ML19318B629
| ML19318B629 | |
| 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 8006270235 | |
| Download: ML19318B629 (34) | |
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[ *,,,, y.S.i NUCLEAR REGULATORY COMMISSION UNITED STATES
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JUN 0 2 to80 Docket No. : 50-155 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Cogany 212 West Michigan Avenna 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 Manager.
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 minitrum of disruption to ongoing activities. We hope that this reorganization will igrove both our effectiveness and our lines of cormunication sith 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, Dennis M. Crutchfield, Ch' Operating Reactors Branch #5 Division of Operating Reactors
Attachment:
As stated cc w/ enclosure:
See next page THIS DOCUMENT CONTAINS P00R QUAUTY PAGES 8006270 M b f
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e Mr. David P. Hoffman CC Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigar 49201 Region Y Office ATTN: EIS COORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Conpany 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 Commission Isham, Lincoln & 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 Commission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Sheldon, Harmon and Weiss U. S. Nuclear Regulatory Commission 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 Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chai rman 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 Crystal Mall #2 Arlington, Virginia 20460
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Office of Nuclear Reactor Regulation Director i
liarold R. Denton l
Deputy Director Edson 6. Case l
l TMI Program Office Planning & Program Analysis Staff Program Director Bernard J. Snyder Director
- Vacant Deputy
.n Program Director John T. Collins
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Resource & Sclieduling Branch Frank J. Miraglia, Chief d
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'g-i Emergency Preparedpess Program Office Management Analysis ' Branch
~. Ilerbert N. Berkow, Chief Program Director
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Brian K. Grimes Technical Support Branch
~Willjam:T. Russell, Chief 5
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Deputy Program Director l
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Vacant
- Emergency Preparedness Licensing Branch FrankG.Pagano, Chief (Acting)
Emergency Preparedness Development Branch Vacant.
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l Division of Licensing Division of Division of Systems Division of Iluman Division of Safety Engineering Integration factors Safety Technology 4
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4 Division of Licensing Director Darrell G. Eisenhut
'Depu'ty ' Director Robert A. Purple i
Assistant Director for Operating Assistant Director for Licensing Assistant Director for Safety i
Reactors Assessment Thomac M. Novak Robert L. Tcdesco Gus C. Lainas Operating Reactors Branch 1
- Licensing Branch 1 Operating Reactors Branch 5 B. Joe Youngblood, Chier
- Dennis it. Crutchfield, Chief Steven A. Varga, Chief
_ Operating Reactors Branch 2
._ Licensi,ng Branch 2
._ Systematic Evaluation Program Branch Thomas A. Ippolito, Chief
- Albert Schwencer, Chief Dennis M. Crutchfield, Chief (Acting)
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i Operating Reactors Branch 3 Licensing Branch 3 Operating Reactors Assessment Branch l
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- ie: 'i n i' q Vacant Robert A. Clark, Chief Vacant'
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i Standardization and Special Operating Reactors Branch 4 Robert W. Reid. Chief '
l Projects Branch
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James R. Miller, Chief t
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Division of Engineering Director Richard it. Vollmer I
I Assistant Director for Environmental Assistait Director for Components Assistant Director for Materials &
& Structures Engineering Qualifications, Engineering Technology James P. Knight Vincent S. Noonan Daniel R. Muller
'-Mechanical Engineering Branch Materials Engineering Branch '
--Environmental ' Engineering Branch Robert J. Bosnak, Chief d Stefan'SL Paw 11cki, Chief Rona,ld L. Ballard, Chief
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_ Structural Engineering Branch
_ Chemical Engineering Branch
. Siting Analysis Branch Franz P. Schauer; Chief Victor Denaroya, Chler William 11. Regan, Chief
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~~Geosciences Branch
'-Equipment Qualification Branch
~~ Utility Finance Branch
' Robert E. Jackson, Chief' '
Zoltan R. Rosztoczy, Chief Jerome D. Saltzman,, Chief
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'llydrologic and Geotechnical
