ML19326D802

Advises That Licensing Activities Will Be Coordinated by W Paulson,As Result of Reorganization of Ofc of Nuclear Reactor Regulation.Description of Reorganization Encl

ML19326D802
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/02/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8007030335
Download: ML19326D802 (28)

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I THIS' DOCUMENT CONTAINS JUN 0 21980 P00R QUAUTY PAGES l

Docket No. : 50-155 RBMI0iF! MT FE COPY i

c Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201

Dear Sir:

The reorganization of the Office of Nuclear Reactor Regulation became effective l

on April 28, 1960, and as a result, licensing activities for the Big Rock Point Plant are being coordinated by Mr. Walt Paulson, who is your Project Manager.

Mr. Paulson is now a sesber of Operating Reactors Branch #5, which is headed by Mr. Dennis M. Crutchfield e

The new NRR organization is described in the attachment to this letter. There will be a necessary period of transition from the old responsibilities and 1

interfaces to the new, but we intend ~to sake the change with a minisum of disruption to ongoing activities. We hope that this reorganization will improve both our effectiveness and our lines of cosuunication with licensees and other parties concerned with nrclear. reactor replation.

Should you have'any ' questions concerning this new organization feel free to contact your Project Manager. S,p,e;

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Jun oe eso Docket No. : 50-155 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Cogany 212 West Michigan Avenue Jackson, Michigan 49201

Dear Sir:

The reorganization of the Office of Nuclear Reactor Regulation became effective on April 28, 1980, and as a result, licensing activities for the Big Rock Point Plant are being coordinated by Mr. Walt Paulson, who is your Project Mansger.

Mr. Paulson is now a member of Operating Reactors Branch #5, which is headed by Mr. Dennis M. Crutchfield The new NRR organization is described in the attachment to this letter. There will be a necessary period of transition from the old responsibilities and interfaces to the new, but we intend to make the change with a minimum of dismption to ongoing activities. We hope that this reorganization will igrove both our effectiveness and our lines of consnunication with licensees and other parties concerned with nuclear reactor regulation.

Should you have any questions concerning this new organization feel free to contact your Project Manager.

Sincerely,

_L Dennis M. Crutch teld, Ch Operating Reactors Branch 5 Division of Operating Reactors

Attachment:

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See next page

Mr. David P. Hoffman Cc Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Cogany Agency 212 West Michigan Avenue A *ral Activities Branch Jackson, Michigan 49201 Region Y Office ATTN: EIS COORDINATOR

'udd L. Bacon. Esquire 230 South Dearborn Street Consumers Power Comany Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo Esquire U. S. Nuclear Regulatory Comission Isham, Lincolr: & Beale Washington, D. C.

20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.

20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Peter W. Steketee, Esquire Washington, O. C.

20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Sheldon, Harmen and Weiss U. S. Nuclear Regulatory Comission 1725 I Street, N. W.

Washington, D. C.

20555 Suite 506 Washington, D. C.

20006 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Charlevoix Pubite Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Office of the Governor (2)

Room 1 - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency

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Arlington, Virginia 20460

Office of Nuclear Reactor Regulation Director l

Harold R. Denton Deputy Director Edson G. Case TMI Program Office Planning & Program Analysis Staff Program Director Bernard J. Snyder Director:

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John T. C011 ins Resource & Scheduling Br6nch d

Frank J. Miraglia. Chief

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Emergency Preparedness Program Office Management Analysis Branch i

Program Director

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Brian K. Grimes Technical Support Branch 3

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Division of Licensing Division of Division of Systems Division of iluman Division of Safety Engincering Integration Factors Safety Technology s

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Division of Licensing Director Darrell G. Eisenhut.

