ML082330378

From kanterella
Jump to navigation Jump to search
Issuance of the Core Operating Limits Report for Reload 9, Cycle 10, Revision 4, Incorporates a Change to Operating Limit Minimum Critical Power Ratio, and Changes Associated
ML082330378
Person / Time
Site: Limerick Constellation icon.png
Issue date: 08/20/2008
From: David Helker
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML082330378 (15)
v • d • e


Text

Exelon Nuclear www.exeloncorp.com 200 Exelon Way Nuclear Kennett Square, PA 19348 TS 6.9.1.12 August 20, 2008 u.s. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NBC Docket No 50-353

Subject:

Issuance of the Core Operating Limits Report For Reload 9, Cycle 10, Revision 4 Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 2, Reload 9, Cycle 10, Revision 4. Revision 4 incorporates a change to Operating Limit Minimum Critical Power Ratio, and changes associated with the rod block monitor downscale setpoint.

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.

Respectfully, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachment cc: S. J. Collins, Regional Administrator, Region I, USNRC E. M. DiPaolo, USNRC Senior Resident Inspector, LGS P. Bamford, Project Manager [LGS], USNRC

Exelon Nuclear Fuels Doc 10: COLR Limerick 2, Rev. 4 CORE OPERATING LIMITS REPOR T FOR LIMER ICK GENERATING STATION UNIT 2 RELOAD 9, CYCLE 10 Prepared By: Date: 03/13 /0'8 I ,

G. Rubinaceio Preparer Reviewed By:

Michael Holmes Date; ~

Independent Reviewer Approved By:

-p J. J. Tusar Manager- BWR Design (GNF)

Date:

Stat~onQualified~~J ~

Reviewed By: Date:

Scott Auve Station Qualified Reviewer Page 1 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 Table of Contents Page 1.0 Terms 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 of14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 I Jst of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types 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 9 Table 5-2 LHGR Single Loop Operation (SLO) Reduction Factor 9 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 10 Table 5-4 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 Minimum Required Bypass Valves To Maintain System Operability 12 Table 8-1 OPRM PBDA Trip Setpoints 13 Table 9-1 Modes ofOperation 13 Page 3 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 1.0 Terms 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 Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point during the cycle in Dual Loop mode.

DTSP Rod Block Monitor Downscale Trip Setpoint EOOS Equipment Out of Service End of Rated (EOR) 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 rCF Increased Core Flow rTSP Rod Block Monitor Intermediate 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(P) ARTS MCPR thermal limit power dependent adjustments and multipliers MCPR(F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Critical Power Ratio OPRM PBDA Oscillation Power Range Monitor Period Based Detection Algorithm RPTOOS Recirculation Pump Trip Out of Service Page 4 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVOOS Turbine Bypass Valves Out of Service 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 10:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • Minimum Critical Power Ratio (MCPR)
  • Single Loop Operation (SLO) MCPR adjustment
  • ARTS LHGR thermal limit multipliers (LHGRFAC(p) or LHGRFAC(F))
  • Rod Block Monitor (RBM) setpoints
  • MAPLHGR single loop operation reduction factor
  • LHGR single loop operation reduction factor
  • Linear Heat Generation Rate (LHGR)
  • Oscillation Power Range Monitor Period Based Detection Algorithm Trip Setpoints These values have been determined using NRC-approved methodology (Reference 6), and are established such that all applicable limits of the plant safety analysis are met.

This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 1. Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuels T&RM NF-AB-120-3600.

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 % ofrated core flow during full power operation
  • Increased Core Flow (ICF) up to 110% of rated core flow
  • Final Feedwater Temperature Reduction (FFWTR) up to 105°F during cycle extension operation
  • Feedwater Heater Out of Service (FWHOOS) up to 60°F feedwater temperature reduction at any time during the cycle prior to cycle extension.

Further information on the cycle specific analyses for Limerick 2 Cycle 10 and the associated operating domains discussed above is available in Reference 2.

Page 5 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 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 (References 2 and 9). The limiting MAPLHGR value is the same for all fuel types in the Limerick Unit 2 Cycle 10 core. For single loop operation, a reduction factor is used which is shown in Table 3-2 (Reference 2).

MAPFAC(P) and MAPFAC(F) are 1.0 for all power and flow conditions. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F).

TABLE 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (References 2 and 9)

Average Planar Exposure MAPLHGR Limit (GWD/STl (kW/fO 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)

SLO Reduction Factor I 0.80 Page 6 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 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 10 fuel types and operating domains. Table 4-1 includes treatment of these MCPR limits for SLO. Bounding MCPR values are also provided for inoperable Recirculation Pump Trip or inoperable Steam Bypass System. These two options represent the Equipment Out of Service conditions. 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) is sufficiently generic to apply to all fuel types and operating domains (Reference 2). In addition, there are also two sets of power-dependent MCPR multipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (References 2 and 3).

Section 7.0 contains the conditions for Turbine Bypass Valve Operability. 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. The MCPR(P) curves are independent of recirculation pump trip operability (Reference 3).

TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)l (Reference 2)

SCRAM Cvcle EXDosure Time < EOR-2800 2: EOR-2800 EOOS Combination Option2 MWd/ST MWd/ST B 1.33 1.38 BASE A 1.36 1.41 B 1.44(3) 1.44(3)

BASESLO A 1.44(3) 1.44(3)

B 1.37 1.43 TBVOOS A 1.40 1.46 B 1.44(3) 1.45 TBVOOSSLO A 1.44(3) 1.48 B 1.40 1.48 RPTOOS A 1.51 1.65 B 1.44(3) 1.50 RPTOOS SLO A 1.53 1.67 I This table is valid for all Cycle 10 fuel types.

