RBG-17-067, Forwards Response to Informal Questions Re FSAR Chapter 13 Raised by Licensee Qualification Branch Based on Review of .Info Necessary to Complete Input to SER

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Forwards Response to Informal Questions Re FSAR Chapter 13 Raised by Licensee Qualification Branch Based on Review of .Info Necessary to Complete Input to SER
ML20080S405
Person / Time
Site: River Bend  Entergy icon.png
Issue date: 02/17/1984
From: Booker J
GULF STATES UTILITIES CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RBG-17-067, RBG-17-67, NUDOCS 8402290089
Download: ML20080S405 (93)


Text

-

l O l GULF ~ STATES UTILITIES COMPANY POSTOFFICE GOX 2951

  • BEAUMONT, TEXAS 7'704 AREA COOE 409 838 6631 February 17, 1984 RBG- 17,067 File No. G9.5 Mr. Harold-R. Denton,-Director Office of Nuclear Reactor Regulation U. S.: Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

River Bend Station - Units 1 & 2 Docket Nos. 50-458/50/459 Enclosed are Gulf States Utiliti,es Company's (GSU) responses to

the informal questions raised by reviewers from the Licensee Qualification Branch (LQB-RIV) based upon their review 'of the December 2,1983-docketed letter from Mr. Booker t6 Mr. Denton. As a result of meetings'between GSU and LQB-RIV on January 6, 1984, further clarifications with regard to the Final Safety Analysis Report (FSAR),

Chapter 13, were necessary to complete input to the Safety Evaluation Report (SER). Attachment 1 summarizes-these clarifications and references where the response is provided. Enclosure 1 provides the changes to-the FSAR which will be included in the next amendment.

Sincerely,

. Y.

J. E. Booker Manager - Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group Attachment Enclosure I

l

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  • 8402290089 840217 PDR ADOCK 05000458 E PDR

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Attachment 1 i

Item No. 1 Corporate Organization The Staff requested a sufficiently detailed description of the corporate organization to understand the position of individuals and organizations which interface with-or provide technical

' support for the nuclear group.

See revised Section 13.1.1.1.3 and Figure 13.1-la.

Item No. 21 Nuclear Operations Organizations The Staff requested FSAR organizational- charts and text to fully described the Nuclear Operations organization, including the Training Staff's size and minimum qualifications.

See revised Section 13.1.1.2.1.3 and Figures 13.1-2a and 13.1-2b for_ descriptions of the Nuclear Operations organization; the

-Training Staff's minimum qualifications will be addressed in a future submittal.

-Item No. 3 Radiation Protection Technician Qualifications The Staff requested that the Radiation Protection Technicians meet the minimum requirements of the Radiological Assessment Branch.

The response to Question 471.21 on Page Q&R13.1-1 as contained in Amendment 11 stipulates the minimum qualifications for the Radiation Protection / Chemistry Supervisor and the Radiation Protection Superviscr-(see Appendix 13A for the Radiation Protection / Chemistry Supervisor's resume - the posiiton or

' Radiation Protection Supervisor has not yet been filled.) GSU will attempt to hire ANSI qualified Radiation Protection

- Technicians, or technicians with 3 years of Radiation Protection experience as defined in ANSI /ANS 3.1-1978. In addition, GSU requires ~ Radiation Protection Technicians to have 4 weeks of commercial power plant experience at greater than 20% power and refueling experience at a BWR. If these additional requirements are not met, GSU will send the technicians (s) to an operating BWR to obtain the necessary experience.

Item No. 4 Fire Brigade Leader 1The Staff requested that another individual, knowledgeable in plant' systems, other than'the Control Operating Foreman, be designated Fire Brigade Leader.

See-revised Sections 9B.4.8, 13.1.2.2.6, and 13.1.2.2.7.

Item No. 5 Technical Support-The Staff requested additional specificity with regard to the organization of corporate resources to provide technical support to the plant, including staffing levels, and minimum qualification requirements.

e

(

i

'The off-site technical support for River Bend Station (RBS) is described in revised Section 13.1.1.1.3 with additional specificity provided in Sections 13.1.1.2.1.4.1 through 13.1.1.2.1.4.4. Operational staffing levels are included in revised Figure 13.1-4, while minimum qualification requirements are delineated in.Section 13.1.1.3.1.

Item No. 6 Availabic Offsite Expertise The Staff requested additional information concerning offsite technical expertise in the areas of chemistry / radiochemistry and health physics, further details regarding drawing update and revision support, and delineation of responsibilities regarding

' disposal of spent fuel and high level wastes.

See revised. Sections' 13.1.1.1.3 (Offsite Expertise and Drawing Support) 13.1.1.2.1.3.3 (Drawing Support) and 13.1.1.2.1.4.4 (Disposal of Spent Fuel-and Wastes).

Item No. 7 Independent Safety Engineering Group The staff requested that the Independent Safety Engineering Group (ISEG)-be located onsit2, but report directly offsite to a corporate official, holding a high level, technically oriented position not'in the management chain for power production.

See. revised Section 13.4.3.

Item No. 8 Quality Assurance Organization The Staff requested an organization chart showing the numbers and types of QA personnel normally assigned onsite.

See the revised response to Question 260.1 and Figures 13.1-1 and 17.2-1.

Item No. 9 Minimum Qualification Requirements The Staff requested that the minimum qualification requirements for classes of personnel responsible for the technical support of the plant.be delineated.

Commitment to ANSI /ANS 3.1-1978 is provided in 13.1.1.3.1 and 13.1.3.1 for the'offsite and onsite staffs respectively. The minimum qualifications for the Quality. Assurance Department will ebe submitted to the Staff in'a future submittal.

Item No.~10 Resumes The Staff requested resumes for all principal members of the plant staff and of the corporate staff who provide technical support to the plant.

See revised FSAR Appendix 13A. Additional resumes for the Quality Assurance will be supplied to the Staff in a future submittal.

4

' Item No. 11 ~ Training Contact Hours

.The Staff: requested that GSU specify the minimum number of contact hours of training in heat transfer, thermodynamics, and fluid flow for~1icense candidates.

GSU will submit this information in a future submittal.

Item No. 12'. Adequacy'of STA Training

, .The _ Staff requested information to confirm STA adequacy by providing:

~

z a .~ 1Dua number of semester hours of college level instruction provided and the basis.for selecting the course.

b. Confirmation that the training was conducted by an accredited institution and'will be so conducted in the future.

~

~GSU will. submit this information in a future' submittal.

lltem No. 13 'Research Reactor Training

~

-The Staff.requeste1 an operator training program which either meet 1 Appendix A to ANSI /ANS 3.1-1978 or-provide acceptable justification for. variations.

GSU will submit this information in a future submittal.

-Item No. 14 ~ Assistant Plant Managers Training The Staff requested better-definition of the training and qualifications of the Assistant Plant Manager - Operations and the Assistant Plant Manager - Services.

'GSU will submit this information'in'a future submittal.

Item No.-15 Fire Protection Training

~

.The Staff' requested a description of the training programs

_provided for the Fire Protection Staff and for the Offsite Fire Departments.

GSU will submit.this information in a future submittal.

Item No. 16 STA. Management Training The Staff requested GSU show the equivalency of STA training in

~ Management / Supervisory skills and Administration, or provide justification for difference.

GSU will srbmit this information in a future submittal, itme No. 17 Radiation Protection Training.

The Staff requested GSU define the training program for radiological protection, chemistry, and maintenance personnel.

l GSU will submit this information in a future submittal.

Item No. 18 Procedures Training The Staff requested GSU define a program covering training in job-related procedures and instruction.

GSU will submit this information in a future submittal.

~ Item'No. 19 Conformance to Regulatory Guide 8.13.

f' .

The Staff requested a training program to indoctrinate female a employees, their supervisors, and co-workers in the dangers of prenatal radiation exposure in accordance with Regulatory Guide 8.13.

GSU will submit this~information in a future submittal.

Item No. 20 Facility Rcelew Committee llus Staff requested instrumentation and controls expertise on the

. Facility Review Committee.

See revised Section 13.4.1.1.

Item No. 21 ~ Nuclear Review Board 7.,

The Staff requested expertise in the areas of chemistry / radiochemistry and radiological controls on the Nuclear Review Board.

See revised Section 13.4;2.1.

Item No. 22. Emergency Preparedneas Program

'The Staff requested the emergency preparedness program be audited at-least once every 12 months.

See revised Section.13.4.2.7.

.=

RBS FSAR

e7 taken to locate the compressor in areas free of dust and

<e contaminants.

RIVER BEND STATION POSITION The site fire brigade is trained and equipped to ensure an adequate manual fire fighting capability for protection of safety-related structures, systems, and components. Five /

DELETE AND members of each shift (khe Control Operations Foreman, twa REPLACE WITH { Nuclear Equipment Operators, one Chemistry Technician. and INSERT 1 t are one Test Technician-Nuclead) required have fire brigade duties and to pass an Annual physical examination. The AND

[ Control Operations Foremadi acts as fire brigade leader and I CE WITH MSERT 2 informs the Shift Supervisor from the scene of the fire.

The fire brigade leader understands the effects of fire and fire suppressants on safe shutdown capability (two ad-ditional brigade members possess similar knowledge).

Turnout coats, boots, gloves, hard hats, portable hand lights and extinguishers are provided for fire brigade members. Page party /public address (PP/PA) equipment is avLilable for. emergency communications. In the main control room 10 full-face, positive pressure, self-contained breath-ing apparatuses (SCBA), and 3 spare air bottles per SCBA are provided for fire brigade use. Each SCBA supplies one in-dividual for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during moderate exertion. Routine (hg',

. replenishment is available through a casade system located onsite with offsite replenishment available through com-pressed gas suppliers in the Baton Rouge area.

9B.4.9 Fire Brigade Training (Item III.I of Appendix R)

The fire brigade training program shall' ensure that the capability to fight potential fires is established and maintained. The program shall consist of an initial class-room instruction program followed by periodic classroom instruction, fire fighting practice, and fire drills. .

.1 . Instruction

a. The initial classroom instruction shall include:

l l

Amendment 4 9B.4-7 June 1982 b[ .

. y 7

Insert I for Page 98.4-7 a Nuclear Control Operator, two Nuclear Equipment Operators or one Nuclear. Control Operator.and one Nuclear' Equipment Operator depending on shift experience,.one Test Technician - Nuclear, and one Chemistry

' Technician or Radiation Protection Technician but not both.

Insert 2 for Page 9B.4-7 Nuclear Control Operator a

r 2

S e

y RBS FSAR

g The Emergency Planning section directs the preparation of

'Fgf the necessary emergency plans for RBS to assure that the federal, state, and local regulatory requirements for licensing and operating the nuclear generating facility are met in a timely fashion.

The Nuclear Fuels section coordinates, monitors, and directs (1) GSU contracts and activities for procurement, it conversion, enrichment, and fabrication of uranium fuels; (2) spent fuel, high level, and low level waste disposal programs; (3) material safeguards programs; and (4) incore fuels management programs.

The Power Plant Engineering and Design Group (supporting g,_GSU's fossil clants) is an inhouse orannization vailable to the River Bend Nuclear Group (Fig. 13.1 ). Whenever additional expertise or resources are required, GSU's Power Plant Engineering and Design Group or outside consultants are contacted.

INSERT 1 r Since GSU has only one nuclear project, the River Bend Nuclear Grot) (RBNG) was formed to concentrate the company's expertise on RBS. Therefore, there are no plans for offsite technical support in the areas of chemistry / radiochemistry, health physics, and fueling and refueling ope r ativ.~.-

support. It is GSU's contention that these areas are f,71 capably handled by the onsite organization as delineated in

\5i Section 13.1.2. However, the Department of Nuclear Plant

' Engineering does have technical staff available/for input in' DELETE AND these areas as required. This support is available on an 11 REPLACE WITH individual-problem area basis as specified by the Diractor-INSERT 2 Nuclear Plant Engineerino.

13.1.1.2 Organizational Arrangement 13.1.1.2.1 General Fig. 13.1-1 depicts an organization chart for the Corporate Structure; Fig. 13.1-2 depicts an organization cnart for Plant Operations; Fig. 13.1-3 depicts an organization chart for Project Management present only during construction; Fig. 13.1-4 depicts an organization chart for additional technical support; and Fig. 13.1-5 depicts an organization chart for unit shift staffing of Unit 1 during operations.

11 GSU is committed to providing the necessary fire protection for RBS during construction, startup, and operation.

Administrative controls and procedures exist which ensure safe,- reliable activities at RBS. Additional details regarding fire protection at River Bend Station can be found Amendment Il 13.1-9 January 1984 c.

A

i.

Insert 1 for;Page 13.1-9

'The-Department of Technical Services provides operational drawing support to River Bend Nuclear Group when requested.

