ML101480555
| ML101480555 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/27/2010 |
| From: | Cowan P Exelon Corp, Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML101480549 | List: |
| References | |
| Download: ML101480555 (40) | |
Text
{{#Wiki_filter:Exelon Nuclear www.exeloncorp.com ExeIen: 200 Exelon Way Nuclear PA1q48 Kennett Sq ua re, PA 19348 PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 10 CFR 50.90 27, 2010 May 27,2010 U.S. U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Peach Bottom Atomic Power Station, Unit 2 Renewed Facility Operating License No. DPR-44 NRC Docket No. 50-277
Subject:
License Amendment Request - Safety Limit Minimum Critical Power Ratio Change In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (Exelon) requests a proposed change to modify Technical Specification (TS) 2.1.1 ("Reactor SLs). (°Reactor Core SLs"). Specifically, this change incorporates revised Safety Limit Minimum Critical Power Ratios (SLMCPRs) due to the cycle specific analysis performed by Global Nuclear Fuel for Peach Bottom Atomic Power Station (PBAPS), Unit 2, Cycle 19. The proposed changes have been reviewed by the Peach Bottom Atomic Power Station Plant Operations Review Committee, and approved by the Nuclear Safety Review Board in accordance with the requirements of the Exelon Quality Assurance Program. In order to support the upcoming refueling outage at PBAPS, Unit 2, Exelon requests approval of the proposed amendment by September 1, 2010. Once approved, this amendment shall be implemented within 30 days of issuance. Additionally, there are no commitments contained within this letter. 1 contains the evaluation of the proposed changes. Attachments 2 and 3 provide the marked up TS page and the retyped TS page, respectively. (letter from J. M. Downs (Global Nuclear Fuel) to J. Tusar (Exelon Generation Company, LLC), dated May 6, 2010) specifies the new SLMCPRs for PBAPS, Unit 2, Cycle 19. contains information proprietary to Global Nuclear Fuel. Global Nuclear Fuel requests that the document be withheld from public disclosure in accordance with 10 CFR 2.390(b)(4). An affidavit supporting this request is also contained in Attachment 4. Attachment 5 contains a non-proprietary version of the Global Nuclear Fuel document. Attachment 6 contains the power/flow map for Cycles 18 and 19. In accordance with 10 CFR 50.91, Exelon is notifying the State of Pennsylvania of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official. Attachment 4 transmitted herewith contains Proprietary Information. When separated from attachments, this document is decontrolled.
License Amendment Request Safety Limit Minimum Critical Power Ratio Change May 27,2010 27, 2010 Page 2 Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510. th 27 II declare under penalty of perjury that the foregoing is true and correct. Executed on the 2yth of May 2010. Respectfully, 1f f)4/) ~:....L- _ Pamela B. Cowan Director, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) Evaluation of Proposed Changes
- 2) Markup of Technical Specifications Page
- 3) Retyped Technical Specifications Page
- 4) Proprietary Version of Global Nuclear Fuel Letter
- 5) Non-Proprietary Version of Global Nuclear Fuel Letter
- 6) Power/Flow Map for Cycles 18 and 19 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Commonwealth of Pennsylvania S. T.
T, Gray, State of Maryland
Attachment 11 Attachment Peach Bottom Peach Atomic Power Bottom Atomic Power Station, Unit 22 Station, Unit Renewed Facility Renewed Facility Operating No. DPR-44 License No. Operating License DPR-44 Evaluation of Evaluation Proposed Changes of Proposed Changes
ATTACHMENT 11 CONTENTS
SUBJECT:
Safety Limit Minimum Critical Power Ratio (SLMCPR) Change 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedents 4.3 No Significant Hazards Consideration 4.4 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
License Amendment Request Safety Limit Minimum Critical Power Ratio Page 1 1 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to amend Renewed Facility Operating License No. No, DPR-44 for Peach Bottom Atomic Power Station (PBAPS), Unit 2. The proposed change modifies Technical Specification (TS) 2.1.1 ("Reactor(Reactor Core SLs"). SLs). Specifically, this change incorporates revised Safety Limit Minimum Critical Power Ratios (SLMCPRs) due to the cycle specific analysis performed by Global Nuclear Fuel for Peach Bottom Atomic Power Station (PBAPS), Unit 2, Cycle 19. 2.0 DETAILED DESCRIPTION The proposed change involves revising the SLMCPRs contained in TS 2.1.1 for two recirculation loop operation and single recirculation loop operation. The SLMCPR value for two-loop operation is being changed from 2 1.07 to 2 1.10. The SLMCPR value for single-loop operation is being changed from 2 1.09 to 2 1.14. Marked up Technical Specification page 2.0-1 showing the requested changes is provided in .
3.0 TECHNICAL EVALUATION
The proposed TS change will revise the SLMCPRs contained in TS 2.1.1 for two recirculation loop operation and single recirculation loop operation to reflect the changes in the cycle specific analysis performed by Global Nuclear Fuel for PBAPS, Unit 2, Cycle 19. The new SLMCPRs are calculated using NRC-approved methodology described in NEDE- NEDE General Electric Standard Application for Reactor Fuel," 24011-P-A, "General Fuel, Revision 16. A listing of the associated NRC-approved methodologies for calculating the SLMCPRs is provided in (Methodology) of Attachment 4. Section 1.0 ("Methodology") The SLMCPR analysis establishes SLMCPR values that will ensure that during normal operation and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling if the limit is not violated. The SLMCPRs are calculated to include cycle specific parameters and, in general, are 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-power/R factor distribution. Information to support the cycle specific SLMCPRs is included in Attachment
- 4. That attachment summarizes the methodology, inputs, and results for the change in the SLMCPRs. The PBAPS, Unit 2 Cycle 19 core will consist of GE14 and GNF2 fuel types. contains the power/flOW power/flow map for Cycles 18 and 19.
No plant hardware or operational changes are required with this proposed change.
4.0 REGULATORY EVALUATION
4.1 AIicable Applicable Requlatory Regulatory Requirements/Criteria Technical specifications, 10 CFR 50.36, "Technical specifications," paragraph (c)(1), requires that power reactor facility TS include safety limits for process variables that protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The fuel cladding integrity
License Amendment Request Safety Limit Minimum Critical Power Ratio Page 2 SLMCPR is established to assure that at least 99.9% of the fuel rods in the core do not experience boiling transition during normal operation and abnormal operating transients. Thus, the SLMCPR is required to be contained in TS. 4.2 Precedents The NRC has approved similar SLMCPR changes for a number of plants: (US. Nuclear Regulatory Commission) to K. W. Singer
- 1) Letter from M. H. Chernoff (U.S.
