ML20058P868

From kanterella
Jump to navigation Jump to search
Cycle 9 Colr
ML20058P868
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 10/31/1993
From: Blom M, Karcher K
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19311B274 List:
References
NUDOCS 9312270312
Download: ML20058P868 (21)
v • d • e


Text

_ . ._ -. . .. . _ _.

I i

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BIC9 Core Operating Limits Report Page 1, Revision 0 I BRUNSWICK UNIT 1, CYCLE 9  :

CORE OPERATING LBilTS REPORT $

)

OCTOBER 1993 -

i i

Controlled Copy />l l

l i

i I

l I

1 l

l l .

l t

1

~

! Prepared By: Michael A. Blom i

P i

i Approved By:, [ .

M Date: /C V f3 ,

f Kenneth E. Karcher Manager BWR Fuel Analysis  ;

l r

9312270312 931217  : -

PDR ADOCK 05000325  ;<

p PDR 1

l CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 ,

BIC9 Core Operating Limits Report Page 2, Revision 0 l l

LIST OF EFFECTIVE PAGES Pace (s) Revision

-i 1-16 0 l

1 1

e d

, e - r- --,--,-,-ev -r - 1 v--- ,we

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BIC9 Core Operating Limits Report Page 3. Revision 0 5

i INTRODUCTION AND SUMM ARY This report provides the values of the power distribution limits and control rod withdrawal block instrumentation

serpoints for Brunswick Unit 1, Cycle 9 as required by Technical Specification 6.9.3.1. The values of the Average i i Planar Linear Heat Generation Rate (APLHGR) limits, along with associated core flow and core power adjustment l factors are provided as required by Technical Specification 6.9.3.1.a. The values of the Minimum Critical Power l Ratio (MCPR) limits, along with associated 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 repon was performed in accordance with CP&L Nuclear Fuels Management & Safety Analysis Quality Assurance requirements as documented in Reference 1.

APLHGR LIMITS The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average exposure is given in Figures 1 through 6. These values were determined with the SAFER /GESTR LOCA methodology described in GESTAR-II (Reference 2). Figures 1 through 6 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 7 and 8. For any given flow / power state the minimum of MAPLHGR(F) determined from Figure 7 and M APLHGR(P) determined from Figure 8 is used to determine the governing limit.

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 B1C9 Core Operating Limits Report Page 4, Revision 0 MCPR LIMITS i

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 Table 1.

These values were determined with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-ll (Reference 2) and are consistent with the Safety Limit MCPR of 1.07 specified by Technical Specification 2.1.2.

The core flow and core power adjustmenty' factors for use in Technical Specification 3.2.2.1 are presented in Figures  !

9 and 10. For any given flow / power state the maximum of MCPR(F) determined from Figure 9 and MCPR(P) determined from Figure 10 is used to determine the goveming limit.  ;

ROD BLOCK 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-2493.0053,

" Preparation of the Brunswick Unit 1, Cycle 9 Core Operating Limits Report," (September 1993).

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

i l

l CP&L Nuclear Fuels Mgmt & Sofety Analysis File: NF-2202.021  !

B1C9 Core Operating Limits Report Page 5, Revision 0 1 Figure 1 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 13 THIS FIGURE IS REFERRED TC' BY Tl:CHNICAL SPECIFIC @Ob 3.2.1 12.2 12,3 g #N 12,1 12

/ N 11.C

[ N  :

5 11

$ I PEF:MISSIBLE v 10.9 REClON OF OPi: RATION g

s

] \ 10. 5 s

z 10 \

$ bs '

N  ;

, \ l 9.0 l

8 0 5 10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPOSURE (GWd/ST) l 4

I l

CP&L Nuclear Fuels Mgmt & Sofety Analysis File: NF-2202.021 ,

B1C9 Core Operating L;mits Report Page 6. Revision 0

)

i Figure 2 FUEL TYPE BD3238 (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THIS FIGUFE IS RETRF:ED TO liY TE::HN CAL SPECIFit:ATIONJ.2.1 13.14

t 1275 i 13 12.1 9

[ K 12.07 12

[1 1.81 h l 1.

