ML19318A520
| ML19318A520 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/02/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 8006230263 | |
| Download: ML19318A520 (35) | |
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UNITED STATES I 7,,.,.,,
j NUCLEAR REGULATORY COMMISSION
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- %. J j' JUN 02 g Docket No. : 50-219 Mr. I. R. Finfrock, Jr.
Vice President - Generation Jersey Central Power & Light Cogany Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960
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 Oyster Creek Nuclear Plant are being coordinated by Mr. Walt Paulson, who is your Project Manager. Mr. Paulson is now a merter 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 disruption to ongoing activities. We hope that this reorganization will igrove both our effectiveness and our lines of comunication 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, f
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Operating Reactors Branch #5 Division of Operating Reactors
Attachment:
As stated cc w/ enclosure:
Sae next page 80062 3 0 M
Mr. I. R. Fi nf rock, J r.
cc G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036
- 380 Scotts Road Trenton, New Jersey 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Mart L. First Licensing Manager Deputy Attorney General 260 Cherry Hill Road State of New Jersey Parsippany, New Jersey 07054 Department of Law and Public Safety Environmental Protection Section Anthony Z. Roisman 36 West State Street Natural Resources Defense Council Trenton, New Jersey 08625 91715th Street, N. W.
Washington, D. C.
20006 Joseph T. Carroll, Jr.
Plant Superintendent Oyster Creek Nuclear Generating Steven P. Russo, Esquire Station 248 Washington Street P. O. Box 388 P. O. Box 1060 Forked River, New Jersey 08731 Toms River, New Jersey 08753 Joseph W. Ferraro, Jr., Esquire Director, Technical Assessment Deputy Attorney General Division State of New Jersey Office of Radiation Programs Department of Law and Public Safety (AW-459) i 1100 Raymond Boulevard U. S. Environmental Protection Newari, New Jersey 07012 Agency Crystal Mall #2 Ocean County Library Arlington, Virginia 20460 Brick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS COORDINATOR Lacey Township 26 Federal Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Consnissioner Department of Public Utilities State of New Jersey 101 Consnerce Street Newart, New Jersey 07102 i
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Office of Nuclear Reactor Regulation Director Ilarold R. Denton Deputy Director Edson G. Case TMI Program Office Planning a Program Analysis Staff Program Director Bernard J. Snyder Director Deputy Vacant Program Director John T. Collins Resource & Scheduling Branch Frank J. Miraglia, Chief f Emergency Preparedness Prugram Office Management Analysis' Branch Program Director Herbert N. Berkow, Chief Brian K. Grimes u.
Technical Support Branch Deputy Program Director
' William T. Russell, Chief -
Vacant
- Emergency Preparedness Licensing Branch Frank G. Pagano, Chief (Acting)
- Emergency Preparedness Developmeat Branch Vacant I
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l Division of Licensing Division of Division of Systems Division of Human Division of Safety Engineering Integration Factors Safety Technology W
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Division of Licensing Director Darrell G. Eisenhut
' Deputy ' Director Rob rt A. Purple i
Assistant Director for Operating Assistant Director for Licensing Assistant Director for Safety Reactors Assessment Thomas M. Novak Robert L. Tedesco Gus C. Lainas Cperating Reactors Branch 1 Licensing Branch 1 Operating Reactors Branc' 5 h
Steven A. Varga. Chief B. Joe Youngblood, Chief
.i Dennis M. trutchfield, Chief
_ Operating Reactors Branch 2
_ Licenst.ng Branch 2
_ Systematic Evriuation Program Branch Thomas A. Ippolito, Chief,
Albert Schwencer, Chief Dennis M. r utchfield, Chief (Acting) e Operating' Reactors Branch 3
- Licensing Branch 3 Operating Reactors Assessment Branch Robert A. Clark, Chief Vacant' r ii *i Vacant
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-Operating Reactors Branch 4 Robert W. Reid, Chief.
- Standardization and Special Projects Branch James R. Miller, Chief i
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Division of Engineering Director Richard 11. Vollmer I
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Assistant Director for Components Assistant Director for Materials &
Assistant Director for Environmental
& Structures Engineering Qualifications Engineering Technology James P. Knight Vincent S. Noonan Daniel R. Muller
-Mechanical Engineering, Branch
-Materials Engineering Branch
- Envimnmental Engineering Branch Robert J. Bosnak, Chief Stefan S. Pawlicki, Chief Ronald L. Ballard, Chief
_ Structural Engineering Branch
_Che:alcal Engineering Branch
_ Siting Analysis Branch Franz P. Schauer, Chief Victor Benamya, Chief William H. Regan, Chief
-Geosciences Branch Equipment Qualification Branch Utility Finance Branch Robert E. Jackson, Chief Zoltan R. Rosztoczy, Chief....
