ML20136B977

Ei Hatch Nuclear Plant Unit 2 Cycle 13 COLR Rept, Rev 1

ML20136B977
Person / Time
Site:	Hatch
Issue date:	03/07/1997
From:	GEORGIA POWER CO.
To:
Shared Package
ML20136B975	List: HL-5327, Forwards Ei Hatch Nuclear Plant Unit 2 Cycle 13 COLR, Rev 1 ML20136B977
References
NUDOCS 9703110219
Download: ML20136B977 (22)

Text

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!O 1

GEORGIA POWER COMPANY EDWIN L HATCH NUCLEAR PLANT 4

UNIT 2 CYCLE 13 l

CORE OPERATING LIMITS REPORT 4

Revision 1 i

i j-l 4

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

9703110219 970307 PDR ADOCK 0S000366 P

PDR

.. -.. -. ~, -.

i Edwin I. Hatch Nuclear Plant Unit 2 Cycle 13 j

Core Operating Limits Report l

j; TABLE OF CONTENTS 1

1 4

l Section Title Eagt 1

1 1.0 Introduction 1

i.

1 2.0 Rod Block Monitor 1

i l

3.0 APLHGR Limit 2

4.0 MCPR Limit 11 i

5.0 APRM Flow Biased Simulated Thermal Power - High l

l Time Constant 18

' 6.0 References 18 i

l i

i i

i O

i Revision 1 l

TABLE OF CONTENTS (Continued) h LIST OF FIGURES I

i Finure No.

Iills P_ags 3-1 MAPLHGR Multiplier (MAPFACF ) Versus Core 3

Flow 3-2 MAPLHGR Multiplier (MAPFACp ) Versus Core 4

Power 3-3 APLHGR Versus Average Planar Exposure GE9B-P8D WB314-7G4. 0-80M-150-T-NOSHIP 5

j 3-4 APLHGR Versus Average Planar Exposure GE9B-P8DWB314-8G4.0-80M-150-T 6

3-5 APLHGR Versus Average Planar Exposure GE9B-P8DWB314-8G4.0A-80M-150-T 7

'l 3-6 APLHGR Versus Average Planar Exposure g

GE9B-P8DWB330-10GZ-80M-150-T 8

3-7 APLHGR Versus Average Planar Exposure GE13-P9HTB327-12GZ-100T-146-T-L UA-[GE13]

9 3-8 APLHGR Versus Average Planar Exposure GE9B-P8DWB315-8G.4.0-80M-150-T 10 4-1 MCPR Multiplier (Kp) Versus Core Power 14 i

4-2 MCPR Limits (MCPRr) Versus Core Flow 15 4-3 MCPR Limit Versus Average Scram Time (with Turbine Bypass Valves Operable andEOC-RPT System Operable) 16 4-4 MCPR Limit Versus Average Scram Time l

(with Turbine Bypass Valves Operable andEOC-RPT SystemInoperable) 17 O

ii Revision 1

TABLE OF CONTENTS (Continued) 1 i

LIST OF TABLES Table No.

m g

4-1 Operating Flexibility Options Applicability 13 i

I 1

L i

l i

')

i V

iii Revision 1 i

H

3 Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report

1.0 INTRODUCTION

i The Core Operating Limits Repon (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 1 l

t.nd 2). Results from the fuel vendor's reload analyscs for the fuel in Unit 2 Cycle 13 are documented in References 3 and 4.

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

I a.

Control Rod Block Instrumentation - Technical Specificati m 3.3.2.1 I

b.

Average Planar Linear Heat Generation Rate (APLHGR) -- Technical l

Specification 3.2.1

]

Mimmum Critical Power Ratio (MCPR) - Technical Specifications 3.2.2 c.

and 3.3.2.1 i

d.

APRM Flow Biasei Simulated Thermal Power - High, Time Constant - Technical Specifications Survdace Requirement 3.3.1.1.14 2.0 ROD BLOCK MONITOR (Technical Specification 3.3.2.1) l 3

s i

j 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 < 1.70; t

or i

b.

Thermal Power is 2 90% of Rated Thermd i>ower, and MCPR is < l.40.

k O

1 Revision 1

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report O

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:

The flow-dependent multiplier, MAPFAC, from Figure 3-1, a.

F or b.

