ML20069N893

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Rev 0 to Brunswick Unit 2,Cycle 11 Colr
ML20069N893
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 05/31/1994
From: Blom M, Karcher K
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19304C281 List:
References
NUDOCS 9406230251
Download: ML20069N893 (25)
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Cr&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.024 Il2C11 Core Operating Limits Repon Page 1, Revision 0 l

l l

l BRUNSWICK UNIT 2, CYCLE 11 CORE OPERATING LIMITS REPORT ,I MAY 1994 t

Controlled Copy i i

I t

t i

i j

Prepared By: Michael A. Blom j l

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Approved By:/

07 W ' ' _! A Date: ([ ,Y Kenneth E. Karcher '

Manager .

BWR Fuel Analysis {

9 Eg623o2519

^ mck o Mob, ,

PDR l

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF 2702.024 Page 2, Revision 0 t B2C11 Core Operating Limits Report LIST OF EFFECTIVE PAGES Pane (S)

Revision ,

1-19 0 l

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i 4

1

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.024 B2Cl1 Core Operating Limits Report Page 3. Revision 0 JIiTRODUCTION AND SUMM ARY This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 11 as required by Technical Specification 6.9.3.1. The values of the Average Planar Linear llcat Generation Rate (APLliGR) limits, along with associated core flow and core power adjustment factors are provided as required by Technical Specification 6.9.3.1.a. The values of the Minimum Critical Power Ratio (MCPR) limits, along with assoc;3ted core flow and core power adjustment factors are provided as required by Technical Specifications 6.9.3.1.b and 6.9.3.1.c The control rod block upscale trip setpoints and allowable values are provided as required by Technical Specification 6.9.3.1.d.

Per Technical Specification 6.9.3.2 and 6.9.3.3, these values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.

Preparation of this report was performed in accordance with CP&L Nuclear Fuels Management & Safety Analysis Quality Assurance requirements as documented in Reference 1.

APLHGR LIMITS The limiting APLliGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average exposure is given in Figures I through 9. These values were determined with the SAFER /GESTR LOCA methodology described in GESTAR-il (Reference 2). Figures I through 9 are to be used when hand calculations are required as specified in Technical Specification 3.2.1.

The core flow and core power adjustments factors for use in Technical Specification 3.2.1 are presented in Figures 10 and 11. For any given flow / power state, the minimum of M APLliGR(F) determined from Figure 10 and M APL11GR(P) determined from Figure 11 is used to determine the governing limit.

CP&L Nuclear Fuels Mgmt & Safety Analysis File: N F-2202.024 Page 4, Revision 0 B2Cl1 Core Operating Limits Report MCPR LIMITS The ODYN OPTION A, ODYN OPTION B, and non-pressurization transient MCPR limits for use in Technical Specification 3.2.2.1 and 3.2.2.2 for each fuel type as a function of cycle average exposure are given in Tabic 1.

These values were determined with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-li (Reference 2) and are consistent with the Safety Limit MCPR of 1.07 specified by Technical Specification 2.1.2. The analysis was performed without End of Cycle-Recirculation Pump Trip (EOC-RPT) operable.

The core flow and core power adjustments factors for use in Technical Specification 3.2.2.1 are presented in Figures 12 and 13. For any given flow / power state, the maximum of MCPR(F) determined from Figure 12 and MCPR(P) '

determined from Figure 13 is used to determine the governing limit.

ROD Bl.OCK INSTRUMENTATION SETPOINTS The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in Technical Specification 3.3.4 (Table 3.3.4-2) are presented in Table 2. These values were determined consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-II (Reference 2).

REFERENCE (s) 1)

CP&L Nuclear Fuels Management & Safety Analysis Quality Assurance File NF-2494.0026,

" Preparation of the Brunswick Unit 2, Cycle 11 (B2Cl1) Core Operating Limits Report (COLR),

Revision 0,* (May 1994).

2)

NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel," (latest approved version).

= .

CP&L Nucleor Fuels Mgmt & Safety Anotysis File: NF-2202.024 ,

B2C11 Core Operating Umits Report Page 5, Revision 0 j i

l i

Figure 1 l l

FUEL TfPE BP8DRB299 (BP8X8R) -

AVERAGE PLANAR LINEAR HEAT '

GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE l

13 rHlf F1 3URE 13 REFERRED 10Irf REC iNICAL. SP, CIFICA"l0b 3.2.1

  1. g h

'\

12

/

F ERHISSIBLI:

F t t.UIJN Ut '\  !

