Text

Applicant Exhibit A-7,consisting of Forwarding Amend 39 to Plant FSAR
	ML20078F679
Person / Time
Site:	Vogtle
Issue date:	01/05/1995
From:	Rice P; GEORGIA POWER CO.
To:	;
References
	OLA-3-A-007, OLA-3-A-7, NUDOCS 9502020211
	Download: ML20078F679 (40)
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November 23, 1988 i

U.S. Nuclear Regulatory Commission File: X7N00.0-39 Attu.: Document Control Desk Log GN-1502 4

Washington, D.C.

20555 NRC DOCKET NUMBERS 50-424 AND 50-425 OPERATING LICENSE NPF-68 CONSTRUCTION PERMIT NUMBER CPPR-109

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V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2

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FSAR AMENDNElfr NUMBER 39 i

Gentlemen Georgia Power Company, acting on its own behalf and as agent for Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and the City of 4

Dalton, Georgia, hereby submits Amendment 39 to the Vogtle Electric Generating Plant (VEGP) Final Safety Analysis Report (FSAR).

The changes resulting from this amendment are identified in the Attachment.

These changes are applicable to both Unita 1 and 2.

All substantive changes, for Unit 1, were evaluated as required by Title 10 CFR 50.59. This==andment contains all the known processed changes for Unit 2 as of October 31, 1988.

Due to the time lag associated with the as-built notification process, not sil of the FSAR figures have been updated in this amendment. Our submittals to the staff, as noted in the Attachment, do contain the information on drawing modification sheets and provide the appropriate cross references to the affected FSAR figures. Your staff will be notified should the final drawin5s asteria11y differ from what was previously provided.

In accordance with the requirements of Title 10 CFR 50.30(f) and i

Title 10 CFR 50.4(b), one (1) signed original and thirty-seven (37) copies of Amendment 39 are submitted for your use. Also in accordance with the requirements of Title 10 CFR 50.4(b), copies of Amendment 39 are being sent to the NRC Regional Office and the NRC Resident Inspector.

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1 U.S. Nuclear Regulatory Commission File: X7N00.0-39 November 23, 1988 Log:

GN-1502 Page 2 Should you have any questions on the enclosed submittal, do not hesitate to contact me.

Yours truly,

^3 P. D. Rice SWORN AND SUBSCRIBED BEFORE ME, THIS h DAY OF November

, 1988.

/ h

'NofanifPublic Alabama State at Large b

2W My commission erpires PDR/sm Attachment xc: NRC Regional Administrator NRC Resident Inspector FSAR Distribution List l

l 1548V

ATTACIDENT Amendment 39 Changes Reason for Chante FSAR Section (s)

Catesory*

i 1.

Implementation of ATWS 1.3, 1.6, 3.2, 7.2, 7.3, 2

requirements (AMSAC).

7.7, 9.5.1, 9A, 10.2 NRC approval by letter dated 10/3/88.

2.

Conformance to 10CFR73.2(a)

Table 1.8-1 2

rather than SRP recommended RG 5.12, see Security Plan.

3.

Invoking revision 2, 4/87, 1.9.8 2

of RG 1.8.

NRC Technical Specification approval by letter dated 11/1/88.

4.

Clarification of HEPA and 1.9.52, 1.9.140, 6.4.5, 3

carbon filter testing and 6.5.1, 9.4.1, 9.4.2, conformance to TS.

9.4.3, 9.4.4, 9.4.5, 9.4.6 f

5.

Update analysis to reflect 2.2.3 3

newly installed diesel and gasoline storage tanks at the warehouse.

i 6.

Completion detail information, 2.5.4.5 3

placement of undocumented fill i

in nonsafety related area.

7.

Liquid and dry radwaste system 1.2, Table 3.2.2-1, 7.6, 2

and facility changes as 9.1, 9.2, 9.3, 9.4, notified to the NRC in GN-1461, 10.4.6, 11.2, 11.4, 6/14/88 and GN-1472, 8/1/88.

11.5, 12.3 8.

Missile protection of DG fuel Table 3.5.1-7 3

lines included under " Cat 1 piping and elec. cables" 9.

Reflect addition of drain lines Figure 3.6.4-1, 3

to support LLRT.

Table 6.2.4-1, Figure 6.2.4-1 P

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' ATTACHMEE Page 2 Reason for Chante FSAR Section (s)

Catenory*

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10. Update figure sheets to reflect Figures 3.6.1-1-& 2 2

use of fabricated nonstandard tees. Nonairror Unit 2 break I

locations as notified to the NRC in GN-1495, 9/29/88.

