ML20111A955

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Ei Hatch Nuclear Plant Unit 1,Cycle 17 Colr
ML20111A955
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/07/1996
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20111A951 List:
References
NUDOCS 9605140104
Download: ML20111A955 (22)
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Text

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GEORGIA POWER COMPANY EDWIN L HATCH NUCLEAR PLANT UNIT 1 CYCLE 17 CORE OPERATING LIMITS REPORT Revision 0 I

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

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9605140104 960507 PDR ADOCK 05000321 p PDR

l Edwin I. Hatch Nuclear Plant Unit 1 Cycle 17 Core Operating Limits Report i i

TABLE OF CONTENTS 1

Section 31tle East l 1.0 Introduction 1 2.0 Rod Block Monitor 1 3.0 APLHGR Limit 2 l

4.0 MCPR Limit  ;

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5.0 APRM Flow Biased Simulated Thermal Power - High '

18 Time Constant 6.0 References 18 1

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TABLE OF CONTENTS (Continued)

LIST OF FIGURES Figure No.

Iills P.agt 3-1 MAPLHGR Multiplier (MAPFACp ) Versus Core 3 Flow 3-2 MAPLHGR Multiplier (MAPFACp ) Versus Core 4 Power 3-3 APLHGR Versus Average Planar Exposure (GE9B-P8DWB330-10GZ-80M-150-T) 5 3-4 APLHGR Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0-80M-150-T) 6 3-5 APLHGR Versus Average Planar Exposure (GE9B-P8DWB331-10GZ-80M-150-T) 7 3-6 APLHGR Versus Average Planar Exposure (GE13-P9HTB327-12GZ-100M-146-T-L UA-RECON) 8 3-7 APLHGR Versus Average Planar Expost.re (GE9B-P8DWB346-10GZ-80U-150-T) 9 3-8 APLHGR Versus Average Planar Exposure (GE12-P10HSB331-6G5.0/4G4.0-100T-150 '!) 10 4-1 MCPR Multiplier (Kp) Versus Core Power 14 4-2 MCPR Limits (MCPRs) Versus Core Flow 15 4-3 MCPR Limit Versus Average Scram Time 16 (with Turbine Bypass Yahes Operable andEOC-RPT System Operable) 4-4 MCPR Limit as Function of Average Scram Time 17 (with Turbine Bypass Valves Operable andEOC-RPT SystemInoperable) ii Revision 0

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TABLE OF CONTENTS (Continued)

LIST OF TABLES Table No. Title Eage 4-1 Operating Flexibility Options Applicability 13 1

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l Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report

1.0 INTRODUCTION

! (

. The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 17 is prepared in  !

accordance with the requirements of Technical Specification S.6.5. This document was l

also produced in accordance with the requirements of BWRCA procedure BCA 40-10 and is documented in a DRF under QA No. NFS-96-029. 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 17 are documented in References 3 and 4.

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

a. Control Rod Block Instrumentation - Technical Specification 3.3.2.1
b. Average Planar Linear Heat Generation Rate (APLHGR) - Technical Specification 2.1 I
c. Minimum Critical Power Ratio (MCPR) - Technical Specifications 3.2.2 and 3.3.2.1
d. APRM Flow Biased Simulated Thermal Power - High - Technical Specifications Surveillance Requirement 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 MCPR is < l.70; or
b. Thermal Power is 2 90% of Rated Thermal Power, and MCPR is < l.40.

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Plant Hatch Unit 1 Cycle 17 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 of either:

a. The flow-dependent multiplier, MAPFACr, 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 fuel (i.e., GE9-330, GE9-331, GE13-LUA, GE9-346, and GE12-331) must be less than or equal to the APLHGR limits shown in Figures 3-3, 3-5, 3-6,3-7, 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 3-3,3-5,3-6,3-7, and 3-8.