Browns Ferry Nuclear Plant, Unit 11 - Issuance of (Tennessee Valley Authority), "Browns - Amendment Regarding Cycle-Specific Safety Limit Minimum Critical Power Ratio (TAC NO. MD1 721) (TS-455), MD1721) 6, 2007 (TS-455)," dated February 6,2007
- 2) Letter from J. Kim (U.S. Nuclear Regulatory Commission) to Site Vice President (Entergy Nuclear Operations, Inc.), Pilgrim "Pilgrim Nuclear Power Station - Issuance of Amendment RE:
Technical Specification Change Concerning Safety Limit Minimum Critical Power Ratio NO, ME0241)," (TAC NO. ME0241 ), dated March 26, 2009
- 3) Letter from J. Wiebe (U.S. Nuclear Regulatory Commission) to C. Pardee (Exelon Generation Company, LLC), "Quad Quad Cities Nuclear Power Station, Units 11 and 2 - Issuance of Amendments RE: Safety Limit Minimum Critical Power Ratio (TAC NOS. MD7374 AND MD7375), dated February 28,2008 MD7375)," 28, 2008
- 4) Letter from C. Lyon (U.S. Nuclear Regulatory Commission) to Vice President, Operations Grand Gulf Nuclear Station, Unit 11 - Issuance of Amendment (Entergy Operations, Inc.), "Grand -
RE: Change to the Minimum Critical Power Ratio Safety Limit (TAC NO. ME2474),"ME2474), dated March 25, 2010 4.3 No Significant S[nificant Hazards Consideration Exelon Generation Company, LLC (Exelon) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set amendment, as discussed below: Issuance of amendment," forth in 10 CFR 50.92, "Issuance
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. The derivation of the cycle specific Safety Limit Minimum Critical Power Ratios (SLMCPRs) for incorporation into the Technical Specifications (TS), and their use to determine cycle specific thermal limits, has been performed using the methodology NEDE-2401 1-P-A, "General discussed in NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel, Revision 16. Fuel," The basis of the SLMCPR calculation is to ensure that during normal operation and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling if the limit is not violated. The new SLMCPRs preserve the
License Amendment Request Safety Limit Minimum Critical Power Ratio Page 3 existing margin to transition boiling. The MCPR safety limit is reevaluated for each reload using NRC-approved methodologies. The analyses for Peach Bottom Atomic Power Station (PBAPS), Unit 2, Cycle 19 have concluded that a two loop MCPR safety limit of ~ 1.10, based on the Fuels NRC-approved MCPR safety limit methodology, will application of Global Nuclear Fuel's ensure that this acceptance criterion is met. For single-loop operation, a MCPR safety limit of ~ 1.14 also ensures that this acceptance criterion is met. The MCPR operating limits are presented and controlled in accordance with the PBAPS, Unit 2 Core Operating Limits Report (COLR). The requested Technical Specification changes do not involve any plant modifications or operational changes that could affect system reliability or performance or that could affect the probability of operator error. The requested changes do not affect any postulated accident precursors, do not affect any accident mitigating systems, and do not introduce any new accident initiation mechanisms. Therefore, the proposed TS changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No. The SLMCPR is a TS numerical value, calculated to ensure that during normal operation and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling if the limit is not violated. The new SLMCPRs are calculated using NRC-approved methodology discussed in NEDE-24011-P-A, NEDE-2401 1-P-A, "General General Fuel, Revision 16. The proposed changes do Electric Standard Application for Reactor Fuel," not involve any new modes of operation, any changes to setpoints, or any plant modifications. The proposed revised MCPR safety limits have been shown to be acceptable for Cycle 19 operation. The core operating limits will continue to be developed using NRC-approved methods. The proposed MCPR safety limits or methods for establishing the core operating limits do not result in the creation of any new precursors to an accident. Therefore, this change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No. There is no significant reduction in the margin of safety previously approved by the NRC as a result of the proposed change to the SLMCPRs. The new SLMCPRs are NEDE-2401 1-P-A, "General calculated using methodology discussed in NEDE-24011-P-A, General Electric Fuel, Revision 16. The SLMCPRs ensure that during Standard Application for Reactor Fuel," normal operation and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling if the limit is not violated, thereby preserving the fuel cladding integrity. Therefore, the proposed TS changes do not
License Amendment License Amendment RequestRequest Safety Limit Safety Limit Minimum Minimum Critical Power Ratio Critical Power Ratio Page 44 Page involve reduction in significant reduction involve aa significant margin of the margin in the of safety previously approved safety previously approved by by the the NRC. NRC. Based on Based on the above, Exelon the above, Exelon Generation Company, LLC, Generation Company, LLC, concludes that the concludes that the proposed proposed amendment does amendment does not significant hazards involve aa significant not involve hazards consideration under the consideration under the standards standards setset forth forth in 10 in 10 CFR CFR 50.92(c), and, accordingly, 50.92(c), and, finding of accordingly, aa finding no significant of no consideration is hazards consideration significant hazards is justified. justified. 4.4 4.4 Conclusions based on the considerations discussed above, (1) In conclusion, based In is reasonable assurance (1) there is assurance that the health and safety of of the public will not be endangered by operation in by operation in the proposed manner, (2) such activities will be conducted in in compliance with the Commissions Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
ENVIRONMENTAL A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical 51 .22(c)(9). Therefore, pursuant to 10 exclusion set forth in 10 CFR 51.22(c)(9). 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in in connection with the proposed amendment.
6.0 REFERENCES
General Electric Standard Application for Reactor Fuel," NEDE-2401 1-P-A, "General
- 1) NEDE-24011-P-A, Fuel, Revision 16.
ATTACHMENT 22 ATTACHMENT Markup of Markup Specifications Page Technical Specifications of Technical Page Revised TS Revised TS PaQe Page 2.0-1 (Unit 2.0-1 (Unit 2) 2)
Ls SSLs 2.0 2.0 o 2.0 2.0 SAFETY LIMITS (SLs) SLs 2.1 SLs 2.1.1 Reactor Core SLs Reactorçre 2.1.1.1 2.1.1,1 steam dome pressure << 785 psig or core With the reactor steam core 10% rated core flow: flow << 10% THERMAL POWER shall be ~ 25% RTP. 2.1.1.2 With the reactor steam dome pressure ~ 785 psig and core flow ~ 10% rated flow rated~or cor flow flow'
~~o MCPR~~'),Lbe MCPR sha 1 be > 1.07
.0 r for sing
~reCirCU1.tion 1.07 for wo recirculation loop operation ee recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. 2.1.2 Reactor Coolant SYstem System Pressure SL Reactor steam dome pressure shall be ~ 1325 psig. ,() 2.2 SL Violations With any SL violation, the following actions shall be completed within 2 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert insert all insertable control rods. (continued) (conti nued)
'\
j PBAPS UN IT 22 UNIT 2.0-1 Amendment No. 259
ATTACHMENT 33 Retyped Technical Specifications Page Page Revised TS Paqe Page 2.0-1 (Unit 2)
SLs S Ls 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < < 785 psig or core flow << 10% rated core flow: THERMAL POWER shall be s 25% RTP. 2.1.1.2 With the reactor steam dome pressure ~ 785 psig and core flow ~ 10% rated core flow: MCPR shall be ~ 1.10 for two recirculation loop operation or ~ 1.14 for single recirculation loop operation. 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. fuel 2.1.2 pressure SL Reactor Coolant System Pressure Reactor steam dome pressure shall be s 1325 psig. 2.2 SL Violations Violations* With any SL violation, the following actions shall be completed within 2 2 hours: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods. (continued) (conti nud) PBAPS UNIT 22 2.0-1 Amendment No.
