ML080780244

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Issuance of the Core Operating Limits Report for Reload 12, Cycle 13, Revision 7
ML080780244
Person / Time
Site: Limerick Constellation icon.png
Issue date: 03/17/2008
From: David Helker
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML080780244 (15)
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Text

Exelon Nuclear www.exe]oncorp.com E

200 Exelon Way Nuclear Kennett Square, PA 19348 TS 6.9.1.12 March 17, 2008 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 NRC Docket No 50-352 .

Subject:

Issuance of the Core Operating Limits Report For Reload 12, Cycle 13, Revision 7 Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 1, Reload 12, Cycle 13, Revision 7. Revision 7 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the LGS, Unit 1 (1 R12) refueling outage. (Note: Revision 6 of the COLR was generated, but was superceded

. prior to Cycle 13 startup and is therefore not being submitted (Le., Revision 6 is obsolete as of the date of this submittal>>).

This COLR is being submitted to the NRC in accordance with LGS, Unit 1 Technical Specifications (TS) Section 6.9.1.12.

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 E. M. DiPaolo, USNRC Senior Resident Inspector, LGS P. Bamford, Project Manager [LGS), USNRC R. R. Janati, Commonwealth of Pennsylvania

Exeloo Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 7 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 1 RELOAD 12 CYCLE 13 Prepared By: ~~ . ..

GIUseppe RubmacclO Date: 3/IZJzayg r I Reviewed By: IN1 J~ Date: 3!1?.)D't Michael R. Holmes l~---

~JTU'"

Approved By: Date: 3-12-0f' Manager - BWR Design Station Qualified Reviewed By: ?dJk Robert C. Potter Date: ,1A~Jo~

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Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 Table of Contents Page 1.0 Tenns and Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPRLimits 7 5.0 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 14 11.0 References 14 Page 2

Exelon Nuclear Fuels Doc In: COLR Limerick 1, Rev. 7 I ,ist of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 6 Table 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor 6 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 7 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers 8 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 8 Table 5-1 Linear Heat Generation Rate Limits - UO z 9 Table 5-2 Linear Heat Generation Rate Limits - Gad Rods 9 Table 5-3 LHGR Single Loop Operation (SLO) Reduction Factor 10 Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) 10 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) 10 Table 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 12 Table 7-2 MinimmTI Required Bypass Valves To Maintain System Operability 12 Table 8-1 OPRM PBDA Trip Setpoints 13 Table 9-1 Modes of Operation 13 Page 3

Exelon Nuclear Fuels Doc lD: COLR Limerick 1, Rev. 7 1.0 Terms and Definitions ARTS APRM and REM Technical Specification Analysis BASE CASE A case analyzed with Turbine Bypass System in service and Recirculation Pump Trip in service and Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycle operation in Dual Loop mode.

DTSP Rod Block Monitor Downscale Trip Setpoint EOOS Equipment Out of Service EaR End of Rated. The cycle exposure at which reactor power is equal to 3458 MWth with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intennediate Trip Setpoint LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFAC(P) ARTS LHGR thermal limit power dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) ARTS MCPR thermal limit power dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Critical Power Ratio RPTOOS Recirculation Pump Trip Out of Service Page 4

Exelon Nuclear Fuels Doc tD: COLR Limerick 1, Rev. 7 SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVOOS Turbine Bypass Valves Out of Service 2.0 General Information This report is prepared in accordance with Teclmical Specification 6.9.1.9 of Reference 1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.

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 81 % of rated core flow during full power operation
  • Increased Core Flow (lCF) up to 110% of rated core flow
  • Final Feedwater Temperature Reduction (FFWTR) up to 105°F during cycle extension operation

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Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Table 3-1. The limiting MAPLHGR value is the same for all fuel types in Limerick Unit I Cycle 13. For single loop operation, a reduction factor is used which is shown in Table 3-2. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F),

therefore MAPLHGR(P) and MAPLHGR(F) are equal to 1.

Table 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWD/Sn (kW/ft) 0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)

I SLO Reduction h,,:tor I 0.80 Page 6

Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Table 4-1 is derived from the Reference 2 analyses and is valid for all Cycle 13 fuel types and operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Mode of Operations. The cycle exposure that represents EOR is given in the latest verified and approved Cycle Management Report or an associated Engineering Change Request.

ARTS provides for power- and flow-dependent thermal limit adjustments and multipliers, which allow for a more reliable administration of the MCPR thermal limit. The flow-dependent adjustment MCPR(F) and power-dependent adjustment MCPR(P) are sufficiently generic to apply to all fuel types and operating domains. The MCPR(P) curves are independent of recirculation pump trip operability (Reference 3). MCPR(F) and MCPR(P) are independent of Scram Time Option. 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 flow-dependent MCPR and selecting the greater of the two.