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Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report i i

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///A--

Ell ms \

0.se jl((f[

im W

l 020 s

! cArucc,.M,wAo Maruma g i _ _ . _ _ _ _ _

w I MAPPAC,a MBAK2d N. MAPtM.7,]

3 0.70 l <

l l MAPMULTr e1 A POR PLOW > 81% 1

. = ,an Ptow s.m l Mparo, (r).MeeMtas [1.o,4+ s, p3 l 0.60

,, e a,u m cong a MAXNUM i cons rum l (Y. RATM As op 0.50 l 1er.s oAssi o.s7e4 l l 107.o cAs74 OA758 j i 112.0 04214 tLeso7 l 117A 0.3020 0.8806 1

, . ,1 M @ H N N N N

.2 CORE FLOW (% rated)

FIGURE 3-1 MAPLHGR MULTIPLIER (MAPFACr) VERSUS CORE FLOW 3 Revision 0

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Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.0 l

l 0.9 i 0.5 i ig

/

!, spe0LE LOOP oPsRAftcel(sto)

$ 0.75 - = - -

0.7 f t uP na " Mu"e"ru*an%n

    • "u.*.*'

l g m , ,,, g w m m aggyggo k

I"'

s'P 4 30%:

$ I asAPPAc, = e.ses . esostad (P.30%)

  • j Ponsso% consFLow l0 E

p, i j ...

c.. . v.=>

g' l T M # N oi 2'

p i .mc.. . 4=>

I = =srt=>= "c'*"

,/ \

% . m consnow l o.4 g

52 20 26 30 40 50 80 70 00 90 100 POWER (% rated)

FIGURE 3-2 MAPLHGR MULTIPLIER (MAPFACp) VERSUS CORE POWER 4 Revision 0

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I l l Plant Hatch Unit 1 Cycle 17 i i Core Operating Limits Report l

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M L u

j q UNACCEPTABLE EXPOSURE OPERATION  !

. COORDINATES

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11 X Y E ROD 11.52 51 I5 k g'

a

:' 1. ,1.

100 12.10

$.0 N 9

E00 12.52 g\

"E ll" ACCEPTABLE J *= 1105 OPERATION

. l 100 1119 .

. ; 10.00 1130

. ; l 11s0 1138 1 7 _; 1s.00 1112

. 20.00 12.44 g

. 2s.00 11.n 3s.00 tais K

! GE9B-PSDWB33010GZ 80M 180 T

, a 4s.co a.7s

\

st.e4 s.70 l

e s in is 20 2s 30 as # # so AVERAGE PLANAR EXPOSURE (GWdM)

MOST UMTING LATTICE AS A FUNCTION OF AVERAGE PLANMt expom=

FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB330-10GZ-80M-150-T) 5 Revision 0

Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.

! Y e 3\

12

/ 3 UNACCEPTABLE BON

.j g)ga(g u e

-; e m unares m 11 X Y

~ , ECO 11A

$ M 11A 10 7 1.00 ilo 100 112 N

1 00 113 400 115 ,

5

. j E00 117 ACCEMABLE

  • a .". '28 tu OPERAVON s 00 in 3 10.00 114

. ! 1130 115 7

d 1&00 132

. i 2tL00 115 h

J.! 46.00 9.0 GE9BMDWB3144C404DM 180 T

- -- - \

6

-l S1AT 6A ll mm, , - - _ , ~ . - - - -

0 5 10 15 20 25 M 35 40 46 80 AVERAGE RRMR EXPOSUE(GWWet)

FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T) 6 Revision 0

Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report I

/WI

[ 1 in UNACCEPTABLE ceOsuRs OPERATION

" ~

COORDINATES

  • k g

j ._

am iisT 1 N i

tL20 11.02 10 -! 1.00 11.T5 D .

1 00 11.96 }

f l 1 00 1117

- 4.00 1141 g* m! 5 00 iles

    • g*o g l ACCEPTABLE

__; a m i122 OPERATION I , '

i O.00 1132 10.00 1125 1150 1113 y_ _i 15.00 1198

{ 20.00 1115 l as e.' "t GE98 P8DWB33110GZ40M.150.T

, _; 46.m s.it --

g 80.00 5.06 1 i

},

s a a eo  % 20 25 30 34 40 44 NOTE: 80 Tus a THE APLHOR UANT FOR THE AVERAGE PLANAR EXPOSURE (OWd/st) I MOSY UnETING LATTICE AS A FUNCTION 0F AVERAGE PLANAR ExPoeuns l

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FIGURE 3-5 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB331-10GZ-80M-150-T) 7 Revision 0

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l Plant Hatch Unit 1 Cycle 17 i l Core Operating Lhnits Report  !

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,, UNACCEPTABLE

% OPERATION t f: :: .1 10

-)

EXPOSURE COORDINATES q

H  ; X Y X Y I ~

~

0,00 11M 12.5 11.70 9 (L30 11.14 15.0 11.70

~ 1 1.00 11.32 17.5 11.70 2.00 11.58 20.0 11.56 a

100 11.70 4m ti.70 25.0 10.56 m0 10.1.