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11. Leak Before Break revisions.

3.6.1, 3.6.2, 3.9.N.1, 2

NRC approval in SSEE-7.

5.4.14 12.

Incorporation of WESTAT 3.9.B.1 3

Computer Program.

13. Reflect design detail, changed Table 3.11.N.1-1 3

Veritrak to Tobar pressure transmitter in steam line.

14. Reflect results of grid 4.2.3 3

strength tests of Inconel grids.

15. Unit 1 Cycle 2 change to 4.3, 6.3, 6.5, 9.1.4, 2

reflect the incorporation of Chap. 15, Appendix 155 PMTC. NRC Technical Specification approval by letter dated 10/4/88.

16.

Unit 2 boron increase to 6.1.1, 6.2.2, 6.3.2, 3

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2600 ppa to provide consistency 6.5.3, 15.4.6, 15.6.5 with the Unit 1 Cycle 2 change.

Includes reanalysis of boron dilution transients.

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17. Update containsent coating Table 6.1.2-2, 6.2.5 3

estimates and revised hydrogen generation analysis.

18. Revised LBLOCA analysis.

6.2.1, 15.6.5 3

19. Clarify that inspections of the 6.2.2 3

containment spray system will be done to code rather than a blanket commitment to inspect l

by radiographic means.

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3 ATIACHMENT Page 3 Reason for Change FSAR Section (s)

Catetory*

20.

Changed step sequence for 6.3.2 3

switch over from injection to sump recirculation due to sump pH concerns.

Design _ detail change, RHR discharge cross connect valves vented.

21.

Control room HVAC changes for 6.4, Table 6.4.2-1, 7.3.6, 2, 3 two unit operation. Notified Table 7.3.6-2 to the NRC in GN-1461, 6/14/88.

Technical Specification approval by letter dated 8/17/88.

22.

Design change to reflect 7.3.5, 9.4.2 3

channel blocks to prevent unwanted FHB ventilation actuation.

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23. Allow use of single RAT to 8.3.1, Q430.59 3

provide both class 1E buses in modes 5 and 6.

24. Text " dynamic analysis" 9.1.2 2

changed to " horizontal displacement." Wording changed agreement made during 10/3-5/S8 NRC audit of Unit 2 spent fuel racks.

25. Provide description of the use 9.1.,4 3

l and location of the BPRA, RCCA, and thimble plug change tools.

26. Revise method of removing 9.1.5 3

spent fuel pool gate seals by use of fuel handling machine.

Hoist rope is IPS not stainless steel.

Change to load sensing i

system due to operational modifications.

3 e-ATTACHNENT Page 4 Reason for Change FSAR Section (s)

Category

i 36.

Design detail change to feed-10.4.7 5

water control valve and update to reflect plant operating procedures of main FW control valves.

37.

Text reworded to clearly show 11.2.2 3

water quality is ensured by system design and not water treatment process.

38.

Updates to the PERMS 11.5.2, Tables 11.5.2-1, 3

o Detectable ranges per vendor 11.5.2-2, 11.5.2-5, recommendation Table 12.3.4-2 o RE-2565A,B,&C, containment vent monitors are mounted i

on nonseismic duct o ARE-0025 has automatic control function of tripping electric boiler FW pumps o Change in flow rate range indication for radwaste pathway 39.

A11nw manager HP/ches to act 12.1.1 3

as radiation protection manager.

40.

Revise radiation zone maps Figures 12.3.1-1, 2, and 5 3

due to physical plant changek, radwaste changes and addition i

of Unit 2 information.

41.

Changes to reflect revised Chapter 13.1, 17.2 3

corporate and plant organizations.

42.

Changes to reflect revised 13.2 3

training pro 5 ram. Recognize training for approved equivalent badge training at other facilities.

43.

Revised to reference sections Table 16.3-4 3

more consistent with valves' functions / actuation. Valve closure times revised to not exceed maximum allowable.

t ATTACHNENT Page 6 Reason for Change FSAR Section (s)

Category *

44. Reflect organizational changes 17.1, 17C 2/3 l

to Unit 2, under construction, QA Program; response to 425/88-27-02; and GN-1507 j

11/9/88.

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Category:

1.

Editorial changes and/or corrections (not applicable l

for Amendment 39).

2.

Conforming changes and/or changes previously notified to the NRC.

J 3.

Same licensing criteria; different implementation.

