NL-05-0808, Cycle 22 Core Operating Limits Report (COLR)

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Cycle 22 Core Operating Limits Report (COLR)
ML051250238
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/02/2005
From: Sumner H
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-05-0808
Download: ML051250238 (28)
v • d • e


Text

H. L Sumner, Jr.

Vice President Hatch Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7279 May 2, 2005 4

SOUTHERN LA COMPANY Energy to Serve YourWorld' NL-05-0808 Docket No.:

50-321 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin 1. Hatch Nuclear Plant Unit 1 Cycle 22 Core Operating Limits Report (COLR)

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 I Cycle 22 Core Operating Limits Report (COLR), Version 2.

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

Sincerely, H. L. Sumner, Jr.

HLS/ifl/daj

Enclosure:

Unit I Cycle 22, Core Operating Limits Report, Version 2 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 Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager - Hatch Mr. D. S. Simpkins, Senior Resident Inspector - Hatch F~O[

SOUTHERN NUCLEAR OPERATING COMPANY EDWIN I. HATCH NUCLEAR PLANT Unit 1 Cycle 22 CORE OPERATING LIMITS REPORT Version 2 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report FIGURES Figure No.

Title Page 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) 3-1B 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) 3-31 Power-Dependent MCPR Multiplier (Kp) 13 versus Core Power (Pressure Regulator Inoperable) 3-4A MCPR Limits versus Average Scram Time 14 (BOC to EOR-1800 MWd/st) 3-48 MCPR Limits versus Average Scram Time 15 (EOR-1800 MWd/st to EEOC) iii Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report Figure No.

Title Paae 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) 4-2B Power-Dependent LHGR Multiplier 20 (LHGRFACp) versus Core Power (Pressure Regulator Inoperable) 4-3 LHGR versus Peak Pellet Exposure 21 (Fuel Type: GE13) 4-4 LHGR versus Peak Pellet Exposure 22 (Fuel Type: GE14) iV Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report

1.0 INTRODUCTION

The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 22 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, and 4). Results from the reload analyses for the fuel in Unit 1 Cycle 22 are documented in References 3, 4, 5 and 6.

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 1 operation.

Equipment / Condition Limitation EOC-RPT Out of Service AND Not analyzed Turbine Bypass Valves Inoperable Simultaneously

  • 5 2000 MWth 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 2

Plant Hatch Unit 1 Cycle 22 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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report to IL U.a. 0.9 4

0.86 43 0.85 i.

-f 08 ZL 0.7 a.

O 0.7

.4 a)

  • V 0.6 CI

.20.

0.4 TE1 TLO

~I4 G3SLOI 30 40 50 60 61 70 80 90 tDo 1D Core Flow (% of Rated)

Operating Conditions F

SLO / TLO Fuel Type MAPFACF 30 f Fs 61 TLO All 0.86 61 <F TLO All 1.00 30f 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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report Average Planar APLHGR Exposure Limit 0.00 13.42 24.40 13.42 32.66 12.70 56.70 9.00 63.50 6.40 14.0 13.0 no 0.0 E 90 i8.0 7.0 6.0 5.0 4.0 0.0 5.0 10.0 5.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 Average Planar Exposure (GWd/ST)

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

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report 14.0 Average Planar APLHGR Exposure Limit 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 no 10.0 r-EE 9.0 8.0 7.0 6.0 5.0 4.0 0.0 5.0 IDA 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 Average Planar Exposure (GWd/ST)

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

Plant Hatch Unit 1 Cycle 22 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.

As shown on Figures 3-1 A, 3-1 B, 3-2, 3-4A and 3-4B, the OLMCPR with only one recirculation pump in operation (SLO) is equal to the two loop (TLO) OLMCPR plus 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 ' = 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 r = 0.0. For scram times between Option A and Option B, the rated-power, rated-flow OLMCPR corresponds to r. If r has not been determined, Option A limits are to be used.