. Engineering Branch Walter P. Haass, Chief
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George E. Lear, Chief l'i' l
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Division of Systems Integratfor Director Denwood F. Ross I
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Assistant Director for Assistant Director for Assistant Director for Plant Systems Radiation Protection Reactor Systems William E. Kreger
- f. ester S. Rubenstein Paul S. Check
- Instrumentation & Controit
- Accident Evaluation Branch
- Reactor Systems Branch Systems Branch Robert W. llouston, Chief Themis P. Spels. Chief
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Rodney M. Satterfield, Chief j
- Power Systems Branch
- Radiological Assessment Branch
- Core Performance Branch Faust Rosa. Chief Thomst D. Murphy, Chief Vacant Containment Systems Branch
- Effluent Treatment Systems Branch '
Systems Interaction Branch
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Walter R. Dutler, Chief William P. Ganent11. Chief John F. Stolz, Chief Auxiliary Systems Branch 01an D. Pu r Chief I
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Division of Iluman factors Safety
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Director Stephen S. llanauer Depu'ty Director Voss 4. Moore (Acting) d
- lluman Factors Engineering Branch I "' ** } ' ' '
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- Operator Licensing Branch
,i-Paul F. Collins, Chief
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- Licensee Qualifications Branch I !: ' ' 3' ' 'A I ' ' ' " I Domenic B. Vassallo, Chief
'l il Procedures & Test Review Branch Dennis L. Ziemann, Chief
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i Division of Safety Technology Director Roger J. Ma'ttson I
i Assistant Director for Generic Assistant Director for Technology Projects Frank Schroeder Malcolm L. Ernst
-Generic Issues Branch Safety Program Evaltation Branch Karl Kniel, Chief Robert L. Baer, Chief
-Licensing Guidance Branch
_0perating Experience Evaluation Branch Donald J. Skovholt, Chief Carl 11. Berlinger, Chief (Acting)
Research & Standards Coordination Branch Reliability and Ris'e Assessment Branch George W. Knighton, Chief Sanford L. Israe'., Chief (Acting)
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DISTRIBUTION OF' FUNCTIONS A.
THE DIRECTOR 1.
Develops and administers regulations, policies, and procedures goveriang:
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 c.
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 from licensing and performs Jther functions required for implementation of the licensing program.
B.
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 tne absence of the Director, acts for the Director with full and complete responsibility for the activities of the Office.
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THE PROGRAM DIRE; TOR TMI PROGRAM OFFICE Provides overall direction of TMI-2 cleanup operations, including technical and canage. 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 Programnatic Environmental Icpact Statement and related assessments, including rescurces for ir.-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 DEPUTY 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.
D.
THE PROGRAM DIRECTOR, EMERGENCY PREPAREDNESS PROGRAM OFFICE Responsible for directing and managing the evaluation of licensing actier.s related to emergency preparedness and the NRR effort to u; grade emergency preparedness at and around nuclear power plants.
Provides liaison and coordination with the Federal Emergency Management Agency (FEMA) on matters,f
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1 interf aces, reviews and policy.
Develops policy reco=mendations in relevant areas including criteria for program adequacy, action level criteria, staffing and equipment requirements, thyroid j
blocking and accident management and data interchange.
THE DEPUTY PROGRAM OIRECTOR, EMERGENCY PREPAREDNESS PROGRAM OFFIC,E Assists the Program Director in the accomplishment of Office functions and acts for the Director in his absence.
The Emercency Preoaredness Licensino Branch reviews and evaluates emergency plans associated with the applications for nuclear reactor facilities; reviews emergency prepare! ness evaluations of state and local emergency plans performed by~ FEMA; coordinates the reviews of emergency preparedness areas under joint con-sideration by NRC and FEMA.
The Emeroency Precaredness Development Branch develo'ps and evaluates policy recommendations and regulatory requirements for energency preparedness; develops evaluation criteria for I
use in licensing; identifies needs for relevant guides and standards; provides liaison with other NRC offices, agencies and foreign groups on emergency preparedness programs; coordi-t nates with FEMA in development of criteria for onsite and off-site emergency preparedness; provides technical support for the Emergency Preparedness Licensing Branch.
