ML051570214
| ML051570214 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/03/2005 |
| From: | Cowan P Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051570214 (22) | |
Text
TS 6.9.1.12 June 3,2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC Docket No. Eio-353
Subject:
Issuance of the Core Operating Limits Report For Reload 8, Cycle 9, Revision 1
Dear Sir/Madam:
Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 2, Reload 8, Cycle 9, Revision 1. Revision 1 of this report incorporates the Oscillation Power Range Monitor (OPRM) trip setpoints and corrects typographical errors.
This COLR is being submitted to the NRC in accordance with LGS, Unit 2 Technical Specifications (TS) Section 6.9.1.12.
If you have any questions, please do not hesitate to contact us.
Very truly yours, Pamela B. Cowan Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc: S. J. Collins, Regional Administrator, Region I , USNRC S. Hansell, USNRC Senior Resident Inspector, LGS T. Tate, Senior Project Manager [LGS], USNRC
Limerick Unit 2 Cyde 9 COLR COLK Limerick 2, Rev. 1 1 Page 1 CORE OPERATING LLhlITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 8, CYCLE 9 Prepared 3 y : Date: ~ J ~ f i ~ ~
I Preparer Reviewed By:
Independent Reviewer
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 I Page 2 Page 1 .O Terms and Definitions 5 2.0 References 6 3.0 General Information 7 4.0 MAPLHGR Limits 8 5.0 MCPR Limits 9 6.0 Linear Heat Generation Rate Limits I3 7.0 Control Rod Block Setpoints 19 8,0 Turbine Bypass Valve Paranieters 20 9.0 Stabiftty Protection Setpoints 21 10.0 Modes of Operation 21
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 I Page 3 Table 4-I MAPLHGR Vcrsus Average Planar Exposure All Fuel Types 8 Table 4-2 MAPLHGR Singfe Loop Operation (SLO) Reduction Factor 8 Table 5-1 Operating Limit Minimum CriticaI Power Ratio (OLMCPRf 10 Table 6-1 Linear Neat Generation Rate Limits 1.1 Table 6-2 LHGR Singk Loop Operation (SLO) Reduction Factor 14 Tabte 7-1 Rod Black Monitor Setpoints 19 Table 7-2 Reactor Coolant System Recirculation Flow Upscale Trip 19 Table 8-1 Turbine Bypass System Regponse Time 20 Table 8-2 Nfinimum Required Bypass Valves To illraiatain System Operdability 20 Table 9-1 OPRM PBDA Trip Setpoints 21 1
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. I 1 Page 4 Figure S-1 Power Dependent MCPR Limit Adjustments and Multipliers i1 Figure 5-2 Power Dependent MCPR Limit Adjustments and Multipliers - TBVOOS 12 Figure 5-3 Flow Dependent MCPR Limits MCPR(F) 13 Figure 6- 1 Power Dependent LHGR Multiplier LGHRFAC(P) 15 Figare 6-2 Power Dependent LWGR hfultiplierLHGRFAC(P) - TBVOOS 16 Figure 6-3 Flow Dependent LHGR Multiplier LHGRFAC(F) 17 Figure 6-4 Fiow Dependent LHGR MulttpIier LCRFAC(F)-SLO ia
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 1 Page 5 1.0 Terms And Ikfinitions ARTS APRM and RBM Technical Specification Analysis DTSP Rod Black Monitor Down.jcale Trip Setpoint End of Rated (EOR) The cycle exposure at which reactor power i s equal to 3455 MWth with recirculation system flu% equal to 1uO%, all control rods fully withdrawn, all feedwater heating in service and equ~l~brium Xenon.
FF7VI-R Final Feedctarer Temperature Reduction moos Feedwater Heaten Out of Service HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ESP Rod Block Monitor Intermediate Trip Setpoint LHGR Linear Heat Generation Rate LHGWAC(F) ARTS LHGR thermal limit ffow dependent adjustments and multipliers LHGRFAC(P1 ARTS LHGR thermal limit power dependent adjustments and multipliers LTSP Rod Block Monitor Lob Trip Setpoint MAPLHCR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(P) ARTS MCPR thermal limit power dependent adjustments and mukipliers MCPR(F) ARTS MCFR t h e m 1 limit flow dependent adjustments and multipfiers MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Criticai Power Ratio OPRM PBDA Oscillation Pouer Range LMonitorPeriod Based Detection Algorithm RCF Rated Core Flow RrnQOS Recirculation Pump Trip Out of Service SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation
Limerick tnit 2 Cyck 9 COLR COLR Limerick 2, ~ e vI. I Page 6 TBVOOS Turbine Bypass Valves Out of Scrvicc 2.0 Keferences
- 1. Technical Specifications and Bases for Limerick Generating Station Unit 2, Docket No. 50-353, License No. hTF-85.
2, Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 8 Cycle 9, Globs1 Nuclear Fuel Document No. ~ 7705-SRLR,
~ Revision 3 0, Januarj 2005.
3 . GE14 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units I and 2. GE-NE-LI 2-00884W-OtP, March 2001.
- 4. OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick 2 Reload 8 Cycle Y, TODI #4-00254
- 5. ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Stition and Limerick Generating Station, GENE Document NEDC-32847P, June 1998.
- 6. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-1.1, June 2ooO and U S .
Supplement BEDE-2401 I -&A- 14-US. June 2 0 .
- 7. Power Range Neutron Monitoring System Setpoint CaIculations Limerick Generating Station, Units I
&2 Mod. No. P(w224, LE-0107, Rev. 0, March 2OOO.
- 8. Limerick 1 and 2 Off-Rated Analyses Below the PLLT Power Level,GE Nuclear Document No. CE-NE-0000-0037-3253-R0,March 2005.
- 9. Fuel Bundle Infonndtiori Report for Limerick Generating Station Unit 2 Reload 8 Cycle 9,Global Nuclear Fuei Document No. oo00-003I -7705-FBIR, January 2005.
- 10. Limerick 2 Cycle 9 Option Txp Stability Anajpis, GE Nuclear Energy Document No. G E ~ ~ ~ ~ ( ~ 3 7 1045-fi0, March 2Otl5.
Limerick Unit 2 Cycle 9 COLK COLR Limerick 2, Rev. 1 I Page 7 3.0 Gerieeral Information This report provides the following cycle-specifzc parameter limits for Limerick Generating Station Unit 2 Cycle 9:
Maximum Average Pianar Lineal.Hear Generation Rate (,MMLHGR) s Miaimuni Critical Power Ratio (MCPR)
- Single Loop Operation (SLO)MCPR adjustment m ARTS MCPR them1 limit adjustments and multipliers (MCPRP) or MCPR(F))
ARTS LWGR thertnaf limit multipliers (LHGRFAC(P)or I,HGRFAC(F))
m Rod Block Monitor (R3M) setpoints MAPLHGR single loop operation reduction factor LHGR single loop operation reduction factor Linear Heat Generation Rate (LHCR)
Turbine Bypass Valve parameters Reactor Coolant System Recirculation Ffow L'pscale Trips Oscillation Power Range Monitor Period Based Detection Algorithm Trip Setpoints These values have k e n determined using NRG-approved methodology (Reference 6), and are established such that art applicable h i t s of the plant safety analysis are met.
This report is prepared in accordance with Technicaf Specification 4.9.1.9of Reference I . Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuel Management T&RM NF-AB- 120-8600.
The data presented in this report is valid for all licensed operating domains on the operating map, including:
Maximum Extended Load Line Limit down to 815% of rated core flow during full power operation Increased Core Flow (ICF) up to f 10%of rated core flow Final Feedwater Temperature Reduction (FFWTR) up to 105°Fdunng cycle extension operation Feedwater Heater Out of Service {FWHOOS)up to 60°F feeduarer temperature reduction at any time during the cycle prior to cycle extension.
Further information on the cycle specific analyses for Limerick 2 Cycle 9 and the associated operating domains discussed above is available in Reference 2.
Limerick Unit 2 Cycle Y COLK COLR Limerick 2, Rev. 1 I Page 8 4.0 SLWLHGR Limits The MAPLHGR h i t s provided in Tables 4-1 and 4-2 are referenced in Technical Specifications 3 2 . 1 . The lirniitins K4PLHG.R value for the most limiting lattice (excluding natural uranium) of each fuel typc as a function of average planar exposure is given in Table 4-1 (Rcfercnces 2). The limiting MAPLHCR value is the same for all fuel type5 in the Limerick Unit 2 Cycle 9 core. Table 4-1 is used when hand caIculations are required as specified in Techntcal Specification 32.1. For single loop operation, a reduction factor is used u hich is shown in Table 4-2 (Reference 2).