4.

Change in licensing criteria (not applicable for Amendment 39).

5.

Non-safety description changes.

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VEGP-FSAR-13 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLI' ANT C

l 13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION i

This section provides information concerning corporate i

organization, functions, and responsibilities, participation in the facility design, design review, design approval, construction management, testing, and operation of the plant.

GPC nuclear operations' corporate and plant organizations are responsible for directing activities at VEGP.

The organizations described in chapter 13 support and report to nuclear operations for assigned activities.

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13.1.1.1 Design and Operating Responsibilities i

i The following paragraphs summarize the degree to which design, construction, and preoperational activities have been accomplished and describe the specific responsibilities and activities relative to technical support for operations.

t 13.1.1.1.1 Design and Construction Activities (Project Phase) 13.1.1.1.1.1 Principal Site-Related Engineering Work.

Principal site-related work such as meteorology, geology, seismology, hydrology, and demography has been developed and is described in chapter 2.

The VEGP preoperational monitoring program is described in the envir*,nmental report; this program establishes a preoperational baseline from which to evaluate future monitoring of environmental effects, i

l 13.1.1.1.1.2 Design of Plant and Auxiliary Systems.

Unit 1 engineering and construction are complete.

As of August 1988, Unit 2 was 90.2-percent complete.

13.1.1.1.1.3 Site Layout with Respect to Environmental Effects and Securitg Provisions.

Site layout with respect to environmental effects is described in chapter 2.

Site security with respect to plant geographical layout and equipment is described in the security plan.

Amend. 16 4/85 Amend. 35 3/98 13.1.1-1 Amend. 39 11/SB

f VEGP-ESAR-13 I

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13.1.1.1.1.4 Development of Safety Analysis Reports.

Overall responsibility for preparation of the Final Safety Analysis Report (FSAR) rests with Southern Company Services (SCS) l Nuclear Support and Quality Assurance Department.

Preparation l

of the individual sections was assigned to the cognizant j

technical groups within Bechtel, Westinghouse, ECS, and Georgia l

Power Company (GPC).

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13.1.1.1.1.5 Review and Approval of Material and Component Specifications.

Project specifications for safety-related

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equipment are reviewed in accordance with the quality assurance program as described in ch, apter 17.

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13.1.1.1.1.6 Procurement of Materials and Equipment.

Procurement of Unit 2 materials and major-engineered equipment j

is complete.

i 13.1.1.1.1.7 Management and Review of Construction Activities.

The project organization reports to the project management I

board, which is composed of senior executives of GPC, SCS, i

Bechtel, Westinghouse, and representatives of'the plant's j

co-owners.

The board reports to the chairman of the GPC board of directors and chief executive. officer.

The vice president-project director (VP-PD), located.at the jobsite, receives project direction from the project management l

board while reporting functionally to the GPC senior executive i

vice president.

He is the_overall project manager and has comprehensive line responsibility for design, construction,

' licensing, procurement, startup, and other project activities.

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t Reporting to the VP-PD are the project licensing manager (PLM),

j Vogtle proje.ct engineering manager (VPEM), manager-project i

support (MPS), vice president-Vogtle project construction (VPC),

l the project comptroller, the Unit 2 project startup manager, the

.special projects manager, the general manager-Vogtle project i

prudence, and the readiness review manager.

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f Amend. 16 4/85 Amend. 24 6/86 Amend. 29 11/86 Amend. 35 3/88 13.1.1-2 Amend. 39 11/88 i

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VEGP-FSAR-13 13.1.1.1.2 Preoperational Activities 13.1.1.1.2.1 Development of Human Engineering Design objectives and Design Phase Review of Proposed Control Room Layouts.

The VEGP control room was designed using a reduced size control l

board and CPC operator input into the control board control configurations.

The design incorporated the human factor design i

criteria at that time.

An independent evaluation on human factor design has been performed on a mockup of the control room.

-A detailed discussion of control room design review and human engineering factors is described in chapter 18.

Design recommendations based on the mockup review.were i

incorporated in the control board design or deferred for further.

evaluation.

A detail design review was conducted on the l

as-built control room and utilized the plant simulator, j

l 13.1.1.1.2.2 Development and Implementation of Staff Recruiting and Training Programs.

The operating staff is described in subsection 13.1.2.

Recruiting of personnel to fill these positions started in 1977.

Unit 1 is essentially fully staffed.

Training programs have been developed for this facility and are described in section 13.2.

