen A. Watford (GNP-A) to US. Nuclear Regulatory Commission Document Control Desk with attention to Joseph E. Donoghue (NRC), "Final Presentation Material for GEXL Presentation -February 11,2002", FLN-2002-004, February 12,2002. 4. Letter, John F. Schardt (GNF-A) to U.S. Nuclear Regulatory Commission Document C()ntrol Desk with attention to Mel B. Fields (NRC), "Shadow Corrosion Effects on SLMCPR Channel Bow Uncertainty", FLN-2004-030, November 10; 2004. 5. Letter, Jason S. Post (GENE) to US. Nuclear Regulatory Commission Document Control Desk with attention to Chief, Information Management Branch, et al. (NRC), "Part 21 Final Report: Non-Conservative SLMCPR", MFN 04-108, September 29,2004. 6. Letter, Glen A. Watford (GNF-A) to US. Nuclear Regulatory Commission Document Control Desk with attention to Alan Wang (NRC), "NRC Technology Proprietary Slides-July 31 -August 1,2002", FLN-2002-015, October.31, 2002. 7. Letter, Jens G. Munthe Andersen (GNF-A) to US. Nuclear Regulatory Commission Document Control Desk with attention to Alan Wang (NRC), "GEXL Correlation for lOX 1 0 Fuel", FLN-2003-005, May 31, 2003. 8. Letter, Andrew A. Lingenfelter (GNF-A) to US. Nuclear Regulatory Commission Document Control Desk with cc to MC Honcharik (NRC), "Removal of Penalty Being Applied to GEl4 Critical Power Correlation for Outlet Peaked Axial Power Shapes", FLN-2007-031, September 18,2007. 9. Letter, Andrew A. Lingenfelter (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with cc to MC Honcharik (NRC), "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR n), NEDC-33270P, Revision 2, June 2009 and GEXL Correlation for GNF2 Fuel, NEDC-33292P, Revision June 2009", MFN 09-436, June 30, 2009. 10. Letter, Richard n. Ennis (NRC) to Michael Kansler (Entergy Nuclear "Vennont Yankee Nuclear Power Station -Issuance of Amendment Re: Extended Power Uprate (TAC No .. MC0761)"m March 2, 2006. References GNF NON-PROPRIETARY INFORMATION Class tAttachment ~12 jo 38 E!36 D F1E 32 M 30 M E 2o-@rlq1 28--] RF 0 R 26-- M*L] @1'I]22 -MiH W%20 -R R E ]R 16--RG 12 G 10 EE ti 8 II R nF nL I r D *1 [fF] nF [Gfl n,'M [11)Ffl r Lin, W1 fl wffl E a 6 a 1 0'IR n1flul on ffl Fri] Mil F F8 EC] 8 A I H J-El E K] D KI E, +]Imfl[:D P FE] nK j A H 0 G ni L'J+I M EA n@Dj J nH EM ] nK nJ rffl E- PIE-1 M M ED Ifl F, ýj 4rL- H HýM Meýj F rB] r8l, I rM] in Bi =8-1 EF I I H" I nM nM MB MI Y =Jiý[flF [flD L EIEHt WElln El%nMI L F, nF N-N El El n M.Kq M h jEl M J K ro L J EL Ej nJ nK rEl nK 0 nH M on =11 i B F=MIL On EF:- j IEI nFFýSj [EF] [ 0 0 R 1fl FEI K p G F 0 na no nG--1 r 71 ns 8 P M nB C I'MA il MA :81 Em-ED M 1 8 nmiN ýD Ej T nG 0 nH A K An F-0 Mi =t, 1 KEA 21 EHln M RtHI ED: IE EflK M A Fil 9 RB 06: dol M FG=1'El I Mi RJ [ 11 ] ML RF Yin rEl Mji 8 EG I M=-1 F--P c m EEI[flF 8 1i FG1 IFýr-r]nM [1] FEJ 6-2 I I1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 