ML20214C867
| ML20214C867 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 02/14/1986 |
| From: | Dewease J HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20214C871 | List: |
| References | |
| CON-#186-128 OL, NUDOCS 8602210302 | |
| Download: ML20214C867 (118) | |
Text
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'86 FEB 20 NO:20 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMISSION gFff g g ,g BEFORETHEATOMICSAFETYAPOLICENSINGBOAR0 In the Matter of )
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HOUSTON LIGHTING & POWER ) Docket Nos. 50-498 OL COWANY, ET AL. ) 50-499 OL
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(South Texas Project, Units 1 )
and 2) )
Affidavit of Jerrold G. Dewease On The Progress of HL&P's Preparations for Operation Of STP Since 1982
- 1. My name is Jerrold G. Dewease. I am employed by Houston Lighting &
Power Company (HL&P) as Vice President, Nuclear Plant Operations. I testified previously in this proceeding on June 16, 1982, as part of a panel with Mr.
J. H. Goldberg. My educstional background and professional qualifications are described in that previous testimony. Since giving that testimony, I have become a Registered Professional Engineer in the State of Texas.
- 2. The purpose of this affidavit is to update the information provided in the testimony Mr. Golterg and I gave in 1982 regarding the operation of the South Texas Project.
- 3. In my testimony in 1982, I stated that HL&P had underway a review of the organizational structure for operation of STP, ar.d that the organizational structure would continue to evolve in response to NRC guidance and industry experience. There have indeed been some changes in the organization since 1982. The current organization is generally described in the attached portions of the Final Safety Analysis Report (FSAR Sections 13.0, 13.1, 13.2, 13.4 and 13.5; Attachment A) and that description is not repeated in this affidavit. 8602210302 e60214 gDR ADOCK O y8
A few recent organization changes are not yet reflected in the FSAR. First, the Nuclear Security Department has been transferred from tL&P's Group Vice President, Administration and Support to the Vice President, Nuclear Plant Operations. Second, within the STP Plant Operations Department, HL&P has created an Outage Management Division. The Outage Management Division will be responsible for the overall planning and scheduling of outage related work including modifications. It will also provide overall management of outages; log, track, and status modification requests and modifications; and maintain capital budget and cost control. Third, the Metrology Laboratory was made a separate section of the Maintenance Division. Finally, a new section responsible for non-power block maintenance, grounds maintenance, and
, janitorial and decontamination laundry services has been developed. This section is called Facilities Services Section. Although it can be expected that, with evolving guidance and experience, additional changes will take place both before and after the commencement of operations, the current organization is basically representative of the eventual plant organization.
- 4. Since my testimony in 1982 there have been various changes in the HL&P organization for Plant operation. On the executive level, Mr. Oprea retired and Mr. Goldberg has become Group Vice President, Nuclear. In addition addition to the Vice President, Nuclear Plant Operations the following managers currently report directly to the Group Vice President, Nuclear:
Special Projects, Nuclear Assurance, Nuclear Licensing, Nuclear Engineering, Engineering Assurance, and STP Project.
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- 5. Within the Nuclear Operations organizatiori there have been several organizational changes. The functions mentioned in the organizational description I provided in 1982 are all addressed in the revised organization, but we have added a few more steff functions and realigned the organization to provide what I believe will be improved lines of management authority.
The most prominent of these changes are reflected in Figure 1, which is a simplified organization chart showing the three departments within Nuclear Operations and the seven divisions and one section within the Plant Operations Department. In 1982 the Plant was managed by a Plant Superintendent who reported directly to the Vice President, Nuclear Plant Operations, as did the Plant Superintendent for the Allens Creek project. Virtually, the entire Plant operations staff for STP reported to the Plant Superintendent through an Assistant Plant Superintendent. In our current organization, as shown in Figure 1, we have a Plant Manager who, along with the Managers of Training and Nuclear Security, reports directly to the Vice President, Nuclear Plant Operations. The Plant Superintendent, the Manager of Outage Management, the Manager of Health and Safety, the Manager of Management Services and the Facilities Services Supervisor report to the Plant Manager. Reporting to the Plant Superintendent are the Managers of Reactor Operations, Chemical l Operations and Analysis, Technical Support and Maintenance. The effect of these changes is to allow the Plant Superintendent to focus on Plant operation and maintenance, free from a number of administrative functions that previously were associated with the Plant Superintendent position, both
! at STP and elsewhere in the industry.
- 6. There have been several changes in the organization of the various divisions reporting to the Plant Superintendent. In 1982 there was a Technical General Supervisor who was responsible for Reactor Engineering, Chemical Operations, Chemiccl Analysis and the Plant Results Engineers. The current organization has divided these responsibilities into two divisions, the Chemical Operations and Analysis Division and the Technical Support Division. Within these divisions there are new support sections. There is also a new Computer Support Section under the Technical Support Division which is responsible for maintenance of the Plant's process computers. The latter section was added because of the increased role of computers in the current generation of nuclear power plants.
- 7. In the Maintenance Division, HL&P has added a Metrology Laboratory Section. The Metrology Laboratory will perform calibration of all measurement and test equipment. Formerly t.his activity was performed under the Instrument and Control Section.
- 8. With the exceptions of Nuclear Security, Outage Management, the Facilities Service Section and the Metrology Laboratory mentioned above, Section 13.1 of the FSAR describes the organizational structure and explains l the responsibilities of each section. There is substantially more detail there than I have included in this affidavit, including the detailed organization charts for two unit operation shown in Figures 13.1-2A through 13.1-2G.
- 9. In the balance of the Plant Operations Department, new sections have been established in both the Health and Safety Services Division and in the Management Services Division. The Health and Safety Division has been subdivided into four sections: Radiological Protection, Radiological Laboratory, Emergency and Safety Services, and Radiological Support. The Radiological Laboratory is one of the few nuclear power plant radiological laboratories to date to be certified for calibration of Gama radiation instrumentation by the National Bureau of Standards under the National Voluntary Laboratory Accreditation Program. The Health and Safety Division is responsible for essentially all of the functions which in 1982 were divided between a corporate Health Physics group and the Plant Health Physics section.
The four sections of the Management Services Division provide word processing, document control, personnel services, information computer services, and other administrative type support to the plant staff.
- 10. The Nuclear Training Department is a full scope training organization responsible for the training activities of the Nuclear Group and will consist of approximately 56 personnel when fully staffed. The Nuclear Training Department is organized into two Divisions and a Staff Group; the Operations Training Division, the Staff Training Division, and the Program Design and Evaluation Section. Twelve of the fourteen man staff of the Operator Training and Simulator Training Sections are NRC Certified Instructors or have been previously licensed as SRO's on operating commercial l nuclear power plants.
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The Program Design and Evaluation Section, headed by a Supervisor, is a staff group of four (4) doctoral or masters level professionals responsible for the design, evaluation and academic soundness of all established Nuclear Training Department training programs. The Section is responsible for the management of the Institute on Nuclear Power Operations (INPO) Accreditation effort and the development and implementation of the Instructor Certification Program.
- 11. In my testimony in 1982 I described the shift organization HL&P envisioned. At that time HL&P anticipated addressing the post-TMI requirement for a Shift Technical Advisor (STA) by providing Shift Supervisors with adequate training to meet the requirements for STA's. Since then we have instead decided to include separate STA's as part of the shift organization.
The shift organization for each unit in operation is shown in Figure 2. The STA's will also serve as Reactor Performance Engineers in the Reactor Performance Section of the Technical Support Division.
- 12. HL&P is emphasizing preventative maintenance in its operations plans. One aspect of the program is the assignment of a systems engineer responsible for the performance of each Plant system. The Computer Support Section and the Metrology Laboratory were also added to enhance the maintenance program. HL&P is a full participant in the INPO Nuclear Plant Reliability Data System, which collects data on nuclear plant component reliability from participating utilities for use in planning equipment maintenance and replacement. In addition, HL&P will maintain its own equipment history and trending program for the Plant and it has developed a j sophisticated spare parts traceability program that is now being used as we l
acquire spare parts. It will provide the information necessary to promptly locate specific types of Plant equipment as the need to do so may arise during Plant operation. Rotating Plant equipment will be vibration analyzed during initial operation and periodically thereafter during Plant operation to detect deterioration and permit corrective maintenance or replacement before failure.
- 13. We have been fortunate to have attracted an experienced staff for the Metrology Laboratory. The Laboratory is in current operation performing the calibration of inspection and test equipment used by Ebasco personnel during construction. In the other sections of the Maintenance Division, HL&P has also been able to attract a core of journeymen with significant nuclear experience and it has an extensive training program for apprentices. We currently intend to seek IP0 accreditation for this apprentice training progracn.
- 14. The maintenance program is being actively implemented on the systems which have been released for testing (currently 41 of the approximately 160 systems have been turned over to the startup group) and we are planning to accomplish turnover of the Unit 1 Turbine Building and Fuel Handling Building early enough to obtain significant experience implementing the operating and maintenance procedures before fuel load of Unit 1.
- 15. The Nuclear Training Department has been devoting a good deal of attention to personnel training. To date, three phases (I through III) of the Cold Licensed Operator Training Program have been completed. Phase IV, On-Site training, is currently in progress. The M1C examination dates are tentatively scheduled for July and November of 1986. We currently have 44 i
personnel who either completed all three phases of the program or possess equivalent experience and training to be eligible for cold licensing.
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In November 1982, we started the Auxiliary Operator Training and Chemical Operator Training Programs (now the Plant Operator Apprentice Training Program). Sixty-three (63) personnel of the Reactor Operations Division have completed the Auxiliary Operator Program with one class of nine (9) personnel in progress at this time. Twenty-five (25) personnel have completed the Chemical Operator Training Program with one class of six (6) personnel in progress at this time.
In January 1985, we completed Fire Brigade Leader Training for fourteen (14) Chemical Operations personnel.
In January 1985, we started the Phase IV, On-Site Training portion of the Cold Licensed Operator Training Program for 44 operations personnel and 11 Shift Technical Advisors (STA's). This program will be completed in July for the first group and in November for the second group. This corresponds to the scheduled date of the cold license exams.
- 16. Prior to the cold license exams and as part of the Cold Licensed Operator Training Program we plan to conduct 24 days of Operating Procedures / Simulator training. When that is completed, we will conduct a Pre-License Review Series and Audit before our personnel take the NRC license examination. We placed enough people into the Cold Licensed Operator Training Program to man both Units 1 and 2. Although we do not expect a 100% pass rate, we are confident that this approach will ensure enough licensed personnel for Unit 1 (24 operators are required).
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- 17. Once the Plant begins operation, our training program is structured to bring people in at the entry level and train them to qualify for the Senior Reactor Operator (SRO) license by means of three programs. The first is the Plant Operator Apprentice Training Program. This program consists of six levels and will take three years to complete. Classroom and on-the-job training is provided in each level of apprentice training. Upon completion of the apprenticeship program, Plant Operators are eligible to enter the Reactor Operator Training Program. This is the second of the three programs. We intend to conduct the program on an annual basis including the required classroom Fundamental / Theory Program, Simulator Training Program, and On-The-Job Training (Shift Experience Training) under the direction of a licensed Reactor Operator (RO). Finally,RO license candidates will complete the Pre-License Review Series and Audit, followed by the MRC license examination.
- 18. The third program is the SRO Training Program. We will conduct the program on an annual basis including Supervisory Skills Training, Advanced Theory Training, Sinulator Training with emphasis on the role of the supervisor and On-The-Job Training (Shift Experience Training) under the direction of a licensed SRO.
- 19. All Plant Operators, RO's and SRO's will undergo retraining on a continuous basis as part of the Operator Requalification Program. We plan to utilize a six-shift rotation which provides that five days in each 42 are used exclusively for training. The Operator Requalification Program will include lectures, simulator exercises, examinations, General Employee Training, Licensee Event Report (LER) review, respiratory training, fire brigade training, procedures review, and supervisory training.
- 20. The plant-specific simulator for STP is located on site, approximately 1/2 mile from the Plant, in the Nuclear Training Facility. The simulator is now operational and is being used in training license candidates.
The simulator will be used in the retraining of licensed operators and, when possible, to support training programs for other personnel. The Simulator Support Section of the Nuclear Training Department is responsible for maintaining and updating the simulator throughout Plant operation.
- 21. Another major activity for Nuclear Plant Operations personnel over the past few years has been the preparation of procedures. Approximately 3500 procedures will be required for Unit 1 operation. Approximately 2000 of the required procedures have been completed. Of the balance, many will be substantially based on start-up procedures which are being prepared by the start-up organization, and will be transferred to Nuclear Plant Operations after start-up testing. Procedure preparation is progressing according to schedule, and will properly support the current schedule for system turnover.
In addition to procedure development, training and experience visits to commercial nuclear power plants, Nuclear Plant Operations personnel have been performing spare parts evaluations and procurement, and development of training materials. Plant personnel are also involved in pre-operational testing. Operators, Electricians, Mechanics, Chemical Technicians and I&C Technicians are assigned as needed. Very valuable experience is being gained by our personnel in this way.
- 22. When I testified in 1982 the Nuclear Plant Operations staff level was somewhat over 100 persons. As of February 1,1986, the Nuclear Plant Operations staff was 491, and we are projecting approximately 675 persons by
the time that fuel is loaded for Unit 1, which is scheduled for June 1,1987.
All of the key staff positions except one (Mechanical Maintenance Supervisor) are already filled with qualified personnel. Most of the positions yet to be filled are for non-professional positions, such as janitors and clerks, or for craft positions. We expect to fill most of the craft positions with personnel now employed in Plant construction. The current staff is close to our planned level and we are confident that H.&P will nave the necessary qualified personnel in-house in time to complete required training before fuel load. -
The qualifications of key supervisory personnel are described in the FSAR, with the exception of two positions which were filled after the most recent y[
FSAR amendment (Amendment 52). These are the Plant Superintendent, Mr. J. W.
Loesch, and the Chemicals Operation and Analysis Superintendent, Mr. T. E.