' Deputy' Director Robert A. Purple i

i Assistant Director for Operating Assistant Director for Licensing Assistant Director for Safety i

Reactors Assessment Thomas M. Novak Robert L. Tedesco Gus C. Lainas

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Opera ting Reactors Branch 1

~ Licensing Branch 1 Operating Reactors Branch 5

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_ Licensi,ng Branch 2

_ Systematic Evaluation Program Branch Thomas A. Ippolito, Chief *',

Albert Schwencer, Chief r Dennis M. Crutchfield, Chief (Acting) t 1

Operating Reactors Branch 3 Licensing Branch 3 Operating Reactors Assessment Branch Robert A. Clark, Chief Vacant ~

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I Assistant Director for Environmental Assistant Director for Components Assistant Director for Materials &

& Struch.es Engineering Qualifications Engineering Technology James P. Knight Vincent S. Noonan Daniel R. Muller

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_ Mechanical Engineering Branch

_ Materials Engineering Branch '

_ Envi mnmental ' Engi neei in'g Branch '

Ronald L; Ballard, Chief Robert J. Bosnak, Chief d Stefan'St'Pawlicki, Chief i

_ Structural.Engincering Rranch

_ Chemical Engineering Branch

_ Siting Analysis Branch Franz P. Schauer; Chief Victor Benemya, Chier William H. Regan, Chief I

Geosciences Branch Equipment Qualification Branch Utility Finance Branch Robert E. Jackson, Chief' '

Zoltan R. Rosztoczy, Chief Jerome D. Saltzman, Chief *

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- Accident Evaluation Branch

- Reactor Systenp Branch l

Robert W. Houston, Chief Themis P. Spels Chief Systems Branch Rodney M. Satterfield, Chief

- Power Systems Branch

- Radiological Assessment Branch

..., - Core Performance Branch Faust Rosa, Chief Thomas.D. Murphy, Chief Vacant 1

- Containment Systems Branch Effluent Treatment Systems Branch,.

. Systems' Interaction Branch' Walter R. Butler, Chief William P. Gansalli, Chief

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Paul F. Collins, Chief

- Licensee Qualifications Branch

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- Procedures & Test Review Braich i

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-Generic issues Branch Safety Program Evaluation Branch Karl Kniel, Chief Robert L. Baer, Chief

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_ Operating Experience Evaluation Branch Carl H. Berlinger, Chief (Acting)

Research S Standards Coordination Branch Reliability and Risk Assessment Branen George W. Knighton, Chief Sanford L. Israel, Chief (Acting)

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OlSTRIBUTION OF' FUNCT10NS A.

THE DIRECTOR 1.

Develops and administers regulations, policies, and procedures governing:

the licensing of manufacturing, production and utilization a.

facilities other than those 'concerning fuel reprocessing plants and isotopic enrichment plants; b.

source, byproduct, and special nuclear material used or produced at such facilities; and

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the licensing of operators of such facilities..

2.

Reviews reactor safety aspects of proposed berthing of ~ nuclear powered vessels.

3.

Provides special assistance as required in matters. involving facilities exempt fr$m licensing and performs other functions required for inglementation of the licensing program.

8.

THE DEPUTY DIRECTOR

, Assists the Director in the accomplishment of Office functions, and oversees direction of management activities related to the Office's assigned missions. During the absence of the Director, acts for the Director with full and complete responsibility for the activities of the 0ffice.

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THE PROGRN4 DIRECTOR TMI PROGRAM OFFICE Provides everall direction of TMI-2 cleanup cperations, including technical and manage. ant supervision of related NRC inspection, licensing, analysis, public information, and government relations actions on-site, in the Middletown office, and in the Washington, D.C. area. Manages and directs the preparation of the Programmatic Environmental Icpact Statement and related assessments, including rescurces for in-house analyses or for contracts, scheduling, coordination with other agencies and with the public, and pre-sentation of results.

Coordinates all NRC activities relating to,

the cleanup which involve other Federal agencies, state and local governments, and groups or members of the public,.

THE DEPtJTY PROGRAM DIRECTOR. TMI PROGRAM OFFICE Stationed at NRC's Middletown, Pennsylvania office. Assists the Program Manager in the accomplishment of Office duties, including direct supervision of inspection and licensing activities and local NRC personnel.

