ML061670151
| ML061670151 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/12/2006 |
| From: | Crouch W Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ANP-2541, Rev 0 | |
| Download: ML061670151 (68) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 12, 2006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN Pl-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket No. 50-260 Tennessee Valley Authority
)
Docket No. 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 and 3 -
EXTENDED POWER UPRATE (EPU)
RELOAD ANALYSIS REPORT This letter provides the Reload Analysis report for Unit 2 Cycle 15, which is the first BFN operating cycle that uses Areva core design and analysis methods at EPU conditions.
TVA previously submitted BFN EPU license amendment requests for Units 2 and 3 on June 25, 2004 (ADAMS Accession No. ML041840301) as proposed Technical Specifications Change 418, which is currently being reviewed by NRC.
The enclosed reload report includes the results of the cycle-specific core analyses, and of the transient and accident analyses performed for Cycle 15 operation.
Cycle 15 is scheduled to begin operating in Spring 2007.
This submittal responds to NRC's letter dated May 27, 2005 (ML051320146),
which asked that TVA submit the supplemental reload licensing reports (SRLRs) for the first planned cycles of EPU operation no later than six months prior to EPU implementation.
NRC later requested in a March 1, 2006, letter (ML060530095) that TVA submit
U.
S.
Regulatory Commission Page 2 June 12, 2006 the Unit 1 SRLR by May 20, 2006, and the Unit 2 Reload Analysis by July 1, 2006, in order to facilitate completion of the draft EPU Safety Evaluation for the three BFN units by October 2006.
The SRLR for the first Global Nuclear Fuel (GNF) based EPU cycle (Unit 1 Cycle 7) was submitted on May 15, 2006 (ML061450390).
The enclosed Unit 2 Cycle 15 Reload Analysis report is the Areva equivalent of the GNF SRLR and satisfies the NRC staff's request for a site-specific core safety analysis for the first Areva designed EPU cycle at BFN.
There are no regulatory commitments associated with this submittal.
If you have any questions about this submittal, please contact me at (256) 729-2636.
Sincerely, William D. Crouch Manager of Licensing and Industry Affairs
Enclosure:
ANP-2541 - Browns Ferry Unit 2 Cycle 15 Reload Analysis, June 2006 cc: See page 3
U.
S. Regulatory Commission Page 3 June 12, 2006 Enclosure Cc (w/Enclosure):
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Malcolm T.
Widmann, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms.
Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
Enclosure Browns Ferry Nuclear Plant (BFN)
ANP-2541 -
Browns Ferry Unit 2 Cycle 15 Reload Analysis, June 2006
AREVA NP Inc.
ANP-2541 Revision 0 Browns Ferry Unit 2 Cycle 15 Reload Analysis sjp/paj
Customer Disclaimer Important Notice Regarding the Contents and Use of This Document Please Read Carefully AREVA NP Inc.'s warranties and representations concerning the subject matter of this document are those set forth in the agreement between AREVA NP Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither AREVA NP Inc. nor any person acting on its behalf:
- a.
makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights; or
- b.
assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this document.
The Information contained herein is for the sole use of the Customer.
In order to avoid impairment of rights of AREVA NP Inc. in patents or inventions which may be included in the information contained in this document, the recipient, by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by AREVA NP Inc. or until after six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement. No rights or licenses in or to any patents are implied by the furnishing of this document.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page i Nature of Changes Item Page Description and Justification
- 1.
All This is a new document.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page ii Contents 1.0 Introduction....................................................................................................................
1-1 2.0 Fuel Mechanical Design Analysis..................................................................................
2-1 3.0 Thermal-Hydraulic Design Analysis...............................................................................
3-1 3.2 Hydraulic Characterization.................................................................................
3-1 3.2.1 Hydraulic Compatibility.........................................................................
3-1 3.2.3 Fuel Centerline Temperature...............................................................
3-1 3.2.5 Bypass Flow.........................................................................................
3-1 3.3 MCPR Fuel Cladding Integrity Safety Limit (SLMCPR)......................................
3-1 3.3.1 Coolant Therm odynamic Condition......................................................
3-1 3.4 Licensing Power and Exposure Shape..............................................................
3-2 4.0 Nuclear Design Analysis................................................................................................
4-1 4.1 Fuel Bundle Nuclear Design Analysis................................................................
4-1 4.2 Core Nuclear Design Analysis............................................................................
4-3 4.2.1 Core Configuration...............................................................................
4-3 4.2.2 Core Reactivity Characteristics............................................................
4-3 4.2.4 Core Hydrodynamic Stability................................................................
4-4 5.0 Abnorm al Operational Transients..................................................................................
5-1 5.1 Analysis of Plant Transients at Rated Power Conditions...................................
5-1 5.1.1 NEOC Licensing Exposure...................................................................
5-1 5.1.2 EOC Licensing Exposure.....................................................................
5-2 5.1.3 FFTR/Coastdown Licensing Exposure.................................................
5-2 5.2 Analysis for Reduced Flow Operation................................................................
5-3 5.3 Analysis for Reduced Power Operation..............................................................
5-3 5.4 ASME Overpressurization Analysis....................................................................
5-4 5.5 Control Rod W ithdrawal Error.............................................................................
5-4 5.6 Fuel Loading Error (Infrequent Event)................................................................
5-4 5.6.1 Mislocated Fuel Assembly....................................................................
5-5 5.6.2 Misoriented Fuel Bundle.......................................................................
5-5 5.7 Determ ination of Therm al Margins.....................................................................
5-5 6.0 Postulated Accidents......................................................................................................
6-1 6.1 Loss-of-Coolant Accident..................................................................................
6-1
.6.1.1 Break Location Spectrum.....................................................................
6-1 6.1.2 Break Size Spectrum............................................................................
6-1 6.1.3 MAPLHGR Analyses............................... I............................................ 6-1 6.2 Control Rod Drop Accident.................................................................................
6-2 6.4 Fuel and Equipment Handling Accident.............................................................
6-2 7.0 Technical Specifications........................... *..................................................................... 7-1 7.1 Limiting Safety System Settings.........................
7-1 7.1.1 MCPR Fuel Cladding Integrity Safety Limit..........................................
7-1 7.1.2 Steam Dome Pressure Safety Limit.....................................................
7-1 7.2 Limiting Conditions for Operation.......................................................................
7-1 7.2.1 Average Planar Linear Heat Generation Rate......................................
7-1 AREVA NP Inc.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page iii 7.2.2 Minimum Critical Power Ratio..............................................................
7-2 7.2.3 Linear Heat Generation Rate...............................................................
7-2 8.0 Methodology References...............................................................................................
8-1 9.0 A dditional References....................................................................................................
9-1 Tables 1.1 EOD and EOOS Operating Conditions..........................................................................
1-2 3.1 Licensing Basis Core Average Axial Power Profile and Licensing Axial Exposure R atio...............................................................................................................
3-3 4.1 C ore C om position..........................................................................................................
4-6 4.2 OPRM Setpoint versus Stability-Based MCPR Operating Limits...................................
4-7 4.3 Neutronic Design Values................................................................................................
4-8 5.1 Flow-Dependent MCPR Limits for Maximum Flow of 102.5% of Rated F low................................................................................................................................
5-7 5.2 Flow-Dependent MCPR Limits for Maximum Flow of 107% of Rated Flow................... 5-7 5.3 ATRIUM-10 Flow-Dependent LHGRFACf Multipliers for Maximum Flow of 102.5% and 107% of Rated Flow...................................................................................
5-8 5.4 GEl4 Flow-Dependent MAPFACf Multipliers for Maximum Core Flow of 102.5% and 107% of Rated Flow...................................................................................
5-8 5.5 MCPRp Limits for NSS Insertion Times BOC to NEOC..................................................
5-9 5.6 MCPRp Limits for TSSS Insertion Times BOC to NEOC..............................................
5-13 5.7 MCPRp Limits for NSS Insertion Times BOC to EOC..................................................
5-17 5.8 MCPRp Limits for TSSS Insertion Times BOC to EOC...............................................
5-21 5.9 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown............................. 5-25 5.10 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown............................ 5-28 5.11 LHGRFAC/MAPFACp Multipliers NSSITSSS Insertion Times All Exposures....................................................................................................................
5-31 5.12 Control Rod Withdrawal Error MCPR versus RBM Setpoint Results (for Rated Power and 1.08 SLMCPR)................................................................................
5-32 5.13 RBM Setpoint Applicability...........................................................................................
5-32 AREVA NP Inc.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page iv Figures 4.1 Lower Right Quarter Core Layout By Fuel Type............................................................
4-9 This document contains a total of 65 pages.