The power-dependent multiplier, MAPFACp, from Figure 3-2.

For the fuel types whose APLHGR limits are shown in Figures 1-3 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 Figures 3-6 and 3-7. When APLHOR values are determined by the process computer, the lattice-dependent APLHGR limits are used.

g Under these conditions, some axial locations may have APLHGR values exceeding the values shown in Figures 3-6 and 3-7.

O 2

Revision 1

Plant Hatch Unit 2 Cycle 13

' Core ' Operating Limits Report.

O V

i l

)

l f

OWs 107%

I 0.90 -

1:2%

i 0.86 - -

117 %

l r

4 l

6 0.80 -

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.A,u.OR,.=A FAc.. mAru.OR l

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g b4A LHOReve= 8TANDARD MAPLHOR UMITS 8

.A.F A.. -P R,0.. A T.,

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0.70 IAA.MULT e 1.0 FOR FLOW = 81%

1 e 0.84 FOR FLOW 5 e1%

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teFR,0 p {F) e RANIliuta (1.0, AF+ 5 F F]

l 0.H F=

FRACTION OF RATt0 CORE FLOW i

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(% RATED)

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.i O.40 ed 70 80 to 100 30 40 80 si core FLOW (% rated) l I

l L

l l

FIGURE 3-1 i

MAPLHGR MULTIPLIER (MAPFACp) VERSUS CORE FLOW l-3 Revision !

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report 9

1 1.0 i

{

0.9 8

l p#

g e

0.8 p%

SINGLE LOOP OPERATION (SLO) g 0.75 4

l s 60% CORE FLOW MAPLHGR p a MAPFAC p

• MAPLHOR sto.

MAPLHOR rro a STANDARD MAPLHOR UMITS g7 FOR 28% > P:

NO THERMAL UMITS MONITOfUNG REQUIRED h

(SLO, TLO)

NO UMITS SPECIFIED 8

FOR 24% 5 P 4 30%:

g (SLO TLO)

MAPFAC p = 0.806 + 0.008224 (P. 80%)

i O.8 FOR s 80% coma FLOW aAAPFAC p= 0.433

• 0.008224 (P. 30%)

i i

FOR. 00..OR,_

l l

FOR30% s P:(TLO)

OR FOR 30% s P = s2%:(SLO) 0.5 i

j MAPFAC, a 1 A + 0.004234 (P.100%)

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,,0%.OR,mW

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FIGURE 3-2 MAPLHGR MULTIPLIER (MAPFACp) VERSUS CORE POWER 9

4 Revision 1

Plant Hatch Unit 2 Cycle 13 Coro Operating Limits Report GV i

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FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE GE9B-P8D WB314-7G4. 0-80M-150-T-NOSHIP

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5 Revision 1

1 Plam Hatch Unit 2 Cycle 13 Core Operating Limits Report l

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AVERAGE PLANAR EXPOSURE GE9B-P8DWB314-8G4.0-80M-150-T 6

Revision 1

Plant Hatch Unit 2 Cycle 13 CoroOperating Limits Report 1

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7 Revision 1

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report O

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TMS S THE APLHGR UMIT FOR THE 80087 UMmMG LATTICE AS A FUNCTION OF AVERAGE PLANMt EXPOSLlUtE FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE GE9B-P8DWB330-10GZ-80M-150-T O

8 Revision 1 1

l Plant Hatch Unit 2 Cycle 13

. Cote Operating Limits Report l

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MERAGE PLANAR EXPOSURE (GWWSt) 4 NOTE:

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4 FIGURE 3-7 l

AVERAGE PLANAR LINEAR HEAT GENERATION RATE j

VERSUS j

AVERAGE PLANAREXPOSURE GE13-P9HTB327-12GZ-100T-146-T-L UA[GE13]

9 Revision 1

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report O

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10 Revision 1

l Plant Hatch Unit 2 Cycle 13 Core' Operating Limits Report

!O 1

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

i 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 determined as follows:

i

a. For 25% :s power < 30%, the OLMCPR is given in Figure 4-1.

i

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

j

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

or

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

As stated in the note on Figures 4-3 and 4-4, 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 determineA, Option A limits are to be used. Refer to Table 4-1 to determine the applicable set of fuel-type dependent curves.

I1 Revision 1

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report O

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

Tave - TD t

= 0,or

, whichever is greater.

