ML20094R553

From kanterella
Jump to navigation Jump to search
Ei Hatch Nuclear Plant Unit 2,Cycle 13 Colr
ML20094R553
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 11/28/1995
From:
GEORGIA POWER CO.
To:
Shared Package
ML20094R533 List:
References
NUDOCS 9512050032
Download: ML20094R553 (22)
v • d • e


Text

. . _ _ _ _

1

.i 2

i f

GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 13 CORE OPERATING LIMITS REPORT REVISION 0 i i

1 4

J Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 4

9512050032 951128 PDR ADOCK 05000321 P . _ _ . .. , .< - . RDR,..

1 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 13 CORE OPERATING LIMITS REPORT 4

TABLE OF CONTENTS Section lille Eage 1.0 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 i

l

)

l l

1

)

i

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

~ _., .

i t

e >

- t

(

TABLE OF CONTENTS (Continued)  !

j LIST OF FIGURES .  :

1 I

.. . Finire No. Title Eage  :

. r 31 MAPFACp 3 l l

- 3-2 MAPFACp 4 )

l 1

3-3 APLHGR Versus Average Planar Exposure  !

5 l (GE9B-P8D WB314- 7G4. 0-80M-150-T-NOSHIP) i-3-4 APLHGR Versus Average Planar Exposure 6

, (GE9B-P8DWB314-8G4.0-80M-150-T) 1 3-5 APLHGR Versus Average Planar Exposure (GE9B-P8D WB314-8G4. 0A-80M-150-T) 7 .

l i

3-6 . APLHGR Versus Average Planar Exposure  !

8  :

(GE9B-P8DWB330-10GZ-80M-150-T) i 3-7 APLHGR Versus Average Planar Exposure +

i (GE13-P9HTB327-12GZ-100T-146-T-L UA (GE13)) 9 l a 3-8 APLHGR Versus Average Planar Exposure 10

~

(GE9B-P8DWB315-8G4.0-80M-150-T) 4-1 Power-Dependent MCPR Multiplier (Kp) 14

4-2 Flow-Dependent MCPR Limits (MCPRr) 15 4-3 MCPR Limit as Function of Average Scram Time 16 j (with Turbine Bypass Valves OPERABLE and with EOC-RPTSystem OPERABLE) i

, e 4-4 MCPR Limit as Function of Average Scram Time 17 l (with Turbine Bypass Valves OPERABLE and with }

EOC-RPTSystem Inoperable)  !

k[ i ii

. i i  !

I TABLE OF CONTENTS (Continued) 2 LIST OF TABLES i

e Table No. Title Eage 4-1 OPERATING FLEXIBILITY OPTIONS 13 APPLICABILITY i

i i

l 4 ,

i J-i  !

r l

i d

4 6

4 1

l I

i d

a 1

l l

I iii E

EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 13 CORE OPERATING LIMITS REPORT I.0 INTRODUCTION The CORE OPERATING LIMITS REPORT (COLR) for Plant Hatch Unit 2 Cycle 13 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 I and 2). Results from the fuel vendor's reload an alyses for the fuel in Unit 2 Cycle 13 are documented in References 3 and A The following cyclt-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.

i

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

3.3.1.1.14.

2.0 ROD BLOCK MONITOR (Technical Specification 3.3.2.1) l l

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

a. THERMAL POWER is 2 29% and < 90% of RATED THERMAL POWER, and the MCPR is < 1.70, or
b. THERMAL POWER is 2 90% of RATED THERMAL POWER, and the MCPR is < l.40.

l l

Plant Hatch Unit 2 Fuel Cycle 13 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:

l

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., GE13-LUA or GE9B-P8DWB330-10GZ-80M-150-T) -

fuel must be less than or equal to the APLHGR limits shown in Figure 3-6 or (

Figure 3-7. 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 either Figure 3-6 or 3-7.

k.

2

- Plant Ittch Unit 2 Fuel Cycle 13 Core Operating Limits Report 4

J 1

4 i i

i i 1.00 og i l // 1.m l O.90

- 112 %

^

7 0.84 ------ 117%

l '

t

' l l 0.80 -

f MAPLHORp.MAPFAC,* MAPLHGRgro l MAPLHGRsTo* 5TANDARD MAPLHGR LIMITS E MAPFAC p e WNwuM [MFRPDF , MAPMULT r) 0.70 j g  ;

l MAPMULT e 1.0 FOR FLOW D 61% l  !

e 0.86 FOR FLOW 5 41%  ;

I MFRPDF (F)e WNIMUM [1.0, Ap + B p F)

I* l l

Fo FRACTION OF RATED CORE FLOW MAxwuu CORE FLOW

(% RATED) Ae Bp 0.50 -

l 102.s W W l' 107.0 0.4574 0.8768 112.0 0.4214 0soof l

(

117.o cas2s o. sees l 0.40 ,

30 40 50 80 70 80 90 100 61 CORE FLOW (% rated)

FIGURE 3-1 i

I MAPFACv 3

. . ... .. . . - -. - - . - _ = - _ . . . - . ,

.  ?