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Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page v AOT ARO ASME AST BOC BPWS CGU CPR CRDA CRWE Nomenclature abnormal operational transient all rods out American Society of Mechanical Engineers alternative source term beginning of cycle banked position withdrawal sequence commercial grade uranium critical power ratio control rod drop accident control rod withdrawal error EFPD EOC EOC-RPT-OOS EOD EOFPL EOOS FFTR FHOOS FWCF effective full-power days end of cycle end of cycle recirculation pump trip out-of-service extended operating domain end of full power life (100%P/100%F normal FW temperature) equipment out-of-service final feedwater temperature reduction feedwater heaters out-of-service feedwater controller failure ICF increased core flow LFWH LHGR LHGRFACj LHGRFACp LOCA LPRM LRNB MAPLHGR MAPFACf MAPFACp MCPR MCPRf MCPRp MELLLA MSIV MSRVOOS loss of feedwater heating linear heat generation rate flow-dependent linear heat generation rate factors power-dependent linear heat generation rate factors loss-of-coolant accident local power range monitor load rejection no bypass maximum average planar linear heat generation rate flow-dependent maximum average planar linear heat generation rate factors power-dependent maximum average planar linear heat generation rate factors minimum critical power ratio flow-dependent minimum critical power ratio power-dependent minimum critical power ratio maximum extended load line limit analysis main steam isolation valve main steam relief valves out-of-service AREVA NP Inc.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page vi Nomenclature (Continued)
NEOC near end of cycle NRC Nuclear Regulatory Commission, U.S.
NSS nominal scram speed OLMCPR operating limit minimum critical power ratio 0OS out of service OPRM oscillation power range monitor PAPT protection against power transient PCT peak clad temperature PLUOOS power load unbalance out-of-service RBM rod block monitor RNW reduced notch worth RPT recirculation pump trip SER safety evaluation report SLC standby liquid control (boron)
SLCSDM standby liquid control shutdown margin (boron)
SLMCPR safety limit minimum critical power ratio SLO single-loop operation TBVOOS turbine bypass valves out-of-service TIP traversing in-core probe TIPOOS traversing in-core probe out-of-service TLO two-loop operation TSSS technical specification scram speed UFSAR updated final safety analysis report ACPR change in critical power ratio AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 1-1 1.0 Introduction This report provides results of analyses performed by AREVA NP, Inc.* as part of the reload analysis. This report is intended to be used in conjunction with the AREVA topical Report XN-NF-80-1 9(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, which describes the analyses performed in support of this reload, identifies the methodology used for those analyses, and provides a generic reference list. Section numbers in this report are the same as corresponding section numbers in XN-NF-80-19(P)(A) Volume 4 Revision 1. Methodology used in this report which supersedes XN-NF-80-19(P)(A) Volume 4 Revision 1 is referenced in Section 8.0. The application of the methodology used in the computer codes that were utilized in performing the analyses presented in this report were applied in accordance with the NRC technical limitations (safety evaluation report (SER) restrictions) as stated in the methodology.
The core consists of a total of 764 fuel assemblies, including 374 unirradiated ATRIUM T-10t assemblies, 279 irradiated ATRIUM-10 assemblies and 111 irradiated GE14 assemblies. The reference core configuration is described in Section 4.2.
The effects of channel bow are explicitly accounted for in the safety limit analysis. The Extended Operating Domain (EOD) and Equipment Out-Of-Service (EOOS) conditions presented in Table 1.1 are supported.
AREVA NP Inc. is an AREVA and Siemens company.
t ATRIUM is a trademark ofAREVA NP.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 1-2 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased core flow (ICF)
Maximum extended load line limit analysis (MELLLA)
Combined FFTR/coastdown Equipment Out-of-Service (EOOS) Conditions*
Turbine bypass valves out-of-service (TBVOOS)
EOC recirculation pump trip out-of-service (EOC-RPT-OOS)
Feedwater heaters out-of-service (FHOOS)
Power load unbalance out-of-service (PLUOOS)
Combined EOC-RPT-OOS and TBVOOS Combined EOC-RPT-OOS and FHOOS Combined EOC-RPT-OOS and PLUOOS Combined TBVOOS and FHOOS Combined TBVOOS and PLUOOS Combined FHOOS and PLUOOS Combined EOC-RPT-OOS, TBVOOS, and FHOOS Combined EOC-RPT-OOS, TBVOOS, and PLUOOS Combined EOC-RPT-OOS, FHOOS, and PLUOOS Combined TBVOOS, FHOOS, and PLUOOS Combined EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Single-loop operation (SLO)
SLO may be combined with all of the other EOOS conditions. Base case and each EOOS condition is supported in combination with 1 MSRVOOS, up to 2 TIPOOS or the equivalent number of channels (per operating requirements defined in Reference 9.6 Section 3.2), andlor up to 50% of the LPRMs out-of-service.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 2-1 2.0 Fuel Mechanical Design Analysis Applicable AREVA Fuel Design Reports References 9.12 and 9.16 To assure the power history for the ATRIUM-1 0 fuel is bounded by the assumed power history in the fuel mechanical design analyses, LHGR operating limits have been specified in Section 7.2.3. In addition, ATRIUM-10 LHGR limits for Abnormal Operational Transients (AOTs) have been specified in References 9.12 and 9.16 (AOT is equivalent to anticipated operational occurrences used in References 9.12 and 9.16). The exposure limits for the ATRIUM-10 bundles are specified in References 9.12 and 9.16.
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Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 3-1 3.0 Thermal-Hydraulic Design Analysis 3.2 Hydraulic Characterization 3.2.1 Hydraulic Compatibility Hydraulic demand curves for ATRIUM-1 0 and GE fuel are provided in Reference 9.1, Figures 3.2, 3.3, and 3.4. All thermal-hydraulic compatibility criteria have been met.
3.2.3 Fuel Centerline TemDerature Applicable Reports ATRIUM-10 References 9.12 and 9.16, Figure 3.2 3.2.5 Bypass Flow Calculated Bypass Flow Fraction at 100%P/100%F 14.5%
(includes water channel flow) 3.3 MCPR Fuel Cladding Integrity Safety Limit (SLMCPR)
Two-Loop Operation*
Single-Loop Operation*
1.08 1.10 Reference 9.6 3.3.1 Coolant Thermodynamic Condition Thermal Power (at SLMCPR)t Feedwater Flow Rate (at SLMCPR)
Steam Dome Pressure (at rated conditions)
Feedwater Temperature 5586.05 MWt 23.20 Mlbm/hr 1050 psia 394.80F Includes the effects of channel bow, 2 TIPOOS or the equivalent number of TIP channels (per operating requirements defined in Reference 9.6 Section 3.2), a 2500 EFPH LPRM calibration interval, and up to 50% of the LPRMs out of service
" Thermal power at SLMCPR is specific to SLMCPR methodology (Reference 8.2). The methodology increases ("pushes") the core power to reach the SLMCPR.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 3-2 3.4 Licensing Power and Exposure Shape The licensing axial power profile used by AREVA for the plant transient analyses bounds the projected end of full power (EOFP) axial power profile. The conservative licensing axial power profile as well as the corresponding axial exposure ratio are given in Table 3.1. Future projected cycle power profiles are considered to be in compliance when the EOFP normalized power generated in the core is greater than the licensing axial power profile at the given state conditions when the comparison is made over the bottom third of the core height.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 3-3 Table 3.1 Licensing Basis Core Average Axial Power Profile and Licensing Axial Exposure Ratio State Conditions for Power Shape Evaluation Power, MWt 3952.0 Core pressure, psia 1064.7 Inlet subcooling, Btu/Ibm
-27.75 Flow, Mlb/hr 107.62 Control state ARO Core average exposure 31,075 (EOFPL + 15 EFPD), MWd/MTU Licensing Axial Power Profile (Normalized)
Node Power Top 25 0.202 24 0.624 23 0.816 22 0.938 21 1.032 20 1.102 19 1.157 18 1.207 17 1.251 16 1.342 15 1.375 14 1.405 13 1.399 12 1.37 11 1.319 10 1.252 9
1.174 8
1.084 7
0.992 6
0.903 5
0.829 4
0.776 3
0.718 2
0.576 Bottom 1 0.157 Licensing Axial Exposure Ratio (EOFP + 15 EFPD, ARO)
Average Bottom 8 ft/12 ft = 1.0505 AREVA NP Inc.
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Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 4-1 4.0 Nuclear Design Analysis 4.1 Fuel Bundle Nuclear Design Analysis The fuel cycle design used as the basis for the reload analysis is described in Reference 9.3.
The core composition is presented in Table 4.1 and Figure 4.1. The detailed fuel bundle design information for the fresh ATRIUM-10 fuel is provided in Reference 9.2. The following summary provides the appropriate cross-reference.
