Text

Proposed Tech Specs Using Two Demonstration Assemblies Which Contain Fuel Rods Whose Clad Compositions Fall Outside Specification Range of Zircaloy-4
	ML20073E981
Person / Time
Site:	Mcguire, McGuire
Issue date:	04/18/1991
From:	; DUKE POWER CO.
To:	;
Shared Package
ML19302E548	List: ML20073E974; ML20073E981;
References
	NUDOCS 9105010180
	Download: ML20073E981 (18)
	v • d • e

_ _ . .

Attachment I Eronosed Technical Suecification Chance 9105010180 910418 PDR ADOCK 05000369 P PDR r

DESIGN FEATURES 5.2.1.2 REACTOR BUILDING

a. Nominal annular space = 5 feet,

b. Annulus nominal volume = 427,000 cubic feet,

c. Nominal outside height (measured from top of foundation base to the top of the dome) = 177 feet.

d. Nominal inside diameter = 125 feet,

e. Cylinder wall minimum thickness = 3 feet,

f. Dome minimum thickness = 2.25 feet,

g. Dome inside radius = 87 feet.

DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment is designed and shall be maintained for a maximum internal pressure of 15.0 psig and a temperature of 250*F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly 5 nominallycontaining264fuelrodscladwithZircaloy-4?exceptthatsubstitu-tions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, (

or by vacancies, may be made in fuel assemblies if justified by cycle-specific {e reload analyses using NRC-approved methodology. Should more than 30 rods in the core, or 10 rods in any assembly, be replaced per refueling, a special report (

describing the number of rods replaced will be submitted to the Commission (

pursuant to Specification E.9.2 within 30 days af ter cycle startup. Each fuel p rod shall have a nominal active fuel length of 144 inches. Reload fuel shall a be similar in physical design to tha initial core loading and shall have a maximum enrichment of 4.0 weight percent U-235. x

)

CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. The full-length control rod assemblies snall contain a nominal 142 inches of absorber material. The nominal values of absorber material for Unit 1 control rods shall be 80% silver, 15% indium, and 5% cadmium. The nominal values v7 absorber material for Unit 2 control rods shall be 100%

boron carb He (S4C) for 102 inches and 80% silver, 15% indium, and 5% cadmium for the 40-inch tip. All control rods shall be clad with stainless steel gs Unfr 1 um. SE 'WO O*##

U) '

lf '

mm8l.lFs Gjiu. coaThit) > b fue< Bohs EACH UHICH MG Kab WITH A pg 2 RCo utur & D M O W W > N Amendment No. 85(Unit 1)

McGUIRE - UNITS 1 and 2 5-6 Amendment No. 66 (Unit 2)

Attachment II Justification and Safety Analysis Introductioq In the upcoming fuel cycle (Cycle 8) at McGuire Unit 1, Duke plans to insert two demonstration fuel assemblies to test a variety of advanced fuel rod cladding materials and fuel pellet designs.

These fuel assemblies will be manufactured by B&W Fuel Company (BWFC), the supplier of the remainder of the reload fuel batch.

The test assemblies will be irradiated for three fuel cycles, to demonstrate the performance of the advanced clad material with respect to corrosion, creep, and growth.

Technical Specifications currently require (see specification 5.3.1) that fuel rods be clad with Zircaloy-4. Some of the fuel rods being considered for this demonstration project contain claddings whose compositions are outside the specification ranges of Zircaloy-4. Therefore, this Tecb."ical Specification (TS) change is needed to permit use of these asse.?blies at McGuire.