~

Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report f

t i

I l

a i

1.0 l

l 1

, 0.9 - l Y #e i'

0 l '

O.8 lg SINGLE LOOP OPERATION (SLO) s 50% CORE FLOW MAPLHGR p e MAPFAC p

  • MAPLHOR sto MAPLHGR pro e STAN AR htAPLHOR LMITS OJ l'

} FOR 2s% > P: NO THERMAL UMITS MONITORING REQUIRED (SLO. TLO) NO LIMITS SPECIFlED l

i FOR 20% 5 P 4 30%:

I (SLO, TLO) l MAPFAC e = 0.805 + 0.006224 (P = 30%) l 0.6 - FOR s 50% CORE FLOW  !

l I MAPFAC e = 0.433 + 0.005224 (P . 30%) -[

FOR > 00% CORE FLOW g i FOR 30% s P:(TLO) l l ,

0.5 , OR FOR 30% 5 P = 82%:(SLO) ,

MAPFAC p =1.0 + 0.005224 (P .100%)

l f FOR 52% 5 P:(SLO) MAPFAC pa 0.75 1 . s0% CORE FLOW 0.4 Y >

! I I i l$2 I i I l I 20 25 30 40 50 60 70 80 90 100 POWER (% rated) ,

W FIGURE 3-2 MAPFACp i

4 .

I

Plant Hetch Unit 2 Fuel Cycle 13 Core Operating Limits Report i

13 k

P "" UNACCEPTABLE

"^*

in i OPERATION 1

11.79

~

LOW EXPOSURE A COORDINATES 10

"_ i o.o 12.01 1 4.

N f

6 cJ 1.0 12.os 12.is g . .

2.o 12.31 ,

3.0 124e '" l

~

l 1 4.o 12.s2  !

g a -- - ** 12 "

ACCEPTABLE ,

8.0 12.97 l

72 ".5 8 OPERATION 7 .- - s.o 13.32 3

9.0 13.as i

10.0 13.43 l

8 13.50 NE' ""

12.s j  ! s.es at i q p GE98.Ps0WB;57G4.0.a0Eis0.T.NOSHIP l s l

l l , , , l l 5

0 5 10 15 20 25 30 35 40 45 60 AVERAGE PLANAR EXPCSURE (GWdist)

FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-7G4.0-80M-150-T-NOSHIP) 5

4 Plant Hatch Unit 2 Fuel Cycle 13 .

Core Operating Limits Report

[

E

. I I I 93

.; A

. izu l UNACCEPTABLE

~ '"

12 OPERATION

~

J 11.82 low ExPosune

coontnNATES l

x v  :

10 08 11 88 f

e.2 11.s2 6 { 1.0 11.72 2.0 11.m I 2.0 12.Os s.7s 4.0 12.24 g . u 12 44 ACCEPTABLE a-- s.O tu2

~

l 78 12 8' OPERATION 7 -- s.0 12.91 9.0 12.34 10.0 11.00 NE' M8; '

6 -

12.s 13.se 5

GE98#8DWB3144G4.0 80M 150-7 g

)

j ,

GWest 5

0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWdtst)

FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T) b' 6

- Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report l

M

l  ! 1

~

[ " 'd UNACCEPTABLE I 1244 12 h 11.79 OPERATION LOW EXPOSURE

} ,

_ cooRDNATES X Y F ,7  ! l "" I

( ,, ~ .

o.2 is.n N

6 t.o it.se g[ _

2.0 tzis l

o n.n I s.n j

, i j  !

J g .

4.o its:

l t  :  ; {

f a- - 5* 1172 ACCEPTABLE  :

s.o 12.es 7.o is.so i

OPERATION i 7- - s.o 53.mo s.o is.2s l l'

I to.o 13.3s 6- FueWE:

12.s 1s.es otsersowest44G4.oA4ou.1so.T ,

l l l E'a 5

0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWdist) l FIGURE 3-5 4

AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0A-80M-150-T) 7 4

l Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report -j l

~

j g

13.12 UNACCEPTABLE 12 OPERATION 11.7 11 i

d - COCRDINATES X Y

' I  !

o.o 11.s  ! "'"

f, 10 '.