Underwood. Since Mr. Loesch was formerly Chemical Operations and Analysis Superintendent, his experience is already summarized in Table 13.1-1 of the FSAR. Mr. Underwood holds a BSCE degree and has 8 years of nuclear experience.
- 23. HL&P has made significant progress toward preparation for Plant operation in the organizations outside the Nuclear Plant Operations Department. In 1983 Mr. Mark McBurnett was appointed Supervising Engineer, Operating Plant Licensing, reporting to the Manager, Nuclear Licensing. The Operating Plant Licensing group has been actively involved in development of the Technical Specifications, the Emergency Plan and the Security Plan. It also is responsible for other licensing work related to operations, including Special Nuclear Materials, Source and Byproduct Materials licensing. During
- Plant operation the group will also coordinate preparation of required reports
to NRC. The Nuclear Licensing Department also reviews NRC generated input, including I&E Bulletins, Notices, new regulations, and Regulatory Guides, and INPO Significant Event Reports (SER), Significant Operating Experience Reports (SOER) and Operations and Maintenance Reminders (OW). Information of interest in these documents is sent for action to the appropriate management and technical personnel, including those in Operations. In the Sunmer of 1985, Mr. Ralph Hernanoez was appointed head of the on-site Operations Stpport Engineering Division, which reports to the Manager, Engineering. During Plant operation this organization will number approximately 40; as of February 12, 1986, 22 engineers were assigned. This organization's responsibilities will include management. or maanaw. c.* a..lU'cE'Itab fnip ca;tncs-!n; support for operations, maintenance of as-built drawings and maintenance of the physical model of the Plant. At present they are working on procedure development and pre-service and in-service inspection programs and spare parts engineering support.
- 24. In addition to the on-site engineering support, H.&P will have a nuclear physical design organization responsible for major modifications (anticipated to number approximately 90 personnel). The personnel who are expected to staff the nuclear engineering and construction organizations are generally already working on the Project performing design or construction functions. As the Project progresses toward completion these personnel will be reassigned in accordance with a written transition plan.
- 25. Before fuel is loaded in the Plant, HL&P will conduct tests of the Plant equipment and systems. A separate HL&P organization, called the Startup Group, has been established to conduct these tests. The Startup Manager reports to the Deputy Project Manager. His qualifications are described in Section 13.1 of the FSAR. The Startup Organization is described in Section 14.2 of the FSAR. It includes a number of e n erienced engineers, both HL&P and contract. Plant Operations personnel, including Operators, Chemical Technicians, and I&C Technicians, are assigned to the Startup Group to assist in the performance testing. The Startup Group is now conducting performance testing.
As each Plant system nears completion the HL&P Startup Group, HL&P Project QA, Bechtel Energy Corporation (Bechtel) QA, and Bechtel Engineering jointly review the status of the system to determine what must be done for the system to be ready for testing. This activity includes " walk-downs" of the system to identify hardware exceptions or deficiencies. When nonconforming
! conditions are identified a Nonconformance Report (NCR) is generated. The NCR will be dispositioned by the organization that has design responsibility at the time the nonconforming condition is identified. Depending on the scope of work necessary to disposition the NCR, either IMP Maintenance or the Constructor will implement the disposition of the NCR. Once a system is tested and the test results approved, it will be turned over to Plant Operations.
- 26. My 1982 testimony described the Plant Operations Review Committee (PORC). The changes in the Plant Operations organization and job titles necessitated some change in the composition of the PORC. It is now composed of the Plant Superintendent, Technical Support Manager, Reactor Operations Manager, Maintenance Manager, Chemical Operations and Analysis Manager, Health and Safety Manager, and Operations QA Manager. The PORC advises the Plant Manager on matters important to safety.
The PORC reviews quality-related administrative procedures, proposed changes to the Technical Specifications and safety-related systems, Technical Specification violations, 24-hour notification items, and the Security and Emergency plans.
- 27. The NSRB is a corrrnittee reporting to the Group Vice President, Nuclear. It will be composed of a full time director, senior line managers and such outside expertise as is appropriate to ensure proper overview of the nuclear program. The NSRB will become functional approximately six months before initial fuel load. The functions of the NSR8 are detailed in Section 13.4.2.1 of the FSAR.
- 28. Additional review of Plant operations will be provided by the Independent Safety Engineering Group (ISEG). HL&P currently has under 5,tudy the details of its operation. Our current plan is that the ISEG will report to the Manager of Nuclear Assurance and will be composed of a small staff of on-site, full-time engineering personnel. Its responsibilities will include those specified in NUREG-0737, " Clarification of TMI Action Plan Requirements."
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- 29. A more extensive description of HL&P's organization and programs for operation of STP is contained in Sections 13.0, 13.1, 13.2, 13.4 and 13.5 of Chapter 13 of the FSAR, copies of which are attached (Attachment A). Since the filing of the most recent amendment (Amendment 52, November 15, 1985),
there have been several adjustments to the HL&P organization and program.
Attachment B is a list of changes to pertinent portions of FSAR Sections 13.0, 13.1, 13.2, 13.4 and 13.5 that are necessary to bring those Sections up to date as of Februsry 13, 1986. With the incorporation of the changes listed in Attachment B, the portions of FSAR Sections 13.0, 13.1, 13.2, 13.4 and 13.5 directly pertaining to the nuclear program are true to the best of my knowledge and belief.
3dN K nJnA c rrold G. Dewease State of Texas )
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County of Hatagorda )
Sworn to and subscribed before me this/ day of February,1986.
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, rf Q ' Notary Public SUSAN E. GRANSON NOTARY PueuC. STATE OF TEXAS 4,7 ,
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STP FSAR 13.0 CONDUCT OF OPERATIONS The South Texas Project is owned by Houston Lighting & Power Company (HL&P).
City Public Service Board of San Antonio (CPS), City of Austin (COA), and Central Power and Light Company (CPL) as tenants in common.
HL&P is the project manager of the STP, Units 1 and 2, and as such is respon-sible for the engineering, design, licensing, construction, startup, and oper-ation of the STP units.
For STP Units 1 and 2. Brown & Root (B&R) initially performed the engineering, design, procurement, and construction activities. In September 1981, Bechtel Energy Corporation (BEC) began preparations for assuming responsibility rela- l30 tive to engineering, design, procurement, and construction management.
During the transition period, HL&P coordinated the activities of B&R and BEC to effect an orderly transfer of engineering, design, procurement, and con-struction management responsibilities to BEC.
After transition, BEC became responsible for engineering, design, procurement, h5 and construction management. Ebasco Services. Inc. became responsible for construction. l38 Westinghouse Electric Corporation (Westinghouse) has designed, fabricated, and delivered the Nuclear Steam Supply System (NSSS), turbine generator (TC) unit and its auxiliaries. Westinghouse will also design, fabricate, and deliver 15 the nuclear fuel assemblies for the initial core loading.
13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1.1 Management.and Technical Support Organization 13.1.1.1 Design and Operating Responsibilities. The following para-graphs summarize the degree to which design, construction, and preoperational activities have been accomplished, and describe specific responsibilities and activities relative to technical support for operations.
13.1.1.1.1 Design and Construction Activities (Project Phase) 38 13.1.1.1.1.1 Principal Site-Related Engineering Work -
- 1. Meteorology A preoperational meteorological monitoring program was established at the site in July 1973 to provide those meteorological factors that bear upon plant design, operation, and safety. The program was conducted by NUS Corporation until July 1975, with the responsibility for the program being assumed by the HL&P Environmental Air Quality Division at that time. Data collected through September 1977 was used for design and licensing purposes. The monitoring system continued to collect data until 1982, at which time it was shut down for upgrading in accordance with current requirements. Teledyne Geotech has been retained to design and install the upgraded system, which is expected to 38 be on-line in 1984.
13.1-1 Amendment 38
- 2. Geology and Seismology The geological and seismological investigations and evaluations were conducted by Woodward-Clyde Consultants (WCC). The geotechnical engineering investi-gations and analysis for the plant location and Essential Cooling Pond (ECP) were also conducted by WCC. A major portion of the field boring and sampling program and some specialized laboratory and field studies associated with this work were done by subcontractors under the supervision of WCC personnel. The geotechnical investigations and analysis for the reservoir and reservoir-re-lated facilities were conducted by McClelland Engineers, Inc.
Design and evaluation activities in the plant and reservoir areas in connec-tion with earthwork and foundation construction were conducted by B&R. WCC conducted the foundation verification and geological mapping activities asso-ciated with Category I plant facilities and provided continued consultant ser-vices to B&R for plant area geotechnical design-related issues during con-s t ruc tion. Pittsburgh Testing Laboratory provided quality control inspections and laboratory testing for all plant and ECP area earthwork during construc-tion. McClelland Engineers, Inc. prcrided consultant services and laboratory testing for the reservoir-related earthwork during construction. Overall di-rection of all geological, seismological, and geotechnical engineering studies was by B&R and HL&P.
- 3. Hydrology B&R initially developed the probable maximum flood from offsite areas for STp l38 Units 1 and 2 based upon hydrologic investigations of the Colorado River Basin previously made by the Fort Worth, Texas District Office of the U.S. Army Corps of Engineers (USACE). Physical data, previous reports, and unpublished engineering studies, together with technical guidance, were made available by both the Fort Worth and Calveston District USACE offices. Detailed current l38 information concerning hydrology is given in Section 2.4.
- 4. Demography B&R performed the initial demographic studies relative to population distri-bution near the plant. HL&P has since updated these population distributions 38 based on the 1980 census, see Section 2.1.3 for details.
- 5. Environmental Effects A preoperational monitoring program for STP Units 1 and 2 was developed to en-able the collection of data necessary to determine possible impacts on the en-vironment due to construction activities and to establish a preoperational base line from which to evaluate fu:ure environmental monitoring. This program is described in the STP Environmental Report (ER).
An Environmental Protection Control Plan provides for periodic review of all construction activities to ensure that those activities conform to the en-vironmental conditions set forth in the construction permit. If harmful ef-fects or evidence of irreversible damage are detected by the monitoring program, RL&P will provide the Nuclear Regulatory Commission (NRC) with an analysis of the problem and a plan of action to be taken to mitigate detri-mental effects or damage.
13.1-2 Amendment 38
STP PSAR Preoperational radiological monitoring activities have been initiated. 113 13.1.1.1.1.2 Desian of Plant and Ancillary Documents - Total engineering progress as of January 31, 1984 was 71.1 percent complete overall. l38 13.1.1.1.1.3 Review of Plant Design Features - Design control and reviev l24 is performed in accordance with the Quality Assurance Program for STP Units 1 and 2, as discussed in the Quality Assurance Program Description (QAPD) for the Design and Construction Phase of the South Texas Project and Chapter 17 of 38 the FSAR.
13.1.1.1.1.4 Development of Safety Analysis Reports - Overall respon-sibility for preparation of the Final Safety Analysis Report rests with HL&P Nuclear Licensing. Preparation of individual sections was assigned to the l20 cognizant technical groups within B&R or BEC, as appropriate and within Westinghouse for the NSSS system and nuclear fuel design. 122 13.1.1.1.1.5 Review of Material and Component Specifications - All l24 safety-related project specifications are reviewed in accordance with the QAPT for STP Units 1 and 2 and in Chapter 17.
13.1.1.1.1.6 Procurement of Materials and Equipment - The procurement of material and equipment for STP Units I and 2 is approximately 75 percent 24 complete.
13.1.1.1.1.7 Management and Review of Cotistruction Activities - HL&P Construction Management has performed the following management and control activities at the Construction site since change to Bechtel Energy Corporation on December 16, 1982.
- 1. HL&P constriction personnel monitor field activities in order to assure that STP's construction is in compliance with design and being accom-p11shed by the most expeditious, economical, and safe means possibic.
This monitoring includes: (1) random inspection of ongoing construction activities for conformance to specifications, drawings, and procedures and; (2) general review of the security, safety, and environmental 38 programs. Construction management plays an active part in the resolution of any problem identified during field monitoring. The construction or-ganization provides the action, direction, and coordination required by other groups, internal or external to the Company, for the prompt resolu-tion of these problems.
- 2. The contractor's cost and schedule performance is monitored to keep con-struction management and project management informed of project status.
The construction department evaluates ongoing construction activities for cost and schedule impacts and actively participates in identifying, se-1ecting, and implementing resolutions to eliminate or reduce the effect of such impacts.
13.1-3 Amendment 38
STP PSAR 13.1.1.1.2 Preoperational Activities:
13.1.1.1.2.1 Development of Human Enaineerina Desian Objectives and Desian Phase Review of Proposed Control Room Layouts - The human engi-nearing concepts and objectives used in the control room design have been 3g provided to the NRC as part of the Detailed Control Room Design Review.
13.1.1.1.2.2 Development and Implementation of Staff and Trainina Progress - The training programs to be utilized for this facility are described in Section 13.2. This program is being implemented in accordance with the schedule indicated in that section. Recruiting of personnel to fill these positions is currently taking place.
13.1.1.1.2.3 Development of Plans for the Initial Test Program - The initial plant test program for STP is described in Chapter 14. The infer-nation presented in that chapter is supplemented by the STP Startup Manual and the STP Plant Procedures Manual. These documents provide administrative guid-ance during the initial plant test program and contain instructions and proce- 38 dures which address various test activities. These activities include, but are not limited to, organisation, interfaces, test procedure development, review and approval, schedules, document control, calibration of test equip-ment, housekeeping and system cleaning, test conduct, and deficiency reso-lution.