Assembly Average Enrichment (ATRIUM-1 0 fuel)
Al0-4227B-15GV80-FBB (FT2)* 4.23 wt%
Al 0-4239B-1 5GV80-FBB (FT3) 4.24 wt%
A10-3552B-1OGV80-FBB (FT4) 3.55 wt%
Radial Enrichment Distribution (enriched lattices only)
AlOB-4545L-15G80-FBB A103B-4555L-13G80-2CGU495-FBB A1OT-4414L-12G80-3CGU495-FBB Al OT-4415L-12G50-3CGU495-FBB AlOB-4545L-15G80-FBB Al OB-4555L-1 3G80-2CGU495-FBB A1OT-4454L-1G80-4CGU495-FBB A1OT-4454L-1 1G50-4CGU495-FBB AlOB-3698L-10G80-FBB Al OB-3937L-8G80-2CGU495-FBB Reference 9.2, Figure D.2 Reference 9.2, Figure D.3 Reference 9.2, Figure D.4 Reference 9.2, Figure D.5 Reference 9.2, Figure D.8 Reference 9.2, Figure D.9 Reference 9.2, Figure D.10 Reference 9.2, Figure D.11 Reference 9.2, Figure D.14 Reference 9.2, Figure D.15 Reference 9.2, Figures 2.1-2.3 Reference 9.2, Figures 2.4-2.6 Reference 9.2, Figures 2.4-2.6 Axial Enrichment Distribution Burnable Absorber Distribution Non-Fueled Rods Neutronic Design Parameters Fuel Storage Spent Fuel Storage Pool Table 4.3 Reference 9.4 The BFE2-15 reload batch fuel design meets the criticality safety limitations defined in Table 2.1 of Reference 9.4 and therefore can be safely stored in the pool.
New Fuel Storage Vault Reference 9.14 See Figure 4.1 for fuel type definitions.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 4-2 The BFE2-15 reload batch can be safely stored in the new fuel storage vault per the criticality safety limits defined in Table 2.1 of Reference 9.14.
Shipping Container References 9.19 and 9.20 The BFE2-15 reload assemblies conform to the nuclear criticality requirements established for the RAJ-11 shipping container in Reference 9.19. Satisfying the Reference 9.19 requirements ensures that the BFE2-15 fuel design may be stacked according to the constraints of the RAJ-I1 shipping container stacking analysis provided in Reference 9.20.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 4-3 4.2 Core Nuclear Design Analysis 4.2.1 Core Configuration Figure 4.1 Core Exposure at EOC 14, MWd/MTU 33,526 (nominal value)
Core Exposure at EOC 14, MWd/MTU 32,989 (short window)
Core Exposure at BOC 15, MWd/MTU 12,388 (from nominal EOC 14)
Core Exposure at NEOC,* MWd/MTU (from nominal EOC 14) 27,788 Core Exposure at EOC (EOFPL + 15 EFPD),t MWd/MTU (from nominal EOC 14) 31,075 Maximum Core Exposure,* MWd/MTU 32,274 4.2.2 Core Reactivity Characteristics' **
BOC 15 cold k-eff, all rods out 1.1295 BOC 15 cold k-eff, all rods in 0.9657 BOC 15 cold k-eff, strongest rod out 0.9900 BOC 15 cold shutdown margin 1.00% Ak/k Reactivity defect/R-value 0.00% Ak/k (minimum at 0.00 MWd/MTU cycle exposure)
Standby liquid control (SLC)1t system reactivity, 816 ppm at 3660F (equivalent to 720 ppm boron at 68°F)*
e Maximum k-eff 0.9783 Minimum SLCSDM 2.17% Ak/k NEOC analyses and limits are applicable up to this core exposure.
EOC analyses and limits are applicable up to this core exposure.
FFTREcoastdown analyses and limits are applicable up to this core exposure.
k-eff data are bias corrected. Bias corrected k=1 +[k(MCB2)-k(target)].
- Evaluated based on short window.
t A minimum SLCSDM of 0.88% Ak/k is required to protect manufacturing and calculational uncertainties when analyzed at temperature of RHR initialization.
STVA Browns Ferry SLC licensing basis documents indicate a minimum of 720 ppm boron at a temperature of 70°F. The AREVA cold analysis basis of 68°F represents a negligible difference and the results are adequate to protect the 70°F licensing basis for the plant.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 4-4 4.2.4 Core Hydrodynamic Stability Browns Ferry has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM). Reload validation has been performed in accordance with Reference 9.9. The stability based Operating Limit MCPR (OLMCPR) is provided for two conditions as a function of OPRM amplitude setpoint in Table 4.2. The two conditions evaluated are for a postulated oscillation at 45% core flow steady state operation (SS) and following a two recirculation pump trip (2PT) from the limiting full power operation state point. Current power and flow dependent limits provide adequate protection against violation of the Safety Limit MCPR for postulated reactor instability as long as the operating limit is greater than or equal to the specified value for the selected OPRM setpoint.
Evaluations by General Electric have shown that the generic DIVOM curves specified in NEDO-32465-A, may not be conservative for current plant operating conditions for plants which have implemented Stability Option I1l. Specifically, a non-conservative deficiency has been identified for high peak bundle power-to-flow ratios in the generic regional mode DIVOM curve. The deficiency results in a non-conservative slope of the associated DIVOM curve so that the Option III trip setpoint is too high. GE issued a Part 21 Notification in GE 10 CFR Part 21 Notification, Stability Reload Licensing Calculations Using Generic DIVOM Curve, MFN 01-046, August 31, 2001.
To address this issue related to the generic DIVOM slope, AREVA has performed calculations for the relative change in AMCPR as a function of the calculated hot channel oscillation magnitude (HCOM). These calculations have been performed with the RAMONA5-FA code.
This code is a coupled neutronic-thermal hydraulic three-dimensional transient model for the purpose of determining relationship between the relative change in AMCPR and the HCOM on a plant specific basis. This model has been developed consistent with the recommendations of the BWROG in OG04-0153-260, Plant-Specific Regional Mode DIVOM Procedure Guideline, June 15, 2004. The generation of the plant-specific DIVOM data with this model is consistent with the BWROG resolution of the above Part 21 notification as provided in BWROG-03047, Resolution of Reportable Condition for Stability Reload Licensing Calculations Using Generic Regional Mode DIVOM Curve, September 30, 2003.
The stability-based OLMCPRs were calculated using the most limiting calculated change in relative AMCPR for a given oscillation magnitude. The reload validation calculation AREVA NP Inc.
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ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 4-5 demonstrated that reactor stability does not produce the limiting OLMCPR as long as the selected OPRM setpoint produces values for OLMCPR(SS) and OLMCPR(2PT) that are less than the corresponding acceptance criteria.
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Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 4-6 Table 4.1 Core Composition Cycle Number of Fuel Description Loaded Assemblies GE-14 P1ODNAB416-16GZ 13 6
GE-14 PIODNAB416-16GZ 13 90 GE-14 PlODNAB416-18GZ 13 8
GE-14 PIODNAB417-18GZ 13 7
ATRIUM-10 A10-3920B-14GV70 14 279 ATRIUM-10 A10-4227B-15GV80-FBB 15 206 ATRIUM-10 Al 0-4239B-1 5GV80-FBB 15 112 ATRIUM-10 A10-3552B-10GV80-FBB 15 56 AREVA NP Inc.
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Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 4-7 Table 4.2 OPRM Setpoint Versus Stability-Based MCPR Operating Limits BOC to FFTR / Coastdown OPRM Setpoint A(SP) 1.05 1.06 1.07 1.08 1.09 1.10 1.11 1.12 1.13 1.14 1.15 OLMCPR (SS) 1.17 1.19 1.21 1.23 1.25 1.27 1.29 1.31 1.33 1.35 1.37 OLMCPR (2PT) 1.11 1.13 1.14 1.16 1.18 1.20 1.22 1.24 1.26 1.28 1.30 Rated Power OLMCPR as described in Section 5 Acceptance Off-rated Accptace OLMCPR Criteria Flow
@45% Flow AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 4-8 Table 4.3 Neutronic Design Values Number of fuel assemblies 764 Rated thermal power,* MVVW 3952 Rated core flow,* Mlbm/hr 102.5 Fuel channel dimensions Comer thickness, inch 0.100 Reduced thickness, inch 0.075 Fuel assembly pitch, inch 6.0 Wide water gap thickness, inch 0.630 Narrow water gap thickness, inch 0.414 Control Bladest Total span, inch 9.810 Total support span, inch 1.580 Total thickness, inch 0.312 Total face-to-face internal dimension, inch 0.200 B4C rod absorber Number of rods 21 Rod diameter ID/OD, inch 0.138 /0.188 Theoretical density of 84C, %
70 Statepoint parameters for individual solutions are based on consistent heat balance calculations for the core power and flow prescribed for the condition being modeled.
t The control rod data represent the Duralife-1 ODD/BVWR-4 blade type.
