ML051570208

Issuance of the Core Operating Limits Report for Reload 10, Cycle 1 1, Revision 3

ML051570208
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: ML051570208 (26)

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 1 Facility Operating License No. NPF-39 "RC:

DQ&z~ No. 50-35.2

Subject:

Issuance of the Core Operating Limits Report For Reload 10, Cycle 1 1, Revision 3

Reference:

1) GE Nuclear Energy SCO4-15, 10 CFR Part 21 Notification,

Subject:

Turbine Control System Impact in Transient Analyses, October 31, 2004

Dear Sir/Madam:

Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 1, Reload 10, Cycle 1 1, Revision 3. Revision 3 of this report incorporates revised off-rated thermal limits to address a 10 CFR Part 21 Safety Communication (Reference 1). Revision 3 of this report also 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 1 Technical Specifications (TS) Section 6.9.1.1 2.

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

Very truly yours, Pamela 6.

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 1 Cycle 11 COLR COLR Limerick 1, Rev. 3 I

Page 1.

CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION WNIT 1 RELOAD 10, CYCLE 11 Prepared By:

Date: /5 Reviewed By:

Date: :h$/m

Limerick Unit 1 Cyck I1 COLR 1.0 Terms and Definitians 2.0 References 3.0 General Infomation 4.0 MAPLHGR Limits 5.0 MCPR Limits 6.0 7.0 Control Rod Block Setpoints 8.0 Turbine Bypass Valve Parameters 9.0 Stability Protection Setpoints 10.0 Modes of Operation Linear Heat Generation Rate Liniits COLR Limerick 1, Rev. 3 Page 2 1

Pdge 5

6 7

8 17 22 23 24 1

25 2s

Limerick Unit 1 Cycle 11 COLR Table 4-I MAPLHGR Versus Average Planar Exposure Bundle Type GE 13-"3417-I 3GZ-I WT-146-T (GE 13)

Table 4-2 MAPLHGR Versus Average Planar Exposure Bundle Typt. GEI 3-P9CTB417-11GZ-100T-146-T (GE13)

COLR Limerick 1, Rev. 3 1

Page 3 9

9 Tabfe 4-3 W L W G R Versus Average Planar Exposure Bundle Type GE14-PIOC~AB417-7G8.0/8C7.0-1 OOT-150-T-2527 (GE14C)

I0 Table 4-4 MMLEGR Versus Average Planar Exposure Bundle Type C;E14-PIOCNAB4t7-13CZ-100T-l 50-T-2528 (GEf4C) 10 Table 4-5 MAPLHGR Versus Average PIanar Exposure Bundle Type GE14-P10C~~417-7G8.0/8G7.O-XO~4SR-I 50-"-2531 (GE14C) 1 1 Table 4-6 MAPLHGR Versus Average Planar Exposure But>dle Type CE14-PIOCN~J17-15GZ-1 OT-150-T-2592 (GEf4.C) 1 1 Tabfe 4-7 MAPLHGR Versus Average Planar Exposure Bundle Type GEt4-PI ~NAB414-13GZ-l(WT-150-T-2701 (GEI4C) 12 Table 4-8 'WLHGR Single Loop Operation (SLO) Reduction Factor 12 Table 5-1 Operating Limit Minimum Critical Power Ratio 18 Table 6-1 Linear Heat Generation Rate Limits 22 Table 7-1 Rod Block Monitor Setpaints 23 Table 7-2 Reactor Coolant System Recirculation Flow Upscale Trip 23 Table 8-1 Turbine Bypass System Response Time 24 Table 8-2 Minimum Required Bypass Valves To,Maintain System Operability 24 Table 9-1 OPRM PBDA Trip Setpoincs 25 I

Limerick Unit I Cycle 11 COLR COLK Limerick I, Rev. 3 1

Page 4 Figure 4-I Figure 4-2 Figure 4-3 Figure 4-4 Figure 5-1 Figure 5-2 Figure 5-3 Power Dependent MAPLHGR Multiplier MMFAC(P)

Power Dependent MAPLHGR Multiplier MAPFAC(P) - TBVOQS Flow Dependent MAPLHGR hiultiplier MMFAC(F)