AITACHMENT ATTACHMENT 55 Version of Non-Proprietary Version Non-Proprietary Global Nuclear of Global Fuel Letter Nuclear Fuel Letter
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class! Class I GNF GNF Attachment Attachment May 2010 May 2010 GNF -0000-01 GNF-0000-0 0-4753-RO-N 1 I10-4753- RO-NP P eDRFSection:: 0000-0110-4 eDRFSection 753 RO 0000-0110-4753 RO GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Peach Bottom 2 C19 C 19 Peach Peach Bottom Bottom 22 C 19 C19 Verified Information Verified Information Page of 25 Page 11 of25
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY Class II GNF GNF Attachment Attachment Proprietary Information Notice non~proprieta'Y version of the GNF proprietary report. From the This document is the GNF non-proprietary GNF proprietary version, the information denoted as GNF proprietary (enclosed in double brackets) was deleted to generate this version. Important Notice Regarding Contents of this Report Please Read Carefully The information contained in this document is furnished solely for the purpose(s) stated in the transmittal letter. The only undertakings of GNF-A with respect to information in this document are contained in the contracts between GNF-A and its customers or participating utilities, and contract. The use of this nothing contained in this document shall be construed as changing that contract, information by anyone for any purpose other than that for which it is intended is not authorized; 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. Copviiglit 2010. Global Nuclear Fuel-Copyright Fuel Americas, LLC. All Rights Rcserycd Americas. LLC, Reserved Proprietary Information Notice Verified Information Page 2 of25 Page of 25
GNF NON-PROPRIETARY INFORMATION GNF ON-PROPR1ETARY INFORMATION Class II Class GNF Attachment GNF Attachment Table of Table of Contents Contents 1.0 1.0 METHODOLOGY METHODOLOGY 44 2.0 2.0 DiSCUSSiON DISCUSSION 44 2.J. 2.1 M MAJOR :iRmItoRx jo Uo1 CONTRlm;TORS SLMCPR Cii.oi: TO SLMCPR CII.-\NGE .4~ 2.2. 2.2. DFvI.r1oNs DEVIATIONS I\ IN NRC-A ROVED Uomwr.uNIms NRC-AI'I'ROVED UNCERTAINHES 55 2.2./. 2.2.1. R*Fa(;/ur R&tcior 55 2.2.2. 2,2,2. Core 1low (ore nul\' Rate Rate and ami Random Randum E/feth.e E.!Tectilte TIP l?eading Reading 55 2.2.3. 2.2.3. LPRAf (.pdaie LPRI Update Interval Interval and alld Calculated Bundle Power Ca/culated Bundle Power 6 2.3. DEI'AR'll.;R£ 1:1o.1 DEPRmRF: NRC-ApPROVED ME FROM NRCAPPRov1o iIiODOUXY METHOIXJL(X:;Y 77 2.4. 2.4. F AXIAL POwER El ANI..u FI*E!. SII.WE Pi.>i POWER Sii.ri: :r PEN.*\I.TY 77 2.5. METIIOIX)UXiY RLS1Rlc NlflR)lX)l.(Xi RESTRICTIONS lIONS, 88 2.6. MINIMI;M CoRt: I\l\tL\l CORE FiowFr.ow C0\i)[flO\ CO"I)I1'I01"< 88 2.7. 2.7. LIM rI1NG CON Lixirimu CONTROL ROD P,.vm:Rxs i Rn!. ROD PXlTERNS 99 2.8. 2.8, COI~E MONIIORIM; Ciu MONITORING S STEM SYSTEM 99 2.9. POWLE/Fww PO\\'ERlFr..OW MAP MAI' 99 2.10.
- 2. 10. CoRECORE Loucco oici 1
Di LOADING DIAGRA:-.I 99 2.11.
- 2. 11. Fio iRE FIGI REFERENCES RI Ri:nRFNCEs 9
<)
2. 2.12.
- 12. ADf)(TIOI'L\L Licisrco Cc1)iliocs AI)DIIlo\..\J. SLMCPR LICENSING CONDrnONS 1()
10 2.13. SiIL\RY SUM1vL\RY 1(.) 10
3.0 REFERENCES
111J List of Figures FIGI iRE 1. Ci RRENi CYCLE CORE CURRENT Lo..oau DJAGRA"'1 Coii LOADING DL\GR\M 12 12 FIGUIU: FLOURE 2. PRI~V(OUS PIEvioLs CYCLE Cyei.i CORIo Lowoo DIAGRAM CoRE LOADING 13 13 FiotRE FIGI 'RE 3.3, iRE -4.1 FROM FiuRE3.1 FIGI NEDC-3260 I P-A EROMNEDC-32601P-A 14 14 FIGliRE FLoIRE 4. FIOURE 111.5I FROM FIotRi: 1II.5-1 NEDC326() IPA ERo\I NEDC-32601 P-A 15 15 FiuRl: 5. FIGl.*RE 5. FICitlRE 111.52 FRO~f FIGrRI. IH.5-2 NEDC32601PA FROM NEDC-3260IP-A 16 16 List of Tables T.\131.E I.1. DESCRIPTIO" T\BLE DESCR1PTJ()N OF CORE oi CORE.. 17 17 T.4.UU: 2. 2. SLMCPR SLMCPR CALCULA'!10N C.\LCu1,..vIIoN MEnloIXlLCXiIES METIIOIX)LOGJES 18 18 T,NJILF: 3. TAllLE 3. MONTE MONTh CARLO C.i,ct imD SLMCPR C.iu.o CALCUL\TED SLMCPR \is. vs. ESTIMATE EsnM.vn ....,......,,,,.. 19 19 TABLE~. NONPoWER DISTRIBU'110N T\Bu 3. NO!':-POWER DISTRIBUTION U1\(.TR*(',\INTIES UNcIRT.IscIEs 21 21 T,\131.i; 5. TABLE 5. POWER DISlR1I3UT1ON UNCERTAI1\TlES POWER DISTRIBUTION UNcERT.I.r1Es 2323 TABLE T.BLE 6. 6. CRme\!. CRmc..\I.. POWER UNCERT..[NT1Es Po\vLR UNCERTAINTIES 25 25 Table Table of ofContents Contents Verified Verified Information Information Page 33 of25 Page of 25
NON-PROPRIETARY INFORMATION GNF SON-PROPR1ETARY GNF Class Class II GNF GNF Attachment Attachment 1.0 Methodology 1.0 GNF performed GNF Bottom 22 C19 Peach Bottom performed the Peach C19 Safety Limit Minimum Safety Limit Power Ratio Critical Power Minimum Critical Ratio calculation in (SLMCPR) calculation accordance to in accordance to NEDE-24Ol NEDE-240 II-P-A "General Electric Standard 1-P-A General Application for Reactor (Revision 16) Fuel" (Revision Reactor Fuel 16) using the following NRC-approv using the NRC-approved ed methodologi methodologies es uncertainties:: and uncertainties
- NEDC-32601IP-A NEDC-3260 P-A Methodolog "Methodology Uncertainties for Safety Limit y and Uncertainties MCPR Evaluations Limit MCPR Evaluations" (August 1999).
- NEDC-32694P-A NEDC-3269 "Power Distribution 4P-A Power Uncertainties for Safety Limit MCPR Evaluations" (August 1999).
Evaluations 1999).
- NEDC-32505P-A NEDC-3250 "R-Factor Calculation Method for GEl I, 5P-A R-Factor GE12 and GE13 Fuel I. GEI2 Fuel" 1999).
