NL-05-0448, Cycle 19 Core Operating Limits Report (Colr). Version 1

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Cycle 19 Core Operating Limits Report (Colr). Version 1
ML050800202
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 03/16/2005
From: Sumner H
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-05-0448
Download: ML050800202 (31)


Text

H.L Sumner, Jr. Southern Nuclear Vice President Operating Company, Inc.

Hatch Project Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7279 SOUTHERNZak March 16, 2005 COMPANY Energy to Serve Your World' Docket Nos.: 50-321 NL-05-0448 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin 1. Hatch Nuclear Plant Unit 2 Cvcle 19 Core Onerating Limits Renort (COLR). Version 1 Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5, Southern Nuclear Operating Company (SNC) hereby submits the Edwin 1. Hatch Nuclear Plant Unit 2 Cycle 19 Core Operating Limits Report, Version 1.

This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely, H. L. Sumner, Jr.

HLS/ifl/daj

Enclosure:

Unit 2 Cycle 19 Core Operating Limits Report (COLR), Version I cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. G. R. Frederick, General Manager - Plant Hatch RTYPE: CHAO2.004 U. S. Nuclear Reg.ulatorv Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager - Hatch Mr. D. S. Simpkins, Senior Resident Inspector- Hatch Aool

j SOUTHERN NUCLEAR OPERATING COMPANY EDWIN I. HATCH NUCLEAR PLANT Unit 2 Cycle 19 CORE OPERATING LIMITS REPORT Version 1 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201

Edwin I. Hatch Nuclear Plant Unit 2 Cycle 19 Core Operating Limits Report TABLE OF CONTENTS Section Title Paqe 1.0 Introduction 1 2.0 APLHGR Limits 2 3.0 MCPR Operating Limits 6 4.0 LHGR Limits 16 5.0 PBDA Amplitude Setpoints 24 6.0 References 25 i Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report TABLES Table No. Title Page 3-1 MCPR Operating Flexibility Options 8 4-1 LHGR Operating Flexibility Options 17 ii Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report FIGURES Figure No. Title Pane 2-1 Flow-Dependent APLHGR Multiplier 3 (MAPFACF) versus Core Flow 2-2 APLHGR Limit versus Average Planar 4 Exposure (Fuel Type: GE13) 2-3 APLHGR Limit versus Average Planar 5 Exposure (Fuel Type: GE14) 3-1A Power-Dependent MCPR Limit (MCPRp) 9 versus Core Power from 24% to 28% of Rated Core Power (Turbine Bypass Valves Operable) 3-1 B Power-Dependent MCPR Limit (MCPRp) 10 versus Core Power from 24% to 28% of Rated Core Power (Turbine Bypass Valves Inoperable) 3-2 Flow-Dependent MCPR Limit (MCPRF) 11 versus Core Flow 3-3A Power-Dependent MCPR Multiplier (Kp) 12 versus Core Power (Pressure Regulator Operable) 3-3B Power-Dependent MCPR Multiplier (Kp) 13 versus Core Power (Pressure Regulator Inoperable) 3-4A MCPR Limits versus Average Scram Time 14 (BOC to EOR-1400 MWdlst) 3-4B MCPR Limits versus Average Scram Time 15 (EOR-1400 MWd/st to EEOC)

.. Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report Figure No. Title Page 4-1 Flow-Dependent LHGR Multiplier 18 (LHGRFACF) versus Core Flow 4-2A Power-Dependent LHGR Multiplier 19 (LHGRFACp) versus Core Power (Pressure Regulator Operable and High Pressure Heaters In Service) 4-2B Power-Dependent LHGR Multiplier 20 (LHGRFACp) versus Core Power (Pressure Regulator Inoperable and High Pressure Heaters In Service) 4-2C Power-Dependent LHGR Multiplier 21 (LHGRFACp) versus Core Power (Pressure Regulator Operable and High Pressure Heaters Out of Service) 4-3 LHGR versus Peak Pellet Exposure 22 (Fuel Type: GE13) 4-4 LHGR versus Peak Pellet Exposure 23 (Fuel Type: GE14) iv Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report

1.0 INTRODUCTION

The Core Operating Limits Report (COLR) for Plant Hatch Unit 2 Cycle 19 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, 2, 3, 4, and 5). Results from the reload analyses for the fuel in Unit 2 Cycle 19 are documented in References 3, 4, 5, 6, and 7.