Jerome D. Saltzman,. Chief
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-Hydrologic and Geotechnical Quality Assurance Branch H" f '
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Engineering Branch Walter P. Haass, Chief George E. Lear, Chief e
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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 Paul S. Check William E. Kreger Lester S. Rubenstein
- Instrrentation & Control
- Accident Evaluation Branch
- Reactor Systems Branch Syster; Branch Robert W. Houston, Chief Themis P. Spels, Chief Rodney M. Satterfield, Chief i-
- P6wer Systems Branch
- Radiological Assessment Branch Core Perfonnance Branch Faust Rosa. Chief Thomas D. Murphy, Chief yacant'
- Containment Systems Branch
- Effluent Treatment Systems Branch '
Systems Interaction Branch Walter R. Butler, Chief William P. Ganen111. Chief John F. Stolz. Chief Auxiliary Systems Branch Olan D. Parr, Chief g
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Division of Iluman factors Safety Director Stephen S. llanauer Deputy D' rector Voss A. Moore (Acting)
- Human Factors Engineering Branch Vacant
- Operator Licensing Branch Paul F. Collins, Chief
- Licensee Qualifications Branch Domenic B. Vassallo, Chief
- Procedures & Test Review Branch Dennis L. Ziemann, Chief 4
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Division of Safety Technology Director Roger J. Mattson I
I Assistant Director for Generic Projects Assistant Director for Technology Frank Schroeder Malcolm L. Ernst Genecic Issues Branch Karl Kniel, Chief Safety Program Evaluation Branch
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Robert L. Baer, Chief
--Licensing Guidance Branch Donald J. Skovholt, Chief
__ Operating Experience Evaluation Branch Carl H. Berlinger, Chief (Acting)
--Research & Standards Coordination Branch
- Reliability and Risk Assessment Branch George W. Knighton, Chief Sanford L. Israel, Chief (Acting) e e
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DISTRIBUTION OF FUNCTIONS 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 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,involvir.g facilities exempt from licensing and performs other functions required for implementation of the licensing program.
B.
THE DEPUTY DIRECTOR Assists the Of rector 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 activ4'.tes of the Office.
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THE PROGRM DIRECTOR. TMI PROGRAM OFFICE Provides overall direction of TMI-2 cleanup operations, including technical and management 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 Impact Statement and related assessments, including resources 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 DEPUTY PROGRM 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
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Responsible for directing and managing the evaluation of licensing actions related to emergency preparedness and the NRR effort to upgrade emergency preparedness at and around nuclear power plants. Provides liaison and coordine. tion with the Federal Emergency Management Agency (FEMA) on matters of l
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i 3-interfaces, reviews and policy. Develops policy recommendations in relevant areas including criteria for program adequacy, action level criteria, staffing and equipment requirements, thyroid blocking and accident management _ and data interchange.
THE DEPUTY PROGRAM DIRECTOR, EMERGENCY PREPAREDNESS PROGRAM 0FFICE Assists the Program Director in the accomplishment of Office functions and acts for the Director in his absence.
The Emergency Preparedness Licensing Branch reviews and evaluates emergency plans associated with the applications for nuclear reactor facilities; reviews emergency preparedness 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 Emergency Preparedness Development Branch develops 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 NRC offices, agencies and foreign groups on energency preparedness programs; coordi-nates with FEMA in development of criteria for onsite and off-site emergency preparedness; provides technical support for
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the Emergency Preparedness Licensing Branch.
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THE DIRECTOR, PLANNING & PROGRAM ANALYSIS STAFF Provides administrative management and cQordination 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 perfornance 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.
4 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 maintains data and records on priorities, 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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4 The Management Analysis Branch: manages all personnel administration ratters; performs management and organizational studies and prepares proposals thereon; recommends, prepares and 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 models for analyzing and presenting NRR staff and program support expenditures; manages 15e personnel development and training function; controls and coordinates correspondence, FOIA requests, action items and records management.