(Revision 1, July 1999) a* NEDO-I0958-A NEDO-l General Electric BWR Thermal 0958-A "General Thermal Analysis Basis (GETAB): Data, Application" (January 1977). Correlation and Design Application Table 2 identifies the actual methodologi methodologies es used for the previous cycle and the current cycle 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 bundle-by-bundle MCPR distribution, and (2) flatness of the bundle pin-by-pin power/R-core bundle-by-bundle power/k-factor distribution. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR. MIP MW (MCPR Importance Parameter) measures bundle-by-bundle MCPR distribution and RIP the core bundle-by-bundle RiP (R-factor Importance Parameter) power/k-fact measures the bundle pin-by-pin power/R-factor or distribution. The impact of the fuel fuel loading pattern on the calculated TLO SLMCPR using rated core power and rated core flow conditions has been correlated correlated to the parameter MIPR1P, which combines the MIP and RIP values. parameter MIPRIP, Table 3 presents the MIP and and RIP parameters for for the the previous cycle and the current along current cycle along with the TLO SLMCPR SLMCPR estimate MIPRIP correlation. estimate using the MlPRIP correlation, Ifif the minimum core flow flow case is is applicable, applicable, the TLO SLMCPR also provided for estimate is also SLMCPR estimate for that case case although MIPRIP although the MlPRIP correlation correlation isis only applicable to the applicable to the rated core flow case. This is flow case. is done done only to provide some some reasonable assessment of the basis of assessment basis minimum core the minimum flow case core flow case trend. Inin addition, addition, Table presents Table 33 presents Methodology Methodology Verified Information Verified Information Page 44 of25 Page of 25
GNF NON-PROPRIETARY INFORMATION GNF N()-PROPR1ETARY INFORMATION Class II Class GNF Attachment GNF Attachment estimated impacts estimated impacts on the TLO on the TLO SLMCPR due to SLMCPR due to methodology penalties, and/or deviations, penalties, methodology deviations, uncertainties deviations uncertainties approved values. Based deviations from approved Based on the MIPRIP on the correlation and MIPRlP correlation and anyany impacts due impacts due to deviations approved values, deviations from approved estimated TLO values, aa final estimated SLMCPR is TLO SLMCPR is determined. determined. Table 33 also Table also provides provides the the actual calculated Monte Monte Carlo SLMCPRs. Given the bias Carlo SLMCPRs. bias and and uncertainty in uncertainty the MIPRIP correlation [[ in the the inherent jj]] and the inherent variation in the Monte Carlo the Monte Carlo results [[ [[ n, the change in JJ, the change in the Peachthe Peach Bottom 22 C19 CI9 Monte Carlo calculated Monte TLO SLMCPR using rated core power and rated core flow conditions is Carlo TLO corresponding consistent with the correspondin g estimated TLO SLMCPRSLMCPR value. 2.2. Deviations in NRC-Approv NRC-Approved ed Uncertainties Tables 4 and 55 provide a list of NRC-approvNRC-approved ed uncertainties along with values actually used. A A discussion of deviations from these NRC-approv NRC-approved ed values follows; all of which are conservative NRC-approved values. relative to NRC-approved values Also, estimated impact on the SLMCPR is provided in Table 33 for each deviation. 2.2.1. 2.2.1, R-Factor At this time, GNF has generically increased the GEXL R-Factor uncertainty from [[
]] to account for an increase in channel bow due to the emerging unforeseen phenomena
]]
corrosion-induced channel bow, which is not accounted fbr called control blade shadow corrosion-induced for in the channel bow uncertainty component of the approved R-Factor uncertainty. The step "(J RPEAK a RPEAK" in Figure 4. NEDC-3260 I P-A, which has been provided for convenience in Figure 33 of 4, I1 from NEDC-32601 this attachment, is affected by this deviation. deviation, Reference 4 technically justifies that a GEXL R- R Factor uncertainty of [[ [[ ]J accounts for a channel bow uncertainty of up [[
]] to jJ.
]].
Peach Bottom 2 has experienced control blade shadow corrosion-induced corrosion-induced channel bow to the N RC-approved R-Factor uncertainty [[ extent that an increase in the NRC-approved [[ ]] is deemed prudent to address its impact. Accounting for the control blade shadow corrosion-induced corrosion-induced channel bow, the Peach Bottom 2 C 19 analysis shows an expected channel bow uncertainty of [[ 1l. 11. which is bounded by a GEXL R-Factor uncertainty of [[ [[ nJJ. Thus the use of a GEXL R R-Factor uncertainty of [[ [[ j] adequately accounts for the expected control blade shadow
]]
corrosion-induced channel bow for Peach Bottom 2 C 19. corrosion-induced 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 NRC-approved process to calculate the SLMCPR only at the the rated core power and rated core flow condition is adequately bounding relative to the SLMCPR calculated calculated at at rated core power and minimum core flow, see Reference 5. 5. The minimum core flow condition condition can be more limiting due to the the control rod pattern used. GNF GNF has modified the NRC-approv NRC-approved ed process for for determining determining the SLMCPR to include analyses SLMCPR at at the the rated core core power and and minimum licensedlicensed core flow point in core flow in addition addition to to analyses at at the rated core core power power and rated core core flowflow point. GNF believes this modificationmodification is is conservative conservative and and may in the future in the future provideprovide justification justification that that the the original original NRC-approv NRC-approved ed process process is is adequately adequately Discussion Discussion Information Verified Information Page 55 of25 Page of 25
GNF NONPROPRlETARY NON-PROPRIETARY INFORMATION Class II GNF Attachment bounding. For the TLO calculations performed at 82.8% core flow, the approved uncertainty values for the core flow rate (2.5%) and the random effective TIP reading (1.2%) are conservatively adjusted 82.8/100, The steps "() CORE FLOW" by dividing them by 82.8/100. FLOW and "(j (INSTRUMENT) in a TIP (INSTRUMENT)" Figure 4.1 from NEDC-3260 IP-A, which has been provided for convenience in Figure 33 of this iEDC-3260lP-A, attachment, are affected by this deviation, respectively. respectively Historically, these values have been construed to be somewhat dependent on the core flow conditions as demonstrated by the fact that higher values have always been used when performing SLO calculations. It is for this reason that GNF determined that it is appropriate to consider an increase in these two uncertainties when the core flow is reduced. The amount of increase is determined in a conservative way. For both parameters it is assumed that the absolute uncertainty remains the same as the flow is decreased so that the percentage uncertainty how. This is conservative relative to the increases inversely proportional to the change in core flow. core flow uncertainty since the variability in the absolute flow is expected to decrease somewhat as the flow decreases. For the random effective TIP uncertainty, there is no reason to believe that the percentage uncertainty should increase as the core flow decreases for TLO. Nevertheless, this uncertainty is also increased as is done in the more extreme case for SLO primarily to preserve the historical precedent established by the SLO evaluation. Note that the TLO condition is different than the SLO condition because for TLO there is no expected tilting of the core radial power shape. The treatment of the core flow and random effective TIP reading uncertainties is based on the assumption that the signal to noise ratio deteriorates as core flow is reduced. GNF believes this (non is conservative and may in the future provide justification that the original uncertainties (non-flow dependent) are adequately bounding. The core flow and random TIP reading uncertainties used in the SLO minimum core flow SLMCPR analysis remain the same as in the rated core flow SLO SLMCPR analysis because these uncertainties (which are substantially larger than used in the TLO analysis) already account for the effects of operating at reduced core flow. 2.2.3. interval and Calculated Bundle Power LPRM Update Interval To adequately address the LPRM update/calibration interval in the Peach Bottom 2 Technical GF has increased the LPRM update uncertainty in the SLMCPR analysis for Specifications, GNf Peach Bottom 2 C 19. The approved uncertainty values for the contribution to bundle power uncertainty due to LPRM update [[ [[ ]j and the resulting total uncertainty in calculated