The two demonstration fuel assemblies will contain a maximum of 104 advanced-clad fuel rods, all located around the periphery of the two assemblies to permit inspection. A variety of cladding materials and fuel pellets will be used. A detailed description of the clad compositions, fuel pellet designs, and pellet / clad combinations can be found in the BWFC report which describes the advanced cladding demonstration program (see Attachment V). A summary description of the various clad types and pellet designs appears below in the safety analysis portion of this attachment.

lystification In order to achieve higher fuel burnups without increasing the risk of fuel failure, analyses and tests are conducted to explore various options in fuel assembly design and materials. Duke has participated in three previous BWFC test programs, at both Oconee and McGuire. Valuable information has been obtained through each of these programs. The proposed program is expected to add significantly to the base of knowledge of how various clad materials react under in-reactor conditions.

The cladding compositions being considered for this demonstration have been chosen based on ex-core testing, theory, and previous irradiation programs. Each of the rods to be tested is expected to perform at least as well as the current fuel design. It is anticipated that the best-performing clad composition will become qualified for future use in fuel reloads.

The non-Zircaloy-4 clad types being considered in the demonstration have been tested for corrosion resistance, tensile and burst strength, and creep characteristics. Details concerning the test

programs that have been performed in support of this demonstration can be found in the attached BWFC report.

Safety Analysis The safety significance of this change is considered minimal. The number of fuel rods involved is very small in comparison to the total core inventory. Failure of all of the advanced cladding fuel rods from a cause related to the demonstration would constitute significantly less than the 1% fuel failure postulated in FSAR Chapter 15 safety analyses. Failure of the fuel as a result of some unrelated phenomenon would not result in greater inventory release than non-demonstration fuel.

There are three groups of claddings being considered for this demonstration program: type B, type - N, and type F. Each type represents a different strategy for obtaining better performance at higher burnups. Within each type, relatively minor variations in

-composition are present, to create a total of twelve different advanced claddings. The type B claddings are slight variations of the current cladding used by BWFC, and all are within the Zircaloy-4 specification range. The two of the type N claddings are l within the Zirc-4 range and two are just outside. The type F claddings are further from the Zirc-4 range.

Five different pellet types will be used in the demonstration program. The pellet types NP1, NP2, and NP3 are intended to display'a range of densification characteristics. These pellets will be used in type N claddings. Pellet type FP1 will be used in clad type F. The remaining pellets are standard BWFC-specification pellets. The dimensions of the type F clad correspond to the dimensions of the type FP1 pellet. The dimensions of the remaining pellets and clads correspond to the balance of the BWFC reload batch.

The demonstration assemblies meet the same design bases as the fuel L which is currently in the reactor. No safety limits have been changed or setpoints altered as a result of the use of these assemblies. The FSAR analyses are bounding for the demonstration assemblies as well as the remainder of the core.

l The demonstration assemblies will be placed in core locations which

! will allow them to accumulate approximately 45 to 50 GWD/MTU during three cycles of exposure. The assemblies will be placed in core locations which will not experience limiting power peaking in any

-cycle.

Figure 1 shows the reload core map for McGuire Unit 1 Cycle i 8, with the demonstration assembly locations identified. Figures

! 2 and 3 show power distributions at beginning and end of cycle, which show that the assembly and pin powers for the demonstration l assemblies will not be limiting. These figures were taken from the

! final fuel cycle design report for M1C8. They will also ne l included in the reload submittal which will be submitted for NRC approval in early June, 1991, 1

t Following each cycle, the demonstration assemblies will undergo a post-irradiation examination (PIE) . The PIE will be conducted in the spent fuel pool, using a portable PIE rig. The examination will consider the visual and physical characteristics of the assemblies. The data will be' used for more explicit modeling, as well as to compare the various advanced clad types.

Conclusion It is concluded that the Unit can operate safely with the demonstration program in place. The advanced zirconium-based alloys have been shown through testing to perform satisfactorily under conditions representative of a reactor environment. In addition, the relatively small number of fuel rods involved does nct represent a prohibitively large inventory of radioactive material which could be released into the reactor coolant in the event of fuel failure, i

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Notti Full core locattoo H 8 tefere l YT l REC 10W NW381 to cycle 6 location.