C'PEftAT1 3N N e

N 11

, N '

!!C I T J 2 EXPCiSUltE UMIT T (i3Wd/K) [kW/ft) \

t- \ ]

T 2 U. dZ l U.UU J 1. 10 11.00 \  !

5. 51 11.!i0 N l 11.02 12.20 g l 3 2$$! i!'i.

X

27. 56 11.!iO Q 33.07 11.00 l

TR ;R infin \

44.09 9.70 \ '

49. 30 9.00 T 9 - ,

i i

8-0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT) d I

l l

CP&L Nuclear Fuels Mgmt & Sofety Analysis File: NF-2202.024 B2C11 Core Operating Limits Report Page 6, Revision 0 Figure 2 FUEL TYPE BD323A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THIE FIGURE 13 REFERRE010DY EC iNICAL SP ECIFICA"10b 3.2.1 13-  %

[

\

/ \

12 F ERMISSIBLI:

F EGl0N OF C'PEFATION h\

11 \

2 \

N N x rypyt pr- I tierr \

10

GW
f/sT) (k)//ft)

'E 0.00 11 33  %\

9 \

7.72 12 E9 z 11 .02 13 14 J 13.78 13.05 Q 16.53 12 72 (

22.05 12 04 27.56 11 38 33.07 10 75 38.58 10.12 \

44-09 9 31  ;

7 i 49.60 8 49 1 55.12 6 02 6-L 5

15 20 25 30 35 40 45 50 55 60 0 5 10 AVERAGE PLANAR EXPOSURE (GWd/MT)

CP&L Nuclear fuels Mgmt & Sofety Anofysis File: NF-2202.024 82C11 Core Operating Umits Report Page 7. Revision 0 -

L Figure 3 FUEL TYPE BD317A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14-THIS FMUBE 13 REFERRED 10ilY TEC iNICAL SPIECIFICA10b 3.2.1 13 l  %

/ N 12 h -

/ PEF:MISSIB I \

, e*

/ REClOb OF OPl:RK10N \

" x

  • N k

a ** # '"#

N*

" 10 T

',GW:f/sT) (kW/ft) e 2 0.00 11 23 N

$x-9 F.32 i2 57 N 1 11 .02 13 02 \ 1 l

J 16 53 12 65 3 k 8

' \

33 07 lbl7 38.58 10.03 44.09 9 20 49.60 8 37 7 up.u a v 6- a l

5- . )

5 15 20 25 30 35 40 45 50 55 60 0 10 AVERAGE PLANAR EXPOSURE (GWd/MT)  :

I

CP&L Nuclear Fuels Mgmt & Sofety Anotysis File: NF-2202.024 D2C11 Core Operating Limits Report Page 8. Revision 0 Figure 4 ,

FUEL TYPE NBD330A (GE8X8NB AVERAGE PLANAR LINEAR HEAT )

GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 13 fHIS Fl 3URE 13 REFERRED 10Irf TEC 4NICAL spi:CIFICA" lob 3.2.1 Y  %

12 N

/ PERh ISS BLE REGION OF \

11

/ OPEFATION \ 3 4

\

N*

2 N

10 \

1 N  :

b \

h EXPOSt RE lGWd/hT)

LilAIT (kW/ft) 0 0.00 10 60 \

to 77 x 5 e 1 10 5.51 11 40 ]

6.61 11 56 9.92 12 07 ,

11 .02 12 24 7-2kb5 27,56 ff 63 11 10

\  !

33.07 10 57 38.58 10 04 6 **M R 98 49.60 7 92 '

54.00 5 91 5

20 25 30 35 40 45 50 55 60 0 5 10 15 AVERAGE PLANAR EXPOSURE (GWd/MT) i

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.024 82C11 Core Operating Umits Report Page 9. Revision 0 Figure 5 FUEL TYPE NBD329A (GE8X8NB AVERAGE PLANAR LINEAR HEAT )

GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 13-rHl! FIGURE 13 REFERRED 10Irf h g REC iNICAL SP. CIFICA"10b 3.2.1

/ x 12 N ERMISSIBU:

F

\

j

/ F EGION OF C PEFtATION

\ '

/ N N

N 2

N 10 '

i \

e s '

b EXPOSURE

GWd/AT)

UldlT (kW/ft) 0 0.00 10 70 b 8

?M 4.41 11 16 11 46 1

n.