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THE PROGRAM DIRECTOR, EMERGENCY PREPAREDNESS PROGRAM OFFICE Responsible for directing and managing the evaluation of licensing actio.s related to emergency preparedness and the i

NRR effort to u; grade emergency preparedness at and around nuclear power plants.

Provides liaison and coordination with the Federal Emergency Maoagement Agency (FEMA) on matters of l

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interfaces, reviews and policy. Develops policy reccmmendations in relevant areas including criteria for program adequacy, action level criteria, staffing and equipment requirements, thyroid blocking and accident management and data interchange.

iiiE DEPUTY PROGRAM OIRECTOR, EMERGENCY PREPAREDNESS PROGR#t OFFICE Assists the Program Of rector in the accomplishment of Office functions and acts for the Director in his absence.

The Emergency Preoaredness Licensing Branch reviews and evaluates emergency plans associated with the applications for n'uclear reactor facilities; reviews emergency preparedness evaluations of state and local emergency plans perfonned by FEMA; coordinates l

the reviews of emergency preparedness areas under joint con-sideration by NRC and FEMA.

The Emergency Preparedness Development Branch develchs and evaluates policy recommendations and regulatory requirements for emergency preparedness; develops evaluation criteria for use in licensing; identifies needs for relevant guides and standards; provides liaison with other MRC offices, agencies

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and foreign groups on emergency preparedness programs; coordi-nates with FEMA in development of criteria for onsite anri off-site emergency preparedness; provides technical support for

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the Emergency Preparedness Licensing Branch.

. E.

THE DIRECTOR, PLANNING & PROGRM ANALYSIS STAFF Provides administrative management and coordination of the programs and resources of the Office.

Establishes priorities, schedules and resource allocations; establishes interdisciplinary teams and task forces from the divisions; performs resource forecasting, long and short-range program planning, budget preparation and coordination, resource control and perfonnance auditing, fiscal analysis, management and control. Provides administrative and management support including personnel management, management studies, management directives, personnel development 'and training, correspondence and action item control; provides technical assistance and support in special and diversified licensing-related projects and improvements to the licensing program.

The Director, Planning & Program Analysis Staff, is delegated the authorities defined in Chapter NRC-0123, Subsections 028 and 029.

The Resources and Scheduling Branch: develops and mintains data and records on prior'ities, schedules and assignments of NRR resources and of the status of all projects and tasks; performs long and short-range program planning, resource forecasting, budget preparation and coordination, manpower and program support resource management, auditing of performance against established goals and objectives.

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5-The Manacement Analysis Branch: manages all personnel administration matters; performs management and org'anizational studies and prepares proposals thereon; recommends, prepares and reviews management and administrative operating procedures, policies and directives; im-1 plements procedures for fiscal control of all program. support and travel resources; develops and implements procedures and models for analyzing and presenting NRR staff and program support expenditures; manages the personnel development and training function; controls and coordinates correspondence, FOIA requests, action items and records management.

The Technical Sucoort Branch:

provides technical coordination

nd oversight for resolution of special technical problems and those which involve more than one division and other offices; provides technical assistance to the Director of NRR; serves as the staff interface with the ACRS; recommends and develops im-provements to the licensing program; provides overall rehiew, coordination, allocation and management of the NRR technical assistance program in.cluding development of procedures for re-source control; establishes and coordinates Office procedures for contracting and interagency agreements; responds' to corres-pondence and Commission actions of a general nature; prepares

. and coordinates NRR inputs to the NRC Annual Report.

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THE DIRECTOR, DIVISION OF LICENSING Directs and administers the licensing process for all utilization

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and production facili. ties, other than fuel reprocessing and.

isotopic enrichment plants, including safety and environmental

' evaluations of power' and non-power reactors required to be licensed and f acilities licensed for operation. Directs the evaluations i

cf design, operation and modification of DOE-and 000-owned facilities exempt from licensing, as requested. Directs and supervises the processing of applications and petitions for license 4

amendments for all licensed reactor facilities. Develops related policies, procedures and programs and assures proper implementation.