6 Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report The average scram time of the control rods, T, is defined as:

'ave - tB X

= 0, or

, whichever is greater.

TA - 'B where:

TA

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

'CB

=

+ 1.65 - a *Ni tN where:

.i

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

a

= 0.018 sec (standard deviation of g).

n E Nit i= I tave

=

i E Ni

,=,

where:

n

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

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

To

= 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 2

-U--

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report TABLE 3-1 MCPR Operating Flexibility Options Rated-'

Cycle Turbine MCR Prsueowr A

EOC-RPT Curve Regat I

Curve Rated F ow Exposure:

Vaves :OLMCPRs in Service Oeal iue33 BOC or Operable Figure 3-1A Operable Figure 3-3A to Out of Service Inoperable Figure 3-3B Figure 3-4A EOR-1800

.Operable Figure 3-3A In Service Inoperable Figure 3-1 B Inoperable Figure 3-3B In Service Operable Figure 3-3A EOR-1800 or Operable Figure 3-1A operable Figure 3-3 to Out of Service Inoperable Figure 3-3B Figure 3-4B EEOC In Service Inoperable Figure 3-1 B Operable Figure 3-3A I

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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report 2.8 0.

2.6

c.

>60 Fl

. - ;00.;

0; 0 -

-0l0 h

owl X;

o2.4 20.

0.

20'~

'0 f '

_ 1f

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

MCPRp(TLO) = A + B*P MCPRp(sLo) = MCPRp(TLo) + 0.02 FA I

B I

IF <60 2.15 o0.00 F > 60 3.340

-0.0300 P = Percent of Rated Core Power F = Percent of Rated Core Flow 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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report a.

cc C.)

E

-j 0.

0 0.

S 0.

S0 0

0.

3.8 3.6 3.4 3.2 3.0 2.8 2.6 2.4 22 24 25 26 Core Power (%of Rated) 27 28 MCPRp(rLO) = A + B*P MCPRp(SLO) = MCPRp(TLO) + 0.02 I F: *60 I4.360 K 0.0700I F >60 6.588 1-0.1167 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 3-lB3 Power-Dependent MCPR Limit (MCPRp) versus Core Power from 24% to 28% of Rated Core Power (Turbine Bypass Valves Inoperable) 1 0 Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report t6 I - I l

I Maximum now 1orl%

I.

i i  :

i 1; :  : 

1 La 0~

EU 14

-J C

CL 4) 0

.L 2 L. 112 N

w

.N

.I I

z I w I I I I

4, I-I

 7



I 11 i L Mim I LU OLMCPR 7 1::

r -

30 40 50 60 70 80 90 M

Core Flow (%of Rated)

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

MCPRF(SLo) = MCPRF(TLO) + 0.02 Operating Conditions Values of Variables Maximum Core Flow (% of A

B Rated) 107.0 1.697

.0586 F = Percent of Rated Core Flow FIGURE 3-2 Flow-Dependent MCPR Limit (MCPRF) versus Core Flow 11 Version 2

aI Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report t8 P

7 I

1 0

G e

0<

0.

C 0C0.

0 0.3:

9?

  • 6 12

[t -- _

28 32 36 40 44 48 52 56 60 64 68 72 Core Power (% of Rated) 76 80 84 88 92 96 100 Kp = A+ B*P P

A B

28 s P <55 1.7612

-0.00643 55 < P < 60 I 4.2406

-0.05151 60 s 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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report 18 Y.

Z t6

= t

')14 V

M 13 Q.

0

.L t2 0a-10

. -, --- g 0100f, _ _-, '.' _ _ -., - -.' _ <

i.. -X1X _

.--, s M.

