ML20128E763

Rev 0 to Ei Hatch Nuclear Plant Unit 2,Core Operating Limits Rept for Operating Cycle 11

ML20128E763
Person / Time
Site:	Hatch
Issue date:	11/30/1992
From:	GEORGIA POWER CO.
To:
Shared Package
ML20128E754	List: HL-2985, Forwards Rev 0 to Ei Hatch Nuclear Plant Unit 2,Core Operating Limits Rept for Operating Cycle 11 ML20128E763
References
NUDOCS 9212080175
Download: ML20128E763 (19)

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EDWIN I. HATCH NUCLEAR PLANT

~b UNIT 2 I

D -

I l CORE OPERATING LIMITS REPORT for l OPERATING CYCLE 11 ;5 D

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REVISION O NOVEMBER 1992

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Intorof'fico Correspondence Georgia Power d DATE: November 6, 1992 RE: Hatch proiect Suonort - licensina Core Operating Limits Report for Hatch 2 Cycle 11 File: Fuel Cycle Technical 1 Log: HL-3022 FROM: S. J. Bethay T0: All Unit 2 Technical Specif cations Holders -

I By Amendment 106 to the Unit 2 Technical Specifications (TS), the NRC authorized relocation of certain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Report (COLR). This i letter transmits to all Unit 2 Technical Specifications holders a copy of Revision 0 of the Core Operating Limits Report for Hatch 2 Cycle 11. This 3 document is utilized in conjunction with the Unit 2 Technical Specifichtions l as referred to in the Specifications. Normally, the shift technical advisor (STA) or reactor engineer utilizes this report. Where necessary, the fuel limits from the COLR are included in plant procedures.

If changes to the core operating limits contained within this report are required, a complete revised COLR will be issued and the appropriate procedures revised.

If there are any questions regarding this report, please contact me at extension 8-821-7392 or telephone number (205) 877-7392. _

SRP/cr i 004280 Attachment cc: NORMS s

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D GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT I- UNIT 2 FUEL. CYCLE 11 CORE OPERATING LIMITS REPORT REVISIDH 0 NOVEMBER 1992 I .

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I SOUTHERN NUCLEAR OPERATING COMPANY.

P. O. BOX 1295 BIRMINGHAM, AL 35201 I

4 EDWIN 1. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 11 CORE OPERATING LIMITS REPORT

1. It[T_RODUCT ION l This CORE OPERATING LIMITS REPORT for Hatch Unit 2 Cycle 11 is prepared in accordance with the requirements of Hatch Unit 2 Technical t

Specification 6.9.1.11. The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2).

Results from the reload analyses for the Gm eral Electric fuel in Hatch Unit 2 Cycle 11 are documented in Re/erences 3 and 4.

The following cycle-specific core operating ' 4its are included in I this report:

a. Control Rod Program Controls - Rod Clock Monitor (Technical Specification 3/4.1.4.3)

I

b. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3/4.2.1)

c. Minimum Critical Power Ratio (MCPR) Operating Limit (Technical Specification 3/4.2.3)

d. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3/4.2.4)

2. ROD BLOCK MONITOR (Technical Specification 3/4.1.4.3)

Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3/4.1.4.3 and when:

a. THERMAL POWER is < 90% of RATED THERMAL POWER and the MCPR is less than 1.70, or

b. THERMAL POWER is 1 90% of RATED THERMAL POWER and the MCPR is less than 1.40.

REVISION 0 1 NOVEf1BER 1992

EDWIN I. HATCH NUCLEAR PLANT Oh!T 2 FUEL CYCLE 11 CORE OPERATING LIMITS REPORT I 3. APlHGR LIMIT (Technical Specification 3/4.2.1)

The APLHGR limit is given by the applicable rated-power, rated-flow limit taken from Figures 3-3 through 3-8, multiplied by the smaller of either:

a. The factor given by figure 3-1, or i

b. The factor given by Figure 3-2.

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

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4. MCPR LIMIT (Technical Specification 3/4.2.3)

The MCPR operating limit (OLMCPR) is a function of fuel design, average scram time, core flow, number of operating recirculation loops, and core power. Note the rated-power and rated-flow OLMCPR is fuel-type dependent in Figure 4-3. For example, the Option B limits are 1.24 for GE7B, 1.25 for GE9, and 1.28 for Gell.