Issues, denies and amends all limited work authorizations, permits and licenses for power and non-power reactors. Serves as NRR coordi-nation with the Office of Inspection and Enforcement.

The Director, Division of Licensing, is delegated the authorities defined in Chapter NRC-0123, Subsections 021a, 022, 023, 025, 026, 0210, 0212, 032a, 032c, 033a, 033c, 034, 035, 038, 039, 0310, 0311 abd 0313.

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THE DEPUTY DIRECTOR, DIVISION OF LICENSING Assists the Director in the accanplishnent of Division functions and acts for the Director in his absence.

1.

The Assistant Director for Operating Reactors plans and directs the safety and environmental reviews of licensed operating power reactors and the review of proposed amendments to operating licenses. Supervises the programs and activities 1

of the Operating Reactors Branches. Assists the Director in administering the Division's programs.

a.

The Ocerating Reactors Branches 1-4 perform the overall 1

safety and environmental project management for assigned licensed operating power reactors, including review of technical and procedural aspects involving p'roposed amendrents to operating licenses.

1 2.

The Assistant Director for Licensing plans and directs the I

program for safety and environmental review and evaluhtion of applications for limited work authorizations, construction permits, operating license's, prelindnary and final standard design approvals, early site approvals and topical report approvals'.

Evaluates design, operation and modification of test, research and critical facilities, Naval reactors, 00E-and 000-owned facilities exempt from licensing, and advanced reactor concepts. Supervises the programs and activities of the Licensing and Standardization & Special Projects Branches.

Assists the Director in adninistering the Division's programs.

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The Licensir.; 3 ranches 1-3 perform the overall safety j

and envir:n: et.a1 project management for assigned power reacter limited woric authorization, construction permit and operating license applications.

b.

The Standardization and Special pro.iects Branch performs the overall safety and environmental project man'agement for assigned preliminary and final standard design approval, early site approval, topical report approval, research and 4

i test reactor and critical facility applications.

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similar functions for Naval reactors, advanced reactor concepts and COE-and 000-owned facilities exempt from licensing.

Provides the NRR interface and coordination with NMSS on reactor safeguards matters; conducts porting reviews of nuclear-powered vessels.

3.

The Assistant Director for Safety Assessment plans and directs the safety and environmental reviewis of licensed operating power reactors. undergoing systematic re-review i

and the technical evaluation of proposed routine operating license amendcents.

Supervises.the programs and activities of the Operating Reactors Branch 5, the Systasatic Evaluation Program Branch and the Operating Reactors Assessment Branch.

Assists the Director in administering the Division's programs.

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The Oceratino' Reactors Branch 5 performs overall coordination and routine project management including safety, environmental and procedural aspects, as well as proposed amendments for those operating power reactors which are under re-review as part of NRC's program to systen.atically evaluate the margins of safety of the design and operation with respect to current licensing requirenents.

b.

The Systematic Evaluation Program Branch provides the overall coordination and task management functions, for the review areas related directly to SEP matters, for those operating power reactors which are under re-review as part of "NRC's SEP program.

Also, coordina.tes the efforts of those technical specialists from other divisions assigned to the SEP program.

The Ooerating Reactors Assessment Branch provider' inter-c.

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disciplinary full-time dedicated technical support to operating reactors projects in the processing of re-latively routine, short-duration licensing actions.

Also, provides rapid initial evaluation of unanticipated events and defines needed support from the other NRR divisions.

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THE DIRECTOR, DIVISION OF ENGINEERING Directs and administers the detailed evaluation, in the safety engineering and environmental disciplines, for power and non-power i

reactor applications, for reactor fteilities licensed for operation and for DOE-and 000-owned facilities exempt from licensing; develops and administers related safety and environmental programs and policies governing the licensing and cperation of nuclear reactors.

The Director, Division of Engineering, is delegated the authorities defined in Chapter NRC-0123, Subsections 021a', 022, 023, 024, 025, l

026, 036, 037, and 0311.

