ML20085A887

Forwards Draft Rev 0 to Procedure NPG-0151-81G, Objectives & Responsibilities - Plant Design Section. Statement for Section I & App E Requested.Response Requested by 770810

ML20085A887
Person / Time
Site:	Crane
Issue date:	07/22/1977
From:	Frederick Sullivan BABCOCK & WILCOX CO.
To:	Roy D BABCOCK & WILCOX CO.
References
TASK-*, TASK-GB 790722, GPU-0460, GPU-460, NUDOCS 8307070373
Download: ML20085A887 (19)

Text

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THE BABC0CK & WILCCX COMPANI j-POWEP GENERATION GROUP To l

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DRAFT NPG-0151-81C i,,...............----.

Attached is a draf t copy of NPG-01.51-81G, " objectives and 14sponsib(1 Plant Design Section** for your review and concurrence prior to su'oalttal to.f.C. Deddens for approval.

Please note that there is no statement under Sectica I - Objective or I am regnestir.g you enter nadar the General section of Appendix E.

a statemnt for each.

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RATivE MANUAL i

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NPC-Cl31-41C (Rev 0)

SUQJECT SECTICH O5JECTIVES AND TiISPONSIBILTTIES-f 01CANIZATION, RISPONSIBILITIES PLANT DESIGN SECTION AND RELATIONSHIPS

' I.

01JECTIVES DRA q i

i CONFIDENTIAL II. 3ISP055151LITIES LOUN FI T

If3 c*u entor f"- ~ =ssociated systems ana Perform the functional design = d

.e preparation of specificatioFl/ B & V-h coolant and secondary systems; t supplied sy' stems and component. rem -

- a,u M o n s and f5teTf2Cof balance-of-formation; the review of bid specifications; plant criteria, and of proposal 4"

. stem, plant and NPCD engineering activi. ties the integration of mechanical, syv - M h (33R) contracts.

supporting Babcock-Brown-3cveri U--

A.

STNCARDS ito determine reactor coolant sy' stem flow 1.

Perform analyses requir*A-d ylenent related vessel model flow tests.

distributim Plan and 1-w dard system and component requirement speci-2.

Prepare and maintain st- - -- -

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fications for the scope-ci

--f-supply defined in the Vork Breakdown Structure (VES).

3.

Prepare and nain'tain s Aard system descriptions of the reactor coolant and secondary systems -

- -d the balance-of plant criteria documents.

ed system design descriptions and component d

4.

Raview and approve stan -

compliance with requirement ssiecifications design reports to assur ~

and applicable state anA ~

+ 1ederal regulations and guides.

Iaviewaddappro<aplan:

design changes affecting the Plant Parameter

.c requirement specifications, and the RCS/

5.

List, systes and compon--

Standard System design da vscriptions.

6.

Establish and implemeat -

-pproved results engineering programs utilizing data from operating p'=~

ts.

t Prepare engineering st -

-.Aards and procedures.

l 7.

l Development in establishing future product f

8.

Participate with Produc-e trends and market requi-

-esents.

Recorssend MD programs 1 leading to changes in the standard product.

9.

Mainister approved *'-

funded proge'sms.

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.P01.lCIES AND PROCEDURES NPG-0151--81c a.

T' II.

RESPONSIBII.ITIES (Cont'd)

'A.

STANDARDS. (cont'd)

Prepare standard Safety Aaaiysis Report (SAR) material and support i

10.

standard licensing effort.

B.

DOMESTIC CONTRACTS l*

Provide analyses required to establish perfor=.ance and functional 1

design criteria for reactor control pressurizer and pressurizer 1.

control, steas generator control, custooer feedwater and steam systems and Integrated Control System.

I Establish heatup, cooldown, and operational characteriscies of the 2.

l Provide input for rehted auxiliary system design.

NSS.'

Provide analyses requi' red to establish perfornance criteria and 3.

functional requ,izements for the reactor coolant system and steam i

plant system.

Prepara and maintain contract system and co=ponent requirement 4.

specifications for the scope-of-supply defined in the W.S.

Prepare and maintain contract syste.s descriptions'of the reactor 5.

coolant and secondary systems and the balance-of-plant criteria document.

