ML100850058
| ML100850058 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/24/2010 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EDMS: L32 100215 802, TVA-COLR-BF3C15, Rev 0 | |
| Download: ML100850058 (15) | |
Text
Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing March 24, 2010 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report for Cycle 15 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 3 Cycle 15 (i.e., the upcoming cycle), Core Operating Limits Report (COLR), Revision 0. This Unit 3 COLR was issued as an interim measure to include Shutdown Margin criteria in support of fuel loading for Cycle 15 (Mode 5 operation). A revision to the COLR will be issued prior to Cycle 15 startup covering all licensed power levels of operation (Modes 1 through 5).
There are no new commitments contained in this letter. If you have any questions please contact Terry Cribbe at (423) 751-3850.
Respectfully, R. M. Krich
Enclosure:
Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report, Revision 0, for Cycle 15 Operation cc: See Page 2 printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 March 24, 2010 Enclosure cc: (w/Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, Revision 0 For Cycle 15 Operation (See Attached)
QA Document TVA Nuclear Non-Proprietary S]Nuclear Nuclear Fuel Engineering - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit 3 Cycle 15 Core Operating Limits Report, (105% OLTP)
TVA-COLR-BF3CI 5 Revision 0 (Final)
February 2010 Page 1 Prepared:
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Chairman, PORC Approved:
EDMS: L32 100215 802 BFE-2897, Revision 0 (Final)
Pages Affected: All
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TVA.OOLR43F3C15 Reuvifn 0 (Fue), Page 2 Table of Contents Total Number of Pages = 12 (inclucung cover sheet)
List of Tables.................................................................................................................................
3 List of Figures..............................................................................................................................
4 Revision Log..................................................................................................................................
5 Nomenclature................................................................................................................................
6 References....................................................................................................................................
8 1
Introduction........................................................................................................................
10 1.1 Purpose...................................................................
10 1.2 Scope..........................................................................................................................
10 1.3 Fuel Loading...........................................................................................................
10 1.4 Acceptability............................................................................................................
10 2
Shutdown Margin Limit..........................................
12 EDMS: L32 100215 802 BFE-2897, Revision 0 (Rnal)
I I-
B.roamFe" Urit 3 Cde 15 Cowe cperA~n Umis Paport (10W. OLWM IVAb-GOLR-BF3CI5 RqftegO(ft4i)Page3 List of Tables Nuclear Fuel Types.....................................................................................................................
11 IIS 3
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IIIl EDMS: L32 100215 802 SFE-2897, Refton 0 (Final)
B~m"nFeny Un1301,.915 Com Opwa*ig LhiIts RPot~ (105% OLTP) 1VACOLR-BF3CI Iav~swi 0 TkWIn)
Page 4 List of Figures None No table of figures entries found.
EDMS: L32 100215 802 BFE-2897, Revision 0 (Final)
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Bra"B Ferry Jnht3 Cycle 15 Cor0Iem~
UmftLark RepAr (105% 011?)
TVAOCOLR.8F3C15 ReWitkn 0 SMId) Paae 5 Revision Log Number Page I
Description l-RO All New document, per NFTP-111, Section 3.3, Item Q.
EDMS: L32 100215 802 BFE-2897, Revision 0 (Final)
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B&ans Feny Unit 3 Cyde 15 Core OpsUa Umn Pa=L (106% OLTP) 1VA.COLR43P3C15 FRvtukn 0 (Fmgli Page 6 Nomenclature APLHGR APRM AREVA NP ARTS BOC BWR CAVEX CD COLR CPR CPRFAC CRWE Average Planar LHGR Average Power Range Monitor Vendor (Framatome, Siemens)
APRM, Rod Block Monitor, and Technical Specification Improvement Program Beginning of Cycle Boiling Water Reactor Core Average Exposure Coastdown Core Operating Limits Report Critical Power Ratio Multiplier to determine off-rated OLMCPR, relative to rated conditions Control Rod Withdrawal Error DTSP Dual TSP EIS EOC EOFP EOOS EOR FFWTR FHOOS GWd HPSP HTSP ICF IPSP ITSP Equipment-In-Service End of Cycle End of Full Power (no ICF or FFWTR)
Equipment OOS End of Rated Conditions Final Feedwater Temperature Reduction Feedwater Heaters OOS Giga Watt Day High PSP High TSP Increased Core Flow (beyond rated)
Intermediate PSP Intermediate TSP Vendor Specific Nomenclature for CPRFAC Linear Heat Generation Rate LHGR Multiplier (Power or Flow dependent)
Low Power Range Monitor Low PSP Generator Load Reject, No Bypass Low TSP MAPLHGR multiplier (Power or Flow dependent)
Minimum CPR Middle of Cycle Main Steam Isolation Valve MSIV 00S LHGR LHGRFAC LPRM LPSP LRNB LTSP MAPFAC MCPR MOC MSIV MSIVOOS EDMS: L32 100215802 BFE-2897, Revision 0 (Final) i
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MSR Moisture Separator Reheater MSROOS MSR OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NFT Nuclear Fuel Type NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit OOS Out-Of-Service OLTP Original Licensed Thermal Power (100% OLTP, 3293 MWt)
Pbypass Power, below which TSV Position and TCV Fast Closure Scrams are bypassed PLU Power Load Unbalance PLUOOS PLU OOS PSP Power Setpolnt RBM Rod Block Monitor RPT Recirculation Pump Trip RPTOOS RPT OOS SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation SRV Safety Relief Valve SRVOOS SRV OOS TAU Vendor Specific Variable (1) Representing Scram Timing.