When the actual Scram speed falls between Option B (Tau = 0) and Option A (Tau = 1), linear interpolation shall be used to determine MCPR limits.

Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

All Fuel Types (Reference 2)

SCRAM Cycle Exnosure Time < EOR-2675 2: EOR-2675 EOOS Combination Ontion MWd/ST MWd/ST B 1.34 1.39 BASE A 1.37 1.42 B 1.44 (I) 1.44(1)

BASE SLO A 1.44(1) 1.44 B 1.37 1.42 TBVOOS A 1.40 1.45 B 1.44(1) 1.44 TBVOOSSLO A 1.44(1) 1.47 B 1.40 1.46 RPTOOS A 1.51 1.63 B 1.44(1) 1.48 RPTOOS SLO A 1.53 1.65 OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Analysis (Reference 2).

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Exelon Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 7 TABLE 4-2 Power Dependent MCPR Limit Adjustments And Multipliers (References 2, 3, and 9)

Core Core Thermal Power (% of Rated)

EOOS Flow 0 25 <30 >30 45 60 100 Combination (% of Operating Limit MCPR Operating Limit MCPR rated Multinlier Kn

< 60 2.66 2.66 2.44 Base 1.481 1.280 1.150 1.000

>60 3.39 3.39 2.93

< 60 2.68 2.68 2.46 Base SLO 1.481 1.280 1.150 1.000

> 60 3.41 3.41 2.95

< 60 2.66 2.66 2.44 RPTOOS 1.481 1.280 1.150 1.000

> 60 3.39 3.39 2.93 RPTOOS <60 2.68 2.68 2.46 1.481 1.280 1.150 1.000 SLO > 60 3.41 3.41 2.95

<60 3.07 3.07 2.63 TBVOOS 1.481 1.280 1.150 1.000

> 60 4.54 4.54 3.77 TBVOOS <60 3.09 3.09 2.65 1.481 1.280 1.150 1.000 SLO > 60 4.56 4.56 3.79 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)

(References 2, 3 and 5)

Flow MCPR(F)

(% rated) Limit 0.0 1.7073 79.06 1.25 110.0 1.25 PageS

Exelon Nuclear Fuels Doc 10: COLR Limerick I, Rev. 7 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR is an exposure dependent value. Table 5-1 provides the exposure dependent LHGR limit for all U0 2 pins for all bundles in the Cycle 13 core. Table 5-2 provides the exposure dependent LHGR limit for Gad pins in the Cycle 13 core. The LHGR SLO multiplier is shown in Table 5-3.

ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR thennallimits. There are two sets of flow-dependent LGHR multipliers 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 with the Turbine Bypass Valves in service and TBVOOS conditions (References 3 and 10). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power- and flow-biased calculation. The LHGRFAC(P) curves are independent of recirculation pump trip operability (Reference 3 and 10).

TABLE 5-1 Linear Heat Generation Rate Limits - UOz All Fuel Types (Reference 8)

Peak Pellet Exposure LHGR Limit (GWD/Sn (kW/ft) 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 TABLE 5-2 Linear Heat Generation Rate Limits - Gad Rods AIl Fuel Types (Reference 8)

Peak Pellet Exposure LHGRLimit (GWD/ST) (kW/ft) 0 11.76 12.08 11.76 54.21 7.02 59.98 4.39 Page 9

Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 TABLE 5-3 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)

I SLO Reduction Facto" I 0.80 TABLE 5-4 Power Dependent LHGR Multiplier LHGRFAC(p)

(References 2, 3, and 9)

Core Core Thermal Power (% of rated)

EOOS Flow Combination (% of 0 25 <30 > 30 100 rated) LHGRFAC(P) Multiplier

< 60 0.485 0.485 0.490 Base 0.6340 1.0000

>60 0.434 0.434 0.473

< 60 0.485 0.485 0.490 Base SLO 0.6340 1.0000

>60 0.434 0.434 0.473

< 60 0.485 0.485 0.490 RPTOOS 0.6340 1.0000

> 60 0.434 0.434 0.473

< 60 0.485 0.485 0.490 RPTOOS SLO 0.6340 1.0000

> 60 0.434 0.434 0.473

<60 0.463 0.463 0.490 TBVOOS 0.6340 1.0000

> 60 0.352 0.352 0.386

< 60 0.463 0.463 0.490 TBVOOSSLO 0.6340 1.0000

> 60 0.352 0.352 0.386 TABLE 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F)

(References 2, 3 and 5)

Core Flow (% of rated)