The Technical Support Branch:
provides technical coordination and oversight for resolution of special technical problems and those which involve more than one division and other offices; l
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 review, 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 administer!. the licensing process for all utilization and production facilities, other than fuel reprocessing and.
isotopic enrichment plants, including safety and environmental evaluations of po Ar'and non-power reactors required to be licensed and facilities licensed for operation. Directs the evaluations of design, operation and modification of 00E-and 000-owned facilities exempt from licensing, as requested. Directs and supervises the processing of applications and petitions for license 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.
1 The Of rector, 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 accomplishment 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 of the Operatir.g Reactors Branches. Assists the Director in administering the Division's programs.
a.
The Ooerating 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 proposed amendnents to operating licenses.
2.
The Assistant Director for Licensing plans and directs the program for safety and environmental review and evaluation of applications.for limited work authorizations, construction permits, operating licenses, 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, DOE-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 administering the Division's programs.
, The Licensing Br'anches 1-3 perform the overall safety a.
and environmental project management for assigned power reactor limited work authorization, construction permit and operating license applications.
b.
The Standardization and Special projects Branch performs the overall safety and environmental project management for assigned preliminary and final standard design approval, i
early site approval, topical report approval, research and l
test reactor and critical facility applications.
Performs j
similar functions for Naval reactors, advanced reactor concepts and 00E-and D00-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 licensad operating power reactors undergoing systematic re-revice and the technical evaluation of proposed routine operating l
license amendments.
Supervises the programs and activities of the Operating Reactors Branch 5, the Systematic Evaluation Prog-am Branch and the Operating Reactors Assessment Branch.
l Assists the Director in administering the Division's programs.
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The Operating Reactors Branch 5 performs overall coordination and routine project management including safety, environmental and procedural aspects, as well as proposed amendments for i
those operating power reactors which are under re-review as j
i part of NRC's program to systematically evaluate the margins of safety of the design and operation with respect to current licensing requirements.
b.
The Systamatic Evaluation Program Branch provides tae
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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, coordinates the efforts of those technical specialists from other divisions assigned to the SEP program.
c.
The Operating 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 dis;iplines, for power and non-power i
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.
1.
The Assistant Director for Components and Structures Engineering 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.
s a.
The Mechanical Engineering Branch reviews and evaluates seismic and pipe whip design; mechanical design of
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reactor vessels, reactor core supports, reactor fuel components, reactor coolant pumps, steam generators, reactor coolant piping, pressurizers, component supports and other safety-related mechanical components; mistile impacts.
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The Structural Engineering Branch reviews and evaluates missile protection, design and loadings of concrete and steel contain:ents 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 respt:t to the seismological, and geological aspects of the site; I
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 Breach 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 assists in developing programs'to fill these needs.
. 2.
The Assistant Director for Materials & Qualifications Engineering plans, directs and supervises the programs a'nd activities of the Materiais Engineering, Chemical Engineering, Equipment Qualification and Quality Assurance Branches.
Assists the Director in admin'istering the Division's programs.
a.
The Materials Engineering Branch evaluates the materials-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 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; per"orms general technical review, analysis and evaluation of water chemistry management, activity cleanup ara removal systems and process control systems.
c.
The Equioment Oualification Branch evaluates the i
capability of plant systems and components important to safety to function acceptably under all anticipated normal and accident environments including thennal, pressure, moisture, radiation, dynamic and seismic; establishes performance requirements and reviews qualification test programs and results.
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The Quality Assurance Branch reviews reactor license applications and operating license amendments to assure compliance with Commission quality assurance criteria during plant design, ' construction and operation.
3.
The Assistant Director for Environmental Technoloay plans, directs and supervises the programs and activities of the Enviromnental 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.
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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 performs evaluations of suitability of proposed and
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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.
3 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 antitrust matters, and 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-tential anti-competitive activities by applicants; pre-pares relevant testimony; provides technical assistance on economic, engineering and power supply aspects of antitrust cases; 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 i
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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 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 00E-and 000-owned facilities exempt from licensing; develops and administers related safety programs and policies governirq the licensing and operation of nuclear reactors.
The Director, Division of Systems Integration, is delegated the authorities defined in Chapter NRC-0123, Subsections 021a, 022, 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 Systecs,' 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 instrumentation, and control instrumentation; and participates in the development of guides and re'gulations pertaining to instrumentation and control systems.
b.