I 1 22 I. CYCLE 7 LOCATIOM3 DEMoMST RNTIO N A SS Y LocA7/oNS - N.g c-/2

t M1008 RADIAL POWER DISTRIBUTION HFP, EQXE, 004 EFPD TRF ON, ARO, 1160 PPMB hh JOBID/CASEID = ACAV/DPLOO4012A DATE RUN = 03JUL90 D C B A G F E H ****************************

- - - - 343

.8339

1.1235

1.0658

1.2005

1.1505

1.2

1.0078 * .8392

8* .8768

1.2809

1.1332

1.3365

1.2221

1.3566 1.1188

1.1239 *

1.1102

1.0515

1.1401 ** 1.0632 ** 1.1133 ** 1.0623 P I N L

- D M

C M ** 1.3391 1.0991 CM

K P

QQ CM *******************

- - - - 1.1996

1.1300 * .9993

1.2010

1.0324

1.2325

1.0595 *

.6523 *

.9041

9* 1.2823

1.1030

1.3320

1.1221

1.3743

1.1553

1.3420 *

1.1348 ** 1.1038 ** 1.1090 ** 1.0868 ** 1.1150 ** 1.0904 C E

- 1.1188B I ** 1.3862 B L **

QQ MN QQ E O QA *******************

- - - - 1.0372

1.0713

1.2055

1.1546

1.1626

1.1054

1.2283

1.1882

1.1105

.7977

10* 1.1321

1.3370

1.2546

1.2779

1.2174

1.3596 *

1.0567

1.1091 ** 1.0866 ** 1.0992 ** 1.1014 R E

- 1.1069A ,Q

- 1.1456 D E ** 1.3921 C E **

QQ E D D E

M C *******************

f

- - - - 1.1133

1.2054

1.0355

1.1644

1.1286

1.2202

1.1210 *

.4528 *

.8057

11* 1.3410

1.1250

1.2811

1.2212

1.3585

1.2446

1.3261 *

1.1125

1.0864

1.1002

1.0820** 1.1134 ** 1.1103 ** 1.1911 C H

- 1.7793 A A

O E

E D

H N Q A E D

I P **********************

.6374

1.1263

1.1506

1.2324

1.1050

1.2183

1.0107 ' 1.3106 ' " .9967

12* 1.2168

1.3717

1.2159

1.3559

1.0724 " 1.5638 *

1.0575

1.1131 ** 1.1004 ** 1.1129 * *1.0610 1.1636 A A *

L N

A Q E N AQ N E

' A-A ' j l******** * * *

- - - - 4 -

.3439 *

1.2315

1.0566

1.2255

1.1175

1.1237 * .6990 .9348 *

.6816

13* 1.3532

1.1525

1.3569

1.2412

1.3099 *

1.0989

1.0908 ** 1.1073 ** 1.1108 ** 1.1657 A A

- 1.3374A A ** 1.9824 A A **

MD

E C Q A D E ******

- - - - (AVG)

1.0050

1.1959

1.0339

1.1102 * .6362 * .3439

P 14

1.1233

1.3384

1.1841

1.3223 * .9942 * .6818

PEAK PIN

1.1177

1.1191 * *1.1454

1.1911 *

1.5625

A A

1.9826

A A

PEAK

PIN/ LOCASS

MC

I B E D H C

=m**********************************************************

.8355 * .6496 * .7951 * .4514

15* 1.1186 * .9006

1.1068 * .8032 *

1.3389

1.3864 ** 1.3921 *w 1.7795 **

MC

L D E C A A

- *** e m e e e e ;. * ** *** **** ** ** *** *** * ***** ** ***

The maximum assembly power is 1.2343 at locatior. C-8.

The mar.imum pin power is 1.3743 at location D-9.