]]
bundle power [[ [[ ]] are conservatively increased. The steps "0'o TIP (INSTRUMENT)" (lNSTRUENT) and "0' o BUNDLE (MODEL)"(MODEL) in Figure 4.1 from NEDC-32601P-A, which has been provided for convenience in Figure 33 of this attachment, are affected by this deviation. Discussion Verified Information 25 of25 Page 6 of
GNP NON-PROPRIETARY GWF NON*PROPRJETARY INFORMATION JNFORMATION Class! Class I GNF GNF Attachment [[ J]]] The total bundle power LPRM update uncertainty as detailed in Section 3.3 of NEDC uncertainty is a function of the LPRM NEDC-32694P-A 32694P-A. 2.3. Departure from NRC-Approved Methodology No departures from NRC-approved methodologies were used in the Peach Bottom 22 C 19 C19 SLMCPR calculations. 2.4. Fuel Axial Power Shape Penalty detennined that higher uncertainties and non-conservative biases in the At this time, GNF has determined (t e, inlet, cosine, outlet and coirelations for the various types of axial power shapes (i.e., GEXL correlations methodolo!,'Y values, see relative to the NRC-approved methodology double hump) could potentially exist relatie References 3, 6, 7 and 8. The following table identifies, by marking with an "X",X, this potential for each GNF product line currently being offered: [{ [1 II 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 detennined accordance to the following table: [[ Discussion Discussion Verified Information Page 7 of25 of 25
NON-PROPRIETARY INFORMATION GNF NON.PROPRIETARY INFORMATION Class II GNF GNF Attachment r I
\I 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 66 provides a list of the GEXL critical power uncertainties detennined in accordance to the NRC-approved methodology contained in NEDE-2401 determined NEDE-24011-P-Ai-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 Peach Bottom 22 C19 SLMCPR SLMCPRvalues. values. 2.5. 25 Methodology Restrictions The four restrictions identified on Page 33 of NRCs NRC's Safety Evaluation relating to the NEDC326O1P, General Electric Licensing Topical Reports NEDC-32601 P, NEDC-32694P, and Amendment 25 NEDE-240] I-P-A (March I], to NEDE-240i1-P-A 11, ]999) 1, 2, 3, and 9 1999) are addressed in References 1,2,3, 9. No new GNF fuel designs are being introduced in Peach Bottom 2 C19; C 19; therefore, the NEDC-NEDC statement if 32505P-A statement" ... if new fuel is introduced, GENE must confirm that the revised R-Factor method is still valid based on new test data"data is not applicable. 2.6. Minimum Core Flow Condition For Peach Bottom 2 C 19, the minimum core flow SLMCPR calculation perfonned performed at 82.8% core flow and rated core power condition was limiting as compared to the rated core flow tiow and rated core power condition. At low core flows, the search spaces for the limiting rod pattern and the nominal rod pattern are essentially the same. Additionally, the condition that MIP ([ [[ fl, establishes a reasonably bounding limiting rod pattern. Hence, the
]],
rod pattern used to calculate the SLMCPR at 100 percent rated power/82.8 percent rated flow reasonably assures that at least 99.9% 99,9% of the fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences nonnal Discussion Verified Information Page 80f25 8 of 25
GNF NON*PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class II Class GNF Attachment during the operation of Peach Bottom 22 C19. of Peach C 19 Consequently, SLMCPR value calculated from Consequently, the SLMCPR 82.8% core the 82.8% limiting MCPR distribution reasonably power condition limiting core flow and rated core power bounds this mode of operation for Peach Bottom 22 Cl 9. C 19. 2.7. Limiting Control Rod Patterns The limiting control rod patterns used to calculate the SLMCPR reasonably assures that at least 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 Peach Bottom 22 Cl9. C19. 2.8. Core Monitoring System C 19, the 3DMonicore system will be used as the core monitoring system. For Peach Bottom 2 C19, 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 11 and 2 provide the core-loading diagram for the current and previous cycle cyc.le respectively, NEDE-2401 i-P-A, Table I provides a which are the Reference Loading Pattern as defined by NEDE-24011-P-A. description of the core. 2.11. Figure References Figure 3 is Figure 4.1 4,1 from NEDC-32601 111.5-1 from NEDC-3260IP-A. P-A. Figure 4 is Figure III.5-1 NEDC-32601P-A. NEDC-32601P-A. Figure 5 is Figure 111.5-2 NEDC-32601P-A. 111.5-2 from NEDC-32601 P-A. Discussion Verified Information of 25 Page 9 of25
GNF NON-PROPRIETARY INFORMATION GNF NONPROPR[ETARY INFORMATION Class! Class I GNF Attachment GNF 2.12. Additional SLMCPR Licensing 2.12. Licensing Conditions C19, no additional SLMCPR Bottom 22 Cl), Peach Bottom For Peach SLMCPR licensing conditions are licensing conditions included in the are included analysis. 2.13. Summary 1.10 for TLO and SLMCPR values are 1.10 The requested changes to the Technical Specification SLN4CPR 14 for SLO for Peach Bottom 22 Ci 1.14 9. C 19. Discussion Verified Information of 25 Page 10 of25
GNF NON-PROPRIETARY INFORMATION GNF NO?J-PROPRIETARY INFORMATION Class II Class GNF Attachment GNF Attachment 3.0 References 3.0 1.I. Letter. Glen A. Letter, Glen Watford (GNF-A) A. Watford (GNF-A) to U.S. Nuclear to U.S. Commission Document Regulatory Commission Nuclear Regulatory Document Control Desk Control with attention Desk with attention to R. Pulsifer to R. Pulsifer (NRC), "Confirmation of (NRC), Contrmation lOx 10 of lOx Fuel Design 10 Fuel Design Applicability Applicability to to Improved Improved SLMCPR, SLMCPR, Power Power Distribution Distribution and and R-Factor R-Factor Methodologi es. Methodologies", FLN-2001-016, FLN-200 September 24, 1-016, September 2001. 24,2001.
- 2. Letter.
- 2. Glen A, Letter, Glen Watford (GNF-A)
A. Watford (GNF-A) to U.S. Nuclear to US. Commission Document Regulatory Commission Nuclear Regulatory Document Desk with Control Desk attention to J. with attention (NRC), Contirmatio
- 1. Donoghue (NRC), "Confirmation n of Applicability of the Applicability of the of GEXL 14 the GEXL Correlation and Associated R-Factor Methodology 14 Correlation Methodology for Calculating Calculating SLMCPR Values in Cores Containing SLNCPR Containing GEI4 Fuel", FLN-2001-0 GEI4 Fuel, FLN-2001-017, 2001 17, October 1,1,2001.
- 3. Letter, Glen A. Watford (GNF-A) (GNF-A) to U.S. U,S. Nuclear Regulatory Commission Document attention to Joseph E. Donoghue (NRC), Final Desk with attention Control Desk "Final Presentation Material GEXL Presentation - February 11, for GEXL 2002", FL-2002-004 I I, 2002, , Febniary 12, 2002.
FLN-2002-004, February 4, Letter, John F. Schardt (GNF-A) to U.S. uclear
- 4. Nuclear Regulatory Commission Document Control Desk with attention to Mel B. Fields (NRC), Shadow "Shadow Corrosion Effects on FLN-2004-030, November 10,2004.
Uncertainty",, FLN-2004-030, SLMCPR Channel Bow Uncertainty 10, 2004. 5, Letter, Jason S. Post (GENE) to U.S. Nuclear Regulatory Commission Document Control 5. Desk with attention to Chief, information Management Branch, et a1. Chiet Information (iRC), "Part a!. (NRC), Part 21 SLMCPR, MFN 04-108, September 29, Non-Conservative SLMCPR", Final Report: Non-Conservative 2004. 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 NRC Technology Update -
Proprietary Slides - July 31 1, 2002, FLN-2002-015. 3 1 - August 1,2002", 31, 2002. IS, October 31,2002.
- 7. Letter, Jens G. Munthe Andersen (GNF-A) to U.S. Nuclear Regulatory Commission U.S. Nuclear Document Control Desk with attention to Alan Wang (NRC), "GEXL GEXL Correlation for I OX 10 Fuel",
IOXIO FLN-2003-005, May Fuel, FLN-2003-005, 31, 2003. May 31,2003. 8,
- 8. Letter, Letter. Andrew A. Lingenfelter (GNF-A) to U.S. Nuclear Regulatory Regulatory Commission Document Document Control Control Desk Desk with cc to to NC MC Honcharik (NRC), Removal "Removal of Penalty Being of Penalty Being Applied to GE GEI414 Critical for Outlet Peaked Correlation for Outlet Peaked Critical Power Correlation Axial Power Shapes, Power Shapes",
FLN-2007-03I, FLN-2007-03 1, September 18, 2007. September 18,2007. 9.