11 13 FUEL TYPE A = 6NF2-PI00628iO3-IG6.0-10OT2-150-T6-3259 H = 6EIi-PIODNABi21-160Z-IOOT-150-T6-308i 8 = 6NF2-PIOD628Oi-IAGZ-1OOT2-150-T6-3260 I z 6NF2-PI0OG28iO3-1166.O-1OOT2-15O-T6-3261C = GNF2-PIODG28387-!SGZ-10OT2-1SO-T6-2977-LUA J = GNF2-PIOD$2840-1SGZ-IOOT2-1SO-T$-3262 D = 6EIi-PIOONABa22-IiGZ-1001-1SO-T6-2965 K = 6EIi-PIOONA8388-1566.,-IOOT-150-l6-3086 E 0OT-150-16-2865 L = 6EII-PIODNABi20-156Z-IOOT-1S0-T6-3085 F 6E14-PIOODNA38e-ISGZ-IOOT-1S0-"T-2988 M = GE1I-PIOHNA9388-iCGZ-lOOT-ISO-T6-3087 G GEIi-PIONA8388-156Z-IOOT-150-Ts-2959 Figure 1. Current Cycle Core Loading Diagram References Page 10 of 23 GNP CFassE GNP' AtJtaenm:ent 000000 [IJ 1 3 5 1 9 11 13 15 17 19 21 23 2S 27 29 31 33 3S 31 39 'II '\3 FUEl TYPE A = 6NF2-PI00628'103-1'l66.0-100T2-1S0-T6-32S9 B = GNF2-PIOOG2B'lO'l-I'lGZ-IOOT2-1S0-fS-3260 C = GNF2-PIODG28387-1SGZ-I00T2-1S0-T6-2977-LUA D = 6El'l-PlOONAB'l22-i'lGZ-i001-!50-T6-296S E = GEI4-PIOONA8383-116S.0-!OOT-lSO-T6-2865 F = G£14-PIODNAB388-15GI-I00T-ISO-T6-29S8 G = 6El'l-PIOONAB389-156l-!OOT-150-T6-2969 H : 6EI'l-PIODNAB'l21-16GZ-IOOT-ISO-T6-308'l I = 6NF2-PIOOG2B'103-1166.0-IOOT2-1S0-T6-3261 J = GNF2-PtOD62B404-i9GI-IOOT2-150-TS-3262 K : 6El'l-PlOONAB388-1566.0-100T-lSO-TS-308S l = H = Figure i.Current Cycle Core Loading Diagram References Pa,ge 10 of23 GNF NON-PROPRIETARYW IFORMAION! Class, tAttachment, 44 42 40 38 36 34 32 30 28 26 24 22 20 18 16 14 12 10 8 6 4 2 19 ll I Ej,-Un E LREI B E 12HJIIIEI (DBI (E]L E 011 IEI[EDI [HH]19 El[EL] [EK] ES I'E E Mj- PID J H FGJ o El [E] AL-j B E (DI nN Eill IEI Ip ILE21 P[D[Ell D 00SF2GI Lhj p r7, H N EA ] EO [DA+El 01Lj F2 ] ýEEl El ID LTH PGJ [DO [AE][ME] [ME] L;j F21 (E] [9 LEM G 0 A 0 A LI eJG [ 09 ILUDIE1019 110 A 0][BE] [EE] [AE] F20 ] "G LULWEEIL, 2JIL--J Eýjl E I [H] [H] [7]ID FLI[EK]I[GE] M G [EN]II----JIID[JDTEEH ] El FEI E] IE][E] [2DE]I[GE] [FEE]II[EE] FLIE] IflI[B][LD!` [BE]'I El END,, EfEl Ej Tj lnýED[AD'[FEC2 [EH] (EA] ý H [HBj B K L BF0, E-ITI-9 t N M -F[D Leim IND U0 F1 L F I : , L EA FG JEH ] [,Dt PA EDEGDEGIEDII I EDE(] Sm j "j ýL io Fq, Ot EITD EMS TAO, FA[AE]F20] [AE] F202J]I[oH [EN]II[E] E [H]El LI Q 101LB Lý rE ElpoEl F211D !10 101E] [9[AD FWI [HE] H G A EO] F20 EMýjIUjLhjF1EIF21E1 El IEI [EIIE[9 Li Lj WiM [q 7[D M A G e[o I A E [E]eal [HE] 7FL Lý+JýLj [ H ]I [HE] [0E]j[AE] [OE] [GD [MH]j[H] [ED r-B-1 El[5 M C C F+/-m]l [E] (7D 7[D F2-] r[g 0=[E-][EZG;] [AE] [ME] m A G [EE] 0 (GqLie B El M EI] A E 21 EIIE Li M i NED ID ME ea 1 0 0 [Ep HH G A I An H [D F20] [EE] [!OEI [OE] [ED [OD [GE] [OD [ADEI] EE ] [BE] [CE]LeIn ME IWO po F20 ] PIGF071 [OD [GE] F20] [AD [E] [DI[o [G Lek] I M-T -0 N I M M [ID N [EE][HUI ED MIE9 1119 UID EILL)[E] [all- 19 El H A H H K SH II(E] [E]II[KE] [flEILEH[DIEL] [[E]IRB]1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 Fuel Type A=GE14-FPIODNAB422-16G7-IOOT-150-T6-2862 (Cycle 2.) l=G' 14-P IODNAB42 1-l6GZ-!00T-1 50-T6-3084 (Cycle 27)B=GE 14-PI ODNAB3S3-14G6.0-IOOT-150-T6-2864 (Cycle 25) J=GE14-PIODNAB3g3-14G6.0-IOOT-lSO-T6-2864 (Cycle 25)C=OGI'4-PIOZ)NAB383-13G6.0-tOOT-150-T6-2863 (Cycle 25) K=GEI14-PIODNA13383-13G6.0-100T-150-T6-2863 (Cycle 25)Dt=NI.F2-PiODG2B387-15G%-OOT2-t 50-T6-2977-LUA (Cycle I..