The maximum pin to assembly factor is 1.9826 at location C-14.

l l

M1008 RADIAL POWER DISTRIBUTION HFP, tQXE, 350 EFPD -""'

THF ON, ARO, 100 PPMB JOBID/CASEID = AGAV/DPL350370A DATE RUN = 03JUL90 H G F E D C B A

1.0043

1.3204

1.1231

1.2929

1.0892

1.1071 * .9336 * .8091

8* 1.0298

1.3794

1.1836

1.3538

1.1351

1.2054

1.0084

1.0525 *

1.0255

1.0447

1.3539

1.0472

1.0421

1.0888

1.0801

1.3008 *

L M

Q I

D L

A I

D L

A I

B L

A I *

- - - - +********************************

1.3231

1.0871

1.3047

1.0322

1.2o05

1.0043

1.1428 * .6534

9* 1.3809

1.1398

1.3745

1.0713

1.3206

1.0865

1.2475 * .8589 *

1.0437

1.0484

1.0534

1.0379

1.0477

1.0819

1.0916

1.3145

I Q

MN

A A

E O

A A

C H

AQ

B L *

- - - - (**********************************************************************************

1.1249

1.3066

1.0916

1.0763

1.0608

1.2496 * .9736 * .7829

10* 1.1802

1.3754

1.1821

1.1485

1.1387

1.3139

1.0823

1.0499 *

1.0491

1.0527

1.0829

1.0671

1.0734

1.0514

1.1116

1.3410 *

A A

E D

A A

N E * * *

.L D A Q

D E A A

*: . ;. ;. . :. :. ;. *** ** ** * * ** *w** * ** * * * *++ * * ** * *** * ** s * * ** ** ** ** * ** * ***** :. ;. ;. ;. ;. ;. :. ;. a a ;. a a ************

1.2948

1.0335

1.0771 + 1.0534

1.2554

1.0628

1.0618 * .4817

11* 1.3560

1.0725

1.1499

1.1247

1.3136

1.1482

1.2409 * .7652 *

1.0472

1.0378

1.0675

1.0676

1.0463

1.0804

1.1688

1.5886 *

I A

U E *

MN

A A

- - - - +**;.a.:.;;.;.e**************************************-

QA

D E

A A

A A *

.i..t...et.**************

l

1.0896

1.2607

1.0612

1.2551

1.0065 ' I 1.1459 I r .6806

12* 1.1418

1.3217

1.1386

1.3134

1.0453 '

1.2795 "

.9442 *

1.0479

1.0484

1.0730

1.0465

1.0386 i

- 1.1166 ' ' 1.3873

L D A A

E N

AQ

N E '

g A A ;j A A *

- - - .At.;.e;*********************************************, ---_. .

e;;;e******

l

1.1067

1.0036

1.2495

1.0622

1.1455 * .7676 * .4267

13* 1.2047

1.0858

1.3138

1.1478

1.2790 * .9464 * .7526 * -

1.0885

1.0819

1.0515

1.0805

1.1166

1.2329

1.7635 *

I A

MC

Q A

E D

A A

C E

A A *

.9336

1.1426 * .9733

1.0618 * .6809 * .4271

P (AVG) 14* 1.0119

1.2473

1.0817

1.2409 * .9443 * .7531

PEAK PIN

1.0839 **1.0916 * *1.1114

1.1687

1.3868

1.7635

PEAK / ASS

L B Q A E D

A A

A A

A A

PIN LOC

- - - - w-e++********

.8086 * .6530 * .7829 * .4817

1 15* 1.0518 * .8584

1.0498 * .7652 *

1.3008

1.3145 *. 1.3409

1.5887 *

I A

L. B

A- A

A A *

.;.e;..

.;.************************************

l

.The maximum assembly power is 1.3231 at location H-9.

The maximum pin power is 1.3809 at location H-9.

The maximum pin to assembly factor is 1.7635 at location B-13.

I

-Attachment III Sionificant Hazards Analysis The-fOllowing analysis, required by 10 CFR 50.91,.is provided to justify the determination that the proposed Technical Specification change will not create a Significant Hazards Consideration (SHC).