Review and approve contract systen design descriptions and component

6. ' design reports to assure compliance with requirenant specifications I

and applicable state and federal regulations and guides.

a Betermine the dynamic and stati loadings imposed on components and 7.

supports of the, reactor coolant syste'.

8.

Prepare engineering manhour and computer hour estinates in support of proposal and contract engineering work.

Ptsvide engineering support of marketing and sales efforts as required 9.

by Marketing Departme.nt and Product Developnent Section.

Evaluate potential or postulated transient and accident conditions 10.

l to determine that system response and consequences are within accept-t able limits.

i

11. Prepare SAA material. Assist in presentation and defense of applicable SAR material as required by Licensing Section.

Perform analyses required to establish performance and functional 12.

criteria for all systems or equipnent intended to prevent, citigste, and/or terminate postulated accident conditions.

Perfore analyses required to establish perfor ance and functional 13.

criteria for radioactive vaste handling systens.

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I NPC--0151 R1 C RESPohSIBILITIES_(cont'd)

II.

DOMESTIC CONTP. ACTS (cont'd) i B.

Establish reactor building and sub--compartuent design criteria.

14.

Manage the applicable VBS tasks to perform in accordance with NSS 13.

Contract requirements.

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Develop and maintain VFD/WA's and TCN's f or tasks assigned.

i 16.

j Support other VBS tasks as defined la the Work Package Descriptions.

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17.

C.

BBR CONTP. ACTS Coordinate, schedule, integrate, expedite, and approve Engineering d

Department activities and inforu.ation flow between BLW and BBR, an 1.

between internal B&V engineering units for BBR related activities.

n This function applies to Design Overview Program (DOP), MasterConsulting Ac

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Service, Licensing Agreenent, or negotiated with International Engineering activities as directed Program Management (liot).

Review, se:erate, or cause to be generated, DOP connents on BBR i

systems, components, or procedures as described in 3BR docunentat on.

2.

.j Initiate, fetculate, and recocaend tean members for Special Purpose Reviews (SPR's) for systens, components, and problen areas.

3.

Perform integration and review activities to assure technical adequacy, accuracy and completeness of Engineering Departnent

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technical information subnitted to BBR.

l Provide task descriptions to IPM with resource estimates and schedu es i

or Consulting Work.-

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to define DOP, M. aster Service, License Agreement, Prepare and maintain cot e analytical input requirenents documentation.

i 6.

Prepare or cause to be prepared contract docu' mentation in accord with e

o provide BER with timely, 7.

Engineering Department procedures er des'gn changes that directly documented, B&*.I initiated designs af fect the BBR design.

-END-1 l

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e RESPONSIBILITIES _(caat'd)

II.

DOMESTIC CO!iT7 ACTS (cont'd)

B.

Establish reactor building and sub--compa-tnent design criteria.

14.

Fanage the applicable k'BS tasks to perform in accordance with NSS 13.

Contract requirements.

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Develop and maintain k'PD/WA's and TCN's for tasks assigned.

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16.

N Support other k'BS tasks as defined in the Work Package Descriptions.

I 17.

C.

BBR COrfRACTS Coordinate, schedule, integrate, expedire, and approve Engineering Department activities and information ficrs between BLV and SBR, and 1.

between internal B&V engineering units for BBR related activities.

l This function applies to Design Overview Progran (DOP), Master Consulting Activities, and other

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Service, Licensing Agreement, Engineering activities as directed or negotiated with International Program Management (IPM).

Keview, generate, or cause to be enerated, DOP cocnents on B3R systens, components, or procedures as described in 3BR docunentation.

2.

forculate, and recossend tean members for Special Purpose

Initiate, Reviews (SPR's) for systems, conponents, an.i problen areas.

3.

Perform integration and rc e few activities to assure technical adequacy, accuracy and completeness of Engineering Department

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4.

technical information subniited to BBK.

Provide task descriptions to IPM with resource estisates and schedules Work.

to define DCP, Master Service, License Agree.nent, or Consulting 3.

Prepare and maintain core analytical input requirements docu=entation.

6.

Prepare or cause to be prepared contract docuhentation in accord with procedures o provide BLR with timely, 7.

docunected, B&*.T initiated designs se des'gn changes that directly Engineering Depart =ent affect the BBR design.

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RESPONSIBILITIES (cont'd) s DOMESTIC Co m ACTS (cont'd) t 3.

