ML20198B869
| ML20198B869 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek |
| Issue date: | 12/17/1997 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20070L059 | List: |
| References | |
| LR-N97781, NUDOCS 9801070097 | |
| Download: ML20198B869 (25) | |
Text
{{#Wiki_filter:, f ! k; PutAc Service s. Eiedric ar d Gas Company E C, Simpson Pubhc Service Electro and Gas Company P.O. Box 236. Hancocks Ondge. NJ 08038 609-339-1700 s-- we r- - tm DEC 171997 LR-N97781 United Staces Nuclear Regulatory Commission Document-Control Deuk Washington, DC 20555 CORE OPERATING LIMITS REPORT, NFS.0162, REV. O HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Gentlemen: In accordance with Technical Specific ation 6. 9.1. 9, Public -Service Electric and Gas (PSE&G) hereby transmits the Hope Creek Generating Station Cycle 8/ Reload 7 Core Operating Limits Report, NFS-0162, Revision 0 (Attachment 1 of this letter). The specific core operating limits contained in NFS-0162 have been determined using NRC-approved methodology and were established such that all applicable limits of the plant safety analysis continue to be met. The appendices of NFS-0162 have not been included as they contain proprietary information of the General Electric Company (GE). However, the proprietary information contained in Appendices A, B and C have been previously docketed with the NRC in the following two GE reports: " Supplemental Reload Licensing Submittal for Hope Creek . Generating Station Unit 1, Reload 3, Cycle 4", General Electric 23A6526AA, Rev. O, Supplement 1, January 1991. " Lattice-Dependent MAPLHGR Report for Hope Creek Generating Station Unit 1, Reload 5, Cycle 6", General Electric 23A7219AA, Rev. O, October 1993. The proprietary information contained in Appendices D and E of NFS-0162 have not been docketed previously with the NRC. Therefore, GE has provided an affidavit (Attachment 2) in accordance with 10CFR2.790 for the attached GE report -(Attachment 3): " Lattice-Dependent MAPLHGR Report for Hope Creek Generating Station, Reload 7, Cycle 8", General Electric 24A5392AA, Rev. f 0, May 1997. F 9601070097 971219 [(~['] V ' I PDR ADOCK 05000354 /. i P P DR,. THE INFORMATION IN ATTACHMENT 3 OF THIS LETTER IS PROPRIETARY - NOT FOR PUBLIC DISCLOSURE - fN em.d on. y, ( s? wam i m.
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A-Document ControliDesk'- 2 ._LR-N97781: ~ ~ J3hould;you;have any questions'or: comments'on this= transmittal,-do
- not hesitate to contact us.,
Sincerely, / Affidavit- ' Attachment s.J- ( 3 ) - i C/ Mr. H. J. : Miller, Administrator, . Region I ~ U. S. Nuclear. Regulatory Commission
- 475 Allendale Road-King of Prussia, PA'19406 M a'. - B. Mozafari, Licensing Project Manager - Hope Creek
- U.cS. Nuclear Regulatory Commission One White Flint North - 11555-Rockville Pike -Mail Stop.14E21 Rockville, MD 20852~ 1 Mr. S. Morris USNRC Senior Resident Inspector (X24) - Mr. K. Tosch,' Manager IV Bureau of Nuclear Engineering - PO Box-415 Trenton, NJ- 08625 1 e d .g .THE INFORMATION IN ATTACHMENT 3 0F THIS LETTER IS PROPRIETARY - - NOT FOR PUBLIC DISCLOSURE - l 95 4933 -. I
s t-1 REF:-LR-N97781- - S_ TATE OF NEW JET.SEY :-) - . )' SS. COUNTY OF SALEM. )' ~ E.-C.eSimpson, being-duly sworn according to law deposes and
- saysi,
-I.'am Senior Vice President Nuclear Engineering of.Public Service Electric-and' Gas Company, and as.such,-I find the matters' 1 ~ set forth in the above referenced. letter, concerning Hope Creek - Generating Station, Unit 1, are true to the best.of my knowledge, information~and belief. ) / .nry3xrx ( g-Subscribed and Sworn to'befere T.; g this /7 day of //e d, 1997 ~
- NotaryPtOlic-ofkbw'JMrsey ELIZABETH J.1000
- NOTARY PUBUC OF NEW JERSEY My Commission expires on. My Commission Empires Apes 26,2000 + t e 4 v L -g t4 --r-e y p e n-e ~ n 4 n, r r
4 ATTACHMENT 1 liope Creek Generating Station Core Operating Limits Report, Cycle 8 / Reload 7 NFS-0162, Rev. O
. O PSEG if,fe'n 62 November 25,1997 IIOPE CREEK GENERATING STATION CORE OPERATING LIMITS REPORT CYCLE 8 / RELOAD 7 November 25,1997 Prepared By:
- 2
/ oe# Date: / / Serhor ' taff Engineer S Reviewed By: AM / Ad Dee:
- /E 97 Senior ha f Eng(n#
eer Concurrence, / Date: s - ilC R&SA init[upervisor Approved By: ^ - /- Date: Manager NuctedFuel
Re s on November 25,1997 I i TABLE OF CONTENTS l Section Descrlptlon Page l.0 I NT R O D U CTION....................................... 5 2.0 LIMITING CONDITIONS FOR OPERATION..................... 6 2.1 AVERAGE PLANAR LINEAR llEAT GENERATION RATE ..... 7 2.2 MINIMUM CRITICAL POWER RATIO........... 13 - 2.3 LINEAR llEAT GENERATION RATE........ 1.6 3.0 RE FE R E N C ES.... '..................................... 17 i APPENDIX A Bundle Descriptions and Composite APLilGRs for Fuel Bundle ' GE98 P8CWB324 90Zl 80M 150 T........................... 18, APPENDIX B Bundle Descriptions and Composite APLilGRs for Fuel Bundle GE98 P8CWB325-ilGZl 80M 150-T.......................... 21 APPENDIX C Bundle Descriptions and Composite APL11GRs for Fuel Bundle GE9h P8CWB325 1IGZ2 80M 150-T......................... 21 APPENDIX D Bundic Descriptions and Composite APLiiGRs for Fuel Bundle GE98 P8CWB298-8GZ 80U 150-T............................ 27 APPENDIX E Bundle Descriptions and Consposite APLilGRs for Fuel Bundle GE98-P8CWB327-80Zl 80U 150 T ,......................., 30 ~ v i w F . Page 2 of 32 ^
.O PSFL ""23 November 25,1997 i i LIST DF FIGURES FigureTitle Page 21 APLilGR Limit fot Fuel Bundle GE98 P8CWB324 90Z180M 150 T.. .8 2-2 APLIIGR Limit for Fuel Bundle GE9B P8CWB32511GZ180M 150 T.... 9 23 APLilGR Limit for Fuel Bundle GE9B P8CWB325 ilGZ2 80M 150 T... 10 2-4 APLIIGR Limit for Fuel Bundle GE98 P8CWD298 8GZ-800150 T...... I1 25 APLIIGR Limit for Fuel Bundle GE9B P8CWB327 8GZl-800150 T..... 12 2-6 Minimum Critical Power Ratio Operating Limit 14 27 K f M ultiplier curve...................................... 15 s A1 Lattice Definitions for Fuel Bundle GE98 P8CWB324 9GZ180M 150-T.... 19 B1 Lattice Definitions for Fuel Bundle GE98-P8CWB32511GZl 80M 150-T,. 22 C-1 Lattice Definitions for Fuel Bundle GE98-P8CWB325-11GZ2 80M 150-T... 25 D-1 Lattice Definitions for Fuel Bendle GE9B P8CWB298 8GZ-80U-150-T..... 28 E-1 Lattice Definitions for Fuel Bundle OE9B-P8CWB327-8GZl-80U-150 T.... 31 ~ Page 3 of 32 p-Jh e y -awg g
~ - Rev sion - November 25.1997 LIST OF TABLFJ Table Title Page ll 2 1-Li lG R LL e ts........................................... 16 A1 APLHGR Data for Fuel Bundle GE9B P8CWB324 9GZl-80M-150-T..... 20 j B1 - APLHGR Data for Fuel Bundle GE9B P8CWB32511GZl 80M 150 T..... 23 C1 APLilGR Data for Fuel Bundle GE9B P8CWB325 ilGZ2-80M-150 T.... 26 D1 APLIIGR Data for Fuel Bundle GE9B P8CWB298 80Z-800150 T....... 29 E-1 APLilGR Dua for Fuel Bundle GE9B P8CWB3274GZl 80U-150 T..-.... 32 1 3 . Page 4 of 32 y a W y yay,,. g 3 y-p+y. w-y -y-- gg +y p -pq,,ney-g-m-g, -,y--.wgwm y e.r,
NrS-0162 . O' PSEG Revision 0 November 25,1997
1.0 INTRODUCTION
The purpose of this report is to provide the Core Operating Limits for the llope Creek Generating Station Unit 1 Cycle 8 / Reload 7 operation. The limits presented here correspond to the core thermal limits for Average Planar Linear IIcat Generation Rate (APLilGR), hiinimum Critical Power Ratio (h1CPR), MCPR Flow Adjustment Factor (K,), and Linear lleat Generation Rate (LilGR). These operating limit values have been determined using NRC approved methods contained in GESTAR-il, NEDE-24011-P A, (latest approved version), and are established such that all applicable fuel thermal-mechanical, core thermal hydraulic, ECCS, and nuclear limb such as shutdowns margin, and transient and accident analysis limits are met, hiethods for th( cycle specific evaluation of the Safety Limit Minimum Critical Power Ratio (SLhiCPR) have been approved by NRC in llope Creek Technical Specification Amendment #107. The operating limit values for the MCPR LCO include a conservative penalty relative to, GESTAR-II, NEDE 240ll P A to account for the potential effects of a condition being evaluated or pending resolution through the PSE&G Corrective Action Program. This is due to evaluations for Time Varying Axial Power Shapes. The evaluation of Fuel Spacer Band Flow rabs has been concluded without an LCO impact. These items were evaluated in References 7 and 8 and are