The following core operating limits are included in this report:

a. Average Planar Linear Heat Generation Rate (APLHGR) - Technical Specification 3.2.1
b. Minimum Critical Power Ratio (MCPR) - Technical Specification 3.2.2
c. Linear Heat Generation Rate (LHGR) - Technical Specification 3.2.3 From a fuel thermal limits perspective, the following limitations are placed on Unit 2 operation.

Equipment / Condition Limitation EOC-RPT Out of Service AND Not analyzed Turbine Bypass Valves Inoperable Simultaneously High Pressure Feedwater Heater(s) Out of Service AND Not analyzed Pressure Regulator Inoperable Simultaneously

  • 2000 MWt Single-Loop Operation (SLO) *
  • 56% Core Flow Option B Scram Speeds Pressure Regulator Inoperable Met (in place)

Also included in this report are the maximum allowable scram setpoints for the Period Based Detection Algorithm (PBDA) in the Oscillation Power Range Monitor (OPRM).

1 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 2.0 APLHGR LIMITS (Technical Specification 3.2.1)

The APLHGR limit for each six inch axial segment of each fuel assembly in the core is the applicable APLHGR limit taken from Figure 2-2 or 2-3, multiplied by the flow-dependent multiplier, MAPFACF, from Figure 2-1.

2 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.0 4'U-0.86 0.8

~0.8 a 03 '.' '. ....... . . .. . . . . .. . . . . . .j 0.7 i..

0.4 3 30 40 5 Core Flow (%of Rated)

Operating Conditions Flow SLO I TLO Fuel Type MAPFACF 30*5 F* 61 TLO All 0.86 61 <F TLO All 1.00 30*<F SLO GE13 0.85 30< F SLO GE14 0.80 F = Percent of Rated Core Flow FIGURE 2-1 Flow-Dependent APLHGR Multiplier (MAPFACF) versus Core Flow 3 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 14D Average Planar APLHGR 13.0 Exposure Umit 0.00 13.42 24.40 13.42 32.66 12.70 56.70 9.00 'no 63.50 6.40 E 1.0

9.0 a-

-i 8.0 a.

7.0 6.0 5.0 44DD :: :: :; :.:: :; :::.;a:;;' -;: :: ;: :; :: :; ;: ;: :' :; ;I'I I ': :; ; ;;::';I I 1'; ', ' 1, '! 1;1 0.0 5.0 10.0 15. 20.0 25.0 30.0 350 400 45.0 50.0 55.0 600 65.0 70.0 Average Planar Exposure (GWd/ST)

FIGURE 2-2 APLHGR Limit versus Average Planar Exposure (Fuel Type: GE13) 4 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report MD.0 A'erage Planar APLHGR Exposure urnit 0.00 12.82 2.0 14.51 12.82 19.13 12.82 ito 57.61 8.00 63.50 5.00 E

i 9.0

..j8.0 IL 7.0 6D 5.0 4.0 0.0 5.0 10D 15D 20.D 25D 30.0 350 40D 45D 50D 55.0 60.0 65D 70.0 Average Planar Exposure (GWdIST)

FIGURE 2-3 APLHGR Limit versus Average Planar Exposure (Fuel Type: GE14) 5 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 3.0 MCPR OPERATING LIMITS (Technical Specification 3.2.2)

The MCPR operating limit (OLMCPR) is a function of core power, core flow, average scram time, number of operating recirculation loops, EOC-RPT system status, operability of the turbine bypass valves, and whether both pressure regulators are operable.