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THE DIRECTOR, 3LANNING & PROGRAM ANALYSIS STAFF Provides administrative management and egordination of the programs and resources of the Office.
Establishes priorities, schedules and resource allocations; establishes interdisciplinary teans and task forces from the divisions; performs resource forecasting, long and short-range program planning, budget preparation and coordination, resource control and performance auditing, fiscal analysis, management and control. Provides administrative and management support including personnel ranagement, management studies, management directives, personnel development 'and training, correspondence and action item l
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.
l The Resources and Scheduling Branch: develcps and maintains data and records on prior' ties, schedules and assignments of NRR resources i
and of the status of all projects and tasks; performs long and short-range program planning, resource forecasting, budget preparation and coordination, canpower and program support resource management, auditing of perforcance against established goals and objectives.
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. The Manacement Analysis Branch: manages all personnel adrainistration ratters; performs management and org'anizational studies and prepares proposals thereon; reccmmends, prepares arid reviews management and administrative operating procedures, policies and directives; im-plements procedures for fiscal control of all program. support and travel resources; develops and implements procedures and undels 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 Succort Branch:
provides technical coordination and 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 rebew, coordination, allocation and management of the NRR technical assistance program including 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 facilities, other than fuel reprocessing and.
isotopic enrichment plants, including safety and environmental evaluations of power ~ and non-power reactors required to be licensed and facilities licensed for operation.
Directs the evaluations cf design, operation and modification of DOE-and DOD-owned f acilities exempt from licensing, as requested. Directs and supervises the processing of applications and petitions for license amendments for all licensed reactor facilftfes. 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, 025, 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 accomplish:ent of Division functions and acts for the Director in his absence.
1.
The Assistant Director for Ooerating 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 of the Operating Reactors Branches. Assists the Director in administering the Civision's programs.
a.
The Oceratina Reactors Branches 1-4 perform the.overall safety and environmental project management for assigned licensed operating power reactors, including review of technical and procedural aspects involving p' reposed amendnents to operating licenses.
2.
The Assistant Director for Licensing plans and directs the program for safety and environmental review and evaluhtion of applications for limited work authorizations, construction permits, operating license ~s, preliminary 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 frem licensing, and advanced reactor concepts. Supervises the programs and activities of the Licensing and Standardization & Special Projects Branches.
Assists the Director in administering the Division's programs.
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The Licensir.; 3 ranches 1-3 perform the overall safety and envircrc.ar al project management for assigned power reaeter limited work authorization, construction permit and operating license applications.
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The Standardization and Soecial projects Branch performs the overall safety and environmental project management for assigned preliminary and final standard design approval, early site ap;reval, topical report approval, research and 1
test reactor and critical facility applications.
Performs similar funecions for Naval reactors, advanced reacter concepts and COE-and 000-owned facilities exempt from licensing.
Provides the NRR interf ace 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 reviews of licensed operating power reactors undergoing systematic re-review and the technical evaluation of proposed routine operating l
license amendeents.
Supervises.the programs and activities j
of the Operating Reactors Branch 5, the Systematic Evaluation l
Program Branch and the Operating Reactors Assessment Branch.
Assists the Director in administering the Division's programs.
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The Ocerating ' 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 systematically evaluate the margins of safety of the design and operation with respect to current t
licensing requirements.
b.
The Systematic Evaluation Procram 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.
c.
The Ocerating Reactors Assessment Branch provides inter-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 reactor applications, for reactor facilities 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 operation of nuclear reactors.
The Director, Division of Engineering, is delegated the authorities defined in Chapter NRC-0123, Subsections 021a', 022, 023, 024, 025, 026, 036, 037, and 0311.
