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#REDIRECT [[NL-15-1535, GNF-002N9964-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Hatch 1 Cycle 28]]
| number = ML15252A187
| issue date = 08/31/2015
| title = GNF-002N9964-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Hatch 1 Cycle 28
| author name =
| author affiliation = Global Nuclear Fuel - Americas, LLC, Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000321
| license number =
| contact person =
| case reference number = NL-15-1535
| document report number = GNF-002N9964, Rev. 1
| package number = ML15252A185
| document type = Response to Request for Additional Information (RAI), Technical Specifications
| page count = 14
}}
 
=Text=
{{#Wiki_filter:Edwin I. Hatch Nuclear Plant -Unit 1License Amendment Request Concerning Safety LimitMinimum Critical Power RatioEnclosure 2Non-Proprietary GNF Report GNF-002N9964-R1  
-NP August 2015GNF-002N99 64-Ri1-NP PLM Specification 002N9964 RiNon-Proprietary Information
-Class I (Public)GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPRHatch 1 Cycle 28Copyright 2015 Global Nuclear Fuel -Americas, LLCAll Rights Reserved GNF-002N9964-R1
-NPNon-Proprietary Information
-Class I (Public)Information NoticeThis is a non-proprietary version of the document GNF-002N9964-R1-P, which has theproprietary information removed.
Portions of the document that have been removed areindicated by an open and closed bracket as shown here [[].Important Notice Regarding Contents of this ReportPlease Read Carefully The design, engineering, and other information contained in this document is furnished for thepurpose of providing information regarding the requested changes to the Technical Specification SLMCPR for Southern Nuclear Operating Company Hatch 1. The only undertakings of GNF-Awith respect to information in this document are contained in the contract between GNF-A andSouthern Nuclear Operating
: Company, and nothing contained in this document shall beconstrued as changing that contract.
The use of this information by anyone other than SouthernNuclear Operating
: Company, or for any purposes other than those for which it is intended is notauthorized; and with respect to any unauthorized use, GNF-A makes no representation orwarranty, and assumes no liability as to the completeness,
: accuracy, or usefulness of theinformation contained in this document.
Information Notice Pg f1Page 2 of 13 GNF-002N9964-R1
-NPNon-Proprietary Information
-Class I (Public)Table of Contents1.0 Summary ...........................................................................................
42.0 Regulatory Basis .................................................................................
43.0 Methodology.....................................................................................s 3.1. Methodology Restrictions............
...................................................
54.0 Discussion........................................................................................
64.1. Major Contributors to SLMCPR Change..............................................
64.2. Deviations from Standard Uncertainties
...............................................
74.2.1. R-Factor..........................................................................
74.2.2. Core Flow Rate and Random Effective TIP Reading ........................
74.2.3. Flow Area Uncertainty..........................................................
84.2.4. Fuel Axial Power Shape Penalty ...............................................
85.0 References
.......................................................................................
9List of TablesTable 1. Monte Carlo SLMCPR.......................................................................
11Table 2. Description of Core...........................................................................
12Table 3. Deviations from Standard Uncertainties
....................................................
13Table of ContentsPae3ol Page 3 of 13 GNF-002N9964-R1
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-Class I (Public)1.0 SummaryThe requested changes to the Technical Specification (TS) Safety Limit Minimum Critical PowerRatio (SLMCPR) values are 1.09 for Two-Loop Operation (TLO) and 1.12 for Single LoopOperation (SLO) for Hatch 1 Cycle 28. Additional details are provided in Table 1.One of the primary reasons for the change is that Cycle 28 will be the first full reload of GNF2for Hatch 1. The critical power uncertainty for GNF2 is higher than the previous cycle's fueltype. As a result of the introduction of GNF2 fuel, the SLMCPR values have increased.
Anotherreason for the change is that in the limiting case the core bundle-by-bundle Minimum CriticalPower Ratio (MCPR) distribution is significantly flatter than the limiting case in the previouscycle. This difference caused the SLMCPR values to increase.
2.0 Regulatory Basis10 Code of Federal Regulations (CFR) 50.36(c)(1),
"Technical Specifications,"
requires thatpower reactor facility TS include safety limits for process variables that protect the integrity ofcertain physical barriers that guard against the uncontrolled release of radioactivity.
The fuelcladding is one of the physical barriers that separate the radioactive materials from theenvironment.
The purpose of the SLMCPR is to ensure that Specified Acceptable Fuel DesignLimits (SAFDLs) are not exceeded during steady state operation and analyzed transients.