13.1.1.1.2.3 Development of Plans for Initial Testing.

The general manager-nuclear plant (GMNP) is responsible for all aspects of the initial test program of the VEGP.

As part of his responsibilities, the GMNP (or his designee) will direct the development of the startup manual.

The startup manual defines the startup organization,. defines the responsibilities of involved organizations and personnel, delineates the qualifications necessary for startup personnel, and contains the administrative controls necessary for the implementation of the initial test program.

Also, refer to paragraph 13.1.2.2.5 for a discussion of the initial test program.

The administrative controls, qualification for testing personnel, and other required procedures for conducting that k

l part of the initial test program after fuel load will be j

included in the plant procedure manual or startup test l

procedures manual.

Amend. 16 4/85 Amend. 24 6/86 Amend. 35 3/88 13.1.1-3 Amend. 39 11/88

VEGP-FSAR-13 13.1.1.1.2.4 Development of Plant Maintenance Programs.

The work force assigned to the VEGP will provide qualified maintenance personnel prior to initial fuel loading.

Structures, systems, and components that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public will be maintained in accordance with the quality assurance program.

The maintenance staff will be sized to perform the routine and preventive maintenance workload.

The staff will be supplemented by outside contractors as deemed appropriate by plant management.

Maintenance is performed under the direction of cognizant supervisors and in accordance with accepted work practices.

The scope and frequency of the preventive maintenance will be based on past experience with similar equipment and the manuf acturer's recommendat3 ;ns.

Records will be kept to establish the maintenance history of major safety-related equipment.

Maintenance and repairs will be performed by qualified personnel in accordance with written work orders, maintenance procedures, standing orders, vendor technical manuals, and/or applicable codes and regulations.

Qualified maintenance personnel will possess the skills to perform work without detailed written procedures.

Except for emergencies, maintenance work will be preplanned.

Training meetings will be held to foster safety awareness and quality of workmanship.

13.1.1.1.3 Technical Support for Operations The GPC nuclear support (Vogtle) organization has overall l

authority and responsibility for assuring the availability of, providing, or securing adequate technical support for the VEGP.

Technical support for the operation of GPC's nuclear power plants has been established and is functioning for its Hatch Nuclear Plant.

Similar support capability is being planned and will be provided for the VEGP.

This capability will be available through the joint efforts of the GPC nuclear support (Vogtle) general l.

office staff and GPC's architect-engineer / service company, Southern Company Services (SCS).

SCS's support will be provided through an onsite nuclear plant support group, a dedicated Vogtle nuclear operational / support organization in SCS's home office, and the Nuclear Engineering and Licensing (Vogtle) Department on l

the GPC nuclear support (Vogtle) corporate staff.

The SCS site l

support group will be an adjunct to the SCS home office headquarters' organization.

Portions of SCS's obligations may be fulfilled through the use of outside contractors as discussed below.

Amend. 16 4/85 Amend. 24 6/86 Amend. 35 3/88 13.1.1-4 Amend. 39 11/88

f VEGP-ESAR-13 i

In fulfillment of these responsibilities, the GPC nuclear support (Vogtle) organization interfaces directly with, obtains services from, and holds SCS accountable for various assigned support activities which normally include the following:

Architect-engineering services required for the design-engineering of plant modifications, including maintenance-related design changes, plant improvement-related design changes, and design changes or major plant additions as a result of new regulatory require-ments and commitments.

These services include both conceptual and detail design, issue and maintenance of design drawings and specifications, review / approval of design change requests, incorporation of as-built notices, procurement, related Quality Assurance functions, etc.

B.

Design-related safety evaluation and analysis.

C.

Safety evaluation and analysis which are not directly related to design, i.e.,

operational requirements, technical specification changes, etc.

D.

Inservice inspection and testing (both planning and actual implementation).

E.

Nuclear fuel procurement.

F.

Nuclear fuel core analysis.

t G.

Generic safety evaluations on prospective licensing issues.

H.

Environmental, health physics, and plant chemistry support.

i SCS currently has an organization in place for its " project phase" (Standard Review Plan terminology) scope of responsibility in support of the design, construction and licensing of the VEGP.

This organization has both home office and onsite responsibilities and capabilities which are being converted into long-term operational support organization to provide the type a

support noted above.

This organization will be inclusive of all major design disciplines and will have the capability to contract for outside specialty technical support where additional expertise is needed and for major surges in manpower needs.