Establish reactor building and sub-compartnent design criteria.

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&nage the applicable WBS tasks to perform in accordance with NSS

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Contra.:t requirements.

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Develop and asiatain WPD/WA's and TCN's for tasks assigned.

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Support other WBS Casks as defined in the Work Package Descriptions.

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BBR CONTRACTS _

Coordinate, schedule, integrate, expedite, and approve Ecgineering l

Department activities and information ficra between BLW and SBR, and 1.

l between internal B&V engineering units for BBR related activities.

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f This function applies to Design Overview Program (DOP), hster Consulting Activities, and other i

l Service, Licensing Agreement, or negotiated with International Engineering activities as directed Program Management (IPM).

Review, generate, or cause to be generated, DOP connents on BBR systems, components, or procedures as described in 35R docu=entation.

2.

l' Initiate, formulate, and reco;= send team members for Special Purpose d problen areas.

3.. Reviews (SPR's) for systems, components, an r

Perform integration and review activities to assure technical adequacy, accuracy aod completeness of Engineering Department

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4 technical information subnitted to BBE.

I Provide task descriptions tc I?M with resource estimates and schedules or Consulting Work.-

5.

to define DOP, Master Service, License Agreement, requirenants documentation.

Prepare and maintais core analytical input 1

6.

Prepare or cause to be prepared contract docu' mentation in accord with Engineering Department procedures *o provide BT,R with tinely,se des' 7.

documented. B&W initiated designs af fect the BSR design.

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At*41 N I S TR ATI Y C MMU Al.,

POLICIES AND PROCEDURES Iw ata 3

NPC-0151-A10 f

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APPENDIX A FLANT INTECRATIM UNIT DRAFT I.

CENERAL he Plant Integration Unit is responsible for achieving a unity of effort among tnis is acco major functional specialists in the NPCD Engineering Depart =ent.

by assuring an accurate. consistent and timely ilov of information fro:a

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requirements a'nd analytical inputs to the delivery of high quality equipoent.

-l His duty is carried out through the definition of technical system requirements the design and equipment for the Nuclear Steam System and the assurance that consititute the product are in conformance with established codes v.hich regulations and requirenents. leads to a primary role in the solution of critica assessnent of the, need for product change.

1.

STANDARDS AND CCNTPJLCTS-A.

Design lead for the Nuclear Steas Supply and S 1.

nis includes definition of requirements subsystems and components.

d and contract and issuance and maintenance of corresponding standar documents.

Identify and coordinate the analysis vork tequire'd to define both 2.

Plant Level and System / Component Requiremerts.

3., Review and approve system design descriptioes and cocponent and specifications for compliance with functional require.ments.

Coordinate the overall resolution of critical product problems.

4.

l Approve design chanses involving the NSS/xsc components or systems.

I 5.

i Review, approve and prepare selected pottions of the SAR.

i e

l 6.

Chair and participate in formal design reviews of new designs or 7.

r.ajor redesigns of NSS/XSC components and systems.

8.

Maintain the WBS.

Participate in cor:sittee and task force work for Nuclear Industrial 9.

Codes and Standards.

Participate in the develepcent of QA and operating gocedures.

10.

3.

PROPOSALS _

Raview custcc.er bid specificatica and identify deviations fren the 1.

Standard.

Review and. approve proposal veite-ups.

2.

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DRAFT SATETY AI*AI.YSIS 1; NIT L

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CEXEFAL_

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is responsible for the comprehensive evaluation of The Safety A=alysis Unit re. actor safe =y factors related to the design and operation of systems and Responsibility includes proving equipment wishin the, nuclear steam systes.

thac.the reactor plant is an acceptable risl' to the public by shoving that j

potential or postulated reactor accident or radioactive caterial releases

,1 do not exceed acceptable lintis.

II.

ACCIDEYf ANA '.TSIS_

A.

STANDAAr.S Prepara standards, guide specifications and backup information.

1.

Prepare calculational standards for all routine calculations.

2.

Estaiblish and e.aintain flies of ANS, MRC and other standard design criterin 3.

that apply te reactor safety and environment.

Maisrain cognizance of US NRC - sponsored R&D programs irr, accident 4.

analysis areas.