< 5.51 11 63 11 .02 12 56 13.78 12 44 16.53 12 18

\ 6 33.07 10 58 38.58 10.05 44.09 9 04 6- #9 60 e n2

  • 54.22 5 90 5

10 15 20 25 30 35 40 45 50 55 60 0 5 AVERAGE PLANAR EXPOSURE (GWd/MT)

1 I

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1 CP&L Nuclear fuels Mgmt & Sofety Analysis File: NF-2202.024 82C11 Core Operating Umits Report Page 10. Revision 0 I

Figure 6 i

FUEL TYPE GE10-P8HXB329-12GZ1-100M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT ,

GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE t 14 THIS FIG'JRE IS RE7 ERRED TC BY TkCH ilCALSPECIFICATDN 3.2.1 13-A

[ h

/ N 12- f y ,

/ N

/

PEF:MISSIBlf RKLOM Of

\g 11 unm ivn s O \

q '

N

!!! rox, or ium \ ,

GW1/5T) (kW/ft) \ i 5 0.00 10 52 gg h

3

  • H2 x '

g i:iB i5 63 I 3.31 11 17

-J 4.41 11 35 5.51 11 53 Q 8 e.g jj fi 7.72 11 90 8.82 12 12 9.92 12 37 11,02 12 63 \

7 12 82 1478 1453 12 65 22LOS 12.13 11 47 27g56 Am in n \

6- 49,60 8 63 6

55,67 5 90 5 i 0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT) i 9

o

~.

CP&L Nuclear Fuels Mgmt & Sofety Anolysis File: NF-2202.024 B2C11 Core Operating Umits Report Page 11, Revision 0 Figure 7 ,

FUEL TYPE GE10-P8HXB324-12GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE ,

t 14 THIS FIG JRE IS RETRRED TC BY TI:CH'4lC/1SPECIFICATDN 3.2 1 13-f' N N

12

[

  1. p ;rwi35igiE \

REGION OF 03 ERAT 10N

\

O 11 8 '

R / N EXPOSL RE UIMT \

GWd/hT) (kW/ft) K 3

~3 10 " U.uu 0.22 lu /a 10 78

\ 1 1

g o

1.10 2.20 10 87 11 07 k  !

b 9 .

11 83

$ 5.51 E.61 12 02 7.72 12 22 I 8.82 12 44 G  ? 19 "

8 11 .02 12 96 13.78 13 17 16.53 12 93 22,05 12,27 (

27,56 11.62 \

7- g,g7 39,9, 38.58 10.27 44.09 9 52 49.60 8 78 " i 55.12 6 27 1 6 i 10 15 20 25 30 35 40 45 50 55 60 O 5 AVERAGE PLANAR EXPOSURE (GWd/MT)

t i

CP&L Nuclear Fuels Mgmt & Sofety Anolysis File: NF-2202.024 '

B2C11 Core Operating Umits Report Page 12, Revision 0 Figure 8 FUEL T(PE GE10-P8HXB320-11GZ-100M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE  :

14-THIS FIG JRE IS RETRRED TC BY Tl:CH91 CAL !;PECIFICATI')N 3.2.1 13-J \ '

12- ' l

[ N PER AIS!;lBLE REGION OF K '

OPE l RATION h

3 EXPDSt. RE LildlT \

l

'GWd/kT)

, (kW/ft) 3 10 U.uu iu si N

~i 0.22 10 87  %

1 .10 10 97

$ 2.20 11 10 b 9 .

5.51 11 53 Q 6.61 11 68 <

472 11 84 5.82 12.00 g; a o9 to ts 11 .02 12 33 13.78 12 52 '

16.53 12 40 22.05 11,93 27.56 11.44 k 7_ JJ,U / 1U4CD 38.58 10,26 1

44.09 9 47 49.60 8 68 55.12 6 15 a ,

0 5 10 15 20 25 30 35 40 45 50 55 60 )

AVERAGE PLANAR EXPOSURE (GWd/MT) i

_l

4 CP&L Nuclear Fuels Mgmt & Sofety Anolysis File: NF-2202.024 B2C11 Core Operating Umits Report Page 13, Revision O Figure 9 FUEL T(PE GE10-P8HXB322-11GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE h 14 TlilS FIG JRE IS RETRRE0 TC BY TECH ilCJLSPECIFICATI)N 3.2.1 13