TABLE 4-1 MAPILHCR Versus Average Wanac Expcrsure All Fuel Types (Reference 2)
TABLE 4-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor (Reference2)
SLO Reduction Factor 0.80
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev, 1 1 Page 9 5.0 MCPR Limits The MCPK values provided in Table 5-f are referenced in Technical Specification 3.2.3. Table 5-1 1s derived from the Reference 2 analyses and is valid for all Cycfe 9 fuel types and operating domains. Tabte 5-1 includes treatment of these MCPR limits for SLO. Bounding MCPR valuer are also provided for inoperabte Recirculation Pump Trip or inoperable Steam Bypass System. Thew two options represent the Equipment Out of Service conditions. The cycle exposure that represents EOR i s piken in the latest verified and approved Cycle ~ ~ n a g Reporte ~ or~ an n associatcd
~ Engineering Change Request.
ARTS provide5 for powcr- and ffow-dependent thermal limit adjustments and multipliers, whicli allow for a more reliable administratton of the MCPR thermal limit. The flowdependent adjustment MCPR(F) IS sufficiently generic to apply to a11 fuet types arid operating domains (References 2 and 5 ) . In addition, there are afso two sets of power-dependent MCPR multipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (Reference 8). Section 8.0 contains the conditions for Turbine Bypass Valve Operability. These adjustments and rnultipliers are shown in Figures 5-1 through 5-3 and are referred to by Technical Specification 3.2.3. The MCPRP) curves are independent of recirculation pump trip I operability (Reference 8).
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 1 Page 10 TABLE 5-1 Operating Limit Mnimum Critical Power Ratio (OLMCPR)
(ReEerence 2)
TBV In Service and TBV out of Service RIYT Out of Service RPT In Service (TEWOOS) 1 I BOC toEUR- 1.32 I 1.35 1.44 I 1.47 1 . When Tau does not:equal 0 or I, determine OLMCPR via linear interpolation.
- 2. OLMCPR iimit ser by the Single Loop Operation Recirculation Pump Seizure Analysis (Reference 2).
- 3. This table is valid for all Cycle 9 fuel types.
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. f I Page 11 FIGURE 5-1 Power Dependent MCPR Limit Adjustments And Muttipliers This Figure Is Vdid Far -411Operating Domains except TBVOOS (References 2 and 8) 4.0 3.8 3.6 3.4 3.2 Eu 9
a 3.0
..I s
2.8 b
3 2.6 8.
p 2.4 Q
2 2.2 CL, I.
P
+j2.0 E
EI:
p 1.8 I
1.6 1.4 1.2
-c 1.0 -
a 20 40 60 80 100 Power(% Rated)
Limerick h i t 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 1 Page 12 FIGC'RE 5-2 Power Dependent MCPR Limit Adjustments And Multipliers TBVOOS -
This Figure Is Valid For The TBVOOS Operating Domain (References 2 and 8) 5.0 4.6 4 . 2 * \
A
)PEliWTIUC LI"1.II'l: 'MCPR(P) = K,
- OPERATlhG LIMIT t\fCPR( 100) ae 3.8 3.79 OR P .:2 5 4 . NO THERMAL LAMIT MONITORING REQLtRED iP!
L hO LIMITS SPEClFlED A OR 25% 5 P c P,,,,, (P,,p,Gs = 30%)
p& 3 . 4 E
u OLMCPR(P) = [Z 65 0088(30% P)1
!?
3
%
R 3.0
/\ ;
3.09 '
FOR 5 MI*%CORE FZOW OLMCPRPI = [3 79 + O L54t3OCe. P)]
FOR > 6 0 6 CORE E O W n 2.65 2 2.6
-4 -< 60% Flow i OR 30% 5 P C.50% K, = I 37 C 0,00965(506 P) I i!