Davw. lop new methods of calculation.and improvements to existing methods L

5. afs c:he arca of safety analysis.

3.

CONTRAC3 Specify functional safety criteria for Reactor Protection System.

1.

Specify functional safety criteria for Control Rod Drive System.

2.

3.

Specify functional safety criteria. for feedwater system.

1

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Specify fucctional safety criteria for steam system.

,4.

Specify functional safety criteria for primary system (relief capacity 5.

rectaituents for accidents).

6.

Specify functional safety criteria for RC pump inertia, f

Establish and specify functional safety criteria for ESAS and reactor redundancy, etc.

j 7.

buf.1 ding isolation system related to electrical circuit i

. j Pre pare writeups and supporting analysis for accident analysis section e

l 8

of SAA and environmental repu ts.

Decernine magnitude of steam releases and fuel f ailures for environcental i

9.

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coesequences evaluation.

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RAFT II.

ACCIDENT ANAI.YSIS_ (cont'd)

B.

CONTRACTS ' (cont'd)

Establish maximum limits of operation and acceptable damage criteria 10.

to for:s basis of reactor protection s'ysten.

11.

Specify set point.s and li=its for reactor protection syste.a.

12.

Prepare and present safety analysis section of customer training programs.

13.

Review and evaluate test specificaticas and operating procedures related'to accident analysis.

14 Review SAR Sections related to accident analysis.

3.

Ravie.w customer prepared material related to accident analysis.

16. ' Review plant'cooponent specificaticas and equirxnt engineering changes that relate to accident analysis.

C.*

PROPOS AI.S 1.

Provida design support to Proposal Unit on Safety Analysis and Reactor Protection System Tunctional Requirements.

2.

Frepare technical reports and presentations which ansver customer or NRC questions.

III. RADIATION ANAI.YSIS A.

STANDARDS 1.

Prepare calculational standards for all routine calculations.

Establish and maintain files of ANS, URC and 'other standard design 2.

criteria that apply to reactor safety and environment <

+

Maintain cognizance of USSRC-sponsored R&D programs in radiation 3.

protection areas.

I 1.

Develop new method's of galculation and icprovements to e21 sting cethods in the area of safety analysis.

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E DRAFT APPINDIX_5_ (coot'd)

III. RADIATION ANAZ.YSIS (coat'd) 3.

CdNTRACTS Specify functional safety ' criteria for vaste Disposal system.

1.

Specify functional safety criteria for fission product cleanup 2.

systems, including spray rate and spray system functional requirements if chemical iodine removal is used.

Specify safety criteria for permissible caterials and protective 3.

coatings in reactor building following LOCA.

Evaluate post-accident chemical phesocena and specify related limita-4 tions or criteria for other plant systems.

Evaluate post-LOCA hydrogen generation and control in teactor building 5.

reactor building and specify functional requirements for post-accident hydrogen removal equipment or methods.

(.

Establish activity levels fort A.

, Reactor Coolant System B.

Secondary Steam System

. C.

Makeup & Pucification System D.- Radioactive Vaste System Determine source activitiets 'f.or operation and shutdovu to be used in 7.

shielding analysis for A.

Reactor Coolant System 3.

Secondary Steam System C.

Makeup & Purification System D.

Radioactive Waste Oystem 8.

Prepart writeups and supporting analysis for,*

Radioactive Waste Msnagement section of SAR A.

Evaluation of 5 pray System Effectiveness part of SAR B.

Evaluation of post-accide e chemical phenomena (H generation C.

and control) part of'SAR Environmental consequences of reactor accidents section of SAR D.

9 for accident radioactive release section of E.

Activisj is n..

environmental reporc Deteraine fission product activities and radiation levels in reactor 9.

building, emergency core cooling system solution, and reactor core i

under accident conditions as, required by shielding analysis.

Evaluate environmental consequences of normal operation of reactor 10.

. plant.

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I NPC-0151-81C DRAFT APPE.NOIX 5_ (cont'd) 5.

CohTRACIS (coot'd)

11. Establish environmental conseguence of a ticipated reactor transients i ment to mitigate environmental and identify eparations procedure or equ f

conseguences.

i Sper.ify technical specification linics fo'r prim.iry and secondary system 12.

activity levels.