~ Insert 2 for.Page 13.1-9

- in.these areas within the Department of Nuclear Plant Engineering'on an individual-problem area basis, or'available within other

- departments such as Emergency Planning and Nuclear Fuels. In addition,;outside consulting organizations are available to support

- Nuclear Plant Engineering if. required.

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a 4 n

, RBS FSAn t'

s 16 . ' Direct the operations staff of the River Bend- .

.-k < bkj- =

Station facility.

7. Direct contract management and procurement of )

materials, equipment, and services excluding nuclear fuel.

" 11 8.- Direct. Nuclear Training which plans, administers,

-and documents all nuclear-related training required for the startup and operation of River Bend  :

Station.

11NSERT 5-13.1.1.2.1.4- Manager-Engineering, Nuclear Fuels and Licensing

[ Construction Organizational Strtetur The' Manager-Engineering, ' Nuclear Fuels and Licensing, is

' responsible for the administration of the Nuclear . Licensing,

,  ; Emergency . Planning, Nuclear Fuels, and Nuclear Plant Engineering Sections. His supervision ensures that the

, ,necessary licenses are obtained in compliance with pertinent regulations; emergency plans are adequate, effective, and" up-to-date .to ensure the safety of the public and plant 13 personnel; are made to support schedules; . nuclear in-core fuel procurements fuel' management programs are adequate;

< ,6!3i and . engineering support 'for design, construction, and

("$"

  • operations is available and commensurate with the changing .

needs of.RBS. =His principal duties include

1. Directly prepare and submit.all supportive data for

.RBS nuclear licenses'and permits and speci fically assure the. collation and- submission 'of data to "

support'the application for the operating license. -

9 2 -Review and analyze propose'd design changes

- '(specifications cand drawings) of the plant to ensure that the design meets GSU Jcorporate requirements and the requirements of regulatory '

criteria (10CFR50.59, etc) and industry concerns.

This includes investigation and suggestion of

. alternative designs if there'is concern with the 21 existing or proposed design.

!3. 1 Interface with other RBNG and parent GSU F. availability of technical departments to assure l-

-information, to project internal cost estimates and schedules,-and.to aseure compliance with regulatory agency requirements and GSU policies.

~

13.1-11 January 1984 ,

LAmendment 11 i

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_.-,---.,__,.-,-_w,_-~.,---_,.,.-,.-..,....,,---

y Insert for Page 13.1-11 13.1.1.2.1.3.1 Director - Nuclear Training The Director - Nuclear Training is responsible for the development, administration, and implementation of the nuclear training program to candidates for both licensed and non-licensed positions, as well as the training program for the remainder of the River Bend Station Staff and River Bend Nuclear Group personnel. He is also responsible for a full-scope, plant-referenced simulator used in the R0/SRO training courses. See Section 13.2 for a further description of the RBS Training Program.

13.1.1.2.1.3.2 Plant Manager The Plant Manager is responsible for the overall safe, reliable, and efficient operation of River Bend Station; responsible for maintaining compliance with the requirements of the operating license and technical specifications; responsible for maintaining a properly trained and licensed operating staff; and responsible for maintaining River Bend Station security. Additional discussion is contained in Section 13.1.2.2.1.

13.1.1.2.1.3.3 Director - Support Services The Director - Support Services is responsible for Records Management such that sufficient records shall be maintained in accordance with 10CFR50 Appendix B, Criterion 17 and Document Control such that issuance of documents (instructions, procedures, and drawings) is in accordance with 10CFR50 Appendix B, Criterion 6; responsible for the procurement process from receipt of an approved purchase requisition to the receipt of the purchased item at the plant, including the collection of all applicable documentation; responsible for originating and maintaining out-of-plant procedures, including the review, comment, and approval of new or revised out-of plant procedures; end, responsible for plant budgeting, accounting, and office administration.

L

, RBS FSAR 11 4. Maintain appropriate GSU corporate interface with ..A the NRC and appropriate state and local officials. 'C 11 5. Develop a satisfactory emergency response plan for RBS that meets regulatory requirements to support the; operating license application and to ensure that such a plan remains up-to-date and cognizant of regulatory requirements.

11 6. Develop and assist local (parish) emergency response programs and assist and interface with analogous state (Louisiana and Mississippi) groups to meet regulatory requirements.

11 7. Coordinate, manage, and monitor contracts and activities for the procurement, conversion, enrichment, and fabrication of uranium fuels for RBS to meet the schedule of first core fuel loading by April 1985, to meet reload schedules as required, and to minimize financial impact on GSU.

8. Develop nuclear fuel safeguards and incore fuel 11 management programs.
9. Develop programs for disposal of spent fuels and high level- . wastes .that will meet agency requirements and minimize GSU expenditures.

(-

10. Direct the analysis of potential safety problems which may need to be reported to the NRC as significant deficiencies (as defined by 10CFR50.55(e)) or substantial safety hazards (reportable under 10CFR21).
11. Review analyses pertinent to safety as conducted in 11 response to issues that raise regulatory and industry concern.
12. Coordinate and oversee technical support from the I

corporate engineers.

13. Oversee the yearly FSAR updates and other license documents.

IN SERT 13.1.1.2.1.5 Project Manager

- Du' ring the- construction phase, the Project Manager assists

,' the Vice President-RBNG through the direction and 11 coordination. of four areas: 1) Accounting, Cost and Scheduling, which involves managing monies and schedules to Amendment 11 13.1-12 January 1984 g, e-

Insert for Page 13.1-12 13.1.1.2.1.4.1 Director - Nuclear Plant Engineering The Director - Nuclear Plant Engineering (NuPE) is responsible for the Mechanical, Electrical, and Nuclear Sections of Nuclear Plant Engineering and all changes to the design of equipment / systems during operation. He is also responsible for engineering support during design, construction, and operations such that RBS meets GSU corporate requirements, regulatory criteria, and industry concerns. The Independent Safety Engineering Group reports to the Director - NuPE on technical matters providing on-site, technical expertise and independent assessment of plant activities. In addition, the Director

- Loss Prevention provides technical support in the area of Fire Protection as a consultant; the Departaent of Power Plant Engineering and Design provides technical support and the Department of Technical Services provides drawing support when requested; or outside consultants are contacted.

13.1,1.2.1.4.2 Director - Nuclear Licensing

.The Director - Nuclear Licensing coordinates and effects official communications with the NRC Staff and appropriate state and local officials. Develops supporting documentation concerning the station facility licenses and permits, and provides recommendations on regulatory issues. In addition, the Director - Nuclear Licensing is responsible for preparation and updating of the Final Safety Analysis Report and the Environmental Report and analysis of potentici safety problems which may be reported to the NRC as significant deficiencies (10CFR50.55(e) or 10CFR21).

13.1.1.2.1.4.3 Supervisor - Emergency Planning The Supervisor - Emergency Planning is responsible for developing a satisfactory emergency response plan for RBS that meets regulatory requirements to support the operating license application, and ensure such a plan remains up-to-date and cognizant of regulatory requirements. He is also responsible for the interfaces between local and state emergency response programs.

13.1.1.2.1.4.4 Supervisor - Nuclear Fuels The Supervisor - Nuclear Fuels is responsible for developing and monitoring the contracts and activities for the procurement, conversion enrichment and fabrication of uranium fuels for RBS first core and subsequent reloads, as well as execution and management of the DOE Spent _ Fuel and/or High Level Waste Disposal contract. In addition, the Supervisor - Nuclear Fuels is designated the " Nuclear Materials Manager" and is also responsible for the development and application of in-core fuels management programs.

-~ ,

RBS FSAR 13.1.2.2.3 operations Supervisor 11 The Operations Supervisor, an SRO, is responsible for the f').

Q-actual day-to-day operation of the plant, including the radwaste system. He reports to the Assistant Plant Manager-

_33 Operations. He supervises a group of approximately 48 operatars and 14 supervisors including the Radwaste Foreman.

The Operations Supervisor is responsible for issuing special orders to shift operations personnel.

In the absence of the Operations Supervisor, his responsibilities are assumed by the Assistant Operations 33 Supervisor.

13.1.2.2.4 Assistant Operations Supervisor The Assistant Operations Supervisor, an SRO, functions as the Operations Supervisor's Senior Shift Supervisor and is 11 qualified to assume the Operations Supervisor's responsibilities and duties if necessary.

13.1.2.2.5 Shift Supervisor 11 The Shift ~ Supervisor, an SRO, is responsible to the Operations Supervisor for all activities relating to station operation and safety during. his assigned shift. This responsibilility includes compliance with applicable license (

and regulatory requirements, personnel and equipment.

and the safety of plant In the event of an accident or

(

emergency, the Shift Supervisor is responsible for determining the severity of the situation and directing the actions of the shift personnel until he is relieved. The Shift Supervisor has the responsibility to shut down the plant if, in his judgment, conditions warrant this action. . .

There is one Shift Supervisor assigned to each shift, representing the senior management individual on shift, and L 11 is onsite,-in the main control room, when fuel is being

! moved or loaded.

13.1.2.2.6 Control Operating Foreman j2

, The J Control Operating Foreman, an SRO, monitors landl r 11 Iman1Dulatest the reactor controls, directs all core alterations, and directs the activities of the Nuclear Control Operators and Nuclear Equipment Operators. He reports to the Shift Supervisor and has the authority and responsibility to shut down the plant if, in his judgment, conditions warrant this action. There is at least one Control Operating Foreman assianed to each shift. / Th4

] Control Operating Foreman will be the Fire Bricade Leader oni l

Amendment 11- 13.1-18 January 1984

( ]

, RBS FSAR f(i his assigned shift. FSAR Section 9B.4.8 describes fire' i (j' brigade size and membership. Administrative provisions exist so that in the event that the Control Operating Foreman is temporarily acting as the Shift Supervisor at the 11 time a fire breaks out, the Shift Supervisor or Assistant Operations Supervisor is notified immediately, thus allowing the Control Operating Foreman to assume his duties as Fire Brigade Leader.

13.1.2.2.7 Nuclear Control Operator The Nuclear Control Operators, under the direction of the Control Operating Foreman or the Shift Supervisor, monitor and manipulate the reactor controls as well as other controls and plant auxiliary equipment. There are normally three Nuclear Control Operators assigned to each shift and 11 at least one in the main control room at all times.g INSERT 13.1.2.2.8 Nuclear Equipment Operator The Nuclear Equipment Operators, under the direction of the Control Operating Foreman or Shift Supervisor, operate the plant auxiliary equipment and the radwaste system. There are normally four Nuclear Equipment Operators assigned to each shift. They are non-licensed personnel.

General Maintenance Supervisor

') 13.1.2.2.9 The General Maintenance Supervisor is responsible for overall direction of electrical maintenance, mechanical maintenance, instrumentation and control maintenance, and spare parts supply at RBS. He reports to the Assistant l 11 Plant Manager-Operations and is responsible for compliance with technical specifications relating to maintenance. The - -

' General Maintenance Supervisor provides maintenance expertise and directs the work of the Mechanical Maintenance Supervisor, Electrical Maintenance Supervisor, Instrumentation and Controls Supervisor, Maintenance and 11 Planning. Coordinator,.and the Building and Grounds Foreman.

Amendment 11 13.1-19 January 1984

. Insert for Page 13.1-19 A Nuclear Control Operator, an R0, will be the Fire Brigade Leader on his/her assigned shift. Section 9B.4.8 describes fire brigade size and membership.

CHAIRMAN OF THE BOARD CORPORATE OFFICES RIVER BEND STATION 3 SENIOR VICE PRESIDENT RBNG l ll ll ll VICE PRESIDENT RBNG l DURING l,/ ! CONSTRUCTION ONLY q

l l .