Ffow Dependent MAFLHGR Multiplier MAPFAC(F) -SLO Power Dependent MCPR Limit Adjustments and Multipliers Power Dependent MCPR Limit Adjustments and Multipliers - TBVOOS Flow Dependent MCPR Limits MCPRrF)

Page 13 1.1 1.5 16 19 20 2t

Limerick Unit 1 Cycle 11 COLR 1.0 TERMff AND DEFINITIONS COIX Limerick 1, Rev, 3 Page 5 I

ARTS DTSP End of Rated (EOR) m WHOOS HTSP ICF ITSP LHGR LTSP M M F AC (F) 1\\IIApFAC(P)

MAPLHGR MCPR MCPR(P)

MCPR(F)

MELLLA OPRM PBDA RCF W O O S SLMCPR SLO TBVOOS hPRM and RBM Technical Specification Analysis Rod Block Monitor Downscak trip serpoint The cycle exposure at which reactor power is equal to 3458 MWth Qith recirculation system flow equal to fW%, all control rods fully withdrawn, all feedwater heating in service arid equilibrium Xenon.

Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Rod BIock Monitor High trip setpoint Increased Core Flow Rod Block Monitor Intermediate trip setpoint Linear Heat Generation Rare Rod BLock Monitor t o w trip setpoint AR'TS MAPLHGR thermal Iimtt flow dependent adjustments and multipliers ARTS MAPLHGR thermal limit-power dependent adjustments and multipliers Maximum Average Planar Linear Heat Generation Rate Miniinurn Critical Power Ratio ARTS MCPR thermal limit power dependent adjustments and multipliers ARTS MCPR thermal limit floui dependent adjustments and multipliers Maximum Extended Load Line Limit Analysis Oxiliation Period Range Monitor Period Based Detection Algorithm Rated Core Flow Recirculation Pump Trip Out of Service Safety Limit Minimum Critical Power Ratio Single Loop Operation Turbine Bypass Valves Out of Service

IAmeriek Unit 1 Cycle II COLR

2.0 REFERENCES

COLR Limerick 1, Rev. 3 Page 6 1

1.

2.

3.

4.

5.

6.

7,

8.

9.

10.

Technical Specifications and Bases for Limerick Generating Station Unit l, Docket No. 50-352.

License No. XPF-39.

Supplemental Reload Licensing Report for Limerick Generating Station Unit 1 Reload 10 Cycle 1 I, Global Nuclear Fuel Document No. ~ ~ 1 8 - 2 4 1 0 - S ~ +

Revision 0, January 2004.

Lattice Dependent MAPLHGR Report for Linlerick Generating Station Unit 1 Reload 10 Cycle 1 i, Globaf Nuclear Fuel Document No. ~ - ~ 1 8 - ~ 4 1 ~ M ~ L H G R,

Revision 0, February 2004.

Lattice Dependent MAPLIIGR Report for Limerick Generating Station Unit I Reload 9 Cycle lo, Global Nuclear Fuel Document No. f 1 1-Q3984MAPL, Revision 0, January 2002.

GEi4 Fuel Design Cycie-Independent Analyses for Limerick Generating Station Units I and 2. GE-NE-L12-008$4-00-0IP, MXCh 2001.

OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick 1 Reload 10 Cycle 1 1, Resolved as documented in DRF 201 1 1 (LIC I 1 Reload Licensing DRF),

Limerick Generating Starion Units 1 and 2 ECCS-LOCA Evaluation for CEIV, GE Nuclear Energy Document No. GE-NE-J 1 1 413793-09-0 I P, February 200 I.

ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, GEM3 Document I\\;EDC-32847P, June 1998.

General Electric Standard,4pplication for Reactor Fuel, XEiDE-2401 I-P-A-I 4, June 2OOO and US.

Supplement NEDE-2401 l-P-A-14-tJS, June 2OOO.

Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units I

&2 Mod. No. POO224, LE-0 107, Rev. 0, March 2ooO.

1 1. Fuel Bundle Information Report for Limerick Generating Station Unit 1 Reload 10 Cycfe 1 l, Global Nuclear Fud Document KO. ooo0-0018-2410-FBR, Jariuary 2004.