The criteria of 10 CFR 50.92 are applied to the proposed change to support that determination.

i 1)- The proposed change-will not involve a significant increase l -the probability or consequences of any accident previously-evaluated in the FSAR.

The test assemblies with the zirconium-based claddings are mechanically and thermal-hydraulically similar to- the remainder of the reload batch and the rest of the core, so no failure probability is increased, nor is any operational

-practice changed which could introduce a new initiator'of an accident. - The only credible event which could occur as a L result of this demonstration is clad failure of the test fuel rods. The number of fuel rods involved is such a small percentage of -the core inventory that even a postulated failure of all the demonstration fuel rods from a ' cause related to the - demonstration would not result in - dose consequences greater than existing limits. A failure of the fuel rods from a cause not related to the demonstration would L not result 1n consequences greater than those which would have 1

occurred had the assemblies not been demonstration assemblies.

2)- The proposed change will not create the possibility of a new accident not previously evaluated.

The mechanical and_ thermal-hydraulic similarity of the test assemblies to- the remainder of assemblies in the core

-precludes the credible possibility of creating any new failure

mode or accident sequence. The use of - . the demonstration l- assemblies does _not involve any alterations to plant equipment

-or procedures which would introduce - any new - or unique operational = modes'or accident precursors 3)L :The proposed change- will not involve a significant decrease in a margin of safety.

The demonstration-' assemblies meet the same design bases as the remainder of assemblies in the core.

m Existing reload' design and safety ' analysis limits are maintained, and the' FSAR analyses are bounding. No_special setpoints or other safety-settings are required as a result of the use of these two test assemblics. The assemblies will be placed in locations which will not-experience limiting peak power conditions, l-

.~ - - . _ . _ . . -.

Conclusion The proposed change has been- shown in the accompanying Justification and Safety Arialysis (see Attachment II)- to be transparent in terms of the operation of the plant. No new operational or safety considerations will be created, and no procedures or practices will be changed. The demonstration assemblies will be mechanically, neutronically, and thermal-hydraulically similar to the rest of the assemblies in the reload batch and the remainder of the core.

Based upon the above analysis, it is concluded that the proposed change will not involve a Significant Hazards Consideration.

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I Attachment IV Acolication for Exemotion From Recuirement of 10 CFR 50.46 That Fuel Claddina Must Be Zircaloy Introduction

~ The Code of Foderal- Regulations, 10 CFR 50.46, contains requirements for Emergency Core Cooling Systems (ECCS) at light- l

.w ater nuclear power plants. Part 50. 46 (a) (1) (i) specifies that l reactor-fuel will consist of uranium oxide pellets enclosed in l Zircaloy tubes. It does_not define what is considered "Z3rcaloy".

Therefore, it is not clear - whether the deviations from the !

composition specifications of Zircaloy-4 of some of the fuel rods l in the proposed demonstration program are within the regulatory basis of the "Zircaloy" specified in 50.4 6. In the absence of regulatory guidance on the definition of "Zircaloy" as used in 1 50.46,- Duke Power requests that an exemption be granted to permit i the use of those fuel rods whose compositions are outside the range of Zircaloy-4. !

The criteria of 10 CFR 50.12 are addressed below to justify this exemption,- to demonstrate the special circumstances which are '

required to be present for the granting of an exemption.

Soecial Circumstances From 10 CFR 50.12:

"Special circumstances are present whenever -

(ii)-Application of the regulation in the particular circumstances would: not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule." (Emphasis added)-.

The-underlying purpose of 10 CFR 50.46 is to establish' requirements for ECC systems. . The specification of Zircaloy as the clad

" material is an explicit assumption which does not have a defined basis in the regulation. Nevertheless, the purpose of the rule, the implementacion of ECCS, has been accomplished.

