ML060800366

Issuance of the Core Operating Limits Report for Reload 8, Cycle 9, Revision 2

ML060800366
Person / Time
Site:	Limerick
Issue date:	03/20/2006
From:	David Helker Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML060800366 (15)

Text

Exelon Nuclear www.exeloncorp.com 200 Exelon Way Kennett Square, PA 19348 TS 6.9.1.12 March 20,2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC: fh.&&Lh5~-35.?

Subject:

Issuance of the Core Operating Limits Report For Reload 8, Cycle 9, Revision 2

Dear SirlMadam:

Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 2, Reload 8, Cycle 9, Revision 2. Revision 2 of this report incorporates the adjusted off-rated thermal limit multipliers for the revised Power Load Unbalance Analysis.

This COLR is being submitted to the NRC in accordance with LGS, Unit 2 Technical Specifications (TS) Section 6.9.1.1 2.

If you have any questions, please do not hesitate to contact us.

Very truly yours, David P. Helker Manager - 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. Valentine, Project Manager [LGSJ, USNRC

Exelon Nuclear Fuels Dac ID: COLR Limerick 2, Rev. 2 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATINGSTATIOS UNIT 2 RELOAD 8, CYCLE 9 (This is a complete rewrite)

Preparer Approved By: Date: 3i//33/0b  !

1 J. J. Tusar anager BWR Design (GNF)

~

Page 1

Exelan Nuclear Fuels Dac ID: COLR Limerick 2, Rev. 2 Page 1 .0 Terms and Definitions 3 2.0 General ~ ~ ~ o ~ n a t ~ o n 5 3 .0 MAFLHGR Limits 6 4.0 nilCPR Limits 7 5 .o Linear Heat Generation Rate Limits 9 6.0 Control Rod Block Setpoints 11 7.0 Turbine Bypass Valve Parameters 12 8.0 Stability Protection Setpoints 13 9.0 Modes of Operation 13 10.0 Methodology 13 1 1 .0 References 14 Page 2

Exeton Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 Page Tabte 3- t ?IIAPLHGR Versus .4verage Planar Exposure Aft Fuel Types 6 Table 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor 6 Table 4- 1 Operating Limit ~ ~ j i i m LCritical

~ m Power Ratio (OLMCPR) 7 Table 1-2 Power Dependent hfCPR Limit Adjustments and ~ ~ l ~ i p i i e r s 8 Table 4-3 Flow Dependent MCPR Limits R;ICPR(F} 8 Table 5-1 Linear Heat Generation Rate Limits 9 Table 5-2 LHGR Single Loop Operation (SLO) Reduction Factor 9 Table 5-3 Power Dependent.LHGR Mulripfier LHCRFAC(P) 10 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 1.0

'fable 6- 1 Rod Block Monitor Setpoints 11 Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 11 Table 7-1 Turbine Bypass System Response Time f2 Table 7-2 l u ~ Bypass Valves To Maintak System Operability

~ i n ~ nRequired 12 Tabie 8- I OPRM PBDA Trip Setpoints 13 Table 9- 1 Modes af Operation 13 Page 3

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 1.0 Terns And Definitions ARTS APRM and RBM Technical Specification Analysis BASE CASE A caSe analyzed with Turbine Bypass System in service and Recirculation Pump Trip in service and Feedwater Temp~ratureReduction aliowed (EFWTR inclrides feedwater heater 00s or final feedwater temperature reduction) at any point during the cycle in Dual Loop mode.

DTSP Rod Block Monitor Downscafe Trip Setpoint EOUS Equipment Out of Service End of Rated (EOR) The cycle exposure at which reactor power is equaf to 3458 MWth with recirculation system flow equal to lO@%, all control rod3 fully withdrawn, all feedwater heating in service and e q u l ~ i b r ~Xenon.