AG VICE B MANAGER C DIRECTOR y PRESIDENT ENGINEERING, PROJECT QUALITY NUCLEAR FUEL , MANAGER NUCLEAR ASSURANCE AND LICENSING OPERATIONS gg l II

_________J l

l NOTES:

l A1. SEE FIGURE 17.2-1 l B 2. SEE FIGURE 13.1-2 C 3 . SEE FIGURE 13.1-3 l D 4. SEE FIGURE 13.1-4 l

)

FIGURE 13.1-1 CORPORATE STRUCTURE

._ RIVER BEND STATION - UNIT 1 RIVER BEND STATION FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JANUARY 1984

Chairman of the Board and Chief Executive Officer l l President and

  • President f

Chief Operating Prudential Officer Drilling TCompany Executive , Executive Vice President Vice President Administrative Finance

& Technical

%rv4 e m _

~

Vice President Vice President # Senior Technical .-m Power Plant Vice President Services Engineering and Executive Design Proj ects Vice President Senior General

  • Vice President Services River Bend Nuclear' Group j

Manager

  • Senior #

l Risk Management Vice President Services External Affairs l

i Director

/ Figure 13.1-la Corporate Structure Loss Gulf States Utilities Company f

l Prevention

~

  • Entire organization not shown; shown for clarity only Nuclear Review Board (NRB) member I '#

- . - . . - . , _ _ . ~ _ . . . _ _ _ _ , . _ , _ _ _ _ . _ _ . _ . . _ _ , . . _ . _ . . . - ..,.._.,_.__.___,,,-s.__ _ _ _ . __.,~,,,,,_,____,...-.,__..._.,-m-,., _ . , - - -

VICE PRESIDENT NUCLEAR at OPERATIONS I I DIRECTOR C DIRECTOR PLANT NUCLEAR SUPPORT l TRAINING MANAGER SERVICES i

e ammmm amme ammms ammmun summe amm ammme

{ g I I l '

l ASSISTANT PLANT MANAGER ASSISTANT PLANT MANAGER " ' ls l SERVICES OPERATIONS l

l (38) REACTOR A

_ TECHNICAL - ENGINEERING OPERATIONS - @}

(?yg SUPERVISOR SUPERVISOR ,

SUPERVISOR Y::

1 RADIATION g

_ ADMINISTRATIVE PROTECTION AND ammE SUPERVISOR CHEMISTRY SUPERVISOR PLANT GENERAL

- SECURITY MAINTENANCE """

SUPERVISOR SUPERVISOR m- mummmm mummeu DIRECT ACCESS FOR RADIATION PROTECTION MATTERS

(#) NUMBER OF TECHNICAL PERSONNEL ON STAFF A SEE FIGURE 13.1-5 B SEE FIGURE 13.1-2b

! C SEE FIGURE 13.1-2a FIGURE 13.1-2 PLANT OPERATIONS STRUCTURE RIVER BEND STATION - UNIT 1

@ RIVEP, BEND STATION FINAL SAFETY ANALYSIS REPORT -

AMENDMENT 11 JANUARY 1984

Director -

Support -

Services Senior Records River Bend Accountant Supervisor Supervisor -

Section Head Procurement Office

_ Administration Lead Procedure Writer Figure 13.1-2a

j. Plant Operations Structure Administrative Services Section River Bend Station-Unit I l

l

Director Nuclear Training -

Nuclear Training Nuclear Training .

" na Coordinator License k$[fe ne Training Training

- Representative l{Presgnggpive -

Licensed Operator Mechanical Training Training

- Representative Representative - .

NEO Instrumentation &

cc,n ,. vc, 3 ,

Nuclear Training Nuclear Ccordinator Training -'

Technical Coordinator-GET l

Training Training Representative Specialist / "

Radiation Protection Representative l Training Training l Representative Assistant Chemistry Figure 13.1-2b Plant Operations Structure Nuclear Training Section River Bend Station-Unit 1 1

(. _ - . _ - - . . - - - - - , _ _ - - . .

. . . - . . . - - - , - - - . - - . . , , . - - - - - - - - . ~ , ,---- -

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PROJECT MANAGER I

I I I I PROJECT

" AC OUNT NG SUPERINTENDEN C NTRACT MA AGEME

' R * "

MANAGEMENT SYSTEMS l SCHEDULING I I i 1

l

^ SUPERVISOR CONSTRUCTION = PGCC PLANNING SUPERVISOR SUPERVISOR AND SCHEDULING Ag Ag A SUPERVISOR ) SUPERVISOR 3 ASSISTANT cs.;. ENGINEERING tg '

SUPERVISO PROJECTAg SUPERVISOR DESIGN m - SUPERVISOR J - PREOPERATIONAL EriGINEERING TESTING l APP CAT ONS A II O SUPERVISOR , SUPERVISOR COORDIN ATION ' - - PREOPERATIONA AND EXPEDITING TESTING SUPERVISOR SUPERVISOR SITE - - PREOPERATIONA CONTROLS TESTING A i LOCATED AT RIVER BEND STATION B STAFF i.OCATED AT RIVER BEN 9 STATION AND CORPORATE OFFICES FIGURE 13.1-3 PROJECT MANAGEMENT STRUCTURE (CONSTRUCTION PHASE ONLY)

O3 RIVER BEND STATION - UNIT 1 RIVER BEND STATION FINAL SAFETY ANALYSIS REPORT -

AMENDMENT 11 JANUARY 1984

.D

a:

, MANAGER ENGINEERING.

NUCLEAR FUELS.

AND LICENSING I

I I I I l SUPERVISOR A clRECTOR SUPERVISOR DIRECTOR EMERGENCY (2) NUCLEAR PLANT PLANNING ENGINEERING NUCLEAR FUELS NUCLEAR LICENSING  ;

I I I l SUPERVISOR SUPERVISOR

- - M ECH ANICAL SUPERVISOR (3) SUPERVISOR _

NUCLEAR mum IN. CORE ENGINEERING NUCLEAR LICENSING -

ENGINEERING FUELS

.t k

SUPERVISOR (12) SUPERVISOR- (4) OUT.0 F-COR E SUPLRVISOR ELECTRICAL mum - CIVIL - "

FUELS NUCLEAR LICENSING ENGINEERING ENGINEERINd ,

SUPERVISOR (3)

- ENGINEERING ENVIRONMENTAL ,

ENGINEERING umm COORDINATOR LICENSING ANALYSIS 1

A ' LOCATED AT RIVER BEND STATION SUPERVISOR ,;; """" ADMINISTRATIVE DETAILS ONLY ENGINEERING ( ) NUMBER OF TECHNICAL PERSONNEL ON STAFF I

- 1 I

INDEPENDENT A SAFETY (5:

ENGINEERING

- GROUP FIGURE 13.1-4 TECHNICAL SUPPORT (OFFSITE)

RIVER BEND STATION - UNIT 1 RIVER BEND STATION ~

FINAL SAFETY ANALYSIS REPORT e ' AMENDMENT 11 JANUARY 1984

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

SRO A

- OPERATIONS SUPERVISOR I

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8"U ASSISTANT A SHIFT OPERATIONS SUPERVISOR SUPERVISOR

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l R RADIATION 1/6 SRO CONTROL 1/6 ER d

-- PROTECTION OPERATING RADWASTE A FOREMAN TECHNICIANS FOREMAN I I I s 1/G RO 3/18 ER NUCLEAR NLR NUCLEAR l'h

-- CONTROL EQUIPMENT TECHNICI N OPERATORS OPERATORS I I 1/6 NLR NUCLEAR 4/24 l

L-munuNLR TEST TECHNICIAN EQUIPMENT NUCLEAR OPERATORS f NLR NO LICENSE REQUIRED SRO SENIOR REACTOR OPERATOR RO REACTOR OPERATOR x/y NUMBER PER SHIFT / TOTAL STAFF

  • i TRAINED TO A LEVEL EQUIVALENT TO A SHIFT TECHNICAL ADVISOR (STA) i A[, NOT ON SHIFT; SHOWN FOR CLARITY ONLY FIGURE 13.1-5 l

RIVER BEND SHIFT ORGANIZATION RIVER BEND STATION - UNIT 1 RIVER BEND STATION FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JANUARY 1984

- -- , , - - - , . , -y,,-, , ,--,.y- - - - , , _ , - . , . _ , -

J

, RBS ESAR 11 staff and others as necessary, and functions to advise the a r.

Plant Manager on all matters related to nuclear safety. The ig?

FRC activities and membership are defined in a written administrative procedure.

13.4.1.1 Membership

.The FRC membership is:

11 Assistant Plant Manager, Operations - Chairman.

Operations Supervisor - Member.

Technical Supervisor - Member.

General Maintenance Supervisor - Member.

' Reactor Engineering Supervisor - Member.

- Radiation Protection / Chemistry Supervisor - Member.

11 Operations Quality Assurance Supervisor - Non-Voting Member.

Nuclear Licensing Representative - Non-Voting Member.

. INS 3RI i-13.4.1.2 Alternates i*gg Alternate members are appointed in writing by the FRC chairman to serve on a temporary basis. An alternate ha:

-qualifications comparable to the absent permanent member.

No more than'two alternates participate as voting members in FRC activities at any one time.

13.4.1.3 Meeting Frequency i

f The FRC meets at least- once per calendar month and as convened by the Chairman or his designated alternate.

13.~4.1.4 Quorum The minimum quorum necessary for the performance of the FRC responsibility and authority consists of the Chairman, or his designated alternate, and four members including no more than two voting alternates.

11_ l .

Amendment 11- 13.4-2 January 1984 t__

Insert for Page 13.4-2 Supervisor - Site Engineering - Non-Voting Member Additional technical support is available from the Engineering Staff located at the site. This includes the areas of instrumentation and controls, health physics, radiochemistry, and refueling, as well as other technical areas in which the FRC would require consulting support.

I L=

. RBS FSAR 13.4.1.5 Responsibilities The FRC is responsible for: /

) 7

1. Review of all / procedures grequired by Technical 7 g:n:rsl i pe ifi ation 6.8 and its changes A and of any other administrative proposed procedures, programs, and changes as pl nt determined by the Plant Manager which constitute an 11 unreviewed safety question.
2. Review of all proposed tests and experiments that affect nuclear safety.
3. Review of all proposed changes to the technical specifications.
4. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5. Investigation of all violations of the technical specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Operations Supervisor and the NRB.

' ((4 6. Review of events requiring 24-hr written T2 notification to the NRC.

7. Review of unit operations to detect potential nuclear safety hazards.
8. Performance of special reviews, investigations or analyses, and reporting on them as requested by the - -

Plant Manager or the NRB.

9. Review of the- Physical Security Plan and Implementing Procedures, and submittal of recommended changes to the NRB.
10. Review of the Emergency and Fire Protection Plans and Implementing Procedures, and submittal of recommended changes to the NRB.
11. Review of unplanned releases, which require reporting, of radioactive material to the environs including the preparation and forwarding of reports 11 covering evaluation, recommendations and disposition of the corrective action to prevent Amendment 11 13.4-3 January 1984

RBS FSAR lj. 13.4.1.7 Records The FRC maintains written minutes of each meeting that, at a minimum, document the results of all FRC activities performed under the responsibility and authority provisions of Section 13.4.1. Copies are provided to the Plant Manager and the NRB.

13.4.2 Independent Review The NRB, which is responsible for independent reviews, will be established and functional at least 6 months prior to initial fuel loading. The NRB is chaired by the Senior Vice 31

' President - External Affairs and includes a majority of members who are not directly responsible for plant operationc. The NRB functions to provide independent review and audit of designated activities in the areas of nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy, instrumentation and control, radiological safety, mechanical and electrical engineering, quality assurance practices, and any other appropriate fields associated with the unique characteristics of the nuclear power plant. _

13.4.2.1 Membership

( The NRB membership is: '

Senior Vice President, External Affairs - Chairman.

Vice President, River Bend Nuclear Group - Alternate Chairman.

Vice President, Nuclear Operations - Member.

Vice- President, Power Plant Engineering and Design -

Member.

and Licensing - 11 Manager, Engineering, Nuclear Fuels, Merber.

Director, Quality Assurance - Member.

RBS Plant Manager - Member.

Director, Nuclear Plant Engineering - Member.

Director, Nuclear Licensing - Member.

INSERT r Amendment 11 13.4-5 January 1984 G

~ - - - - - - - --e p- -------yg--n. , ,,n ,, , , , , , 7__,- _ .,

Tnsert for Page 13.4-5 Additional technical support is avail.able from the Nuclear Plant Engineering staff located off-site. This includes tha areas of chemistry / radiochemistry, radiological controls, as well as other technical areas in which the NRB would require censulting support.

L.

RBS FSAR

4. Proposed changes to Technical Specifications.
5. Violations of codes, regulations, orders, technical specifications, license requirements, or of internal procedures or instructions bra'ing nuclear safety significance.
6. Significant operating abnorma)ities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
7. Events requiring 24-hr written notification to the NRC.
8. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
9. Reports and minutes of meetings of the FRC.

13.4.2.7 Audits Audits of River Bend Station activit ? as are performed by the l 11 Quality Assurance Department under the cognizance of the NRB. These audits encompass:

1. Conformance of' unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
2. Performance, training, and qualifications of the entire unit staff at least once per 12 months.
3. Results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months.
4. Performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10CFR50, at least once per 24 months.
5. Emergency lan and Implementing Procedures at least once per months.
6. Security Plan and Implementing Procedures at least once per 24 months.

Amendment 11 13.4-7 January 1984

RBS FSAR c

Reports of reviews encompassed by Section 13.4.2.6 Y h.

E2ff; 2.

are prepared, approved, and forwarded to the Senior 11 Vice President - River Bend Nuclear Group within 14 days following completion of the review.

3. Audit reports encompassed by Section 13.4.2.7 are forwarded to the Senior Vice President - River Bend 11 Nuclear Group and to the management positions responsible for the areas audited within 30 days after completion of the audit.

~

13.4.3 Independent Safety Engineering Group l The ISEG is an onsite, technically oriented, independent review organization. This group will be established and functional at least 3 months prior to initial fuel load and physically located at River Bend Station. The function of the ISEG is to increase,the available technical expertise located onsite and provide continuing, systematic, and independent assessment of, plant activities.

