ML20086S727

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Core Operating Limits Rept for Fuel Cycle 16, Ei Hatch Nuclear Plant Unit 1,Rev 1
ML20086S727
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/28/1995
From:
GEORGIA POWER CO.
To:
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ML20086S718 List:
References
NUDOCS 9508020103
Download: ML20086S727 (50)
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Text

..

EDWIN I. HATCH NUCLEAR PLANT i UNIT 1  !

CORE OPERATING LIMITS REPORT for FUEL CYCLE 16 I

Revision 1 EBRSE8682Zi8?ssu

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i f

l GEORGIA POWER COMPANY ,

EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPERATING LIMITS REPORT

. REVISION 1

  • i I

f Southem Nuclear Operating Company Post Office Box.1295 Bimdngham, Alabama 35201

EDWIN 1. HATCH NUCLEAR PLANT i UNIT 1 FUEL CYCLE 16 CORE OPERATING LIMITS REPORT f

a EFFECTIVE PAGE LIST l Unless noted othenvise, all pages are Revision 1.

l I

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i i

t' 7/13/95

EDWIN I. HATCH NUCLEAR PLANT UNIT I FUEL CYCLE 16 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS .

Section Title Pagg l.0 Introduction 1 2.0 Rod Block Monitor 1 3.0 APLHGR Limit 2 4.0 MCPR Limit 11 5.0 APRM Simulated Thermal Power Monitor 18

) Time Constant 6.0 References 18 I

l ii Revision 1

. . 4 . ,a.. 4 4m. _.m e

,- j I

TABLE OF CONTENTS (Continued)

LIST OF FIGURES Finure No. Titig Eggs 3-1 MAPFACr 3

3-2 MAPFACp i 4 I i

3-3 APLHGR Versus Average Planar Exposure (BP8DRB284H) 5 3-4 APLHGR Versus Average Planar Exposure (GE9B-P8DWB330-10GZ-80M-150-T) 6

  • r 3-5 APLHGR Versus Average Planar Exposure (GE9B-P8DWB315-8G4.0-80M-150-T) 7  ;

3-6 -t APLHGR Versus Average Planar Exposure .

(GE9B-P8DWB314-8G4.0-80M-150-T) 8 '

3-7 APLHGR Versus Average Planar Exposure  ;

(GE9B-P8DWB331-10GZ-80M-150-T) 9 ,

3-8 APLHGR Versus Average Planar Exposure I

(GE13-P9HTB327-12GZ-100M-146-T-RECON) 10 4-1 i Power-Dependent MCPR Multiplier (Kp) 14 4-2 Flow-Dependent MCPR Limits (MCPRF) 15 4-3 MCPR Limit as Function of Average Scram Time 16 (with Turbine Bypass Valves Operable and with ,

either EOC-RPTSystem Operable or with EOC-RPT .

\

System inoperable up to EOC - 2,000 mwd /st) 4-4 MCPR Limit as Function of Average Scram Time 17 (with Turbine Bypass Valves Operable and with EOC-RPTSystem Inoperable during the last 2,000 MWdht ofthe Operating Cycle)

~

m Revision 1 i

.- , - l

TABLE OF CONTENTS (Continued)

LIST OF TABLES Table No. g 4-1 TABLE OF OPERATING FLEXIBILITY OPTIONS 13 APPLICABILITY l

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iv Revision 1

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EDWINI. HATCH NUCLEAR PLANT l UNIT 1 FUEL CYCLE 16  !

CORE OPERATING LIMITS REPORT J

1.0 INTRODUCTION

1 The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 16 is'  !

prepared in accordance with the requirements of Technical Specification 5.6.5.'

The core operating limits presented herein were developed using NRC-approved  !

methods (References 1 and 2). Results from the fuel vendor's reload analyses for the fuel in Unit 1 Cycle 16 are documented in References 3 and 4.

l The following cycle-specific core operating limits are included in this report:

a. Control Rod Block Instrumentation - Technical Specification 3.3.2.1.  !
b. Average Planar Linear Heat Generation Rate (APLHGR) -

l Technical Specification 3.2.1.

c. Minimum Critical Power Ratio (MCPR) - Technical Speci6 cation 3.2.2. and 3.3.2.1.
d. APRM Flow Biased Simulated Thermal Power - High, time constant - Technical Specifications Surveillance Requirement SR 3.3.1.1.14.