Nuclear Plant Operations Department (NPOD) procedures for the STP are uti-lined, as appropriate, by Startup to effect a coordinated transition from the startup phase to the operational phase of the project. l44 13.1.1.1.2.4 Development of Plant Maintenance Proareas - Organization of the resident maintenance forces is described in Section 13.1.2, " Operating 1 Organisation." The journeyman and apprentice electricians and their helpers report through foremen to the Electrical Maintenance Supervisor. The jour- 13 neyman and apprentice mechanics and their helpers report through foremen to the Mechanical Maintenance Supervisor. The journeyman and apprentice instru-ment and control technicians report through their foremen to the Instrument and Control Supervisor. A 3-year formal apprenticeship program administered by HL&P, or equivalent training, must be completed for an employee to become a journeyman. Gradual expansion of the work force assigned to the STP will provide qualified and experienced maintenance personnel prior to initial fuel loading. -
The STP maintenance program will enab'le equipment to be maintained in a reli-able condition and satisfy the requirements of the regulatory agencies having i jurisdiction. The maintenance of those 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 requirements of the HL&P Operaticns Quality Assurance Program, i
i 13.1-4 Amendment 44
STP FSAR The maintenance staff will be sized to perform the routine and preventive l13 maintenance work load. The station staff will be supplemented by HL&P central maintenance forces or by non-HL&P contract forces during overhaul and repair of major equipment and systems. Maintenance is performed under the direction of cognizant supervisors and in accordance with accepted work prac-tices and procedures.
The scope and frequency of preventive maintenance will be based on past expe-rience with similar equipuent and the manufacturer's recommendations. Suit-able records will be kept to establish the maintenance history of major safe-ty-related equipment. Written procedures, orders, and instructions which govern maintenance will include sufficient detail to ensure satisfactory com-plation of the work, but will not necessarily include detailed step-by-step delineations of basic skills normally possessed by qualified maintenance personnel. Except for emergencies, maintenance work will be preplanned.
Routine training meetings will be held to foster safety awareness and quality of workmanship.
"13.1.1.1.3 Technical Support for Operations: - The engineering staffs of 27 the Nuclear Engineering and Construction Department will provide the technical support in the areas of nuclear safety, engineering, fuel, and licensing to 4 support the testing and operation of STP. These engineering staffs are Q described in Section 13.1.1.2. 422.
1 The STP plant chemical staff provides radiochemistry support. Health Physics support is an integral part of the Nuclear Plant Operations staff.
l24 If the technical support cannot be provided by HL&P, then a consultant will be 3g retained.
13.1.1.2 Organizational Arrangements.
13.1.1.2.1 Ceneral: HL&P, the project manager of STP, is engaged in the production, transmission, distribution, and sale of electric energy for lighting, heating, cooling, and power purposes to residential, commercial, and industrial customers. HL&P's service area is in and around Houston, Texas, and includes approximately 5,600 square miles. HL&P operates electric gener-ating plants with a total net capability of 12,196 MW, as of December 31, 38 1982. The company has experience in the design, construction, startup, testing, operating, and staffing of modern generating facilities. l24 The corporate organization, which provides line responsibility for operation of the company, is shown on Figure 13.1-1. Ultimate responsibility for design, procurement, construction, testing, quality assurance, and operation of STP rests with the Group Vice President, Nuclear reporting to the Chairman of the Board and Chief Executive Officer. The Group Vice President, Nuclear 44 assigns responsibilities to the various HL&P organizations described below. l38 13.1.1.2.2 Nuclear Plant Operations: The Vice President, Nuclear Plant 124 Operations, reports to the Group Vice President, Nuclear and is responsible 44 for activities related to operation, maintenance, and training of the nuclear generating stations. The Plant operation organization is described in Section 13.1.2.2.
i 13.1-5 Amendment 44
STP FSAR 13.1.1.2.3 Engineering, Construction and Technical Services 13 13.1.1.2.3.1 Nuclear Engineering and Construction: The Group Vice President, Nuclear reports to the Chairman of the Board and Chief Executive 44 Officer and is responsible for power plant engineering, construction, and operation activities as they relate to NL&P's nuclear power facilities. The 13 Nuclear Engineering and Construction Organization is shown in Figure 13.1-3.
124 13.1.1.2.3.1.1 South Texas Project - The Manager South Texas Project, is responsible to the Group Vice President, Nuclear for the management, coor- l44 dination, scheduling, cost control, engineering, construction and startup of the South Texas Project. The STP Department is shown on Figure 13.1-3. 4 The team members are responsible through the Project Management Team, and l 27 ultimately through the Manager South Texas Project, for the technical ade-quacy of work executed in support of STP. Some members of the Project Management Team are assigned to the team by various departments within the HL&P organization. These assigned team members also serve as interfaces be- 24 tween their individual line organizations and the Project Management Team to ensure the accomplishment of the project-related work pertinent to their de-partments.
13.1.1.2.3.1.2 Nuclear Engineering - The General Manager, Nuclear I Engineering, reports to the Group Vice President, Nuclear and is responsible l44 ,
for Nuclear Services and Nuclear Fuel. (Refer to Figure 13.1-3). l27 13.1.1.2.3.1.2.1 Nuclear Servicer - The Manager of the Nuclear Services l41 Department is responsible to the General Manager, Nuclear Engineering, for 27 providing technical support to STP in the analytical and specialized engineering area. These areas include plant and safety analyses, reliability l 38 analyses, N-stamp, and radioactive waste disposal. I 13.1.1.2.3.1.2.2 Nuclear Fuel - The Manager, Nuclear Puel, reports to l41 the General Manager, Nuclear Engineering. He is responsible for the economic analyses, procurement activities, and analytical activities relative to nu- 38 clear fuel. Nuclear Fuel interfaces with the STP management team on fuel related NSSS and balance-of-plant (BOP) items.
13.1.1.2.3.1.3 Engineering Assurance - The Manager of the Engineering l27 Assurance Department is responsible 'to the Group Vice President, Nuclear for l 44 reviewing the technical adequancy of the engineering and design for SIP. l 24 13.1.1.2.3.1.4 Nuclear Licensing - The Manager of the Nuclear Licensing l 41 Department is responsible to the Group Vice President, Nuclear for the l44 development and coordination of nuclear licensing policy for HL&P. He l 19 provides technical direction to project licensing engineers and coordinates 27 the flow of nuclear licensing related information among nuclear groups.
13.1.1.2.3.2 Nuclear Plant Purchasing - The Manager, Nuclear Plant Purchasing, reports to the Vice President, Purchasing and Services, and is responsible for providing project personnel to the South Texas Project in the 39 following disciplines: purchasing, material control, and contract adminis-tration.
13.1-6 Amendment 44
STP PSAR 13 .1.1.2 .3 .3 Environmental Protection - The Manager, Environmental 24 Protection, reports to the General Manager, Fossil Plant Engineering and is responsible for the areas of environmental licensing, air and water quality, l 27 ecology, water resources and nonradioactive waste handling. We is responsible l 38 for preparation of the Environmental Report and the environmental-related por-tions of the safety analysis report. His responsibility also includes acqui- 15 sition of all local, state, and federal permits and approvals, exclusive of NRC licensing. The Division Manager, Environmental Planning and Assessment, l 38 is responsible for supervising the above activities. The Environmental Protection Department is represented on the STP Project Management Team. This 15 individual is responsible for project interface with the Environmental 183 Protection Department. (Refer to Figure 13.1-5). 115 13.1.1.2.4 Nuclear Assurance: The Manager, Nuclear Assurance, reports 49 to the Group Vice President, Nuclear. The Manager, Nuclear Assurance, has the authority and responsibility to identify, initiate, recommend, or provide so-lutions to quality related problems and verify the implementation and effect-iveness of the solutions. This position has the authority to "stop work" for 20 cause in engineering, design, procurenient , fabrication, construction, and operation phases of the nuclear plant. (Refer to Figure 13.1-4). l44 13.1.1.2.4.1 Proiect Quality Assurance Manater - During the STP con- l41 struction phase, the Project Quality Assurance Manager reports directly to the 138 Manager, NA, on all matters related to quality assurance and is responsible l48 for providing the prograssistic direction, and administering policies, goals, objectives, and methods which are described in the Project Quality Assurance 38 Plan.
The Project Quality Assurance Manager has the authority to resolve quality l27 related problems and to verify the implementation and effectiveness of the solutions. He has the authority to "stop work" for cause on any quality-re- 20 lated activity of the South Texas Project.
In regards to STP operation, the functions of this position will be further defined in an updated Section 17.2. 38 13.1.1.2.4.2 Operations ouslity Assurance Manater - The Operations l48 Quality Assurance Manager reports directly to the Manager, NA on all matters related to Operational Quality Assurance. During the pre-operational testing and plant operation phases, he is responsible for providing the programratic 38 direction, and administering policies, goals, objectives, and methcds which will be described in the Operations Quality Assurance Plan.
13.1.1.2.4.3 Technical Services General Superviors - During the STP l48
) construction phase, the Technical Services General Supervisors, reports on all 138 l technical and administrative matters directly'to the Manager, Nuclear Assurance. l48 l He is responsible for performing vendor evaluations, surveys, surveillances.
- and audits for the STP. 38 i
i In regards to STP operation, the functions of this position will be further defined in an updated Section 17.2.
13.1-7 Amendment 48
STP FSAR The QA Organization during STP operation and the Operations Quality Assurance 38 functions are further described in Chapter 17.2 13.1.1.2.5 Safeteam: The Manager of the Safeteam Department reports to I44 the Manager, Nuclear Assurance and is responsible for the investigation of l48 employee concerns.
13.1.1.2.6 System Engineerine: The Vice President, System Operations is l41 responsible for contractual activities related to the design and construction 138 of the switchyard. In addition, he is responsible for the design of the interfaces between the switchyard and the plant electrical auxiliary systems including the main, unit auxiliary, standby and emergency transformers. The Manager, Engineering Design and Development, is responsible for the design of switchyard electrical equipment and protection, and the interfaces between the 15 switchyard and the plant electrical auxiliary system. These include the main, unit auxiliary, standby, and emergency transformers. He is also responsible for specifying generator characteristics to ensure proper integration of the unit into the system. (Refer to Figure 13.1-1).
13.1.1.3 Oualifications. Within HL&P, the persc'n whose job position 3 27 most closely correspor.ds to that identified as " engineer-in-charge" as defined l 24 by ANSI N18.1-1971 is the Group Vice President, Nuclear. His resume is l 44 provided in Section 13.1.1.4. The educction and experience of STP key Project Management and Engineering Team personnel are susunarized in Table 13.1-1. 24 13.1.1.4 Ouslifiestions of Engineerine Personnel. Resumes of key engineering personnel involved in STP are provided in this section. HI.&P 15 organizational charts are provided as figures at the end of Section 13.1.
- 1. Group Vice kresident, Nuclear 44 Name: Jerome H. Goldberg, P.E.
Formal Education:
1953 BS, Marine Engineering - U.S. Merchants Marine Academy 1960 MSNE - Massachusetts Institute of Technology 15 Experience:
1955 - 1964 - Bethlehem Steel Involved in the building of nuclear warships.
1964 - 1971 - General Dynamics During this time Mr. Coldberg became Nuclear Construction Manager and was responsible for the construction of the nuclear portion of four submarines at the Quincy, Massachusetts facility.
1971 - 1975 - Stone & Webster Nuclear Engineer assigned to the Beaver Valley 1 Project.
Became Project Manager of Beaver Valley 1 where he remained until the project was finished in 1975.
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STP FSAR 1975 - 1977 - Stone & Webster Chief Engineer for Engineering Mechanics.
1977 - 1980 - Stone & Webster 15 As Vice-President and Deputy Director of Construction.
Mr. Goldberg was involved in a number of nuclear power plant projects relative to their construction, maintenance and refueling.
1980 - (January) 1985 - Houston Lighting & Power Company l44 As Vice-President Nuclear Engineering and Construction, Mr. Goldberg has direct responsibility for the South Texas 15 Project Nuclear Services, Nuclear Licensing, and other l4g nuclear support activities.
!20 1985 - Present - Group Vice President Nuclear. 44
- 2. Vice President, Nuclear Plant Operations (See Section 13.1.3.2) 38
- 3. Manager, South Texas Project l20 Name: James T. Westermeier Formal Education:
1953 BSENG - U.S. Naval Academy 1959 MSNE - U.S. Air Force Institute of Technology Experience:
1953 - 1957 - U.S. Air Force Various training, operations, and maintenance assignments in Air Training Command and Strategic Air Command; none related to the nuclear power field.
1957 - 1959 - U.S. Air Force Wright-Patterson AFB, Ohio. Graduate student in nuclear 41 engineering, U.S. Air Force Institute of Technology.
1959 - 1961 - U.S. Air Force National Reactor Testing Station Idaho.
Operations / training officer and later officer-in-charge of SL-1 nuclear power plant. Responsibla for research and development, engineering, operation, and crew training functions. Participated in recovery operations following reactor accident.
1961 - 1963 - U.S. Air Force Loaned to New York Operations Office Atomic Energy Commission. Located at Baltimore, Maryland 2-61 to 6-61; Sundance AFS, Wyoming from 6-61 to 2-63. Resident engineer and officer-in-charge of PM-1 nuclear power plant.
Responsible for shop fabrication and testing in plant, shipment en field, installation, initial plant operation, 13.1-9 Amendment 44
l STP FSAR and crew training. Turned operational plant over to Air Defense Command.
1963 - 1963 - U.S. Air Force Electronic Systems Division. Hanscom Field, Mass. Project officer for nuclear power plant portion of hardened, deep underground command and control system. Project cancelled before reaching construction phase.
1963 - 1966 - U.S. Air Force Air Force Weapons Laboratory, Kirtland AFB, N.M.
Responsible for research and development *Drk on Advanced Nuclear Reactor and radioisotope concee i '6'c both aerospace r
and terrestrial applications. Engineeis** support and consultant work, including extensive site work, on various military nuclear power plants.
1966 - 1968 - U.S. Air Force Air Force Technical Applications Center Washington, D.C.
Classified project.
1968 - 1973 - U.S. Air Force Directorate of Nuclear Safety, Kirtland AFB, N.M.
Responsible for regulatory review and inspection of Air Force nuclear reactor, nuclear test, and aerospace nuclear facilities and equipment world-wide.
41 1973 - 1974 - Commonwealth Edison Company Field Engineer, Station Construction Department Zion Station.
1974 - 1974 - Commonwealth Edison Company Project Engineer, Carroll County Station, Units 1 and 2.