- 9. Letter, Letter. Andrew Andrew A. A. Lingenfelter (GNF-A) to Lingenfelter (GNF-A) to U.S. Nuclear Regulatory U.S. Nuclear Commission Regulatory Commission Document Control Desk Document Control Desk with with cc cc to to NC MC Honcharik Honcharik (NRC),
(NRC), GiF2 "GNF2 Advantage Advantage Generic Generic Compliance Compliance with NEDE-2401 1-P-A (GESTAR with NEDE-24011-P-A (GESTAR II), NEDC-3327 11), NEDC-33270P, 0P, Revision Revision 2, June 2, June 2009 2009 and and GEXL Correlation for GEXL Correlation GNF2 Fuel, for GNF2 NEDC-33292P Revision Fuel NEDC-33292P, Re.ision 3, 3 June 2009 June 2009", MFN MFN 09-436, 09-436, June June 30, 30, 2009. 2009. References References information Verified Information Verified Page II Page of 25 II of25
GNF NON-PROPRIETARY INFORMATION Class!I Class GNF Attachment Figure 1. I. Current Cycle Core Loading Diagram Go Ic SR - J1 1T 11 flJ1 El ss Si Tj L J T L s2 so w 48 e m T JLEl w- El E1fl Ei I!1i il E 1 E1 @J 1 1 1 11 tJ i El 1 Jit 42- EJ LiiJ Ji1 tJ T Ji 4O- JJJ 38-A- 1-32-G 28- !JiL LJ i!iJ LkLi EL EJit jLU JiiEi 1 Fi:jiL p1 L!J i1 26 Tj 22-2O-18-16 - -m~~~
-jØj 11--- [!]1!l1!J1!I[][!]
12 - rn El I!l ~ [h [] []i ~(ffi []iJ ] [li] [h i] ii] iW [h[J £]i] El El 10 -
- [!][[][][El E1 iVE fl!1fi El 8 - - - - -
m~ J fl1iJ hJ flJi ht fJiI 6 * - - - - [i][I](j] El it] LitIJ tJ I I I [[J @Ji II ht Eit! El IIiiiiiiiiiiii 1 $ 7 11 i5 1$ 11 t21 22$229 1 $7$1j 1i$4iL Fuel Type A'~GNF2-PIOJXJ2B393*15GZ*IOOT2-150-T6-.B34 ACNF2-Pl01Xi2B393- 15G7-100T2- I 50-T6-3334 K=(i I 567-10072-150-76-3335 NF2-P IOIXi2B392-ISGZ-100T2-1 K{INF2-P10JX2B392- S()*T6-3335 B RGE 14 PIODNAI3416-h6/ 1001 bO lo 290 (ii 14-PIODNAB416-150Z-IOOT*150.T6-2908 (if 14 P10I)NA11420 136/ 1001 1 0 16 3097 1LfiEI4*PIODNAB420*lJGZ*IOOT*150*T6*3097 C~OE C. 6114 P10I)NAH4I7 13(i60 1001 bO 16 2909 14-PIODNAB417-13G60*IOOT-150-T6-2909 M (ii 14 PI0DNAB416-1 36/ 1001 N) 16 3098 M"GEI4-PIODNAB416-15GZ-IOOT-150-16-3098 D~GEI4-PlODNAB41 D 5-1 SGZ-looT-ISO-T6-29 10 GEI4-PIODNAB4I5-150Z-IOOT-150-T6-2910 N0E14-PIODNAB4I6-ISGZ-100T-150-T6-2911 N-GEI4-PIODNAB416-15GZ-100T-150-T6-2911 14 PI0DNAB4IO (if 14-I'IODNAB4 IEOE 16-1156/ 1001 bO 16 2911 50Z-looT-150-T6-29 11 OGE14P10DNAB4 11I 567-1007-150163099 OGEI4-PIODNAB411.-15GZ-100T-150-T6-J099 14 PI0DNAB4 16 1 Aj/ 1001 1 0 I t 2012 F~GEI4-PIODNAB416-15GZ-IOOT-150-T6-2912 F(iI 14 i101)NAB3O9 P61E14*1' P=G 1)6/ lOOT-I 1ODNAB409-15Gl- 1001 130 16 291 50-16-2913 6 6114 G**GE PIODNAH4O9 b6/ 14-PWDNAB409-1 5Gl* 1(X) lOOT- 130 16 2913 1 150-T6-2913 QGNF2-P101X12B388-6G80667Mf2(I63)- QwGNF2-1' IO[)G2B388-6GIW i (,(}7 .0/2G6.0-110072-150-76-3336 00T2-150*T6-3336 HXiNF2-Pi0IXi2B406- I2G60-100T2-1 50-16-3337 HONF2-PlOfXi2B406-12G6.0-100T2-150-T6-3337 156/- 1(X) 12150-163335 RGNF2-PIOIXi2B3'.12-15GZ-100T2-150-T6-3335 R6N12P10D6211392-1GNF2-PIODG2I1393- 156/10072-1 50-76-3334 TGNl:2-PIOIXi2B393-15GZ-IOOT2-IS(J-T6-.B34 S6N12-P10D0211392-SGNF2-P I 567-10072-150-76-3332 IO\X,2B392-15GZ- 1OOT2-1 so* T6-3332 J GNF2-P1oDci2B38s-6G8o6G702O60- 10072-1 50-76-3336 .1GNF2*PIODG2B388-6G80/6G7.0206.0-IOOT2-ISO-T6-3336 Figure 1. Current Cycle Core Loading Diagram Page 12 of25 12of25
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class Class II GNF Attachment GNF Attachment Figure 2. Figure 2. Previous Previous Cycle Core Loading Diagram Cycle Core Diagram 60 58 56 54 54 52 52 H G c B F J D I J 0 0 J L 0 J F B C C H 50 50 48 46 48 44 44 42 42 40 f [J EEI Ii ti 1 38 38 36 36 EThEJ E iEJ JJ !JiG Øi 13Ji0 iI iL1 DiI 1!kiJ iE EJiE tD Di Ji 34 34 32 32 LJiLJ JiU LJiLJ JiEJ IiEJ 1i1i 1JiIJ JiJ ilJ Ji11 I!JiIJ JiEJ UiJ JiJ 30 30 28 JiLJ ill 1J1J LiiJ EIi I1 !hIJ JjI Ji 1iit2J UilJ EJiJ 26 24 24 EliEl iD EiE) E1il E]it!] [!Ji[] Eli[9 iP ta ] 1!] E]iEl Di1 EliEl 22 22 20 20 iEliEif 18 16 16 iiØDiDiiiiiiDDiiDEl 14 12 1 Ø 10 10 EllEl EllEl E]lEl EI EllEl EllEl Ell[D EIEI ]l 8 ElilUiDEli1UElLElE1 6 4 2 11 3 5 7 9 11 13 13 15 15 1717 19 21 21 23 25 27 29 29 3131 3333 35 37 39 41 43 45 47 49 51 53 55 57 59 59 Fuel Type A~GEI4-pIODNAB416-IS07.-IOOT-ISO-T6-2908 ACE 14-PIODNAB4 161 5GZ- 1 (K)T- I 50-T6-290X H~()EI4-pIODNAB41 5-1 60Z- IOOT-150-T62790 IIGF14-P1ODNAB4i 5-16GZ-100T-150-T6-2790 B (rI 14 PIODNAI1417 1 (i6 01001 B"'OEI4-PI0DNAB417-13G6,O... 16 2909 IDO . T6*2909 IOOT-150. !"'OE 14 PI01)NA13420 1 G/ 1001 LU JO 097 1 (ii 14-PIODNAB420-13G1,-l00T-150*T6-3097 C (t 14 P1 ODN 1141 1(i/ 100 F I DO 16 2910 CGEI4-PIODNAB415-15G1,-100T-150-T6-2910 F'GE 14 P10I)NAB4JO JI SOZ-IOOT-l (xl 14-PIODNAB416- DO 16 IO9 ( c/ 1001 1 50-1'6-3098 D"GEI4-PJODNAB416-15GZ-l00T-ISO-T6-291 D GE14M0DNAB41615GZ-100 T150-16-291 II K GE14P10DNAB416-15GZ-i00T-i5O-T6-29Il K'OEI4-PIODNAB416-15GZ-I00T-1.50- T6-29 11 E* I GE 13 P101)NA0416 bO! 1($i1 LU 16 01 14-1'IODNAB416-15GZ-IOOT-ISO-T6-2912 I L'GE 14 P1O1)NAB4II JI -IbO/ xI I4-PlODNAB4 1(X)! IDO 16 3009 SGZ-IOO'l'-150-T6-3099 F=Ci 1 0/ 1001 LU lo 29113 1$ P1fl1)NAB400 15GZ-IOOT-150-T6-29 FOnE 14-PIODNAB409- M0! 14 PIODNAP4U9 bO! 1001 bO 16 291 M'"'GEI4-PIODNAB409-15GZ-IOOT-150-T6-2913 (1 "GEI4-PlODNAB415-15GZ-(J GEI4p1ODNAR415i5G/i00L 150-16-2789 100T-150-T6-2789 Figure 2. Figure 2. Previous Previous Cycle Cycle Core Core Loading Loading Diagram Diagram Page 13 Page of 25 13 of25
GNFNON-PROPR GNF IETARY INFORMAT NON-PROPRIETARY ION INFORMATION Class II Class GNF Attachment GNF Attachment [[[[
]]1]
Figure Figure 3. 4.1 from Figure 4.1