5 u
2.2 OR5OQtPcbOB K,= L.i.5 +Q00867f60Q-P) s OR 60% 5 P K, = I .OO + 0.003751 100%- P) 1.8 1 . 4 1.0 0 20 40 65 80 100 P o w e r (% Rated)
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 1 Page 13 Flow Dependent MCPR Limits ItTCPR(F)
This Figure Is Valid For All Operating Dumains (References 2 and Sf 2.oo 1.90 For Two Loop Operation, MCPR(F) = The Maximum of EITHER 1.25 OR { -0.5784 x (W-g,tOO)i-1.7073) 1.80 WT = O h Rated Cora Flow 1.70
-% 1.60 8
2 1.50 1.40 1.30 1.20 1.10 30 40 50 60 7 0 80 90 loo 110 Core Flow ( % Rated)
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 1 Page 14 6.0 Linear Heat Generation Kate Limits The maximiim C'O2 LHGR value for each fuel tjpe for use in Technical Specification 3.2.4 is provided in Table 6-1 bclow. The LHGR is an exposure dependent value. Due to the proprietary nature of these values only the maximum UO?LHGR for each fuel type is listed in Table 6-1.
ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the LHCR thermal limits. There are two sets of flow-dependent LGHR rnu1tiplier.i for dual-loop and single-loop operation (References 2, 3, and 5). In addition, there are also two sets of power-dependent LHGR multipliers for use wirh the Turbine Bypass Valves in service and TBVOOS conditions (Reference 8). Section 8.0 contains the conditions fur Turbine Bypass Vatve Operability. The LHCR multipliers are shown in Figures 6-I through 6-4 and are referred to by Technical Specification 3.2.4.
Thema1 limit monitoring must be performed with the more limiting LHGR fimif resulting: from the power-and flow-biased calcukation. The LHGWACfPf curves are independent of recirculation pump trip operabilrty (Reference 8).
TABLE 6-1 Linear Hmt Generation Rate Limits (Reference 9)
FUEL TYPE MAXIMUM VALUE GE14 I 3.4 kW/&
TABLE 6-2 LHGR Single Loop Operation @LO)Reduction Factor (Reference 2)
SLO Reduction Factor' 0.80 I Apptied through Figure 6-4
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 I Page 15 Power Dependent I X G R Multiplier LHGRFAC(P)
This Figure Is Valid For A11 Operatirig Domains except TBVOOS (References 2 and 3) 0.634
&
0.485 +----d 0.490
/0.473 0.434
> 60% Flow f 0 2 0 40 60 80 3.00 Power (76 Rated)
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev. 1 I Page 16 Power Dependent LXIGR ~ u ~ t i I,HGRFAC(P)
~l~e~ - TBVOOS This Figure Is Valid For The TBVOOS Operating Domain (References 2 and 8)
-r 60% Flow FOR P < 25% : NO THER MAL LIMIT MONITORING REQUIRED NO t i M w SPECIFIED FOR 25% 2 P < 30% : LHGRFX(F) = 0.490 .i- 0.0054(P-30)
For S 60% Flow LHGRFAC(P) = 0.386 + 0.0068(P-30)
Far 60% Flow FOR 3 0'6 S P < 50% : LHGRFAC(P) = 0.939 -+ 0.005224(P-100)
FOR P 2 50% : FWGRFAC(P) 1 .O i0.005224(P-100) 1 I 0 20 40 60 BO 100 P o w e r (% Rated)
Lherick Unit 2 Cycle 9 COLK COLK Limerkk 2, Rev. 1 I Page 17 FICUW 6-3 Flow Dependent LHGR Multiplier I,HGRFAC(F)
This Figure Is Valid For All Operating Domains Excluding Single Lmp Operation (References2,3 and 5) 1.1 1.0 0 . 9
-
b 0
2 0.8 P
"A L
s 8
u, 2
u, 0.7 LHGR(F) = LWGRFAC(F)
- LHGRstd a
!i
-I
! FOR Two Loop Operation, > 70% WT LHGRFAC(FJ= The Minimum of ElTtlER 1.0 0 . 6 OR c0.0268 x ~T-70)/10+0.9732)
FOR Two Loop Operation, I 70% WT LHGRFAC(F) = (5.6682 x WTI100)+0.5055 0.5 Where WT = % Rated Core Flow 0.4 30 40 50 60 7 0 80 go 100 110 Core low ( % Rated)
Limerick Cnit 2 Cycle 9 COLR COLK Limerick 2, Rev. 1 I Page 18 FIGURE 6-4 Flow Dependent LHGR Multiplier X,HCRFAC(F) SLO -
This Eiguse Is Valid For Single Loop Operation (References 2 and 5 )
1.1 2.0 0.9
-
k.