13.1.1.1.3.1 Nuclear, Mechanical, Structural, Electrical, Thermal-Hydraulic, Metallurgy and Materials, and Instrumentation j

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Amend. 35 3/88 13.1.1-5 Amend. 39 11/88 i

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VEGP-ESAR-13 and Control Engineering.

SCS will be the primary source of engineering in these disciplines.

The Nuclear Engineering and Licensing (Vogtle) Department of the GPC b

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13.1.1-Sa Amend. 39 11/88

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13.1.1-Sb Amend. 39 11/88

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VEGP-FSAR-13 nuclear support (Vogtle) organization is responsible for the interface with SCS.

The duties of the maneger-nuclaar engineering and licensing (Vogtle) are described in paragraph 13.1.1.2.2.7.

13.1.1.1.3.2 Plant Chemistry.

Support in the area of plant chemistry is the responsibility of SCS, as discussed in paragraph 13.1.1.1.3.

13.1.1.1.3.3 Health Physics.

Health physics support is provided by SCS as discussed in paragraph 13.1.1.1.3 13.1.1.1.3.4 Fueling and Refueling Ooerations support.

The Nuclear Engineering and Licensing (Vogtle) Department of the nuclear support (Vogtle) organization is responsible for procuring support in this area from SCS and others, as discussed in paragraph 13.1.1.2.2.7.

13.1.1.1.3.5 Maintenance Support.

The Nuclear Maintenance and Support (Vogtle) Department in the nuclear support (Vogtle) organization provides this support as discussed in paragraph 13.1.1.2.2.8.

13.1.1.2 Organizational Arrangement 13.1.1.2.1 Power Supply Organization The senior executive vice president responsible for power supply directs all power plant construction and fossil and hydro generating plant operation.

Included in the power supply organization are organizations of the general manager-fuel services, the senior vice president-fossil and hydro power, and the vice president and Vogtle project director.

1 Amend. 16 4/85 Amend. 24 6/85 Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35 3/88 13.1.1-6 Amend. 39 11/88 j

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VEGP-FSAR-13 i

i 13.1.1.2.2 Nuclear Operations Organization The nuclear operations organization, under the supervision of the executive vice president-nuclear operations, has direct responsibility for the operation and maintenance of GPC's nuclear plants.

The nuclear operations organization consists of the plant operating staffs, the safety audit and engineering review organization, and the nuclear support (Vogtle) organization which provides support in the areas of engineering, licensing, maintenance, and administration.

Engineering support during plant operat. ion will be provided primarily by the SCS Nuclear Plant Support Department.

The SCS Technical Services-Nuclear Department will provide nuclear fuel contract administrative services, reload licensing, and operating licensing support.

The structure of the General Office oraanization is shown in figures 13.1.1-2 and 13.1.1-3 and is described in the following paragraphs.

13.1.1.2.2.1 Executive Vice President-Nuclear Operations.

The executive vice president-nuclear operations, an officer of both Georgia Power Company (GPC) and Alabama Power Company (APC), is responsible to the chairman and CEOs of each company for all aspects of operation of the nuclear generating plants in the GPC and APC syr.cems, as well as technical and administrative support activities provided by SCS.

The executive vice president-nuclear operations directs the senior vice president-nuclear operations in fulfillment of his responsibility.

Amend. 16 4/85 Amend. 24 6/86 Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35 3/88

'3.1.1-7 Amend. 39 11/88

VEGP-FSAR-13 I

13.1.1.2.2.2 Senior Vice President-Nuclear Operations.

The senior vice president-nuclear operations, an officer of both Georgia Power Company (GPC) and Alabama Power. Company (APC),

reports to the executive vice president-nuclear operations.

This individual is responsible for the safe, reliable, and efficient operation of Plants Vogtle, Hatch, and Earley.

The senior vice president-nuclear operations directs the efforts of the vice president-nuclear (Vogtle), the vice president-nuclear (Hatch),

and the vice president-nuclear (Farley).

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13.1.1.2.2.3 Vice President-Nuclear (Vogtle).

The vice s

president-nuclear (Vogtle) reports to the senior vice president-nuclear operations and is responsible for operation and maintenance of Plant Vogtle as well as licensing, engineering, maintenance, and administrative support activities.

The vice i

president-nuclear (Vogtle) directs the general manager-nuclear

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plant (Vogtle), the general manager-nuclear support (Vogtle), and the manager-safety audit and engineering review (Vogtle).