13. Review and evaluate test specifications and operating procedures related to radiation p'rotection.

14. Reviev SAR, Sections related to radiation protection.

t Review customer prepared material related to radiation protection.

15.

16. Raview plant 'couponent specifications and equipnent engineering changes that relate to radiation protection.

+

C.

PROPOSALS _

Frovide design support to Proposal Unit add radiation require =ents.

1.

2.

Prepara technical reports and presentations which answer customer or NRC questions.

IV.

RADLk! ION ANALYSIS 4

• t.

.A.

STANDARDS _

1.

Prepare calculational standards for all routine calculations.

2.. Preparation of standards, guide specifications and backup inform.ation.

Establish and naintain files of ANS, NRC and other standard design criteria 3.

that apply to reactor safety 46d environnent.

4.

Maintain cognizance of US FRC-sponsored R&D prograss in shielding.

Develop nev methods of calucations and improvements to existing methods 5.

in the area of safety analysis.

3.

CONTRACTS _

Specify Shielding Design Criteria for protection of operating personnel, 1.

the public, and equipsient fron radiation e.xposure.

Establish neutron fluxes and shielding requirenent for the out-of-core 2.

detectors during nor=al operation.

Determine NVT in reactor internals and reactor vessel.

3.

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APPD"3II B (cceir'd) h 17 RADIATION ANALYSIS (cont'd)

B.

CONT 7 ACTS (cont'd)

Deternine heat generation rates in reactor vessel, its internals. and 4.

support structure, and in the prinary shield and supply to therr21 an tysis group.

s Prepare writeups and supportig analysis for radiation protectiou

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5.

section of SAR.

Review custo::c,e prepared naterial alated to shielding.

6.

Review plant ecoponent specifications and' equipment engineering 7.

c.hanges that relate to shielding.

C.

FitOPOSALS_

Provide design support to Preposal Unit Shielding Requirements.

1.

s Prepare technical reports and presentations which answer customer or 2.

EdC questions.

s.

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APPENDIX C DRAFT CONTROL ANAI.YSIS UNIT _

I.

CENERAL the Control Analysis Un' is responsible for providing the analysis required to define functional desis--

eriteria for the Reactor Coolast System,and Secondaiy System co=ponents and e ;

.uipmen t.

A.

5TrtDAES A.ND CONT?h

-- d

+7 sis required per the applicable V3S for defining 1.

Provide the er.t.

functional desk

- criteria for the RCS/SS components and equipment.

2.

Reco:=nend R&D p-

,gt.ns for standard product improvement or cost reduction and administer- * -

,,ptoved, funded programs.

SAR material and support licensing effort.

P.repara standar' 4

3.

4 Develop and e

. ain VFD/VA's and TCN's for Control /Perf arnance Analysis task.

Support other kn wr.1 rssks es defined in the Work Package Descriptions.

3.

6.

Support the r=--

atution of site probles.s and review test results tw

. acceptability.

7.

Support Interm--

f onal projects as required.

8.

Identify, and p-

--rticipate in the resolution of risk items.

9.

Review RCS and-sS Descriptions pri r to their release.

l o the Plant Parameter list describing plant sperating l

10. Provide input tr conditions ~A--etpcints.

11. Keep Engineeri -

-g and Project Management advised of work status and critical " prob f >--- -- areas.

12. Provide a seu;

• e to other NPC3 organizations requiring the unique A within the Unit.

e.xpertise fo' B.

PROPOSALS _

l Provide analyi:--

s necessary to support custoser bid specifications which 1.

require devia.

-nos from Standard Flanc.

2.

Provide techn*.

"I expertise to Marketing when required f or answerin5 custooer inquiz:.

-es.

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POLICIES AND PROCEDURES NPC.0151-810 j

APPENDIX D DERCENCY CORE COOLutT SYSTD1 UNIT (ECCS)

i. --

The ICCS Analysis Unit is responsible for the analysis of the toss of Coelant Accident leading to develop =ent of functional requirenants for NSS equipment, reactor building design and developr.ent of LOCA related operational limits.

.i A.

STANDARDS AND DEVELOP'ENT Frepare &ad maintain standard analysis programs, functional criteria, 1.

analysis procedures, and standard input data.

Recocaend R&D programs for Tests and Developmental programs leading 2.

to more reasonable analysis results and improved design at lower cost.