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17.6 26 38.6 33 1
20.9 2
0.0 1
21.1 2
0.0 1
19.4 2
0.0 1
18.9 2
0.0 1
21.6 3
0.0 4
0.0 2
0.0 4
0.0 3
0.0 25 38.8 35 2
0.0 1
21.0 2
0.0 1
21.6 2
0.0 1
21.9 2
0.0 1
20.5 2
0.0 1
21.5 3
0.0 1
21.3 3
0.0 1
14.1 26 25.3 37 1
21.4 2
0.0 1
21.5 2
0.0 1
20.8 2
0.0 1
19.6 2
0.0 1
20.0 2
0.0 4
0.0 3
0.0 4
0.0 3
0.0 30 41.4 39 2
0.0 1
19.4 2
0.0 1
20.9 2
0.0 1
20.8 2
0.0 1
20.4 2
0.0 1
21.4 3
0.0 26 26.5 3
0.0 1
21.2 30 41.5 41 1
21.0 2
0.0 1
21.6 2
0.0 1
20.7 2
0.0 1
21.3 2
0.0 1
21.8 3
0.0 4
0.0 2
0.0 4
0.0 1
17.4 26 35.4 43 2
0.0 1
18.9 2
0.0 1
19.6 2
0.0 1
21.5 2
0.0 1
21.6 2
0.0 1
22.2 3
0.0 1
20.6 3
0.0 1
21.7 26 40.2 45 1
21.1 2
0.0 1
20.2 2
0.0 1
20.6 2
0.0 1
21.6 2
0.0 1
20.6 2
0.0 4
0.0 3
0.0 26 29.7 26 33.5 47 2
0.0 1
22.0 2
0.0 1
20.1 2
0.0 1
21.7 2
0.0 1
20.5 2
0.0 1
13.7 3
0.0 1
18.1 29 39.8 49 1
20.3 3
0.0 1
21.3 2
0.0 1
21.5 3
0.0 1
22.1 2
0.0 1
13.8 2
0.0 1
22.1 26 36.3 26 38.3 51 2
0.0 4
0.0 3
0.0 4
0.0 3
0.0 4
0.0 3
0.0 4
0.0 3
0.0 1
21.8 26 28.2 53 1
21.6 2
0.0 1
21.5 3
0.0 26 26.5 2
0.0 1
20.7 3
0.0 1
17.9 26 34.5 55 3
0.0 4
0.0 3
0.0 4
0.0 3
0.0 4
0.0 3
0.0 26 27.4 26 39.2 25 38.9 57 1
17.6 3
0.0 1
13.9 3
0.0 1
15.1 1
17.6 1
21.8 26 36.6 59 26 36.4 30 41.5 26 25.6 26 38.3 30 41.5 26 35.8 26 40.1 Nuclear Fuel Type BOC Exposure (OWd/MTU)
Fuel Type Description Cycle Loaded No. Per Lower Right-hand Quadrant 25 26 29 30 1
2 3
4 GE14-PlOrNAB416-16GZ 13 2
GE14-PlO*AB416-16GZ 13 20 GE14-PlOrNAB416-18GZ 13 1
GE14-PlONAB417-18GZ 13 4
A10-3920B-14GV70 14 70 A10-4227B-15GV80-FBB 15 52 A10-4239B-15GV80-FBB 15 28 A10-3552B-10GVO-FBB 15 14 Figure 4.1 Lower Right Quarter Core Layout By Fuel Type AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-1 5.0 Abnormal Operational Transients Applicable Disposition of Events Reference 9.5 5.1 Analysis of Plant Transients at Rated Power Conditions Reference 9.6 Limiting Transients:
Load Rejection No Bypass (LRNB)
Turbine Trip No Bypass (TTNB)
Feedwater Controller Failure (FVVCF)
Loss of Feedwater Heating (LFWH)t Control Rod Withdrawal Error (CRWE), see Section 5.5 5.1.1 NEOC Licensing Exposure Peak Peak Neutron Heat Scram Flux Flux ACPR Transient Speed (% Rated)
(% Rated)
ATRIUM-l0 I GE14 LRNB*
TSSS 304 116
.31/.31 TTNB*
TSSS 307 116
.31 /.31 FVVCF*
TSSS 299 120
.33 /.33 LRNB*
NSS 273 114
.28/.28 TTNB*
NSS 274 114
.29/.28 FWCF*
NSS 278 118
.30/.30 LFWHt
.10/.10 The results presented are based on base case operation at I 00%P/1 05%F and are the most limiting considering earlier exposures.
t The inadvertent HPCI pump startup event (including asymmetric injection effects) has been analyzed generically for Browns Ferry and has been determined to be nonlimiting (Reference 9.5). The EPU inadvertent HPCI pump startup analysis demonstrated that the event did not reach the level 8 trip setpoint (with sufficient margin); therefore, the event does not result in a turbine trip and the resulting pressurization transient.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-2 5.1.2 EOC Licensing Exposure Peak Peak Neutron Heat Scram Flux Flux ACPR Transient Speed
(% Rated)
(% Rated)
ATRIUM-1 I GE14 LRNB*
TSSS 355 120
.32 /.31 TTNB*
TSSS 360 121
.32 /.31 FWCF*
TSSS 348 124
.33/.33 LRNB*
NSS 326 119
.30/.30 TTNB*
NSS 330 120
.31 /.30 FVCF*
NSS 327 123
.31 /.31 LFWHt
.10/.10 5.1.3 FFTR/Coastdown Licensing Exposure Peak Peak Neutron Heat Scram Flux Flux ACPR Transient Speed (% Rated)
(% Rated)
ATRIUM-10 GEI4 LRNB*
TSSS 355 121
.32 /.31 TTNB*
TSSS 360 122
.32 /.31 FWCF*
TSSS 353 128
.33 /.33 LRNB*
NSS 326 120
.30/.30 TTNB*
NSS 330 120
.31/.30 FWCF*
NSS 351 127
.32 /.31 LFWHt
.10/.10 The results presented are based on base case operation at I 00%PI1 05%F and are the most limiting considering earlier exposures.
The inadvertent HPCI pump startup event (including asymmetric injection effects) has been analyzed generically for Browns Ferry and has been determined to be nonlimiting (Reference 9.5). The EPU inadvertent HPCI pump startup analysis demonstrated that the event did not reach the level 8 trip setpoint (with sufficient margin); therefore, the event does not result in a turbine trip and the resulting pressurization transient.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-3 Reference 9.6 5.2 Analysis for Reduced Flow Operation Limiting Transient: Slow Flow Excursion MCPRf-ATRIUM-1o0, and GE14 Fuel Tables 5.1 and 5.2 Reference 9.6 Figures 2.1 and 2.2 LHGRFACf - ATRIUM-10 Fuel Table 5.3 Reference 9.6 Figure 2.3 MAPFACf - GE14 Fuel Table 5.4 Reference 9.6 Figure 2.4 MCPRf, LHGRFACi, and MAPFACf results are applicable at all cycle exposures and in all EOD and EOOS scenarios presented in Table 1.1.
5.3 Analysis for Reduced Power Operation Limiting Transients:
Load Rejection No Bypass (LRNB)
Turbine Trip No Bypass (TTNB)
Feedwater Controller Failure (FWCF)
MCPRp Base Case and EOOS Operation Referer LHGRFACp and MAPFACp All Conditions Referer Reference 9.6 Tables 5.5 - 5.10 ice 9.6 Sections 3.0 and 4.0 Table 5.11 ice 9.6 Sections 3.0 and 4.0 AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 5-4 5.4 ASME Overpressurization Analysis Reference 9.6 Limiting Event MSIV Closure Worst Single Failure Valve Position Scram Maximum Vessel Pressure (Lower Plenum) 1345 psig Maximum Steam Dome Pressure 1317 psig 5.5 Control Rod Withdrawal Error The CRWE event was analyzed assuming no xenon and credible instrumentation out-of-service in the rod block monitor (RBM) system. The analysis further assumes that the plant could be operating in either an A or B sequence control rod pattern.
The rated power CRWE results are shown in Table 5.12. For the analytical RBM high power setpoint values of 107% to 117% and all intermediate and lower power setpoint values, the MCPRp values for ATRIUM-10 and GE14 fuel bound or are equal to the CRWE MCPR values.
The MCPR values are based on an SLMCPR of 1.08. For other values of SLMCPR the CRWE MCPR can be adjusted by the difference in the SLMCPR and 1.08. AREVA analyses show that the filtered RBM setpoint reductions given in Reference 9.15 are supported.
The ATRIUM-10 fuel design meets the 1% plastic strain and centerline melt criteria by not exceeding the protection against power transient (PAPT) LHGR limit during the event (References 9.12 and 9.16). The co-resident fuel has also been evaluated to remain below its transient LHGR limit.
The recommended operability requirements based on the generic unblocked CRWE results are shown in Table 5.13 based upon'the SLMCPR values of Section 3.3. For other values of SLMCPR, the MCPR in Table 5.13 can be adjusted by the ratio of the SLMCPR values. For Cycle 15, the CRWE results at all power levels are equal to or bounded by the MCPRp values given in Tables 5.5 - 5.10.
5.6 Fuel Loading Error (Infrequent Event)
As described in the AREVA topical report XN-NF-80-19(P)(A) Volume 4 Revision 1, the Fuel Loading error is characterized as an Infrequent Event and the acceptance criteria is that the offsite dose consequences due to the event shall not exceed a small fraction of the 10 CFR 50.67 limits.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 5-5 5.6.1 Mislocated Fuel Assembly AREVA has performed a bounding fuel mislocation error analysis and has demonstrated continued applicability of the bounding results. This analysis evaluated the impact of a mislocated assembly against potential fuel rod failure mechanisms due to increased LHGR and reduced CPR. Based on these analyses, the offsite dose criteria (a small fraction of 10 CFR 50.67) is conservatively satisfied. Since no rod LHGR would exceed the transient LHGR limit, and since less than 0.1% of the fuel rods are expected to experience boiling transition which could result in a dryout induced failure, a dose consequence evaluation is not necessary.