Responsible for the preparation of bid specification and evaluation of NSSS proposals, initial site environmental studies, and interface with other participating utilities.
Project was deferred.
i 1974 - 1984 - Commonwealth Edison Company Project Engineer,* Byron /Braidwood Stations, Units 1 and 2.
Responsible for degign, equipment / material / field labor i specifications, licensing, and engineering activities I associated with these stations. Supervised structural, electrical, mechanical, and nuclear engineering groups who coordinated the detail design with the architect-engineer and NSSS contractor. Directs the budget and program aspects of the project; responsible for quality assurance, code compliance, and contractual matters. Coordinates project j activities with construction, production, and other departments within the company.
1984 - Present - Houston Lighting & Power Company South Texas Project Manager 13.1-10 Amendment 44
- 4. South Texas Project, Deputy Project Manager l27 Name: Stephen M. Dew, P.E.
Formal Education:
1968 BSCE - University of Missouri at Columbia Experience:
1968 - 1972 - Babcock & Wilcox Company Fossil and Nuclear start-up engineer; Mr. Dev was instru-i mental in the development of Babcock & Wilcox's PWR test program; supervised the shipment and receipt of B&W's first nuclear fuel shipment to the Oconee Nuclear Station; had considerable involvement with the testing program on fossil and nuclear plants totaling 4300 MWe.
1972 - 1974 - Babcock & Wilcox Three Mile Island d
Established the B&W startup office and continued as startup
" engineer following B&W Systems through all stages of testing and power escalation on TM1 Unit I. 24 1
1974 - 1980 - Stone & Webster Engineering Corporation Mr. Dew was Assistant Project Engineer in charge of the Beaver Valley Site Engineering Office; developed the site project office and procedures which ensure control and responsive support of construction with minimum offsite coordination.
1980 - 1981 - Brown & Root. Inc.
Assistant Engineering Project Manager in charge of the Systems and Equipment Design Group.
1981 - 1984 - Houston Lighting & Power Company l41 Manager, Engineering, South Texas Project, responsible for a
, all engineering activities on STP.
1 l 24
- 1984 - Present - Houston Lighting & Power Company Deputy Project Manager, South Texas Project; responsible for assuring that the construction and start-up phases of the 4g
- project are accomplished in accordance with approved design j and within the approved schedule and budget.
i
- 5. Manager, Engineering Assurance i
j Name: R. A. Frazar Formal Education: '
! 1968 BSCE - Lamar University I
I t
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I I
Experience: 1 l
1968 - 1972 - Monsanto Company Corrosion Engineer in the Material Technology Sectior -
responsible for conductinF corrosion studies and field investigations in support of chemical operations.
1972 - 1973 Manufacturing Department - supervised the operation of a pressurized reaction copolymer resin unit.
1973 - 1974 - Houston Lighting & Power Company Metallurgical Engineer in Quality Assurance.
1974 - 1975 Supervising Engineer for South Texas Project Quality Assurance Program.
24 1975 - 1977 Project Quality Assurance Manager for South Texas Project 1977 - 1981 Manager of Quality Assurance Department - responsible for all HL&P activities related to quality assurance in both the nuclear and fossil plants.
1982 - Present Manager, Engineering Assurance Department - responsible for engineering assurance activities for the Nuclear Engineering and Construction Department.
- 6. Manager, Nuclear Services Name: K. K. Chickara, Formal Education:
1963 BS (Honors) Physics, Punjab University, India 1964 MS (Honors) Physics, Punjab University, India 1972 PH.D Nuclear Engineering, University of Cincinnati, Experience:
1964 - 1966 - Kurukshetra University, India 34 Lecturer in the Physics Department. Taught courses in Thermodynamics, Heat Transfer, Mathematical Physics, etc.
1972 -1974 - Southern California Edison Group Leader, Core and Fuel Analysis - responsible for core operaitonal analysis, technical support, and fuel management of San Onofre Unit 1. Performed nuclear analyses for San Onofore Units 2 and 3 relative to design review and licensing support.
Also worked in the Fuel Supply Department in the areas of fuel cycle economics and fuel contracts.
l 13.1-12 Amendment 44
FTP FSAR 1974 - 1976 - General Electric Coupany
- Senior Engineer involved in the nuclear design of BWR-6 and retrofit of advanced concepts to earlier product lines.
Participated in the development of fuel pptimization models.
1976 - 1985 - Cincinnati Gas & Electric Company Manager, Nuclear Services Department - responsible for managing activities in the areas of independent safety engineering, nu-clear systems and reliability analysis and nuclear fuel.
Responsible for organizing and overseeing the review and eval-untion of design and engineering changes, station operating procedures, emergency procedures and the nuclear safety aspects of plant performance. Responsible for the generic licensing
, issues through the BWR Owners Group. Direct the development of in-house capability in the areas of safety analysis, reliabi-lity analysis, and pro 2nbilistic risk assessment. Direct all aspects of nuclear fuel supply and fuel management. Managed nuclear training until July, 1983.
Manager, Nuclear Fuel and Advanced Engineering Projects -
, responsible for managing activities in the areas of nuclear i fuel, nuclear systens TMI action plan coordination, generation planning, special corporate studies, and R&D coordination.
Special corporate studies included load management evaluations, fuel 71 anning (coal, oil, and nuclear), coal inventory model, and evaluations of various corporate alternatives with finan-44 cial model. Testified as the Company's witness at hearings of the NRC and the Public Service Commission of Kentucky.
Head of Nuclear Fuel Group - responsibilities included nuclear fuel procurement, contract management, economic analysis, core management, and fuel performance. Directed a corporate project on the marginal costs of electric supply in response to an order of the Public Utilities Commission of Ohio.
- 7. General Manager, Nuclear Engineering Name: C. G. Robertson, P.E.
Formal Education:
! 1958 BS - U.S. Military Academy, West Point 1965 MSNE - Massachusetts Institute of Technology 1967 NENE - Massachusetts Institute of Technology 19 i Experience:
1 1958 - 1963 - U.S. Army Artillery Corps 1966 - 1973 - General Electric Company (KAPL Division) l Performed safety analyses and core thermal / hydraulic analyses on the reactors for the Nimitz class attack carriers.
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SIP FSAR 1973 - 1974 - New York Atomic Energy Council Nuclear Facilities Specialist performing technical safety reviews of nuclear power plants located in New York State.
1974 - 1977 - New York State Energy Research and Development Authority Managed the state-wide environmental and technical studies to identify and evaluate sites for major new electrical gen-eration plants. Coordinated and directed the Authority's interests in the West Valley reprocessing plant and waste burial facility.
g9 1977 - 1981 - Stone & Webster Appointed Supervisor of Engineered Safety Systems and Analysis Group in January, 1978. Previously, served as Licensing Engineer for Stone & Webster's Standard Plant (SWESSAR) and in Operations Services Division related to various licensing activities for operating nuclear plants.
1981 - 1982 - Houston Lighting & Power Company Manager, Nuclear Licensing 1982 - Present 27 General Manager, Nuclear Engineering
- 8. Environmental Protection, Divi.sion Man.ger 38 Name: Robert W. Lawhn, P.E.
Formal Education:
1968 BA - University of St. Thomas 15 1973 ME - Texas A&M University Experience: Houston Lighting & Power Company 1973 - 1975 Engineer, Nuclear Division - Assigned to various licensing j activities on the Allens Creek project.
~
1975 - 1977 Senior Engineer, Nuclear Division - Responsible for coor-dinating licensing activities on the Allens Creek project, the South Texas Project and generic subjects. 20 1977 - 1980 Lead Engineer, Environmental Planning and Assessment l Division - Responsible for preparation of Environmental Reports and Emergency Plans for nuclear projects, r
1980 - 1981
( Supervising Engineer, Environmental Planning and Assessment
- Responsible for the technical and administrative 13.1-14 Amendment 44
STP FSAR supervision of environmental licensing activities on nuclear proj ec ts.
1981 - Present 20 Division Manager, Environmental Planning and Assessment -
Responsible for the technical and administrative supervision of environmental licensing activities on nuclear and fossil projects.
- 9. Manager, Nuclear Fuel Name: Thomas M. Sobey Formal Education:
1968 BS Physics - Texas A&M University 1969 MS - Nuclear Engineering - Texas A&M University Experience:
1969 - 1972 - U. S. Army Research Physicist, Lawrence Livermore Laboratory.
His research work supported the underground nuclear testing program being run by the U. S. Government. He left military service with the rank of Captain.
4 Q
1972 - 1974 - Houston Lighting & Power Company 422 Nuclear Fuel Engineer. Promoted to Supervising Engineer' .5 Nuclear Fuel Section in early 1973. Responsible for saper- 27 vising, performing and/or coordinating all company activ-ities pertaining to the nuclear fuel requirements for four planned nuclear power plants.
1974 - 1979 - NUS Corporation Staff Consultant Manager, Nuclear Resource Analysis, and subsequently named Manager, Fuel Supply Services Department.
In this latter capacity Mr. Sobey was responsible for all corporate consulting activities associated with the supply of nuclear fuel. His assignments included supply and demand analyses of the several fuel cycle activities; economic, political and technical analyses of uranium enrichment projects in France and South Africa; contract negotiating i
assistance for procurement of supplies and services; and I
resident consulting to a Brazilian utility for eleven months.
- 1977 - 1982 - S.M. Stoller Corporation l Manager of Special Projects - Worked on a variety of nuclear l
industry related assignments including providing client ser-vices on business aspects and economic potential of uranium properties, and obtaining nuclear fuel related supplies and l
services; supervising the activities of geologists and mining engineers performing technical evaluations of uranium 1
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STP FSAR properties; developing basic structures of joint venture l programs; and assisting in the negotiations of requisite l documents to effect the various fuel related activities. ;
1982 - Present - Houston Lighting & Power Company '
g Manager Nuclear Fuel Department - Responsible for all corporate activities related to nuclear fuel supply and nuclear fuel operations support for STP.
- 10. Manager, Nuclear Assurance 48 Name: J. E. Geiger, P.E.
l Formal Education:
1961 BSIE - State University Sacramento, California Experience:
1957 - 1972 - Aerojet General Corporation, Sacramento, Ca.
1960 - 1964 Manager, Receiving Inspection Planning and Data 1964 - 1968 Manager, Document Center 1968 -'1972 Manager, Quality Systems 1972 - 1974 - Self Employed 24 1974 - 1976 - Yayo Inc., Sacramento, Ca.
Freelance QA Engineer 1976 - 1978 - Argonne National Lab (Ill.)
QA Engineer 1978 - 1981 - Los Angeles Power Division BPC Senior Engineer QA Staff and Supervisor Field Activities 1981 - 1982 - Houston Lighting ti Power Company QA Manager, STP 1982 - 1985 - Manager, QA 48 1985 (April) - Present - Manager, NA
- 11. Manager, Nuclear Licensing 27 Name: Mark R. Wisenburg 13.1-16 Amendment 48
1964 BS - United States Naval Academy 1965 U.S. Naval Nuclear Propulsion Training Program Experience:
1966 - 1975 - U.S. Navy Served en active military duty assigned to various nuclear submarines. Completed qualification as Engineering Officer and served one tour as Executive Assistant to the Deputy Chief of Naval Operations (Submarine Warfare).
1975 - 1982 - U. S. Tennessee Valley Authority 1975-1976 Principle licensing engineer for the Browns Ferry Nuclear Plant. Responsible for the licensing activity required to return the plant to operation following the 1975 fire and for obtaining the initial operating license for Unit 3.
1976 - 1979 Supervisor, PWR Projects Section, Regulatory Staff. 27 Responsible for licensing activities for the Sequoyah, Watts Bar, Bellefonte, and Yellow Creek Nuclear Plants including obtaining a CP for Yellow Creek, preparation and submittal of the Bellefonte FSAR and coordination of the Sequoyah OL review.
1979 - 1982 Staff Nuclear Engineer, Regulatory Staff. Acted as assistant licensing manager for TVA.
1982 - Present - Houston Lighting & Power Company May-Sept. 1982 Special Assistant to Manager, Nuclear Licensing Sept. 1982 - Present Manager, Nuclear Licensing
- 12. Safute.ao Mannger Name: W. N. Phillips Formal Education:
44 1969 Jackson County Junior College (General Coursework) 1973 University of North Carolina (General Coursework) 13.1-17 Amendment 44
STP FSAR 1978 University of Houston (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> towards a B.S. in Mechanical Engineering) 1978 Texas A&M University (Executive Development Course)
Experience:
1963 - 1969 - U. S. Navy Nuclear Power Program Nuclear Power Submarine Operations and Maintenance 1969 - 1969 - Ingalls Shipbuilding Nuclear Inspector responsible for NDE performance to 250-1500-1, mechanical equipment installation checks, hydrostatic testing, machine shop inspection, and claanliness inspection.
1969 - 1973 - Carolina Power & Light Company Assistance Resident Engineer, H. B. Robinson Unit No. 2, single unit, 650 MW nuclear unit until December 1970.
QA Specialist, Brunswick Steam Electric Plant, Southport, North Car'olina, a two unit, 850 MW (each), BVR.
Responsible for the performance of all site QA/QC activities including: NDT performance and review, welding inspection, 40 welding procedure review, fuel inspection, concrete QC activities, coordination for inservice inspection, startup testing, and records.
1973 - Present - Houston Lighting & Power Company Served as a QA Specialist - responsible for the performance of audits, development of QA program documents, and planning for nuclear and fossil project activities.
Served as Supervisor, Support Services - responsible for the management of vendor surveillance and audits of fossil and nuclear projects in support of engineering and procurement activities.
Served as Project QA Manager of the South Texas Project.
Served as Project QA Manager - responsible for the QA management of fossil and nuclear projects from inspection through commercial operations including: licensing, engi-neering, procurement, construction, and startup. This in-cludes the management of approximately 30 people on site and in the home office.
Served as Projects QA Manager - responsible for the QA man-agement of fossil projects. Duties include: planning, l .