1.

The Assistant Director for Cenconents and Structures Engineering plans, directs and supervises the programs and' activities of the Mec5anical Engineering, Structural Engineering, Geosciences and Hydrologic & Geotechnical Engineering Branches.

Assists the Director in administering the Division's programs.

e a.

The Mechanical Engineering Branch reviews and evaluates seismic and pipe whip design; mechanical design of reactor vessels, reactor core supports, reactor fuel components, reactor coolant pumps, steam generators, reactor coolant piping, pressurizers, compone.~ supports and ot'ter safety-related mechanical components; miss.ile impacts.

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The Structural Engineering Branch reviews and-evaluates missile protection, design and loadings of concrete and steel containments and design of other safety-related plant structures; performs technical review, analysis, and evaluation of the design, construction and operation of reactor and related structures.

c.

The Geosciences Branch performs the technical review and evaluation of the acceptability of proposed and operational nuclear reactor sites with respect to the seismological, and geological aspects of the site; directs the analytical effort of consultants and assesses their input in the preparation of site safety evaluations; identifies areas in which appro-priate earth science methodology needs further resea'rch

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and development and assists in developing programs to fill these needs.

d.

The Hydrologic and Geotechnical Engineering Branch per-forms the technical review and evaluation of the accepta-bility of proposed and 1perational nuclear reactor sites with respect to the hydrologic and coastal engineering characteristics of those sites; reviews and evaluates the geotechnical engineering aspects of the safety of supports for structures and earth structures; directs the analytical effort of consultants and assesses their input in the pre-paration of site safety and environmental evaluations; identifies areas in which the hydrologic and geotechnical methodologies need further research and development and assists in developing programs to fill these needs.

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The Assistan-Cirector for Materials & Qualifications Engineering plans, directs and supervises tne programs and activities of the Materials Engineering, Chemical Engineering, Equipment Qualification and Quality Assurance Branches.

Assists the Dir2ctor in administering the Division's programs.

The Materials Engineering' Branch evaluates the materials-a.

related design and performance of components and systems important to safety; performs general technical review, analysis and evaluation of the materials, fabrication, inspection and testing of nuclear power reactor components and systems.

b.

The Chenical Engineering Branch evaluates the chemical and process-related design and performance'of effluent control and plant auxiliary systems, and the systems and administrative controls for fire protection at operating plants and plants under review; performs general technical review, analysis and evaluation of water chemistry management, activity cleanup and removal systems and process control systems.

c.

The Ecutonent Qualification Branch evaluates the capability of plant systems and components important to i

safety to function acceptably unde' a i. anticipated normal t

and accident environments inr;tA!!n;.arri, pressure, moisture, radiation, dynamic y.nd seismis; establishes.

- performance requirements and reviews qualificar, ion test programs and results.

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d.

The Ouality Assurance Branch reviews reactor license applications and operating license amendments to assure compliance with Co= mission quality assurance criteria during plant design, construction and operation.

3.

The Assistant Director for Environmental Technolocy plans, directs and supervises the programs and activities of the Environmental Engineering, Siting Analysis and Utility i

Finance Branches. Assists the Director in administering the Division's programs.

a.

The Environmental Engineering Branch provides specialized technical capabilities in the areas of yater quality

. engineering, aquatic and terrestrial ecology, and land use assessments; interfaces with other NRC divisions and Federal, and State agencies in 'the resolution of generic and case-related environmental issues; prepares the. facility en-vironmental technical specifications portion of each r.3w facility operating license. Provides NEPA coordination with the Council on Environmental Quality; coordinates NRR responsibility for reviewing other agency impact statements and serves as NRR focal point for NEPA-related matters and responsibilities.

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The Siting Analysis Branch evaluates risks associated with nearby industrial, transportation and military facilities; performs demographic and other site characteristic studies; develops criteria for and perfoms evaluations of suitability of proposed and alternate sites from the standpoint of population and land use; provides specialized technical capa-bilities in the areas of local and regional socio-econernic impacts of nuclear power plants.

c.