13.1.1.2.2.4 General Manager - Nuclear Support (Vogtle).

The general manager-nuclear support (Vogtle) reports to the vice president-nuclear (Vogtle) and is responsible for corporate support in the areas of engineering, licensing, maintenance, and administration.

The general manager-nuclear support (Vogtle) directs the manager-nuclear engineering and licensing (Vogtle),

the manager-nuclear maintenance and support (Vogtle), and the manager-nuclear administration (Vogtle).

13.1.1.2.2.5 Manager-Safety Aindit and Engineering Review (Vogtle).

The responsibilities of the manager-safety audit and engineering reviev (Vogtle) are described in section 17.2.

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A'iend. 16 4/85 A.?end. 24 6/86

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Amend. 16 4/85 Amend. 24 6/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35 3/88 13.1.1-9 Amend. 39 11/88

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Amend. 16 4/85 Amend. 24 6/86 Amend. 25 9/86 Amend. 26 10/86 Amend. 35 3/88 13.1.1-10 Amend. 39 11/88

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VEGP-FSAR-13 13.1.1.2.2.6 Manager-Nuclear Administration (Vogtle).

The I

manager-nuclear administration (Vogtle) reports directly to the general manager-nuclear support (Vogtle) and is responsible for the following:

A.

Develop and implement a contract administration program to ensure that contractors are properly qualified, appropriate approval of contracts is obtained, contractor performance is monitored, and prompt t

Amend. 35 3/88 13.1.1-11a Amend. 39 11/88

VEGP-FSAR-13 (This page has been intentionally left blank.)

13.1.1-11b Amend. 35 3/88

VEGP-FSAR-13 corrective action is taken when necessary.

Ensure that contracted services can be procured on an expedited basis to support unanticipated needs.

B.

Maintain and ensure implementation of the Nuclear Operations Procurement Policy.

Provide methods to ensure the availability of parts and materials for routine operation and outage Octivities.

Ensure that appropriate criteria are specified in procurement documents and that deviations from those criteria are properly controlled.

Monitor parts and materials usage.

Ensure proper receipt inspection, handling, storage, issuance, and recordkeeping for parts and materials.

Periodically assess materials management activities and facilities and ensure corrective actions are carried out.

C.

Administer a human. resources planning program which identifies staffing needs and providew qualified personnel.

Implement programs to identify and select candidates for employment, transfer, or promotion into positions in the Nuclear Operations Department.

Ensure that effective performance appraisal and fitness-for-duty programs are implemented.

D.

Ensure that records management programs provide for the 24 appropriate handling of engineering and procurement documents, plant and corporate procedures, and other support documents.

Ensure that the program identifies the necessary documents, specifies format and content requirements, designates responsibilities for disposition, provides for appropriate distribution, and provides for the necessary tracking and updating of documents.

Provide facilities for reenrds storage and ensure that procedures exist for monitoring records management performance.

E.

Monitor plant programs for industrial safety.

Ensure the establishment of industrial safety rules and practices.

Review industry and regulatory safety information and incorporate into safety programs.

Monitor plant safety data to identify trends and ensure the implementation of corrective actions when l25 i

necessary.

Monitor plant fire protection program.

F.

Develop and implement the Nuclear Operations Corporate t

Policy, Instruction, and Directive System.

Ensure that corporate guidance is incorporated and that responsibilities are clearly understood by plant and corporate departments.

Amend. 16 4/85 Amend. 24 6/86 13.1.ls12 Amend. 25 9/86

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G.

Establish and implement plans and budgets for meeting

'i the goals and objectives of the Nuclear Administration (Vogtle) Department.

H.

Ensure that work done by and for the n;; clear administration staff is of sufficient quality to ensure reliable service and satisfies the applicable requirements of the QA program.

i k

i Amend. 16 4/85 Amend. 24 6/86 Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35 3/88 13.1.1-13 Amend. 39 11/88 l

VEGP-FSAR-13 13.1.1.2.2.7 Manager-Engineering and Licensing-Vogtle.

The manager-nuclear engineering and licensing (Vogtle) reports to the general manager-nuclear support (Vogtle) and is responsible for engineering and licensing support as well as emergency planning and fuel coordination.

Specific functions include:

Amend. 24 6/86 Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 l

Amend. 35 3/88 13.1.1-13a Amend. 39 11/88

VEGP-FSAR-13 A.

Review, evaluate, and analyze ragulatory information.

Recommend positions on issues applicable to Plant Vogtle.

f Interpret and translate NRC requirements and commitments t

into company standards.

B.