5.6.2 Misoriented Fuel Bundle AREVA has performed a bounding fuel assembly misorientation analysis. The analysis was performed assuming that the limiting assembly was loaded in the worst orientation (rotated 1800) while producing sufficient power to be on the MCPR limit if it had been oriented correctly.
The analyses demonstrate that the small fraction of 10 CFR 50.67 offsite dose criteria is conservatively satisfied. A dose consequence evaluation is not necessary since less than 0.1%
of the fuel rods are expected to experience boiling transition and the change in LHGR for the misoriented assembly remains below the transient LHGR limit.
5.7 Determination of Thermal Margins The results of the analyses presented in Sections 5.1-5.3 and 5.5 are used for the determination of the MCPR and LHGR operating limits. Section 5.1 provides the results of analyses at rated conditions. Section 5.2 provides for the determination of the MCPRf and LHGRr limits at reduced flow (MCPRf, Tables 5.1-5.2, LHGRFACf/MAPFACf, Tables 5.3-5.4).
Section 5.3 provides for the determination of the MCPRp limits and LHGRFACýIMAPFACp at conditions of reduced power (Tables 5.5-5.11). Exposure dependent limits are presented for base case operation and the EOOS conditions presented in Table 1.1. MCPRp limits for single-loop operation (SLO) will be 0.02 higher than those for two-loop because the SLO SLMCPR is 0.02 higher.
TLO MCPRf limits and LHGRFACi and MAPFACf multipliers are applicable for SLO without any adjustment. The flow-dependent limits are based on a slow flow excursion of two recirculation loops for TLO, which is conservative relative to a single recirculation loop excursion that could occur in SLO.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 5-6 For SLO operation, the MAPLHGR multiplier listed in Section 7.2.1 is applied to ATRIUM-1 0 fuel. For GE fuel, the SLO MAPLHGR limits are determined from the most limiting of the MAPFACp, MAPFACt, and SLO MAPLHGR multipliers. It is not necessary to apply the SLO multiplier from Section 7.2.1 if the MAPFAC corrections are more limiting.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 5-7 Table 5.1 Flow-Dependent MCPR Limits for Maximum Flow of 102.5% of Rated Flow Core Flow MCPRf MCPRI
(% of rated)
ATRIUM-10 GE14 30 1.37 1.37 72 1.21 1.21 102.5 1.21 1.21 Table 5.2 Flow-Dependent MCPR Limits for Maximum Flow of 107% of Rated Flow Core Flow MCPRr
- MCPR,
(% of rated)
ATRIUM-10 GE14 30 1.40 1.40 78 1.21 1.21 107 1.21 1.21 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-8 Table 5.3 ATRIUM-10 Flow-Dependent LHGRFACf Multipliers for Maximum Flow of 102.5% and 107% of Rated Flow Maximum Core Flow of Maximum Core Flow of 102.5% Rated 107% Rated Core Flow Core Flow
(% of rated)
LHGRFACf
(% of rated)
LHGRFACf 30 0.97 30 0.95 37.3 1.00 41.7 1.00 102.5 1.00 107 1.00 Table 5.4 GE14 Flow-Dependent MAPFACf Multipliers for Maximum Core Flow of 102.5% and 107% of Rated Flow Maximum Core Flow of Maximum Core Flow of 102.5% Rated 107% Rated Core Flow Core Flow
(% of rated)
MAPFACf
(% of rated)
MAPFACf 30 0.61 30 0.59 72 1.00 75 1.00 102.5 1.00 107 1.00 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-9 Table 5.5 MCPRp Limits for NSS Insertion Times BOC to NEOC*
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.38 1.38 60.0 1.58 1.62 55.0 1.61 1.64 50.0 1.69 1.73 50.0 1.78 1.78 Baerase 40.0 1.85 1.89 operation 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at - 50%F 2.63 2.83 100.0 1.42 1.42 60.0 1.62 1.66 55.0 1.65 1.67 50.0 1.71 1.75 50.0 1.78 1.78 TBVOOS 40.0 1.85 1.90 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at < 50%F 2.64 2.79 23.0 at < 50%F 2.88 3.07 100.0 1.38 1.38 60.0 1.58 1.62 55.0 1.61 1.64 50.0 1.69 1.73 50.0 1.78 1.78 EOC-RPT-OOS 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.66 1.70 50.0 1.75 50.0 1.78 1.79 FHOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at 5 50%F 2.60 2.79 1 23.0 at S 50%F 2.75 2.96 Limits support operation with any combination of I MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis AREVA NP Inc.
ANP-2541 Revision 0 Page 5-10 Table 5.5 MCPRp Limits for NSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.38 1.38 60.0 1.58 1.62 55.0 1.73 1.73 50.0 50.0 1.78 1.78 PLUOOS 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.42 1.42 60.0 1.62 1.66 55.0 1.65 1.67 50.0 1.71 1.75 50.0 1.78 1.78 andRT-OOS 40.0 1.85 1.90 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at < 50%F 2.64 2.79 23.0 at 5 50%F 2.88 3.07 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.66 1.70 50.0 1.75 50.0 1.78 1.79 and FHOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at<5 50%F 2.75 2.96 100.0 1.38 1.38 60.0 1.58 1.62 55.0 1.73 1.73 50.0 50.0 1.78 1.78 and PLUOOS 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-11 Table 5.5 MCPRp Limits for NSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.78 1.81 TBVOOS 40.0 1.92 1.98 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at < 50%F 2.72 2.88 23.0 at < 50%F 2.97 3.18 100.0 1.42 1.42 60.0 1.62 1.66 55.0 1.73 1.73 50.0 50.0 1.78 1.78 TdVOOS 40.0 1.85 1.90 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at s 50%F 2.64 2.79 23.0 at < 50%F 2.88 3.07 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.73 1.73 50.0 50.0 1.78 1.79 and PLUOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at:> 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at S 50%F 2.60 2.79 23.0 at S 50%F 2.75 2.96 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.68 1.72.
50.0 1.77 EOC-RPT-OOS, 50.0 1.78 1.81
- TBVOOS, 40.0 1.92 1.98 and FHOOS 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at -< 50%F 2.72 2.88 1 23.0 at -< 50%F 2.97 3.18 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-12 Table 5.5 MCPRp Limits for NSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl 4 Condition
(% of rated)
Fuel Fuel 100.0 1.42 1.42 60.0 1.62 1.66 55.0 1.73 1.73 50.0 EOC-RPT-OOS, 50.0 1.78 1.78
- TBVOOS, 40.0 1.85 1.90 and PLUOOS 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at < 50%F 2.64 2.79 23.0 at < 50%F 2.88 3.07 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.73 1.73 50.0 EOC-RPT-OOS, 50.0 1.78 1.79
- FHOOS, 40.0 1.90 1.97 and PLUOOS 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at> 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.73 1.73 50.0
- TBVOOS, 50.0 1.78 1.81
- FHOOS, 40.0 1.92 1.98 and PLUOOS 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at < 50%F 2.72 2.88 23.0 at < 50%F 2.97 3.18 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.73 1.73 50.0 EOC-RPT-OOS, 50.0 1.78 1.81
- TBVOOS, 40.0 1.92 1.98
- FHOOS, 26.0 2.35 2.49 and PLUOOS 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at < 50%F 2.72 2.88 23.0 at < 50%F 2.97 3.18 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-13 Table 5.6 MCPRp Limits for TSSS Insertion Times BOC to NEOC*
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.41 1.41 60.0 1.59 1.65 55.0 1.63 1.66 50.0 1.71 1.75 50.0 1.79 1.79 operation 40.0 1.86 1.91 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.44 1.45 60.0 1.64 1.65 55.0 1.66 1.69 50.0 1.73 1.78 50.0 1.79 1.79 TBVOOS 40.0 1.87 1.93 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at < 50%F 2.65 2.79 23.0 at < 50%F 2.88 3.08 100.0 1.41 1.41 60.0 1.59 1.65 55.0 1.63 1.66 50.0 1.71 1.75 50.0 1.79 1.79 EOC-RPT-OOS 40.0 1.86 1.91 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at - 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.79 1.81 FHOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-14 Table 5.6 MCPRp Limits for TSSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.41 1.41 60.0 1.59 1.65 55.0 1.74 1.74 50.0 50.0 1.79 1.79 PLUOOS 40.0 1.86 1.91 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at 5 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.44 1.45 60.0 1.64 1.65 55.0 1.66 1.69 50.0 1.73 1.78 50.0 1.79 1.79 andRT-OOS 40.0 1.87 1.93 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at < 50%F 2.65 2.79 23.0 at < 50%F 2.88 3.08 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.79 1.81 and FHOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.41 1.41 60.0 1.59 1.65 55.0 1.74 1.74 50.0 50.0 1.79 1.79 EOC-RPT-OOS 1.86 1.9 adPU S40.0 1.86 1.91 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-15 Table 5.6 MCPRp Limits for TSSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.70 1.74 50.0 50.0 1.79 1.83 and FHOOS 40.0 1.94 2.00 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at < 50%F 2.72 2.88 23.0 at5