12. deleted

13. Limerick 1 and 2 Off-Rated Analyses Below the PLW Power Level, CE Nuclear Document Xo. GE-

~ - ~ ~ 3 7 - ~ ~ 5 3 - ~ 0,

March 2005

$4. Limerick I Cycle 1 1 Option I[J Stability Analysis, GE Nuclear Energy Document No. GEkuTE-W 0037-0728-R0, March 2005.

Limerick Unit 1 Cycle 11 COLK COLR Limerick 1, Rev. 3 Page 7 f

3.0 GENERAL I

~

F

~

R

~

~

T I

~

~

This report provides the follow'ing cycle-specific parameter limits for Limerick Generating Station Unit 1 Cycle 1 I :

b e

0 b

e b

0 Maximum Avemge Planar Linear Heat Generation Rate (MAPLHGR)

,Minimum Critical Power Ratio (MCPR)

Single Loop Operation (SLO) MCPR adjustment ARTS MCPR thermal firnit adjustments and mukiptiers (MCPR(P) or MCPR(F))

ARTS MAPLHGR thermal limit multipliers (MAI?FAC(P) or MAPFAC(F))

Rod Block Monitor (RBM) sctpornts MAE'LHGR single loop operation reducliori factor Linear Heat Generation Rate (LHGRl Turbine Bypass Valve parameters Reactor Coolant System Recirculation Flow Upxale Trips OPRV Period Based Detection Algorithm (PF3DA) trip setpoints These values have k e n determined using NRC-approved methodology (Reference 91, 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 perf%med in accordance with Exetan Nuclear, Nuclear Fuel Management Procedure NF-AB-120.

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 hcreased Core Flow /KFj up to 1 lo% of rated core Bow Finai Feedwater Temperature Reduction (FTWTR) up to 105OF during cycle extension operation Feedwater Heater Out of Service CFWHOOSj up to 60°F feedwater tetnperature reduction at any time during the cycle prior to cycle extension.

Further infomation on the cycle specific analyses for Limerick 1 Cycle I t and the associated operating doniains discussed above is available in Reference 2.

Limerick Unit 1 Cycle 11 COLR COLK Limerick 1, Rev. 3 Page 8 1

The MAPLHGR limits provided in Tables 4-I through 4-8 are referenced in Technical Specifications 3.2. f.

The limiting MVLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Tables 4-1 through 4-7 (References 3 and 4). Tables 4-1 through 4-7 are used when hand calculations are required as specified in Technical Specification 3.2. I. For single loop operation, a reduction factor is used which is shown in Table 4-8 (Reference 2).

ARTS provides for povcec-and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the MAPLHGK thermal limits. There are two sets of flow-dependent MAPLGHX multipliers for duaf-loop and single-loop operation (References 2, 5 and 8j. fn addition, there are atso two sets of power-dependent MAPLNGR multipliers for use with the Turbine Bypass Valves in service and Operability. The RilAPLHGR multipliers are shown in Figures 4-1 through 4-4 and are referred to by Technical Specification 3.21. Thermal Limit monitoring must be performed with the more limiting MAPLHGR limit resulting from the power-and flow-biased calculation. The W F A C ( P ) c w e s are TBVOOS conditions (Reference 13). Section 8.0 contains the conditions for Turbine Bypass Valve I

1 independent of recirculation pump trip operability (Reference 13).

Limerick Unit 1 Cycle 11 COLR 6.0 COLK Limerick 1, Rev. 3 Page 9 I

~

I 1 53 I

20.0 12.32 58.2 6.29 MAPLHGR Versus Average Planar Exposure Bundle Type GE13-P9CTB417-13GZ-l00T-146-T (GE13)

(Reference 4) t 5.0 I 1.45 6,0 11.37 20.0 12.32 58.03 7.49 17.5 1

12.47 55.0 MAPLHGR Versus Average Planar Exposure Bundle Type GI3 13-~T3417-11~Z-l~T-l~6~T f GE 13)

(Reference 4)

I 1.0 1

10.93 i

9.0 1

12.06 1

35.0 1

10.96 I

I 4.0 1

11.31 i

15.0 1

12.55 1

50.0 I

8.98 1

Limerick Unit 1 Cycle 11 COLR 0.2 Tabie 4-3 10.22 8.0 11.02 30.0 9.86 COLR Limerick 1, Rev. 3 I