Administer approved and funded programs.

Maintain cognizance of Industry /NRC developments leading to improvel 3.

response to Customer /NRC requirenants.

Prepare and maintain standard.dssign and SAR material and support 4

[

standa:rd I.icensing efforts.

3.

CONTRACTS AND CD'ERIC Manage the VBS tasks to perform in a'ecordance with NSS contract require-1.

5ents - including manpower computer costs and schedule. -

Develop and maintain VFD/VA's and TCN for the tasks assigned.

2.

Support interface tasks as described in Vork Package Descriptions and 3.

CID's.

4.

Frovide Contract /Ceneric analyses tot 4.1.

I.stablish core cooling during LOCA.

Specify Auxiliary System post-accident performance requirements 4.2 The Auxiliary Systems including actuating signal and set points.

include Core flooding system RFI system LPI system Building spray and cooling heat removal requirenents Evaluate effects of fuel failure during LOCA.

4.3.

Evaluate solids concentration in reactor vessel af ter LOCA.

4.4 Establish technical specifications for ECCS equipment.

4.5.

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At>41NISTRATivt u muat POLICIES AND PROCEDURES PtLNB(R NFC-0151 81C s

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APPENDIX D _(cont'd) h

.i I.

GENERAL (cont'd) 3.

CC!IT" Ac!1 VP c73ritte (coa.g'd) 4.

(coat'd)

Review test and operating procedores for ECCS systems and equipment.

4.6.

4.7.

Evaluate ICCS system and equipment field performance data.

Establish LOCA AP loading for reactor internals.

4.8 4.9.

Establish LOCA thrust loads for NSS equipment.

4.10.

Establish jet impingement forces during LOCA.

4.11.

Specify number and sire of intgraals vent valves.

4.12.

Specify nunber and size of Core Flood tanks.

4.13.

Specify mass and energy release rates for building design.

Specify building design pressure, temperature, volune and cooling 4.14.

requirements.

Specify building subcompartment design requirements including venting 4s15.

area.

Preparation of LOCA input for SAR's and review of appropriate 4.16.

SAR sections.

4.17.

Establish LOCA limits.

Keep line and Project Management advised of work status and identifica-5.

tion of problem areas requiring their participation in resolution.

C.

PROPOSALS Review appropriate sections of custErmer's bid specifications, identify 1.

deviations, and provide resource estimate to satisfy deviation.

Develop and usintain standard ECCS related descriptive material for I

2.

Proposals.

Provide Marketing support by technical presentations.

3.

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48 34990 8 ACD41NISTR AtlVC L34&L POLICIES. AND PROCEDURES M P8ER NPC-0151 AIC

' APPENDIX E ORAFT SYSTCt MEutANI ANALYSIS _

I.

CENERAL_

A.

STANDARDS Perform the servetural analysis necessas to predict the dynazic and 1.

static loadings imposed on coc;ponents ar.d supports of the Resccor coolant System by thermal expansion, dead weight, seismic vibrations, and loss-of-coolant accident conditions.

2.

Prepare and issue " Reactor Coolant System Youndation & Nozzle Leading Specification: (1235).

3.

Develop and supply conceptual design layout drawings of RCS supports and restraints.

Perform the slaplified stress analysis ~ of the prinary coolant system 4.

piping required by ASMI Section III, and issue a piping stic, report showing the results of this analysis.

5.

f:enerate and issue seismic, response spectra for points where customer supplied pipir.g attaches to r_he component of the reactor coolant syste:s.

6.

Supply input to Safety Analysis Reports and respond to NRC licensing questions as necessary to describe and justify the criteria, methods, and models utilized to predict the structural response of the reaccor coolant system to seismic LOCA, thatual, and weight coaditions.

Supply to the appropriate NPCD organi:ations, detailed seismic and 7.

LOCA response data for the design of R.V. Internals. Tuel Assemblies, CRDM's, and R.C. pumps and motors.

8 Provide support to Marketing and Product Development in standardining B&W's product line and identifying the, cost of changes.

Prepare and maintain standard cost esticates acd other documentation 9.

as required by product development.

Manage and develop the analysis and design activities needed to predict 10 the structural response of the reactor coolant system to scacic aod This responsibility includes providing dynamic loading conditions.

the lesdership, manpower, schedules, plans and budgets to efficiently evaluste and justify the structural adequacy of the reactor coolant system equipment.