2.0 ROD BLOCK MONITOR (Technical Specification 3.3.2.1)

Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.2.1 and when:

a. THERMAL POWER is 229% and < 90% of RATED THERMAL POWER, and the MCPR is < l.70.

or

b. THERMAL POWER is 2 90% ofRATED THERMAL POWER and the MCPR is < 1.40.

Revision 1

1 Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 3.0 APLHGR LIMIT (Technical Specification 3.2.1)

The APLHGR limit for each fuel type is given by the applicable rated-power, rated-flow APLHGR limit taken from Figures 3-3 through 3-8, multiplied by the smaller ofeither:

a. The flow dependent multiplier, MAPFACp from Figure 3-1, or
b. The power dependent multiplier, MAPFACp from Figure 3-2.

For the fuel types whose APLHGR limits are shown in Figures 3-3 through 3-8, the APLHGR limit shall be applied to each axial location in the fuel assembly.

As required by GESTAR (Reference 1), the hand-calculated APLHGR values for a multi-lattice (i.e., GE9-330, GE9-331, and GE13-LUA) fuel must be less than or equal to the APLHGR limits shown in Figures 3-4,3-7 and 3-8, respectively. When APLHGR values are determined by the process computer, the lattice-dependent APLHOR limits are used. Under these conditions, some axial locations may have APLHGR values exceeding the values shown in Figures 3-4,3-7, and 3-8.

l i

2 Revision 1

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Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Repon 1.o0 - '

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FIGURE 3-1 5 MAPFACp 3

Revision 1 1

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FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type:BP8DRB284H) 5 Revision 1

l Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report i I

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VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB330-10GZ-80M-150-T) 6 Revision 1

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Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

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Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report n Y

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Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

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FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE13-P9HTB327-12GZ-100M-146-T-RECON) 10 Revision 1

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report i

4.0 MCPR LIMIT (Technical Specification 3.2.2)

The MCPR operatin2 limit (OLMCPR) is a function of core power, core fl average scram time, fuel type, number of opreing recirculation loops, operability of end-of-cycle recirculation pump trip (EOC-RPT) system, and operability of turbine bypass valves. "

With both recirculation pumps in operation (TLO), the OLMCPR for each fuel ^

type with various combinations ofequipment operablity, scram times, core flow and core power is determined as follows:  ;

i For 25% s power < 30%, the OLMCPR is given in Figure 4-1.

Forpower 2: 30%, the OLMCPR is the greater of either:

i A) The flow-dependent MCPR limit determined from the applicable i maximum core flow limit line ofFigure 4-2, o

or i

B) The product ofthe values from Figures 4-1 and the applicable Figure i 4-3 through 4-4 as determined by Table 4-1.

A3 stated in th; note on Figures 4-3 through 4-4, with one recirculation pum operating (SLO), the calculated operating limit MCPR determined above, is {

increased by 0.01.  ;

i In Figures 4-3 through 4-4, Option A scram time MCPR limits' correspond to  !

t = 1.0, where t is determined from scram time measurements performed in accordance with Technical Specification SR 3.1.4.1 and SR 3.1.4.2. Option B  !

values correspond to t = 0.0. For scram times between Option A and Option B,  ;

the MCPR limit for each fuel type corresponds to T. Ift has not been determined, Option A limits are to be used. Refer to Table 4-1 to determine the l j

applicable set of fuel-type dependent curves. "

i 11 Revision 1 l

_~ _ _ _ _~ -

-. 1

}

Plant Hatch Unit 1 Fuel Cycle 16 4 Core Operating Limits Report i The average scram time of the control rods, t, is defined as:

l Teve

, limit to notch 36)  !

