ML20094R535

From kanterella
Jump to navigation Jump to search
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)
v • d • e


Text

i l

i 2

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

3 1

2 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 l

1 i

10/26/95

[

EDWIN I. HATCH NUCLEAR PLANT UNIT I FUEL CYCLE 16 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS Section Title fast 1.0 Introduction 1

2.0 Rod Block Monitor I

3.0 APLHGR Limit 2

4.0 MCPR Limit 11 5.0 APRM Simulated Thennal Power Monitor 18 Time Constant

(',

~

6.0 References 18 l

(

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 (MCPR )

15 F

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

~

TABLE OF CONTENTS (Continued)

(

LIST OF TABLES Table No.

Ijilg past 4-1 TABLE OF OPERATING FLEXIBILITY OPTIONS 13 APPLICABILITY

(

(

iv Revision I

1 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

~

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 3.2.2. and 3.3.2.1.

4

~

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:

i

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

^

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.

(

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%

~

7/

,,e,

I

[

o.es u,,

t I

I i

o.s0 mC,. m._ m l

l l

_.._._..__T, f

l mAPeiyLT e t A POR PLOW > e1%

i e eAe POR PLOW 5 41%

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

P=

PRACTIO8d 0F RATED ODIE PLOW i

5 CORE PLOW l

(% ItATED)

AP Se l

0.s0 l

in.4 rm r-T wsr-1er.e esets e.even nu esm

e. sus l

l ura

e. nee eiew 1

1

'i i

0.40 30 40 50 00!

70 to 90 100 l

e1

-l CORE FLOW (% rated) 1

)

i

}

i FIGURE 3-1 MAPFACy I

l 3

Revision 1 i

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

i l

1.0 i

i l

0.9 s

I

/e l pk 0.0 SMGLE LOOP OPERATION (SLO) 0.75.-

s 60% comE PLOW I

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%:

10.5 (SLO,TLO)

ABAPPAC, e 0.585

  • 9.008334 (P. 30%)

l Pon s ses coat eLow M4PFAC P= 0A.83

  • 8A.05234 (P 30%)

I con o m co E rto I

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

4

, m co.E,Lo.

con m 5 r: cSLo) mAme,...n W'

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

(

4 Revision I

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

,/

4 i

i i

~

UNACCEPTABLE

~I t

.<.r 9}

OPERATION 13

.s-

...;. a d_

..'.y 4 2

~

a e..

y?"l r

  • ?w r -[,,Y&

j

},,

,,l 12 f

y 2

f

,s.e

.y y

,.,.9 l

.c.

g g

Low exposune

,;)

5 11 coonoimies g

  • 8 X

Y su k

u so.e

<a ACCEPTABLE

.J e.

su

\\ I.

9 2.8 112 4.o it.s OPERATION

% ~"~s Si

~

. '"; j s.o ti.e s.s is.s 9

10.0 12.3 12.s 12.4 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

[

i l

I I

13 '

I

[

UNACCEPTABLE 58 '8 j

~5!

12 -

OPERATION; t

[

.,JN?.>

4

,,,73 11!

N coonomates

.r X

Y k

10 -.

e.e it.s to.to e

11.8e i

\\

' I e

St e.ro ]

.j s.o 12.to

'4 4.s ts.se 8h ACCEPTABLE

]

.,)

74 124.

OPERATION 7

e.e ts.es

\\

[

e.e ts.te 3,

tes ts.se 12.s taas pygt ryPE:

onesMowes e 1eaz4ess tea-T 8 fo p

ste144 W#'t

~

t 5

j wayg.

AVERAGE PLANAR EXPOSURE (GWWeQ ES!T ue"sE#$Nr"nYas'a e

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)

(

6 Revision 1

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

L

~

,3

(

UNACCEPTABLE

.]

1:

. OPERATION J

11.79

~

t,0w EXPotufts

~6,3' coonomians i

X Y

10.44

=

"s 10 eA HAs 9

SJ 11.92 h

  • j

~

12 13.03 g',

2.0 11.17 4

3.0 11.35 WI f

l 4.0 13.se 4

s.

58 tus ACCEPTABLE

.a ns.

7.o u.1s OPERATION 9 ',l [

r.

es un h f n.n 10A 13.41 6-12.6 13.80 I

FUEL TYPE:

GEssMDws3164G4.840M.180-T g.as et 4

$1.6 Owetet

.........i

'.i..'

8 6

.4 4..

i...

i i....