Tne Utility Finance Branch establishes and administers those delegated NRC functions required to implement antitrust reviews of license applications for* nuclear facilities, including responsibility for compliance with l

license conditions pertaining to antitru'st matters, and

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those functions related to indemnification of licensees against public liability claims arising out of nuclear incidents; reviews, investigates and evaluates power supply, inter-system coordination and existing and po-tantial anti-competitive activities by applicants; pre-pares relevant testimony; provides technical assistance l

'on economic, engineering and power supply aspects of antitrust cas'es; assists in formulation of antitrust policies and guidance; reviews financial. qualifications of applicants and licensees and specifies license con-ditions to assure utility commitments for construction and operation of nuclear reactors; provides specialized technical capabilities in evaluation of the benefits and costs of nuclear power plants and need for power.

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The Chief, Utility Finance Branch, is delegated the authority' contained in Chapter NRC-0123, Subsections 024, 036 and 037.

H.

THE DIRECTOR, DIVISION OF SYSTEMS INTEGRATION Oirects and administers the detailed evaluations in the nuclear system performance-oriented disciplines for power and non-power reactor applications, for reactor facilities licensed for operation, for advanced reactor concepts and for DOE-and 000-owned facilities exempt from licensing; develops and administers related safety programs and policies governing the licensing and operation of nuclear reactors.

The Director, Division of Systems Integration, is delegated the authorities defined in Chapter NRC-0123, Subsections O'1a, 022, 2

023, 025, 026, and 03il.

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The Assistant Director for Plant Systems plans, dirccts 4

and supervises the pregams and activities of the Instru-mentation & Control Systems, Power Systems, Containment Systems and Auxiliary Systems Branches and assists the Director in administering the Division's programs.

a.

The Instrumentation and Control Systems Branch reviews and evaluates the design, fabrication, and operation of reactor protection and safety instrunentation, and control instrumentation; and participates in the development of guides and re'gulations pertaining to instrumentation and control systems.

b.

The Power Systems Branch reviews the design, fabrication and operation of onsite and offsite electrical power systems and the steam and power conversion systems; participates in the development of guides and regulations perte.ining to these systems.

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The Containment Systems Branch reviews the design, fabrication and operation of the containment system and associated subsystems., includi'ng emergency heat removal

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. systems, heating and ventilation, isolation equipment and controls, and combustible gas control systems.

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The Auxiliarv Systems 3 ranch reviews the design, fabrication 'and operation of auxiliary systems.

2.

The Assistant Director for Radiation Protection plans,

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directs and supervises the programs and activities of the Accident Evaluation, Radiological Assessment and Effluent Treatment Systems Branches and assists the Director in administering the Division's programs.

a.

The Accident Ev'aluation Branch develops models for and performs calculations and evaluations of potential accidents and event scenerios from initiation through consequence f

mitigation for both safety and environmental evaluations; reviews reactor license and amendment applications, as well as operating data, to evaluate engineered safety features with respect to mitigation of offsite dose consequences and habitability aspects of control room design and site meteorology.

b.

The Radiological Assessment Branch reviews reactor license and amendment applications, as well as operating data, to evaluate the radiological impact of facility operation on man and the environment, and the adequacy of the radiation protection program for the plant work force; develops analytical models, assumptions, acceptance criteria and calculational methods to conduct these reviews.

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c.

The ~ffluent Treatment Systems Branch reviews reactor license applications and amendments, as well as operating

,i data, to evaluate nuclear reactor radioactive waste treatment and management systems, radioactive effluent control and monitoring systems; develops analytical models, assumptions and calculational methods for evalu-4 ating the effectiveness of proposed systems; carries out j

reviews, studies and anal'yses related to these reviews and development of radioactive waste standards.

3.

The Assistant Director for Reactor Systems plans, directs and supervises the programs and activities of the Reactor Systems, Core Performance and Systems Interaction Branches

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and assists the Director in administering the Division's programs.

a.