General Design Criterion (GDC) 10, "Reactor Design,"
of Appendix A to 10 CFR 50 states thatthe reactor core and associated
: coolant, control, and protection systems shall be designed withappropriate margin to assure that SAFDLs are not exceeded.
Guidance on the acceptability of the reactivity control systems, the reactor core, and fuel systemdesign is provided in NUREG-0800, "Standard Review Plan [SRP] for the Review of SafetyAnalysis Reports for Nuclear Power Plants."
Specifically, SRP Section 4.2, "Fuel SystemDesign,"
specifies all fuel damage criteria for evaluation of whether fuel designs meet theSAFDLs. SRP Section 4.4, "Thermal Hydraulic Design,"
provides guidance on the review ofthermal-hydraulic design in meeting the requirement of GDC 10 and the fuel design criteriaestablished in SRP Section 4.2.The Hatch 1 construction permit was received under the 70 general design criteria discussed in"General Design Criteria for Nuclear Power Plant Construction,"
issued for comment inJuly 1967 and was not, therefore, developed in consideration of the 64 new general designcriteria discussed in the "General Design Criteria for Nuclear Power Plants,"
effective May 21, 1971, and subsequently amended July 7, 1971. However, Criterion 6 of the designcriteria on which the Hatch 1 construction permit was based is analogous to the current GDC 10.SummarySummaryPage 4 of 13 GNF-002N9964-R1
-NPNon-Proprietary Information
-Class I (Public)3.0 Methodology GNF performs Safety Limit Minimum Critical Power Ratio SLMCPR calculation in accordance with NEDE-2401 1-P-A "General Electric Standard Application for Reactor Fuel, (GESTAR II)"(Reference
: 1) for plants such as Hatch 1 that are equipped with the GNF 3DMonicore coremonitoring system, by using the following Nuclear Regulatory Commission (NRC)-approved methodologies and uncertainties:
* NEDC-32601P-A, "Methodology and Uncertainties for Safety Limit MCPREvaluations,"
August 1999. (Reference 2)* NEDC-32694P-A, "Power Distribution Uncertainties for Safety Limit MCPREvaluations,"
August 1999. (Reference 3)* NEDC-32505P-A, "R-Factor Calculation Method for GEl 1, GEl2 and GEl3 Fuel,"Revision 1, July 1999. (Reference 4)These methodologies were used for the Hatch 1 Cycle 27 and Cycle 28 SLMCPR calculations.
3.1. Methodology Restrictions Four restrictions were identified on page 3 of the NRC's Safety Evaluation (SE) relating to theGeneral Electric (GE) Licensing Topical Reports (LTRs) NEDC-32601P, NEDC-32694P, andAmendment 25 to NEDE-2401 1-P-A (Reference 5).The four restrictions were addressed for GEl4 in FLN-2001-16 "Confirmation of 10xl0 FuelDesign Applicability to Improved SLMCPR" (Reference
: 6) and FLN-2001-17 "PowerDistribution and R-Factor Methodologies" (Reference 7).The following statement was extracted from the generic compliance report for the GNF2 fuelassembly design (Reference
: 8) that GNF sent to the NRC in March of 2007:"The NRC Safety Evaluation (SE) for NEDC-32694P-A provides four actions tofollow whenever a new fuel design is introduced.
These four conditions are listedin Section 3 of the SE. In the last paragraph of Section 3.2.2 of the Technical Evaluation Report included in the SE are the statements "GE has evaluated thiseffect for the 8x8, 9x9, and 10xl0 lattices and has indicated that the R-Factoruncertainty will be increased
... to account for the correlation of rod poweruncertainties" and "it is noted that the effect of the rod-to-rod correlation has asignificant dependence on the fuel lattice (e.g., 9x9 versus 10xl0). Therefore, inorder to insure the adequacy of the R-Factor uncertainty, the effect of thecorrelation of rod power calculation uncertainties should be reevaluated when theNEDC-32601P methodology is applied to a new fuel lattice."
Therefore, thedefinition of a new fuel design is based on the lattice array dimensions MethodologyPae5o3 Page 5 of 13 GNF-002N9964-R1
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-Class I (Public)(e.g., NxN). Because GNF2 is a 10xl0, and the evaluations in NEDC-32694P-A include 10xlO0, then these four actions are not applicable to GNF2."In an NRC audit report (Reference
: 9) for this document, Section 3.4.1 page 59 states:"The NRC staff's SE of NEDC-32694P-A (Reference 19 of NEDC-33270P) provides four actions to follow whenever a new fuel design is introduced.