~ni FFWTR Final Feedwater Temperature Reduction WHOOS Feedwater Heaters Out of Service HTSP Rod BIock Monitor High Trip Setpaint XCF Increased Core Flow ITSP Rod BIock Monitor Intermediate Trip Setpoint LHCR Linear Weat Generation Rare LHGRFAC(F) ARTS LHCR thermal limit flow dependent adj~stmen~s and multipliers LHGRFAC(P) ARTS LHGR thermal limit power dependent adjustments and muItipliers LTSP Rod Block Monitor LQWTrip Sexpaint MAPLHGR Maximum Average Planar Linear Heat Generation Rsre MCPR ~ ~ n Critical i ~ i Power

~ i Ratio

~

MCPRCP) ARTS hrCPR thermal limit pouer dependent adjustments and m u l ~ i p [ ~ ~ ~

MCPR(F) ARTS MCPR thermal limit flow dependmt adjustments and multiplier<

MELLLA ~ ~ ~ Extended

~ ~ Loadm Lint:

~ Limit r n Analysis BLMCPR Operating Limit ~ ~ ~ i m Critical u m Power Ratio OPRM PBDA Oscillatim Pocter Range Moniror Period Based Detection Algorithm I-WTOOS Recirctiiation Pump Trip Out of Service Page 4

Exelon Nucltear Fuels Doc ID: COLR Limerick 2, Rev, 2 SLMCPR Safety Limit M~nimumCritical Power Ratio SLO Single Loop Operation TBVUOS Turbine Bypass Valves Out of Service This reprt provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 9:

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Minimum Critical Power Ratio (MCPR)

Single Loop Operation (SLO) NCPR a d j u s t ~ ~ n t ARTS MCPR thermal limit adjustments and multipliers (MCPR(Pf or ILICPR(F))

ARTS LHGR thermal f imit multipliers (LWCWAC(P) or LHGRFAC(F))

Rod Bfock Monitor (RBM) setpoints MMLWGR single loop operation reduction factor LHCR singfe foop operation reduction factor Linear Heat Generation Rare (LHGR)

Turbine Bypass Valve parameters Reactor Coolant System Recircuiation Flow Upscale Trips Oscillation Power Range Monitor Period Based Detection Algorithm Trip Setpoints These values have been determined using NRC-approved me&hodology(Reference 6), and are established such that all applicable fimits of the plant safety analysis are m e t i o In.9 of Reference I . Preparation of this This report is prepared in accordance with Technical S ~ ~ ~ f i c a t6.9.

report was performed in accordance with Exefon Nuclear, Nuclear Fuel Management T&RM NF-AB-I20-3600.

The data presented in this report is valid for all iicensed operating domains on the operating map, including:

0 Maximum Extended Load Line Limit dctwn to 81% of rated core flow during full power operation 0 Increased Core Flow (ICF) up to I IO% of rated core flow Find Feedwater Temperature Reduction (FFWTR) up to 105°F during cycle extension operation 0 Feedwater Hearer Out of Service (FWWOOS) up to 60°F feedwater temperature reduction at any time during the cpcte prior to cycle extension.

n cycle specific analyses for Limerick 2 Cycle 9 and the associated operating Further i n f ~ ~ a t ~ono the domains discussed above is available in Reference 2.

Page 5

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 3,O MAPLHGR Limits 3.1 Technical Specification Section 3.2. I 3.2 Description The limiting MAF'LHGR value for the most limiting Iattice {excludingnatural uranium) of each fuel type as a function of average planar exposure is given in Table 3-1 (Reference 2). The limiting MAPLHCR value is the same for alt fuel types in the Limerick Unit 2 Cycle 9 core. For single loop operation, a reduction factor is used which is shown in Table 3-2 (Reference 2).

TABLE 3-1 MAPLHCR Versus Average PIanar Exposure All Fuel Types (Reference 2)

MAPLHGR Limit TABLE 3-2

&WLHGR SingIe I,mp Operation (SLO) Reduction Factor (Reference 2)

S t U Reduction Factor Page 6

E x e h Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Table 4-1 is derived from the Reference 2 anaXyses and is valid for ail Cycle 9 fuel types and operating domains. Table 4-1 includes treatment of theiie MCPR limits for SLO. Bounding MCPR values are afso ~ r o v for ~ ~inoperable d Recircufation Pump Trip or inoperable Steam Bypass System. These two options represent the Equipment Out of Service conditions. The cycle exposure that represents EOR i s given in the latest verified and approved Cycle e n ~ or an associated Engineering Change Request.

M a n a ~ e ~Report ARTS pratides for power- and ~ l o w - d e ~ n d thermal~nt limit adjustments and muttiplicrs.

which allow for a more reliable adminis~rati~n of the MCPR thermal limit. The flow-dependent adjustment MCPR(F) is sufficiently generic to apply to alf fuel types and operating domains (References 2 and S). In addition, &ere are also two sets of powerdependent MCPR muftipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (References 8 and 11). Section 7.0 contains the conditions for Turbine Bypass Valve Operabiiity. These adjustments are provided in Table 4-2 and 4-3. The OLMCPR IS determined for a given power and flow condition by evaluating the power-dependent MCPR and the ftow-dependent MCPR and selecting the greater of the two. The MCPR(P) curves are i n d e ~ n d eof i~~

refircutation pump trip operability (Reference 8).