==E t4-Plt0DNA13383-17G6.0-100T1-t50-T6-2865 (Cycle 25)26) M=GE 14-P I ODNAB388- ! 5G6.0-lO00T-150-1'6-3086 (cycle 27)E=GEI4-PiOt)NAB422-14GZ-100T-Il50-T6-2965 (Cycle 26) N=GE14-PIODNAB420-16GZ,100.lT-150-46-3085 (Cycle 27)F=GE 14-PIOI)NA13383-1706.O-i0OT-t 50-T6-2865 (Cycle 25) O=GE 14-1 ! 0D)NAB388-i6GZ- 100T-I 50-T6-3087 (Cycle 27)G=GE 14-P IODNAB388-MSGZ-I OOT-150-T6-2968 (Cycle 26)li=GE 4-Pl O0DNAB388-15GZI D100T-I 50-T6-2969 (Cycle 26)Figure 2. Previous Cycle Core Loading Diagram Figure 2. Previous Cycle Core Loading Diagram Page I I of 23 44 42 40 38 36 34 32 30 28 26 24 22 20 18 16 14 12 10 8 6 4 2 GNF llNiFORMAlfION CEass I GNlF A1!fadlm:ent 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 Fuel Type AcGEI4*P IODNAB422* I 6G7 ... I 001'-1 SG-T6*2862 (Cycle 25,) (Cycle 27) B=GEI4-PIODNAB383-14G6.G-IOO1'-ISO-1'6-2864 (Cyclc2S) J=GE 14*P I ODNAB383-14G6.0-100T -ISO-1'6-2&64 C=GBI4-PIOI)NAB383-13G6.o-IOO1'-150-T6-2863 (Cycle 25) (Cycle 25) ():.GNF2-PIODG2B387-15GZ-100T2-1 SO-T6-2977-I.UA (Cyclc L-GE 14-1'1 OONAB383-17Q6.O-JOOT-1 50-1'6-2865 (Cyclc 25) 26) M=GE 14-1' I ODNAB388-15G6.0-1 00,.-150*,.6*3086 (Cyclc27) E=GEI4-P1ODNAB422-14G7 .... 100T-150-1'6-2965 (Cycle 26) N=GE14*PI0I)NAB420*16GZ-IOOT-ISO-T6-3085 (Cyclc 27) FcGE 14*PIOI)NA13383-17G6,o-IOOT-ISO-T6-2865 (Cycle 25) O=GEI4-PIODNAB388-16GZ-1OOT*.50-T6-3087 (Cycle 27) G=GEI4-PIODNAB388-15GZ-1OO1'-ISO-1'6-2968 (Cycle 26) li==GE 14*1'1 O])NAB388-1 507 ... 1 001--150-1'6*2969 (Cycle 26) Figure2. Previous Cycle Core Loading Diagram Figure 2.1Previolls 'Cyde Oore Loading Diagram 111 of 23 GNF NON-PROPRIETARY INFORMATION, Class, I GNF, Attachment lIE 13 1 1]Figure 3. Figure 4.1 from NEDC-32601-P-A Figure 3. Figure 4-1 from NEDC-32601-P-A.Page 12 of 23., JlNiFCDR:lVfiA1ITCDN E GNF A1it!aenmeRt: Figure 3. Figure 4.1 from NEDC-32601-P-A Figure 3. Figure 4_1 from NEDC-32601-P-A Page 12 of 23 GNF NON-PROPRIETARY Class [GNF Attachment [Ii 13)]]Figure 4. Figure 111.5-1 from NEDC-32601P-A Figure 4. Figure 1115-1 from NEDC-32601P-A P4ge 13 of 23 GNFNON:"PROPRffilfPffi:Y llNlFORMAlITON! Ctass'[ GNlF AttacImtent Figure 4. Figure IlI.S-l from NEDC-32601P-A Figure 4. Figure RL5-1 from NBDC-32601P-A Page 13 of23 GNF NON'-PROPRIETARY NFORNATIONI Class L GNF' Attachment t3)]]Figure 5. Figure 111.5-2 from NEDC-32601P-A Figure 5. Figure M1.5-2 from NEDC-32601P-A Page 14 of 23 nn nNJFORMAlITONf CFass I GNP' At!t!ad!tmetLt. Figure 5. Figure 111.5-2 from NEDC-32601P-A Figure 5. Figure m.S-2 mom NBDC-32601P-A Page 14 of23 GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 1. Description of Core Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case Number of Bundles in the 368 368 Core 368 368 Limiting Cycle Exposure Point (ie, N/A EOC N/A EOC B O C /M O C /E O C ) ....... .......................... Cycle Exposure at Limiting Point N/A 10600 N/A '10600 (MWd/STU)% Rated Core Flow N/A 100 N/A 100 Reload Fuel Type GE14 GNF2 Latest Reload Batch 32.6 31.5 Fraction, %Latest Reload Average Batch Weight % 4.01 4.04 Enrichment Core Fuel Fraction: GEl4 0.989 0.674 GNF2 0.011 0.326 Core Average Weight % 3.99 4.01 Enrichment Table 1. Description of Core Page 15 of 23. GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 1. Description of Core Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case Number of Bundles in the 368 368 Core Limiting Cycle Exposure Point (Le. N/A EOC N/A , EOC BOC/MOCIEOC) ." Cycle Exposure at Limiting Point N/A 10600 N/A l0600 (MWdlSTU) d_", .* ,,_,,_ " -,,-. -... .. % Rated Core Flow N/A 100 N/A' 100 .. " .. --. -.. --,-._,.--Reload Fuel Type GE14 GNF2 ---,,-----_ .. _---------------. .. Latest Reload Batch 32.6 31,5 Fraction, % . -. .. Latest Reload Average Batch Weight % 4.01 4.04 Enrichment ,,---Core Fuel Fraction: GE14 0.989 0.674 GNF2 0.011 0.326 Core Average Weight % 3.99 4.01 Enrichment Table 1. Description of Core GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 2. SLMCPR Calculation Methodologies Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case Non-power Distribution NEDC-32601-P-A NEDC-32601-P-A Uncertainty__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _U e. ai y ........ .....Power Distribution NEDC-32601-P-A NEDC-32601-P-A Methodology NEDC...2601.-P.A Power Distribution NEDC-32694-P-A NEDC-32694-P-A Uncertainty ......__ED _-32694-P-ANEDC-32694-__A Core Monitoring System 3D Monicore 3D Monicore Table 2. SLMCPR Calculation Methodologies page 16 of 23 Description Non-power Distribution UncertaiI!ty Power Distribution Methodology Power Distribution Uncertainty Core Monitoring System GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 2. SLMCPR Calculation Methodologies .. -Previous Cycle Previous Cycle Rated Current Cycle Cycle Rated Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case NEDC-32601-P-A NEDC-32601-P-A NEDC-32601-P-A NEDC-32601-P-A .. -_ .... -.... -----NEDC-32694-P-A NEDC-32694-P-A " "-'",,-,. ,-_.""",,-

. __ . 3D Monicore 3D Monicore ---.---Table 2. SLMCPR Calculation Methodologies Page 10 GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case[I __________________