- (

5.00 11.70 35.0 9.54 ACCEPTABLE

a00 t i.70 40.0 as0 OPERATION

~ 7.00 11.70 45.0 8.25 7 1 00 11.70 50.0 7.57 l l 'l 1 00 11.70 55.0 6.08 l l

^

10.0 11.70 57.27 6.51 '

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'_ , , , , GE13 P9HTB32712GZ 100M-146-T LUA RECON e a to il 20 25 30 35 40 45 50 SE NOTE: AVERAGE PLANAR EXPOSURE (GWd/st)

THISIS THE APLHOR UnsT FOR1E WOS7 UANTING LAT110E AS A FUN 0710N OF AWEl%QE PL# TAR ExFoeunE i

FIGURE 3-6 l

AVERAGE " LANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE13-P9HTB327-12GZ-100M-146-T-LUA-RECON) 8 Revision 0

Plant Hatch Unit 1 Cycle 17 i Core Operating Limits Report 5:

A _.

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2 f 5 UNACCEPTABLE EXPOSURE OPERATION

,1 -

""7s8 q s,!

0.00 11.07 N

g 10 -

0.30 11.73 1.00 11.e4 l

5=

!" ;i"

!" ll" N N

{

1" ;i" i= ;;;

ACCEPTABLE OPERATION

(\

. 10.00 12.70 12.50 12.06 7 _ 15.00 12.52

- 20.00 11.91

- 2500 112 h 35.00 e.se GE9B-PSDWB34610GZ-80U-150-T g - 4sm s.7s -

51.71 SM y, s

l AVERAGE PLANAR EXPOSU (GWdleQ j uos uwmotArnes AS A i pu am or memos pwm i ex u uns I man. -

FIGURE 3-7 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB346-10GZ-80U-150-T) 9 Revision 0

1 Plant Hatch Unit 1 Cycle 17 ,

Core Operating Limits Report i i i i EXPOSURE la cooRomTES -

_ X Y X Y

. ECO R12 12A0 180 _

UNACCEPTABLE ** * '****"

im as" um am OPERATION .00 an ism aa

,, __ am am 17m aae _

4.00 EM 20.00 E0e 6.00 1 81 25.00 EST E00 RST 30.00 1 14 10 7.00 9.73 36.00 7.71 -

&OD 4000 7

, .m .Est M . m 30, 10.00 10.03 50.00 E43 g '

11.00 EM M21 106 -

t

ACCEPTABLE q r OPERATION ,

i ....- -,4 .14 1 s ,

1 I I I I a = <a is 30 as 30 as e a ao NOTT.: AVERAGE PLANAR EXPOSURE (GWaput) wasonearmaR uns? PoRne MOST UmTING LA7710E AS A PUNF'M OF AVERedE PLANAR sxposunE j

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1 FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION RATE l VERSUS i AVERAGE PLANAR EXPOSURE l (Fuel Type: GE12-P10HSB331-6G5.0/4G4.0-100T-150-T) l 10 Revision 0

Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 4.0 MCPR LIMIT (Technical Specification 3.2.2)

The MCPR operating limit (OLMCPR) is a function of core power, core flow, average i scram time, fuel type, number of operating recirculation loops, operability of the end-of-cycle recirculation pump trip (EOC-RPT) system, and operability of the turbine bypass l valves.

With both recirculation pumps in operation (TLO), the OLMCPR for each fuel type with various combinations of equipment operability, scram times, core flow and core power is I determined as follows: I

a. For 25% s power < 30%, the OLMCPR is given in Figure 4-1.
b. For power 2 30%, the OLMCPR is the greater of either:
1) The flow-dependent MCPR limit determined from the applicable mammum core

{

flow limit line ofFigure 4-2, '

or 1

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

As stated in the note on Figures 4-3 and t-4, with one recirculation pump operating (SLO), the calculated OLMCPR determined above is increased by 0.01.

In Figures 4-3 and 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 Specifications Surveillance Requirements 3.1.4.1 and 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.

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l Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report l The average scram time of the control rods, T, is defmed as:

1 Tm - TB t = 0,or , whichever is greater.

TA-Ts where: TA = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36).

1/2 Ni is = +1.65

  • o * ,

[N,

,, ist ,

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

o = 0.018 sec (standard deviation of p).

fNit im = '"!

E, Ni where: n = number of surveillance tests performed to date in the cycle.