~Imoact on the Environment The will be no perceptible impact on the environment as a result of this' exemption. No operational or safety considerations are

-introduced by this. change. The advanced claddings are expected to perform at least as well as the cladding currently- in use. The only credible consequence of this-- change would be a failure of the demonstration' claddings. Even in the case of gross fuel' failure, the number of rods _ involved (a ' maximum of 104 rods will use advanced clad compositions) is sufficiently small that

, environmental impact would be minimal, and is bounded by previous assessments.

, s Redress of Adverse Environmental Imoact As noted above, the potential for' adverse environmental impact is minimal. Nevertheless, fuel failure is recognized as a possibility, and has been considered in plant analyses and design.

The capability to deal with fuel failure has been demonstrated in the past, and the proposed change will not result in any environmental impact which could not be redressed.

Foreclosure of Subsequent Alternativos Implementation - of the proposed change will not foreclose the implementation of any subsequent alternatives. The only ,

alternative to be considered would be to forgo the demonstration l program and revert to using standard claddings. This alternative l remains available in the event the demonstration program does not ;

result in improved fuel rod performance. '

Effect of Delav There is not a quantifiable effect of delaying the demonstration program. Long range benefits may be expected from this program in terms of reduced incidence of fuel failure, longer operating cycles, and higher fuel burnups.

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(' '4 l- Attschment V

l. BWFC Demonstration Procram Descrintion

.{$AW-2133P) i l

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y v s'

l AFFIDAVIT OF JAMES H. TAYLoB L

i-A. My1name is James H. Taylor. I am Manager of Licensing Services-in the B&W Nuclear Services Company (BWNS), which is a part of B&W Nuclear Technologies (BWNT). The B&W Fuel Company is

' administrative 1y responsible to B&W Nuclear Technologies and utilitzes.the.BWNS Licensing _ Services. Therefore I am authorized to execute this Affidavit.

B. IJam familiar with the criteria applied by B&W to determine whether certain-information of B&W is proprietary and I am

-familiar with the. procedures established within-B&W,

.particularlyfthe Nuclear Services Company, to ensure the proper application of these criteria.

C. In determining whether a B&W document is to be classified as

. proprietary information,.an' initial. determination is made by the Unit Manager, who is. responsible-for originating the document, '

as to whether it falls within the criteria set forth in

Para' graph:D-hereof'. If the :Information falls within any one of these criteria,_it-is classified as-proprietary by the

!= originating Unit Manager. _This initial' determination isi

.reviewealby the-cognizant Section-Manager. LIf the. document.is designated as-proprietary, it'is reviewed again by' Licensing-personnel and other management within-BWNS as designated by.the Manager of Licensing Services to assure that the regulatory requirements of 10-CFR Section 2.790 are met.

D.- The~following;information is provided'to demonstrate that the f

-provisions of-10-CFR Section 2.790 of the Commission's regulations have been considered:

, (1)- The information'has been= held in confidence by B&W..

~

Copies of_theodocument are clearly. identified as

. proprietary. ~In addition, whenever B&W transmits the y;

i -1 t . . .S .

AFFIDAVIT OF JAMES H._ TAYLOR (Cont'd.)

information to a customer, customer's agent, potential customer or regulatory agency, the transmittal requests the recipient to hold the information as proprietary.

Also, in order to strftetly limit any potential or actual customer's use of proprietary information, the following provision is included in all proposals submitted by B&W, and'an applicable version of the proprietary provision is included in all of B&W's contracts:

" Purchaser may retain Company's proposal for use in connection with any contract resulting therefrom, and, for that purpose, make such copies thereof as may be necessary. Any proprietary information-concerning Company's or its Supplier's products or manufacturing processes which is so designated by Company or its Suppliers and disclosed to Purchaser incident to the performance of such contract shall remain the property of Company or its Suppliers and is disclosed in confidence, and Purchaser shall not publish or otherwise disclose it to others without the written approval of Company, and no rights, implied or otherwise, are granted to produce or have produced any products or to practice or cause to be practiced any manufacturing processes covered thereby.

