ML083190040
| ML083190040 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/11/2008 |
| From: | Brandon M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TVA-COLR-BF1C8, Rev 0 | |
| Download: ML083190040 (13) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 November 11, 2008 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D.C. 20555-0001 In the Matter of
)
Docket No. 50-259 Tennessee Valley Authority
)
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 - CORE OPERATING LIMITS REPORT (COLR), FOR CYCLE 8 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is the Unit 1 Cycle 8, Core Operating Limits Report, Revision 0. This Unit 1 COLR was issued as an interim measure to include Shutdown Margin criteria in support of fuel loading for Cycle 8 (Mode 5 operation). A revision to the COLR will be generated prior to Cycle 8 startup covering all licensed power levels of operation (Modes 1-5).
There are no new commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.
Sincerely, Michael K. Brandon Interim Manager of Licensing and Industry Affairs Enclosure cc: See page 2
U.S. Nuclear Regulatory Commission Page 2 November 11,2008 Enclosure cc (Enclosure):
Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Eugene F. Guthrie, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303Z8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970
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QA Document TVA Nuclear Non-Proprietary WNuclear Nuclear Fuel Design - BWRFE 1101 Market Street, Chattanooga, TN 37402 Browns Ferry Unit I Cycle 8 Core Operating Limits Report, (105% OLTP)
TVA-COLR-BFl C8 Revision 0 (Final)
October 2008 Page 1
ýýT.W. Eichenberg, Sr. S'p&ialist Verified:
W. B. Bird, Engineer Approved:
G C Storey, ManagV, BWR Fuel Engine Date:
L6 fab Date: iO/o/zoo0 Date: ______
ering Date:
ng-Date:
Reviewed:
i/
-/Keck, Supervi Engineeri Approved:<z airma PO.RO EDMS: 1.32 081010 803 BFE-2707, Revision 0 (Final)
EDMS: L32 081010 803 PFE-2707, Revision 0 (Final)
Pages Affected: All
(7 j~1 Browns Ferry Unit 1 Cycle 8 TVA-COLR-BFIC8 Core Operating Umis Report (105% OLTP)
Revision 0 (Final), Page 2 Table of Contents Total Number of Pages = 11 (including cover sheet)
List of Tables...................................
3 List of Figures.................................................................................................................
4 Revision Log..................................
5....................
5 Nomenclature.........................................................................
6 References....................................................................................................................................
8 1
Introduction 9
1.1 Purpose.......................................................................................................................
9 1.2 Scope....................................................
............................................................. 9 1.3 Fuel Loading.............................................................................................................
9 1.4 Acceptability....................................................................................................
I............. 9 2
Shutdown Margin Limit...................................................................................................
11 EDMS: 132 081010 803 BFE-2707, Revision 0 (Final)
EDMS: L32 681010 803 BFE-2707, Revision 0 (Final)
Browns Feir~yUnit 1Cycle 8 Core Oneraitna Limils ReporL (105% OLTP)
TVA-COLR-BFICS Revision 0 (Final), Paae 3 List of Tables Nuclear Fuel Types.....................................................................................................................
10 EDMS L3 08110 03~
FE-707,Revsion0(FnaI EDMS: L32 081010 803-BFE-2707, Revision Q(Finaf)
)
Browns Ferry Unit I Cycle 8 Core Operating Limts Repo (105% OLTP)
TVA-COLR-BFIC8 Revision 0 (Final), Page 4 List of Figures None EDMS: L3 081010803 BFE-707, Reiso0(Fn)
EDMS: L32 081010 803 BFE-2707, Revision 0 (Final)
Browns Feny Unit I Cycle 8 Core Operating Limits Report, (105% OLTP)
TVA-COLR-BFIC8 Revision 0 (Final), Page 5 Revision Log Number Page I-RO All Description New document, per NFDP-1, Section 3.2, Item N.
I EDMS: L32 081010 803 BFE-2707~ Revision 0 (Final)
EDMS: L32 081010 803 V 13FE-2707, Revision 0 (Final)
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Browns Ferry Unit 1 Cycle 8 TVA-COLR-BF1C8 Core Operating Limits Report (105% OLTP)
Revision 0 (Final), Page 6 Nomenclature APLH.GR Average Planar LHGR APRM Average Power Range Monitor AREVA NP Vendor (Framatome, Siemens)
ARTS APRM, Rod Block Monitor, and Technical Specification Improvement Program BOC Beginning of Cycle BWR Boiling Water Reactor CAVEX Core Average Exposure CD Coastdown COLR core OperatingLimrits Report CPR Critical Power Ratio CPRFAC Multiplier to determine off-rated OLMCPR, relative to rated conditions CRWE Control Rod Withdrawal Error DTSP Dual TSP EIS Equipment-In-Service EOC End of Cycle EOFP End of Full Power (no ICF or FFWTR)
EOOS Equipment OOS EOR En-dof Rated-Conditions FFWTR Final Feedwater Temperature Reduction FHOOS Feedwater Heaters OOS GWd Giga Watt Day HPSP High PSP HTSP High TSP ICF Increased Core Flow (beyond rated)
IPSP Intermediate PSP ITSP Intermediate TSP I*
Vendor Specific Nomenclature for CPRFAC LHGR Linear Heat Generation Rate LHGRFAC LHGR Multiplier (Power or Flow dependent)
LPRM Low Power Range Monitor LPSP Low PSP LRNB Generator Load Reject, No Bypass LTSP Low TSP MAPFAC MAPLHGR multiplier (Power or Flow dependent)
MCPR Minimum CPR MOC Middle of Cycle MSIV Main Steam Isolation Valve MSIVOOS MSIV OOS E
IS 3
8.1 0
F-20,Rvso Fnl EDMS: L32 081.010 803 13FE-2707, Revision 0 (Final)
'V I-Bmrwns Ferry Unit I Cyde 8 TVA-COLR-BFIC8 Core Operating Umits Report, (105% OLTP)
Revision 0 (Final), Page 7 MSR Moisture Separator Reheater MSROOS MSR OOS MTU Metric Ton Uranium MWdIMTU Mega Watt Day per Metric Ton Uranium NEOC
Pbypass
-Power, below which TSV Position and TCV Fast Closure Scrams are bypassed
- PLU, Power: Load Unbalance..