The Reactor Systems Branch reviews and evaluates the design and performance of reactor thennal-hydraulic systems, reactor coolant systems, emergency core cooling systems and associated auxiliary systems; reviews, analyzes and evaluates calculational methods used by applicants and licensees in these areas; develops and uses independent calculational methods for analyzing perfonnance of these systems under steady-state, transient and accident conditions; reviews, analyzes and evaluates the effects of severe accidents, including core de-gradation and melt accidents, on reactor designs; evaluates means for mitigating the effects of such accidents.

. The Core Per' ormance Branch reviews and evaluates the f

b.

nuclear, thermal, hydraulic and reactor fuel aspects of

-I nuclear reactor design and perfonnance reviews, analyzes and evaluates calculational methods used by applicants in these areas; develops and uses independent calculational methods for evaluating these aspects of reactor design and operation under a spectrum of normal and off-normal conditions.

c.

The Systems Interaction Branch performs systems engineering evalur.tions of overall plant design and performance, including integration among ma,jor syste::3, multiple,ratlures and impects of common cause failures on systems, both safety and non-safety; ceveitops methodologies to conduct such evaluations; coordinates among all technical review activities to ar 51 eve an overall systen level, integrated review which assures. adequacy of overall design and performance, particularly across system interfaces and the man-machine interface; evaluates ability of all systems and equipment essential to safety to function reliably under all potential environments; makes recommendations l

regarding changes needed to regulatory guidance to correct significant safety concerns developed fran systems interaction evaluations.

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I.

THE DIRECTOR, DIVISION OF HUMAN FACTORS SAFETY Directs and administers evaluations in the operational, ad-ministrative and people-oriented disciplines for nuclear reactor

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applications and for reactor facilities licensed for operation; develops and administers related programs, policies and pro-cedures governing these aspects of the licensing and operation of nuclear reactors.

... The Director, Division of Human Factors Safety, is delegated the authorities defined in Chapter NRC-0123, Subsections' 021,

- 022, 032b and 033b.

THE DEPUTY DIRECTOR, DIVISION OF HUMAN FACTORS SAFETY Assists the Director in the accomplishment of Division functic,ns and acts for the Director in his absence.

i 1.

The Human Factors Engineering Branch performs multi-disciplined reviews and evaluations of. the interaction of systems and equip-ment with humans in the design and operation of nuclear reactors; reviews and evaluates the type, quality and quantity of critical l

process and safety parameter information provided to control room operators; evaluates information and control systems such as display panels and computerized diagnostic systems; participates in the development of guides and regulations pertaining to human factors engineering.

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- 21 2.

The Ocerator Licensing Branch prepares, administers and grades licensing examinations for reactor operators and

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senior operators, certification examinations and annual requalification examinations; develops testing techniques and standards for evaluating candidates in coordination with the Licensee Qualifications Branch; accredits training pro-grams and facilities and audits operator training programs - --

on sinmlators.

3.

The Licensee Oualifications Branch establishes requirenents and qualifications' standards for licensee management, licensed operators and other plant personnel; reviews and evaluates the technical and managerial qualifications for constructing and operating the plant and handling accidents; eval'uates the qualifications and training of all utilit'y and key plant personnel including licensed operators; coordinates with the Operator Licensing Branch.

4.

The Procedures & Test Review Branch reviews and evaluates selected preoperational, startup, operational and emergency operating procedures with respect to design, engineering and operational aspects; evaluates results of significant tests to assure conformance with design and operational requirements; develops guidance on format and content of test pro;edures and repo rts.

. J.

THE DIRECTOR, DIVISION OF SAFETY TECHNOLOGY Directs and administers the Office programs to assure that the Commission's basic safety and environmental policies, goals and requirements are satisfied by the regulatory process.

The Director,' Division of Safety Technology, is delegated the authorities defined in Chapter f RC-0123, Subsections 022, 027, 0211 and 0312. -

1.