//

reports to the., Supervisor-Site Engineering onsiYii~ ?

DELETE AND REPLACE WITH 'The ISEG INSERT who- reports to the Director-Nuclear Plant Engineering.

Finally, the Director-Nuclear Plant Engineering informs the Manager-Engineering, Nuclear Fuels and Licensing of all ISEG activities and recommendations.

li? '

EI/ 13.4.3.1 Membership The ISEG is composed of at least five, dedicated, full-time il engineers located onsite. Each has as a minimu.a, a Bachelor's Degree in Engineering or a related science, and at least 2-years of professional level experience in their

' field, one of which must be in the nuclear field.

13.4.3.2 Meeting Frequency As a full-time engineering group, the ISEG does not hold routinely specified meetings but interacts, instead, on a cont 1nuous basis with the technical staff, operational staff, quality assurance organizations, and engineering support groups in order to complete their responsibilities as defined in Section 13.4.3.3. Special meetings may be called for and announced by the Manager-Engineering, Nuclear Fuels, and Licensing in order.to accommodate any abnormal occurrences or special problems.

Amendment 11 13.4-9 January 1984 g;

. O k ...

Insert for Page 13.4-9 The ISEG reports administratively to the Supervisor - Site Engineering located on-site; however, the group reports to the Director - Nuclear Plant Engineering (NuPE) located off-site on all technically-oriented issues.

?

RBS FSAR INSERT 1 Procedures are classified as safety-related or nonsafety- _ ;,3 INSERT 2 related and are reviewed #by qualified individuals / Approved -

tgy plant procedures required to support fuel load will be completed at.least 70 days prior to ' fuel load. Approved 11 procedures may be changed in accordance with River Bend y/#

Station Ooerations Manual Administrative Proceduresp" [ThesdT INSERT 3 gevisions to safety-related procedures are reviewed for conformance to 10CFR50.59 by a qualified individual =t

. INSERT 4 13.5.1.3 Procedures 11 A~ procedures status list includes the procedure type, pr cedure number,/and responsible office for each procedure.

INSERT 5 These include:

1. Administrative procedures (ADM)
2. Abnormal operating procedures (AOP)
3. System operating procedures (SOP)
4. General. operating procedures (GOP)
5. Surveillance test precedures (STP)
6. General maintenance procedures (GMP) a Alarm response procedures'(ARP)

~

7. $
8. Etnergency operating procedures (EOP)

- 9. Chemistry and radiochemistry procedures (CRP)

10. Radiation protection procedures g?PP) _ _

. 11. Fuel handling procedures (FHP)

12. Reactor engineering procedures (REP)
13. ' Instrument control procedures (ICP)
14. _ Plant procurement procedures (PPP)
15. Material handling procedures (MHP)
16. Plant engineering procedures (PEP)
17. Plant security procedures (PSP)
18. Fire fighting procedures (FFP)

/

Amendment 11 13.5-2 January 1984 ..

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. Insert 1 for'Page 13.5-2 Land approved Insert 2 for Page 13.5-2 l in sections'for which they apply.

Insert 3 for Page.13.5-2 or applicable-support: department procedures.

s

Insert 4 for Page 13.5-2

- while- revisions to administrative procedures are reviewed by the FRC and approved by the Plant Manager.

Insert 5 for Page 13.5-2

< procedure revision, r

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1 4 4

1

4 RBS FSAR

2. Text -

purpose, entry conditions and symptoms, operator actions _ (including instructions and ( ~h contingency actions)

Licensed plant operators are required to know the entry conditions in the Emergency Operating Procedures.

Emergency Operating Procedures include, but are not limited to, the following:

1. Reactor Pressure Vessel (RPV) control

- 2. Primary containment control

3. Secondary containment control
4. Radioactivity release control

. 5. Level restoration

6. Emergency RPV depressurization
7. Steam cooling _
8. Core cooling without level restoration
9. Alternate shutdown cooling '
10. RPV flooding
11. Level / power control INSERT 13.5.2.1.5 Alarm Response Procedures . _

Each' alarm response procedure (ARP) is composed of a group of individual alarm enclosures. These groups are normally by systems and aie located near the panel that contains the alarms annunciator to provide timely reference by the operator.

11 Each Alarm Response Procedure contains at least the following information:

1. ' Alarm number
2. Alarm window / title 33
3. Alarm panel, sections, and grid numbers
4. Alarm set points Amendment 11 13.5-14 January 1984

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' Insert for.? age-13.5-14

. The Emergency-Operating Procedures were: developed using the technical

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guidelines from the BWROG Emergency Procedure Guidelines (EPG),
, Revision'3. The EPG's were established in compliance-with NUREG-0737,

-Item I.C.1.

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APPENDIX'13A

.s; :. f This appendix contains resumes iof key corporate' personnel

- . responsible for. technical support, either directly or indirectly

through the management of-that support.

v  %

.li William J. Cah'111, Jr. Senior'Vice President -

River Bend Nuclear Group

12. James'C; Deddens' Vice President -

. River Bend Nuclear Group 3.. James G. Weigand Vice President -

Nuclear Operations

~

4. James E.: Booker:- rManager -

Engineering, Nuclear Fuels, and Licensing U S.: Randy W; Helmick River Bend Project Engineer

,6. James M. Glazar = Director -

Nuclear Plant-Engineering

=7. William J. Reed, Jr. Director -

Nuclear Licensing

~

8. John-G. Cadwallader Supervisor -

Emergency Planning

'9. John E. Barry Supervisor -

Nuclear Fuels

~

10. Jim W. Wright Supervisor -

Mechanical-Engineer

11. Erwin J. Zoch

~

Supervisor -

Nuclear Engineer

. 12. Donald R.' McCarter ' Director -

Loss Prevention

.-13.:W1111amLJ. O' d ell' ' Director -

Nuclear Training 14.'E11erylL.Hammond, Plant Manager 15.,Phillip D. Graham Assistant Plant Manager - Services

16~.-Peter E. Freehill Superintendent - Startup and Test /

Assistant Plant Manager - Services-a

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^/---

~17. Maxey F.1Cassada Radiation Protection /

Chemistry Supervisor

18. Charles'P. Bogolin Operations Supervisor.

'19.~ Joe L. Burton General Maintenance Supervisor

20. L'ionel'R. Thompson' Instrumentation and Controls Supervisor
21. Craig H. Greene Technical Supervisor
22. Dan Williamson Reactor Engineering Supervisor

-23. David L. Davenport Plant Security Supervisor

' 24. E. Linn Draper Senior _.Vice' President -

External-Affairs

'25. James H. Derr,.Jr. Vice President - Power Plant Engineering and

- Design

~

Resumes'for the fo11owing positions will be supplied in a future-submittal:

1. Director - Quality Assurance

=2. Supervisor - Quality Engineering

~

3. Supervisor.- Quality Systems

.4. Supervisor - Operations QA

" 5. Supervisor'- Quality Control 6.: Director - Support Services 7.-Administrative Supervisor.

-~i, . .

8. Radiation Protection Supervisor
19. Supervisor - Electrical Engineering 10.-Supervisor -1Civi1' Engineering Ell.' Supervisor - Engineering Analysis
12. Supervisor - Site Engineering-p

RBS FSAR RESUME WILLIAM J. CAHILL, JR.

SENIOR VICE PRESIDENT - RIVER BEND NUCLEAR GROUP EDUCATION School and Location Maior Date Degree Polytechnic Institute Mechanical 1949 BS Brooklyn, New York Engineering Mechanical 1949- Graduate Engineering 1953 Work EXPERIENCE Gulf States Utilities Company

1. Senior. Vice President - River Bend Muclear Group -

8/80-to present Responsible for all aspects of the construction and operation of the River Bend Station.

Consolidated Edison Company (

1. Vice President - Reporting to the President - 5/75 to 8/80 In charge of licensing of nuclear plants, Quality Assurance Department, Research and Development Department, and Computer Applications Engineering.
2. Vice. President - Reporting to the President - 8/71 to 5/75 Responsible for administrative oversight and direction of the design licensing, construction, and operation of Indian Point Units 1, 2, and 3.

3.- Vice President - 8/69 to 7/71 Administrative management of the activities of Civil, General, and Mechanical Engineering Departments involved in active generation and transmission projects plus preliminary planning and design of future generating capacity.

13A-2

RBS FSAR

4. Assistant Vice President - 1967 to 1969 In administrative charge of Mechanical, Structural, and Nuclear Engineering Departments performing the engineering and design of Con Edison' s power generation facilities.
5. Mechanical Plant Engineer - 1965 to 1967 Responsible- for engineering of nuclear and mechanical systems and equipment covering station improvement work on existing plants and the follcwing new facilities; Indian Point No. 2 and No. 3 (1,000 MW nuclear units) , and Arthur Kill No. 3 (a. 500 MW coal-fired unit) . Also, studies, evaluations, and preliminary design of future projects. In charge of Nuclear, Steam, Field, Turbine, and Control Division personnel.
6. Nuclear and Turbine Plant . Engineer - 1963 to 1965 f

Responsible for nuclear engineering and turbine plant engineering including turbine, condenser, and condensate systems for Ravenswood 1, 2, and 3

,1 (1,800 MW oil and coal) .

k' 7. Division Engineer - 1961 to 1963 In charge of Nuclear Engineering Division responsible for Indian Point Unit No. 1 and the proposed 1,000 MW Ravenswood Nuclear Plant.

l 8. Responsible for engineering design of primary coolant system of Indian Point Nuclear Unit - 9/57 to 9/60 l:

Nuclear Development Associates, White Plains, N.Y.

l t

1. Participated in design of water cooled-beryllium moderated research reactor for Mol, Belgium.

Project Management for sodium cooled-heavy water moderated reactor proposed for Chugach, Alaska -

1/57 to 9/57.

Consolidated Edison Company

1. Resumed duties in engineering of power plant systems, including ash handling facilities for a 400 MW coal-fired generating unit and preliminary 13A-3

RBS FSAR engineering for the 275 MW Indian Point nuclear unit - 1956 to 1957.

Knolls Atomic Power Laboratory, Schenectady, NY

1. Consultant to the General Electric Company to participate in the design and operation of the prototype nuclear power plants for the submarines sea Wolf and Triton - 1954 to 1956.

Consolidated Edison Company

1. Assigned to steam power plant engineering jobs, including coal-oil conversions, fuel oil supply and storage systems, combustion control systems, and the steam generator associated with an 1,800 psi, 1,0000F/1,000*F 200 coal-fired generating unit -

1949 to 1954.

PROFESSIONAL DATA Board member of Empire State Electric Energy Research Corporation (ESEERCO)

Member of EEI Executive Advisory Committee on Nuclear Power vice Chairman of Westinghouse Owners' Group (for post-TMI generic responses)

Chairman of - Electric Power Research Institute (EPRI) Nuclear Safety and Analysis Task Force Past member of AEIC Power Generation Committee Past Director of Atomic Power Development Associates Past member of EEI Prime Movers Committee American Society of Mechanical Engineers American Nuclear Society National Society of Professional Engineers New York State Professional Engineers, License

  1. 30329, issued May 19, 1955 13A-4

RBS FSAR RESUME , 7 JAMES C. DEDDENS }

VICE PRESIDENT - RIVER BEND NUCLEAR GROUP ,

EDUCATION -

School and Location Major Date Degree

. University of Louisville Mechanical' 1952 BS Engine'ering University of Louisville Mechanical 1953 MS Engineering University of Louisville Master of 1972 Engineering Additional Courses or Training Oak Ridge School of Reactor Technology - 1954 Northeastern University - Management Development Program..-1978 EXPERIENCE

.Culf States Utilities Company

1. Vice President - River Bend Nuclear Group - 1982 to present Assists the Senior Vice President - River Bend Nuclear Group with the executive' direction and coordination of the River Bend Nuclear Group.

Babcock & Wilcox Company

1. Manager - Business Administration and Integration Department - 1980 to 1982 N Responsible for integrating the Nuclear Power Generating Division's business activities through the planning process and responsible for Employee and Public Relations and Purchasing Functions. Planned, marketed, and managed the Consumer Servicas Product Line.
2. Manager - Project Management Department - 197E to 1980 Responsible for managing the Company's Nuclear Steam Supply system

. and nuclear fuel cont.racts. Directed activities of project teams to schedule and deliver all of the Company manufactured and procured ,

s, equipment and services provided under these contracts. . .

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3. - Manager - Engineering Department - 1974 to 1978 Responsible for the detailed design and licensing for all NSSS, fuel contracts, and development projects. Finalized the design of the standard B'& W 1200 MWe NSSS and Mark C fuel assembly and obtained preliminary-design approval under the NRC's standard plant program.
4. Manager - Service Section - 1966'to 1974

'R'esponsible for all-startup services including training startup-

. engineers,' furnishing operator and plant staff training programs, preparing startup and test procedures, preparing operating pro-cedures, as well as preparing and evaluating plant test and test re-sults.