PLUOOS:
PLU 005 PSP Power Setpoint 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:L_--
SRV OO TAU Vendor Specific Variable (,r) 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 IDS 32011 80I F-77 evso Fnl EQMS: L32 081010 803 BFE-2707, Revision 0 (Final)
(~7~~)
BrownsFerry Unit1 Cyde8, Core Operating Urnits Report (105% OLTP)
TVA-COLR-BF1C8 Revision 0 (Final), Page 8 References
- 1.
BFE-2686, Revision 1, "Browns Ferry Unit I Reload 7 In-Corn Shuffle Verification,".
Calculation File, Tennessee Valley Authority, October 2008.
Methodology References
- 2.
NEDE-24011-P-A-15, General Electric Standard Application for Reactor Fuel, September 2005..,I--
- 3.
NEDE-2401 1-P-A-15-US, General Electric Standard Application for Reactor Fuel (Supplement for United States), September 2005.
EDMS: L32 081010 803 BFE-2707, Revision 0 (Final)
EDMS: L32 081010 803 BFE-2707, Revision 0 (Final)
( /7'7' )
Bromwns Feny Unit I Cycle 8 TVA-COLR-BF1C8 Core Operating Umils Report (105% OLTP)
Revision 0 (Final), Page 9 IIntroduction III 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 coversMODE 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 Global Nuclear Fuels, Inc., GE13/GE14 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 and 3.
EDMS: L32 081 010 803 BFE-2707, Revision 0 (Final)
EDMS:. L32 081010 803 BFE-2707, Revision 0 (Final)
Browns Ferry Unit I Cycle 8 Core Operatng Limits Report, (105% OLTP)
TVA-COLR-BF1C8 Revision 0 (Final), Page 10 Table 1.1 Nuclear Fuel Types Nuclear Original Number of Fuel Type Fuel Names Fuel Description Cycle Assemblies (NFT)
(Range)
GE13-P9DTB156-NOG-iOOT-146-T6-2887 7
56 3
JLXIO1-JLXIS6 GE13-P9DTB163-NOG-1OOT-146-T6-2888 7
52 12 JL.X157-JLX208 GE14-PIODNAB157-NOG-IOOT-150-T6-2889 7
9 4
JLX209-JLX432 GE14-PIODNAB377-16GZ-10OT-150-T6-2890 7
95 5
JLX433-JLX528 GE14-P1ODNAB402-16GZ-IO0T-150-T6-2891 7
32 6
JLX529-JLX560 GE14-PIODNAB350-16GZ-IDOT-150-T6-2892 7
32 7
JLX561-JLX592 GE14-PlODNAB419-16GZ-IOOT-150-T6-2894 7
32 9
JLX613-JLX644 GE14-PIODNAB368-1 5GZ-100T-150-T6-2895 7
72 10 JLX645-JLX716 GE14-PIODNAB402-19GZ-1OOT-i 50-T'6-2896 7
24 11 JLX717-JLX740 GE1 4-P1 ODNAB377-17GZ-1 O0T-1 50-T6-2B97 7
32 13 JLX741-JLX772 GE1 4-P1 ODNAB406-1 6GZ-1 0OT-1 50-T6-3078 6
48 14 JYE101-JYE148 GE14-PIODNAB406-15GZ-1OT-i"-150-T6-3079 8
64 16 JYE245-JYE308 GE14-P10DNAB418-16GZ-IOOT-150-T6-3080 8
72 18 JYE357-JYE428 GE14-PI ODNAB400-17GZ-1O0T-150-T6-3081 8
96 15 JYE149-JYE244 GE14-P1 ODNAB417-16GZ-1 DOT-1 50-T6-3082 8
48 17 JYE309-JYE356 The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified in this document.
IEDMVS: L32 081010 803 BFE-2707, Revision 0 (Final)
Browns Feny Unit 1 Cycle 8 TVA-COLR-BFICB Core Operating Umits Report, (105% OLTP)
Revision 0 (Final), Page 11 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 EDMS: L32 081010 803 BFE-2707~ Revision 0 (Final)
EDMAS: L32 081010 803 BFE-2707, Revision 0 (Final)