..: n.a  !  ; }

1.0 11.11

~

9_ 88 " J' e -

s.o ius l

,,7, l g -

4. n.=  !

!' l

$ s. _

..o 12.s ACCEPTABLE  ;

4

.0 12.11

74 12.se OPERATION _
7. n...

. ..e So 13.19 (

10.0 13.30 ,

a: n..

Su. .

g ,um1 PE:

OE,,,,_,,..,,mo.,.,

. 7.

, , , , , 4 o=

l l , , ,

5 3'O 35 40 45 50 O 5 10 ' 15 ' 20 ' 25 unyg AVERAGE PLANAR EXPOSURE (GWd/st)

IESr'*u'u"iE"fr"re UfMriOu !

OF AVERAGE PMNAR EXPOSURE l l

FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB330-10GZ-80M-150-T) k 8

Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report

I I I 13 UNACCEPTABLE 12

" 78 OPERATION

re:::: '  :

^ ^ _

,, j Low "# ) ,,,

ry tu. I gso 0.0 no? l10.1. L g 0.2 11.14

- 1.0 11J2 gy 2.0 11.54 ^

I 3.0 11.70 4.0 858 11.70 8.0 s_ _

sj ;j0 11.70 ACCEPTABLE ,

I b

I 7.87 s.O 11.70 i

' I 3.0 n.70 OPERATION l I 10.0 11.70 l

"'80 12.8 11.70

' M27G M T 6  ! I FUEL TYPE: GE13LUA GE13 P9HTB32712GZ.100T.144.T.LUA (GE13) 5 5' 10 15 20' ' 2'S ' '3O ^ ' 35 ' ~40 '45 ~ 50 '$$

6 AVERAGE PLANAR EXPCSURE (GWdist)

NOTE:

TMS IS THE APLHGR LMIT FOR THE E l'fv E E T U Ix % If " "

i FIGURE 3-7 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE l (Fuel Type: GE13-P9NTB327-12GZ-100T-146-T-LUA(GE13))

9 ,

Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report

(

~

13

( "d' UNACCEPTABLE OPERATION 12 n

11.79 11

_ - - coomures X Y 10 oo 11 As e.2 11.e2 h I

t.o 12.es 2.o n.17 i  !

. . u.= l I 4.0 12.H a: _

s.o u.rs ACCEPTABLE 6.0 12.96

(

74 n.is OPERATION 7 - 8.0 13.24
6.o n.31 l

FUEL TYPE: CE98.P0DWB31s4G4.e40M-16o T I s.86 at 5I GWd et j ' ' i

5. ' '

0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st) l FIGURE 3-8 i

AVERAGE PLANAR LINEAR HEAT GENERATION RATE  ;

VERS'US l AVERAGE PLANAR EXPOSURE  :

(Fuel Type: GE9B-P8D WB315-8G4.0-80M-150-T) l k!

10

. Plant Hitch Unit 2 Fuel Cycle 13 Core Operating Limits Report 4.0 MCPR LIMIT (Technical Specification 3.2.2) .

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

- operability of end-of-cycle recirculation pump trip (EOC-RPT) system, and , l operability of turbine bypass valves. .

I 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: l For 25% 5; power < 30%, the OLMCPR is given in Figure 4-1.  ;

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

A) The flow-dependent MCPR limit determined from the applicable 1 maximum core flow limit line of Figure 4-2, I 1

l or l B) The product of the values from Figures 4-1 and the applicable Figure 4-3 throup 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. l In Figures 4-3 through 4-4, Option A scram time MCPR limits correspond to i = 1.0, where T is determined from scram time measurements performed in accordance with Technical Specifications SR 3.1.4.1 ar i SR 3.1.4.2. Option B values correspond to T = 0.0. For scram times betwe' ' tion A and Option B, the MCPR limit for each fuel type corresponds to T. If .ias 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.

I1

Plant Hatch Unit 2 Fuel Cycle 13 I

Core Operating Limits Report

( ,

The average scram time of the control rods, t, is defined as: j Tsve ~ TB T = 0,~ or , whichever is greater  ;

TA"TB i

where: tr = 1.084 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36)

' ~

m Ni TB = p + 1.65

  • a + ,,

[No where: p = 0.822 sec (mean scram time used in the transient analysis) -

o = 0.018 sec (standard deviation of )

1

$t

. r.,, = ;

I, m d

1 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 3.1.4.1.