13.1-18 Amendment 51
STP FSAR staffing, budgeting, and management of all inspection and QA activities at the construction site, vendors facilities and the home office.
Projects QA Manager - temporarily assigned in support of South Texas Project litigation 44 Manager of the Safeteam Program - responsible for the devel-opment and implementation of the Safeteam Program for the South Texas Project. Duties include: planning, staffing, budgeting, and management of subcontractors for interviewing and investigations.
- 13. South Texas Project, Engineering Manager Name: E. W. Dotson, P.E.
Formal Education:
1963 BSME - University of Cincinnati, Ohio 1969 MSME - University of Akron, Ohio 1976 MBA - University of North Florida Experience:
1959 - 1963 - Diamond Power Corp.
Co-Op Student - Alternating quarters; most of time spent in the Service Department, testing and developing control rod drives and stud tensioners for nuclear power plants.
1964 - 1966 - U.S. Army 41 1st Lieutenant, (Honorable Discharge) - Majority of time spent as Atomic Demolition Platoon Leader, Corp. of Engineers. Later, in Viet Nam, as Assistant S-3 Officer in charge of constructing a hospital at Cam Rahn Bay.
1963 - 1964 and 1966 - Honeywell Aerospace Environmental Engineer - Designed test stand and tested several products including temperature, vacuum, vibration and radiation, often simultaneously.
1966 - 1970 - Babcock and Wilcox Senior Engineer - Some of the work was 1/6 Plastic Scale Model of reactor 7, 19, and 37 tube full temperature and press steam generator models, studies and models of fuel spacers, piping pressure drop and nuclear navy.
1970-1972 - Burns & Roe l Lead Nuclear Engineer for Three-Mile Island, Unit #2 -
Responsible for NSSS interface with B&W and Nuclear related systems. Much the same as above except for fewer systems.
- Supervised two engineers and ten designers.
t i
l 13.1-18a Amendment 51 b
STP FSAR 1972 - 1976' - Westinghouse Lead Nuclear Systems Engineer for Floating Nuclear Plant -
In charge of five engineers and ten designers' work.
Responsibilities included Westinghouse interface for Nuclear Steam Supply Systems. (NSSS), all emergency and NSSS support systems; liquid, gas, and solid radioactive vaste systems; associated HVAC and cooling water systems and other miscel-laneous systems such as radiation monitoring, fire pro-taction, diesels, and leveling and mooring barge.
1976 - 1984 - Florida Power and Light Project Manager, St. Lucie Nuclear Plants - Since Unit #2 vent commercial August, 1983, responsible for Backfit for two 800 MWe Combustion Engineering Nuclear Plants. Maj or effort was Core Barrel repair for Unit #1 scheduled for refueling February, 1984 and being ready for Unit #2 outage in October, 1984. Supervised directly twenty-five Florida Power and Light engineering, cost and schedulb personnel, and 140 architect / engineer and vendor personnel assigned to the site. Previously Project Manager (since 1980), or Assistant Project Manager, totally responsible (even while Assistant) for all engineering, licensing and purchasing, plus support of construction and start-up.
1984 - Present - Houston Lighting & Power Company South Texas Project, Manager, Engineering
- 14. South Texas Project, Startup Manager Name: R. J. Daly, Jr. 'l Graduate Newton Vocational School Navy Nuclear Power School Navy Nuclear Power Training Unit (SIC)
Attended various Navy courses including; Submarine School, Suhmarine Engineering School, Diving School, Officer's Candidate School, Electrical and Electronics School t'd Maintenance and Management School.
Experience:
1950 - 1972 - U.S. Navy Twenty-two years of Naval Service, retired with the rank of Lieutenant Commander. Served in nuclear and conventional submarines in the Atlantic and Pacific Fleets. Entered the Navy Nuclear Program in 1957, attended Nuclear Power School at New London, Conn. and prototype training in the commis-sioning crew of SIC at Windsor Locks Conn, 1972 - 1972 - Power Utility - State of New York James A. Fitzpatrick Nuclear Station - Assigned as a Startup Engineer assisting in the preparation of Pre-Op and mainten-ance procedures.
13.1-18b Amendment 44
STP FSAR 1972 - 1974 - Duquesne Light Co.
Beaver Valley Power Station (900 M.W.) - Assigned as Senior Startup Engineer responsible for the flushing, startup and testing of major NSSS and BOP systems.
1974 - 1977 - Virginia Electric Power Co.
North Anna Unit #1 (900 M.W.) - Assigned as Assistant Startup Manager and subsequently Startup Manager for Unit #1 at North Anna. Responsible for directing all phases of plant startup activities including Cold Hydro, Hot Functional Testing, SIT /ILRT and Startup support of fuel load and initial power escalation testing. Also assisted and advised station personnel in the maintenance of radioactive components.
1977 - 1980 - Stone and Webster Engineering Corporation North Anna Unit #2 (900 M.W.) - Assigned as Startup Manager (Stone and Webster Senior Advisory Engineer) responsible for directing all phases of the plant startup activities in-cluding Cold Hydro, Hot Functional Testing, SIT /ILRT, startup support of fuel load and initial power escalation testing. Joint Test Group (J.T.G.) member representing the Architect / Engineer (Stone and Webster Engineering Corp.).
At the completion of Unit #2 startup was assigned as Special Proj ect Engineer for VEPCO (Virginia Electric Power Co.)
during the first refueling operation of Unit #1 to accom- 41 plish Three Mile Is. backfits and advise on the maintenance of radioactive components.
1980 - 1981 - Westinghouse Electric Corporation Angra Nuclear Station (600 M.W.) Angra dos Reis, Brazil.
Assigned as Lead Mechanical Startup Engineer for Westinghouse Electric Corp. at Brazil's first nuclear power station. Responsible for the overall startup of all NSSS and BOP systems. Directed the day to day activities of 30 Westinghouse and Brazilian startup engineers. Responsibil-i ities included the scheduling of system startup, flushing of all plant systems, preparation of pre-op test procedures, i
Also directed major plant evolutions such as Hot Functional l testing and SIT /ILRT.
1981 - 1982 - Union Electric Co.
Callaway Unit #1 (1200 M.W.) - Assigned as Startup Group Supervisor for all NSSS systems and a major portion of the BOP systems. Responsible for the initial operation and pre-op testing of assigned equipment. Also responsible for directing the day-to-day activities of 25 startup engineers including initial equipment startup, system flushing, proce-dure preparation, pre-op testing and system turn over' to plant operation personnel. Member of the Joint Test Group (J.T.G.). Certified Level Three Tester per ANSI 45.2.6.
13.1-18c Amendment 44
STP FSAR 1982 - 1984 - Public Service Co. of New Hampshire Seabrook Station Unit #1 (1200 M.W.) assigned as Test Group Manager for overall Phase I the Startup and Test activities of a 1200 M. W. Nuclear Station.
Responsibilities include directing initial equipment oper-ation and startup testing, flushing and testing of all plant piping systems including ASME Systems and scheduling of 43 startup activities. Certified Level Tester in accordance with ANSI 45.2.6.
1984 - Present - Houston Lighting & Power Company South Texas Project, Startup Manager 13.1.2 Operating Organization 13.1.2.1 Plant Oreanization. The general plan for staffing STP has the organization as shown on Figures 13.1-2A through 13.1-2G. 38 13.1.2.2 Plant Personnel Resoonsibilities and Authorities. The func-tions and responsibilities of various positions at STP, including a specific l 38 succession to responsibility for overall operation of the plant in the event of absences, incapacitation of personnel, or other emergencies, are described in this section.
13.1.2.2.1 Plant Management:
PLANT MANAGER The Plant Manager reports to the Vice President, Nuclear Plant Operations and 38 has responsibility for plant production and production support activities to ensure the safe, reliable and efficient startup, operations, maintenance and refueling of the STPEGS. Production responsibilities include operations, maintenance, technical support, and chemical operations and analysis. Produc-tion support responsibilities include radiological service, management ser-vices, outcge management, and public relations. He is responsible for adhe- 144 rence to all requirements of the Operating License and the Technical Specifications.
PIANT SUPERINTENDENT The Plant Superintendent reports to the Plant Manager. He is directly respon- 38 sible for all plant production activities including operations, maintenance, technical support, and chemical operations and analysis. He is directly responsible for the safe, efficient, and reliable operation of the STPEGS in accordance with the requirements of the Operating License and the Technical Specifications. He assumes the authority and responsibility of the Plant Manager in his absence unless otherwise delegated.
13.1-19 Amendment 51
STP FSAR 13.1.2.2.2 Reactor Operations Division:
REACTOR OPERATIONS SUPERINTENDENT (SRO)
The Reactor Operations Superintendent reports to the Plant Superintendent and is responsible for the safe and efficient operation of the plant and required support facilities at the STPEGS in accordance with the requirements of the Operating License and the Technical Specifications. He is responsible for orderly operations and compliance with operating procedures. He assumes the responsibility and authority of the Plant Superintendent in his absence unless otherwise delegated.
OPERATIONS SUPERVISOR (SRO)
The Operations Supervisor is responsible for directing the activities of the Reactor Operations personnel assigned to his unit of the STPEGS. He is responsible for assuring the safe and efficient operation of the unit in accordance with the requirements of the Operating License and the Technical Specifications and for compliance with operating procedures. The Operations Supervisor reports to the Reactor Operations Superintendent and the Senior Operations Supervisor on duty assumes the authority and responsibility of the Reactor Operations Superintendent in his absence unless otherwise delegated.
OPERATIONS SUPERVISOR - OUTAGE / SUPPORT (SRO)
The Operations Supervisor-Outage / Support is responsible for the development and periodic review of the plant procedures for his unit of the STPEGS. He is responsible for coordinating his units outage activities between Reactor Oper-ations and other Nuclear Plant Operations Department Divisions. He is respon-sible for coordinating the training of Reactor Operations personnel assigned to his unit. The Operations Supervisor-Outage / Support reports to the Reactor Operations Superintendent.
SHIFT SUPERVISOR (SRO)
The Shif t Supervisor is responsible for directing the activities of the Reac-tor Operations personnel assigned to his unit of the STPEGS during his shift.
He is responsible for assuring that shift operations are performed in accor-dance with approved procedures, the Operating License and the Technical Speci-fications. He authorizes the placement of system, components and equipment in or out of service as required for the safe and efficient operation of the plant as required to meet the Technical Specifications. The Shift Supervisor reports to the Operations Supervisor and may be assigned the authority and responsibility of the Operations Supervisor in his absence.
UNIT SUPERVISOR (SRO)
The Unit Supervisor is responsible for supervising the Reactor Operations personnel assigned to his unit and for directing control room activities to assure safe and efficient unit operation in accordance with the Operating License, Technical Specifications, and approved procedures during his shift.
He is cognizant of all work or tests which may affect the operation of the unit in accordance with administrative control procedures. He directly super-vises control room activities during startup, shutdown, abnormal and emergency 13.1-20 Amendment 38
STP FSAR conditions. He reports to the Shift Supervisor cf his assigned unit and may assume the duties and responsibilities of the Shift Supervisor in the event he should be unavailable.
REACTOR OPERATOR (RO)
The Reactor Operator is responsible for the safe and efficient operation of the control room equipment of his assigned unit in accordance with the Oper-ating License, Technical Specifications, and approved procedures during his shift. He monitors and controls unit parameters and unit equipment from the control room and performs required operational checks and surveillance testc.
He initiates the immediate actions necessary to maintain the unit in a safe operating condition during abnormal and emergency conditions. He maintains required records, logs and charts of unit data, shift events, and performance checks. He initiates requests for equipment repairs and clears and tags equip-ment as directed by shift supervision. The Reactor Operator reports to the Unit Supervisor of his assigned unit.
REACTOR AUXILIARY OPERATOR The Reactor Auxiliary Operator is responsible for safe operation of systems and equipment as directed from the control room of his assigned unit. He
! monitors plant parameters as required to be aware of plant conditions, per-forms required operational checks, initiates requests for equipment repairs, clears and tags equipment as directed and maintains required logs, charts and 38 records of plant data, shift events and performance checks on his shift. The j
Reactor Auxiliary Operator reports to the Shift or Unit Supervisor of his assigned unit.
ADMINISTRATIVE AIDE The Administrative Aide is responsible for tasks of an administrative nature which are required during his shift. He performs those routine administrative duties which will relieve the Shift Supervisor of these duties and processes and routes records, logs and correspondence as required. He reports to the Shift Supervisor on his shift.
l 13.1.2.2.3 Chemical Operations and Analysis Division:
l i
CHEMICAL OPERATIONS AND ANALYSIS SUPERINTENDENT The Chemical Operations and Analysis Superintendent is responsible for chem-ical control of plant primary, recondary, and auxiliary systems. In addition to the performance of chemistry and radiochemistry sampling and analyses, this responsibility includes the operation of water and waste treatment systems including the station makeup water treatment plant, radwaste treatment sys-tems, condensate treatment system and chemical waste treatment systems as well as the conduct of the plant non-radiological environmental control programs 51 and the shipment of radioactive / hazardous waste. He is responsible for assur-ing that plant programs and related procedures are developed and administered to meet plant needs and regulatory requirements for chemical control and environmental discharges. The Chemical Operations and Analysis Superintendent reports to the Plant Superintendent.
1 13.1-21 Amendment 51
STP FSAR CHEMICAL OPERATIONS SUPERVISOR The Chemical Operations Supervisor is responsible for the safe and ef ficient operation of the plant water and waste treatment systems including the station makeup water treatment plant, radwaste treatment systems, condensate and blowdown treatment systems, and chemical waste treatment systems. He is responsible for the safe and efficient operation of these systems, compliance with chemical operating procedures and for developing and implementing radwaste minimization techniques. The Chemical Operations Supervisor reports to the Chemical Operations and Analysis Superintendent.