4.1 Two Recirculation Loon Operation For 25% 1 Power < 30%, the OLMCPR is given in Figure 4-1.

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

a. The applicable limit determined from Figure 4-2, or REVISION 0 2 NOVEMBER 1992

EDNIN 1. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 11 CORE OPERATING LIMITS REPORT

b. The appropriate Kp given by figure 4-1, multiplied by the appropriate limit from figure 4-3 where the scram time dependence is given in the Bases for Technical Specification 3/4.2.3.

4.2 Single Recirculatiqn loop Operation For single-loop operation, the MCPR operating limit shall be 0.01 greater than the two-loop value which is determined as specified in Section 4.1.

5. LHGR LIMIT (Technical Specification 3/4.2.4)

The LHGR 1imit is 13.4 kW/ft for all GE7B fuel. The LHGR 1imit for GE9B and Gell fuel is 14.4 kW/ft.

6. REFERENCES I 1. " General Electric Standard Application for Reactor Fuel,"

NEDE-240ll-P-A-10-US, March 1991. _

2. Letter, L. P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of I Amendment Nos. 151 and 89 to Facility Operating Licenses DPR-57 and NPF Edwin 1. Hatch Nuclear Plant Units 1 and 2 (TACS 66524/66525)," dated January 22, 1988.

3. " Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Plant Unit 2 Reload 10 Cycle 11," GE Document 23A7191, Revision 0, September 1992.

i[ REVISION 0 3 NOVEMBER 1992

, EDWIN I. HATCH NUCLEAR PLANT

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UNIT 2 FUEL CYCLE 11 CORE OPERATING LIMITS REPORT I 4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P, December 1986.

5. Technical Specifications Bases for Sections 3/4.1.4.3, 3/4.2.1, 3/4.2.3, and 3/4.2.4.

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REVISION 0 4 NOVEMBER 1992

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l MAPLHORp - MAPFACp

• MAPLHGRgg h O 80 MAPil4GR373 - ST ANDARD MAFU1GR LIMITS g

ret 1

MAPFACp - MINIMUM (MFRPDp . MAPMULTp t C MAPMULT - 1.0 FOR FLOW > 61%

- 0 86 FOR FLOW 561% Mh

$ MFRPD p lF) = MINIMUM (;.0,Ap + B gF) hn

, $ F = FRACTION OF RATED CORE FLOW, d

p j 0 70 -

AND A p. ByARE FUtt. TYPE DEPENDENT m" n g r- 4 8

-O CONSTANTS GIVEN BELOW:

FOR 7X7, 3h y

$ MAXIMUM 8X8.8X8R FOR F8X8R 3 CORE FLOW O

1. F M g (% RATED) F F F o 40 -

3 102.6 0.4698 0.6857 0.4861 - 0.6784 3 107.0- 0.4421 0.6533 0.4574 0.6758 y 112.0 0.4074 06581 0.4214 06807 117.0 0.3701 06666 0.3828 06806 0 So -

Z O

0 40

$ w 4o so sol Fo 80 M '88 "8 x .4 .

N CORE FLOW t% M ATEDI FIGURE 3-1 mal'FAC F

mp m m m MM m M M m W W E7 W to W

{

U l Cl U U mE W .

M api ttGR = M APf AC ep.M apt itGR p gg ,

~ M apt D4GH g

= $f AND AHD MPAt $4GH & IMel$ ,

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tb g M APf ACp = 0 4 33 + 0 005224 IP - 30s

1

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fun) $0% CORE F L OW o

g iOTe30%i Pt 454 0 f t O 4

M APF ACp = 1 O + 0 00$ 2 24 IP - 100% 8 SLO ISINGLE LOOP OPER ATIOt4) n o m I

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• m Mg-ast O. O t4 t_ g"' *C oa e *

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AVERAGE PLANAR EXPOSURE (GWd/st) 5 FIGURE 3-4 AVERAGE PLANAR LINEAR 9 HEAT GENERATION RATE LIMIT

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O - AVERAGE PLANAR EXPOSURE (GWd/st) 5 FIGURE 3-5 AVERAGE PLANAR LINEAR 9 HEAT GENERATION RATE LIMIT vs. AVERAGE PLANAR EXPOSURE is

_ _ _ _ - _ = .