With both recirculation pumps in operation (TLO), the OLMCPR is determined as follows:

a. For 24% < power < 28%, the power-dependent MCPR limit, MCPRp, as determined by Table 3-1.
b. For power 2 28%, the OLMCPR is the greater of either:
1) The flow-dependent MCPR limit, MCPRF, from Figure 3-2, or
2) The product of the power-dependent multiplier, Kp, and the rated-power, rated-flow OLMCPR, as determined by Table 3-1.

With only one recirculation pump in operation (SLO), the OLMCPRs in Figures 3-1A, 3-1B, 3-4A and 3-4B must be increased by 0.02.

These limits apply to all modes of operation with intermittent feedwater temperature reduction, as well as operation with normal feedwater temperatures.

In Figures 3-4A and 3-4B, Option A scram time OLMCPRs correspond to T = 1.0, where Xis 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 X= 0.0. For scram times between Option A and Option B, the rated-power, rated-flow OLMCPR corresponds to T. If Xhas not been determined, Option A limits are to be used.

6 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report The average scram time of the control rods, T, is defined as:

T ave - TB T = 0, or , whichever is greater.

'EA- 'CB where: tA = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36).

'B = it+ 1.65 *- aY*

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

G = 0.018 sec (standard deviation of A).

ENiT,

==

'rave = - n ZNi i=,

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

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

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

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

7 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report TABLE 3-1 MCPR Operating Flexibility Options C'ycle Tu rbine MCR Prsueowr R-Fated-'

.Average Bypass Cre Rgltr Kp Curve RtdFo

. Exposure Valves - OLMCPRs Operable Figure 3-3A Operable Figure 3-1 A Oeal iue33 BOC Inoperable Figure 3-3b to Figure 3-4A EOR-1 400 Operable Figure 3-3A Inoperable Figure 3-l B

. Inoperable Figure 3-3B Operable Figure 31A Operable Figure 3-3A EOR-1400 Inoperable Figure 3-3B to Fgr -1 EEOC Operable Figure 3-3A Figure 3-4B Inoperable Figure 3-1 B Inoperable Figure 3-3B BOC = Beginning of Cycle EOR = End of rated conditions (100% power, 100% flow, ARO, with nominal feedwater temp.)

EEOC = Extended End of Cycle (beyond EOR, 100% power, 105% flow, with reduced feedwater temp.)

8 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 28 S.

E: 2.6

-J cc IL E 2A cm 0

cC.

0 3' 22 0

2.0 24 25 26 27 28 Core Power (% of Rated)

MCPRP = A + B*P F l A Il F <60 l 2.17 l 0.00 l F> 60 3.360 l -0.0300 P = Percent of Rated Core Power F = Percent of Rated Core Flow NOTE: For SLO, increase the value of A by 0.02.

FIGURE 3-1A Power-Dependent MCPR Limit (MCPRp) versus Core Power from 24% to 28% of Rated Core Power (Turbine Bypass Valves Operable) 9 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 4.0.-.. .. .. . ...

CL 3.6 Q.

3.4 ...... j tjjijjiiiii.-..... .

U E

0.

0 3.0 C

0

0. a60% Flow 0
0. 28 0) 0
0. 2.6 24 ---

22 ~ ~ . . . . . . . .... ......-

22 ...

24 25 26 27 28 Core Power (%of Rated)

MCPRP = A + B*P F l A I B I F <60 4.400 -0.0707 F > 60 6.648 -0.1178 P = Percent of Rated Core Power F = Percent of Rated Core Flow NOTE: For SLO, increase the value of A by 0.02.

FIGURE 3-1 B Power-Dependent MCPR Limit (MCPRp) versus Core Power from 24% to 28% of Rated Core Power (Turbine Bypass Valves Inoperable) 10 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 16

-~15 E 14 14, CL

1. . . .. ..

30 40 50 60 70 80 90 to Core Flow (%of Rated)

MCPRF = Maximum [1.31, (A + B*F)]

Operating Conditions Values of Variables Maximum Core Flow (% of A B Rated) 107.0 1.713 -0.00591 F= Percent of Rated Core Flow FIGURE 3-2 Flow-Dependent MCPR Limit (MCPRF) versus Core Flow 11 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.7 - . . . .