described in DEF # Dell-93-00183 and PIRS item #971008105, llope Crcek Technical Specifict.tions section 3.2 references this report as the source for certain Llh11 TING CONDITIONS FOR OPERATION. These are included in section 2 of this document, llope Creek Technical Specifications section 6.9.1.9 also requires that this report. including any mid-cycle revisions, shall be provided, upon issuance, to the NRC. This document is specific to llope Creek Unit 1 Cycle 8 / Reload 7 and shall not be applicable to any other core or cycle design. The current revision of this report covers the operation from the date of issuance through the end of effective full power capability, or a cycle exposure of 8,860 hiWD/STU, whichever comes first. End of effective full power capability is reached when 100% rated power can no longer be maintained by increasing core flow (up to 105% of rated core flow), at rated feedwater teniperatures, in the all-rods-out configuration. Page 5 of 32
_.- _. - ~. NFS 0162 ', Q* g Revision 0 November 25.1997 i 2.0 LIMITING CONDITIONS FOR OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the liope Creek Technical Specifications. Tech. Spec Ijtig 3/4.2.1 Average Planar Linear IIcat Generation Rate 3/4.2.3 Minimum Critical hswer Ratio 3/4.2.4 Linear IIcat Generation Rate f 6 t L Page 6 of 32
O PSFL f;Sfd November 25,1997 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION: All AVERAGE PLANAR LINEAR llEAT GENERATION RATES (APLilGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in Appendix A. Table A l. Appendix B Table B 1, Appendix C, Table C 1, Appendix D. Table D 1 and Appendix E, Table E 1. The limits specified shall be reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation. NOTE The lattice dependent APLilGRs for the P8CWB (GE9B) fuel types are included in the appendices to this report in order to accommodate GE proprietary considerations. The appendices will be identified to contain GE proprietary data and handled accordingly by the NRC when they receive their copy of the COLR report. The APLilGR LCOs contained in tie appendices to this report shall have the same consideration rad treatment by PSE&G personnel as if they were in the body of the COLR. In addition, note that the APLilGR LCOs in the appendices are established in the NSSS computer for thermal limits monitoring via approved plant procedures, m When hand calculations are required, all AVERAGE PLANAR LINEAR llEAT GENERATION RATES (APLilGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in Figures 21 through 2-5. The limits specified shall be reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation. The accompanying figures graphically nresent the " Limiting" column of Tables A 1, B 1, p-1, D 1 and E 1. = Page 7 of 32 ,e ,. m 6 er, y ,-m.,
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O PSEG NFf,f i November 25,1997 2.2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit specified in Figure 2-6 times the Kr curve value specified in Figure 2-7. The Kf curve requires an adiustment be made to the MCPR limit for bundle flows below 0.4 Mlb/ft'-hr. This adjustment has been incorporated in Fig. 2 7. The MCPR limit must be increased by 3% if the core inlet subcooling exceeds 70 BTU /lbm. The MCPR limit is a functio' of core average scram speed, EOC RPT operability, and Main Turbine Bypass operability. Core average scram speM, t (Tau), is defined by llope Creek Technical Specification 3.2.3., End-of-Cycle Recirculation Pump Trip system operability is defined per Hope Creek Technical Specification 3.3.4.2. Main Turbine Bypass operability is defined per Hope Creek Technical Specification 3.7.7. NOTE These operating limit values include a conservative penalty relative to GESTAR-II, NEDE.240ll-P-A to account for the potential effects of a condition being evaluated or pending resolution through the PSE&G Corrective Action Program. This is due to evaluations for Time Varying Axial Power Shapes. The evuluation of Fuel Spacer Band Flow T6s has been concluded without an LCO impact. These items were evaluated in References 7 and 8 and are described in DEF #DEH 93-00183 and PIRS item
- 97100810.5.