TBV Turbine Bypass Valve TBVIS Turbine Bypass Valves IS TBVOOS Turbine Bypass Valves OOS TCV Turbine Control Valve TIP Transverse In-Core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TSV Turbine Stop Valve TVA Tennessee Valley Authority EDMS: L32 100215 802 SFE-2897, Revision 0 (Final) t
Brws Fefy Urdt 3 Cyce 15 TVA-COLR-BF3CI5 Co.
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Ii
- iaei, 0 (Frnal) Page 8 References
- 1.
BFE-2904, Revision 1, "Browns Ferry Unit 3 Reload 14 In-Core Shuffle Verffication,"
Calculation File, Tennessee Valley Authority, February 2010.
Methodoiog Reference s
- 2.
XN-NF-81-58(PXA) Revision 2 and Supplements I and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
- 3.
XN-NF-85-67(PXA) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.
- 4.
EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(PXA), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.
- 5.
ANF-89-98(P)(A) Revision I and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
- 6.
XN-NF-80.19(P)(A) Volume I and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.
- 7.
XN-NF-80-19(PXA) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
- 8.
EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.
j
- 9.
XN-NF-80-19(PXA) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
- 10.
XN-NF-84-105(P)(A) Volume I and Volume I Supplements i and' 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-HydraulIc Core Analysis, Exxon Nuclear Company, February 1987.
- 11.
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.
- 12.
ANF-913(PXA) Volume I Revision 1 and Volume I Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
EDMS: L32 100215 802 BFE-2897, Revision 0 (Final)
Bmis Ferwy Uri 3 Cyte 15 1VA-COLR-BF3CI5 Cou Opwalwg Lbb RWt (106% OLTP)
Reist 0 OFqa, Page 9
- 13.
ANF-1358(P)(A) Revision 1, The Loss of Feedwater Heating Transient In Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.
- 14.
EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, Siemens Power Corporation, September 2009.
- 15.
EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001.
- 16.
EMF-2292(P)(A) Revision 0, ATRIUM m-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
~uM~: LU 1UIU1~ w~e BFE-2897', RevisIon 0 (FInal)
EUMS: LAZ 100215 802 SFE-2897, RevWm 0 (Final)
BTrm" Fefy Unit 3Cyde 15 Camn Opwalnar Lnimb Repoit. (1050A OLTP)
TVACOLR43F3C15 Fft~iam0(RWhal Pace 10 I
Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.
1.1 Purpose The primary purpose of this document is to satisfy requirements identified by unit technical specification section 5.6.5. This document may be provided, upon final approval, to the NRC.
1.2 Scope This version of the COLR is specifically intended to support the refueling outage. Consequently, this document only covers MODE 5 operation of the unit. Operation outside MODE 5 will be addressed in a future COLR revision. This document will discuss the following area;
> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1) 1.3 Fuel Loading The core will contain all AREVA NP, Inc., ATRIUM-10 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented in Reference 1.
1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 2 through 16.
~m~1 E:DMSd: L32 10M15~l 802 BFE-2897, Revision 0 (Final)
Blmwo "~ LWI:t3 Cycle 15 core 0Owara Lkit Rcevork (105% O01W)
TVA4COLR-BF3C15 PW4sIon 0 (Flr~al Pane I I Table 1.1 Nuclear Fuel Types" Nuclear Original Number of Fuel Type Fuel Names Fuel Descriptlon.Cye Assemblies,(NFT (Range)
ATRIUM-10 AIO-4171B-14GV80-FCB 13 43 1
FCB001-FCB8064 ATRIUM-10 AIO-41638-16GV80-FCB 13 68 2
FCBOSS-FC8232 ATRIUM-10 AIO-41818-13GV80-FCB 13 64 3
FCB233-FCB296 ATRIUM-10 A10-4218B-15GV80-FCC 14 215 4
FCCOO1-FCC216 ATRIUM-10 AIO-4218B-13GV80-FCC 14 72 5
FCC219-FCC29D ATRIUM-10 AIO-3831B-15GV80-FCD 15 200 6
FCDO01-FCD200 ATRIUM-10 A10-3403B-gGV80-FCD 15 20 7
FCD257-FC8276 ATRIUM-10 A10-33925-IDGV80-FCD 15 36 8
FCD221-FCB256 ATRIUM-10 AIO-4218B-i5GVS0-FCC 15 2
9 FCC217-FCC218 ATRIUM-10 AIO-42189-13GV80-FCC 15 4
10 FCC307-FCC310 ATRIUM-10 A10-37578-10GV80-FCC 15 40 11 FCC335-FCC374 The table dweti the epected fuel typebreakdo nnInw on of final core loading. The fin, composon of the core depends upon unoertainties durin the outage such as dlsoovedng a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and moitoftn requirements identified in this document IDM:I32102I80 IIIIIIIevsln (Inal EDMS: L32 100215 $02 BFE-2897, RWslon 0 (Final)
BrM Fevy Urdt 3 Cyle 15 TVA.COLR-BF3C15 Co.e OperaOti Umif Repor (105% OLTP)
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,oA, Page 12 2 Shutdown Margin Limit (Technical Specification 3.1.1)
Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLE control blades are fully inserted, the core shall be sub-critical and meet the following minimum shutdown margin:
> 0.38% dk/k ED S
II2 1001502IF-I97 ReIIon0 FIaI EDMS: L.32 100215 802 SFE-2897. ReMsIon 0 (Final)