Thesefour conditions are listed in Section 3.0 of the SE. The analysis and evaluation ofthe GNF2 fuel design was evaluated in accordance with the limitations andconditions stated in the NRC staff's SE, and is acceptable."
Another methodology restriction is identified on page 4 of NRC's SE relating to the GE LTRNEDC-32505P (Reference 10). Specifically, it states that 'if new fuel is introduced, GENE mustconfirm that the revised R-Factor method is still valid based on new test data.' NEDC-32505P addressed the GE12 10xl0 lattice design (i.e., how the R-Factor for a rod is calculated based uponits immediate surroundings (fuel rods, water rods or channel wall)). Validation is provided by thefact that the methodology generates accurate predictions of Critical Power Ratio (CPR) withreasonable bias and uncertainty.
The applicability of the R-Factor method is coupled anddocumented (along with fuel specific additive constants) with the GEXL correlation development (References 11 and 12), which is submitted as a part of GESTAR II compliance for each new fuelproduct line.4.0 Discussion In this discussion, the TLO nomenclature is used for two recirculation loops in operation, and theSLO nomenclature is used for one recirculation loop in operation.
Table 2 provides the description of the current cycle and previous cycle for the reference loadingpattern as defined by NEDE-2401 1-P-A (Reference 1).4.1. Major Contributors to SLMCPR ChangeIn general, for a given power-flow statepoint, the calculated safety limit is dominated by two keyparameters:
(1) flatness of the core bundle-by-bundle MCPR distribution, and (2) flatness of thebundle pin-by-pin power/R-Factor distribution.
Greater flatness in either parameter yields morerods susceptible to boiling transition and thus a higher calculated SLMCPR. Therefore, thecalculated SLMCPR may change whenever there are changes to the core configuration or to thefresh fuel designs.
The plant-cycle specific SLMCPR methodology accounts for these factors.The uncertainty in the MCPR boiling correlation (GEXL critical power uncertainty) varies fromfuel product line to product line. Because the fresh fuel bundles generally dominate theSLMCPR calculation, a change in product line provides a cause for a potentially significant change in the SLMCPR.Discussion DiscusionPage 6 of 13 GNF-002N9964-R1
-NPNon-Proprietary Information
-Class I (Public)Cycle 28 core bundle-by-bundle MCPR distribution is significantly flatter than Cycle 27. Also,Cycle 28 will be the first reload of GNF2 for Hatch 1. The GNF2 GEXL correlation uncertainty
[[ ]] is larger than that of the GEI4 fuel [[ ]] used in the prior cycle. These twochanges tend to make the final SLMCPR higher.4.2. Deviations from Standard Uncertainties Table 3 provides a list of deviations from NRC-approved uncertainties (References 2 and 3). Adiscussion of deviations from these NRC-approved values follows; all of which are conservative relative to NRC-approved values.4.2.1. R-FactorGNF has generically increased the GEXL R-Factor uncertainty from [[ ]] toaccount for an increase in channel bow due to the phenomena called control blade shadowcorrosion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the approved R-Factor uncertainty.
Reference 13 technically justifies that a GEXLR-Factor uncertainty of [[ 3] accounts for a channel bow uncertainty of up toEr 11. The Hatch I Cycle 28 analysis shows an expected channel bow uncertainty ofEr ]], which is bounded by a GEXL R-Factor uncertainty of [[~ ]]. Thus, the useof a GEXL R-Factor uncertainty of [[ ]] adequately accounts for the expected controlblade shadow corrosion-induced channel bow. The effect of this change is considered notsignificant (i.e., < 0.005 increase on SLMCPR).4.2.2. Core Flow Rate and Random Effective TIP ReadingIn Reference 14 GNF committed to the expansion of the state points used in the determination ofthe SLMCPR. Consistent with the Reference 14 commitments, GNF performs analyses at therated core power and minimum licensed core flow point in addition to analyses at the rated corepower and rated core flow point. The approved SLMCPR methodology is applied at each statepoint that is analyzed.