<50%F 2.98 3.18 100.0 1.44 1.45 60.0 1.64 1.65 55.0 1.74 1.74 50.0 50.0 1.79 1.79 and PLUOOS 40.0 1.87 1.93 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at < 50%F 2.65 2.79 23.0 at < 50%F 2.88 3.08 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.74 1.74 50.0 50.0 1.79 1.81 FHOOS 40.0 1.92 1.99 and PLUOOS 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.70 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.83
- TBVOOS, 40.0 1.94 2.00 and FHOOS 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at - 50%F 2.72 2.88 1 23.0 at5 -50%F 2.98 3.18 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-16 Table 5.6 MCPRp Limits for TSSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.44 1.45 60.0 1.64 1.65 55.0 1.74 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.79
- TBVOOS, 40.0 1.87 1.93 and PLUOOS 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at s 50%F 2.65 2.79 23.0 at S 50%F 2.88 3.08 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.74 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.81
- FHOOS, 40.0 1.92 1.99 and PLUOOS 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at S 50%F 2.60 2.79 23.0 at S 50%F 2.75 2.96 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.74 1.74 50.0
- TBVOOS, 50.0 1.79 1.83
- FHOOS, 40.0 1.94 2.00 and PLUOOS 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at < 50%F 2.72 2.88 23.0 at5 s50%F 2.98 3.18
.100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.74 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.83
- TBVOOS, 40.0 1.94 2.00 and PLUOOS 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at < 50%F 2.72 2.88 1 23.0 at:< 50%F 2.98 3.18 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-17 Table 5.7 MCPRp Limits for NSS Insertion Times BOC to EOC*
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.39 1.39 60.0 1.58 1.62 55.0 1.61 1.64 50.0 1.69 1.73 50.0 1.78 1.78 operation 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at s 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.43 1.43 60.0 1.62 1.66' 55.0 1.65 1.67 50.0 1.71 1.75 50.0 1.78 1.78 TBVOOS 40.0 1.85 1.90 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at < 50%F 2.64 2.79 23.0 at - 50%F 2.88 3.07 100.0 1.39 1.39 60.0 1.58 1.62 55.0 1.61 1.64 50.0 1.69 1.73 50.0 1.78 1.78 EOC-RPT-OOS 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at s 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.66 1.70 50.0 1.75 50.0 1.78 1.79 FHOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-18 Table 5.7 MCPRp Limits for NSS Insertion Times BOC to EOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl 4 Condition
(% of rated)
Fuel Fuel 100.0 1.39 1.39 60.0 1.58 1.62 55.0 1.73 1.73 50.0 50.0 1.78 1.78 PLUOOS 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.43 1.43 60.0 1.62 1.66 55.0 1.65 1.67 50.0 1.71 1.75 EOC-RPT-OOS 50.0 1.78 1.78 andRT-OOS 40.0 1.85 1.90 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at < 50%F 2.64 2.79 23.0 at < 50%F 2.88 3.07 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.66 1.70 50.0 1.75 50.0 1.78 1.79 and FHOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.39 1.39 60.0 1.58 1.62 55.0 1.73 1.73 50.0 EOC-RPT-OOS 50.0 1.78 1.78 and PLUOOS 40.0 1.85 1.89 26.0 2.22 2.35 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at S 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis AREVA NP Inc.
ANP-2541 Revision 0 Page 5-19 Table 5.7 MCPRp Limits for NSS Insertion Times BOC to EOC (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.78 1.81 and FHOOS 40.0 1.92 1.98 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at S 50%F 2.72 2.88 23.0 ats 50%F 2.97 3.18 100.0 1.43 1.43 60.0 1.62 1.66 55.0 1.73 1.73 50.0 50.0 1.78 1.78 TBVPUS 40.0 1.85 1.90 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at s 50%F 2.64 2.79 23.0 at < 50%F 2.88 3.07 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.73 1.73 50.0 50.0 1.78 1.79 and PLUMS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F, 2.95 3.15 26.0 at s 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.68 1.72 50.0 1.77 EOC-RPT-OOS, 50.0 1.78 1.81
- TBVOOS, 40.0 1.92 1.98 and FHOOS 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at < 50%F 2.72 2.88 1 23.0 at < 50%F 2.97 3.18 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-20 Table 5.7 MCPRp Limits for NSS Insertion Times BOC to EOC (Continued)
MCPRp Operating Power ATRIUM-10 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.43 1.43 60.0 1.62 1.66 55.0 1.73 1.73 50.0 EOC-RPT-OOS, 50.0 1.78 1.78
- TBVOOS, 40.0 1.85 1.90 and PLUMOS 26.0 2.23 2.36 26.0 at > 50%F 3.09 3.20 23.0 at > 50%F 3.39 3.52 26.0 at < 50%F 2.64 2.79 23.0 at < 50%F 2.88 3.07 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.73 1.73 50.0 EOC-RPT-OOS, 50.0 1.78 1.79
- FHOOS, 40.0 1.90 1.97 and PLUOOS 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.73 1.73 50.0
- TBVOOS, 50.0 1.78 1.81
- FHOOS, 40.0 1.92 1.98 and PLUMOS 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at s 50%F 2.72 2.88 1 23.0 at5 <50%F 2.97 3.18 EOC-RPT-OOS,
- TBVOOS, FHOOS, and PLUOOS 100.0 60.0 55.0 50.0 50.0 40.0 26.0 26.0 at > 50%F 23.0 at > 50%F 26.0 at < 50%F 23.0 at < 50%F 1.44 1.64 1.73 1.78 1.92 2.35 3.19 3.50 2.72 2.97 1.46 1.66 1.73 1.81 1.98 2.49 3.31 3.65 2.88 3.18 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-21 Table 5.8 MCPRp Limits for TSSS Insertion Times BOC to EOC*
MCPRp Operating Power ATRIUM-1 0 GEl 4 Condition
(% of rated)
Fuel Fuel 100.0 1.41 1.41 60.0 1.59 1.65 55.0 1.63 1.66 50.0 1.71 1.75 50.0 1.79 1.79 operation 40.0 1.86 1.91 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.44 1.45 60.0 1.64 1.65 55.0 1.66 1.69 50.0 1.73 1.78 50.0 1.79 1.79 TBVOOS 40.0 1.87 1.93 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at < 50%F 2.65 2.79 23.0 at 50%F 2.64 2179 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.79 1.81 FHOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at - 50%F 2.75 2.96 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-22 Table 5.8 MCPRp Limits for TSSS Insertion Times BOC to EOC (Continued)
MCPRp Operating Power ATRIUM-10 GEI4 Condition
(% of rated)
Fuel Fuel 100.0 1.41 1.41 60.0 1.59 1.65 55.0 1.74 1.74 50.0 50.0 1.79 1.79 PLUOOS 40.0 1.86 1.91 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at _ 50%F 2.63 2.83 100.0 1.46 1.47 60.0 1.64 1.65 55.0 1.66 1.69 50.0 1.73 1.78 50.0 1.79 1.79 and TBVOOS 40.0 1.87 1.93 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at s 50%F 2.65 2.79 23.0 at < 50%F 2.88 3.08 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.79 1.81 and FHOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.41 1.42 60.0 1.59 1.65 55.0 1.74 1.74 50.0 EOC-RPT-OOS 50.0 1.79 1.79 PT-OOS 40.0 1.86 1.91 and PLUOOS 26.0 2.23 2.37 26.0 at > 50%F 2.64 2.79 23.0 at > 50%F 2.82 3.00 26.0 at < 50%F 2.51 2.68 23.0 at < 50%F 2.63 2.83 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-23 Table 5.8 MCPRp Limits for TSSS Insertion Times BOC to EOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.70 1.74 50.0 50.0 1.79 1.83 and FHOOS 40.0 1.94 2.00 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at < 50%F 2.72 2.88 23.0 at < 50%F 2.98 3.18 100.0 1.44 1.45 60.0 1.64 1.65 55.0 1.74 1.74 50.0 50.0 1.79 1.79 adVOOS 40.0 1.87 1.93 26.0 2.25 2.39 26.0 at > 50%F 3.10 3.20 23.0 at > 50%F 3.40 3.52 26.0 at < 50%F 2.65 2.79 23.0 at < 50%F 2.88 3.08 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.74 1.74 50.0 50.0 1.79 1.81 and PLUOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.70 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.83
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-24 Table 5.8 MCPRp Limits for TSSS Insertion Times BOC to EOC (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.46 1.47 60.0 1.64 1.65 55.0 1.74 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.79
- TBVOOS, 50.0 1.79 1.83
- TBVOOS, 40.0 1.94 2.00
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-25 Table 5.9 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown*
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.66 1.70 50.0 1.75 50.0 1.78 1.79 operation 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.78 1.81 TBVOOS 40.0 1.92 1.98 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at < 50%F 2.72 2.88 23.0 at!< 50%F 2.97 3.18 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.66 1.70 50.0 1.75 50.0 1.78 1.79 EOC-RPT-OOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 1 23.0 at < 50%F 2.75 2.96 Limits support operation with any combination of I MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Limits also support operation with FFTRIFHOOS which bounds operation with feedwater heaters in service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis AREVA NP Inc.