^

X

\

N 12- ,

N g jg.pgF \

O'ERATIC N O

q 11 e N D(POST. RE UldiT \

GW3/hT) (kW/ft) K 3 10 U.uu au n+ 'N3

~) 0.22 10 88 g

o 1 .10 2.20 10 95 11 08 k

b 9-5.51 11 50

% 6.61 11 67 7.72 11 92 8.82 12 26 09 '? "'

8-11 .02 12 95 13.78 13 12 16.53 12 89 22.05 12 29 \

27.56 11.67 \

7 aa,v f 3v,3o 38.58 10 26 44,09 9 52 49.60 8 78 m 55.12 6 29 6

0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

l File: NF 2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 14, Revision 0 B2Cll Core Operating Limits Report t

Figure 10 i

Flow - Dependent MAPLHGR Limit, MAPLHGR (F) i 5

1.0 -

se? c qs0 ,E g O.9 -

Y #

g[

s N

h O8 -

MAPLHGRtF)-MAPFACp MAPLHGRSTO 3

e MAPLHGRSTD

V MAPFACptF)- MINIMUM (1.0, ApWC/100 + Spl O.7 WC = % RATED CORE FLOW j

O.6 -

MAXIMUM I CORE FLOW 1% rated) Ap Bf 102.5 06784 0.4861 107.0 0.6758 0.4574 O'5 -

0.4214 112.0 0.6807 117.0 0.6886 0.3828 I I I I I l 0.4 l i 90 100 110 >

60 70 80 30 40 50 CORE FLOW (% reted) I I

I 1

His figure is referred to by i Technical Specification 3.2.1 j l

l l

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l

. 1 File: NF 2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 15, Revision 0 i B2Cl1 Core Operating Limits Report i

l Figure 1I )

i Power - Dependent MAPLHGR Limit, MAPLHGR (P) 1.0 1 0.9 -

N t -

E ,

$ 0.8 -

G

& M APLHGR(Pl = M APFACp' M APLHGRSTO g  ;

t MAPLHGRSTD = STANDARD M APLHGR LIMITS g 0.7 s 50% CORE FLOW 4

2 FOR 25% >P. NO THERMAL LIMITS MONITORING REQUIRED i E ,

5 FOA 25% sP<30%:

6 06 -

MAPFACp 0.585 + 0.005224 (P- 30%)  ;

b FOR s 50% CORE FLOW O l MAPFACp = 0 433

  • 0.005224 lP- 30%) '

'" i FOR > 50% CORE FLOW l >50% CORE FLOW O.5 -

l g FOR 30% 5P. ,

s g

M APFACp . 1.0 + 0.005224 (P- 100%) '

{

l I I I ,

I I I 04 I 90 100 50 60 70 80 20 25 30 40 '

POWER (% ratedi k

l Dis figure is referred to by Technical Specification 3.2.1 l l

t i

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.024 Il2Cl1 Core Operating Limits Report Page 16 Revision 0 Table 1 MCPR Limits (EOC-RPT Not Required)

Non-pressuri7.ation Transient MCPR Limits Exposure Range: 110C11 to EOC11 GE8x8NB-3 BP8x8R/GFEx8FILGFAx8NH GE8x8NB-3 G E10-P811XB324 12GZ-70M-150-T GE10 P811XB322-IlGZ-70M-150-T/ All GE10-P811XB320 llGZ-100M-150-T/

GE10 P8HXB329-12GZl-100M-150-T 1.25 1.20 1.31

. Pressurization Transient MCPR Limits MCPR - Option A GE8x8NB/GE8x8NB-3 BP8x8R/GE8x8EB Exposure Range: IlOC11 to EOCil-3000 mwd /MT 1.34 1.33 Ey>osure Range: EOCl13000 mwd /MT to EOCll 1.35 1.33 MCPR - Option 11 GE8x8NB/GE8x8NH-3 BP8x8R/GE8x8EB Exposure Range: 110C11 to EOCll-3000 mwd /MT 1.27 1.26 Exposure Range: I:OCl13000 mwd /MT to EOCll 1.31 1.29 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2 l

l

l File: NF 2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 17. Revision 0 B2ClI Core Operating Limits Report i 4

Figure 12 Flow - Dependent MCPR Limit, MCPR (F) f 5

FOR WC (% RATED CORE FLOW) a:40%  :