O g3 11 29 5 PI:RMISSIB'E 10,65  :

3 RI:GION Ol 6 OPER/ TION h 10 3

\ 23 s

3 g 3\

k 52 8 -

7 N F.06 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST)

i CP&L Nuclear Fuels Mgmt & Sofety Anotysis File: NF-2202.021 B1C9 Core Operating Umits Report Page 7, Revision 0 ,

l l

1 Figure 3 l FUEL TYPE BD339A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE l 14  !

Tli!S FIGUFE 15 RETRF:ED TO Irf TECHN; CAL SPECIFICATKIN 3.2.1

.88 $3 ,g4 13 2.58 l 12 2.02 \ g i

/ \ 1 1.58

/

11.43 11 ' 6

\\ 1 B. 97 l

7 .

PERMl!;SIBl.E \

hG l F lON \ 1E .36 3 10

\  :

3 9. 57 s

s, \s Q h 8 .79 l l

8

\

7 \

6.22 , l 6 ,

O 5 10 15 20 25 30 E 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST)

CP&L Nuclear Fuels Mgmt & Sofety Anolysis B1C9 Core Operating Umits Report File: NF-2202.021 I Page 8, Revision 0 Figure 4 FUEL TYPEAVERAGE GE10-P8HXB322-11GZ-70M-150-T PLANAR UNEAR HEAT (GE8X8NB-3)

GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THIS FlGUFE 15 RE TRF:ED TO Irf TECHN CAL SPE CIFICATKN 2.2.1 13-

/\

12 N

R$1d $# \

0) ERAT 10F O 11 -# #

x

  • EXPOSURE UkiT (GWd, /ST)
  • (kW/ft) 3 10 u.uu l u.ia k 0.20 10.38 3 1.00 10.95

$ 2.00 11.08 b 9-

% 5.00 A 11.30 6.00 7.00 11.57 h 11.92 8.00 12.,'26 8- """ ' A' 10.00 12.95 12.50 13.12 15.00 12.89 20.00 12.29 7_ 25.00 11.67 av.vu i v.w o 35.QO 10.26 40.00 9.62 45.00 8.78 50.00 6.:29 6- ,

0 5 1 ,

1 10 15 20 t j 25 30 35 40 1

45 50 AVERAGE PLANAR EXPOSURE (GWd/ST)

l CP&L Nuclear Fuels Mgmt & Sofety Analysis File: NF-2202.021 B1C9 Core Operating Umits Report Page 9, Revision 0 Figure 5 FUEL TYPE GE10-P8HXB324-12GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT i VERSUS AVERAGE PLANAR EXPOSURE 14 I THIS FIGUFE 15 RETRFlED TO Irf TE::HNl CAL SPECIFICATION 3.2.1 13 <

A ,

/ N\

I RIEGIO4OF O'ER)T10PI \

O 11 d x

" E.XPOSURE Ub1T (3Wd/ST) (kW/ft) t H \w 3 10 u.uu l u. ro .

J 0.20 10. 78 1.00 10.37

$ 2.00 11.07 3 g N N Q 5.k0 ii.ii3 h 6.00 12.02 7.00 12.:22 8.00 12.44 3

o an 19 vn 10.00 12.50 12.6

13. 7

\

)

15.00 12. 3 -

20.00 25.00 12.l17 11.62

\ \

7 Ou.uu i v.w+

35.00 10.:27 40.00 9.62 45.00 8.78 '

50.00 6.:27 6

0 5 10 15 20 25 30 35 40 . 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST)

i t

i CP&L Nuclear Fuels Mgmt & Safety Anolysis File: NF-2202.021 B1C9 Core Operating mits Report Page 10, Revision 0 Figure 6 FUEL TYPE GE10-P8HXB320-11GZ-100M-150-T- (GE8X8NB-3)