Ni = number of active control rods measured in the ith surveillance test.

ti = average scram time to notch 36 of all rods in the ith surveillance test.

Ni = total number of active rods measured in Technical Specifications Surveillance Requirement 3.1.4.1.

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1 Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report I

TABLE 4-1 l l

I OPERATING FLEXIBILITY OPTIONS APPLICABILITY WITH: USE: l EOC-RPT Turbine Bypass Valves -

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 and intermittent operation with reduced feedwater temperature are included in the MCPR limits presented in Figures 4-3 and 4-4.

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Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 2.6

>50% FLOW 2.5 -

I

'/ CPERATpio U8ST 80CPR(P)e Kp

  • OPERATING Utsff BICPR(100) l FOR P
  • 25% NO THERMRL ulsTS 800NfTOR980 REQU4 RED 14 #

NO UtgrTS SPECIPIED j FOR 25% g P 4 P awaas (WHERE P ewaas e 30% POR HNP = 1,2) ~

i Ke n (Kaw + 0.8200% . P)) i OUACPR (100)

AND 2.3 - l Kan = 2.se PoR g se% CORE Plow i

8 -

t Kaw = 2A0 POR

  • st% Cofts PLOW FOR 30% g P < 45%

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N Ke = 1.2s + o.e134 (4s% . PI i FOR 43% g P 4 00W ~

ait 2 n.

kSO% FLOW Ke m ias

  • o.coes7(so%.P) v$
n. u.

2.1 - '

i FoR 60% 5 P:

K, = 1.o + e.oos7s (1oe%. P)

Vl * . I

$ 2.0  !

b

u. 1.59 1.4 I

_ l k

\

1.3 -

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1.1 - ,

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' lN li P ***i'i 1.0 , , , , , , , i i ,

N 6 i . i i 20 25 30 40 50 60 70 SO 90 100 POWER (% RATED)

FIGURE 4-1 MCPR MULTIPLIER (Kp) VERSUS CORE POWER 14 Revision 0

4 Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.7

_ MAXs4UGd PLOW RATE a

~

117 %

~ POR Wc (% RATED CORE FLOW)

  • 40%

112 %

( heCPRy n( AgW,i100 + By )'[1+0.0032 (40. W,)]

~

N 107%

FOR We (% RATED CORE FLOW)a 40%

ascPR pm asAx (12o, A,W, t too + s, )

1.5 ' * ' N 117A .eA32 1, sos

, 112A 4A02 1,747 197A . ease issy 1.4 102A eA71 14ss W

N,KN '

1.3 NN i

1.2 1.1 i . . ... ....... ..... ..... 4 i i 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% rated)

FIGURE 4-2 MCPR LIMITS (MCPRr) VERSUS CORE FLOW 15 Revision 0

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Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.42

" GE12 s s - "

5.as -

8 " -------

t,a "

GE13 k **

g [s #

8 1.32 E 12 b ----- 7 5

l'"_ __ f GE9B -#

i N

p.-

im

$.34 l 1.22 0 0.1 0.2 0.3 0,4 0.5 0.8 0.7 0.8 0.9 1 TAU (t)

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

1 FIGURE 4-3 MCPR LIMIT VERSUS AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable andEOC-RPTSystem Operable) l l

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l Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report

{

l 1A2 ,

l 1.8 E42 q p-s

$ 1.=

d

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[ 1.44

~

g #~ GE13 ------

% p- 7 31A2 ~

2 #

h1A a s #' l

~

  1. GE9B 7 51.= \ w r s#

p 1.34 121 1.3 1.25 0 0.1 03 0.3 0.4 0.5 0.8 0.7 OJ 0.5 t TAU (t)

NOTE: For SLO, increase the MCPR Limit cbtained from this figure by 0.01.

~

FIGURE 4-4 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable andEOC-RPTSystem Inoperable) 17 Revision 0 J

Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 5.0 APRM FLOW BIASED SIMULATED THERMAL POWER - HIGH Time Constant (Surveillance Requirement 3.3.1.1.14)

The allowable value for the APRM Flow Biased Simulated Thermal Power - High time constant is 5; 7.0 seconds.

6.0 REFERENCES

1. " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A 111, November 1995.
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 (TAC Nos.

73614 and 73615)," December 29,1989.

3. " Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Plant Unit 1, Reload 16, Cycle 17," General Electric Document 24A5353, Revision 0, March 19%.
4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR - LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P. December 1986.

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