EOOS Combination o 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.5055 0.9732 1.00 1.00 Single Loop 0.5055 0.80 0.80 0.80 I Applied through Table 5-5 Page 10

Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 6.0 Control Rod Block Setpoints 6.1 Technical Specification Section 3.3.6 6.2 Description Technical Specification Limiting Condition for Operation munber 3.3.6 requires control rod block instrumentation channels shall be OPERABLE with their trip setpoints consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Flow Upscale Trip is a cycle-specific value and as such is found in Table 6-2 of this COLR. Table 6-2 lists the Nominal Trip Setpoints and Allowable Values, consistent with a HTSP analytical limit of 114%. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow. Additionally, the ARTS Rod Block Monitor provides for power-dependent RBM trips. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 6-1.

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

Power Level Nominal Trip Setpoint Allowable Value LTSP 121.5% 121.5%

ITSP 116.5% 116.5%

HTSP 111.0% 111.7%

DTSP 5.0% 2.0%

TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 7)

Nominal Trip Setpoint 113.4%

Allowable Value 115.6%

I Based on a cycle-specific rated RWE MCPR limit less than or equal to the minimum cycle OLMCPR. The values provided assume the Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds is used.

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Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 7.0 Turbine Bypass Valve Parameters 7.1 Technical Specification Section 3.7.8 and 4.7.8.C 7.2 Description The operability requirements for the steam bypass system are fOlmd in Tables 7-1 and 7-2. If these requirements cannot be met, the MCPR, MCPR(P) and LHGRFAC(P) lirnits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.

TABLE 7-1 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 0.11 sec Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow 0.31 sec (includes the above delay time)

TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 4)

Reactor Power No. of Valves in Service P 2: 25% 7 Page 12

Exelon Nuclear Fuels Doc 10: COLR Limerick 1, Rev. 7 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1.2.F 8.2 Description The Limerick 1 Cycle 13 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 2. The Cycle 13 OPRM PBDA hip setpoints specified in Table 8-1 require a minimum OLMCPR value of 1.34 (See Section 4.0 MCPR Limits). The setpoints provided in Table 8-1 are bounding for all modes of operation shown in Table 9-1.

TABLE 8-1 l

OPRM PBDA Trip Setpoints (Reference 2)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trio Settin!!

<1.14 16 9.0 Modes Of Operation TABLE 9-1 Modes of Operation (Reference 2, 3 and 5) 2 EOOS Ootions Ooeratinll Rel!ion Base Ootion A or B Yes Base SLO Ootion A or B Yes TBVOOS Ootion A or B Yes TBVOOS SLO Ontion A or B Yes RPTOOS Ootion A or B Yes RPTOOS SLO Ootion A or B Yes TBVOOS and RPTOOS Ontion A or B No TBVOOS and RPTOOS SLO Ootion A or B No I The station has conservatively decided to maintain the PDBA Trip Amplitude at 1.12 with a Corresponding Maximum Confirmation Count Trip Setting of 14 until such time where these changes do not introduce a Unit difference at Limerick. Operations and Site Engineering agreed upon this decision.

2 Operating Region refers to operation on the Power to Flow map with or without FFWTR.

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Exelon Nuclear Fuels Doc 10: COLR Limerick I, Rev. 7 10.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

1. "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-15, September 2005 and U.S.

Supplement NEDE-24011-P-A-15-US, September 2005.

11.0 References I. "Technical Specifications and Bases for Limerick Generating Station Unit I", Docket No. 50-352, License No. NPF-39.

2. "Supplemental Reload Licensing Report for Limerick Generating Station Unit I Reload 12 Cycle 13",

Global Nuclear Fuel Document No. 0000-0069-5237-SRLR, Revision 1, Febmary 2008.

3. "GEl4 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units 1 and 2", GE-NE-Ll2-00884-00-0IP, March 2001.
4. "OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick 1 Reload 12 Cycle 13", TOOl NF0700207.
5. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", GENE Document NEDC-32847P, June 1998.
6. "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-15, September 2005 and U.S.

Supplement NEDE-24011-P-A-15-US, September 2005.

7. "Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units 1 & 2 Mod. No. P00224", LE-0107, Rev. 0, March 2000. Including Minor Revision OB, March 1,2008.
8. "Fuel Bundle Information Report for Limerick Generating Station Unit 1 Reload 12 Cycle 13", Global Nuclear Fuel Document No. 0000-0069-5237-FBIR, January 2008.
9. "Limerick Units 1 and 2 Off-Rated Analysis Below PLU Power Level With Credit for Backup Trip", GE-NE-0000-0053-9467-Rl, August 2006.

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