Maintain knowledge of, and respond to, nuclear industry f

issues through regular contact with owners groups, ad hoc groups, and architect / engineer and nuclear steam supply system (NSSS) interfaces.

Review reports of industry 5

experience for events of concern to Plant Vogtle and ensure appropriate preventive measures are taken.

C.

Act as primary company interface with the Nuclear Regulatory Commission (NRC) for Plant Vogtle.

Meet regularly with NRC representatives to maintain effective communication channels.

Communicate company positions on regulatory issues to the NRC.

Respond to NRC requests for information.

D.

Maintain the Vogtle Final Safety Analysis Report (FSAR),

Technical Specifications, Emergency Plan, Security Plan, and other licensing documents.

Provide assistance to the plant staff on questions of interpretation.

E.

Review violations and reportable events and their corrective actions as they affect plant safety or licensing bases.

L

i Amend. 24 6/86 Amend. 35 3/88 13.1.1-13b Amend.-39 11/88

9 4

i VEGP-FSAR-13 i

F.

Direct the engineering organizations supporting Plant.

l Vogtle and hold them accountable for their assigned g

i functions, which include design engineering of plant modifications, design-related safety evaluation and i

analysis, and operations-related safety evaluation and I

analysis.

G.

Ensure technical excellence in the. design process by direct participation in problem-solving and root-cause analysis, establishing design criteria, design verification and validation, control of field deviations, and final approval of designs.

Periodically assess the effectiveness of the design analysis program and incorporate the results into program improvements.

H.

Ensure the existance of design interface controls between different organizations performing engineering work affecting plant design.

These controls include identification of organizational responsibilities, requirements for consistency in the design process, i

establishment of communication channels, conceptual ~ -

design reviews, long-and short-range planning of modifications, work prioritization, controls on procurement specifications and procedures, and coordination of the turnover of modified systems.

I.

Assure that specialized engineering expertise is available as needed.

Assure the availability of i

engineering support for emergency situations.

J.

Ensure that documentation and records'of design-activity are collected,' stored, and maintained.

t I

I

- i Amend. 16 4/85 Amend. 24 6/86 Amend. 25 9/86 Amend. 29-11/86 Amend. 35 3/88 13.1.1-14 Amend. 39 11/88'

VEGP-FSAR-13 K.

Assign project managers to direct and coordinate major and/or complex projects and programs.

Evaluate the project scope and establish the bounds of authority of the project manager.

Ensure that proper authorization of' expenditures is obtained.

L.

Staff the projects primarily with personnel from existing organizations.

Obtain support from contractors if necessary.

M.

Manage the project or program in accordance with its approved scope, ensuring adherence to schedule and budget.

N.

Perform preliminary engineering and feasibility studies as directed by company management.

O.

Review and evaluate industry information and experience, and incorporate lessons learned into engineering activities.

Review plant and equipment performance trends.

P.

Establish and implement plans and budgets to meet the goals and objectives of the Nuclear Engineering and Licensing (Vogtle) Department.

i Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35 3/88 13.1.1-14a Amend. 39 11/88

r VEGP-FSAR-13 Q.

Ensure that work done by and for the Nuclear Engineering and Licensing (Vogtle) Department is of sufficient quality to assure reliable service and to satisfy the applicable requirements of the QA program.

R.

Ensure that specialized nuclear fuel expertise is available as needed, including scheduling, procurement, conversion, enrichment, licensing, and core analysis.

S.

Ensure preparation of plant emergency plans.

Coordinate the planning and execution of emergency drills.

Ensure that an effective training program exists for corporate emergency response personnel.

Act as company interface with federal, state, and local authorities.

Coordinate assessment and improvement of emergency plans.

Develop and implement criteria for emergency facilities and prompt notification systems.

Ensure the existence of procedures for public information exchange.

13.1.1.2.2.8 Manacer-Nuclear Mainrenance and Support (Voctle).

The manager-nuclear maintenance and support (Vogtle) reports to the general manager-nuclear support (Vogtle) and is responsible for the following activities:

A.

Conduct a continuing evaluation of plant maintenance programs.

Identify needed improvements and track their implementation.

Areas to be evaluated include:

preventive maintenance programs, work control systems, surveillance programs, maintenance performance indicators, plant material condition, NPRD utilization, and contracted maintenance services.

B.

Review and evaluate maintenance trends.

Ensure that underlying causes are identified and corrective actions are tracked to completion.

Assess maintenance-related developments and trends in the utility industry for application or impact on Plant Vogtle.