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POLICIES AND PROCEDURES M.s.a8 C A N7C-0151-810 s

l

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APPCiDIX E (cont'd) l I.

CDIERAL (cont'd) r*

A.

STANDARDS _ (cont'd)

11. Participate on ASME and other code coznittees to establish B&W's posit. ion on technical matters and to develop industry standards for structural analysis.

12. Part.'cipate in the development of Q t and M.inagement Information system.

3.

CONTRACT 3 I.

Review and evaluate information received from or transmitted to the i

5 1.

custcrer/AE.. or othe.r B&V organizations that affects the structural characteriscies of the RCS.

i 2.

Perform spa.-4=1 studies and analyses to assist customer /AZ in resolving tact =11 cal or licensing problems.

3.

Support res.slution of site problems.

t' 4.

Provide suport for International projects.

3.

Ident.ify and participate in the resolution of risk itess.

Manage the applicable WBS tasks to perform in accordance with NSS 6.

concract requirements - including costs and scheculing considerations.

C.

PROPOSALS Review cuscomer bid specifications and identify deviations fron Standa.rd.

1.

Provide c'est estimates and recossend desi.1 changes to acccoodate 2

individual customers.

Support Markating by providing and/or presenti5g technical data as 3.

required.

1 I

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wC-0151-31 c W

W f-r(AFT j

S APPENDIX T INTERNATIONAL PROGRAM INTECRATION_

1 I.

c u tRAI._

The International Program Integration Unit (IPI) is responsible for Integration of B&W's Engiceerir.g Department activities and selected Froject Eneineering The Internat. anal Task for Babcock-Erown-Boveri Cub}! (BBR) contracts.the integration functions by inter-(IPI) carries out Progra:a Integration Unit f ace relacionships with various Engineering Department Units and the B5R interface is conducted through the International Program Management (IPM)

Department.

II.

Osm.iiir r 5 Fer4=f re the use of proven B&W design on Muelhein-Kaerlich and follow 1.

on contracts, except where differences are e.andated by Ceman Law, contract Requirements, or Cercan " State'of the Art" practices required by the Customer or Regulatory Agencies.

Maximias use of B&W-USA resources and experience to deliver Muelheim-2.

Kaerlich and follow on contracts for BBR in the minimum reasonabla time and at the least ransonable Lost.

Expedite engineering planning and follow up actions in support of BBR, 3.

including -astabl*.shing priorities, definition of tasks, and establishing i

BBK con =1tx nts.

, special methods'and procedures to accelerate NPCD activit es on Assist in the identification aM resolution of probler.s concerning the 4

ability of 33R to meet its priority cocamitments.

Toru, guide, review, and approve technical information and work that 5.

flows between NPGD to or fron BBR, via International Program Manageocut (IPM).

III. RESPONSIBILITIES The specific responsibilties of Inte'enal Program Integration are:

Coordinate, schedule, integrate, and exp dite and approve Engineering Department activities and information flow between ' 6W an

• BBR, and between internal Z&W Ihis function spplies to engineering units for BBR related activities.

Design overview Program (DOP), Master Service, Licensing Agreement, Consulting Activities, and other Engineering activities as directed or negotiated with IPM.

Review, generate, or esuse to be generated DOP coements on 53R systems, components.

or procedures as described in BBR docunentation.

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POLICIES AND PROCEDURES NPC-0151-31C APPENDIX F_ (cont'd)

-v DRAFT RESPONSIBILITIES (cont'd)

III.

Resolve D;P cossnent differences, if necessary, between interfacing 1.

Engineering Department units.

Review of DOP connants produced by the E. d neering Department units to i

2.

insure technical adequacy.

Approval of final DCP cos:sents for transmittal to B8R.

3.

Initiate, formulate, and reccc: mend team nesbers for ' pecial Purpose S

IPI shall 4.

Reviews (SPR's) for systems, components, and problem areas.IPI personnel will provide scope, guidance, and support to SPR aembers.

comprise at 1 cast one member of the SPR team, unless this function is delegated to an Engineering Department unit.

or deletion system, component, or 3.

Recozzand to BSA via IPM addition problem documentation to the DOP.