' ~

l v1 Na ta = + 1.65

  • o * ,

[N,

. .i .

where:

p = 0.822 sec (mean scram time used in the transient analysis) o = 0.018 sec (standard deviation of )

E MT, x, <;

M E..i where: I n = number of surveillance tests performed to date in the cycle -

l N i = number of active control rods measured in the ith surveillance test ta = average scram time to notch 36 of all rods in the ith surveillance test l

.i N i= total number of active rods measured in Technical Specifications Surveillance Requirement SR 3.1.4.1.  !

12 Revision 1

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report TABLE 4-1 TABLE OF OPERATING FLEXIBILITY OPTIONS APPLICABILITY

'WITH:

' EOC RPT 1USE:. y Turbins BypassValves: - -

Operable Operable Figure 4-3 Inoperable, BOC to EOC- 2000 Operable Figure 4-3 Inoperable, EOC - 2000 Operable Figure 4-4 to extended EOC Operable Notlicen2ed for this Inoperable operating cycle.

Isoperable Notlicensed for this Inoperable operating cycle.

NOTE:

Operation within the licensed power / flow region with a single recirculation loop and intermittent operation with reduced feedwater temperature are included in the MCPR limits presented in Figures 4-3 through 4-4.

1 13 Revision 1

l e

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report i

i 2.8 -

> $0% FLOW }

2.5 -

e

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l OPERATsee Lherf 94CPRfP)e Kp *OPERATNeo UMrf heCPRitte) 2.4

  • POR P e 18%: 0e0 THamasAL undrtS 800Nf70Rede REQueRED

. MO unerfs sPectrisO

. j FOR f 8% s P e P emas twMent P swame a 30% POR HeeP.1.2) ~

2.3 .

e ANOMe a (Msw e e.e2(30% . P)) i OLAICPR (100) new e 2.se POR s ses costa PLOW i

Mew e 2Ae POR > se% CORE PLOW I l Polt 30% s P e es%:

2,2

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  • e.e134 (48%. P)
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u. l l

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. N W 20 25 30 40 so go 70 80 to 100 POWER (% RATED) i i

I FIGURE 4-1 .

POWER-DEPENDENT MCPR MULTIPLIER (Kp) 14 Revision 1

1 i

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report '

l

)

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1.7

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- PORW.(% AATEDCOREPLOw)a4 5 117%

~ 18CPR(P)= ttAX(1.30.MW.it 9f) u t "

, .r. max ,w. = =

193.9 % 117A

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.=

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j 30 40 ..............................

80 00 70 80 to 100 110 120

cone nowm w>

FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS, MCPR(F) 15 Revision 1 3

4 l Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 1A2 l I I l l l l l l 1Ao cais tuA II l

1.38 I

1Je

1.u 1.32 1 8s y 1.30 g

g l

1.25 e

g r i

l l GE7s "

1.26 i 1.24 1.22 0.0 0.1 0.2 0.3 OA 0.5 0.6 0.7 0.8 0.9 1A TAU ( t )

Note: For SLO, increase the MCPR Limit obtained from this figure by 0.01.

l FIGURE 4-3 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable and with eitherEOC-RPT System Operable or with EOC-RPTSystem Inoperable up to EOC-2,000 mwd /st) 16 Revision 1

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 1A l l 1A8 cessLur

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" l 85 0.2 c.2 i

ed o.s o.s o.7 a.: a.: s.,

TAU (t )

Note:

For SLO, increase the MCPR Limit obtained from this figure by 0.01.

FIGURE 4-4 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable and with EOC-RPTSystem inoperable during the last 2,000 mwd /st ofthe Operating Cycle) 17 Revision 1

.4 Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 5.0 APRM SIMULATED THERMAL POWER MONITOR TIME CONSTANT (Surveillance Requirement SR 3.3.1.1.14)

The allowable value for the APRM Simulated Thermal Power Monitor Time Constant is s 7.0 seconds.

6,.0 REFERENCES

1. " General Electric Standard Application for Reactor Fuel," NFDE-24011-P-A-10-US, March 1991.
2. Letter, L. P. Crocker (NRC) to W. G. Hairston (GPC), " Issuance of Amendment No.168 to Facility Operating License DPR-57 and Amendment No.106 to Facility Operating License NPF Edwin I.

Hatch Nuclear Plant Units 1 and 2 (TACS 73614 and 73615)," December 29,1989.

