ML20094R535

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Rev 2 to Ei Hatch Nuclear Plant Unit 1,Fuel Cycle 16 Colr
ML20094R535
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 10/26/1995
From:
GEORGIA POWER CO.
To:
Shared Package
ML20094R533 List:
References
NUDOCS 9512050012
Download: ML20094R535 (23)
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Text

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GEORGIA POWER COMPANY EDWIN'I. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPERATING LLMITS REPORT REVISION 2 i

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

< l 9512050012 951128 PDR ADOCK 05000321

__.P_.__ _ _.- . .. PDR ..

EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 i CORE OPERATING LIMITS REPORT EFFECTIVE PAGE LIST Unless noted otherwise, all pages are Revision 1.

4 Page Number Revision 16 2 1

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i i 10/26/95

EDWIN I. HATCH NUCLEAR PLANT [

UNIT I FUEL CYCLE 16 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS Section Title fast 1

1.0 Introduction 2.0 Rod Block Monitor I 3.0 APLHGR Limit 2 MCPR Limit 11 4.0 APRM Simulated Thennal Power Monitor 18 5.0 ~

Time Constant (',

6.0 References 18 l

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l ii Revision 1

TABLE OF CONTENTS (Continued)

LIST OF FIGURES Figure No. Title _P_agg 3-1 MAPFACF 3 3-2 MAPFACp 4 3-3 APLHOR Versus Average Planar Exposure (BP8DRB284H) S 3-4 APLHGR Versus Average Planar Exposure (GE9B-P8DWB330-10GZ-80M-150-T) 6 3-5 APLHGR Versus Average Planar Exposure (GE9B-P8DWB315-8G4.0-80M-150-T) 7 3-6 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 Exposme  ;

(GE13-P9HTB327-12GZ-100M-146-T-RECON) 10 1

( 4-1 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-RPT System inoperable during the last 2,000 mwd'st ofthe Operating Cycle) iii Revision 1

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TABLE OF CONTENTS (Continued) ( ,

LIST OF TABLES Table No. Ijilg past 4-1 TABLE OF OPERATING FLEXIBILITY OPTIONS 13 APPLICABILITY

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iv Revision I

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

1.0 INTRODUCTION

i The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 16 is I prepared in accordance with the requirements of Technical Specification 5.6.5.

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

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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) -

Technical Specification 3.2.1.

f c. Minimum Critical Power Ratio (MCPR) - Technical Specification 4 3.2.2. and 3.3.2.1.

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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

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. 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 < l.40.

4 Revision 1

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l Plant Hatch Unit 1 Fuel Cycle 16 .

l %re Operating Limits Report r,

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 APLIIGR limit taken from Figures 3-3 through 3-8, multiplied by the smaller of either:

a. The flow dependent multiplier, MAPFAC, 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 APLHGR 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.

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2 Revision 1

b Plant Hatch Unit 1 Fuel Cycle 16

. Core Operating Limits Report 1

e e t

$ i I 1.00 l 137%

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l mAPeiyLT e t A POR PLOW > e1% i f e eAe POR PLOW 5 41%

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! GAPRPD a (P) e RAletfUSA [1.e, A r + B p P )

P= PRACTIO8d 0F RATED ODIE PLOW

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5 CORE PLOW l

(% ItATED) AP Se

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'i i 0.40 30 40 50 00! 70 to 90 100 l e1

-l CORE FLOW (% rated) 1

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. i FIGURE 3-1  ;

MAPFACy I

l 3 Revision 1 i

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1 Plant Hatch Unit 1 Fuel Cycle 16 -

Core Operating Limits Report i

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1.0 i

i 0.9 l

s 0.0 I

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/e SMGLE LOOP OPERATION (SLO) 0.75 .- -------' I s 60% comE PLOW asAPLHost p e taAPPAC p

  • ABAPLHOR era g,7 j mAPLHOR sus e 5TANDARD MAPLHGR LatifS FoR 38% , P; NO THEntaAL LitNTS 800ftTORING REotARED (SLO. TLO) NO UteTS SPSCIPIED POR 20% 5 P a 30%:

(SLO,TLO)

ABAPPAC , e 0.585

  • 9.008334 (P . 30%)

Pon s ses coat eLow l

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M4PFAC con Poa m s P:(TLo) o m coP= 0A.83 E rto

  • 8A.05234 (P 30%)

I I0.s on con m s P < s3%:(Sto) l l mAmc . 54 * . uu iP . im

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con m 5 r: cSLo) mAme ,. ..n 0.4 l l l l l$ l l l 20 25 30 40 80 80 70 80 90 100 POWER (% rated)

FIGURE 3-2 MAPFACp

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4 Revision I

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

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- sesonsse4H(so un. CHANNELS) 8.s 0 5 10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPO 6URE(GW@st)

FIGURE 3-3 ,

AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: BP8DRB284H) 5 Revision I

Plant Hatch Unit 1 Fuel Cycle 16 -

Core Operating Limits Report

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F OF AVERAGE PLANAR FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB330-10GZ-80M-150-T)

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6 Revision 1

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

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J FIGURE 3-5 i AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB315-8G4.0-80M-150-T) 7 Revision 1 4

Plant Hatch Unit 1 Fuel Cycle 16 .