Page 10 i

1.o 2.0 3.Q W L H G R Versus Average Planar Exposure (Reference 4)

Bundle Type C;El.3.-P10CNAB417-7G8.0/8~~.O-lOOT-150-T-2527 (GEI4C) 10.26 9.0 11.09 35.0 9.3 8 10.32 10.0 it.15 40.0 8.90 10.42 12.0 1 1.25 45.0 1

8.40 I

3.0 1

10.22 1

12.0 I

11.17 1

45.0 1

8.40 I

4.0 MAPLHGR Versus Average PZanaf Exposure Bundle Type G~f4-PlOCNAB$17-13GZ-100T-15U-T-2528 (GE14C)

(Reference 4) 10.53 15.0 j

11.09 50.0 7.86 5.0 10.66 17.0 1

10.98 55.0 5.91 6.0 10.8 1 20.0 I

10.78 57.12 4.55

Limerick Unit t Cycle 11 COLR 60 tO.64 15.0 I

E 1.04 7.a I

10.81 17.0 1

10.95 I

s Table 4-5 55.0 5.89 57.06 4.86 I

COLR Limerick 1, Rev. 3 Page 11 f

MAPltlAGR Versus Average PIanar Exposure BundIe Type GEl4-P10CN~417-7G8.~18G7,0-8015R-lSO-T-2531 (GE14C)

(Reference 4)

I 6.0 1

10.70 I

20.0 I

10.79 1

57.13 1

4.85 I

Table 4-6 RIZAPLHGR Versus Average Pianar Exposure Bundle Type rJE14-PlOCNAB417-15GZ-t~~-

1.50-T-2592 (GE14C)

(Reference 3)

Limerick Unit 1 Cycle 11 COLR 5.0 COLR Limerick 1, Rev. 3 Page 12 1

10.6 1 t 4.0 11.14 50.0 7.76 MAPLXPGR Versus Average Planar Exposure Bundle Type GEl4-PIOCNABJ14-14GZ-100T-150-T-2701 (GE14C)

(Reference 3) 6.0 ffl.73 15.0 I

I1.08 55.0 IIMPLNGR (kW/ft) 10.76 10.30 5.86 1

9.24 1

7.0 10.86 17.0 10.96 1

57.02 4.85 j

SLU reduction factor Table 4-8 0.79 W L N G R Single Loop Operation (SLO) Reduction Factor (Reference 2)

Limerick Unit 1 Cycle 11 COLR FIGURE 4-1 COLR Limerick 1, Rev. 3 Page 13 I

Power Dependent MAPLHGR Multiplier IIIIAfFAC(P)

This Figure Is Valid For the RCF, ICF, MELLL, FWHOOS And FFWTR Operating Domains (RPT In Service Or RPTOOS)

(Reference 13)

I M A P M O W = MAPFAG@')

• MAPLHHORstd FOR P 25% ' NO TWERWIAL LIMIT MONITORING REQUIRED NO LIMITS SPECIFIED 0. 0 !

1 I

0 20 4 0 60 P m r (94 Rated) 80 100

Limerick Unit 1 Cycle I1 COLR CQLR Limerick 1, Rev. 3 Page 14 I

Power Dependent &WLWGR Multiplier MAPFAC(P) - TBVOOS This Figure Is Valid For The TBVOOS Operating Domain (Reference 13)

Limerick Unit 1 Cycle 11 COLR COLR Limerick I, Rev. 3 P q e 15 1

FIGLXE 4-3 Flow Dependerit MAPLHGR MuItiplier W F A C f F)

This Figure Is Valid Fur All Operating Domains (References S and 8)

Excluding Singk Loop Operation 1.1 1.0 0. 9 k

0 4 0. 8 5

2 U ii 2 0. 7

?I!