Notwithstanding the above, Purchaser may provide the NRC or any other regulatory agency with any such proprietary information as the NRC or such other i

l agency may require; provided, hcwever, that Purchaser shall first give Company written notice of such proposed disclosure and Company shall have the right to amend such proprietary information so as to l make it non-proprietary. In the event that Company cannot amend such proprietary information, Purchaser 2

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a .c AFFIDAVIT ~OF JAMES H. TAYLOR (Cont'd.)

shall, prihr to disclosing such information, use its best efforts to obtain a commitment from NRC or such other agency to have-such information withheld from public inspection.

Company shall be given the right to participate _in pursuit of such confidential treatment."

( ii ) -- The-following criteria are customarily applied by B&W in a rational decision process to determine whether1the information should be classified as proprietary.

i Information may be classified as proprietary if one or more of the following criteria are met:

a. Information reveals cost or price information, commercial strategies, production capabilities, or budget levels of B&W, its customers or suppliers.

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b. The information reveals data or material concerning B&W research or development plans or programs of present or potential competitive advantage to B&W.

c. The use of.the-information by a competitor would decrease his expenditures, in time or resources,11n designing, producing or marketing a, siner product.

d.- The information consists of test-dataaor other similar data concerning a process, method _or component, the application of wh'ich results in a p competitive advantage to1 Babcock &-Wi-1cox.

$ e. -The information reveals special aspects of-a process,_ method, component or the like, the exclusive use of'which results in a competitive o

L advantage to Babcock & Wilcox.

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, 4 AFFIDAVIT'OFJJAMES H. ~\YLQB (Cont'd.) !

f.- The-intormation contains ideas for which patent protection may be sought.

The_ document (s) listed on Exhibit "A", which is attached

-hereto-and made a part hereof, has been evaluated in accordance with normal B&W procedures with respect to classification and-has been found to contain information which falls within one or more of the criteria enumerated above. Exhibit "B", which is attached hereto and'made a part hereof, specifically identifies the criteria applicable to the document (s) listed in Exhibit "A".

(iii) _ The document (s) listed in Exhibit "A", which has been made available to the United States Nuclear Regulatory Commission was made available in confidence with a request _that the document (s) and the information i

conta'ned i therein be withhold:from public disclosure.

(iv) The-information is not available in the open literature p and to_the best of'our knowledge-is not known by; Combustion Engineering, EXXON, General-Electric,

-Westinghouse or-other current _or potential domestic or foreign. competitors'of B&W.

(v)- Specific information with regard to whether-public disclosure of the information is likely to cause harm to L -the competitive position of B&W, taking into account the

] tvalue of the information-to B&W; the amount of effort or xmoney expended.by B&W developing the information; and the ease or dif ficulty: with which' the' information could be properly duplicated by others-is given in Exhibit "B".

E.: I=have personally reviewed the document (s) listed on-Exhibit "A" and have found that it is considered proprietary by B&W because it contains information which falls within one or more of the 4

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Mf_$AVIT' OF-- JAMES H. - TAYLOR (Cont'd.)

criteria enumerated in Paragraph-D, and it is information which is customarily' held in confidence and protected as proprietary information by B&W. This report comprises information utilized by B&W in its business which afford B&W.an opportunity to obtain a competitive advantage over those who may wish to know or use the information contained in the document (s).

J AU /ft2 JAMESH.TAYLO[

State of Virginia)

) SS. Lynchburg City of LynchEtrg)

' James H. Taylor,-being duly sworn, on^his oath deposes _and says-that hefis the person who' subscribed his name to the foregoing

-statement,-and that the matters.and facts set forth in-the' statement

.are true..

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[ JAMES-H.TAYLk Subscribgd and sworn before'me this /df/2 day of. <24md ~

7 1991..

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L).- / chtd )

eV AfGC.

Notarypu'bficinandfortheCity of. Lyn dburg, State of Virginia.

g .My' Commission Expires

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ML20073E981

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