I - -

I I R

. 1.6-V

!;4. 1.5-Ca A 1.4-0 I. Hi1.3-21.41

$ 12 11 1.04 .. . . .. . . .. . . .. a 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power (%of Rated)

Kp=A+ B*P P A B 28*! P < 53.2 1.7612 -0.00643 53.2 s P < 60 3.5240 -0.03957 60*5 P 1.3750 -0.00375 P = Percent of Rated Core Power FIGURE 3-3A Power-Dependent MCPR Multiplier (Kp) versus Core Power (Pressure Regulator Operable) 12 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report C.

Z167 vl.lltES~~tt~lWt~g hili .l.}LLXIE.l.ll.l.IL :lii10 ........ i\--.E.-1..

Q 145 o1.4 0

IL 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 1D0 Core Power (%of Rated)

Kp = A B*P P l A l B l 28 s P < 70 1.7612 -0.00643-70s5 P 2.0367 -0.01037 P=Percent of Rated Core Power FIGURE 3-313 Power-Dependent MCPR Multiplier (Kp) versus Core Power (Pressure Regulator Inoperable) 13 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 152 .. . .

I48 1A6

'140X

,A4 cc IA2 138 136L v,-,,,,--134...

OD 0.1 02 03 OA 05 Os 0.7 03 09 t0 Tau Operating Conditions OLMCPR EOC-RPT Bypass Valves Xr = 0.0 X = 1.0 In Service Operable 1.36 1.39 Out of Service Operable 1.40 1.51 In Service I Inoperable 1.41 1.44 NOTE: For SLO, increase each OLMCPR by 0.02.

FIGURE 3-4A MCPR Limits versus Average Scram Time (BOC to EOR-1400 MWd/st) 14 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.64  :;: I

.......I... . .......

U. . . . . . . .

1.56 -

1.54.. . . . .

2 E

1.. g g E-.;..........11 0.

(.

1 4 2. ... . . . . . .

1.440 . . . .. . .

1-52-... . ...

EOC-PVIno Se r vi e a d B V O e a l 1360 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Tau Operatin Conditions OLMCPR EOC-RPT Bypass Valves t = 0.0 l X = 1.0 In Service Operable 1.39 1 1.42 Out of Service Operable 1.45 1.62 In Service Inoperable 1.41 1.44 NOTE: For SLO, increase each OLMCPR by 0.02.

FIGURE 3-4B MCPR Limits versus Average Scram Time (EOR-1400 MWd/st to EEOC) 15 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 4.0 LHGR LIMITS (Technical Specification 3.2.3)

The LHGR limit for each six inch axial segment of each fuel rod in the core is the applicable rated-power, rated-flow LHGR limit taken from Figure 4-3 or 4-4, multiplied by the smaller of either:

a. The flow-dependent multiplier, LHGRFACF, from Figure 4-1, or
b. The power-dependent multiplier, LHGRFACp, as determined by Table 4-1.

Figures 4-3 and 4-4 show the LHGR limits for both U02 rods (which contain no gadolinium) and the most limiting gadolinium-bearing rods for GE13 and GE14 fuel types, respectively. Other gadolinium-bearing rods may have proprietary LHGR limits which lie between these two curves. Compliance with the proprietary limits will be monitored by the plant's process computer, in which case some gadolinium-bearing rods may operate at power levels above the more restrictive limits shown on these curves.

16 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report Table 4-1 LHGR Operating Flexibility Options High

-;Pressure,..,.

Pressure Feedwater Regulator.::

1 Heaters LHGRFACP Operable In Service Figure 4-2A Inoperable In Service Figure 4-2B Operable Service Figure 4-2C 17 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report to a

U-C 0.9 MAX FLOW=

107%/

ca

'&0.8 Xii. X. . .. . .

c 0.7

-j C?