3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 1, Reload 15, Cycle 16," General Electric Document 24A5156. Revision 1, January 1995.

4.

"Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR - LOCA Loss-of Coolant Accident Analysis," WDC-31376-P, December 1986.

5. " Safety Evaluation by the Office ofNuclear Reactor Regulation Supporting Amendment Nos.151 and 89 to Facility Operating Licenses DPR-57 and NPF-5," dated January 22,1988.

18 Revision 1

Enclosure 2 Edwin I. Ilatch Nuclear Plant Unit 2 Cycle 12 Core Oncrating Limits Renort. Revision 2 i

)

E2-1

a*

b e

Enclosure 2 Edwin I. Hatch Nuclear Plant Unit 2 Core Operating Limits Report i

for Fuel Cycle 12 Revision 2

i EDWIN I. HATCH NUCLEAR PLANT UNIT 2 CORE OPERATING LIMITS REPORT for FUEL CYCLE 12 l

Revision 2 s

GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT ,

, REVISION 2 7

1 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201

EDWIN L HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT EFFECTIVE PAGE LIST Unless noted otherwise, all pages are Revision 2.

i l

i i 7/13/95

EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS Section Iitic P. age 1.0 Introduction 1 2.0 Rod Block Monitor 1 3.0 APLHOR Limit 2 4.0 MCPR Limit i1 5.0 APRM Simulated Thermal Power Monitor 18 Time Constant 6.0 References 18 ii Revision 2

E '.

l

-l TABLE OF CONTENTS (Continued) ,

LIST OF FIGURES Fiante No. g 3-1 MAPFACp 3'  :

3-2 MAPFACp 4 3-3 APLHGR Versus Average Planar Exposure (GE7B-P8DRB284-7G4.0-80M-150-T) 5 3-4 APLHGR Versus Average Planar Exposure i (GE8B-P8DQB296-7GZ-80M-150-T) 6  ;

I 3-5 APLHGR Versus Average Planar Exposure -

(GE9B-P8DWB314-7G4.0-80M-150-T-NOSHIP) 7 i i

3-6 APLHGR Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0-80M-150-T) 8 3-7 APLHGR Versus Average Planar Exposure (GE11-P9 HUB 293-7G5. 0/1G4.0-100M-146-T-L UA) 9 3-8 APLHGR Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0A-80M-150-T) 10 4-1 Power-Dependent MCPR Multiplier (Kp) 14 4-2 Flow-Dependent MCPR Limits (MCPRp) 15' 4-3 MCPR Limit as Function ofAverage Scram Time 16-l (with Turbine Bypass Valves Operable and with

{

EOC-RPTSystem Operable) 4-4 MCPR Limit as Function ofAverage Scram Time 17 (with Turbine Bypass Valves Operable and with EOC-RPTSystem Inoperable)

I iii Revision 2

I

'O TABLE OF CONTENTS (Continued)

LIST OF TABLES l

Table No. Iitig Eggg l i

4-1 TABLE OF OPERATING FLEXIBILITY OPT [ONS 13 l APPLICABILITY i

e 1

I

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t l

2 l

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r iv Revision 2

_ til i;s . l grb EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT

1.0 INTRODUCTION

The Core Operating Limits Report (COLR) for Plant Hatch Unit 2 Cycle 12 is prepared in accordance with the requirements ofTechnical Specification 5.6.5.

The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2). Results from the fuel vendor's reload analyses for the fuel in Unit 2 Cycle 12 are documented in References 3 and 4.

The following cycle-specific core operating limits are included in this report:

a. Control Rod Block Instrumentation - Technical Specification 3.3.2.1.
b. Average Planar Linear Heat Generation Rate (APLHGR) -

Technical Specification 3.2.1.

c. Minimum Critical Power Ratio (MCPR) - Technical Specification 3.2.2. and 3.3.2.1.
d. APRM Flow Biased Simmiated Thermal Power - High, time constant - Technical Specifications Surveillance Requirement SR 3.3.1.1.14.