TA-TD where:

ta = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36).

nn Ns

+1.65

• a.

TD

=

[ N, where:

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

o

= 0.018 sec (standard deviation of p).

fNit, T ve "

a

[Ni n.,

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 ti

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

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

Surveillance Requirement 3.1.4.1.

O 12 Revision 1

Plant Hatch Unit 2 Cycle 13

.. Core Operating Limits Report -

O TABLE 4-1 OPERATING FLEXIBILITY OPTIONS APPLICABILITY WITH:

USE:

EOC-RPT Turbine Bypass Valves Operable Operable Figure 4-3 Inoperable Operable Figure 4-4 l

Not licensed for this Operable knperable operating cycle O-Not licensed for this Inoperable Inoperable operating cycle i-l NOTE:

Operation within the licensed power / flow region with a single recirculation loop and intermittent operation with reduced fdwater temperature are included in the MCPR limits presented in Figures 4-3 and 4-4.

1 i

l O

l 13 Revision 1 l

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

2.6 e > 50% Ficw 2.5 2.4 2.3 OPERATING LMT MCPR(P) = K(p)* OPERATING LMT NCPR(100) l FOR P e 25% NO THERMAL LMTTS MON!TORNG REOUIRED

~

i 2.2 NO LMTS SPECf1ED 75 50% Fkw FOR 25% 3 P e h) P(Sps)e 30%

gj K(p) = (1.0611.08) * (K(cyp) + 0.02 * (30% P)) / OLMCPR(100)

{ 2.0 h

K(Byp). 2.00 tor Flow 5 50%

e 2.40 lor FW > 50%

ha FOR 30% s P = 45%: K(p) = 128 + 0.0134 * (45%. P) g I

FOR 45% 3 P e 804: K(p) = 1.15 + 0.00067 * (60% P) gu,

,OR.0%, r.

n,).1.. -75 om. P)

$ 1.8 M

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1.7 Gw4 1.6 1.5 1.4 N

13 K

N 1.2 I

N_

l 11

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l 20 30 40 50 80 70 80 M

100 Power (% Rated)

I i

FIGURE 4-1 i

MCPR MULTIPLIER (Kp) VERSUS CORE POWER O :,

14 Revision 1

Plant Hatch Unit 2 Cycle 13

.. Core Operating Limits Report

.O l

3 1.6 t

FOR R (% RATED OF CORE FLOW)?,,40%

l

~

MCPR(F) s MAX (1J0,Af

• m # 100. Sf)

^

MAX. Flow N

st

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N N

N x

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'3 x

x N

x 4

1.1 30 40 50 00 70 80 90 100 110 120 CORE Ft.OW (% OF RATED)

FIGURE 4-2 MCPR LIMITS (MCPRr)VERSUS CORE FLOW rO 15 Revision 1

~

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report O

1.44 a 1.42 l

GE13 BN 1.38 o

$ 1.36 1.34 O

1.32 1.30 i

3 GE9B x

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2 1.26 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.

FIGURE 4-3 MCPR LIMIT VERSUS AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable and EOC-RPTSystem Operable)

O 16 Revision 1

Plant Hatch Unit 2 Cycle 13

.. Core Operating Limits Report

' /~T V

i 1.46

/

" I'#

GE13 m

y

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1.42 O

1.40 k 1.36 1.36

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1 9.26 1

1.26 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Tau (t) 4 NOTE: For SLO, increase the MCPR Limit obtained from this figure by 0.01.

FIGURE 4 4 MCPR LIMITVERSUS AVERAGE SCRAM TIME p

(with Turbine Bypass Valves Operable andEOC-RPTSystem inoperable)

V 17 Revision 1

Plant Hatch Unit 2 Cycle 13 Core Operating Limits Report O;

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 s 7.0 seconds.

6.0 REFERENCES

1.

" General Electric Standard Application for Reactor Fuel,"

NEDE-24011-P-A-13-US, August 1996.

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 2, Reload 12, Cycle 13," General Electric Document 24A5186, Revision 2, June 1996.

4.

"Edwin 1. 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 ofNuclear Reactor Regulation Supporting Amendments Nos.151 and 89 to Facility Operating Licenses DPR-57 and HPF-5,"

dated January 22,1988.

O 18 Revision 1 i

i