- 3. Figure NEDC-32601P-A from NEDC-3260IP-A Figure Figure 3.3. Figure Figure 4.1 4.1 from from NEDC-3260 1P-A NEDC-3260IP-A Page 14 Page of 25 14 of25
GNF NONaPROP GNF RIETARY INFORMAT NON-PROPRIETARY ION INFORMATION Class II Class GNF Attachment GNF Attachment [[
]]1]
Figure Figure 4.4. Figure Figure 111.5-1 from NEDC-32601P-A from NEDC-32601P-A Figure 4.4. Figure Figure 111.5-1 from Figure III.5-1 NEDC-32601P-A from NEDC-3260IP-A Page 15 Page of 25 15 of25
GNF NON-PROPRJETARY INFORMATION GNF NON-PROPRIETARY INFORMAnON Class Class II GNF Attachment GNF Attachment [[[[ 11
]]
FigureS. Figure NEDC-32601P-A
- 5. Figure 111.5-2 from NEDC-32601P-A Figure 5. Figure Figure 5. 1115-2 from Figure III.5-2 from NEDC-32601 P-A NEDC-32601P-A Page of 25 16 of25 Page 16
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class I1 GNF Attachment Table 1. Description of Core Previous Cycle Previous Cycle Rated Current Cycle Current Current Cycle Rated Current Description Minimum Core Flow Minimum Flow Limiting Core Flow Minimum Core Flow Core Flow Limiting Core Limiting Case Case Limiting Case Case Number of Bundles in the 754 764 754 764 Core Core Limiting Cycle Exposure Point (i.e. EOC EOC EOC EDC EOC BOC/MOC/EOC) BOC/MOC!EOC) Cycle Exposure at Limiting Point 13400 13400 12700 13300 (MWd/STU) (M Wd/STU)
% Rated Core Flow
%RatedCoreFlow 82.8 100 82.8 100 Reload Fuel Type GE14 GNF2 Latest Reload Batch Fraction, %
.,5,o 35.6 35,6 35.6 Latest Reload Average Batch Weight Weight% % 414 4.14 3.94 Enrichment Core Fuel Fraction:
GEI4 1.000 0.644 GNF2 0.000 0.356 Aerage Weight % Core Average 4 07 4 j 4.15 4.07 Enrichment Table 1.1. Description Description of Core Core Verified [nfoffilation Verified Information Page 17 Page of 25 17 of25
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY iNFORMATION Class 1I Class GNF GNF Attachment Attachment Table 2. SLMCPR Calculation Nlethodologies Methodologies Previous Cycle Previous Cycle Previous Cycle Rated Previous Current Cycle Cycle Curt ent Cycle Rated Current Description lescription Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Core Flow Limiting Core Limiting Case Limiting Case Case Case Limiting Case Limiting Case Case Case Non-power Distribution NEDC-3 2601 260 IP-A P-A NEDC-32601P-A NEDC-3 2601 P-A Uncertainty Power Distribution 2601 P-A NEDC-3 P-A 2601IP-A NEDC-3 NEDC-32601 NEDC-3260 Methodology Power Distribution NEDC-32694P-A NEDC -3 2694P-A NEDC-32694P-A Uncertainty Core Monitoring System 3DMonicore 3DMonicore Table Table 2.
- 2. SLMCPR Calculation Methodologies Methodologies Verified Information Page 18 of 25 18 of25
GNF NON-PROPRIFfARY INFORMATION GNF NON-PROPRIETARY INFORMAnON Class I GNF Attachment GiF Attachment Table 3.3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case [[ [[ Table Table 3. 3, Monte Monte Carlo Carlo Calculated SLMCPR SLMCPR VS.vs. Estimate Information Verified lnfonnation Page 19 of25 Page 19 of 25
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class II Class GNF GNF Attachment Attachment Table 3.3. Monte Carlo Calculated Calculated SLMCPR vs. Estimate Estimate Previous Cycle Cycle Previous Cycle Rated Previous Current Cycle Current Cycle Cycle Rated Description Minimum Core FlowFlow Flow Limiting Core Flaw Minimum Core Flow Core Flow Limiting Limiting Limiting Case Case Limiting Case Case IIii Calculated SLMCPR Table 3. Monte Carlo Calculated SLMCPR VS. Estimate vs. Estimate eri fled Information T
\
Verified Information Page 20 of Page of 25
GNF NON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class 1I Class GNF Attachment GNF Attachment Table 4. Non-Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Previous Current Cycle Current Cycle Current Cycle Current Cycle Approved) Value Core Minim um Core Minimum Rated Core Rated Core Flow Flow Minimum Core Rated Core Flow Flow
+/- (J (%)
+/- Flow Limiting Case Case j Limiting Case Flow Limiting Case Limiting Case GETAB GETAB Feedwater Flow Feedwater Flow N/A 11.76 76 N/A N/A N/A N/A N/A Measurement Measurement Feedwater Feedwater Temperature Temperature 0.76 076 N/A N/A N/A N/A N/A N/A N/A N/A Measurement Measurement Reactor Pressure 0.50 050 N/A N/A N/A N/A N/A Measurement Measurement 1
Core inlet Inlet Temperature 0.20 020 N/A N/A N/A N/A N/A N/A Measurement Measurement Total Total Core Core Flow Flow 6.0 SLO/2.5 TLO N/A N/A N/A N/A N/A N/A Measurement Measurement Channel Channel Flow Flow Area 3.0 3 0 N/A N/A N/A N/A Variation Variation Friction Fnction Factor Factor 10.0 100 N/A N/A N/A N/A N/A N/k N/A Multiplier Channel Channel Friction Friction 5 5.0 N/A N/A N/A N/A Factor Factor Multiplier Table 4. Non-Power Distribution Uncertainties Table 4. Verified lnfonnation Information of 25 Page 21 of25
GNFNON-PROPRIETARY INFORMATION GNF NON-PROPRIETARY INFORMATION Class II Class GNF Attachment GNF Attachment Table 4. Table 4. Non-Power Distribution Uncertainties Non-Power Distribution Uncertainties Nominal (NRC-Nominal (NRC- Previous Cycle Previous Cycle Previous Cycle Previous Cycle Current Cycle Current Cycle Current Cycle Current Cycle Approved) Value Approved) Value Minimum Minim urn Core Core Rated Core Rated Core Flow Flow Minimum Core Core Rated Core Rated Core FlowFlow
+/-+/- ri(J (%)