2.0 ROD BLOCK MONITOR (Technical Specification 3.3.2.1)

Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.2.1 and when:

a. THERMAL POWER is 2 29% and < 90% of RATED THERMAL POWER, and the MCPR is < l.70.

or

b. THERMAL POWER is 2 90% of RATED THERMAL POWER and the MCPR is < 1.40.

Revision 2

1 Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 3.0 APLHGR LIMIT (Techalcal Specification 3.2.1)

The APLHGR limit for each fuel type is given by the applicable rated-power, rated-flow APLHGR limit taken from Figures 3-3 through 3-8, multipt'ed by the smaller of either:

a. The flow dependent multiplier, MAPFACp from Figure 3-1, w
b. The power dependent multiplier, MAPFACp from Figure 3-2.

For the fuel types whose APLHGR limits are shown in Figures 3-3 through 3-8, the APLHGR limit shall be applied to each axial location in the fuel assembly.

As required by GESTAR (Reference 1), the hand-calculated APLHGR values for a multi-lattice (i.e., GE8-296 and gel 1-LUA) fuel must be less than or equal to the APLHGR limits shown in Figures 3-4 and 3-7 respectively. When APLHGR values are determined by the process computer, the lattice-dependent APLHGR limits are used. Under these conditions, some axial locations may have APLHOR values exceeding the values shown in Figures 3-4 and 3-7.

2 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12 l Core Operating Limits Report  !

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FIGURE 3-1 MAPFACy 1 i

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1 3 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 1A i

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.e Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report i

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AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE7B-P8DRB284-7G4.0-80M-150-T) 5 Revision 2

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1 FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE8B-P8DQB296-7GZ-80M-150-T) l 1

6 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12 I l

Core Operating Limits Report

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(Fuel Type: GE9B-P8DWB314-7G4.0-80M-150-T-NOSHIP) 7 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12

- Core Operating Limits Report l 13 2 1

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FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 1

VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T) 8 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report I -

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Ties IS THE APLHOR Uts7 POR THE es0ST UtImMS LATTICE AS A PuMCTION OF AVERAGE PLANAR EXPO 5uRE FIGURE 3-7 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE11-P9 HUB 293-7G5.0/1G4.0-100M-146-T-LUA) 9 Revision 2

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FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0A-80M-150-1) 10 Revision 2

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Plant Hatch Unit 2 Fuel Cycle 12.

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' Core Operating Limits Report A

4.0 MCPR LIMIT (Technical Specifleation 3.2.2)

The MCPR operating limit (OLMCPR) is a function of core power, core flow, average scram time, fuel type, number of operating recirculation loops, j

operability of end-of-cycle recirculation pump tsp (EOC-RPT) system, and ,

operability of turbine bypass valves.

With both recirculation pumps in operation (TLO), the OLMCPR for each fuel - t type with various combinations ofequipment operablity, scram times, core flow and core power is determined as follows:

For 25% s power < 30%, the OLMCPR is given in Figure 4-1.

For power 2 30%, the OLMCPR is the greater of either:

A) He flow-dependent MCPR limit determined from the applicable maximum core flow limit line ofFigure 4-2, l

\

B) The product of the values from Figures 4-1 and the applicable Figure I 4-3 through 4-4 as determined by Table 4-1.

As stated in the note on Figures 4-3 through 4-4, with one recirculation pump l operating (SLO), the calculated operating limit MCPR determined above, is '

increased by 0.01. )

In Figures 4-3 through 4-4, Option A scram time MCPR limits correspond to T = 1.0, where t is determined from scram time measurements performed in accordance with Technical Specification SR 3.1.4.1 and SR 3.1.4.2. Option B values correspond to t = 0.0. For scram times between Option A and Option B, the MCPR limit for each fuel type corresponds to T. If T has not been determined, Option A limits are to be used. Refer to Table 4-1 to determine the applicable set of fuel-type depen ~dent curves.