TABLE 4-1 Operating Limit ~ ~ i ~Critical i ~ Power ~ r nRatio (ULMCPR)'

(Reference 2)

' This tabfe is valid for ail C>de 9 fuef types.

' When Tau does not equal 0 or f , determine QLMCPR i

'c ia linear interpolation.

QLMCPR limit set by the Single Loop Operation Recircutation Pump Seizure Analysis (Reference 2.)

Page 7

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev, 2 TABLE 4-2 Pawer Dependent MCPR Limit Adjustments And Multipliers (References2,8 and 11)

Ftaw (n of 0 25 <30

=mt&waw Base 1.300 I . 193 I .150 Base SLO I .300 1.193 I .oa RPTOOS 1.300 1.193 RPTOOS SLO 1.300 1.300 1.193 1 .00(

_ I_ - ____ __I_

TBVOUS 1.370 1.193 1 .m TSVOOS StO 1.370 1.370 1.193 P

TABLE 4-3 Flow Dependent MCPR Limits R/ICPR(F)

(References 2,sand 5 )

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Exelon Nuclear Fuels Dac ID: COLR Limerick 2, Rev. 2 5.0 Linear Heat Generation Rate Limits

5. I Technical Specification Section 3.2.4 5.2 Description The LHGR is an exposure dependent vatue. Due to tfae proprietary nature of these values only the maximum U02LHGR for each fuel type is listed in Table S-1 . For single b o p operation, a reduction factor is used which i s shown in Table 5-2 (Reference 2).

ARTS provides For power- and f l # w - d ~ ~ n d thermal e n ~ limit multipliers, which allow for a more reliable administration of the LHGR thermal limits. There are ~MKIsets of flow-dependent LGHR multipliers for dual-loop and single-loop operation (References 2, 3, and 5).

In addition, there itre also two sets of power-dependent LHGR multipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (References 8 and 1 1). Section 7.0 contains the conditions for Turbine Bypass Vatve Qpcrability. The LHGR multipliers are shown in Tables 5-3 through 5-4.

Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power- and flow-biascd calculation. The LHGWAC(P) curves are independent of recirculation pump trip operability (Reference 8).

TABLE 5-1 Linear Heat Generation Rate Limits (Reference9)

TABLE 5-2 LHGR Siagk Loap Operation {SLO) Reduction Factor (Reference21 SLO Reduction Facror' Page 9

Exelon Nuclear Fuels Doc ID: GOLR Limerick 2, Rev. 2 TABLE 5-3 Power Dependent LHCR Multiplier LHGRFACCP)

(References2,5 and 8)

TBVOOS SLO TABLE 5-4 Flow Dependent LHGR MuItipIier L ~ G ~ A ~ C ~ ~

(References2,s and 5 )

Page 10

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 6.0 Control Rod Block Setpoints 6.1 Technical Specification Section 3.3.6 6.2 Description Technical S ~ ~ ~ f i c a t Limiting jon Condition for Operation number 33.6 requires control rod t i o n shatl be OPERABLE with their trip setpoints consistent with the block i n s ~ ~ ~ ~ t achannels values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The Reactor Cooiant System Recirculation Flaw Upscale Trip is a cycle-specific value and as such is found in Table 5-2 of this COLR. Table 6-2 lists the Nominal Trip Setpoint and Altowable Value. These setpoints are set high enough to ailow futt utilkation of the enhanced ICF domain up to 1 fO% of ritted core flow. Additionally, the A E U S Rod Block Monitor provides for ~ ~ e r - d e ~RBM ~ d ~ n t trips. The trip S e ~ ~ i n ~ ~ a I Ivalues ~ l eapplicable RBM signal filter time constant data. are

~ w a and shown in Table 6-1. These values &refor use with rechnicat Specification 3.3.6.

TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 7)

TABLE 6-2 Reactor Coolant System Recirculation Ftotv Upsate Trig (Referenee 7)

These setpints (kith Rod Block Monitor filter r i m constant &r~.een0. I seconds and 0.55 xxoncts) are based an a cycle-specific rated RWE MCPR limit t\hich is Ie$s than or equat to the ~ ~ i ncyck i ~ u ~ ~

ULMCPR (.seeCOLR references 2 2nd 3.