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f_ __ _ C _.._._i __ d._ -... _ I _ L __ _ - i___ _____.-._ __ _ _! i _ _. h_ _ _ _ B i i i i l l I 1.27 L-- -;l - - - - + - - --H- - - - -- L-------4------ l i ._._4- _..- _.. _ _ _ m _ _ _ _ _ _ ~ _ _ _.!____ __ l I I ) l l l j ] i OLMCPR Indudes: - d - --- -- -j 1.26 DEH 93-00183 Z Main Turbine Bypass Operable l } l o i i t _._-__7___ _7 7_ g I l l t i 9 I i i 1.25 g 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 "$Z l .o < m Tau (Scram Speed) _ g: $ c a C Cs v -aON 4 i t ' +
i i l I l O c y Toe ,a u i 's 1.40 M, l } l 4, I l l 1, 1 i t I I ( 1.35 -l( 25 131 )[ l 109% Flow Limiters 7 = E. 1 5 i .r a + 1 i I t t i i =t t i j l b~~ l- - 5 i I~'~~ I i-- 'g, 1,30 -t ,T i 1 ( f' I I i i l 1 t t ( i l i I i f-U l-l t-o 1.25 L-l --A i~- h -- ) e ) j i i g 1.20 1 t-- h - I m i t i i i j - 1.15 4 --- 4--L-1 + -t 1 o 2: -b-l( 40,1.19 )[- e 3 l I l l j j l i [ 52 1.10 t - 1-l - l j { m-j-+--j- --, L- -- = l l i I' 3 i u l T-4 i- - F i--j-I -4 t--i
- - - + - -
- w 1.05
- t i
i i i l i 1 1.00 L---4 {' l l l t t i I ' -r i, i I l J j l i ) i -h --+-- - I - - f- ;--{ ---{ ,---- j- - l( 82.5.1.00 )l ~ 0.95 I } } I i i l i l i i 0.90 20.00 30.00 40.00 50.00 60.00 70.00 80.00 90.00 100.00 Core Flow (% Rated) y O B X :e z on - @- 6 83 ~ ~ou 1 i
O PSEG "[;f,fooi November 25,1997 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINER,R IIEAT GENERATION RATE (IJiGR) shall not exceed the limits specified in Table 2-1. Table 2-1 LIIGR Limits Fuel Type LIIGR I imit (Kw/fn GE9B P8CWB324 9GZ180M 150-T 14,4 GE9B P8CWB32511GZ1-80M 150-T 14,4 GE9B P8CWB325-11GZ2 80M-150-T 14,4 GE9B P8CWB298 8GZ-80U-150 T 14.4 GE9B P8CWB327 8GZ1-80U 150-T 14.4 l l l l l Page 16 of 32
O PSEG l;f,1162 November 25,1997
3.0 REFERENCES
1. " General Electric Standard Application For Reactor Fuel", General Electric Company, NEDE 240ll P A, Revision 13, August,1996, and the U.S. Supplement, NEDE-24011 P A US, Revision 13. August,1996,. 2. Nuclear Fuel Section Vendor Technical Documen: NFVD GE 97003 00, " Supplemental Reload Licensing Report for llope Creek Generating Station Unit 1, Reload 7 / Cycle 8", General Electric Company,24A5392, Rev 0 September,1997. 3. Nuclear Fuel Section Vendor Technical Document NFU-VTDGE91040-00, " Supplemental Reload Licensing Submittal for llope Creek Generating Station Unit 1, Reload 3, Cycle 4", General Electric Company,23A6526AA, Rev.0, Supplement 1, January,1991. 4. Nuclear Fuel Section Vendor Technical Document NFU-VTDGE93477-00, " Lattice, Dependent MApLilGR Report for llope Creek Generating Station Unit 1 Reload 5, Cycle 6", General Electric Company,23A7219AA, Rev.0, November,1993. 5. Nuclear Fuel Section Vendor Technical Document NFVD-GE 97004-00, " Lattice-Dependent MAPLilGR Report for llope Creek Generating Station, Reload 7, Cycle 8", General Electric Ccmpany,23A5392AA, Rev.0, May 1997. 6. DEF # Deli 93-00183, ' Resolution of the TVAPS issue". 7. Nuclear Fnel Section Safety Evaluation llCT.8-0011, approved 10/30/97, 8. Nuclear Fuel Section Safety Evaluation llCT.8-0012, approved 11/14/97. 9. PIRS #971008105, " Fuel Spacer Band Flow Tabs". Page 17 of 32
ATTACHMENT 2 General Electric Affidavit l
n,. / s v GE Nuclear Energy P O bas 700 minungket Nc 20412 Affidavit I. Glen A. Watford, being ouly sworn, depose and state as follows: (1) I am Manager, Nucicar l'uel Engineering, General Electric Company ("GE") and have beca dele 6ated the function of reviewing the infonnation described in paragraph (2) which is sought to be withheld, and have been authorized to apply for itr. withholding. (2) The information sought to be withheld is contained in the document, lettice Dcpcndcnt MAPlJIGR Reportfor ihope Creek Generating Station. Reload 7, Cycle 8. GE Nuclear Energy Number 24 A5392AA, llevision 0, dated May 1997.