CHEMICAL OPERATIONS FOREMAN The Chemical Operations Foreman is responsible for the safe and efficient operation of plant water and waste treatment systems on his shift. He is responsible for assuring that chemical operating shift operations are per- I formed in accordance with approved procedures. He authorizes the placement of water and waste treatment systems, components and equipment in or out of service as required to meet plant operating needs. He coordinates chemical operating shift activities with the Shift Supervisor as necessary and consults with the Shift Supervisor, who makes the final decision, on chemical operating shift activities which directly affect the safe operation of the plant. The Chemical Operations Foreman reports to the Chemical Operations Supervisor.
CHEMICAL OPERATOR 38 The Chemical Operator is responsible for the safe and efficient operation of the water treatment systems and radioactive and non-radioactive waste treat-ment systems of his assigned unit in accordance with approved procedures during his shift. He monitors and controls unit water and waste treatment equipment locally and from the radwaste control room and performs required operational checks. He initiates the immediate actions necessary to maintain equipment in a safe operating condition during abnormal and emergency condi-tions. He maintains required logs, charts, and records of pertinent data, shift events, and performance checks. He initiates requests for equipment repairs and clears and tags equipment as directed. The Chemical Operator reports to the Chemical Operations Foreman.
CHEMICAL AUXILIARY OPERATOR The Chemical Auxiliary Operator is responsible for safe operation of water and waste treatment systems and equipment as directed by Chemical Operators or the Chemical Operations Foreman. He monitors equipment operation, performs required operational checks, initiates request for equipment repairs, clears and tags equipment as directed and maintains required logs, charts, and records of per-tinent data, shift events, and performance checks on his chift. The Chemical Auxiliary Operator reports to the Chemical Operations Foreman.
CHEMICAL ANALYSIS SUPERVISOR The Chemical Analysis Supervisor is responsible for directing the plant chem-istry and radiochemistry sampling and analysis program. He is responsible for the laboratory procedures and quality control program and for the analytical 13.1-22 Ameddment 38
STP FSAR results and records of this program to provide accurate and precise informa-tion regarding plant chemistry conditions. He is responsible for assuring that the chemistry of plant fluid systems and environmental discharges are 38 maintained within specifications and permit limitations. The Chemical Anal-ysis Supervisor reports to the Chemical Operations and Analysis Superinten-dent.
CHEMICAL SUPPORT SUPERVISOR I
The Chemical Support Supervisor is responsible for the development, imp 1menta-tion, coordination, and administration of the plant chemical and radiochemical technical support progoram. He is responsible for providing technical and administrative direction to professional subordinates; developing and maintain-ing technical chemistry software; providing recommendation for recovery from abnormal chemistry conditions; and providing specific technical expertise in the areas of radiochemical counting procedures and equipment, corrosion mech-anisms, chemical treatment methods, an defective fuel and core damage asses-ment. The Chemical Support Supervisor reports to the Chemical Operations and Analysis Superintendent.
51 NUCLEAR CHEMIST The Nuclear Chemist is responsible for providing technical assistance in chem-istry and radiochemistry to support the development and implementation of the Plant Chemistry Program. He is responsible for performing corrosion and chem-ical treatment studies, developing improved analystical methods for performing primary system chemistry analyses, and developing and maintaining radiochemi-cal counting software. The Nuclear Chemist reports to the Chemical Support Supervisor.
LEAD CHEMICAL TECHNICIAN The Lead Chemical Technician is responsible for directing the shift activities of the chemical analysis percannel assigned to his unit. He is responsible for supervising and monitoring the performance of chemistry sampling and anal-ysis activities on his shift to assure that they are properly coordinated with other plant groups and are performed by qualified personnel in accordance with
+
' approved plant procedures. He is responsible for verifying that unit chem-istry parameters are being maintained within specifications on his shift, notifying appropriate operations personnel of out of specification chemistry conditions, and for recommending corrective action to be taken. The Lead Chemical Technician reports to the Chemical Analysis Supervisor.
CHEMICAL TECHNICIAN 38
' The Chemical Technician is responsible for performing scheduled and routine chemistry and radiochemistry sampling and sample analysis on his assigned unit, including gross gamma and gamma isotopic analysis, using standard tech-niques and approved procedures during his assigned shift. He is responsible for reporting out of specification chemistry conditions detected on his shift to supervisory personnel. He initiates requests for equipment repairs and maintains required logs, charts, and records of chemistry data, shift events, and analytical results on his shift. The Chemical Technician reports to the Lead Chemical Technician.
13.1-23 Amendment 51 -
STP FSAR 13.1.2.2.4 Maintenance Division:
MAINTENANCE SUPERINTENDENT The Maintenance Superintendent supervises the activities of the Mechanical, Electrical, Instrument and Control, and Maintenance Support Groups. He is responsible for corrective and preventive maintenance for both units and com-mon support facilities of the STPECS. His responsibilities include ensuring that equipment, instrumentation, controls, and mechanical and electrical sys-tems of all plant facilities are maintained at optimum dependability and oper-ating efficiency. He is responsible for ensuring that maintenance activitics are conducted in accordance with approved procedures, regulatory requirements, and applicable policies and directives. The Maintenance Superintendent reports to the Plant Superintendent.
INSTRUMENT AND CONTROL SUPERVISOR The Instrument and Control Supervisor is responsible for plant instrumentation and controls engineering and for directing the proper installation, calibra-tion, testing and maintenance of plant instrumentation and control systems to assure their dependability, reliability and operating efficiency to comply l51 with tions.
the requirements of the Operating License and the Technical Specifica-He is responsible for assuring that instrumentation and control (I&C) activities are conducted in accordance with approved procedures, regulatory requirements and established safety standards. The Instrument and Control 38 4
Supervisor reports to the Maintenance Superintendent.
ELECTRICAL MAINTENANCE SUPERVISOR The Electrical Maintenance Supervisor is responsible for directing maintenance activities on electrical equipment and systems to assure their dependability, reliability, and operating efficiency to comply with the requirements of the Operating License and the Technical Specifications. He is responsible for assuring that electrical maintenance activities are conducted in accordance with approved procedures, regulatory requirements, and established safety standards. The Electrical Maintenance Supervisor reports to the Maintenance Superintendent.
MECHANICAL MAINTENANCE SUPERVISOR l
The Mechanical Maintenance Supervisor is responsible for directing maintenance activities on mechanical systems and equipment to assure their dependability, reliability, and operating efficiency to comply with the requirements of the Operating License and the Technical Specifications. He is responsible for l
assuring that mechanical maintenance activities are conducted in accordance l
' with approved procedures, regulatory requirements, and established safety standards. The Mechanical Maintenance Supervisor reports to the Maintenance Superintendent.
MAINTENANCE SUPPORT SUPERVISOR 1
The Maintenance Support Supervisor is responsible for coordinating the plant preventive maintenance program, for coordinating the planning of plant mainte-nance activities, for administering a program to assure timely and proper 13.1-24 Amendment 51
determination of plant spare parts requirements, for administering the plant lubrication program, tool room, and metrology laboratory, and for providing input to the Nuclear Power Reliability Data System program and equipment his-tory and trending program. The Maintenance Support Supervisor reports to the Maintenance Superintendent.
13.1.2.2.5 Technical Support Division:
TECHNICAL SUPPORT SUPERINTENDENT The Technical Support Superintendent is responsible for testing of plant equip-ment and for providing technical support for plant operation and maintenance as well as managing the plant Technical Specification surveillance program, pump and valve testing program, local and integrated leak rate testing pro-grams, snubber testing program, filter testing program, and vibration testing program. He is responsible for monitoring overall plant and system perform-ance and for recommending necessary actions to improve overall plant and system performance. He also directs the development and implementation of the initial startup test program which encompasses initial fuel loading, initial criticality, low power physics testing, and power ascension testing. The Technical Support Superintendent reports to the Plant Superintendent.
REACTOR PERFORMANCE SUPERVISOR 38 The Reactor Performance Supervisor supervises a staff of engineers who are responsible for the following activities: shift technical advisor program; performance of core physics and thermal hydraulic testing programs; monitoring l 51 or reactor core performance utilizing the plant computer and incore instrumen-tation; special nuclear material accountability; performance of initial startup test program; incore fuel management; refueling technical support; and assuring that receipt, inspection, and storage of nuclear fuel is conducted in accordance with vendor and NRC criteria. He coordinates these activities with operating personnel and with offsite support organizations as necessary. The Reactor dent.
Performance Supervisor reports to the Technical Support Superinten-SYSTEMS PERFORMANCE SUPERVISOR The Systems Performance Supervisor supervises a staff of engineers who are responsible for the following activities: performance testing programs for plant equipment such as pumps, valves, heat exchangers, compressors, and fil-ters; development and implementation of the Technical Specification surveil-lance program and the ASME Section XI pump and valve testing program; system operating data trending; integrated leak rate test (ILRT) and local leak rate l51 test
' (LLRT), coordinating design change request proposals; and providing tech-nical support to other plant divisions. He coordinates these activities with operating personnel and offsite support organizations as necessary. The Systems Performance Supervisor reports to the Technical Support Superinten-dent.
13.1-25 Amendment 51-
STP FSAR PERFORMANCE SUPPORT SUPERVISOR )
The Performance Support Supervisor supervises a staff of engineers and techni-cians who are responsible for the following activities: providing technical 38 and physical support to the systems and reactor performance groups in the per.
formance of periodic, special and startup tests; performance of non-system oriented testing such HVAC testing, snubber testing and vibration testing; and providing technical direction of the plant fire protection program. The Per-formance Support Supervisor reports to the Technical Support Superintendent.
COMPUTER SUPPORT SUPERVISOR The Computer Support Supervisor supervises a staff of engineers and techni-cians who are responsible for the following activities: developing and conducting startup testing of plant computer systems; providing sof tware control on these systems; and maintaining operability of these systems by performance of maintanence and periodic testing. The Computer Support 51 Supervisor reports to the Technical Support Superintendent.
13.1.2.2.6 Health And Saferty Services Division:
HEALTH AND SAFETY SERVICES MANAGER The Health and Safety Services Manager is responsible for managing the plant radiological controls (health physics) program and radiological environmental surveillance program to assure that environmental and radiation control is maintained in a manner to protect employees, visitors, the general public, and surrounding communities. This responsibility includes delineating the operat-ing philosophy and procedures and maintaining occupational radiation exposures as low as reasonably achievable. This position corresponds to the position of
" Radiation Protection Manager" as discussed in Regulatory Guide (RG) 1.8. The Health and Safety Services Manager reports to the Plant Manager. l51 RADIOLOGICAL PROTECTION SUPERVISOR The Radiological Protection Supervisor is responsible for the conduct of the plant radiological control program including control of radiation exposure to 38 personnel, maintenance of related records, conduct of radiological surveil-lance, and implementation of the plant policies and procedures for maintaining occupational radiation exposures as low as reasonably achievable. He reports to the Health and Safety Services Manager.
l51 LEAD RADIATION PROTECTION TECHNICIAN The Lead Radiation Protection Technician is responsible for directing the shift activities of the radiation protection personnel assigned to his unit.
He assures that the radiation protection activities on his shift are properly coordinated with other plant groups and are performed by qualified personnel in accordance with approved plant procedures. The Lead Radiation Protection Technician reports to the Radiological Protection Supervisor.
13.1-26 Amendment 51 aw e- ---- - _ -- - - , +- - - - , - - _ _ _ _ _ _ _ _ -
STP FSAR RADIATION PROTECTION TECHNICIAN The Radiation Protection Technician is responsible for performing scheduled and routine radiation protection activities on his assigned unit, including source calibrations of radiological monitoring systems, analysis of radioac-tive samples for surface contamination, and airborne radioactivity, conducting radiological surveys in the plant and environs, whole body counting, and equip-ment and respiratory testing. He maintains required logs, charts, and records of radiation protection data, shift events, and analytical results on his shift. The Radiation Protection Technician reports to the Lead Radiation Protection Technician.
38 13.1.2.2.7 Management Services Division:
MANAGEMENT SERVICES MANAGER The Management Services Manager reports to the Plant Manager and has overall responsibility for the development, implementation, and administration of the business support programs at STPEGS. This includes the development of an integrated Automated Data Processing Program required to support all plant activities. Inherent to this division is a Production Support Section which coordinates the Work Activity Control Program in regard to scheduling activ-ities, Business Systems which coordinates the Budget and Cost Control Program as well as contract administration, Operations Document Control which coordin-ates the Drawings / Document Control Programs and Adminstrative Services which i provides administrative support. 51 13.1.2.3 Nuclear Assurance. The description of the Nuclear Assurance organization and the role of Operations Quality Assurance are provided in Sections 13.1.1.2.4 and 17.2.
13.1.2.4 Nuclear Training. The Training Manager, Nuclear Training Departuent reports to the Vice President, Nuclear Plant Operations, and is 44 responsible for the overall, management and administration of the company's, Nuclear Training program. (Refer to Figure 13.1-2H).
13.1.2.5 Operating Shift Crews. The minimum operating shift crew for STPEGS will be listed in the Technical Specifications.
In addition to the operating shift crew a Radiation Protection Technician will be onsite at all times when fuel is in either reactor to ensure that adequate 38 radiation protection coverage is provided for station personnel. He will inform the Shift Supervisor of radiological conditions of the plant.
A site Fire Brigade of at least five non-licensed personnel who may have nor- [24 mal shift duties, but are trained specifically in fire protection, will be maintained onsite. 38 13.1.3 Qualifications of Nuclear Plant Personnel Key personnel assigned to STP will have had extensive experience in steam electric stations in their respective areas of responsibility, and they will 13.1-27 Amendment 51
__ . ~_ _ _ _ _ _ _ _ . _
STP FSAR be given nuclear training where necessary to prepare them for their specific assignments at the plant. Section 13.2 discusses the nuclear training program j for these personnel. j 13.1.3.1 Qualification Requirements. The qualification requirements for plant supervisory, operating, technical, and maintenance support personnel at STP meet or exceed the guidance given on personnel qualifications contained in RG'l.8 with clarification provided in Table 3.12-1.
l 51 13.1.3.2 Qualifications of Plant Personnel. Resumes of Nuclear Plant 38 Operations Department managerial personnel are provided in this section.