C.

Ensure the implementation of effective maintenance planning and scheduling mechanisms.

D.

Assist in achieving excellence in outage management.

This includes long-term planning for early identification of outage activities, identification of required resources, procurement of outage services, planning of preoutage preparations, monitoring of outage progress and adjustment of outage plans, and evaluation of outage performance.

Amend. 25 9/86 Amend. 35 3/88 13.1.1-14b Amend. 39 11/88 1

VEGP-FSAR-13 E.

Establish and implement Nuclear Maintenance and Support (Vogtle) Department plans and budgets.

Ensure that work done by and for the Nuclear Maintenance and Support (Vogtle) Department is of sufficient quality to assure reliable service and to satisfy the requirements of the QA program.

F.

Manage inservice inspection and testing programs.

i i

Amend. 16 4/85 Amend. 24 6/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35 3/88 13.1.1-15 Amend. 39 11/88

a VEGP-FSAR-13 13.1.1.2.3 Quality Assurance The manager-safety audit and engineering review (MSAER) is responsible functionally to the vice president-nuclear (Vogtle).

The MSAER is authorized to manage the QA program for design, construction, testing, operation, and maintenance and to ensure its implementation in accordance with the requirements of the QA Manual.

The SAER organization is composed of a staff in the corporate headquarters and at the VEGP plant site.

l The SAER organization will not provide technical support (as defined in Section 13.1.1 of Regulatory Guide 1.70) for the j

operation of VEGP.

The activities of the SAER organization are fully described in section 17.2.

Amend. 24 6/86 Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 A. mend. 35 3/88 13.1.1-15a Amend. 39 11/88

l

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I CNANNAAN ANO CEO t

i PRESIDENT h

EXECUTIVE SUNOR vice PRESeENT ExECUTlvE NUCLEJJI OPERATIONS VICE PRESIDENT I

SB00R SENIOR VCE PRESCENT &

VICE PRESIDENT GENERAL unmansag VICE PRES 40ENT YOGTLE PROJECT FOSSIL & HYDRO FUEL SUlvlCES NUCLEAR OPERATlONS DIRECTOR POWER j

unamen i

i i

Amend.

3 1/84 Amend. 16 4/85 Amend. 24 6/86 l

Amend. 25 9/86 i'

Amend. 26 10/86 Amend. 39 11/88 v0cTLE CORPORATE ORGANIZATION GeorgiaPbwer A

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VEGP UNITS 1 AND 2 FIGURE 13,1.1-3.

i a 33-9

EXECUTIVE VICE PRESIDENT NUCLEAR OPERATIONS G, A t

SENIOR VICE PRESIDENT F3UCLEAR OPERATIONS G. A I

I VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT i

NUCLEAR NUCLEAR NUCLEAR (Vogtle)

(Ferky)

(Notch)

G A

G anesesosen i

l i

LEGENO

' Amend. 16 4/85 Amend. 24 6/86 l

A = APC Amend. 25 9/86 i

G = GPC Amend. 26 10/86 l

Amend. 29 11/86 Amend. 35 3/88 Amend. 39 11/88 NUCLEAit OPERATIONS ORGANIZATION eNasc oensnatwee rtAnt VEGP UNITS 1 AND 2

,g g UpeIT 1 Asse UneT 3 FIGURE 13.1.1-2l 2:

VICE PRESIDENT NUCLEAR (V@)

SAFETY REVIEW BOARO I

GENERAL BRANAGER GENERAL RSANAGER NUCLEAR PLANT NUCLEAM SUPPORT W@)

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IIANAGER - SAFETY BAANAGER - NUCLEAR BBANAGER -NUCLEAR ISANAGER - NUCLEAR AUOff & ENG.

ENG. & LICENSING sterTe4WFWWUlf AOG0NIISTRATION STAFF REVIEW WegIIe)

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STAFF STAFF STAFF OBSITE SUPWlVISOR SAFETY AMOIT &

STAFF i

ENG.REVEW I

NIDEPEBIDENT

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ONSITE STAFF SAFETY ENGINEEllING GROUP ONSITE Amend. 15 3/85 Asnend. 16 4/85 Assend. 24 6/06 Assend. 26 Ic/e6 Asnend. 29 11/86 Annend. 35 3/08 Amend. 39 11/98 i

TECHNICAL SUPPORT ORGANIZATION

',,,,,,,,,,,w VEGP UNITS 1 AND 2 useet i asso usset a FIGURE 13.1.1-3i

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