5. ' Market Representative - 1963 to 1966 Responsible for providing proposals and marketing activities for NSSS and fuel to utility customers.
6. Startup Engineer - 1960 to 1963 On-site $epresentativeresponsiblefortheB&Wfurnishedstartup services to Consolidated Edison Company for the startup and initial operation of Indian Point Unit Number 1.

- . . . 7.. 1954 to-1963 Various assignments on the Indian Point. Unit Number 1 project including core design and project engineering for the NSSS contract.

PROFESSIONAL-DATA Registered ^ Professional Engineer - Virginia and Lousiana NSPE, Engineer of the Year - Virginia Section,1978

'; t . . _ . . ..

Member of ASME, ANS, and AIF Jncluding participation in several com-mittes and chairmanships B & W Representative of the U. S. Committee for Energy Awareness y,,N .- a - ~ ,-

u . of many technical papers and n..

Holder of.1.-J - - wpatents;and' i d h %IEO,U . , - -

several author

_presenthtions'

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RBS FSAR RESUME JAMES G. WEIGAND VICE PRESIDENT - NUCLEAR OPERATIONS t . . .

A iEDUCATION .

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'~ . School and Location Major Date Degree U.S. Naval Academy Marine 1958* BS  :

Annapolis, Maryland Engineering  !

i University of Washington Physical 1962** MS  !

Seattle, Washington Oceanography i

! University'of Washington Physical 1964 PhD l Seattle, Washingtor Oceanography

  • Graduated with distinction
    • Elected to Sigma Xi - Scientific Honorary Additional Courses or Training Nuclear Power School - 12 month course in nuclear engineering at Mare Island, California and KAPL Laboratories, New York, 1966 l Advanced Nuclear Engineering for Submarine Commanding Officers - 3 1/2 month course for f submarine captains at the Naval Reactors off1ces

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under the direct supervision of Admiral H. G. Rickover, --

.1973 . . . . ... .

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l EXPERIENCE. .

Gulf States Utilities Company

  • l'. Vice President - Nuclear Operations - 10/16/82 -

.to prese.nt (see.Section 13.1.1.2.1.3 for responsibilities) 2, .Vice President - Nuclear' Operations 'nd. a Technical Systems -

, , , 5/1/80 to 10/15/82 - u-: '---

3. Vice President'- River Bend Operations and Technical Systems -

1/1/80 to 5/1/80 . : --

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Performed same duties as those of present position (see '

-above), ~.however since the River Bend ~ Project grew in scope

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(' technical systems.

4 f. General Manager-Nuclear Projects - 1/1/79 to 1/1/80 Responsible for all aspects of GSU nuclear projects, specifically for the management of the construction of the' River Bend Station located near St. Francisville, Louisiana.

4 5 Technical Assistant to the Chairman of the Board,- 7/16/78 to 1/1/79 Responsible for managing the research and research support for the company, evaluating technological advances for company application, representing the Chairman's office as a member of the Strategic Planning Committee, and performing special projects as directed by the Chairman.

Office of Naval Education and Training

1. Utaff officer for the Chief - 10/76 to 7/16/78
2. - Executive Assistant and Senior Aide to Vice Admiral James B. Wilson Responsible for assigning and coordinating all administrative tasks for one of the Navy's largest commands with over 150,000 students and 20,000 staff.

Nuclear Powered Missile Submarine USSS Nathanael Green (SSBN 636)

1. Commanding Officer - 7/73 to 10/76 Completely responsible for the operation and maintenance of a half-billion dollar submarine.

Responsible for the training, leadership and performance of the officers and crew.

U.S. Navy

1. Executive Officer - 9/71 to 2/73 (Nuclear Powered Submarine) .

Supervised the administration and training of a

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missile submarine crew.

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RBS FSAR As second in command, supervised and was ,

responsible for all routine operations.

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2. Officer -

7/66 to 8/71 (Several different nuclear submarines)

Served as department head in navigation, weapons, and operations departments.

PROFESSIONAL DATA Four (4) research publications, as well as many classified publications for the U.S. Navy on oceanography _ and submarine sonar.

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1' 13A-10 l

RBS FSAR-RESUME JAMES E. BOOKER MANAGER-ENGINEERING, NUCLEAR FUELS, AND LICENSING

-EDUCATION School-and Location Major Date Degree Lamar University, Industrial 1955 BS Beaumont, Texas Engineering Mechanical 1956 BS Engineering Additional Courses or Training University of Michigan's Public Utility Executive Program - 1978 EXPERIENCE

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Gulf States-Utilities Company

1. Manager - Engineering, Nuclear Fuels, and Licensing -

10/16/82 to present In charge of Nuclear Licensing, Emergency Planning, Nuclear Plant Engineering, and Nuclear Fuels (see 13.1.1.2.1.4 for responsibilities)

2. Manager of Technical Programs - 5/1/80 to 10/15/82

.In charge of Nuclear Licensing, Emergency Planning, Out-of-Core Fuels

3. Manager of Technical Programs - 12/1/79 to 5/1/80 In charge of Nuclear Licensing, Emergency Planning, Out-of-Core Fuels, and Project Engineering
4. Project Manager for River Bend Project - 12/1/78 to 12/1/79

-In. charge of Project-Engineering, Nuclear Licensing, and Administrative Services

'5. In charge of licensing for River Bend Project and environmental licensing of fossil power plants - 11/1/77 to 12/1/78'

6. In charge of licensing activities to two nuclear power plants

- River Bend Project and Blue Hills - 9/1/72 to 11/1/77

7. ~ Quality Assurance (QA) Department as QA Coordinator - 3/1/72 to 9/1/72
8. ' Supervisor of Administative Services - 1/1/71 to 3/1/72 13A-11

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In charge _of Corporate Records Department, duplicating, microfilming, telephone services, stenographic services,

~ library and mailroom facilities

'9. System Power Plant Production Department - 8/1/62 to Variousfpos'itions, such as Result Engineer conducting performance tests en gas-oil fired power plants, maintenance planning and scheduling, and Staff Engineer to Production

-Manager coordinating operations, maintenance and personnel requirements for six operating fossil power plants.

10. System Engineering Department - 6/1/56 to 8/1/62 Involved in design and construction of transmission lines and substations, major electrical equipment and requirements, specifications and construction budgeting PROFESSIONAL DATA American Nuclear Society

~The_American Society of Mechanical Engineers Atomic Industrial Forum,'Inc.

Committee on Reactor Licensing & Safety Committee on Environmental Projects Committee'on Nuclear Regulations Committee on Near Term Operating Licensing

-(Chairman on Regulations Subcommittee)

Edison Electric Institute (EEI)

-Nuclear Operations Committee Registered Professional Engineer - State of Texas 13A-12

RBS FSAR T

. /

'. RESUME JAMES M. GLAZAR

-DIRECTOR - NUCLEAR PLANT ENGINEERING EDUCATION ,

School and Location ' Major Date Degree Pennsylvania'S' tate University Machine 1972 MSME State College, Pennsylvania Design

Newark College of Engineering Machine 1965 BSME Newark rNew Jersey Design-EXPERIENCE Gulf States Utilities Company
1. Director - Nuclear Plant Engineering - 10/17/82 to present See Section 13.1.1.2.1.4.1 for responsibilities.
2. Project Engineer - River Bend Nuclear Group - 5/1/78 to 10/15/82 Responsible for all design engineering activities associated with the River Bend Nuclear Project. Manage and control the efforts of the Architect / Engineer's (Stone & Webster) engineering organization, the Nuclear Steam Supply System Vendor (General Electric) and any other vendors as necessary to control the design of the plant.

Omaha Public Power District 3

.l. Lead Mechanical Engineer.in the Generating Stations Engineering Section - 2/1/76.to ,5/1/78; -

. Job. duties included project engineering functions involved with:

- 1) site security (Fort Calhoun Nuclear Station),2) CE/ DOE /0 PPD Re-

^

fueling Outage Reduction Program (Fort Calhoun Nuclear Station), and

3) High-pressure feedwater heaters replacement project (North Omaha fossil station). Duties included design coordination, planning, .

I scheduling, financial estimating, and liaison with architect / engineers, .

Vendors, contractors and plant operating personnel during design, con-tract negotiations, . installation, and material / labor procurements,

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.hy c:Qggfy9District fossil %(nd nuclear j . stations

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as well as design coordination with engineering consultants._  !

. I General Atomic Company

1. Cognizant Program Engineer for HTGR control rod drives - 1/1/74 to 12/1/75 Responsibility for overall prograz 'pl'anning, scheduling and budget administration, customer and vendor liaison, technical . presentations, preparation of technical documents, and obtaining patents.

General Atomic Company

1. Design Engineer on Nuclear Reactor Control Mechanisms - 3/1/68 to 1/1/74 Detail design, supervision of draftsman, design analysis, and engineering liaison of development and qualification test programs. Manufacturing and vendor liaison during fabrication of components for large nuclear power station, Responsible for publication of necessary fabrication, assembly, testing, packaging and shipping procedures including Operation and Maintenance Manual Reponsibility for site / customer liaison, resolution of onsite problems, resulting design changes, and supervision of onsite repairs.

Johnson and Johnson Eastern Surgical Dressing Plant

1. Equipment Design Engineer for Design, Fabrication, and Installation of Plant Production Machinery -

1965 to 1966.

Primarily responsible for the design, development, and installation of new labeling lines.

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2. Equipment Design Department - 1964 Performed layout and detail drafting.

13A-14 Q , ,/

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RBS FSAR Also, research testing of new product concept to determine basic design parameters.

Bell Telephone Laboratories

1. Draftsman - 1959 to 1963 Worked on Nike Missile System Projects, including both mechanical and electrical systems.

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RBS FSAR RESUME C-l WILLIAM J. REED, JR.

DIREC'IOR - NUCLEAR LICENSING EDUCATION School and Location Maior Date Degree University of Arkansas Mechanical 1971 BS Fayetteville, Arkansas Engineering University of Arkansas Mechanical 1973 MS Fayetteville, Arkansas Engineering Additional Courses or Training Louisiana State University - Basic Health Physics Short Course, May 1975 Massachusetts Institute of Technology - Reactor Safety and Licensing Short Course, July 1977 EXPERIENCE Gulf States Utilities Company

1. Director-Nuclear Licensing - 1/1/81 to present .

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See Section 13.1.1.2.1.4.2 for responsibilities.

1

2. Supervisor-Nuclear Licensing -

7/15/78 to 1/1/81 l

Responsibilitiessameasdescrfbedabove.

3. Engineer-Nuclear Licensing -

6/1/75 to 7/15/78 -

Responsible for performing duties as directed relating to the issuance of River Band Station Units 1 and 2 construction Permits.

4.- Engineer-Transmission and Distribution - 4/1/74 to 6/1/75 -

Responsible for computer program maintenance and preparation related to the Distribution Estimating System.

5. Engineer-System Production -

10/25/73 to 4/'./74 -

  • Responsible for preparing computer program for .

determining fossil unit heat rates. Program was used to determine plant efficiency with recommendations for plant improvement. s

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(. United States Army

1. 2nd Lieutenant -

7/73 to 10/73 - Attended and graduated from the U. S. Army Field Artillery School, Pt. Sill, Oklahoma Pettit and Pettit Consulting Engineers

1. Engineer (Part-time while in college) - 9/72 to 5/73 - Reponsible for reporting field inspections of the installation of a Babcock and Wilcox boiler

' addition to the University of Arkansas Physical Plant.

PROFESSIONAL DATA i

Member, American Nuclear Society - South TexasSection I

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RBS FSAR RESUME JOHN G. CADWALLADER SUPERVISOR - EMERGENCY PLANNING EDUCATION Date Degree School and Location Maior Louisiana State University Zoology 1970 BS

. Louisiana State University Physiology 1978 MS Additional Courses or Traininq December 1975 Advanced Medical X-Ray Survey l

Course Bureau of Radiological Health Baylor College of Medicine Houston, Texas May 1976' Medical X-Ray Survey Techniques Bureau of Radiological Health Fort Sam Houston, Texas February 1977 Health Physics and Radiation Protection Course U.S. Nuclear Regulatory Commission Oak Ridge Associated Universities Oak Ridge, Tennessee i July 1977 Medical Use of Radionuclides for State f l

Regulatory Personnel U.S. Nuclear Regulatory Commission l Baylor College of Medicine j

Houston, Texas t

l January 1978 Industrial Radiography for State Regulatory Personnel l

L U.S. Nuclear Regulatory Commission Baton Rouge, Louisiana L September 1978 Orientation Course in Regulatory l Practices and Procedures

' U.S. Nuclear Regulatory Commission Gilver Springs, Maryland

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RBS FSAR March 1979 Radiological Emergency Response Planning Course U.S. Nuclear Regulatory Commission Jackson, Mississippi April 1979 Radiological Emergency Response operations Training Course U.S. Nuclear Regulatory Commission Las Vegas and Mercury, Nevada December 1979 Radiological Emergency Response Coordinators Course U.S. Nuclear Regulatory Commission Wildwood, Florida EXPERIENCE Gulf States Utilities Company

1. Supervisor-Emergency Planning - 11/80 to present Responsible for developing Emergency Response Plan for RBS. See Section 13.1.1.2.1.4.3 for additional description.