The Power Systems Bra.1ch reviews the design, fabrication and operation of onsite and offsite electrical power systems and the steam and power conversion systems; l
participates in the developnent of guides and regulations
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pertaining to these systems.
c.
The Containment Systems Branch reviews the design, fabrication and operation of the containment system and L
associated subsystems, including emergency heat removal systems, heating and ventilation, isolation equipment and controls, and combustible gas control systems.
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The Auxiliary Systems Branch 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.
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a.
The Accident Ev'aluation Branch develops models for and performs calculations and evaluations of potential accidents and event scenerios from initiation through consequence mitigation for both safety and environmental evaluations; reviews reactor license and amendment applications, as well as operating data, to evaluate engineered safety features with rerpect 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 Effluent Treatment Systems Branch reviews reactor license applications and amendments, as well as operating data, to evaluate nuclear reactor radioactive waste treatment and management systems, radioactive effluent 4
control and monitoring systems; develops analytical models, assumptions and calculational methods for evalu-i ating the effectiveness of proposed systems; carries out reviews, studies and analyses related to these reviews and development of radioactive waste standards.
' 3.
The Assistant Director for Reactor Systems plans, directs i
and supervises the programs and activities of the ?eactor Systems, Core Perfonnance 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 systens, emergency core cooling systems and 4
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 evaluatet the effects of severe accidents, including core de-gradation.and melt accidents, on reactor designs; evaluates means for mitigating the effects of such accidents.
.. b.
The Core Performance Branch reviews and evaluates the nuclear, thermal, hydraulic and reactor fuel aspects of nuclear reactor design and performance 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 evaluations of overall plant design and performance, including integration among major systems, multiple failures and impacts of comamn 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 from systems interaction evaluations.
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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, Nvision of Human Factors Safety, is delegated the authorities defined in Chapter NRC-0123, Subsections 021, 022, 032b and 033b.
l THE DEPUTY DIRECTOR, DIVISION OF HUMAN FACTORS SAFETY Assists the Director in the accomplishment of Division functions l
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 humans in the design and operation of nuclear reactors; reviews and evaluates the type, quality and quantity of critical process and safety parameter infomation provided to control room operators; evaluates infomation 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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The Operator Licensing Branch prepares, admin't? ers and grades licensing examinations for reacter 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 i
the Licensee Qualifications Branch; accredits training pro-grams and facilities and audits operator training programs on simulators.
3.
The Licensee Qualifications Branch establishes requirements and qualifications standards for licensee management, licensed i
operators and other plant personnel; reviews and evaluates the technical' and managerial qualifications for constructing and operating the plant and handling accidents; evaluates 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 4
. to assure conformance with design and operational requirements; develops guidance on format and content of test r ocedures and reports.
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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 prcgrams.
a.
The Generic Issues Branch provides ful.1-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
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for inclusion in an Annual Report to Congress; develops procedures for feedback of generic issue solutions and f 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; l
coordinates and monitors the resolution of ACRS generic 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 Committee.
b.
The Licensing 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 updates 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 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 t*RR 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 i
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 Office of Standards Development (OSD) task initiation; reviews OSD issuances and coordinates NRR re-sponses.
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The Assistant Director for Technology plans, directs and supervises the programs and activities of the Safety Program Evaluation, Operating Experience Evaluation, and Reliability & Risk Assessment Branches and assists-the Director in administering the Division's programs.
a.
The Safety Program 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-forms analyses of relevant new information; establishes, neintains 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 < >lue and impact of naw regulatory requirements.
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b.
The Operating Experience Evaluation Branch performs continuing systematic assessments of reactor operating experience, including occasional field audits, with respect to facility performance and operational safety,
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to detect patterns in abnormal occurrences, to identify precursors of possible hazardous events and to tvaluate 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 interf ace 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.'
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 emphasis on new or potential safety issues; fosters the development and coordinates the use of system l
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reliability models, common mode failure analysis and other probabilistic techniques in nuclear reactor regulation;
- identifies high risk accident sequences for consideration in new regulatory requirements or evaluation of existing requirements; applies probabilistic risk assessment to the analysis of new safety requirements, priority setting for resource allocation or ather use of measures of safety significance; coordinates training of NRR reviewers in reliability methods; coordinates NRR efforts in this area with other elements of the RES Probabilistic Assessment Staff and the Integrated Reliability Evaluation Program.
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