FOR WC (% RATED CORE FLOWI < 40% MCPRIF) . MAX (1.20. ApWC /100 + BF ) '

MCPRIF).(ApW C/100 + 8F1 .j

'll + 0.0032140-WC il 7 _ MAX FLOW AF BF s - 0.632 1.809 117.0 112.0 - 0.602 1.747 107.0 - 0.586 1.697 l 1.6 -

102.5 - 0.571 1.655 1

MAXIMUM FLOW RATE = 117.0% '

1.5 -

112.0 %

E 107.0 % >

[ 102.5 % '

.L>

c 1,4 ~

i 1,3 -

i 1.2 -

I I I I l l I I 1,1 ( 90 100 110 120 50 60 70 80 20 30 40 CORE FLOW (% rated) i i

I l

This figure is referred to by l

Technical Specification 3.2.2.1 l

l l

I

File: NF 2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 18. Revision 0 H2Cl! Core Operating Limits Report Figure 13 Power - Dependent MCPR Limit, MCPR (P) 2d &

LMCPR RATED MCPR MULT4PtlER iKp)

R r Q

'e 23 -

> 50% CORE FLOW OPERATING LIMIT MCRP (P) = K,

  • OPERATING LIMIT MCPR (100) o 22 l NO THERMAL LIMITS MONITORING REQUIRED FOR P < 25%:

1 g l NO LIMITS SPECIFIED g g F OR 2 5 % 5 P s P,,,,,,: (P,,,,,, = 30%)

g l l K, = MAXIMUM OF 1.481 OR K g, 20 - l s 50% CORE FLOW Kn, = IK,,, + 0.02 (30% P)) / OLMCPR(1001 o y K ,,, = 1.9 FOR s 50% CORE FLOW h I9

~

2.2 FOR > 50% CORE FLOW l I

  1. 18 - FOR 30% 5 P < 45%:

K, = 1.28 + 0.0134 (45% P)

/

~

l- * = FOR 45% s P < 60%:

e I I K, = 1.15 + 0.00867 (60% Pi i , _

FOR 60% s P; g l g K, = 1.0 + 0.00375 (100% P)

[6 1.3 -

l l

l t

$ 12 -

l l i I

$ i 2 1.1 -

l l l I I 8 I I I I f f f f i E 10 I I 90 100

" 50 60 70 80 20 25 30 40 PDYPASS POWER (% steal This figure is referred to by Technical Specification 3.2.2.1 i 1

l l

l l

CP&L Nuclear Fucts Mgmt & Safety Analysis File: NF-2202.024 Page 19. Revision 0 B2Cl1 Core Operating Limits Report Table 2 RBM System SetpointS Trin Setnoint Allowable Value Setnoint 27.0 s 29.0 lew Power Setpoint (LPSf")

62.0 s 64.0 Intermediate Power Setpoint (IPSI")

82.0 $ 84.0 liigh Power Setpoint (liPSI")

s 115.1 s 115.5 tow Trip Setpoint (LTSP")

s 109.3 s 109.7 Intermediate Trip Setpoint (ITSP")

s 105.5 s 105.9 liigh Trip Setpoint (liTSI*)

s 2.0 seconds s 2.0 seconds to Setpoints in percent of Rated Thermal Power.

  • 115.1/125.0 of full Setpoints relative to a full scale reading of 125. For example, s 115.1 means s scale.

f This table is referred to by Tecimical Specification 3.3.4 (Table 3.3.4-2)

ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 NRC DOCKET NO. 50-324 OPERATING LICENSE NO. DPR-62 SUPPLEMENTAL RELOAD LICENSING REPORT I

I

. 1 I

ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 NRC DOCKET NO. 50-324 OPERATING LICENSE NO. DPR 62 LOSS-OF-COOLANT ACCIDENT ANALYSIS REPORT l

1

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_ _ _ - _ _ _ . _ _____________a

General Electric Company AFFIDAVIT I, James F. Klapproth, being duly sworn, depose and state as follows:

(1) I am Fuel Licensing Manager, General Electric Company ("GE") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is the attached document entitled " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 10 Cycle 11", NEDC-31624P, Supplement 2, Revision 2, April 1994.

(3) In making this application for withholding of proprietary information of which it is the owner, GE mlics upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"),5 USC Sec. 552(b)(4), and the Trade Secrets Act,18  !