ANP-2541 Revision 0 Page 5-26 Table 5.9 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.73 1.73 50.0 50.0 1.78 1.79 PLUOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at 5 50%F 2.60 2.79 23.0 at - 50%F 2.75 2.96 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.68 1.72 50.0 1.77 EOC-RPT-OOS 50.0 1.78 1.81 and TBVOOS 40.0 1.92 1.98 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at < 50%F 2.72 2.88 23.0 at5 <50%F 2.97 3.18 100.0 1.41 1.43 60.0 1.61 1.64 55.0 1.73 1.73 50.0 50.0 1.78 1.79 and PLUOOS 40.0 1.90 1.97 26.0 2.33 2.49 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-27 Table 5.9 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRp Operating Power ATRIUM-1 0 GEl4 Condition
(% of rated)
Fuel Fuel 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.73 1.73 50.0 50.0 1.78 1.81 and PLUOOS 40.0 1.92 1.98 26.0 2.35 2.49 26.0 at > 50%F 3.19 3.31 23.0 at > 50%F 3.50 3.65 26.0 at s 50%F 2.72 2.88 23.0 at5 <50%F 2.97 3.18 100.0 1.44 1.46 60.0 1.64 1.66 55.0 1.73 1.73 50.0 EOC-RPT-OOS, 50.0 1.78 1.81
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-28 Table 5.10 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown*
MCPRp Operating Power ATRIUM-10 GE14 Condition
(% of rated)
Fuel Fuel 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.79 1.81 Baecase 40.0 1.92 1.99 operation 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.70 1.74 50.0 50.0 1.79 1.83 TBVOOS 40.0 1.94 2.00 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at < 50%F 2.72 2.88 23.0 at < 50%F 2.98 3.18 100.0 1.44 1.45 60.0 1.63 1.66 55.0 1.68 1.72 50.0 1.77 50.0 1.79 1.81 EOC-RPT-OOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 1 23.0 at < 50%F 2.75 2.96 Limits support operation with any combination of I MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Limits also support operation with FFTRPFHOOS which bounds operation with feedwater heaters in service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-29 Table 5.10 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRp Operating Power ATRIUM-I 0 GEl 4 Condition
(% of rated)
Fuel Fuel 100.0 1.43 1.45 60.0 1.63 1.66 55.0 1.74 1.74 50.0 50.0 1.79 1.81 PLUOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at> 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 100.0 1.48 1.49 60.0 1.66 1.68 55.0 1.70 1.74 50.0 50.0 1.79 1.83 andETBVOOS 40.0 1.94 2.00 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at 5 50%F 2.72 2.88 23.0 at5 <50%F 2.98 3.18 100.0 1.44 1.46 60.0 1.63 1.66 55.0 1.74 1.74 50.0 50.0 1.79 1.81 and PLUOOS 40.0 1.92 1.99 26.0 2.35 2.51 26.0 at > 50%F 2.75 2.92 23.0 at > 50%F 2.95 3.15 26.0 at < 50%F 2.60 2.79 23.0 at < 50%F 2.75 2.96 AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-30 Table 5.10 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRp Operating Power ATRIUM-10 GEO4 Condition
(% of rated)
Fuel Fuel 100.0 1.46 1.48 60.0 1.66 1.68 55.0 1.74 1.74 50.0 50.0 1.79 1.83 and PLUMS 40.0 1.94 2.00 26.0 2.37 2.52 26.0 at > 50%F 3.20 3.31 23.0 at > 50%F 3.51 3.65 26.0 at < 50%F 2.72 2.88 23.0 ats 50%F 2.98 3.18 100.0 1.48 1.49 60.0 1.66 1.68 55.0 1.74 1.74 50.0 EOC-RPT-OOS, 50.0 1.79 1.83
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 5-31 Table 5.11 LHGRFACp/MAPFACp Multipliers NSSITSSS Insertion Times All Exposures*
Operating Power ATRIUM-10 GE14 Condition
(% of rated)
LHGRFACp MAPFACp 100 1.00 0.98 26 0.64 0.48 Base case 26 at > 50%F 0.51 0.41 operationt 23 at > 50%F 0.48 0.39 26 at < 50%F 0.55 0.46 23 at < 50%F 0.52 0.44 100 1.00 0.98 26 0.64 0.48 EOOS with 26 at > 50%F 0.51 0.41 TBV in-servicet 23 at> 50%F 0.48 0.39 26 at < 50%F 0.55 0.46 23 at < 50%F 0.52 0.44 100 1.00 0.96 26 0.63 0.48 EOOS with 26 at > 50%F 0.45 0.38 TBVOOST 23 at > 50%F 0.41 0.36 26 at < 50%F 0.55 0.43 23 at < 50%F 0.50 0.40 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Base case supports single-loop operation.
t Limits are applicable for all the EOOS scenarios presented in Table 1.1 except those that include TBVOOS.
Limits are applicable for all the EOOS scenarios presented in Table 1.1 including those with TBVOOS.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis AREVA NP Inc.
ANP-2541 Revision 0 Page 5-32 Table 5.12 Control Rod Withdrawal Error MCPR versus RBM Setpoint Results (for Rated Power and 1.08 SLMCPR)
Analytical CRWE RBM MCPR Setpoint (wlo filter)
(%)
107 1.29 111 1.32 114 1.37 117 1.38 Table 5.13 RBM Setpoint Applicability Thermal Power Applicable
(% of rated)
MCPR*
< 1.72 TLO
>27% and < 90%
<1.75 SLO a 90%
< 1.42 TLOt The MCPR values shown correspond to an SLMCPR of 1.08 for TLO and 1.10 for SLO.
t Greater than 90% rated power is not attainable in SLO.
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AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 6-1 6.0 Postulated Accidents 6.1 Loss-of-Coolant Accident 6.1.1 Break Location Spectrum 6.1.2 Break Size Spectrum Reference 9.7 Reference 9.7 6.1.3 MAPLHGR Analyses ATRIUM-10 Fuel: The MAPLHGR limits presented in Reference 9.8 remain valid for ATRIUM-10 fuel.
Limiting Break:
0.5 ft2 split Recirculation Pump Discharge Line Battery (DC) power Based on the PCT results in Reference 9.8 and subsequent evaluations to provide 10 CFR 50.46 reporting estimates (Reference 9.21), the current licensing PCT for ATRIUM-10 fuel is provided below. The MCPR value used in the LOCA analyses for the ATRIUM-10 fuel is less than the rated power MCPR limits presented in Section 5.0.
Maximum PCT (OF)
PCT Impact (OF)
Initial PCT (Reference 9.8)
SPCB coding discrepancy*
Bypass inlet reverse lossl Current Ucensing PCT 2007 2007
+0 2002
-5 2002 The peak local metal-water reaction for the limiting PCT lattice design is 1.71%. The maximum core wide metal-water reaction (for hydrogen generation) for a full ATRIUM-1 0 core is <1.0%.
The PCT for Cycle 15 ATRIUM-10 reload fuel was calculated to be 1969°F; therefore, in terms of PCT, the limiting neutronic design used in Reference 9.8 remains bounding. The peak local metal-water reaction and total core wide metal-water reaction were calculated to be 1.60% and Computer coding discrepancy in the calculation of the SPCB critical power correlation.
Double accounted for leakage paths through the core support plate.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 6-2
<1%, respectively. When compared to the acceptance criteria of less than 17% local cladding oxidation thickness, the local metal-water reaction result remains acceptable.
The plant parameters for the LOCA analysis (Reference 9.7) bound the cycle-specific plant parameters documented in Reference 9.13. The LOCA analysis and results support the EOD and EOOS conditions listed in Table 1.1. Note that the following EOOS conditions have no direct influence on the LOCA events: TBVOOS, EOC-RPT-OOS, PLUOOS, and TIPOOS/LPRM out-of-service.
6.2 Control Rod Drop Accident Browns Ferry Unit 2 uses a banked position withdrawal sequence (BPWS) including reduced notch worth (RNW) rod pulls to limit high worth control rod movements. A CRDA evaluation was performed for both A and B sequence startups consistent with the withdrawal sequence specified by TVA.