For the TLO calculations performed at 92.9% core flow, the approved uncertainty values for thecore flow rate (2.5%) and the random effective Traversing In-Core Probe (TIP) reading (1.2%)are conservatively adjusted by dividing them by 92.9/1 00.The core flow and random TIP reading uncertainties used in the SLO minimum core flowSLMCPR analysis remain the same as in the rated core flow SLO SLMCPR analysis becausethese uncertainties (which are substantially larger than used in the TLO analysis) already accountfor the effects of operating at reduced core flow.Discussion DiscusionPage 7 of 13 GNF-002N9964-R1
-NPNon-Proprietary Information
-Class I (Public)4.2.3. Flow Area Uncertainty GNF has calculated the flow area uncertainty for GNF2 and GEl4 using the process described inSection 2.7 of Reference
: 2. It was determined that the flow area uncertainty for GNF2 and GEl4would be conservatively bounded by a value of [[ ]]. Because this is larger than theReference 2 value of [[ ]], the bounding value was used in the SLMCPR calculations.
The effect of this change is considered not significant (i.e., < 0.005 increase on SLMCPR).4.2.4. Fuel Axial Power Shape PenaltyThe GEXL correlation critical power uncertainty and bias are established for each fuel productline according to a process described in NEDE-2401 1-P-A (Reference 1).GNF determined that higher uncertainties and non-conservative biases in the GEXL correlations for certain types of axial power shapes could exist relative to the NRC-approved methodology values (References 15, 16, 17, and 18). The GE14 and GNF2 product lines are potentially affected in this manner only by Double-Hump (D-H) axial power shapes.The D-H axial shape did not occur on any of the limiting bundles (i.e., those contributing to the0.1% rods susceptible to transition boiling) in the current and/or prior cycle limiting cases.Therefore, D-H power shape penalties were not applied to the GEXL critical power uncertainty or bias.Discussion DiscusionPage 8 of 13 GNF-002N9964-R1
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-Class I (Public)5.0 References
: 1. Global Nuclear Fuel, "General Electric Standard Application for Reactor Fuel,"NEDC-2401 1-P-A, Revision 21, May 2015.2. GE Nuclear Energy, "Methodology and Uncertainties for Safety Limit MCPREvaluations,"
NEDC-32601IP-A, August 1999.3. GE Nuclear Energy, "Power Distribution Uncertainties for Safety Limit MCPREvaluations,"
NEDC-32694P-A, August 1999.4. GE Nuclear Energy, "R-Factor Calculation Method for GEl 1, GEl2 and GEl3 Fuel,"NEDC-32505P-A, Revision 1, July 1999.5. Letter, Frank Akstulewicz (NRC) to Glen A. Watford (GNF-A) "Acceptance forReferencing of Licensing Topical Reports NEDC-3260 1 P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties forSafety Limit MCPR Evaluation; and Amendment 25 to NEDE-2401 1-P-A on Cycle-Specific Safety Limit MCPR (TAC Nos. M97490, M99069 and M9749 1)," MFN-003-099, March 11, 1999.6. Letter, Glen A. Watford (GNF-A) to NRC Document Control Desk with attention to R.Pulsifer (NRC), "Confirmation of l0xlO0 Fuel Design Applicability to Improved SLMCPR,Power Distribution and R-Factor Methodologies,"
FLN-2001-016, September 24, 2001.7. Letter, Glen A. Watford (GNF-A) to NRC Document Control Desk with attention toJ. Donoghue (NRC), "Confirmation of the Applicability of the GEXL14 Correlation andAssociated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Fuel," FLN-2001-017, October 1, 2001.8. Letter, Andrew A. Lingenfelter (GNF-A) to NRC Document Control Desk with cc to MCHorncharik (NRC), "GNF2 Advantage Generic Compliance with NEDC-24011lP-A (GESTAR II), NEDC-33270P, March 2007, and GEXL17 Correlation for GNF2 Fuel,NEDC-33292P, March 2007," FLN-2007-1 1, March 14, 2007.9. Memorandum, Michelle C. Horncharik (NRC) to Stacy L. Rosenberg (NRC), "AuditReport for Global Nuclear Fuels GNF2 Advantage Fuel Assembly Design GESTAR IICompliance Audit, September 25, 2008. (ADAMS Accession Number ML08 1630579)10. Letter, Thomas H. Essig (NRC) to Glen A. Watford (GNF-A) "Acceptance for Referencing of Licensing Topical Report NEDC-32505P Revision 1, R-factor Calculation Method forGElI, GEl2 and GEI3 Fuel, (TAC Nos. M99070 and M95081),"