P -_s a,, _ A.. I., _.'d-- '-'... '. _. -

[Aif C001tA 28 32 36 40 44 48 52 56 60 64 68 72 76 Core Power (%of Rated) 80 84 88 92 96 10 Kp= A + B*P P

A I

B 1

28*5 P < 70 1.7612

-0.00643 70*5 P 2.0367

-0.01037 P = Percent of Rated Core Power FIGURE 3-3B Power-Dependent MCPR Multiplier (Kp) versus Core Power (Pressure Regulator Inoperable) 13 Version 2

I Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report 152 tso 148 t46 aj tF t44 CCU2 2

t42 1.40 138 t36 t34

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t

.:.E ! 7

.i

-.;o

.E ": ':

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- Mt ig; f t 000, ' 0, f 0 ' i " i... - t,, f ffff' '. -. -;,....................... - : id

f - -} f i D- ; ; -
; f : -. ;:

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f l.--

-.- : f.................................................

-f:' ::.

7 ::

0 :

-,,,, :- :, : : f t

- i.: ' i.;':

L.-..

. ', f : i,

-f :: - : :

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i: i' L: '..:

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. L:,

i,

. i,.

,,,,i, ono o.1 02 03 0.4 0.5 0.6 0.7 Tau 0.

0o9 to Operating Conditions OLMCPR(TLo)

EOC-RPT Bypass Valves X = 0.0 r= 1.0 In Service Operable 1.35 1.38 Out of Service Operable 1.39 1.50 In Service Inoperable 1.43 1.46 OLMCPR(sLo) = OLMCPR(TLo) + 0.02 FIGURE 3-4A MCPR Limits versus Average Scram Time (BOC to EOR-1800 MWd/st) 14 i

i i

FI I

i i

i i

i i

Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report 1.64 t62 t60 t58 t56 1.54

g. 152 ts4 a.

2 146 t44 U42 1.40 1.38 136

0'Ou of Serv-'ice?.g

;, t-i',

.i~LD,0:,:

,4d

0 S.D bl 0e'.g'k,!'

_-CP In Servic an

'P Operable 0.0 0.1 02 03 DA 05 0.6 Tau 0.7

0.

0.9 to Operating Conditions OLMCPR(TLo)

EOC-RPT Bypass Valves

=0.0 l

= 1.0 In Service Operable 1.40 1.43 Out of Service Operable 1.46 1.63 In Service Inoperable 1.43 1.46 OLMCPR(sLo) = OLMCPR(TLO) + 0.02 FIGURE 3-4B MCPR Limits versus Average Scram Time (EOR-1800 MWd/st to EEOC) 15 Version 2

Plant Hatch Unit 1 Cycle 22 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 UO2 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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report Table 4-1 LHGR Operating Flexibility Options PressUm

-HGRFACp E-Regue o tgg-i-A

-I Operable Figure 4-2A Inoperable Figure 4-2B 17 Version 2

J Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report to as 4

W 0.9 0X 0.6

° 0.7

-0 C

r-0.6 0.a

.2 0.5 0.4 MAX FLOW 107%

30 40 50 60 70 80 90 100 11V Core Flow (% of Rated)

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

Maximum Core Flow (% of Rated)

A 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 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report CL to ii 4:

0.9 i

0.8 E

s ~60°h. Core,O cc j 0.7 C

0.6 60% Core RFo 0.4 I

I I I

..... I T

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

LHGRFACp = A + B*P Oper ing Conditions Values of Variables Fuel P

F SLO/ TLO Type A

B 24*< P < 28 F > 60 SLO / TLO All 0.17924 0.00967 24 S P < 28 F5 s60 SLO / TLO All 0.41897 0.00510 28*< P < 55 All SLO / TLO All 0.41897 0.00510 55 S P < 61.72 All SLO / TLO All

-0.12353 0.01496 61.72 < P All TLO All 0.4776 0.005224 61.72 < P All SLO GE14 0.80 0.000 61.72*< 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 (Pressure Regulator Operable) 19 Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report ti to 0.

IL c0 0.9

-J 0.

to 0.7 I

0

=

0.6 03 0

Cr0.