AVERAGE PLANAR UNEAR HEAT GENERATION RATE VERSUS AVERAGE P(APLHGR) LIMIT LANAR EXPOSURE 14 THIS FIGUFE IS RETRF:ED TO IW TECHN CAL SPECIFICATIONJ.2.1 13

/ \

12 \

/ PERIAISS:BLE sK  :

REGION 3F I OPEllATION j

x

" E.XPOSURI: LINIT

\\ '

i (3Wd,/ST) (kW/ft) T W

3 10 u.uu i v.a1 N  %

J 0.20 10.37 \ j 1.00 2.00 10.97

11. 10 h l

@ 3.00 11.'.24 l

r l J 9 t"0 11.30 Q 5.h0 6.00 11.!53 11.158

\

7.QO 11.34 8.00 12.00 8

10.00 12.33 1250 12.52 l 15.00 12.40 20.00 11.93 (

7 25.00 11.44 \

av.yu i v.ua 35.03 10.:!6 40.00 9.47 45.00 8.iS8 50.00 6. I5 c 6

0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST) 1

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.U21 BIC9 Core Operating Limits Report Page 11, Revision 0 I

Figure 7 Flow - Dependent MAPLHGR Limit, MAPLHGR (F) i l

1.0 - I l

s*

o*. l

/' ,$ '$* s 0.9 -

g O* l 9

U l

$ 0.8 2 MAPLHCRtF1= MAPFACp MAPLHGRSTD E

S MAPLHGRSyp = STANDARD MAPLHGR LIMITS u

I MAPFAC F IF) MINIMUM 11.0. ApW g C t100 + 8F I WC- % RATED CORE FLOW

i 2 l k 0.6 I MAXIMUM CORE FLOW t% #ated AF SF 0.5 . 102.5 0.6784 0.4861 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.4 I I I l I I I 30 40 50 60 70 80 90 100 110 CORE FLOW t% rated)

This figure is referred to by Technical Specification 3.2.1

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BIC9 Core Opera:ing Limits Repon Page 12, Revision 0 l

Figure 8 l

Power - Dependent MAPLHGR Limit, MAPLHGR (P) i l

1.0 l

l l

1 0.9 -

N l t  ;

  • l E  !

$ 0.8 -

G 1

e MAPLHGR(Pl = MAPFACp'MAPLHGRSTD 0.7

{I s 50% CORE FLOW MAPLHGASTO = STANDARD MAPLHGR LIMITS FOR 25% > P: NO THERMAL LIMITS MONITORING E REQUIRED 8 5% s N 30%

[

f 0.6 -

MAPFACp = 0.5 8 5 + 0.005 224 (P- 30%)

0 FOR s 50% CORE FLOW 5  : uAprACP-0.433 +0.o05224 P-30%i-1 > 50% CORE FLOW FOR > $0% CORE FLOW 0.5 -

t g g e FOR 30% sP:

l MAPFACp = 1.0 + 0.005224 IP- 100%) i l

1 j o.4 I l I l I I l l 20 25 30 40 50 60 70 80 90 100 l

POWER (% rated! )

l, This figure is referred to by l Technical Specification 3.2.1 i

i l'

I i

i

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BIC9 Core Operating Limits Report Page 13, Revision 0 j i

Table 1 MCPR Limits l Non-pressurization Transient MCPR Limits Exposure Range: HOC 9 to EOC9 -

GE8x8NB-3 GE8x8NB-3 GFEx8EB/BP8x8R GE10-P811XB324-12GZ-70M-150-T GE10-P811XB322-IlGZ-70M-150-T/ All GE10-P8HXB320-IIGZ-100M-150-T 1.31 1.23 1.22 i