MFN-046-098, January 11, 1999.References ReferncesPage 9 of 13 GNF-002N9964-R1
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-Class I (Public)11. Global Nuclear Fuel, "GEXL14 Correlation for GEl4 Fuel," NEDC-32851P-A, Revision 5, April 2011.12. Global Nuclear Fuel, "GEXL17 Correlation for GNF2 Fuel," NEDC-33292P, Revision 3,April 2009.13. Letter, John F. Schardt (GNF-A) to NRC Document Control Desk with attention to Mel B.Fields (NRC), "Shadow Corrosion Effects on SLMCPR Channel Bow Uncertainty,"
FLN-2004-030, November 10, 2004.14. Letter, Jason S. Post (GENE) to NRC Document Control Desk with attention to Chief,Information Management Branch, et al. (NRC), "Part 21 Final Report: Non-Conservative SLMCPR,"
MEN 04-108, September 29, 2004.15. Letter, Glen A. Watford (GNF-A) to NRC Document Control Desk with attention to JosephE. Donoghue (NRC), "Final Presentation Material for GEXL Presentation
-February 11,2002," FLN-2002-004, February 12, 2002.16. Letter, Glen A. Watford (GNF-A) to NRC Document Control Desk with attention to AlanWang (NRC), "NRC Technology Update -Proprietary Slides -July 31 -August 1, 2002,"FLN-2002-015, October 31, 2002.17. Letter, Jens G. Munthe Andersen (GNF-A) to NRC Document Control Desk with attention to Alan Wang (NRC), "GEXL Correlation for 10X10 Fuel," FLN-2003-005, May 31, 2003.18. Letter, Andrew A. Lingenfelter (GNF-A) to NRC Document Control Desk with cc to MCHoncharik (NRC), "Removal of Penalty Being Applied to GEl4 Critical Power Correlation for Outlet Peaked Axial Power Shapes,"
FLN-2007-03 1, September 18, 2007.References ReferncesPage 10 of 13 GNF-002N9964-R1
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-Class I (Public)Table 1. Monte Carlo SLMCPR** , -- 'Previous Cycle ..... ...'Current Cycle, Limiting Cases , Limiting CasesDecipinRated Power Rated Power Rated Rated Power Rated Power Rated-.Minimum Core Flow *Core *Flow Minimum Core Flow ,Core FlowLimiting Cycle Exposure Point(Beginning of Cycle (BOC)/Middle BOC (TLO) / BOC (TLO) / EOC EOCof Cycle (MOC)/End of Cycle BOC (SLO) EOC (SLO)(EOC)) _ _ _ _ _ _ _ _Cycle Exposure at Limiting Point0/561/5,11,90590 (MWd/STU)0/15610/1,61,10591 1]Requested Change to the TS N/A 1.09 (TLO)/1 1.21 (SLO)SLMCPRNote:1.[[lTITable 2. Description of CorePae1of3 Page 11 of 13 GNF-002N9964-R1
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-Class I (Public)Table 2. Description of CoreDescription Previous Cycle Current CycleCore Rated Power (MWt)284084.
Minimum Flow at Rated Power (% ratedcore flow)9299.
Number of Bundles in the Core 560 560Batch Sizes and Types:(Number of Bundles in the Core)Fresh 224 GE14 228 GNF2Once-Burnt 232 GE14 224 GE14Twice-Burnt 100 GE141  104 GE14Thrice-Burnt or more 4 GE14 4 GE14Fresh Fuel4.0.6 Batch Average Enrichment (Weight %)4.0.6Core Monitoring System 3DMonicore 3DMonicore Note:1.Hatch 1 Cycle 27 contained four Westinghouse Optima2 Lead Use Assemblies (LUAs) which were on their third cycle of operation.
These four LUAs weremodeled as GEl4 fuel.Table 2. Description of CorePae1of3 Page 12 of 13 GNF-002N9964-R 1-NPNon-Proprietary Information
-Class I (Public)Table 3. Deviations from Standard Uncertainties Dsrpin*NCApproved Value I &deg;- ..Decito NR + (%) Previous Cycle Current Cycle~Power Distribution Uncertainties GEXL R-Factor
[[r][ ][ ]]Random Effective TIP ReadingAll TLO Cases at Rated Power and 1.2 1.292 1.292Minimum Flow ________________________
___________
~Non-Power Distribution Uncertainties Channel Flow Area Variation
[[ ]][[ ] [[ ]]Total Core Flow Measurement All TLO Cases at Rated Power and 2.5 2.69 1 2.69 1Minimum FlowTable 3. Deviations from Standard UncertaintiesPae1of3 Page 13 of 13}}

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