Louisiana Hazardous Waste Management Division

1. Hazardous Waste Specialist- 9/80 to 11/80 Responsible for tracking shipments of hazardous waste and for developing emergency response system for waste spills.

Louisiana Nuclear Energy Division

1. Radiation Specialist- 7/77 to 9/80 From September 9/78 to 9/80, responsible for the establishment and maintenance of environmental surveillance prograss and for the development of the State Peacetime Radiological Response Plan and local parish plans. Worked with NRC, PEMA, and I Louisiana Environmental Control Commission concerning emergency response planning for fixed

. nuclear facilities.

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1. Health Physicist - 9/75 to 7/77 Responsible for the inspection of radioactive materials and X-ray units used and operated by various industries, educational institutions, and hospitals and for the evaluation of radiation protection programs. Accountable for maintenance

'of radiation detection instruments, emergency response to radioactive material accidents, and seminars on radiological health and safety.

United States Air Force

1. 1st Lieutenant-Weapons Controller - 9/70 to 12/73 Professional Data Member, Health Physics Society 1

Member, Health Physics Society-Deep South Chapter j Member, Louisiana Nuclear Society

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RESUME JOHN E. BARRY SUPERVISOR - NUCLEAR FUELS EDUCATION School and Location Major Date Degree Texas A&M University Nuclear 1970 BS College Station, Texas Engineering Lamar University, Engineering 1981 Masters Beaumont, Texas EXPERIENCE Gulf States Utilities Company

1. Supervisor - Nuclear Fuels-10/15/82 to present (see Section 13.1.1.2.1.4.4 for responsibilities.)
2. Supervisor - Out-of-Core Fuels-1/1/80 to present (same duties as delineated in Section 13.1.1.1.3)
3. Nuclear Fuels Engineer - 10/1/77 to 1/1/80 (same duties as delineated in Section 13.1.1.1.3)

Governor's Energy Advisory Council

1. Nuclear Specialist - 1976 to 1977 Responsible for writeup and coordination cf task force input for the GEAC report on nuclear power. Responsible for evaluation of President Carter's Energy Proposals on nuclear power and electrical generation (e.g., mandatory interconnect, bulk sales, and hydro generation). Other responsibilities' included:

Projection of Texas nuclear energy and uranium production.

Monitoring nuclear generation, process heat, waste disposal, uranium mining and other projects in Texas.

t Provisions of liaison and assistance to federal agencies (e.g., the NRC, ERDA, FEA, and USGS) on matters of interest in Texas.

Follow ruclear generation and uranium exploration and production technology in Texas and nationally.

13A-21 1

RBS FSAR Citr Public Service (San Antonio, TX)

1. Engineer - 1972 to 1976 Participated on a special study on fuels and conversion devices in Research and Planning. Later cook engineering position in Nuclear Section of Energy Systems Planning. Undertook special review work on reactor vendor evaluation, training and other' subjects pertaining to the South Texas Project as well as nuclear engineering RSD matters.

In the Nuclear Fuels Section of Nuclear and Environmental Division, aided in successful contracting of enrichment services for Unit 1 of STP II berore the June contracting suspension.

Helped formulate final NSSS and nuclear fuel bid specs for STP II for which CPS had project management.

In January 1975, after indefinite suspension of STP II, undertook pigh priority long-range uranium fuel procurement activities as well as those associated with other aspects of the nuclear fuel cycle.

Texas Employment Commission l 1. Employment Interviewer - 1972 City of Houston

1. Laborer - 1971 to 1972 IBM-NASA
1. Computer Clerk (Temporary) 1971 Welex l

! 1. Field Management Trainee - 1970 to 1971 Pacific Gas and Electric l

j 1. Engineer - 1970 1

i PROFESSIONAL DATA Member, American Nuclear Society; Associate Member, l Texas Society of Profersional Engineers l

13A-22 l -

RBS FSAR RESUME JAMES A. - WRIGHT, JR.

SUPERVISOR - MECHANICAL ENGINEERING EDUCATION School and Location Major Date Degree North Carolina State Mechanical 1971 BS University, Raleigh, Engineering North Carolina EXPERIENCE Gulf States Utilities Company

1. Supervisor - Mechanical Engineering - 6/82 to present Responsibic for the Mechanical Engineering Section of Nuclear Plant Engineering, all mechanical equipment and systems at River Bend Station, all changes' to the design of mechanical equipment and systems before and after commercial operation, and assuring current and future designs are operable and licensable.

Tennessee Valley Authority, Knoxville, Tennessee

1. Technical Supervisor - Mechanical Design Group - 9/79 to 5/82 Responsible for all piping systems and . regulating mechanical high-pressure piping for nuclear facilities. Thorough knowledge of all ASME codes and compliance requirements for govermental agencies. Approved

.all engineering drawings, coordinated all design work, and coordinated with all'contractorc for four separate units. Supervised 25 employees

-(including contract employees) and also served as Administrative Supervisor.

2. Mechanical Engineer - 1/72 to 8/79 Engineer involved in the conception and design of the Bellefonte Nuclear Power Plant. Responsible for locating most of the major pieces of equipment related to the main turbogenerator, the feed pumps and turbine, and the main condenser equipment. Responsible for the design of all systems and design criteria related to this equipment. System engineer on the main feedwater systems, heater drains and vents, condensate demineralizer, miscellaneous connections to the turbogenerator, and feed pump injection ater,

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,' RBS FSAR RESUME ERWIN J. ZOCH SUPERVISOR - NUCLEAR ENGINEERING EDUCATION (

School and Locction Major Date Degree Texas A&M University Nuclear 1972 BS College Station, TX Engineering EXPERIENCE

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1. Supervisor - Nuclear Engineering - 10/16/82 to present Responsible for the Nuclear Engin(ering Section of Nuclear Plant Engineering, all nuclear equipment and systems at River Bend Station,

. all changes to the design of nuclear equipment and systems before ,

l and after commercial operation, and assuring current and future designs are operable and licensable. i

2. Lead Nuclear Engineer - 4/1/79 to 10/15/82 Responsible for nuclear engineering aspects of the design of the River Bend Station.

Engin2er - 7/2/73 to 4/1/79

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Texas Electric Service Company 1.: Junior Engineer - 6/70 to 8/70 Responsibic .for performanc,e tests, and design projects, and reports. -

PROFESSIONAL DATA

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, 2 Membership in Texas Society of Professional Engineers  !

Hembership in American Nuclear Society .

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2. Assistant Chief _ Engineer - Duane Arnold Nuclear Power Plant -

8/71 to 11/76 Responsible-for various aspects of operation, maintenance, and technical support of the 550 MWe BWR. Responsible for various aspects of plant organization and personnel selection.

Additional responsibilities included Chairman of the Operations Review Committee,' Emergency Director, Security Director, Training Director, Pre-Operational and Startup Test Coordinator, as well as being directly responsible for the operating plant quality assurance program.

3. Nuclear Design Engineer'- Duane Arnold Nuclear Power Plant - 8/70 to 8/71.

Responsible for assuring the design of nuclear oriented systems conformed to AEC standards, including review of P&ID's functional control diagrams, equipment specifications, and layout drawings.

Also_ responsible for the primary containment leak rate test and detailed layouts of the NSSS main control room and radwaste control room panel.

PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE

1. Staff Engineer - Seabrook Nuclear Station - 4/69 to 8/70.

Responsible for liaison between Production and Engineering Departments ensuring proper operating and maintenance considerations would be incorporated into the design. Reviewed equipment specifications and drawings, involved in writing technical specifications and the' inservice inspection program, participated in DRL meetings with~AEC for the construction permit.

YANKEE ATOMIC ELECTRIC COMPANY

1. Plant Reactor Engineer - 2/65 to 4/69 Responsible for all reactor and secondary plant performance ediculations, special nuclear material accountability, writing of refueling procedures, and technical specifications and reactor component inspections. Conducted all photography work for maintenance records and reports and taught reactor theory to reactor operator candidates.

NEW ENGLAND POWER COMPANY

1. Technical Assistant to Superintendent of the Salem Harbor Generating Station - 1/62 to 2/65.

13A-36

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P1 ' 'CLEVITE C0kP0 RATION

21. Mechanical Engineer in training - 3/61 to 1/62 Worked on cost reduction in production, research, and quality control departments.

RAYTHEON CORPORATION

1. . Mechanical Engineer - 9/59 to 3/61 Involved.in design and control of complex automatic machinery assembly.

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RBS FSAR RESUME PHILIP D. GRAHAM ASSISTANT PLANT MANAGER-SERVICES EDUCATICN School and Location Major Date Degree Old Dominion Universitv, Electrical 1973 BS Norfolk, Virginia Engineering Additional Courses or Training Naval Nuclear Power Training School and Prototype - 1974 NRC BWR and PWR Technology Course, including simulator training -1979 Lead Auditor Training and Certification as a QA Lead Auditor - 1980 Training in Operational Quality Assurance Program - 1980 Probabilistic Risk Assessment Training - 1980 Procurement Quality Assurance Training - 1981 Effective Management Training - 1982 EXPERIENCE Gulf States Utilities Company

1. Assistant Plant Manager - Services - 9/83 to present Responsible for the management of River Bend Station's Administrative, Technical, and Security sections of the plant staff.
2. Director - Quality Assurance - 5/81 to 8/83 Responsible for QA activities at River Bend Station including the monitoring of Stone and Webster's QA program.
3. Technical / Administrative Assistant to the Senior Vice President of River Bend Nuclear Group - 1/81 to 5/81.
4. Operational QA Supervisor - 3/80 to 1/81 Developed the Final Safety Analyjis Report Section 17.2 - QA during Operations and the Operational QA Manual for River Bend Station Operation Phase.

U.S. Nuclear Regulatory Commission

1. Operations Inspector - 11/78 to 3/80 13A-38

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. Performed various inspections in areas of pre-operational and startup testing, refueling, refueling-startup, and Operations l Maintenance.

U.S. Navy - 6/73 to 8/78

~ 1. Qualified as Engineering Officer of the Watch, Engineering Duty Officer,' Officer of the Deck and qualified in submarines. Spent 2 years in a submarine refueling overhaul following the construciton and.startup testing:of systems.

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13A-39

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RBS FSAR RESUME PETER E. FREEHILL SUPERINTENDENT OF STARTUP

~ SSISTANT PLANT MANAGER-OPERATIONS EDUCATION United States Navy Nuclear Power School, Nuclear Instrument School, Submarine School, and Submarine Electronics School United States Navy S3G Reactor Prototype Training and Quali-fication as an S3G Naval Reactor Operator - 1961 United States Navy S5W Reactor Design School and Qualification as an S5G Naval Lead Reactor Operator - 1963 United States Navy S5G Reactor Design School and Qualification as an S5G naval Lead Reactor Operator - 1964 AEC Senior Reactor Operator License for SEFOR (1968), Senior Reactor Operator Certification at Fukushima II BWR (1972),

Cooper BWR (1973), and Brunswick II BWR (1975)

M.I.T. Nuclear Power Reactor Safety Course - 1982.

EXPERIENCE Gulf States Utilities Company

1. Superintendent-Startup and Test - 12/80 to present See Sections 13.1.1.1.2.3 and 14.2.2.1.1 for responsibilities.

Assistant Plant Manager-Operations - 11/83 to present See Section 13.1.2.2.2 for responsibilities.

2. Acting Plant Manager - River Bend Station - 6/80 to 11/80

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'3. Operations Manager - River Bend Station - 12/79 to 6/80 i . .. e ,

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GENERAL' 'EI E'CTRIC COMPANY ~

1. Operations Manager - 9/77.to 12/79 Responsible for the performance of preoperations and startup test programs'at'-Fukushima~VI for'the'NSSS and some BOP systems, scheduling and procedure preparation as well as design change preparation.- Acted as the Resident Project Manager in his absense in the management of PCV, NSSS, and turbine construction activities and site administration. -
2. Feedwater Sparger Projects Manager - 4/77 to 9/77

,- Project Manager for the repair of feedwater nozzles and control rod drives and replacement of feedwater spargers at Fukushima I and II. '

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3. Operations Superintendent - 12/76 to 4/77 l Provided lead in problem solving during Brunswick I Test Program, scheduled startup tests, and directed the activities of four Shift Superintendents , five Shift Superintendents In-Training, and nine Preoperational Engineers. Acted for Operations Manager in his absence.
4. Startup Engineer - 4/72 to 11/76 For Dresden II, Fukushima II, Brunswick, II, and Copper directed the performance of preoperation testing, initiated and implemented design changes, and provided on-shift technical direction to utility personnel during the Startup Test Programs through the 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty runs. Certified as a Senior Reactor Operator at Fukushima II, Brunswick II, and Cooper.
5. Operations Analyst - 10/71 to 3/72 Monitored SEFOR plant logs and records for trending and problems; assisted the Operations Manager in day-to-day reactor operation, acting as Operations Manager in his absence. Administered the Plant Surveillance Test Programs; designed the plant decommissioning sodium off loading piping and instrumentation.
6. Shift Supervisor - 1/69 to 9/71 Supervised a crew of four SRO's in the initial fuel load, startup, and 3 year SEFOR Test Program. Authored special test procedures for system' diagnostic tests, and plant design changes for both cost savings and reliability /functionability enhancement.