0 2
5 0.8 3
c P
%
U.
L 0.7 0 LHGR(F) = LHGRFAC(F)
- LHGRstd z
s X
-1 FOR Single Loop Operation, 0 . 6 LHGRFAC(F) = ke Minimum of E W E R 0.80 OR 0.6682 x ( ~ ~ / 1 ~ ~ ~ 0 = 5 0 5 ~
Where WT =: % Rated Core Fiow 0 . 5 0.4 30 4 0 50 60 7 0 80 90 100 3.10 Core Flow 4% Rated)
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2. Rev. 1 1 Page 19 7.0 Control Rod Block Setpoints Technical Specification Limiting Condition for Operation number 3.3.6 requires control rod biock t i o n shall be OPERABLE with their trip setpoints consistent with the values d m v n in the
~ r ~ s ~ i ~ e n t achannels Trip Setpoint COILIIIXI of Technical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Flow Upscale Trip i5 a cycle-specific value and as such is found in Table 7-2 of this COLR. Tabie 7-2 lists the Nominal Trip Setpoint and Allowable Value. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 1 iO% of rated core flow. Additionatly, the ARTS Rod Block Monitor provides for potter-dependent RBM trips. The trip setpointslatlowable values and applicable RBM signal filter time constant data are shown in Table 7-1. These values are for use with Technical Specification 3.3.6.
TABLE 7-1 Rod Block Monitor Setpoints' (References 2 and 7 )
Nominal Trip Setpoint Allowable Value 116.5% 1 14.5%
I I
HTSP I
1 I 1 .O% I I
1 IL7%
- 7 I
89.0%
- 1. These setpints (with Rod Biock Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated R W MCPR h i t : which is less than or equal to the minimum cycle OLLMCPR(see COLR references 2 and 7).
TABLE7-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 7) i Nominal Trip Setpoint 1 13.4% ti
- 1 i
i Allowable Value 115.4% i
Limerick Unit 2 CycIe 9 COLR COLR Limerick 2, Rev. 1 1 Page 20 8.0 Turbine Bypass Valve Parameters The operability requirenients for the steam bypass system for use in Technical Specifications 3.7.8 and 3.7 8.C are found in Tabics 8-1 and 8-2. If these rryuirenients cannot be met. the MCPR, MCPR{P) and I LWCRFAC(P) limits for inopecable Steam Bypass System, known as Turbine Bypass Valve Out Of Service, must be used, TABLE 8-1 Turbine Bypass System Response Time
{Reference 4)
Maximum delay time before start of bypass valve opening following generation of the turbine bypass valve flow signal Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow (includes the above delay time) 0.31 sec I
TABLE 8-2 Minimum Required Bypass Valves To ,Maintain System Operability (References 4 and 8) i Reactor Power No, of Valves in Service i
P 2 25%
Limerick Unit 2 Cycle 9 COLR COLR Limerick 2, Rev, 1 f Page 21 9.0 Stability Protection Setpoints The Limerick 2 Cycle 9 UPRlVr Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 2.2.1 are found in Table 9-1. These values are based on the cycle specific analysis documented in Reference 10.
Any change to the OLMCPR value andlor ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Setpoints.
The OPRM PBDA Trip Setpoints are applicable when the associated Technicai Specification (TS Table 33.1-1, Item 2 . 0 is implementecl.
TABLE 9-1 OPRM PBDA Trip Setpoints i
Corresponding Maximum PBDA Trip Amplitude Confirmation Count TriD Setting 10.0 Modes Of Operation Limerick Generating Station has been analyzed to operate with a number of operational flexibility features, iiicluding Increased Core Flow, Maximum Extended Load Line Limit, Coabtdown, EOC Recirculation Pump Trip and Option A/B :MCPR Limits. Limerick Generating Station has also been analyzed to operate with a number of equipment out-of-service conditions, including Turbine Bypass Valves OOS, Single Loop Operation, Feedwater Heating OOS, and Final Feedwater Temperature Reduction. Operation is allowed in any combination of these operational flexrbiiity features and equipment out-of-serviceconditions, wrth one EXCEPTION, which is that Limerick may NOT operate with EOC-RecirculationPump Trip out-of-service in conjunction with Turbine Bypass Valves 00s.