0 5

10 15 20 25 30 35 40 45 80 AVERAGE PLANAR EXPOSURE (GWest) i a

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

(

l d

h 53 r

s se

UNACCEPTABLE 1

OPERATION 12 -'

1 9

tim qq NN s

cmaam X

Y

.g 1E

[ 10 e.o N

.f' 5

oJ 114.

s

~

1.o 13.01 I >:

=

' =. ' '

4 ese '

g sa n.u g s;_

si is.n ACCEPTABLE 44 is.u es si.u 4

fa n.s OPERATION f,

I 7-s.e 13.32 T l

.4 su.

i.4 iu.

s:

in n2.

g FUEL TYPE:

DE95 PSDWBau4G4.0.aetA 180 7

,,,1,7 GWeWst 5

4...

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)

(

8 Revision 1

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

l l

-l h

p%

13 g

12.se 4 UNACCEPTABLE 12.is k

OPERATION 12

- [

.f

(

ts.ss

~.

[ ":

.)

x 5 1e.

e.2 11.s2 t

e.rr 1

.7 g

5.e it.rs

' ~-

...g..)

g_

2A 11.88 4

3.0 12.17 i

~,

4A 12A1 e-

  • A 12As ACCEPTABLE y

s.11 8.0 12.s0

~_

tsA7 OPERATION s

{

7.

8.0 13.22 j

,,]

sA 5:22 u

toA 13.2s

,g 4$

12.s 13.13 a

)

Futt1YPE:

cessssownsat.tecz.cou seo T l

owest 5

O 5

10 15 20 25 30 35 40 45 50 '

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 i

(' t

}

4 r.

1 J

r; 13 ~

/.! ' il UNACCEPTABLE'.

sa f i t."

OPERATION.

'm-

')

~=

.s 7.m

:====;

11.N S i'

a 4

,. a a

sur SJ 11.14 g,:

0 :::

N.-( ^

i 3.

11.70 M

    • [ '-;r-4.0 11.70 8.08 s,.

o...

8:

'j ll7, ACCEPTABLE

'~

r.)st

.A

,,9 as it.n s.s 11.n OPERATION 7-iu ii.n 888 4 d

12.s it.n S.51 AT 57J7 m

(

d PUEL TYPE:

GE13LMA l

oeimer.nr.im u.co.

s g.

..g.

.,g.

.3

.g....g... g....

....g...,..

AVERAGE PLANAR EXPOSURE (GWest) wore:

Mr*u"."n.,#tM.V.."2.'f." =""

=,o 4via ru FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type
GE13-P9HTB327-12GZ-100M-146-T-RECON) t 10 Revision 1

_~

i 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 11 Revision 1

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 4 = 1.084 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time where:

T limit to notch 36) 1/2 ta = p + 1.65

  • a +

[ N'.

where:

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

I o = 0.018 sec (standard deviation of p)

N

[ Nit, t. = '- '

EN' s.s where:

n = number of surveillance tests performed to date in the cycle N = number of active control rods measured in the ith surveillance test i

t = average scram time to notch 36 of all rods in the ith surveillance test i

N = total number of active rods measured in Technical Specifications i

Surveillance Requirement SR 3.1.4.1.

k 12 Revision 1

Plant H:tch Unit 1 Fuel Cycle 16 4

Core Operating Limits Report

/

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.

7 13 Revision 1 i

Plant Hatch Unit 1 Fuel Cycle 16 Core Operating Limits Report

['I 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

~

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 00% FLOW K,

1.1s + e.seest (ses.P)

POR s0% s P:

I1 -

K, a 1.s + e.es375 (1e0%. P)

Mb l

w-I 2.0 h

1.59 l

u-f

,i 1.4 g

l h

1.3 -

l

\\

1.2

~

l l

11-l l

l l

P.v j.

j j

10 l

l l

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

l i

FIGURE 4-1

't POWER-DEPENDENT MCPR MULTIPLIER (Kp)

I l

k 14 Revision 1 l

l

l 1

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

l i

4 i

~

i i

i i

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

~

113 %

1.6 L

main-u

=

5

~

111A 4A.S 1200 9 eggs

/

113A 4A03 tJef '

1.5 ters 4As.

taer m

g 4.,,

I

\\

u

\\

\\

~

u N

N

\\ x

\\

1.2 J Pon m funavsocons naut)em.m

.c wisium, *=ii mi.

n j

3... g... g..

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

u 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 g

1.32 GE9B g

l j

I l

I g

1.30

(..

I I

1.2s I

X l

)

l l

1.24 I

i I

I i

1.22 j

O.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.

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)

,(

16 Revision 2

Plant Hatch Unit 1 Fuel Cycle 16.

. Core Operating Limits Report r

4 us 1A4 I GetsLuA

/

/

/

i j

w.

/

~=

I i.

u0

\\

U*

l E

.1.x 5

/

y 5

sets

\\

d 1.u

'l-

\\ -

/

/

i x

/

se,,

I I

us O.0 0.1 0.2 0.3 OA 0.5 0.8 0.7 0.8 0.0 1.0 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

I 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-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.

(

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

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20094R535&oldid=4323155"