__________________[___________________ __________________ I + I t___________________ I .1. __________________ 1 __________________ 1 Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Vaýe 17 of 23 Description "" -[[ GNF NON-PROPRIETARY INFORMA nON Class I GNF Attachment Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Minimum Core Flow Core Flow Limiting Minimum Core Flow Limiting Case Case Limiting Case \ Table 3. Monte Carlo Calculated SLMCPR VS. Estimate Current Cycle Rated Core Flow Limiting Case GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case I 4. J"Il Table 3. Monte Carlo Calculated SLMCPR vs. Estimate P.Valge, 1$ of,23 Description GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Minimum Core Flow Core Flow Limiting Minimum Core Flow Limiting Case Case Limiting Case Table 3. Monte Carlo Calculated SLMCPR VS. Estimate .. " " .. ... -_. _._ .... " .. .. Current Cycle Rated Core Flow Limiting Case ...... ,."._----._-_ .... -............... _._. --(J}ll GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 4. Non-Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle 1 Current Cycle Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow++/- (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB Feedwater Flow F eedw t 1.76 N/A N/A N/A N/A Measurement__________ __________ __________ _____ _____ Feedwater Temperature 0.76 N/A N/A N/A N/A Measurement Reactor Pressure Mea sure 0.50 N/A N/A N/A N/A Measurement Core Inlet Temperature 0.20 N/A N/A N/A N/A Measurement Total Core Flow 6.0 SLO / 2.5 TLO N/A N/A N/A N/A Measurement Channel Flow Area 3.0 N/A N/A N/A N/A Variation Friction Factor 10.0 N/A N/A N/A N/A Multiplier Channel Friction 5.0 N/A N/A N/A N/A Factor Multiplier 5.0.N/.N/A./A.N/ Table 4. Non-Power Distribution Uncertainties Page, 19 of 23 GNF NON-PROPRIETARY INFORMA nON Class I GNF Attachment Table 4. Non-Power Distribution Uncertainties Nominal (NRC-Previous Cycle Previous Cycle Current Cycle Approved) Value Minimum Core Rated Core Flow Minimum Core +/- cr (0/0) Flow Limiting Case Limiting Case Flow Limiting Case GETAB Feedwater Flow 1.76 N/A N/A N/A Measurement Peedwater Temperature 0.76 N/A N/A N/A Measurement Reactor Pressure 0.50 N/A N/A N/A Measurement Core Inlet Temperature 0.20 N/A N/A N/A Measurement Total Core Flow 6.0 SLO I 2.5 TLO N/A N/A N/A Measurement Channel Flow Area 3.0 N/A N/A N/A Variation -Friction Factor 10.0 N/A N/A N/A Multiplier Channel Friction 5.0 N/A N/A N/A Factor Multiplier Table 4. Non-Power Distribution Uncertainties Current Cycle Rated Core Flow Limiting Case N/A N/A N/A , N/A -,., -""""--w __ '" __ " ___ -N/A N/A ... -N/A -N/A Page 19 of23 GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 4. Non-Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle Current Cycle Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow a a (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case NEDC-32601-P-A Feedwater Flow {3 3 j [[ [[ )Measurement Feedwater Temperature [[ {3}]] [[ {3)]] [[ {3,]] 13) 131Measurement Reactor Pressure ]3}]] [[1]Measurement [[_[_____[[_3}]__} _ [__ _ _Core Inlet Temperature 0.2 N/A 0.2 N/A 0 2 M e a s u r e m e n t _ _ _ _ ........ ... .. .. . ..... .........Total Core Flow 6.0 SLO / 2.5 TLO N/A 6.0 SLO / 2:5 TLO N/A 6.0 SLO /2:5 TLO Measurement Channel Flow Area 3E]] 1311] 131]] 0[ ]Variation [[___3__[[ _3_ ]] [[_ _ _ }]] _[__ __ _ _]]Friction Factor 3,]] 13[] 01M ultiplier ---------- ---- Channel Friction 5.0 N/A 5.0 N/A Factor Multiplier Table 4. Non-Power Distribution Uncertainties Page, 20 of 23 GNF NON-PROPRIETARY INFORMA nON Class I GNF Attachment Table 4. Non-Power Distribution Uncertainties Nominal (NRC-Previous Cycle Previous Cycle Current Cycle Approved) Value Minim urn Core Rated Core Flow . Minimum Core +/- CJ (%) Flow Limiting Case Limiting Case Flow Limiting Case NEDC-32601-P-A Feedwater Flow [[ {3}]] [[ {3 I]] [[ {3}]] [[ {3 1]] Measurement Feedwater Temperature [[ {3}]] [[ {31]] [[ {3}]] [[ {J}]] Measurement Reactor Pressure [[ {3}]] [[ {31]] [[ {3}]] PI Measurement Core Inlet Temperature 0.2 N/A 0.2 N/A Measurement Total Core Flow 6.0 SLO/2.5 TLO N/A 6.0 SLO 12:5 TLO N/A Measurement Channel Flow Area [[ {3}]] [[ {31]] [[ {3}]] [[ {3}n Variation Friction Factor [[ {3}]] [[ {3}]] [[ {3}]] [[ {3 1]] Multiplier Channel Friction 5.0 N/A 5.0 N/A Factor Multiplier Table 4. Non-Power Distribution Uncertainties .. --.... -.. _ .. Currel.lt Cyde Ra,ted Core Flow Limiting Ca,se ([ P}J] [[ {3}]] [[ {3}]1 -"'_'-.". " -0.2 > -_._.,. - ,-, 6.Q 5LO 12,5 TLO --[[ {3}]] --([ {3}JJ 5,0 ... *** _ __ m **** _ GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 5. Power Distribution UncertaintiesNominal (NRC-Previous Cycle Previous Cycle Current Cycle Current Cycle,Description Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow+ a (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB/NEDC-32601-P-A GEXL R-Factor [[ {3}]] N/A N/A N/A N/A Random Effective 2,85 SLO/1.2 TLO N/A N/A N/A N/A TIP Reading _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _________ Systematic Effective 8.6 N/A N/A N/A N/ATIP Reading NEDC-32694-P-A, 3DMONICORE GEXL R-Factor (3) 1[{}][ {}][ 3)]j [ 1,]Random Effective 2.85 SLO/1.2 TLO N/A 2.85 SLO/1.2 TLO N/A 2,85 SLO/l 2 TLOTIP Reading TIP Integral [[ 131] 133 [[ j3}]] [[ jI] [[ i-]Four Bundle Power Distribution Surrounding TIP [[ 3 [[ {3)]] [r 13}]] E[ 131]] 13)Location Contribution to Bundle Power Uncertainty Due to LPkM Update ........Table 5. Power Distribution Uncertainties page 21 of 23 GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 5. Power Distribution Uncertainties Nominal (NRC-Previous Cycle Previous Cycle Current Cycle Description Approved) Value Minim urn Core Rated Core Flow Minimum Core tG(%) Flow Limiting Case Limiting Case Flow Limiting Case GETABINEDC-32601-P-A GEXL R-Factor [[ {3}]] N/A N/A N/A Random Effective 2.85 SLO/1.2 TLO N/A N/A N/A TIP Reading Systematic Effective 8.6 N/A N/A N/A TIP Reading 3DMONICORE GEXL R-F actor [[ {3}]] [[ {3}]] [[ {3}]] [[ {3}J] Random Effective 2.85 SLO/1.2 TLO N/A 2.85 SLO/l.2 TLO N/A TIP Reading TIP Integral [[ {3}]] [[ {3 1]] [[ {3 1]] [[ {31]] Four Bundle Power Distribution [[ (3}]) [[ {3}]] [[ {3 I]] [[ {3}J] Surrounding TIP Location Contribution to Bundle Power [[ {Jl]] [[ {3 1]] [[ {31 n [[ {3}]] Uncertainty Due to LPRMUpdate Table 5. Power Distribution Uncertainties .. Current Rated Core mow Limiting Case N/A N/A N/A "-.,,. -" ... "._ ... "."."-----,,---,, " .----.. [[ {3}JJ . -2.85 SLO/L2 1'1,0 , ----.. -. -, [[ .. -[[ m]J [[ {31]] "._-,,---Page 21 of2J GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 5. Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle Current Cycle Description Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow a a (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case Contribution toBundle Power Due to [[ 1 [[ {3}] [[ 0]1 Er ,]]] [[ Failed TIP Contribution to Bundle Power Due to [" TiI Er 3 01 Er 03 Er 1]Failed LPRM Total Uncertainty in Calculated Bundle [[ {3} Er ]3}] Er {]i [[ {31]] 131Power Uncertainty of TIP Signal Nodal [[ 03}1] Er {31]i [[ {3}] E[ (31] E[ 1]]Uncertainty Table 5. Power Distribution UncertaintiesPage, 22 of 23 GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 5. Power Distribution Uncertainties Nominal (NRC-Previous Cycle Previous Cycle Current Cycle Description Approved) Value Minimum Core Rated Core Flow Minimum Core +/- (J (%) Flow Limiting Case Limiting Case Flow Limiting Case Contribution to Bundle Power Due to [[ {3 1]] [[ {31]] [[ {3 1]] [[ {31]] failed TIP -Contribution to Bundle Power Due to [[ {3}]] PI [[ {3}]] [[ {3}]) Failed LPRM Total Uncertainty in -Calculated Bundle [[ {3 1]] [[ {3 1]] [[ {3 1]] [[ {3}]] Power Uncertainty of TIP Signal Nodal [[ {3}]] [[ {3 I]] [[ {3}]] [[ m]J Uncertainty d.N. _. -Ta15le 5. Power Distribution Uncertainties

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_.-----" Current Cyde Core FIQw Limiting " ._ .. " ... _ ... " '" m """"n "m_ , [[ (3})] [[ {3 1]] [[ {3 t]] - -[[ 1 3 lJ] GNF NON-PROPRIETARY INFORMATION Class I GNF Attachment Table 6. Critical Power Uncertainties Previous Cycle Previous Cycle Current Cycle Current Cycle Nominal Value Description a Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow Flow Limiting Case Limiting Case Flow Limiting Case Limiting-Case [[J Table 6. Critical Power Uncertainties Page 23 of 23 Nominal Value Description +/- (J (%) [[ Table 6. Critical Power Uncertainties GNP NON-PROPRIETARY INPORMA TION Class I GNP Attachment Table 6. Critical Power Uncertainties Previous Cycle Previous Cycle Minimum Core Rated Core Flow Flow Limiting Case Limiting Case . -.... .. --- Current Cycle Current Cyde Minimum Core Rated Core FI()w Flow Limiting Case LimitingXase --" '-.--.-.. Page 23 of23}}

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