2 When Tau does not equal 0 or I, determine OLMCPR via linear interpolation.

3 OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure (Reference 2)

Page 7 of14

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

Core Core Thermal Power (0/0 of Rated)

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

<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)

Flow MCPR(F)

(0/0 rated) Limit 30.0 1.534 79.06 1.25 110.0 1.25 Page 8 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 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. Due to the proprietary nature of these values only the maximum U02 LHGR for each fuel type is listed in Table 5-1. For single loop operation, a reduction factor is used which is shown in Table 5-2 (Reference 2).

ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR thermal limits. There are two sets of flow-dependent LGHR multipliers for dual-loop and single-loop operation (References 2 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 (Reference 3). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. 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-biased calculation. The LHGRFAC(P) curves are independent of recirculation pump trip operability (Reference 3).

TABLE 5-1 Linear Heat Generation Rate Limits (References 8 and 10)

FUEL TYPE MAXIMUM VALUE GE14 13.4 kW/ft TABLE 5-2 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)

I SLO Reduction Factor' I 0.80 1 Applied through Table 5-4 Page 9 of14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)

(References 2, 3 and 11)

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 0.634 Base 1.000

>60 0.434 0.434 0.473

<60 0.485 0.485 0.490 Base SLO 0.634 1.000

>60 0.434 0.434 0.473

<60 0.485 0.485 0.490 RPTOOS 0.634 1.000

>60 0.434 0.434 0.473

<60 0.485 0.485 0.490 RPTOOSSLO 0.634 1.000

>60 0.434 0.434 0.473

<60 0.463 0.463 0.490 TBVOOS 0.634 1.000

>60 0.352 0.352 0.386

<60 0.463 0.463 0.490 TBVOOSSLO 0.634 1.000

>60 0.352 0.352 0.386 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

(References 2, 5 and 9)

Core Flow (0/0 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 Page 10 of14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 6.0 Control Rod Block Setpoints 6.1 Technical Specification Section 3.3.6 6.2 Description Technical Specification Limiting Condition for Operation number 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 Setpoint and Allowable Value. 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. These values are for use with Technical Specification 3.3.6.

TABLE 6-1 1

Rod Block Monitor Setpoints (References 2 and 7)

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%

1 These setpoints (with Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit of 1.30, which is less than or equal to the minimum cycle OLMCPR (see COLR references 2 and 7).

Page 11 of 14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 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 for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Tables 7-1 and 7-2. If these requirements cannot be met, the MCPR, MCPR(P) and LHGRFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service, must be used.

TABLE 7-1 Turbine Bypass System Response Time (Reference 4)

Maximum delay time before start ofbypass 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 of14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1.2.F 8.2 Description The Limerick 2 Cycle 10 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the 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 2. The setpoints provided in Table 8-1 are bounding for all modes of operation shown in Table 9-1.

TABLE 8-1 1

OPRM PBDA Trip Setpoints (Reference 2)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trio Settinl!

~ 1.13 ~ 15 9.0 Modes Of Operation TABLE 9-1 Modes of Operation (References 2, 3 and 5) 2 EOOS Ootions Ooeratint! Ret!ion Base Ontion A or B Yes Base SLO. Ontion A or B Yes TBVOOS. Ootion A or B Yes TBVOOS SLO Ontion A or B Yes RPTOOS Ontion A or B Yes RPTOOS SLO. Ontion A or B Yes TBVOOS and RPTOOS Ootion A or B No TBVOOS and RPTOOS SLO. Ootion A or B No 1 The station has conservatively decided to maintain the PDBA Trip Amplitude at 1.12 with a Corresponding Maximum Count Trip Setting of 14 until such time where these changes do not introduce a Unit difference at Limerick. This decision was agreed upon by Operations and Site Engineering.

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

Page 13 of14

Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 4 10.0 Methodology The analytical methods used to detennine 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", GNF Document, NEDE-24011-P-A-15, September 2005 and U.S. Supplement NEDE-24011-P-A-15-US, Revision 15, September 2005.

11.0 References

1. "Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353, License No. NPF-85.
2. "Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 9 Cycle 10", Global Nuclear Fuel Document No. 0000-0054-5796-SRLR, Revision 2, July 2008.
3. "GEI4 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units 1 and 2", GE-NE-LI2-00884-00-01P, March 2001.
4. "OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick 2 Reload 9 Cycle 10", TODI: NF0600311 Rev. 1
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", GNF Document, NEDE-24011-P-A-15, September 2005 and U.S. Supplement NEDE-24011-P-A-15-US, Revision 15, September 2005.
7. "Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units 1 & 2 Mod. No. P00224", LE-OI07, Rev. 0 (including minor revision OOC), April 2008.
8. "Fuel Bundle Infonnation Report for Limerick Generating Station Unit 2 Reload 9 Cycle 10", Global Nuclear Fuel Document No. 0000-0054-5796-FBIR, Revision 0, January 2007.
9. "Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 8 Cycle 9", Global Nuclear Fuel Document No. 0000-0031-7705-SRLR, Revision 0, January 2005.
10. "Fuel Bundle Infonnation Report for Limerick Generating Station Unit 2 Reload 8 Cycle 9", Global Nuclear Fuel Document No. 0000-0031-7705-FBIR, Revision 0, January 2005.

II. "Limerick Units I and 2 Off-Rated Analysis Below PLU Power Level With Credit for Backup Trip", GE-NE-0000-0053-9467-RI, August 2006.

Page 14 of14

Retrieved from "https://kanterella.com/w/index.php?title=ML082330378&oldid=2154230"