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Exeion Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 7.0 Turbine Bypass Valve Parameters

7. I Technical Specification Section 3.7.8 and 4.7.8.C 7.2 Description

~ sthe steam bypass cystem for use in Technical Specifications The operability r ~ q ~ i r e m e nfor 3.7.8 and 4.7.8.C are found in Tables 7-1 and 7-2. If these r ~ q ~ i r e cannot~ e n ~be~ met, the hifCPR, MCPR(P) and LWCRFAC(P) limits for inopefahfe Steam Bypass System, known as Turbine Bypass Valve Out Of Service, must be used.

TABLE 7-Turbine Bypass SysEem Kespnse Time

~ R e ~ 4)e ~ ~ ~ ~ e

~ ~ x ~ time r nafter u generation

~ of a turbine bypass valve Row signal for bypass valve position to reach 805% of fufl flow TABLE 7-2 mu^ Required Bypass Valves To ~~t~~~ System Operability (References 4 and 8)

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Exelon NucIear Fuels Doc 1D: CULR Limerick 2, Rev. 2 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.12.F 8.2 Description The Limerick 2 Cycle 9 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for rhe OPRM System for use in Technical Specification 2.2.1 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 10. The setpoints provided in Table 8-1 are bounding for a11 modes of operation shown in Table 9- I .

TABLE 8-1 OPRM PBDA Trip Setpoints 9.0 Modes Of Operation TABLE 9-1 Miodes of Operation (Reference 2,3 and 5 )

The anaIytical ~ ~ ~used ~ to5determine d s the core operating limit%Fhaii be thoxe p ~ ~ ~and o

~rskizated ~ ~ l approved by the NRC,specifically those defcribed in the following document:

1. General Eirctric Standard ~ppIica~ion for Reactor Fuel, NEDE-2401I-P-A-14. June ZOO0 and U S ,

Supplement 3EBE-2401I-P-A- 14-LrS, Junt: 1OOO.

Operating R ~ I Orefers

~ I EO trperatron an the Poser to FIoa map with or M ithout FEWTR.

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Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 2 11.0 References 1 . Technical Specifications and Bases for Limerick Generating Station Unit 3, Docket No. 50-353, License No. NPF-85.

2. S u ~ p ~ e m eReload n ~ l Licensing Repon for Limerick Generating Station Unit 2 Reload 8 Cycle 9*,

Global Nuclear Fuel Document No. ~ ~ 1-7705-SRLR, 0 0Revision

~ 0, January 2005.

~ ~ d e ~for~ Limerick Generating Station Units I and X,GE-NE-3 . GE13 Fuel Design C ~ ~ I e - I n d eAnalyses L 1240884-00-01P, March 2001.

4, CPL-3 Transient Protection Parameters Verification for Reload Licensing Anafyses for Limerick 2 Reload 8 Cycle Y, TOD104-00254

5. ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, GEM? Document MEDG-32847P, June 1998.

6. General Electric Standard Application for Reactor Fuet, NEDE-2401 1 +-A- 14, June 2ooO and U.S.

Supplement %DE-240 1 1 -P-A- I4-US, June 2OOO.

7. Power Range Neutron ~ o n ~ t o r i nSystem g Setpoinr Calculations Limerick Generating Station. Units 1

&2 Mod. No. PO0224, LE-0107, Rev. 0, March 2ooO.

8. Limerick I and 2 Off-Rated Analyses Below the PLU Power Level, GE Nuclear Document No. GE-NE-

~ ~ ~ ~ ~ ? - ~March 2 ~ 2005.

3 - R 0 ,

9. *FuelBundle Infomation Repon for Limerick Generating Station Unit 2 Reload 8 Cycle 9, Global Nuclear FueI Document Xo. ~ - i -7705-FBB2,

~ January 3 2005.

10. Limerick 2 Cycle 9 Option III Stability Analysis. GE Nuclear Energy Document No. e E ~ E ~ - ~ ~ 7 -

1of5-RO, March 2005.

I 1 . Application Of The Limerick Unit 1 and Unit 2 Power Dependent Limits for X 5S% FLU Power Level, GE Nuclear Energy ~ u n ~No. ~ ~n Et ~ E - ~ -W~R O~, December - O I 2005.

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