' Resumes of additional plant managerial and supervisory personnel are maintained on file at the plant.
- 1. Vice President, Nuclear Plant Operations Name: Jerrold G. Dewease, P.E.
Formal Education:
1960 BSEE - Christian Brothers College t Experience:
1960 - 1968 - Memphis Light, Gas and Water
- Electrical Engineer and later as Assistant Electrical Main-tenance Supervisor at the T.H. Allen Electric Generating
] Station; Mr. Dewease was involved in providing engineering support and technical guidance to the electrical maintenance section. 20 1968 - 1971 - Tennessee Valley Authority Instrument Engineer at the Browns Ferry Nuclear Plant.
Mr. Dewease initially worked on establishing the instrument program and technical specifications, i
I 1971 - 1974 Assistant Plant. Mr. Engineering Supervisor at the Browns Ferry Nuclear i Dewease had supervisory responsibility over the
- Reactor Engineering, Radio-chemistry, Testing and Instrumen-l tation and Control groups. In this position, Mr. Dewease supervised and establishment of the initial surveillance program which implemented the technical specifications and l participated in the initial startup of units 1 and 2.
l 1974 - 1977 ^
Quality Assurance (QA) Supervisor at the Browns Ferry Nuclear Plant. Mr. Dewease was responsible for plant QA during the recovery from the March 1975 fire, the restart of units 1 and 2 after the fire and the initial startup of unit i
- 3. During 1976, Mr. Dewease became Assistant Plant Superintendent. ;
I l
i 13.1-28 Amendment 51 l
1 l
. _ = _ - - . _ _ , _ -- , , _ _ _ . . . _ _ - . . ,,m, - _ _ _ _ - _ _ _ . . - _ _ . _ . _ _ _ , . . _ _______m _ . . - . _ _ .. _ -- , - - . _ _ _ . - _ . _ . _ _ . ,
STP FSAR 1977 - 1979 Plant Superintendent at the Browns Ferry Nuclear Plant.
1979 - 1981 Assistant Director of Nuclear Operations, with responsi-bility for the plant operations staffs of four TVA nuclear plants: Browns Ferry; Sequoyah; Watts Bar; and Bellefonte.
July 1981 - Present - Houston Lighting & Power Company Vice President, Nuclear Plant Operations. Mr. Dewease has direct responsibility for operation of the South Texas l24 Proj ect, and other nuclear operations support activities.
l41
- 2. Plant Manager l3g Name: Warren H. Kinsey l41 Education:
1965 U.S. Navy Nuclear Power Training Program 1975 BSME - University of Missouri Experience:
1965 - 1968 - U.S. Navy 3
Senior Reactor Operator-Reactor Technician assigned to the U.S.S. Enterprise. Participated in two cruises. Operated reactor and performed maintenance on reactor control instru-mentation.
1968 - 1971 Senior Reactor Operator - Instructor assigned to the DlG '
Nuclear Prototype. Responsible for shift crew of reactor operators and technicians. Performed in plant and classroom 27 training of Navy and civilian employees. Participated in site refueling activities.
i 1971 - 1975 - University of Missouri Licensed Senior Reactor Operator on 10 MW research reactor at University of Missouri. Operated the reactor for experi-mental and industrial uses. Performed maintenance and modi-fications on equipment. Participated in upgrade work for 5 MW to 10 MW conversion.
, 1975 - 1982 - Tennessee Valley Authority 1975 - 1978 4
Mechanical Engineer assigned to the~ Equipment Performance Group at Browns Ferry Nuclear Plant. Responsible for restart of numerous systems following major fire at the plant. Also responsible for initial startup of systems on ,
new unit. Developed ASME Section XI testing program. Pre-pared procedures for startup tests and performed startup tests on mechanical equipment.
I 4 .
13.1-29 Amendment 51
-.---y - - - - . _- , , - . . _, , _ . , _ _ , , , _ , _ _ _ _ _ , _ _ . . _ _ _ , _ _ _ _ _ , _ . , . - , _ _ _ - _ _ _ . _ __ ___.,__-,,._n_
l STP FSAR 1978 - 19'82 Engineering Section Supervisor assigned to Sequoyah Nuclear Plant. Supervised staff of subordinate supervisors, engi-neers of varying disciplines, laboratory technicians, and engineering aides. Responsible for nuclear startup test program, water chemistry, radio-chemistry and environmental (NPDES) regulations. Also responsible for ASME Section XI and Appendix J testing and performance testing of HEPA and 27 charcoal filters, heat exchangers, and pumps. Responsible for the performance of the makeup water treatment plant and full flow condensate demineralizers. Responsible for gen-eral engineering problems associated with the operation of I the plant.
1982 - 1984 - Houston Lighting & Power Company 41 Plant Superintendent at STP.
l27 1984 (October) - Present - Houston Lighting & Power Company Plant Manager at STP.
41
- 3. Plant Superintendent (Vacant)
- 4. Training Manager, Nuclear Training Department Name: Dennis J. Cody Formal Education:
1964 University of Missouri 1968 Army Nuclear Power School 1980 University of the State of New York (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> towards 1
a BS in Business)
Senior Reactor Operator (BWR) 4 State of Ohio, Stationary Engineer Experience:
1968 - 1973 - U.S. Navy (Nuclear Experience)
Operational Health Physicist - served as a member of in-spection teams performing detailed inspections of military bases in the area of health physics and made technical in-terpretations and judgments on personnel protection pro-grams, including administration, personnel monitoring, shielding, instrumentation, environmental surveillance, radioactive waste disposal, and emergency procedures.
Additional responsibilities included review of Navy activ-ities applications for NRC source licenses to ensure com-pliance with NRC directives, Department of Defense, and Navy policies.
13.1-30 Amendment 51
~
- ' ~ _ _ _ . _ - - - _ ._: L. T. _ _ - , _ - -- .. - - - _ _ ,
l 1
As a Shift Supervisor and Senior Watch Advisor of the PM 3A nuclear power station, was responsible for complete oper-ation of the station during shift. Also qualified as Plant Health Physicist during the period.
Served as Shift Supervisor and qualified as Reactor Operator, Equipment Operator, and Plant Health Physicist of the first floating Nuclear Power Plant. Participated in the first refueling'of the NH-1A.and assisted with the develop-ment of new procedures for future refuelings.
1973 - 1978 - Cincinnati Gas & Electric Company Training Coordinator - responsible for the development and administration of nuclear training for Cincinnati Gas &
Electric Company's nuclear effort.
Included direction of the licensed U.S. Nuclear Regulatory Commission (NRC) Operator Initial Replacement and Requalifi-cation Training Programs; Plant Maintenance and i
Radiation / Chemical Control Technicians Training Programs; j Plant Staff Training Programs; and General Employee Training Programs.
Additional responsibilities included development of Chapter 44 13.2, " Training Program", of the final safety analysis report; direction of the System Descriptions manual; served as Principal Instructor for the Operator Requalification Program, and coordinated the new operator selection process.
1978 - 1982 - NUS Training Corporation j
- Manager, Nuclear Training Department, Training Operations Division - responsible for the management of activities re-lated to development and implementation of nuclear training programs for new licensed, non-licensed utility personnel, including maintenance, technical support staff, and industry technical personnel. Additional responsibilities included direction of special programs, training consulting assign-ments, training program development and evaluations, and conduct of license candidate audit examinations.
1982 - 1983 - Houston Lighting & Power Company Manager, Nuclear Training - responsible for managing the Nuclear Engireering and Construction Department training 1
activities.
1983 - Present - Houston Lighting & Power Company Manager, Nuclear Training Department - responsible for the overall management and administration of the Company's Nuclear Training program.
i 13.1-31 Arendment 51 1
k 1 Table 13.1-1 MEarp me ERpimma 30MWtDB
, na m in4r nmuet swmrna; m i
Maeer of Professicsels Agglicele Ihperience Arportig Directly Mme Title Educatim As of 2/1/85 to en missrm numms J. 5. (bleerg Q usp h e Freeldent, Meleme MBE, MBE 30 years (30 Trs. Mclear) 4 IEt32aR MApr
@rstMrt0G 44 J. C. Dnesse he President IEFE 25 years (17 Trs. Releur) 1 l51 W. R. Einary Flam Itmuger IRE 20 years (20 Trs. Meleer) 3
(% cant) Plant Sgerintenism C. L. Psitey Technical Spport Asperista EBE 11 years (11 Trs. Relaar) 4 51 m O J. V. Imach Oumical Operstkom anl Analysta EnE 15 years (9 Trs. Mcleer) 3
- &gerintenlect :$
.e R. L. Emics Reactor Operstie ageristamissut -
20 years (20 yrs. Meleer) 4 M. A. tudwig hintensmce &gerantemdret EEEE 13 years (9 Trs. Mcleur) 4 1
E E
?.
E
Table 13.1-1 (htiand) timDurTGI me 72Futnet2 spetutHS ptst m IG&P MRSrytel SLER* TING STP Amber of Professicants Applicable apariance asportistDirectly thee Title FAcatim As of 2/1/95 To Each IEE2 EAR Fuser (rnWir!GE (Catinsed)
D. L. !bsith Phmugemmut Services Phnger IEDE. NE3 18 ymmrs (4 yre. Maclear) 4 51 .
e- L. Jarwis lhelth ad Safety Services temager - 35 years (23 Trs. maclear) 4 W '@N g
?, hb+mm Cseret Marrrrr. E, Naut, IE5E 19 years (19 Trs. Esclear) 2 Eclear F)girecring SDfR 1TIAf %%CT ,
ES,MBE 32 years (26 Tro. Eclemr) 4 J. T. %eterseier knuger 5 ,
R. J. Marmi muuner, aggott ase 21 years (!STrs.Eclamr) 5 Senices S. M. Der DeputyProject,thsuger ERCE 17 years (17 Trs. Eclamr) 2 E.W.Ddme Menger, hgineerug BSet,MBE PER 21 ymmre (19 Trs. Mclear) 5 R. Daly Start, Mauger - 35 years (28 Trs. Matteur) -
E I
?.
5
i YABLE 13.I-I (Continued)
EDUCATTON AND EXPPRIENCE SUMMARIES FOR KEY HL&P PERSONNEL SUPPORTING STP Number of Professionals Applicable Experience Reporting Directly Name Title Education As of 2/1/85 to Each SOUTH YEXAS PROJECT (Continued)
J. N. Bailey Principle Engine'er, Design BEE 13 years (13 Trs. Nuclear) 2 M. D. Caden Principle Engineer, Services SSNE 13 years (13 Yrs. Nuclear) 2 M. A. Robinson Principle Engineer, Site BSNE, MBA 19 years (19 Yrs. Nuclear) 3 R. R. Hernandez Principle Engineer, Operation BSCE 11 years (10 Yrs. Nuclear) 3 Support 4, L. H. Clark Supervising Pr'oject BSEE 23 years (15 Yrs. Nuclear) 2 Enginers, Electrical and I&C P A. W. Harrison Supervising Project O BSNE, MENE 11 years (10 Trs. Nuclear) 5 5 7 Engineer, Systems 3
U $
J. A. Blewett Supervising Project BSCE, MS Engr. 16 years (16 Yrs. Nuclear) 4 Engineer, Site Systems 40 S. Tiemarsju Supervising Project BSEE, ESME 29 years (23 Yrs. Nuclear) 2 Engineer, Codes Standards
& Material J. L. Barker Construction Manager 35 Engr. 561. 21 years (21 Yrs. Nuclear) 6 J. W. Willisme site Manager 25 years (11 Yrs. Nuclear) 5 A. O. Will Manager Nuclear BA-Ristory 15 years (15 Yrs. Nucleer) 5 Security Division MA-Human Resource Ngt.
J. C. White Principle Engineer, BSME, MSME 11 years (11 Yrs. Nuclear) 4 Programe b
- a E
a,
TABLE 13.1-1 (Continued)
EDUCATION AND EXPERIENCE SUMMARIES FOR REY HL&P PERSONNEL SUPPORTINC STP Number of Professionals Applicable Experience Reporting Directly Name Title Education As of 2/1/85 to Each 44 NUCLEAR AS50RANCE J. E. Celger fianager, WA ES, Industrial 27 years (8 Trs. Nuclear) 48 3
Engloeering T. J. Jorden Project BSNE 11 years (9 Trs. Nuclear) 4 QA Nanager J. D. Creen Operatione Q4 Femager -
22 years (22 Trs. Nucleer) 2 44 W. N. Phillips Manager Safeteam 80 hrs toward ESNE 20 years (20 Trs. Nuclear) 2 C. B. Biggers Technical Services, BA-Phys ic s 20 years (15 Trs. Nuclear)
- General Supervisor 2 43 $*
se J. "
1 1
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YABIE 13.1-1 (Contirued)
EDUCATI(N #0 EXPFRIENCE SLMARIES RR KEY IKAP PERSOML SJPRRITIC SIP Maber of Professionals Appitemhle !!kperimce lleportirs Directly Name Title Pshration As of 2/1/85 to Each MKIFAR SERVIGS K. K. Qiitkara Mangger BS Physics, PE Physics, 13 years (13 Yrs. Nuclear) 8 Ih.D.NE 10CEAR LIQtEDE F N M. R. Wisesturg Manager, Mr. lear Licensing BS 21 years (21 Yrs. Melemr) 3 I 5
$ M. A. Mchanett Spervisirg Bigineer BSNE, }fNE 7 years (7 Yrs. Nuclear) 2 44%
Operating Plet Licensing M. E. Poupil Supervisirg agineer, BEEE, DENE 7 years (7 Yrs. Nelanr) 2 i Melear Licenairg j BUINEERI!C ASSLRMCE l
i R. A. Prazar Manager, Ehgineerirg BSOE 16 years (13 Yrs. Melemr) 4
, Assurance 10CEAR PUEL T. M. Sobey Mangger, !belear Pbel BS, Physics PENE 15 years (15 Yrs. Melamr) 3 s
9.-
?