8 zi Q.6 0. 5 0. 4 I

MAPCHGR(F) = MAPFAC(F)

• MAPLHGRstd FOR Two Loop Operation, > 70% WT MAPFAC(F) = The Minimum of EITHER 1.0 OR {0.0268 x (WT-70)/10+0.9732)

FOR Two Loop Operation, 5 70% WT MAPFAC(F) = ( 0. 6 ~ ~ 2 x wrmo)+o.m55 Where WT = % Rated Core Flow 3 0 4 0 5 0 6 0 7 0 8 0 9 0 1 0 0 3.10 Core Flow I% Rated)

Limerick Unit 1 Cycle 11 COLR COLR Limerick I, Rev. 3 Page 16 I

Flow Dependent MAPLHGR kfultipiier -WFAG(F) - SLO This Figure L?; Valid Far Single Loop Operation (References 2 and 8) 0. 9 0

U 9

9 0. 8 P

P i; 0. 7 MAPLHGR(F) = MAPFAC(F)

• MAPLHGRstd Q 5 b-LL g

FOR Single Loop Operation, 4

0. 6 MAPFAC(F) = The ~

~

n

~

r n

~

~

of EITHER 0.79 OR 0.6682 x @UT/100)+0+5055 0. 5 0. 4 3 0 4 0 S O 6 0 7 0 8 0 9 0 3.00 110 Core FLOW (% Rated)

Limerick Unit 1 Gyck 11 COLR COLR Limerick 1, Rev. 3 Page 17 I

5.0 MCPR LIMITS The MCPR values provided in Table 5-1 are referenced in Technical Specification 32.3. Table 5-1 is derived from the Reference 2 analyses arid is valid for all Cycle 11 fuel types and operating domains. Table 5-1 includes treatment of these MCPR limits for SLO. Bounding MCPR values are also provided for inoperable Rec~rcu~ati~n Pump Trip or inoperable Steam Bypass System. These two options represent the Equipment Out of Service conditions, The cycle cxposure, which represents EOR, is given in the iatest verified and approved Cycle ~ ~ a n a g e ~ n t Repart or associated Engineering Change Request.

ARTS provides for power-and Row-dependent thermal limit adjustments and multipliers. which altow for a more reliable administration of the MCPR thermal limit. The Row-dependent adjustment MCPR(F) is sufficiently generic to apply to all fuel types and operating domains (References 2 and 8). In addition, there are also two sets of power-dependent MCPR multipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (Reference 13). Section 8.0 contains the conditions for Turbine Bypass I Valve Operability. These adjustments and muitipliers are shown in Figures 5-1 through 5-3 and are referred to by Technical Specification 3.2.3. The MCPR(P) curves are independent of recirculation pump trip operability (Reference 13).

I

timeriek Unit 1 Cyde 11 COLR COLR Limerick 1, Rev. 3 1

Page 18 TABLE 5-1 Operating Limit Minimum Critical Power Ratio COLMCPR)

(References 2 and 5)

BOC to EUR -

TBV In Service and TBV ouc of Senlice RPT In Service (TBVOOS)

(RPTOOS)

RPT Out of Service I. When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

2. OLrylCPR limit set by the Single Loop Operation Recirculation Pump Seizure Analysis (Reference 2.)

3. This table is valid for all Cycfe I I Fuet types.

Limerick Unit X Cycle 11 COLR FIGURE 5-1 COtR Limerick I, Rev. 3 Page 19 I

Power Dependent MCPR Limit Adtjustmctnts And Muttipliers This Figure Is Valid For All Operating Domains except TBVQOS (References 2 and 13) 3. 6 3. 8 j cr:

4 k!

1.5 1.4 1.2 2.67 2.45 I 1.481 1.3 2 0 4 0 6 0 a 0 100 0

Power(% Rated)

I I

Limerick Unit 1 Cycle 11 COLR FIGURE 5-2 COLR Limerick 1, Rev. 3 Page 20 I

Power Dependent MCPR Limit Adjustments And Multipliers - TRVOOS This Figure Is Valid FOP The TBVOOS Operating brnain (References 2 and 13) 5. 0 4. 6 4. 2 g 3. 8 2

3 E 3. 4 E 3

!? 3.8 z

't:

P 3 2. 6 4

E y 1.1 1.8 1. 4 1.0 1

\\

1.37 0

a o 4 0 6 0 POW8X f % Rated)

Limerick Unit 1 Cycle if. COLR COLR Limerick 1, Rev. 3 I

Page 21 Flow Dependent MCPR Limits MCPR[F)