USC Sec.1905, and NRC regulations 10 CFR 9.17(a)(4), 2.790(a)(4), and  ;

2.790(d)(1) for " trade secrets and commercial or financial information obtained from ,

a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all " confidential commercial information",

and some portions also qualify under the narrower definition of " trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission.

975F2d871 (DC Cir.1992), and Public Citizen Health ~ Researth Groun v. FDA, 704F2d1280 (DC Cir.1983).

(4) Some examples of categories of information which fit into the definition of i proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting ,

data and analyses, where prevention of its use by General Electric's competitors l without license from General Electric constitutes a competitive economic l i

advantage over other companies; i

b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufactum, shipment, installation, assurance of quality, or licensing of a similar product; l

l

)

.12/13/93RTil Affidavit Page 1  !

. - - J

t

c. Information which reveals cost or price information, production capacities, budget 1cvels, or commercial strategies of General Electric, its customers, or its suppliers;
d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric;
e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

The information sought to be withheld is conside rd to be proprietary for the reasons set forth in both paragraphs 4.a and 4.b, above.

(5) He information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GE, and is in fact so held.

The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GE, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthodzed disclosure, are as set forth in paragraphs (6) and (7) following.

(6) Initial approval of proprietary treatment of a document is made by the manager of the odginating component, the person most likely to be acquainted with the value and sensitivity of the information in Irlation to industry knowledge. Access to such documents within GE is limited on a "need to know" basis.

(7) The procedure for approval of extemal release of such a document typically requires review by the staff manager, project manager. principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2), above, is classified as proprietary because it would provide other parties, including competitors, with information related to General Electric fuel designs and analysis results which were developed at a

considerable expense to General Electric.

l l

l tul3h3RTH Affidavit Page 2

t. ._ _
c. Information which reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers;
d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric;
e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

The information sought to be withheld is considered to be proprietary for the reasons set forth in both paragraphs 4.a and 4.b, above.

(5) The information sought to be withheld is being Submitted to NRC in confidence. The infomiation is of a sort customarily held in confidence by GE, and is in fact so held.

The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GE, no public disclosum has been made, and it is not available in public sources. All disclosures to third parties including any mquired transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agmements which provide for maintenance of the infonnation in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such documents within GE is limited on a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensecs, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2), above, is classified as proprietary because it would provide other parties, including competitors, with information related to General Electric fuel designs and analysis results which were developed at a considerable expense to General Electric.

tvlw3mt Affidavit Page 2

(9) Public disclosure of the information sought to be withheld is likely to cause ,

substantial harm to GE's competitive position and foreclose or reduce the availability '

of profit-making opportunities. The information is part of GE's comprehensive BWR technology base, and its commercial value extends beyond the original development  :

cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process.

l The research, development, engineering, and analytical costs comprise a substantial  ;

investment of time and money by GE.

i The precise value of the expertise to devise an evaluation process and apply the i correct analytical methodology is difficult to quantify, but it clearly is substantial i GE's competitive advantage will be lost ifits competitors are able to use the results of the GE experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar coinclusions.

The value of this information to GE would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.

l 12/13/93RT11 Afnd. wit Page 3 !

STATE OF CALIFORNIA )

) ss:

COUNTY OF SANTA CLARA )

James F. Klapproth, being duly sworn, deposes and says:

That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.

Executed at San Jose, California, thisONday of Me 1994.

2 w v.Yd m W James F. Klapproth 9D General Electric Company Subscribed and sworn before me this S7 day of 44 1994.

f IAA4 k U Notary Pubfic, State of California MARY L. KENDALL E COMM. # 987864 z .

5 Notory Public - Canfornio $

~

l I SANTA CLARA COUNTY r j Comm. Expres MAR 26.1997 ) j

-v -----. .. m  ;

)

i l

tvtan3RT11 Affidavit Page 4 l

l u  :

STATE OF CALIFORNIA )

) ss:

COUNTY OF SANTA CLARA )

James F. Klapproth, being duly sworn, deposes and says:

That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.

Executed at San Jose, California, this-lT7 dayof Mcw 1994.

C' W T. Y82nw%

James F. Klapproth 4D General Electric Company Subscribed and sworn before me this #7 day of (tw 1994.

f h% $

Notary Pubfic, State of California MARY L. KENDALL i1 COMM. # 967864 Noto y P2GC - Cobfomio SANTA CLARA COUNTY g

~

F j My Comm. Egwes MAR 26.1997 )

m l#13/93RTH Affidavit Page 4

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