I1 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12 '

t Core Op.. ding Limits Report l

' 1

. The average scram ti ne of the control rods, t, is defined as:

i i

Tav,* TB t = 0, or , whicheveris greater j TA*TB i where: TA = 1.084 sec (Technical Speci6 cation 3.1.4, Table 3.1.4-1, scram time

  • limit to notch 36) i 1/2 Ta = p + 1.65
  • a
  • Ni

[N, l

. t-n .

where: p = 0.822 sec (mean scram time used in the transient analysis)  ;

i e = 0.018 sec (standard deviation of )

. 1

[Nic, t,,,=<-',

[Ni where: n = number of surveillance tests performed to date in the cycle i

N i = number of active control rods measured in the ith surveillance test i

t i= average scram time to notch 36 ofall rods in the ith surveillance test N i= total number of active rods measured in Technical Specifications Surveillance Requirement SR 3.1.4.1.

1 12 Revision 2 i

d' ' l' Plant Hatch Unit 2 Fuel Cycle 12

- Core Operating Limits Report i

l l'

, TABLE 4-1 TABLE OF OPERATING FLEXIBILITY OPTIONS APPLICABILITY l

WITH::. v . 3. ,  : USE:n

' :EOC RPT CTurbine Byp=== Valves x  : <- '

Operable Operable Figure 4-3 Inoperable Operable Figure 4-4 Not licensed for this Operable Inoperable operating cycle.

Not licensed for this Inoperable Inoperable operating cycle.

NOTE:

Operation within the licensed power / flow region with a single recirculation loop l and latermittent operation with reduced feedwater temperature are included in the MCPR limits presented in Figures 4-3 through 4-4. .l l

l 1

i l

13 Revision 2

l e i I

Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 1

2.8

>50% FW 2.5 - g

,  ; , OPERATING LMff MCPR[P) e Kp ' OPERATW80 LAST R4CPR(100) e

' POR P e 29%: NO TWueAL LBMTS 4AONITO8tsee AEGLARED 24 NO LattrB SPSCE'W -

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1.0 20 25 30 h 50 80 [0 90 90 100 POWER (% RATED)  !

l FIGURE 4-1 l

POWER-DEPENDENT MCPR MULTIPLIER (Kp) 14 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report

)

1.7

~ '

Pon we(% nano come Puntia se%

11T%

IsCPHfP)e RIAX(1.30. Af weites + Sf) 1 3 187 % ISAIPLOW Af pf 1922 % i1TA 4 232 9,gge etta 4.003 t,y47 1.5 \ <m I 1e1.s 4.ses 1.ser ist.s 4 271 1.ses

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) conenowmr e FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS, MCPR(F) 15 Revision 2

Plant Hatch Unit 2 Fuel Cycle 12

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Core Operating Limits Report i

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Note: For SLO, increase the MCPR Limit obtained from this figure by 0.01.

FIGURE 4-3 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable and with EOC-RPTSystem Operable) 16 Revision 2

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Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report c ,

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Note: For SLO, increase the MCPR Limit obtained from this figure by 0.01.

FIGURE 4-4 l MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable and with EOC-RPTSystem Inoperable) 17 Revision 2

w , a c

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y, Plant Hatch Unit 2 Fuel Cycle 12 t

Core Operating Limits Report l

l

[

5.0 APRM SIMULATED THERMAL POWER MONITOR TIME CONSTANT (Surveillance Requirement SR 3.3.1.1.14) '

The allowable value for the APRM Simulated Thermal Power Monitor Time Constant is s 7.0 seconds.

I

6.0 REFERENCES

i

)

1. " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-10-US, March 1991. .

l

2. Letter, L. P. Crocker (NRC) to W. G. Hairston (GPC), " Issuance of Amendment No.168 to Facility Ogaing License DPR-57 and j Amendment No.106 to Facility Operating License NPF Edwin I.  !

Hatch Nuclear Plant Units 1 and 2 (TACS 73614 and 73615)," D-=M 29,1989.

3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 2, Reload 11, Cycle 12," General Electric Document 23A7241. Revision 1, January 1995.-
4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR - LOCA Loss-ofCoolant Accident Analysis,"NFnC-31376-P, December 1986.
5. " Safety Evaluation by the Office ofNuclear Reactor Regulation Supporting Amendment Nos.151 and 89 to Facility Operating Licenses DPR-57 and NPF-5," dated January 22,1988. i i

1 18 Revision 2

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