The CRDA analysis demonstrates that the maximum deposited fuel rod enthalpy is less than the NRC limit of 280 cal/g (fuel dispersal) and that the estimated number of fuel rods that exceed the fuel damage threshold of 170 cal/g is less than the number of failed rods (850 rods) assumed in the Browns Ferry UFSAR radiological assessment. The inputs to the deposited enthalpy calculation are determined on a cycle specific basis using the methods described in Reference 8.5. Key results from the CRDA analysis are summarized below:
Maximum dropped control rod worth, mk 11.7 Core average Doppler coefficient, Ak/k/F
-10.0 x 10-6 Effective delayed neutron fraction 0.0052 Four-bundle local peaking factor 1.48 Maximum deposited fuel rod enthalpy, cal/g 234.1 Bounding number of rods exceeding 170 cal/g 637 6.4 Fuel and Equipment Handling Accident The fuel handling accident radiological analysis implementing the alternative source term (AST) as approved in Reference 9.17 was performed with consideration of ATRIUM-10 core source terms. The number of failed fuel rods for the ATRIUM-10 fuel as previously provided to TVA in Reference 9.18 for use in the AST analysis is unchanged. No other aspect of utilizing the AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 6-3 ATRIUM-10 fuel affects the current analysis; therefore, the AST analysis remains bounding for the AREVA ATRIUM-10 fuel.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 7-1 7.0 Technical Specifications 7.1 Limiting Safety System Settings 7.1.1 MCPR Fuel Cladding Integrity Safety Limit MCPR Safety Limit (all fuel) - two-loop operation MCPR Safety Limit (all fuel) - single-loop operation 1.08*
1.10*
7.1.2 Steam Dome Pressure Safety Limit Pressure Safety Limit 1325 psig 7.2 Limiting Conditions for Operation 7.2.1 Averaae Planar Linear Heat Generation Ratet Reference 9.8, 9.10 and 9.11 ATRIUM-10 Fuel GE14 Fuel MAPLHGR Limits ECCS MAPLHGR Limits:
Average Planar Average Planar MAPLHGR Exposure MAPLHGR Exposure (kW/ft)
(GWd/MTU)
(kW/ft)
(GWd/MTU) 0.0 12.5 0.00 12.82 15.0 12.5 21.09 12.82 67.0§ 7.3 63.50 8.0 70.00 5.0 Single-Loop Operation MAPLHGR Multiplier for ATRIUM-10 Fuel is 0.85.
Single-Loop Operation MAPLHGR Multiplier for GE Fuel is 0.90.
t Limits are applicable for all of the EOOS scenarios presented in Table 1.1. For SLO operation, the MAPLHGR multiplier listed in Section 7.2.1 is applied to ATRIUM-10 fuel. For GE fuel, the SLO multiplier is the minimum of those defined in Section 5.7 and Section 7.2.1.
The GEI4 ECCS MAPLHGR limits do not include thermal-mechanical limits. The composite thermal mechanical and ECCS MAPLHGR limits are provided in Reference 9.10 and are GNF proprietary. In actual practice, the composite limits are used. The use of the standalone ECCS MAPLHGR limits is allowed as long as the SLO and MAPFAC multipliers are applied to the exposure dependent GEI4 LHGR limits. If the composite MAPLHGR limits in Reference 9.10 are used, the SLO and MAPFAC multipliers are only required to be applied to the MAPLHGR limits.
Refer to References 9.12 and 9.16 for the maximum licensing exposures.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Page 7-2 MAPFAC Multipliers* for Off-Rated Conditions - GEl4 Fuel:
- MAPFAC, MAPFACp 7.2.2 Minimum Critical Power Ratio Table 5.4 Table 5.11 Flow-Dependent MCPR Limits:
Exposure-Dependent MCPRp Limits 7.2.3 Linear Heat Generation Rate Tables 5.1 and 5.2 Tables 5.5-5.10 References 9.11, 9.12 and 9.16 ATRIUM-10 Fuel GE14 Fuel Steady-State LHGR Limits Steady-State LHGR Limits Pellet Pellet Exposure LHGR Exposure LHGR (GWd/MTU)
(kW/ft)
(GWd/MTU)
(kW/ft) 0.0 13.4 0.0 13.4 18.9 13.4 16.0 13.4 74.4t 7.1 63.5 8.0 70.0 5.0 The PAPT LHGR curves forATRIUM-10 fuel are identified in References 9.12 and 9.16. The ATRIUM-10 LHGRFACf and LHGRFACp multipliers are applied directly to the steady-state LHGR limits at reduced power and reduced flow to ensure the PAPT LHGR limits are not violated during an AOT.
LHGRFAC Multipliers for Off-Rated Conditions - ATRI UM-10 Fuel:
LHGRFACf LHGRFACp Table 5.3 Table 5.11 The use of the standalone ECCS MAPLHGR limits is allowed as long as the SLO and MAPFAC multipliers are applied to the exposure dependent GE14 LHGR limits. If the composite MAPLHGR limits in Reference 9.10 are used, the SLO and MAPFAC multipliers are only required to be applied to the MAPLHGR limits.
Refer to References 9.12 and 9.16 for the maximum licensing exposures.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 8-1 8.0 Methodology References See XN-NF-80-19(P)(A) Volume 4 Revision 1 for a complete bibliography.
8.1 ANF-913(P)(A) Volume I Revision I and Volume I Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analysis, Advanced Nuclear Fuels Corporation, August 1990.
8.2 ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
8.3 EMF-2209(P)(A) Revision 2, SPCB Critical Power Correlation, Framatome ANP, September 2003.
8.4 EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
8.5 EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-41MICROBURN-B2, Siemens Power Corporation, October 1999.
8.6 EMF-CC-074(P)(A) Volume 4 Revision 0, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
8.7 ANF-89-98(P)(A) Revision I and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 9-1 9.0 Additional References 9.1 - EMF-3121 (P) Revision 0, Browns Ferry Unit 2 Thermal-Hydraulic Design Report for A TRIUMm-1O Fuel Assemblies, Framatome ANP, September 2004.
9.2 ANP-2523(P) Revision 0, Browns Ferry Unit 2 Fabrication Batch BFE2-15 ATRIUMTM-1O Fuel, AREVA NP, April 2006.
9.3 ANP-2531 (P) Revision 0, Browns Ferry Unit 2 Cycle 15 Fuel Cycle Design, AREVA NP, May 2006.
9.4 EMF-2939(P) Revision 0, Browns Ferry Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM'm-1O Fuel, Framatome ANP, August 2003.
9.5 Letter, A.W. Will (AREVA) to G. C. Storey (TVA), "Disposition of Events for Extended Power Uprate at Browns Ferry Units 2 and 3," AVWV:06:065, May 1, 2006.
9.6 ANP-2539(P) Revision 0, Browns Ferry Unit 2 Cycle 15 Plant Transient Analysis, AREVA NP, June 2006.
9.7 EMF-2950(P) Revision 1, Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis, Framatome ANP, April 2004.
9.8 EMF-3145(P) Revision 0, Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA-ECCS Analysis MAPLHGR Limit for ATRIUMM10 Fuel, Framatome ANP, December 2004.
9.9 NEDO-32465-A, Licensing Topical Report, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, GE Nuclear Energy, August 1996.
9.10 Eric Form, John Williams (TVA) to Josh L. Parker (AREVA), "Re: MAPLHGR Lattice Limits," July 31, 2003.
9.11 Letter, E. Riley (TVA) to A. W. Will (AREVA), "GEl4 Reference Information,"
L32 060515 800, May 15, 2006.
9.12 EMF-3114(P) Revision 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-14 ATRIUM-10 FuelAssemblies, Framatome ANP, September 2004.
9.13 EMF-3238(P) Revision 0, Browns Ferry Unit 2 Cycle 15 Plant Parameters Document, Framatome ANP, January 2006.
9.14 EMF-2978(P) Revision 0, Browns Ferry Nuclear Plant New Fuel Storage Vault Criticality SafetyAnalysis forATRIUM-IO Fuel, Framatome ANP, July 2005.
9.15 NEDC-32433P, Maximum Extended Load Line Limit and Arts Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3, GE Nuclear Energy, April 1995.
9.16 ANP-2537(P) Revision 0, Mechanical Design Report for Browns Ferry Unit 2 Reload BFE2-15 A TRIUM-IO Fuel Assemblies, AREVA NP, May 2006.
AREVA NP Inc.
AREVA NP Inc.
ANP-2541 Browns Ferry Unit 2 Cycle 15 Revision 0 Reload Analysis Page 9-2 9.17 Letter, E.A. Brown (NRC) to K.W. Singer (TVA), "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Full-Scope Implementation of Alternative Source Term (TAC Nos. MB5733, MB5734, MB5735, MC0156, MC0157, and MC0158)
(TS-405)," September 27, 2004.
9.18 Letter, T.A. Galioto (AREVA) to J.F. Lemons (TVA), "Fuel Handling Accident Assumptions for Browns Ferry," TAG:02:012, January 23, 2002.
9.19 USNRC Certificate of Compliance for Radioactive Material Packages, Model No.: RAJ-ll, USA9309/B(U)F-96 Revision 1.
9.20 Letter, N.J. Carr (AREVA) to G.C. Storey (TVA), "Update on RAJ-11 Shipping Container, Inner Container Stacking Criticality," NJC:04:052 FAB04-761, October29, 2004.
9.21 Letter, T.A. Galioto (AREVA) to G.C. Storey (TVA), "10 CFR 50.46 PCT Reporting for BFN Units 2 and 3," TAG:05:056, June 30, 2005.
AREVA NP Inc.
AREVA NP Inc.
Browns Ferry Unit 2 Cycle 15 Reload Analysis ANP-2541 Revision 0 Distribution Controlled Distribution OC Brown DD Crockett ME Garrett JM Haun JW Hulsman SW Jones RR Schnepp MS Stricker SA Tylinski AW Will Notification List (e-mail notification)
JS Holm DB McBumey AREVA NP Inc.