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$ 3.0 12.05 8.76 O pZ 7 rn g j 4.0 12.24

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8.0 12.8' 12.91 OPERATION _ __ \ -

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FIGURE 3-7 AVERAGE PLANAR LINEAR E ,,$$$$s7n"e " '*"^ ' HEAT GENERATION RATE LIMIT

vs. AVERAGE PLANAR EXPOSURE l8 i _

m g aun cm nas uma t; t man mur cn man y sus p num uma man G w U u U w w .

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20 25 30 35 40 45 50  !

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O AVERAGE PLANAR EXPOSURE (GWd/st) m 5 FIGURE 3-8 AVERAGE PLANAR LINEAR 9 HEAT GENERATION RATE LIMIT vs. AVERAGE PLANAR EXPOSURE is 4

-u ,-

l g; 2a , , , , ,

~

g > 50% FLOW 7 '-OPERATING LIMIT MCPR(P) = Kp

• OPERATING LIMIT MCPR(100)

O o

2.5-g 2.4 -

_ , A'/

l FOR P < 25% : NO TFIERMAL LIMITS MUNITORING REQUIRED NO LIMITS SPECIFIED g gg _

j FOR 25% < P < P meass (WHERE P mens = 30% FOR HNP 2)

Kp = [Km,+ 0.02(30% - P)]/OLMCPR(100) o A i 2.3 - l m a

AND l

g V  : K , = 2.00 FOR _< 50% CORE FLOW E 2.2- .

g

",= 2.40 FOR > 50% CORE ROW vii

~

d50% FLOWy

" E --

so a. 2.1 - / FOR 30% $ P < 45% :

Kp = 128 + 0.0134 (45WP) 3[

kE -

l FOR 45% $ P < 60% :

. "y g

m E 2.0 - Kp = 1.15 + 0.00867 (60% - P) -< I sq'st o

o3

u. g 1.5_

q i' FOR 60% < P :

Kp = 1.0 + 0.00375 (100%-P)

P{

m o E g o, ,

" r-

- 4_ - - +

w j

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m O u)  :

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~

j\x  ;

l 1.0L

}SYPASS A

i i ,

i i ,

lN%

40 50 GO 70 80 90 100 20 25 30 2

o POWER (% RATED) m 5

FIGURE 4-1 9 POWER-DEPENDENT MCPR MULTIPLIER (Kp)

E

_______.m.

M M M M M M " 'l M MM M E:

M M- M M. 'l C C' l W U U [U W T 1.7- -l- 1 I-- - l----

Q _

MAXIMUM FLOW RATE = ~

25 FOR We (% RATED CORE FLOW) > 40%

6 - 117 % MCPR(F)= MAX (1.20, AfWc/100+Bf)

}

0 1.6 \ / / t-Af Bf MAX FLOW

/7/ f 1 07 %

117.0 -0.632 1,009

/ ' j/ 102.5 %

112.0 -0.602 1.747 m 1.5- --

! /[ 107.0 -0.586 1.697 y

\ - f_/-[/ [ 102.5 -0.571 1.655 g-E s i //

ro.

o 1.4 _ ! .

\\  ! O!

~'p N

i

____. _ _ . ._ _ a 1.3 F .

12 MN --

i FOR We (% RATED CORE FLOW) < 40%

_ MCPRtF)=(AfWc/100+Bf)

_ *[1 +0.0032(40-Wc)]

1.1 . , , ,  !,,3 l ,,i!t ,i l i,, i . . . , i , , ,,4 . ..

30 40 50 60 70 80 90 100 110 120 o CORE FLOW (% raitt2 '

Ni 5 FIGURE 4-2 9 FLOW-DEPENDENT MCPR LIMITS, MCPR(F) 18

- . _ _ _ _ _ . _ . 1

l. -

EDWIN 1. HATCH NUCLEAR PLANT '

UNIT 2 CYCLE 11 1.34 1.33  !

I.

1.32 L

/

5 3 1.31 GE11 P9 HUB 293 /

/!

k LEAD BUNDLES 1 .30 1 L E I

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VI i

f 4 1,29 '

p --

3

9 u.

.28 1

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1 c:

s 4 1.27 .

I l

'g 3 GE98 P8DWB314 p/

g g 1.2s

F s I' GE78.

U 1.25 _

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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

.; FIGURE 4-3 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME REVISION O 15 NOVEMBER 1992

.