The Assistant Director for Generic Projects plans, directs and supervises the programs and activities of the Generic Issues, l

Licensing Guidance, and Research & Standards Coordination Branches and assiets the Director in administering the Division's programs.

a.

The Generic Issues Branch provides full-time dedicated task management of active unresolved safety issues and monitors activities an othei generic issues; prepares an annual report of the status of unresolved safety issues for inclusion in an Annual Report to Congress; develops

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procedures for feedback of generic issue solutions and approaches into the regulatory precess; prepares and issues NUREG reports describing the staff's evaluation of and conclusions for each issue; establishes plans and schedules for implementing solutions on~a plant-by-plant basis; -

23 -

coordinates and monitors he reso'lution of ACRS generic t

issues; coordinates and monitors implementation of the TMI Action Plan and evaluates the results of studies performed in accordance with the Plan; coordinates pre-paration of'the NRR input to the NRC Annual Report to the President's Nuclear Safety Oversight Canmittee.

b.

The Licensing Guidance Branch maintains and updates the standard technical specifications for operating l';ht

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water hower reactors based on new regulatory requimments, new technical considerations and operating experience; pro-j vides guidance and support to project managers in pre-paration of the safety technical specifications portion of~ each new operating license; ensures that custom technical specifications, including changes to technical specifications for operating plants, are maintained con-sistant with standard technical specifications; coordinates updates to the Standard Review Plans and the Standard Fonnat and Content Guide; develops standardized requirements for documentation of the staff's. licensing bases in Safety Evaluation Reports.

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The Research and Standards Coordination Branch provides c.

coordination and cooperation with the Office of Nuclear Regulatory Research (RES) in areas of mutual interest to assure that.S programs are supporting reactor C

licensing needs; reviews all Research Information Letters and coordinates NRR responses; assures that all NRC research reports are reviewed by the NRR staff so 1

that research program results are properly disseminated, evaluated and applied as appropriate thrcughout the NRR reactor licensing program; coordinates review of 'the technical substance of NRR technical assistance contracts for consistency and to avoid duplication internally or with RES programs; monitors participation of NRR staff in Research Review Groups; screens all incoming NRR contractor reports and other documentation to highlight items nee' ding prompt attention; coordinates with the Department of Energy and industry groups in areas of mutual interest; identifies NRR issues for'0ffice of Standards Development (050) task initiation; reviews 050 issuances and coordinates NRR re-sponses.

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2.

The Assistan't Director for Technoloov plans, directs and s nervises the programs and activities of the Safety Pn gram Evaluation, Operating Experience Evaluation, and Reliability & Risk Assessment Branches and assists the Director in administering the Division's programs.

a.

The Safety Procram Evaluation Branch performs a continuing systematic evaluation of the adequacy of regulatory requirements for licensing and operation; provides a technical oversight and quality assurance function for reactor safety' policy implementation, major licensing and other regulatory actions and their documentation; per-fonus analyses of ' relevant new 'information; establishes, maintains and applies a system for assessing safety significance and assignment of priorities for the resolution of new safety issues; provides engineering analyses and support for recommendations by the Division to the Office Director on the value and impact of new regulatory requirements.

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b.

The Oceratine Excerience Evaluation Branch performs continuing systematic assessments of reactor operating

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experience, including occasion &l field audits, with respect.to facility performance and operational safety, l

to detect patterns in abnormal occurrences, to identify precursors of possible hazardous events and to evaluate the adequacy of existing safety factors in design and operation; performs' analysis of other significant events for purposes of identifying significant unre-viewed safety questions; establishes requirements l

l for reporting operating events; defines programs to rectify problems and' improve performance-and safety; provides NRR interface-with the Office for Analysis and Evaluation of Operational Data and coordinates with the Office of Inspection and Enforcement on matters involving operating experience evaluation by NRC and the industry.*

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c.

The Reliability and Risk Assessment Branch performs systematic reliability and risk assessments of nuclear power plants and their systems important to safety, with principal eWhasis on new or potential safety issues; fosters the development and coordinates the use of system l

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