! Core Operating Limits Report

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AVERAGE PLANAR EXPO 6URE(GWdist)

FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T)

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8 Revision 1

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

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! NO11: AVERAGE PLANAR EXPOSURE (GW@st) l@?uk*fn',#tEV"7'L' Lou OF AVERACE PLANAR EXPOSURE 1

FIGURE 3-7

, AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fwel Type: GE9B-P8DWB331-10GZ-80M-150-T) 9 Revision 1

Plant Hatch Unit 1 Fuel Cycle 16 ,  :

Core Operating Limits Report '

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GE13-P9HTB327-12GZ-100M-146-T-RECON) t 10 Revision 1

- . _ . _ . . . .- . . . . _ -_ .-. _~

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. 1 Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Repon 4.0 . MCPR LIMIT (Technical Specification 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, 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 of equipment operablity, scram times, core flow and core power is determined as follows: i For 25% 5 power < 30%, the OLMCPR is given in Figure 4-1.

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

j A) The flow-dependent MCPR limit determined from the applicable maximum core flow limit line of Figure 4-2, or B) The product of the values from Figures 4-1 and the applicable Figure 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

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 dependent curves.

i i 11 Revision 1

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Plant Hatch Unit 1 Fuel Cycle 16

. Core Operating Limits Report 7

The average scram time of the control rods, t, is defined as:

Tave " TB t = 0, or , whichever is greater TA*TB where: T4 = 1.084 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36) 1/2 ta = p + 1.65

  • a + ,'

[ N'.

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

[ Nit, t . = '- '

EN' s.s where: n = number of surveillance tests performed to date in the cycle N i= number of active control rods measured in the ith surveillance test t i= average scram time to notch 36 of all rods in the ith surveillance test N i= total number of active rods measured in Technical Specifications Surveillance Requirement SR 3.1.4.1.

k 12 Revision 1

4 Plant H:tch Unit 1 Fuel Cycle 16 Core Operating Limits Report

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TABLE 4-1 TABLE OF OPERATING FLEXIBILITY OPTIONS APPLICABILITY i

! WITH: .

-- USE: <

EOC RPT Turbine Bypass Valves Operable Operable Figure 4-3 ,

Inoperable, BOC to EOC - 2000 Operable Figure 4-3 Inoperable,

. EOC - 2000 Operable Figure 4-4 i to extended EOC 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 and intermittent operation with reduced feedwater temperature are included in the MCPR limits presented in Figures 4-3 through 4-4.

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. 13 Revision 1 i

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

['I l l

l 2.s

> 80% FLOW 2.5 -

OPERAT#ee Literf teCPR(P)e Kp
  • 0PERATING Liteff IscPit(see) '

l POR P e RSW 000 TNama4AL LaserTS ns0Nff0Ree0 R50UeREO

  • NO LastTs sPEcm 2.4 ~

. POR 28% s P e P eveses (WNERE P owmee e Se% POR HNP .1. 2) l 4 = (Kew + e.ea(sen.P3) s OLascPR ties)

, ANO 2.3 - l mov,. t.se post s ses c0RE PLOW e Keve e IAs POR > 6e% CORE PLOW

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j POR 30% s P e 46%-

' K,=1.se+e.e134less.P) 2.2 ~

N j POR 45% s P e sek e- K, 1.1s + e.seest (ses.P) k 00% FLOW POR s0% s P:

I1 - K, a 1.s + e.es375 (1e0%. P) w- - l Mb 2.0 I _

h u- 1.59 l f - ,i ,

1.4 g

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_  : P .v j. j j 10 l l . . l , , l . . . . . .' ,

20 25 30 40 60 60 70 00 90 100 POWER (% RATED) l l

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FIGURE 4-1 .

't POWER-DEPENDENT MCPR MULTIPLIER (Kp)

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k 14 Revision 1 l

l_ _ __- - - _ ___ _ _______ _ - - _ __ _ _ _ ____ - -__ _ _ _-__ - ___ - _ - _ .

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1 Plant Hatch Unit 1 Fuel Cycle 16 i

Core Operating Limits Report l

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i i i i i pon so.tuamsconsnaur)aaos 11fu nway)emAx(tanusee#sese og ,

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1.6 L

,. main- u =

5 111A 4A.S

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3 . . . g . . . g . . . , . , , 4 . . . g . . . ,,, ,

l cone FLowm ene P

FIGURE 4-2 ,

FLOW-DEPENDENT MCPR LIMITS, MCPR(F) 15 Revision 1

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report 1.42 l l l l l l l I l 1A0 GE13 LUA 1.38 ,

1.36 ,

1.34 l l l  ! l 1.32 ,

g GE9B g j l l I I g 1.30 1.2s I I

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I' j i  !' I I i 1.22 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 O.0 TAU ( t )

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 either EOC-RPT System Operable or with EOC-RPTSystem Inoperable up to EOC-2,000 mwd /st) ,

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16 Revision 2

Plant Hatch Unit 1 Fuel Cycle 16.

- . Core Operating Limits Report r

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4 us -

1A4 I' GetsLuA /

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! us 0.8 0.0 1.0

' O.0 0.1 0.2 0.3 OA 0.5 0.8 0.7 l TAU (t )

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

)

1 FIGURE 4-4

MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME i (with Turbine Bypass Valves Operable and with EOC-RPTSystem Inoperable during the last 2,000 mwd /st of the Operating Cycle)

! 17 Revision 1

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. l Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report  ;

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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-240l l-

. 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 % Facility Operating License NPF Edwin I.

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

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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," NFDC-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.

k 18 Revision 1

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