0 r- 0.5 0

0 0.4 0.3

> 60Core Core-Flow 24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 Core Power (%of Rated) 96 10O LHGRFACP = A + B*P Operating Conditions l Values of Variables Fuel P

F SLO/ TLO Type A

B 24*P<28 F>60 SLO/TLO All 0.17924 0.00967 24*P<28 F*60 SLO/TLO All 0.41897 0.0051 28<P< 70 All SLO I TLO All 0.41897 0.0051 70* P All SLOITLO 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) iI IrI i

i P

II I

-II i

I i

I---,I r

P i

i I

I 20 Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report 16.00 U02 Rods Peak Pellet Exposure LHGR 0.00 14A0 13.24 14.40 32.66 12.70 56.70 9.00 63.50 6.40 14.00 12.00

-J 8.00 S : -- t._ :: :, :'N:E

.',, 4 0'V.fi.L t-i:'

t :: f 0 ' :0:

___ _ -t$y iS$00

.- E LL t.'.'-'-.

_".t

^',

__ k AX 31X: \\ bds l AS

_.... . _.

t

t t

y f

0 i

Gd rbdS 27 > \\

,, X,-5.m

,S';.

D. _ _ iE Limiting Gd Rods Peak Pellet Exposure LHGR 0.00 13.21 10.88 13.21 29.92 11.65 53.50 8.26 60.18 5.87 I

\\

-17 I -_

0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 Peak Pellet Exposure (GWd/st) 50.00 55.00 60.00 65.00 FIGURE 4-3 LHGR versus Peak Pellet Exposure (Fuel Type: GE13) 21 Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report U02 Rods Peak Pellet Exposure LHGR 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Limiting Gd Rods Peak Pellet Exposure LHGR 0.00 12.00 12.17 12.00 54.59 7.16 60.39 4.48

-J 14.00 13.00 92.00-9D.0

.:00 7.00 '.-,.'",-,'C\\i ~i 6.00 E-Ct 5.00 _

4.00 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.D0 45.D0 50.00 55.DO 60.00 65.00 Peak Pellet Exposure (GWd/st)

FIGURE 4-4 LHGR versus Peak Pellet Exposure (Fuel Type: GE14) 22 Version 2

Plant Hatch Unit 1 Cycle 22 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 1C51 K615 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 < FOM *92.1 92.1 < FOM *96.9 96.9 < FOM

  • 102.4 102.4 < FOM
  • 108.0 1.35 1.15 1.13 1.11 1.10 1.36 1.15 1.13 1.11 1.10 1.37 1.15 1.14 1.11 1.11 1.38 1.15 1.14 1.12 1.11 1.39 1.15 1.14 1.12 1.11 1.40 1.15 1.14 1.12 1.11 1.41 1.15 1.15 1.12 1.11 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 1.13 1.12 1.45 1.15 1.15 1.13 1.12 23 Version 2

Plant Hatch Unit 1 Cycle 22 Core Operating Limits Report

6.0 REFERENCES

1.

"General Electric Standard Application for Reactor Fuel," NEDE-2401 1-P-A-14, June 2000, and the US Supplement, NEDE-2401 1 -P-A-1 4-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 0000-001 8-9797-SRLR, "Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Power Plant Unit 1, Reload 21 Cycle 22," Revision 0, March 2004.

4.

SNC Letter CAH-NF-2502, "Generic Pressure Regulator Failure Downscale (PRFDS) Analysis," W. R. Mertz to K. S. Folk, February 16, 2005.

5.

SNC Memo CAH-NF-2465, "TPO Low Power ARTS Multipliers," W. R. Mertz to K.

S. Folk, March 1, 2004.

6.

Global Nuclear Fuel document 0000-0018-9797-FBIR, "Fuel Bundle Information Report for Edwin I. Hatch Nuclear Power Plant Unit 1, Reload 21 Cycle 22,"

Revision 0, March 2004.

24 Version 2

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