- 0) in making this ioptication for withholding of proprietary infonnation 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. $52(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NitC regulations 10 CFil 9.17(a)(4) and 2 790(a)(4) for " trade secrets and commercial or financial infonnation obtained from a person and prisileged or confidential" (Esemption 4) The material for which exemption from disclosure is here sought is all " confidential commercial information," and some portions also quahfy under the narrower definition of" trade secret," within the meanings assigned to those terms for purposes of FOI A Exemption 4 in, respectively, CriticallimEnergyftejectx SicleaLRegulatety_Commissiett 975F2d871 (DC Cir.1992), and INblic_Cilirv1Lilcaltli 1(cstarclLGIOUP111M,704F2dl280 (DC Cir.1983) (4) Some examples of categories of infinmation u ch fit into the definition of proprietary brormation are: a. Infonnation that discloses a pnicess, method, or apparatus, including supporting data and analyses, where presention of its use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other
- compames,
- b. Information which, if und by a competitor, would redu e his expenditute of resources or improse his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; c.
Infonnation which reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers; d. Infonnation which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric; c. Information which discloses patentab! subject matter for which it may be desirable to obtain "atent ptotection. Pagei
A p, ANIdavil 1hc infonnatmn sought to be withheld is comidered to be ptsprietary for the reasons set forth in both paragraphs (4)a. and (4)b., above. (5) 1hc infonaation sought to be withheld is being submitted to NRC in confidence.1he information is of a sort customanly 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 fbr maintenance of the infonnation 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 hmited on a "need to know" basis. (7) 1hc procedure fbr approval of esternal release of such a document typically requires review by the staff manager, project manager, principal scientist or othcr equivalent authority, by the manager of the cognirant marketing function (or his delegate), and by the legal Operation, for technicai 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 ihr the information, and then only in accordance with appropriate regulatory prosisions or proprietary agreements. (8) 1he infbnnation identified in paragraph (2) is classified as proprietary because it contains details of GE's fuel system analysis and the corresponding results which GE has applied to this specife core design with GE's fuel. The development of the methods used in these ana:ysis, along with the testing, development and approval of the supporting data was achieved at a significant cost, on the order of several million dollars, to GE. (9) Public disclosure of the infbnnation sought to be withheld is hkely to cause substantial hann to GE's competitive position and foreclose or reduce the availability of profit-making opportunities. 1he Ibel design is part of GE's comprehensise llWR safety and technology base, and its commercial value e% uds beyond the original development cost. The value of the technology base goes bey ond the cuensis e physical database and analytical methodology and includes development of the espertise to detennine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approsed methods. The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GE. l The precise value of the expertise to devisc an evaluation process and apply the correct analytical l methc.dology is diflicult to quantify, but it cicarly is substantial. l Page 2
l G.. I, Affodavit Gil's corupetitise adsantage will be lost if its competitors are able to use the results of the GE esperience to normalire or serify their own process or if they are able to clairn an equivalent understandmg by demonstrating that they can arris e at the same or similar conclusions. 'lhe value of this infonnation to Gl: would be lost if the information were disclosed to the public. hlaling such information asailable to compe'itors without their hasing been required to undertake a similar espenditure of resources would unfairly provide competitors with a windfall, and deprive Gli of the opportunity to esercise its competitive advantage to seek an adequate return on its large im estment in developing these s cry valuable analytical tools. State of North Carolina ) County of New llanos er ) Glen A Watford, being duly sworn, deposes and sa> s 'lhat he has read the foregoing aflidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief. thecuted at Wilmington, North Carolina, this _53 da.s of 9%.6 . id7 / A :/ 0 en A Y ord General Electric Company l l Subsenbed and sworn before me this J ' day of,_/[(u,,,(yv ,19 9 '/ H -v ?/f, </ns / Notary I'ublic, State of North Carohna hty Commission thpires /v/v//.200/ / / Page 3}}