The Assistant Director for Components and Structures Engineering 1.
plans, directs and supervises the programs and' activities of the Mechanical Engineering, Structural Engineering, Geosciences and Hydrologic & Geotechnical Engineering Branches.
Assists the Director in administering the Division's programs.
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, pressurt:ers, component supports and other safety-related mechanical components; missile 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 struc'tures.
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 research 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 operational 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 I
assists in developing programs to fill these needs.
. 2.
The Assistant Cirector for Materials & Oualifications Engineering plans, directs and supervises the programs and activities of the F.aterials Engineering, Chemical Engineering, Equipment Qualification and Quality Msurance Branches.
Assists the Director 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, fabrica' tion, inspection and testing of nuclear power reactor ccmponents and systems.
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The Chemical 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 managemen't, activity cleanup and removal systems and process control systems.
c.
The Eouioment Qualification Branch evaluates the capability of plant systems and components important to safety to function acceptably under all anticipated normal and accident environments including thermal, pressure, moisture, radiation, dynamic and seismic; establisu.s performance requirements and reviews qualification test programs and results.
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The Ouali'.y Assurance Branch reviews reactor license applications and operr. ting license amendments to assure compliance with Commission quality assurance criteria during plant design, construction and operation.
3.
The Assistant Director for Environmental Technology plans, directs and supervises the programs and acti rities of the Environmental Engineering, Siting Analysis and Utility Finance Branches.
Assists the Director in administering the Division's programs.
a.
The Environmental Engineering Branch provides specialized technical capabilities in the areas of water 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 new 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.
b.
The Sitina Analysis Branch evaluates risks associated with nearby industrial, transportation and military facilities; performs demographic and other site characteristic studies; develops criteria for and perforns 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-economic impacts of nuclear power plants.
c.
The Utility Finance Branch establishes and administers l
those delegated NRC functions required to implement antitrust reviews of license applications for nuclear facilities, including responsibility for compliance with license conditions pertaining to antitru'st matters, and those functions related to indemnification of licensees i
l against public liability claims arising out of nuclear f
l incidents; reviews, investigates and evaluates power supply, inter-system ccordination and existing and po-l tential anti-competitive activities by applicants; pre-l l
pares relevant testimony; provides technical assistance l
'on economic, engineering and power supply aspects of antitrust cases; assists in fomulation 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.
. The Chief, Utility Fina.n.ce Branch, is delegated the 4
authority contained in Chapter NRC-0123, Subsections 024, 035 and 037.
H.
THE DIRECTOR, DIVISION OF SYSTEMS INTEGRATION Directs 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 00D-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 03'11.
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The Assistant Director for Plant Systems plans, directs and supervises the progams and activities of the Instru-mentation & Control Systems, Power Systems, Containment Systems and Auxiliary Systems Branches and assists the
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Director in administering the Division's programs.
a.
The Instrumentation and Control Systems Branch reviews and evaluates the design, fabrication, and eperation of
, reactor protection and safety instrucentation, and control instrucentation; and participates in the development of guides and regulations 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 pertaining to these systems.
c.
The Containment Systems Branch reviews the design, fabrication and operation of the contaimnent system and associated subsystems, including emergency heat removal 4
systems, heating and ventilation, isolation equipment and controls, and combustible gas control systems.
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The Auxiliary Systens 3 ranch reviews the design, fabrication and operation of auxiliary systems.
2.
The Assistant Director for Radiation Protection plans, 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
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and event scenerios fran initiation through consequence mitigation for both safety and enviramnental 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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The ~ffluent Treatment Systems Branch reviews reactor license applications and amendments, as well as operating data, to cvaluate nuclear reactor radioactive waste treatment and management systems, radioactive effluent f
control and monitoring systens; develops analytical l
models, assumptions and calculational methods for evalu ating the effectiveness of proposed systems; carries out i
reviews, studies and anal'yses related to these reviews and deve?.oprent of radioactive waste standards.
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The Assistant Director for Reacter Systems plans, directs and supervises the programs and activities of the Reactor Systems, Core Performance and Systems Interaction Branches and assists the Director in administering the Division's programs.
a.