Perform integration and review activities to assure technical at aquacy, technical information 6.

accuracy and completeness of Engineering Department submitted to BBR.

Provide schedulias and re'ource estimates as required and requested by s

7.

IPM.

Provide task descriptions to IPM with resource estimates and schedules j

• to define DCP, Master Service, License Agreement, or Consulting Work.

8.-

f l

Identify and define open 'ite=s and critical open items and work with 33R and within the Engineering Department; to schedule strategy, and resolve 9.

j Maintain status of open items and critical open ite=s all open items.

(

with IPM.

I I

Prepara and maintain core analytical input requirements documentation.

10, l

Prepare or cause to be prepared centract documentation la accord with 11.

Engineering Dapartment procedures.tc provide BBR with.tirely, documented, the BBR BW initiated designs or design changes that directly affect design.

I Develop and maintain technical awareness within IPI and the Engineering 12.

Department of the EBR desig as folicws:

Maintain vnderstanding and documentation of all BBR systems and l

co=ponents that are within or closely related to the SW Jamestic a.

i scope of supply.

Develop and maintain understanding of Cerssn Licensing Agreements b.

and Licensing stipuistion for Nc1hein-Kserlich and follow--on contracts.

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POLICIES AND PROCEDURES Nuu3tR N PC.-0151 -81C i

APPENDIX F_ (ccat'd)

AFT III.

RESPONSIBILITIES (cont'd)

~

12 (cont'd)

Develop and maintain cop 6'.2& ace of status, problems, strategy of c.

on-going technical activities at BBR. Ccgnizante of tecbufcal activities is to be developed ar.d m.nintained by telephone and/or viteten contact with BBR engineers and by planned, scheduled visits f,

j with BBR personnel.

13.

Participate with IPM, as required, in a sitanc,e to BBR in preparation of proposals.

Originate," or cause to be initiated, internal design reviews of systems 14.

or components that are shared by the B&W and' the BBR design and are critical to BBR warrantees, operational flexibility or schedule.

15. Follow Engineering Departnent procedures to obtain satisfactory,

[

documented product for BBR.

l

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IV.

INTERFACE REI.ATIONSHIPS International Program Integration (IPI) is an Engineering / Integration organization which interf aces internally with U tits within the Engineering Department, and interfaces with BBR through the International Program Laagement (IPM) Department.

g The IPI/IPM -interface responsibilities ares j, [.

1.

IPI is responsible for intergration of all BBR related technical activities within - the Engineering Departnent. In selected major task areas,.IPI shall delegate responsibility to the cognizant Engineering y

Department Unit. In these delegated, major task IFI shall maintain the j Q, a

integration function of review of interfaces, input requirements, input f

1 data, review and ap' proval of the output of the cognizant Engineering

'[

Unit.

L All ' formal IFI correspondence to BBR is through IPM, and subject to

{[

IPM o;serating proceduras fcr communication and document control.

lt t

j Interf acing responsibilities for Engineering Department Units includes 2.

{ {I the followingt l

IPI shall maintain "look ahead" schedules for the Engineering Units a.

engaged in BBR support activities. These schedules shall be updated quarterly.

-h When task activities are required of Eagineering Depart =ent Units, b.

the cognizant IPI Engineer shall conduct negotiations with the These IPI/ Unit Cognizant Engineering Department Unit or Units.

negotiations shall define in writing, the Task defin'ition (WD), the i

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ADelNs5T.tATlYC 64 WJAL POLICIES AND PROCEDURES NwsC R 5 *C-015141C AFFINDII F (cont'd)

DRAFT IV.

INT 1RTACE RitJLTIONSHT75 (cont'd) 2.b.

. (con t 'd) input inforr.ation required (%7D details), the resources required ('4),

and the schedule (*a). khen schedule conflicts occur III shall e.x.ilne or cause to be escalated the concern to Engineering.'.inagement.r4 I?M as required to achieve schedule resolution. Upon eccpletion of tasi negotiation, critical itens shall be entered in the appropriate saaagece t 8

inf ore.atica system for visi*oL11ty. Tasks of norcal priority shall l<

entered in the scheluli:4 action ite=s program or appropriate 123

-systen.

IPI shall assist all interf ace thics supporting a task in schedule and funding.

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