4)

C0.6 03:

0.5 0.4 30 40 50 60 70 80 90 IDO tn Core Flow (%of Rated)

LHGRFACF = Minimum [1.0, (A + B*F)]

Maximum Core Flow (% of Rated) A I B 107.0 0.4574 0.006758 F = Percent of Rated Core Flow FIGURE 4-1 Flow-Dependent LHGR Multiplier (LHGRFACF) versus Core Flow 18 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.1 3 1.0 aL, cc TLO ..........

a 0.9 x

- 0.8 6 % C r Flow C,

M

-I 0.7 C

I 43 8 0.6 43 :IGE 13/14 SLO J.

B.

o 91 -;

U.D

.. ,.>60/Core Flow .1 . . . . . . .I. . . .I. . . .I. . . . . . . ... . .- .-. .. . . . . . . . . . . ... . . . . . .

1 1 -

0.4 24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power (% of Rated)

LHGRFACP = A + B*P Operating Conditions l Values of Variables Fuel P F SLOI TLO Type A B 24<P<28 F>60 SLO/TLO All 0.17924 0.00967 24 S P < 28 FS60 SLO TLO All 0.41897 0.00510 28 S P < 53.2 All SLO / TLO All 0.41897 0.00510 53.2*S P < 61.72 All SLO / TLO All 0.00509 0.01288 61.72S P All TLO All 0.4776 0.005224 61.72* P All SLO GE14 0.80 0.000 61.72*S P < 71.28 All SLO GE13 0.4776 0.005224 71.28 < P All SLO GE13 0.85 0.000 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 4-2A Power-Dependent LHGR Multiplier (LHGRFACp) versus Core Power (PressureRegulator Operable and High PressureHeaters In Service) 19 Version 1

Pln Hac Unt2Cce1 Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.1 - . ...... ---

d Z-10.

(5 E.2 0.7 :5 60% Core Flow ...

I 0

0 0 0.6-09 TL & SLO7T 0

0Z

0. 0.5 0.4 0.3 24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power (% of Rated)

LHGRFACP=A +B*P Operating Conditions, Values of Variables Fuel P F SLO/ TLO Type A B 24 s P < 28 F >60 SLO /TLO All 0.17924 0.00967 24 < P < 28 F < 60 SLO / TLO All 0.41897 0.0051 28 s P < 70 All SLO / TLO All 0.41897 0.0051 70 s P All SLO / TLO All 0.25253 0.00747 P = Percent of Rated Core Power F= Percent of Rated Core Flow FIGURE 4-2B Power-Dependent LHGR Multiplier (LHGRFACp) versus Core Power (Pressure Regulator Inoperable and High Pressure Heaters In Service) 20 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.1 . . . I. . . . . . . .- I . ... . . .I. . . . . . . . . . . . . . . . . . . . . . . .I . . . .I . . . . . . . . . . .

0.

1.u .. . . . . . . . . . . . . . . .

J TLO L.

-- ---I.

/::;

C, 0.9 . . . .. . . . . 1 :  ::  :

.II
... .  ::: . . .I . . . . . :..

.I . . .I.:. ..

1 .. .

7 C) r I.

U- na M

I/

1:5 60% Core Flo c)  ::::,:. 1;: GE13 SLO 0.7

,:.:;:i ;:;:;:;.

C, . . . .

a,

. . . -I- -.----------

0 a 0.6 - - -- . . ------------- -- - ----- -. -

c a.

ns V.0 -1 60%Core Flow L ... . . ...

IGE13 &GE14 SLO 1::

,. . . ., . .. . . r .-. -. -. ,. -. -. -. - -----

- .-. - .-. r. .. . . . . . ........ ...