, i f

1 12

-. Plant Hatch Unit 2 Fuel Cycle 13 ,

Core Operating Limits Report TABLE 4-1 OPERATING FLEX 1BILITY OPTIONS APPLICABILITY WITH: USE:- ,

. EOC RPT Turbine Bypass Valves

-OPERABLE- OPERABLE Figure 4-3  ;

Inoperable OPERABLE Figure 4-4 i

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.

13

Plant Hatch Unit 2 Fuel Cycle 13 .

Core Operating Limits Report

[

T 4

2.8 .

>50% FLOW 2.5 -

OPERATWO Ute? MCPR(P) e Kp

  • OPERATMC Llh47 NCPR(100)

~

l j POR P e 25%: NO THERMAL Llh4TS BAON170RMO REQUtRED 2.4 - NO UDETS SPECFIED -

['hR 25% s P e P ewees (WHERE P svense e 30% POR HNP.1,2)

~

Kee(Keve* 0.02(20%.PD # OLascPR(100) 13 _ m0 Kevee 2.00 FOR s 50% CORE PLOW g ,

Kev,e 2A0 FOR > 60% CORE PLOW g 2.2 pon 3,g , p . 4,g:

  1. g "' * * * *#"# Id '* * "I
n. -

k 50% FLOW FOR 45% 5 P e 60%:

i

[ gg Q 2.1 . K, e 1.15

  • 0.00047 (60% . P) w _ l Pom s0% s P:

t j K, a 1.0 + 0.00375 (100% . P) at (

i

' 9: 1.5 -

3 l l

l

$ 1.4 .

4

  • .  ! i h i 3 u-

~

j j ,

(-

; x 1.1 -  ! .

~

s 1.0 , l l , , [ , , , , , , , , l ,

20 25 30 40 50 60 70 80 90 100 POWER (% RATED) i i

FIGURE 4-1 POWER-DEPENDENT MCPR MULTIPLIER (Kr) 1 14

Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report i

1.7 FOR We (% RATED CORE FLOW)* 40%

117% MCPR(F) e MAX (1.20, Af Wc i100

  • Of) 1.6 _ L l 107% MAX FLOW Af Sf j

/ 102.8% 117.0 -0.832 1,303 112.0 0.602 1,747 1.5 / /l ' 107.e 0.sse 1.ss?

l _ /[  ! 102.5 0.571 1.658 I / l E i F I E 1.4 i

~. .

W  ! ,

l ,  ! l

! I l

\

l 1.3 k I l j

~

l 1.2 FOR Wc (% RATED CORE FLOW)g 40%

MCPR{F) * ( Af Wei100

  • Bf)* (1+0.0032 (40 We )j

! l

! 1.1

! 30 40 50 6'O 70 ' 80 90 100' 110' 1'2 0 CORE FLOW (% rated) ,

l FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS, MCPR(F) l l

I 15

4 Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report -

1,42 g

i 1.40 7

GE13 1.38 a 1.34 l l 1 84 l j j i 5 l I l d 1.32 .

i

! I 0 f  : l g 1.30  ;

< i 1.28 l 4-x  ! ,

:  : s i i i 1 i i i  ! i  ; I  !  !  !

! l .  ! I

! , l l  !

0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 0.0 0.1 0.2 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 EOC-RPT System OPERABLE) ki 16

. Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report 1

1.44 , ,

i I l 1.42 GEt3 f f

\ l l 1.40 E l 1.28 g , ,  ;

I l  !

l 1.x i

E '

L e ,.u 0 l' 1 1.32 l

g j 1.30 GE98 .

I 1.28 i i

  1. V' '

l l I

1.26

[ l i

1.24 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 TAU ( t )

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 (with Turbine Bypass Valves OPERABLE and with EOC-RPT SystemInoperable) >

17

Plant Hatch Unit 2 Fuel Cycle 13 Core Operating Limits Report

[

5.0 APRM SIMULATED THERMAL POWER MONITOR TIME CONSTANT (Surveillance Requirement 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

4 1. " General Electric Standard Application for Reactor Fuel,"

NEDE-24011-P-A-10-US, March 1991.

d

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 2, Reload 12 Cycle 13," General Electric Document 24A5186, Revision 0, September 1995.
4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR - LOCA Loss-of Coolant Accident Analysis," NEDC-31376-P, December 1986.
5. " Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment Nos.151 and 89 to Facility Operating Licenses DPR-57 and NPF-5," dated January 22,1988.

k 18

Retrieved from "https://kanterella.com/w/index.php?title=ML20094R553&oldid=2785813"