Pressurization Transient MCPR Limits i

MCPR - Option A l

GE8x8NB-3 GE8x8EB/BP8x8R Exposure Range: BOC9 to EOC9-2600 mwd /ST 1.36 1.35 Exposure Range: EOC9-2600 mwd /ST to EOC9 1.37 1.36 MCPR - Option B GE8x8NB-3 GE8x8EB/BP8x8R Exposure Range: BOC9 to EOC9-2600 mwd /ST 1.29 1.28 Exposure Range: EOC9-2600 mwd /ST to EOC9 1.33 1.32 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2 l

l .- --

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BIC9 Core Operating Limits Report Page 14, Revision 0 l

Figure 9 Flow - Dependent MCPR Limit, MCPR (F) -l l

!L FOR WC (% RATED CCRE FLOW) < 40% FOR WC (% RATED CCRE FLOW) = 40% - '

MCPR(F) = 1 ApWC/100 + Spl MCPRIFl = MAX (1.20, ApWcf100 + Bpl

'll + 0 0032 (40- WC II

'7 _

MAX FLOW Ap By l l

117.0 -0.632 1.809 .

112.0 -0.602 1.747 1.6 1. 107.0 - 0.586 1.697  :

102.5 - 0.571 1.655 l

i 1.5 - MAXIMUM FLOW RATE = 117.0%

0 112.0 % ^

107.0 %

[

v 102.5 % j 2

1.4 -

e I

1.3 -

J 1.2 -

3,3 I i 1 I I I I I I 20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% retodi This figure is referred to by Technical Specification 3.2.2.1

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BlC9 Core Operating Limits Report Page 15, Revision 0 ,

l 1

l Figure 10 ,

l l

l Power - Dependent MCPR Limit, MCPR (P)

RATED MCPR MULTIPLIER (Kp) r i v

$ 2.3 -

l kl: l i

OPERATING LIMIT MCPR (P)= Kp* OPERATING LIMIT MCPR (100) j o

"  ! > 50% CORE FLOW

$ 22

~

l FOR P< 25%: NO THERMAL LIMITS MONITORING REOUIRED l I

  • NO LIMITS SPECIFIED g l 2A ~

! FOR 25% sPCPsypAss: (PBYPASS = 30%)

i I l g

U 2.0 - l KP"lKBYP + 0.02 (30% - P)l/OLMCPR (100) l I s 50% CORE FLOW Kgyp= 1.9 FOR s 50% CORE FLOW g

I = 2.2 FOR > 50% CORE FLOW

., , ,9 x l 1 g

FOR 30% sP< 45%:

~

l Kp = 1.28 + 0.0134 (4 5% - P)

# f o- 1.5 - FOR 45% sP<60%

z k--

0 I g Kp = 1.15 + 0.00867 (60% -P)

~

h#

e I

l I

l FOR 60% sP:

1.3 l K p = 1.0 + 0.00375 (100% - P) p -

g I

5 l i u -

i l I E  : I l 5u -

i i I 3 l l 1 I E l I I I I I I I I

  • 1.0 40 50 60 70 80 90 100 20 25 30 l

PBYPASS POWER 1% rated)

This figure is referred to by Technical Specification 3.2.2.1 i

4 - _ _ , . . - - . . . - - _ . . - _ . . . . ,__

I CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.021 BIC9 Core Operating Limits Report Page 16, Revision 0 l

1

.'t Table 2 RBM System SetpointS Setooint Trio Setpoint Allowable Value Imw Power Setpoint (LPSP') 27.0 s 29.0 Intermediate Power Setpoint (IPSP') 62.0 s 64.0 High Power Setpoint (HPSP') 82.0 s 84.0 I

Imw Trip Setpoint (LTSPb) s 115.1 s 115.5  !

Intermediate Trip Setpoint (ITSP') s 109.3 s 109.7 )

High Trip Setpoint (HTSP") s 105.5 s 105.9 to s 2.0 seconds s 2.0 seconds Setpoints in percent of Rated Thermal Power.