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7. Senior Reactor Operator - 5/67 to 12/68 Participated in the preoperational testing of SEFOR and received a Senior Reactor Operator's License on .the facility. Authored complete nuclear and process instrumentation set point list; plant operating, casualty and emergency procedures and comprehensive breaker and controller index. .

United States 71avy' "I2/59; t6' 5/67-~ ~"'""' " -- " - -"- " " - "

1.- Electronics Technician First Class / Reactor Operator on three naval' submarine reactor plants. Last position was a Lead Reactor Operator of the'S5G submarine prototype reactor.

-PROFESSIONAL DATA

_ Member of the American Nuclear Society Member of the. Louisiana Nuclear Society w

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n RBS FSAR i RESUME MAXEY F. CASSADA' RADIATION PROTECTION / CHEMISTRY SUPERVISOR EDUCATION ,

' School and-Location Major: Date Degree University of Nebraska, Business .

1980- 2achelor Omaha,. Nebraska Administration General Studies Additional Courses or Training

' Navy Nuclear Power' Training Program - 1961/62 Advanced Health Physics - Rockwell International - 1976 Respiratory Protection Workshop - Los Alamos Scientific Laboratory _- 1978 .

Radiological. Health Physics Course - University of Lowell - 1979 Nuclear Electronics Technology Update - General Atomics - l'981 Radioactive Waste Management Workshop - ASME/EPRI - 1981/82 Radiation ^ Protection Training - INPO - 1982 Radiation Issues for the Nuclear Industry - AIF Environmental Conference - 1982 Assessment of environmental releases of radioactivity - University of Washington at. Seattle - 1982 Radiation Dosimetry Course --Louisiana State University - 1983 Chemistry Managers' Workshop - INPO - 1983 Industrial Water Treatment Seminar - Betz Laboratories - 1983 TLD Workshop - Panasonic - 1983 ,

-Pund&mentals of Ground-Water Quality Protection Workshop - 1983

' EXPERIENCE 3

Gulf States Utilities Company .

1. Radiation. Protection / Chemistry Supervisor - 5/80 to present Responsible for the development and management o'f the Radiation

" " lFrotection, Environmentalahd Chemistry Programs (acquired Chemistry

-Program in March 1983) at River Bend Station to support the fuel loading, licensing and. operation of the plant.

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Responsible'for the development and direction of the Radiation Protection Program prior to fuel load and throughout seven years of operation.

U.S. Navy.

1. Radiological Controls Officer - Nuclear Support Facilities in the Naval Nuclear Submarine Program - 10/65 to 9/72 Management of the Radiation Protection, Radiochemistry, Environmental, Dosimetry and Training programs and staff at two nuclear support facilities which provided radiological support and

-systems repairs for 16 nuclear submarines.

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2 .' ~ Senior Engineering Laboratory Technician - USS George Washington Ballistic Submarine 6/62 to 9/65 Responsible for the Radiation Protection, Radiochemistry, and Chemistry Program during two years of operating and one year of refueling and maintenance. Qualified on all nuclear 'lant p watch stations including Engineering Duty Officer.

PROFESSIONAL DATA Senior member of the Institute of Environmental Sciences Member of the National Helath Physics . Society (served on Public Information Committee from 1978 to 1982)

Member of the Deep South. chapter of the Health Physics Society Member of the Louisiana Nuclear Society i l GSU representative on the EEI Health Physics Committee, INPO, and EPRI

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RBS FSAR RESUME CHARLES P. BOGOLIN OPERATIONS SUPERVISOR EDUCATION Scnool and Location Major Date Degree George C. Wallace Arts 1959. AA Community College Dotham, Alabama Louisiana State History Presently classified University, Baton a senior in the BA Rouge, Louisiana program Additional Courses or Training Naval Submarine School - New London, Connecticut - 1961 Naval Nuclear Power School - Bainbridge, Maryland - 1963 Qualified on General Electric's Dig Land PWR and Westing-house's S5w Submarine PWR.

' ' bairyland ' Power Cooperative RO Course (RO License #2442 in May 1968 and qualified on the Lacrosse Bwr)

Alabama Power Company SRO Course (SRO License #3134-1 in December 1977 and qualified.on the Joseph Farley PWR.)

Westinghouse Nuclear Power Training Program and PWR Simulator Qualification - Zion, Illinois 11/72 to 8/73 Currently undergoing SRO certification training program with Gulf States Utilities Company for River Bend Station EXPERIENCE Gulf States Utilities Company

1. Operations Supervisor - 8/81 to present See Section 13.1.2.2.3 for responsibilities
2. Senior Shift Supervisor - 1/81 to 8/81 As assistant to the Operation Supervisor, the responsibilities of Senior Shif t Supervisor included the execution of directives from the Operatione Supervisor as well as being directly responsible fer the operating staff (see Sections 13.1.2.2.4 and 13.1.2.2.5 for additional details.)

13A-44

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A_labama Power Company

~ 1. Shift Superrisor - Joseph Farley Nuclear Power Plant - 10/77 to 1/81 Responsibilities included lesson plan development in selected system, development of system operating and emergency operating procedures, and work in system valve and pipe ordering, tagging, and labeling activities. Completed hot license training. Received SRO license in December 1977 (Renewal in December 1979) and commenced shift work in 1978 on an 829 MWe PWR.

2. Shift Foreman - Joseph Farley Nuclear Power Plant - 6/75 to 10/77 Assisted in startup testing and operations
3. Operations Department - Joseph Parley Nuclear Power Plant - 11/72 to 6/75 Supported construction activities and completed Westinghouse Nuclear Power Training Program in Zion Illinois (11/72 to 8/73)

Dairyland Power Cooperative

1. Reactor Operator - Lacrosse Bwr Nuclear Power Plant - 1967 to 1972.

Trained for a reactor operator's license on the Lacrosse 50 MWe Bwr Nuclear Power Plant (9 months). Worked as a licensed reactor

. operator at the Lacrosse Bwr, involved in operation of reactor controls turbine generator controls, and turbine atid reactor auxillary systems. Also involved in all initial testing prior to servicing to the Dairyland Power Coop. grid.

United States Navg - 1959 to 1967

.1. USS Carbon Arrow Diesel Submarine - 1961 to 1963.

2.- USS John C. Calhoun Fast Attack Submarine - 1964 to 1967.

3. Remainder of naval service time was' devoted to training and Laupporting qualifications to serve aboard submarines.

13A-45 y'

9 RBS FSAR RESUME JOE L. BURTON GENERAL MAINTENANCE SUPERVISOR EDUCATION School and Location Major Date Degree Mississippi State Nuclear 1973 BS University, Engineering Mississippi State, Mississippi i Louisiana State Nuclear 1979 MS University, Engineering ,

Baton Rouge, Louisiana '

Addit nal Courses or Training Combustion Engineering's PWR Course - 1973 NUS Corporation's Introduction to Nuclear Power Course - 1974 Louisiana State Universitf's Improving Project Management (1977) and Maintenance Management (1979) Course in their MBA Program American Management Association's Appraising Management Efficiency Course - 1982 Southern Methodist University's Assertiveness Training Course - 1983 GSU Personnel Training Courses in Management Skills, Productivity, Interviewing, Speech, and Communications Computer Software Knowledge in Neutron Transport, Statistics, and Optimization Code. ,

1 EXPERIENCE ,

Gulf States Utilities Company

1. General Maintenance Supervisor - 2/84 to present.

See Sections 13.1.1.1.2.4, 13.1.2.1.2 for maintenance section descriptions and 13.1.2.2.9 for responsibilities.

2. General Maintenance Supervisor - Louisiana Station - 7/79 to 2/83.

Similar responsibilities as currently described at River Bend Station, except Louisiana Station consisted of 12 gas units.

3. Engineer - Power Plant Engineering and Design - 2/79 to 7/79.

13A-46 '

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Project Engineer responsible for developing co-generation projects with industrial consumers. Involved in conceptual designs, engineering, contractual / financial details, and licensing.

4. Engineer - Consumer Services - 8/77 to 2/79.

Same responsibilities as in Power Plant Engineering and Design; however, as conceptusi projects grew in size and approached completion, reorgt.nization occurred.

5. Engineer - Power Plant Construction - 7/76 to 8/77.

Involved in the initial site preparation of River Bend Station and environmental modifications required at Louisiana Station.

6. Engineer - Louisiana Station - 9/74 to 7/76.

Staff Engineer providing station operations support.

7. -Engineer - System Production - 6/73 to 9/74.

Staff Engineer providing system operating support.

PROFFESSIONAL DATA

' Professional Engineer in Texas (Nuclear) and Louisiana (Mechanical).

Master thesis publication entitled "An Analysis of !!autral Beam Injection \ Penetrations in Current Tokamak Designs."

ANS Summer 1980 Transactions publication entitled " Neutral Beam Injection: Penetrations."

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RBS FSAR RESUME LIONEL R. THOMPSON INSTRUMENTATION AND CONTROLS SUPERVISOR EDUCATION Prait & Whitney Aircraft Company's Electronic Technician Apprentice Course - 1967 United States Air Force's Guidance System Mechanics School, Basic Electronics Program, and a variety of Technical Seminars Bentley Nevada Corporation's Vibration Systems Seminar University of Maine's Introduction to Microprocessors Course Westinghouse Corporation's Electro-Hydraulic Governor System Seminar Parker-Hannifin Corporation's Tube Fitting and Fabrication Seminar Combustion Engineering Corporation's Reactor Protection System Seminar and Control Element Drive System Seminar Analysis and Measurement services' Industrial Thermometry Seminar and Sensor Response Time Testing Seminar Gulf States Utilities Company's Computerized Plant Maintenance and Material Maintenance System Seminar, as well as courses in management, productivity, interviewing, and assessor /

appraisal training Southern Methodist University's Training for Manager's Course American Management Associations' Improving Managerial Skills for the new or prospective manager course

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EXPERIENCE GULF STATES UTILITIES COMPANY

1. Instrumentation and Controls Supervisor - 11/81 to present.

See Section 13.1.2.2.10 for responsibilities.

2. Instrumentation and Controls Foreman - 8/80 to 11/81.

The acting Instrumentation and Controls Supervisor responsible for developing philosophies concerned with procedure development (surveillance, device, administration), spare parts

! evaluation, building layouts, FSAR review for compliance to NRC regulations and a primary standards laboratory traceable to the NBS. Also responsible for establishing hiring practices and interviewing staff personnel at all levels including the General Maintenance Supervisor and the Electrical Maintenance Supervisor.

13A-48 O

w Maine Yankee Atomic Power Company

1. Instrumentation and Controls Technician - 1970 to 1980.

Responsible for assuring that the instruments installed were in accordance with specifications. Made loop checks of the equipment (both pneumatic and electrical) and corrected for errors when necessary. Ccmpleted initial calibrations of equipment for proper operation and control. Provided technical assistance during start-up of the plant maintenance equipment on a periodic and failure rate.

Pratt & Whitney Aircraft Company

1. Electronics Technician Instructor - 1967 to 1969.

Upon successfully completing the company's 6,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> Electronic Technician Apprentice Course in November, 1967, was assigned as an Electronics Instructor with responsibility for educating two separate classes ranging in size to fifteen students each. Curriculum included virtually all phases of Electronics, including: Basic Mathematics, Physics and Electricity, with additional curriculum in: Hydraulics, Chassis Construction, Technical Report Writing, Numerical Controls, Reading and Interpretation of Blueprints and Schematics.

Additional responsibilities included preparation of curriculum, training guides, and recommended texts (within established guidelines); Administration and Evaluation of examinations; Liaison with Foreman and Supervisors to monitor and evaluate student performance in shop assignments. . -

2. Electronics Technician Apprentice - 1964 to 1967.

Concerned with electr'onic assignments including electrical construction and maintenance, electronics construction and maintenance, and design and development. Also worked with a variety of electronics shops and provided both internal and external liaisons when required.