(%) Flow Flow ILimiting imitu g Case Case Limiting Case Limitmg Case Flow Limiting Case Flow Case Limiting CCase ase NEDC-32601 NEDC-3260 P-A 1 P-A Feedwater Flow Feedwater Measurementt [[ ]] H ii ILU [Iii [IU Measuremen Feedwater Temperature Temperature J] ii [1Ii 1] 1] Measurementt Measuremen Reactor Pressure Measurement [[ ]] [[ ]] [[ ]] [[ ]] [[ ]]j Measui-ement Core Inlet Temperature 0.2 0.2 0.2 0.2 0.2 Measurement Measurement Total Core Flow TLO 6.0 SL0I2.5 SLO/2.5 TLO SLO/3 02 TLO 6.0 SL0I3.02 SLO/2.5 TLO 6.0 SL0/2.5 SLO/302 TLO 6.0 SLO/3.02 6.0 SLO/2.5 TLO Measurement Measurement Channel Flow Flow Area [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Variation Friction Factor Multiplier [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Channel Friction Friction S 0 5.00 5.0 S0 S0 5.0 50 5.0 5.0 Factor Factor Multiplier Table Table 4. 4, Non-Power Non-Power Distribution Distribution Uncertainties Uncertainties Verifi.ed Information Verified Infonnation Page 22 Page of 25 22 of25
GNF NON-PROPRIETARY GNF NON-PROPRIETARY INFORMATIONINFORMATION Class 1I Class GNF Attachment GNF Attachment Table 5. Power Table 5, Power Distribution Distribution Uncertainties Nominal (NRC-ominal (NRC- Previous Previous Cycle Cycle Previous Cycle Cycle Current Cycle Current Cycle Description Approved) Value Minimum Core Minimum Core Rated Core Rated Core Flow Flow Core Minimum Core Rated Core Core Flow Flow
+/- (%)
+/- CJ (%) Flow Limiting Case Flow Limiting Case Flow Limiting Case Limiting Case Limiting GETAB/NEDC-32601P-A GETAB/NEDC-32601 P-A GEXL R-Factor GEXL R-Factor [[ ]]
fl N/A N/A N/A N/A N/A N/A N/A N/A Random Random Effecti ve Effective 2.85 SLO/l.2 TLO 2 85 SLOJI 2 TLO N/A N/A N/A N/A N/A N/k N/A TIP Reading flP_Reading Systematic Effective 88.66 N/A N/A N/A N/A N/A N/A N/A TIP Reading Reading NEDC-32694P-A, 3DMON 3DMONICORE ICORE GEXL R-Factor RFactor [[ ]] Jj [[ [[ ]] 1] [[ [[ ]] 1] [[ [[ ]] 1] [[ ]] 1] Random Random Effective Effective 1 LO 2 85 SLO/I.2 SLO/l 2 TLO 2.85 SLO/l 2 TLO 2 8 SLO/1.2 1 LO 2 85 SL0I1.45 2.85 SLOI1 45 TLO 2.85 SLOI 2 TLO 2 85 SLO/1.2 2.85 SLO/1 45 TLO 285 SLO/l.45 2.85 TIP Reading Reading TIP Integral TiPirnegral [[ n j] [[ [[ ]JjJ 1 [[ ]] [[ )] [[ H J) Four Bundle Power I Distribution Surrounding [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Surrounding TIP Location Contribution to Bundle Power Uncertainty Due to [1 [[ ]]U11 1111 iiii [[ ]] [[ ]] [[ ]] LPRM LPRM Update Update[J_ Table Table 5. Power Distribution Distribution Uncertainties Uncertainties Verified Infonnation Information of 25 Page 23 of25
GNF NON-PROPR GNF NON-PROPRIETARYIETARY INFORMAT INFORMATION ION Class II Class GNF Attachment GNF Attachment Table 5. Power TableS. Distribution Uncertainties Power Distribution Uncertainties Nominal (NRC-Nominal (NRC- Previous Cycle Previous Cycle Previous Cycle Previous Cycle Current Cycle Current Cycle Current Cycle Current Cycle Description Description Approved) Value Approved) Value Minim urn Core Minimum Core Core Flow Rated Core Rated Flow Minimum Core Minimum Core Rated Core Flow Rated Core Flow
+/-G(%)
+/- (%) Limiting Case Flow Limiting Flow Case Limiting Cise Limiting Case FIoi Limiting Case Flow Limiting Case Limiting Case linuhng Case Contribution to Contribution to Bundle Power Bundle Power Due Due to to jj 1] [[ ]] [[ ]] [[ ]]
Failed TlP Failed TIP Contribution to Contribution to Bundle Due to Power Due Bundle Power to [[U [[ji 11 1] [[ ]1]] Failed Failed LPRM LPRM Total Uncertainty in Total Uncertainty in Calculated Calculated Bundle Bundle [[ ]] jj [[ [[ ]] U U [[ ii
]] Ii
Power Power Uncertainty Uncertainty of TIP of TIP I Signal Nodal Signal Nodal [[ [[ ]] J] [[ [[ ]] U [[ U
]] [[ ii
]] [[
[[ 11
]]
Uncertainty Uncertainty Table 5.5. Power Table Power Distribution Distribution Uncertainties Uncertainties Information Verified Information Verified Page 24 of 25 Page 2401'25
GNFNON-PROPRIETARY GNF NON-PROPRIETARY INFORMATION INFORMATION Class II GNF Attachment Attachment Table 6. Critical Power Uncertainties Uncertainties Previous Cycle Cycle Previous Cycle Current Cycle Cy cle Current Cycle Nominal Value Value Description Minimum Core Minimum Rated Core Flow Flow Minimum Core Rated Core Flow Flow
+/- CJ G(%)
Limiting Case Flow Limiting Case Limiting Case Case Flow Limiting Case Flow Limiting [[ [[ 11
]]
Table 6. Critical Power Uncertainties Verified Information lnfonnation Page 25 of25 of 25
AflACHMENT ATTACHMENT 6 Power/Flow Map for Cycles 18 and 19 19
Core Flow (Mlb/hr) 0 0 10 20 30 40 0 SO 60 70 80 90 100 110 0 120 0 120 4000§ 110 A: Z Natar.l Circulation r B: 30" Kinuu,_ Pt.UIlp Speed E F
.W_
w 113.2% Rod LiDe a 0 3600§ OOCw )dI_. C: 61. 6~ Pov.rl J8.0'. rlow
~
100 D: 100.0' Powerl B2.8*. Fle.. D': 98.5- Poverl 81.0", Flow I: 100.0 .. Powerl 100. O' Flow 1 F I QOOO O 3200 _oooo E' : 98.5~ Pawer/ 100.0~ Flow i 90 I~TPO""Line F: 100. O~ Pawerl 110.0", Flow a
- P': 98. S:" P"". . / 110.0' Plaw
/
G: 19. 1~ 'ovet"1 110.0~ !'low
- 0. O
- -, 2800 Thermal Power (MWt) 80 Y: 19.7* Poverl IOO.O'! Flow 91.41% TPO .... LiDo I
.-. I: 19.1, Powerl 37. O~ Flow
~
Thermal Power (%) ICP: Incr****d Cor. flow ~ioQ a
~ ~
U
~
70 2400
--..U
~
u
~
l:l. E 60 SO 8 fCF 2000 l:l. 1600 g
§
'i 0
E U .t: Approx. 30'% Pump SpHd .t: !- 40 A u- Limlt Lile 1200 30 Approx. N8tInl Circuldon 20 / 9 -----. . -----.' ... Cavie.tioa IDlcrtock
-0 0
H G 800
.' 400 10 IOO"! TPO
- 3~14 HWt
,. / 100', CLTP 100, Core Flow
- 3458 M1tt
- t02.S Hlb/hr 0 0 0 10 20 30 40 0 SO 60 70 0 80 90 100 110 120 Core Flow (-1_)
O 0}}