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

I i

l, This table is referred to by Technical Specification 3.3.4 (Table 3.3.4-2)

i ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO. 50-325  :

OPERATING LICENSE NO. DPR-71 )

SUPPLEMENTAL RELOAD LICENSING REPORT t i

l l

l l

l l

_ ._ ---__--_-1

ENCLOSURE 3 I BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO. 50-325 OPERATING LICENSE NO. DPR-71 1 LOSS-OF-COOLANT ACCIDENT ANALYSIS REPORT i

i l

1

l GENERAL ELECTRIC COMPANY AFFIDAVIT l l

1, JAMES F. KLAPPROTil, 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 contained in the document: Loss-of-Coolant Accident Analysis Reportfor Brunswick Steam Electric Plant, Unit 1, Reload 8 Cycle 9, NEDC-31624P, Supplement 1, Revision 1, May 1993. This information is delineated by vertical bars marked in the margin adjacent to the specific material.

(3) In making this application for withholding of proprietary information of which it is the owner, GE relies 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), a-d 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, respe.ctively, Critical Mass Enerev Project v. Nuclear l Reculatory Commission. 975F2dS71 (DC Cir.1992), and Public Citizen Health Research l Groua v. FDA, 704F2d1280 (DC Cir.1983).

l l (4) Some examples of categories of information which fit into the definition of 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 without license from General Electric constitutes a competitive economic advantage over other companies; l
b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
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 l i

customer-funded development plans and programs, of potential commercial value to General Electric; l l

i l

e. Information which discloses patentable subject matter for which it may be  ;

desirable to obtain patent protection. l (5) The 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. Its  ;

initial designation as proprietary information, and the subsequent steps taken to prevent  !

its unauthorized disclosure, are as set forth in (6) and (7) following. 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.  !

(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 docum_ent 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) is classified as proprietary because it contains  :

details of the U-235 enrichment and gadolium distributions for the fuel bundles. In  !

addition, exposure dependent MAPLHGR limits and local peaking factors are provided for each fuel lattice. This information provides insights into the GE thermal / mechanical l criteria, the critical power correlation and the nuclear advantages of the mechanical  ;

improvements incorporated in the fuel design. This information is considered to be i proprietary for the reason set forth in paragraph 4.b, above. l 4

I (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-makin;; upportunities. The information is part of GE's comprehensive BWR technology base, and its ommercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and '

l analytical methodology anc includes development of the expertise to detcrmine and apply the appropriate evaluatirn process. In addition, the technology base includes the value i derived from providing analyses done with NRC-approved methods. l A

i l

The research, development, engineering, analytical, and NRC review costs comprise a substantialinvestment of time and money by GE.

The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.

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 l 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. r 1

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, informa: ion, and belief.  ;

Executed at San Jose, California, this 4bday of M/^m .193 6 .

T Y YRnS James F. Klapproth M General Electric Company Subscribed and sworn before me this J day of  % .19f.

  1. r l.

mRY L KENDALL CoMM. s 087864 5 M

Notary Ptiblic, State of California z: . Noto y Public - Califorrso l Z M #

SANTA CLARA COUNTY

, , , * * ^

th Comm, Expiros MAR 26.1997 .

I i-I l< , g COMM p 987864 z

.e 4 Notory Pubfic - Cohfornlo f

%. ?ANTA CLARA COUNTY

~

-,,__.1.

.. . .fm. Expires MAR 26.1997 f -

. . . . . r J

l

1

~

t GENuclearEnergy c

i f

s I

- - ~.-n,.-c.-.

& ----n. .

P*

>e

-. -w- as w& '

t I

r b'

b 4'

P i

i l

f I

i i

f l

l

( l l 4 l

,

Retrieved from "https://kanterella.com/w/index.php?title=ML20058P868&oldid=3079626"