United States Air Force - 1960 to 1964

1. Airman First Class / Guidance System Mechanic.

Supervised eight Electronics Technicians concerned with checkout and maintenance of Falcon air-to-air missiles and associated supporting equipment for two Squadrons.

4 13A-49

Olin Mathieson Chemical Corporation

1. Hot Roller - Nuclear Fuels Divisions - 1959 to 1960.

PROFESSIONAL DATA Member of Stepney Lodge #133 A.F. & A.M., Bristol Lodge

  1. 74 A.F. &'A.M.

Member of Lincoln Chapter #3 R.A.M.

' Member of American Legion Poet 54 Member of Indian Mound Jaycess Member of Nuclear Power Plant Institute of Engineers e

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RBS FSAR RESUME CRAIG H. GREENE TECHNICAL SUPERVISOR EDUCATION School and Location Major Date Degree Louisiana State Electrical 1973 BS University,- Engineering Baton Rouge, Louisiana Nuclear 1978 MS Engineering EXPERIENCE Gulf States Utilities

.1. Technical Supervisor - 2/83 to present.

See Section 13.1.2.1.4 for Technical Section - escription and 13.1.2.2.12 for responsibilities.

2. Reactor Systems Supervisor - 1/80 to 2/83.

Responsible for the engineering subsystems. Related to the NSSS. Acting Technical Supervisor from 8/80 to 2/83.

3. Electrical Engineer -'5/78 to 1/80.

' Technical Section, Electrical Staff Engineer. Acting Technical Supervisor Crom 11/78 to 2/80.

Los Angeles Department of Water and Power

1. Electrical Engineering Assistant - Power Design and Construction Division, Factory Inspection Section - 9/74 to l' 11/75.

Responsible for the inspection of electrical machinery, equipment, and systems to the requirements of department procedures and specification, state and local codes, as well as engineering standards.- Participated in the investigation of installation or performance of equipment in large projects in order to detect problems and recommend changes. Also participated in liason and field contract administration as well as assisting in new employee training.

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Barbay Engineers, Inc.

1. Electrical Engineer - 7/73 to 9/74.

Responsible for the design and layout of various electrical systems incorporated in sugar refineries. Participated in computer programming and debugging for electrical relay protection of motors, motor control centers, and transformers for Exxon Refinery in Baton Rouge including manual load calculation, coordination, plotting and analysis. Work also included fault calculations, one line diagramming, and physical layouts of motor control centers. Also coordinated with other disciplines involved in the design of such systems.

PROFESSIONAL DATA Member of the American Nuclear Society Louisiana State Radio and Television Technicians License c -

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RBS FSAR

  1. ' RESUME ,

DAN WILLIAMSON REACTOR ENGINEERING SUPERVISOR EDUCATION 4

School and Location Major Date Degree

' University of Florida,. Nuclear 1978 BS Gainesville,. Florida Engineering *

. Additional Courses or Training General Electric's STDSA (Startup & Test) Course - 1978 Honeywell's Process Computer School - 1980

. General Plysics STA Certification Course - 1980 Georgia Power Company's Middle Management School - 1981 Georgia Power Company's SEO Training - SRO

~-

License SOT-20087 - 1983 EXPERIENCE

Gulf States Utilities' Company
l' . Reactor Engineering Supervisor - 2/84 to present

-Responsible for ensuring maximum fuel utilization for cost effective plant operations, and ensuring fuel warranty and NRC requirements are not violated during reactor maneuvers-and operations.

Georgia Power Company

. Reactor Engineer / Shift' Technical Advisor

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Duties at the' Hatch Nuclear Power Plant included training new engineers, writing group procedures, policies and practices, assisting the supervisor, coordinating special plant task

' groups. Also sarved as Assistant Site Computer Engineer.

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i RBS FSAR RESUME DAVID L. DAVENPORT PLANT SECURITY SUPERVISOR EDUCATION School and Location Major Date Degree University of Nebraska Law Enforce- 1970 BS Omaha, Nebraska ment and Corrections Additional Courses or Training

- South Carolina State Law Enforcement Division's Private Security Instructor's Course ATF's Bombs and Exploalves Seminar EXPERIENCE Gulf States Utilities Company

1. Plant Security Supervisor - 1980' to present. .

(See Section 13.1.2.1.6 and 13.1.2.2.15 for responsibilities.)

Sizemore Security International, Inc.

1. Director - Coastal Region - 1978 to 1980.

~ ~

Responsible for the development of the region, acquisition of new business and the hiring and training of personnel.

Achieved a 1000 per cent growth rate over an 18 month period.

Georgia Power Company

1. Sup.rintendent - Uniform Security - 1978.

Supervised the activities of 240 uniformed security personnel through seven plant security supervisors at two nuclear and five hydro / fossil power plants. Member of planning group for development of security at the nuclear sites. Designed programs, established goals, and developed procedures.

2. Nuclear Plant Security Supervisor - Edwin I. Hatch Nuclear Power Plant - 1977 to 1978.

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9 Supervised 74 proprietary security officers responsible for the protection of a nuclear plant with one operating reactor and one reactor under construction. Conducted daily liaison with plant management. Ensured compliance with all rules, regulations and procedures of the Nuclear Regulatory Commission as applied to security.

United States Army - 1957 to 1977

1. Commissioned from Infantry Officer Candidate School in 1963, as an Airborne Infantry Private. Final position (Military Police Corps -Major) was as commander of a Criminal Investigation Division District supervision 85 criminal investigators and

., support personnel. 'While in service, attained a top secret security clearance.

2. Additional work while in military service included:

a._ Instructor in Self Defense and Apprehension Techniques to two training classes of Georgia Power Company Security Officers.

b. Instructor in Report Writing to Special Agents of the Georgia Office of Internal Revenue.
c. Police Science Instructor, Central Texas College, Europe.

PROFESSIONAL' DATA JMember of the American Society for Industrial Security _

(Certified by the Society as a Protection Professional).

Member of the International' Association of Chiefs of Police.

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.i RBS FSAR RESUME E. LINN DRAPER, JR.

SENIOR VICE PRESIDENT - EXTERNAL AFFAIRS EDUCATION k

School and Location Major Date Degree Rice University ---

1964 BA Houston, Texas .

Rice University Chemical 1965 BS Houston, Texas Engineering Cornell University Nuclear Science 1970 PhD

  • Ithaca, New York & Engineering EXPERIENCE.

Gulf States Utilities Company

1. Senior Vice President - External Affairs - 10/82 to present.

Responsible for the Public Affairs, Legal Services, and Rates &

Regulatory Affairs Departments of Gulf States Utilities Company. Chairman - Nuclear Review Board for River Bend Nuclear Group.

'2. Senior Vice President - Engineering and Technical Services -

9/81 to 10/82

3. Vice President - Nuclear Technology - River Bend Nuclear Group

- 5/80 to 9/81 , . . .

4.. Vice President and Technical Assistant to the Chairman of the Board - 2/16/80 to 5/.1/80.

Responsible for managing the research and development budget and for keeping the baairman up-to-date on alternate energy technologies, specializing in nuclear applications.

5 Technical Assistant to the Chairman of the Board - 2/1/79 to 2/16/80.

Same as above.

TEACHING EXPERIENCE

1. .The University of Texas at Austin - 1969 to 1979. ,

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2. Cornell University - 1966 to_1968.

[ 13A-56

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- CONSULTING ACTIVITIES NuTex Corporation Lower Colorado River Authority

. City of Austin Texas Electric._ Service Company Dallas Power and Light

~ Central Power and Light Atomic Industrial Forum

, E. R. Johnson Associates-Niagara Mohawk Power Corporation

.Public Service Electric and Gas -

Florida Power and Light San Diego Gas and Electric

_ Rochester Gas and Electric Public Service of Oklahoma Wisconsin Electric Power ,

Consumers Power

-" No on Propositon 15" Committee

-Hill'and Knowlton Westinghouse' Electric Corporation

' Radiation Management Corporation Leadership Foundation American Nuclear Energy Council Swiss: Atomic Energy Agency '

Future World

, Ecological Analysis, Inc.

South Dakota. Humanities Foundation '

Argonne. Universities Association Oregonians Against the Ban "No on'4-6" National Science Foundation ,

- . City Public Service Board

.Arbrook, Inc.

' Freedom Forum Pennsylvania Electric Association West Associates ,

~

' PROFESSIONAL DATA

. Member of the American Nuclear Society (specializing in Nuclear _ Engineering)

--+,

, Vice President / President.- Elect of the American Nuclear

- Society - 1984/85.

Member of the American Physical' Society (specializing in Fusion Engineering)

' Member of the American Institute of Chemical Engineering ,

(specializing in Neutron Physics) 13A-57 3 Rx: _

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r Member of the Texas Association for Radiation Res, arch

-(specializing in Reactor Physics)

Registered Professional Engineer - State of Texas Served as Expert Witness-(7 occasions)

Published 2 books, 48 major publications, 13 minor publications w

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.RBS FSAR RESUME JAMES H. DERR, JR.

VICE PRESIDENT - POWER PLANT ENGINEERING AND DESIGN EDUCATION School and Location Major Date Degree Williamson' Trade School ---

1940 Trade Media, Pennsylvania ADDITIONAL' COURSES OR TRAINING Hays Combustion School correspondence course McNeese University courses in Advanced Algebra Louisiana State University courses in Electrical Fundamentals University of Michigan course in Business Administration - 1966 Gas - Cooled Reactor course in San Diego, Calif. - 1968

. Stone and Webster Management Training Course - 1976 EXPERIENCE Gulf States Utilities

1. Vice Dresident - Power Plant Engineering and Design - 9/77 to present.

Responsible for fossil site selection for Gulf States Utilities as well is any site work necessary for construction permits.

' ~

He is also responsible for providing engineering support to all fossil units, and RBS as requested by Nuclear Plant -

Engineering.

Coordinates the fossil plant environmental programs, any support requested by K3NG; Gulf States Utilities Fosearch and Design efforts into wind and solar power, coal gasefication, and hydrological / geothermal protects; as well as providing plant services and studies to all fossil units. Member of RBNG Nuclear Review Board (NRB) .

, 2. Manager - Power Plant Engineering and Design - 1975 to 1977.

-Responsible for the engineering and design aspects of all fossil units as well as the nuclear units at River Bend Station and Blue Hills.

13A-59.

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3. Manager - Construction - 1971 to 1975.

Responsible for all Gulf States Utilities fossil and nuclear unit design, engineering, and construction. Involved in

_ obtaining the construction pennit for RBS.

4. Superintendent - Construction - 10/70 to 10/71.

L5. Construction Engineer - Power Plant Construction - 1/65 to 10/70.

6. Maintenance Supervisor - Sabine 5' cation - 6/61 to 1/65.

Involved in 2 startups.

7. Test Supervisor - Nelson Station - 6/58 to 6/61.

Involved in 3 startups.

8. Test Engineer - Riverside - 10/54 to 6/58.
9. Assistant to Superintendent - Louisiana Station - 1951 to 10/54. -
10. Test Department - various jobs - 1/48 - 1951.
11. Office Engineer - 1/45 to 1/48.
12. Department Clerk - 1/43 - 1/45. ,

13.~ United States Navy, San Diego, Calif. - 11/41 to 1/43.

Attached to the Seaman Guard responsible for Naval Base security.

14. Student Engineer - 7/,40 to 11/41.

PROFESSIONAL DATA Member of the Louisiana Engineering Society.

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DIRECTOR -

QUALITY ASSURANCE SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR QUALITY QUALITY OPERATIONS QUALITY ENGINEERING SYSTEMS QA CONTROL QUALITY QUALITY QUALITY QUALITY CONTROL ENGINEERS ENGINEERS ENGINEERS INSPECTORS (1) MECHANICAL (2) LEAD AUDITORS (4) SENIOR ENGINEERS (1) MECHANICAL (1) ELECTRICAL (2) AUDITORS (8) VARIOUS ENGINEERS (1) ELECTRICAL (1) WELD /NDE (1) WELD /NDE (1) I6C (1) I&C (1) RECEIVING FIGURE 17.2-1 QUALITY ASSURANCE ORGANIZATION RIVER' BEND STATION' ;' UNIT 1 h

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. RBS FSAR L .;a : QUESTION 260.1 (17.2)

_ - :./

Provide an organization chart which clearly identifies all major "onsite" and "offsite" organizational elements which function under the coc:lizance .of the QA program (such as design, engineering, procurement, manufacturing, construction, inspection, test, instrumentation and control, nuclear engineering, etc.), and describe their respon-sibilities if not already identified in the SAR.

RESPONSE

Figures 13.1-1 Y cnd 17.2-1 Revised /l Fig. 13.1-21 identif es the organizational elements s of GSU as either "onsite" or "offsite." A descriptior. of their responsibilities is provided in Sections 13.1 and 17.2.1.

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0 Amendment 5 Q&R 17.2-1 August 1982 g

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