The Reactor Systems Branch reviews and evaluates the design and performance of reactor thermal-hydraulic systems, reactor coolant systems, emergency core cooling systems and associated auxiliary systems; reviews, analyzes and evaluates cal'ulational methods used by applicants and licensees in e
i these areas; develops and uses independent calculational methods for analyzing performance of these systems under steady-sta e, 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.
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The Core Per'formance Branch reviews and evaluates the nuclear, thermal, hydraulic and reactor fuel aspects of nuclear reactor design and performatice reviews, analyzes and evaluates calculational methods used by applicants in
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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 evaluations of overall plant design and performance, including integration anong major systems, multiple, failures and impacts of common cause failures on systems, both safety and non-safety; develops methodologies to conduct such evaluations; coordinates among all technical review activities to achieve an overall system 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 regarding changes needed to regulatory guidance to correct significant safety concerns developed fran systems interaction evaluations.
. I.
THE DIRECTOR, DIVISION OF HUMAN FACTORS SAFETY Directs and administers evaluations in the operational, ad-ministrative and people-oriented disciplines for nuclear reactor 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 functio,ns and acts for the Director in his absence.
1.
The Human Factors Engineering Branch performs multi-disciplined reviews and evaluations of the interaction of systems and equip-ment with hunans in the design and operation of nuclear reactors; i
reviews and evaluates the type, quality and quantity of critical process and safety parameter information provided to control roem operators; evaluates informa' ion and control systems such t
as display panels and ccmputerized diagnostic systems; participates in the development of guides and regulations pertaining to human factors engineering.
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The Ocerator Licensino 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 sir slators.
3.
The Licensee Oualifications Branch establishes requirements 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; evaTuates the qualifications and training of all utility 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
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to assure conformance with design and operational requirements; l
develops guidance on format and content of test procedures and l
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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 NRC-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, Licensing Guidance, and Research & Standards Coordination Branches and assists 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 on other generic issues; prepares an annual report of the status of unresolved safety issues for inclusion in an Annual Report to Congress; develops procedures for feedback of generic issue solutions and approaches into the regulatory process; 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;
4 coordinates ~ and monitors he resolution of ACRS gen'eric t
issues; coordinates and monitors implementation of the TMI Action Plan and evaluates the results of studies
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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 Licensinc Guidance Branch maintains and updates the standard technical specifications for operating light water power reactors based on new regulatory requirements, new technical considerations and operating experience; pro-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-sistent with standard technical specifications; coordinates update-to the Standard Review Plans and the Standard Format 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 RES programs are supporting reactor licensing needs; reviews all Research Information Letters and coordinates NRR responses; assures that all NRC research reports are reviewed by the NRR staff so that research program results are properly disseminated, evaluated and applied as appropriate throughout the NRR reactor licensing program; coordinates review of the technical substance of NRR technical assistance contracts for consistency and to avoid duplication internally or I
with RES programs; monitors participation of NRR staff in Research Review Groups; screens all incoming N'RR 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 Office of Standards Development (OSD) task initiation; reviews 050 issuances and coordinates NRR re-l sponses.
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The Assistan't Director for Technology plans, directs and supervises the programs and activities of the Safety Program Evaluation, Operating ~ :perience Evaluation, and Reliability & Risk Assessment Branches and assists the Director in administering the Division's programs.
a.
The Safety Program Evaluation Branch performs a
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continuing systematic evaluaticn 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-forms 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 Experience Evaluation Branch performs continuing systematic assessments of reactor operating experience, including occasional field audits, with respect.to facility performance and operational safety, 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 for reporting operating events; defines programs to rectify problems and' improve performance-and safety; provides NRR interface-with the Office for An.iysis 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.-
c.
The Reliability and Risk Assessment Branch performs syster.atic reliability and risk assessments of nuclear power plants and their systems important to safety, with principal emphasis on new or potential safety issues; fosters the development and coordinates the use of system 1
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