This Figure Is Valid For All Operating Domains (References 2 and 8) a. 0 0 For Two Loop Operation, MCPR(F) = The Maximum of EITHER 1.25 1.90 OR f -0.5784 x (W-IJIOO) 4" 1.7073) 1 - 8 0 WT = % Rated Core Flow 1.70 3 0 4 0 5 0 6 0 7 Q 8 0 9 0 1 0 0 i s a Core Flow (% Rated)

Limerick Unit 1 Cycle 11 COLR FGXL TYPE GE13 GE14 6.0 LINEAR HEAT GENERATION RATE LIAWTS MAXIMUM VALUE f 4.4 kU7/ft 13.4 kW/ft COLR Limerick 1, Rev. 3 Page 22 The maximum LHGR value for each fuel type for use in. Technical Specification 3.2.4 is given in Table 6-1 beiow. The LHGR is an exposure dependent value. Due to the proprietary nature of these values onty the maximum LWGR for each fuel type is listed in Table 6-1.

Limerick Unit 1 Cycle 11 COLK I

I Nominal Trip Setpoint I 13.4%

i COLR Limerick 1, Rev, 3 Page 23 1

i Allowable Value 7.0 COIVTROL ROD BLOCK SETPOINTS f 15.6%

Technical Specification Limiting Condition for Operation 3.3.4 requires control rod block i n 5 ~ ~ m e n ~ t i o n I

channels shall be OPERABLE with their trip,setpints consistent with the values show in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Ftow Upscale Trip is a cycle-specific value and as such is found in 'Fable 7-2 of this COLR. Table 7-2 lists the Noninaf Trip Setpoint and Aflowable Value. These setpoints are set high enough to aflow 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 ~ ~ ~ ~ i n t s / ~ I I o w a b l e 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 $0)

1. These setpoints (with Rod 3lock Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RVVE MCPR limit which is fess than or equal to the minimum cycfe OLMCPR (see COLR references 2 and 10).

Limerick Unit 1 Cycle 11 CULR P 225%

CULR Limerick 1, Rev. 3 1

Page 24 7

8.0 TORBINE BYPASS VALVE PARAMETERS The operability requirements for the steam bypass fystern for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Tables 8-1 and 8-2 (Reference 6 and 13). If these requiretnents cannot be met, the I MCPR, MCPR(P) and W F A C ( P ) limits for inoperable Steam Bypass System, known as Turbine 3ypass Valve Out Of Service, must be used.

TABLE 8-1 Turbine Bypass System Response Time (Reference 6)

Maximum delay time before start of bypass wlve opening following generation of the turbine bypass valve flow signat 0.1 I sec TABLE 8-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 13)

Reactor Power I

No. of Valves in Service

Limerick Unit 1 Cycle 11 COLR COLR Limerick I, Rev. 3 Page 25 9.0 STABILITY PROTECTION SETPOINTS The Limerick 1 Cycle 11 Oscillation Power Range Monitor (OPKM) 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.

Thesz values are based on the cycle specific analysis documented in Reference 14.

Any change to the OLMCPR vafue 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 appiicable when the associated Technical Specification (TS Trtble 3.3.1-1, Item 2 3 is implemented.

OPRM PBDA Trip Setpoints Corresponding Maximum Confirmation Count Trip Setuoint PBDATr~p A ~ ~ ~ i ~ u d ~

10.0 MODES OF OPERATION Limerick Generating Station has been analyzed to operate with a number of operational flexibility features, including Increased Core Flow, Maximum Extended Load Line Limit, Coastdown, EOC Recirculation Pump Trip and Option A/l3 MCPR Limits. Limerick Generating Station has also been analyzed to operate with a number of equipment out-of-service conditiom, including Turbine Bypass Valves OOS, Single Loop Operation, Feedwater Heating OOS, Final Feedwater Temperature Reduction and SafetylRefief Valves 00s (up to 2 of 14 safety/relief salves 00s). Operation is allowed in any combination of these operational flexibility features and equipment out-of-service conditions, with one EXCEPTION, which IS that Limerick may NOT operate with EOC-Recirculation Pump Trip out-of-service in conjunction wrth Turbine Bypas Valves 00s