04 - - - - - - -. - - - --- - - .--

24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power (% of Rated)

LHGRFACP = A + B*P Operating Conditions l Values of Variables P F SLOITLO FuelType A B 24SP<28 FF>60 SLO/TLO All 0.17924 0.00967 24SP<28 F*60 SLO/TLO All 0.41897 0.00510 28SP< 53.2 All SLO/TLO All 0.41897 0.00510 53.2SP < 61.72 All SLO /TLO All 0.00509 0.01288 61.72<5 P < 65.35 All TLO All 0.4776 0.005224 65.35S* P <86.91 All TLO All 0.819 0.000 86.91< P All TLO All -0.3630 0.01360 61.72S P All SLO GE14 0.800 0.000 61.72S P <65.35 All SLO GE13 0.4776 0.005224l 65.35* P All SLO GE13 0.819 0.000 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 4-2C Power-Dependent LHGR Multiplier (LHGRFACp) versus Core Power (Pressure Regulator Operable and High Pressure Heaters Out of Service) 21 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 16.00 U02 Rods Peak 14.00 Pellet Exposure LHGR 0.00 14.40 12.00 13.24 144A0 32.66 12.70 56.70 9.00 63.50 6.40 10.00 Limiting Gd Rods 8.00 Peak Pellet Exposure LHGR 0.00 13.21 6.00 10.88 13.21 29.92 11.65 53.50 8.26 4.0 60.18 5.87 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 60.00 65.00 Peak Pellet Exposure (GWd/st)

FIGURE 4-3 LHGR versus Peak Pellet Exposure (Fuel Type: GE13) 22 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 1.00 13.00-U02 Rods Peak Pellet 12.00 -

Exposure LHGR 0.00 13.40 11.00-14.51 13.40 57.61 8.00 _ 10.00-63.50 5.00 9 00-8.00 Limiting Gd Rods Peak 7.00 Pellet Exposure LHGR 6.00 0.00 12.00 12.17 12.00 5.00 54.59 7.16 60.39 4.48 4.00 "

0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 60.00 65.00 Peak Pellet Exposure (GWd/st)

FIGURE 4-4 LHGR versus Peak Pellet Exposure (Fuel Type: GE14) 23 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report 5.0 PBDA AMPLITUDE SETPOINTS The amplitude trip setpoint in the Period Based Detection Algorithm in the OPRM system shall not exceed the values reported in the Table below. This applies to instruments 2C51K615 A, B, C, and D. Projected Figure of Merit (FOM) value(s) throughout the cycle will be supplied by the Hatch Core Analysis Group.

OLMCPR 0.0 S FOM

  • 92.1 92.1 <FOM *96.9 96.9 < FOM 5102.4 102.4 < FOM *108.0 1.35 1.15 1.14 1.12 1.11 1.36 1.15 1.14 1.12 1.11 1.37 1.15 1.14 1.12 1.11 1.38 1.15 1.15 1.12 1.11 1.39 1.15 1.15 1.13 1.12 1.40 1.15 1.15 1.13 1.12 1.41 1.15 1.15 1.13 1.12 1.42 1.15 1.15 1.13 1.12 1.43 1.15 1.15 1.13 1.12 1.44 1.15 1.15 1.14 1.13 1.45 1.15 1.15 1.14 1.13 24 Version 1

Plant Hatch Unit 2 Cycle 19 Core Operating Limits Report

6.0 REFERENCES

1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-14, June 2000, and the US Supplement, NEDE-24011-P-A-14-US, June 2000.
2. GNF Letter "Plant Hatch Technical Specification Modification to include LHGR," M.

E. Harding (GNF) to E. B. Gibson, January 22, 2004.

3. Global Nuclear Fuel document 0000-0030-0566-SRLR, "Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Power Plant Unit 2, Reload 18 Cycle 19," Revision 1, February 2005.
4. SNC Letter CAH-NF-2501, "H2C19 SNC Reload Licensing Analyses," W. R. Mertz to K. S. Folk, February 16, 2005.
5. SNC Letter CAH-NF-2502, uGeneric Pressure Regulator Failure Downscale (PRFDS) Analysis," W. R. Mertz to K. S. Folk, February 16, 2005.
6. SNC Letter CAH-NF-2410, "H2C18 SNC ARTS Analyses," W. R. Mertz to K. S.

Folk, March 11, 2003.

7. Global Nuclear Fuel document 0000-0030-0566-FBIR, "Fuel Bundle Information Report for Edwin I. Hatch Nuclear Power Plant Unit 2, Reload 18 Cycle 19,"

Revision 0, January 2005.

25 Version 1