TABLE 13.I-1 (Continued)
EDUCATION AND EXPERIENCE SUMMARTES FOR KEY NL&P PERSONNEL SUPPORTING STP Number of
- Professionals Applicable Esperience Reporting Directly Name Title Education As of 2/1/85 to Each 4
ENVIRONMENTAL PROTFCTION DEPARTH E W. T. McGuire Manager BSME 13 years 4 R. W. Lawhn Division Manager BS Physics, MSNE 11 years (11 Trs. Nuclear) 2 NUCLEAR TRAINING DEPARTMENT 44 D. J. Cody Manager Nuclear Training -
17 years (17 Yrs. Nuclear) 3 J. R. Walker Training Manager Operations AA-Mget. 13 years (13 yrs. Nuclear) 4 O Training BSIT B. A. Frants Training Monster Staff AS-Bus. Ngat. 16 years (16 Trs. Nuclear) 3
- Training Division 116 hrs. of 120 g towards BSBA g 48 e
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STP FSAR Figure 13.1-8 has been deleted Amendment 13 11/17/80
i STP FSAR 13.2 TRAININC PROGRAM The goal of the Training Program is to provide qualified personnel to operate and maintain the South Texas Project Electric Generating Station (STPEGS) in compliance with license requirements, Technical Specifications, and appropri-ate governmental regulations. The Training Program is designed using a '
Systematic Approach to Training (SAT) concept and provides the required train-ing based on individual employee experience, the intended position, and previ-ous training / education. The Training Program provides reasonable assurance that fully trained and qualified operating, maintenance, professional, and technical support personnel are available in necessary numbers when fuel load-ing commences. Where practical, the concept of training personnel as a team is used. Personnel shall receive on-the-job training during the pre-opera-tional testing program by performing their job-associated tasks in support of that training. Continuing programs are used after plant startup for training of replacement personnel and for requalification training necessary such that personnel remain proficient. Personnel below the supervisory and technician level, as a minimum, shall complete the required training program as their careers progress. These training programs are described in interdepartmental and/or Nuclear Training Department (NTD) procedures, as appropriate. These programs shall be conducted by qualified HL&P and/or vendor personnel. Appro-priate evaluation is used for each training program and shall include written, oral, demonstration, or a combination of examination / evaluation techniques.
13.2.1 Operator Training Program 13.2.1.1 Cold Licensed Operator Training. The training program for licensing Senior Reactor Operator (SRO) and Reactor Operator (RO) candidates provides a means of preparing these personnel for NRC license examinations and subsequently, station operations.
Station operating and supervisory personnel who must qualify for license exam-inations are categorized by experience as follows:
- 1. Individuals with no previous nuclear experience
- 2. Individuals with nuclear experience at facilities not subj ect to licens-ing 3 .' Individuals holding, or who have held, licenses for comparable facili-ties.
13.2.1.1.1 License Candidates with Fossil Power Plant Experience:
License candidates with fossil power plant experience but with no nuclear experience shall be given the following training:
- 1. Phase I - Nuclear Power Plant Fundamentals (11 weeks)
This training will be conducted at the Vestinghouse Nuclear Training Center or through a combination of onsite classroom instruction and offsite research reactor training. Topics included are:
- a. Nuclear Reactor Theory - 2 weeks
- b. Large PWR Core Physics - 2 weeks 13.2-1 Amendment 51
- c. Health Physics, Instrumentation and Chemistry - 2 weeks
- d. Power Plant Systems and Engineering Concepts - 2 weeks
- e. Reactor Loading, Reactor Operations and Experiments - 3 weeks
- 2. Phase II ~0perating PWR Training (10 weeks)
This training consists of a series of systems lectures. Phase II train-ing shall be completed through a combination of onsite classroom instruc-tion in plant specific systems and systematic observation training at an operating plant similar to STPEGS/or at the Westinghouse Nuclear Training Center with plant observation at the Zion Station of the Commonwealth Edison Company. Classroom lectures dealing with the Zion plant are fol-loved by plant tours to observe the hardware and systems operations which have been discussed.
- 3. Phase III - Simulator Training (9 weeks)
This training provides license candidates with actual plant operations ano transient situations including startups, shutdowns, an operation under normal, off-normal, and emergency conditions. At the conclusion of simulator ten, training, the candidates are given extensive RO and SRO writ-oral, reactor startup, and simulator crew operating examination.
Upon successful completion of simulator training, the candidates receive RO or SRO certification from Westinghouse. Phase III training will be
! conducted on a simulator similar to STPEGS such as the Westinghouse Nu- 51 clear able.
Training Center or on the STPEGS simulator when it becomes avail-(
- 4. Phase IV - Onsite Training Onsite training shall be conducted at the STPEGS to include:
- a. Classroom Training (approximately 24 weeks)
Heat Transfer, Fluid Flow, and Thermodynamics - 2 weeks Reactor Theory, Radiation Protection, and Chemistry - 4 weeks Plant Systems and Procedures - 13 weeks - This series will be half-day classroom lectures with the remaining half day spent in the plant identifying equipment covered in the classroom presentation.
Plant Accident and Transient Analysis - 1 week i
Plant Administrative Procedures, Technical Specifications, and Conditions and I. imitations of the Facility License - I week Mitigating Core Damage (MCD) - 1 week - As identified by H.
Denton letter of March 28, 1980. This program (MCD) ensures
- that all operating personnel (Licensed Operators and appropri-ate managers, and technicians in the I & C, health physics, and I
13.2 2 f
1 Amendment 51 ,
. , - - - - w- . . . - - - . - - - . . , .-- --
STP FSAR chemistry departments) shall receive training commensurate with their responsibilities.
Training program content shall include but not be limited to the following subjects with the above personnel receiving appropriate portions.
Incore Instrumentation Excore Nuclear Instrumentation Vital Instrumentation Primary Chemistry Radiation Monitoring Gas Generation
- b. Procedure Training (approximately 4 weeks)--This training shall be conducted on site using actual or simulated control boards emphasir-ing: .
Normal Plant Operations and Integrated Plant Response - 2 weeks Abnormal and Emergency Plant Procedures - 2 weeks. This train-ing will be conducted on the plant simulator if it is avail-able, if not the actual plant control boards will be used, and 51 if they are not available, a mock-up of the plant control board will be used,
- c. On-The-Job Training (approximately 12 months)
- In addition to this classroom training, operating personnel shall receive approximately 12 months of on-the-job training prior to plant startup. During this period, the Shift Supervisors and Unit Supervisors shall prepare written operating procedures and checkoff lists, prepare systems and equipment for pre-operating testing, and direct and plan the work assignments of the operating personnel.
These personnel shall learn to operate the Nuclear Steam Supply System's support systems and simulate, as closely as possible.
startup and shutdown of the reactor. Operating personnel shall also be actively engaged in pre-operational tests of actual equipment and systems.
- 5. Phase V - Pre-License Review and Audit A three to four week pre-license review shall address the topics covered in Phase IV. In addition, an examination shall be administered in the same manner as the NRC examination as a final step in preparing license candidates for NRC Examination.
13.2.1.1.2 License Candidates with Nuclear Power Plant Exoerience:
License candidates with Navy nuclear power plant experience (qualified as RO, EWS, ERS, PPWS, CRW or E00W, positions listed in NUREC-1021, Section 109) but 13.2-3 Amendment 51
., STP FSAR without commercial nuclear power plant experience shall be given, as a mini-
, mum, a modified Phase III, and Phases IV, and V, as described above.
- 1. Phase I - Nuclear Power Plant Fundamentals Military experience and academic training satisfy this requirement. The evaluation of license candidates during Phases III, IV, and V will ensure that this assumption is valid.
- 2. Phase II - Operating PWR Training Military experience and training satisfy this requirement. The evalua-tion of license candidates during Phases III, IV, and V will ensure that this assumption is valid.
- 3. Phase III - Simulator Training Military experience and training satisfy most of this requirement. How-ever, candidates in this category shall receive two weeks of simulator training in normal and off-normal commercial power plant operations. If the plant simulator is operational and used for procedure training in Phase IV, that training shall fulfill this requirement.
- 4. Phase IV - Onsite Training Candidates shall receive training as described in Section 13.2.1.1.1, Item 4. 51
- 5. Phase V - Pre-License Audit Review Candidates shall receive training as described in Section 13.2.1.1.1, Item 5.
13.2.1.1.3 License Candidates Who Have Been Previcusiv Licensed:
License candidates who have been previously NRC licensed as RO or SRO at a comparable reactor facility shall receive, as a minimum, Phase IV and Phase V training as described in Section 13.2.1.1.1, Items 4 and 5. This will include two weeks of simulator training in normal and off-normal power plant opera-tions.
13.2.1.1.4 SRO Training: Training described in Section 13.2.1.1.1, Items 4 and 5 shall be conducted at the SRO level.
13.2.1.1.5 Instructor cualifications: Instructors who teach safety systems, integrated plant response, transient, and simulator training shall have successfully passed on NRC Senior Operator Instructor Certification Exam-ination or equivalent. The qualifications of these instructors shall be main-tained by their participation in the conduct of the Phase IV training program.
Since a requalification program will not be started until after Cold License, this participation shall be considered as enrollment in appropriate requalifi.
cation program at required by the NRC Harold Denton Letter (03/80). Instruc-tors will participate in the requalification program once it is initiated.
13.2.1.1.6 Coordination with Pre-ooerational Tests and Fuel Loadine: In the event that fuel loading is delayed after the completion of the formal 13.2 4 Amendment 51 ,
l STP FSAR training program, a continuing review and update program similar to the re-qualification program described in Section 13.2.1.3 shall be conducted for individuals scheduled to license prior to criticality.
13.2.1.1.7 Evaluation of Program Effectiveness: Progress of license candidates during the program shall be evaluated by written or oral examina-tion to ensure adequate progress.
13.2.1.2 Reolacement Trainine fur NRC Licensed Plant Personnel and Non-Licensed Plant Ooerators. Training for NRC licensed replacement person-nel, at a minimum, meets the existing NRC requirements as outlined in 10CRF55 Parts 21, 22, and 23; appropriate NUREGS; and the H. Denton letter of March 28, 1980.
These programs are described in Nuclear Training Department proce-dures and are revised as regulations and job requirements change.
Unlicensed Plant Operators shall participate in a continuing operator training and testing program to familiarize them with plant equipment and operations.
This training shall be administered and evaluated by the plant training staff with assistance from operating personnel. Some operators in this program shall qualify to enter a " hot" license training program to enable them to become licensed R0s. Others shall qualify for higher non-licensed operator positions in the chemical operations area.
13.2.1.3 Recualification Training for Licensed and Non-Licensed Operat-ine Personnel.
13.2.1.3.1 Licensed Operator Retraining Prorram: The STPECS Licensed 51 Operator Requalification Training Program is detailed in appropriate Nuclear Training Department procedures. The program meets the requirements of 10CFR55, applicable NUREGS, and the H. Denton Letter of March 28, 1980.
13.2.1.3.2 Non-Licensed Onerator Retraininz Program: Non-Licensed per-sonnel shall receive retraining on a regularly scheduled basis to include familiarization with plant operating experience, modifications and design changes, revisions to procedures, and indoctrination in new procedures appli-cable to the personnel involved.
13.2.1.4 Shift Technical Advisor Trainine.
13.2.1.4.1 Training: The Shift Technical Advisor Training Program con-sists of courses which will supplement and enhance the candidates prior educa-tion or experience. The specifics of the program are contained in the Nuclear Training Department's STA Training Procedure. This training may include the following courses:
- 1. Plant Specific Thermodynamics
- 2. Fluid Flow
- 3. Reactor Physics
- 4. System Engineering
- 5. Transient Analysis 13.2 5 Amendment 51
- 6. Nuclear Instrumentation
- 7. Process Computer
- 8. Mitigating Core Damage Program
- 9. Plant Response
- 10. Duties and Responsibilities of the STA's .
13.2.1.4.2 Raqualification Traininn: Shift Technical Advisors shall receive retraining on a regularly scheduled basis to include familiarizatien with plant operating experience, modifications and design changes, revisions to procedures, and indoctrination in new procedures applicable to the person-nel involved.
13.2.2 Staff Training Programs 13.2.2.1 Maintenance Trainine. Maintenance supervisors, electricians, mechanics, and I&C personnel are generally selected from other operating HL&P facilities or by direct hire as journeymen. As such, they will already have received training appropriate to their particular skill areas. Selected per-sonnel shall receive specialized vendor training on specific equipment or skills. Experienced personnel undergo training and/or indoctrination, as necessary, in the following general subject areas:
SN
- 1. PWR Familiarization or Equivalent
- 2. Maintenance Practices and Procedures
- 3. Maintenance Equipment and Use
- 4. Applicable AdminirtraNive Procedures
- 5. Special Courses presented by the Nuclear Training Department and/or von-dors 6 .' QA Indoctrination
- 7. General Employee and Radiation Worker Training 13.2.2.2 Chemistry Analysis and Radiation Protection. Supervisor and technician level personnel of the Health and Safety Division and the Chemical Operations and /.nalysis Division are selected only after meeting applicable experience requirements. Generally they have completed the appropriate train-ing, or equivalent, associated with their respective job positions. Personnel shall receive additional training, as necessary, in the following subject areas:
- 1. PWR Familiarization or Equivalent
- 2. Chemistry and/or Radiation Protection Practices and Procedures
- 3. Chemistry and/or Radiation Protection Equipment and Use 13.2-6 Amendment $1
"' 4 Applicable Administrative Procedures
- 5. Special Courses presented by the Nuclear Training Department and/or ven-dors 13.2.2.3 Technical Suonort Trainine. The goal of the Technical Support Personnel Training Program is to provide highly skilled personnel to support the various testing programs (i.e., Plant Surveillance Program; ASME Section XI-Pump and Valve Testing; 10CFR50, Appendix J-Leakage Rate Testing, etc.) and
- power plant operations. The programs delineated in this section shall be detailed in Nuclear Training Department procedures and conducted by qualified HL&P and/or vendor personnel.
Reactor En51 neer Training Prior to fuel load, selected personnel shall at-tend a vendor-offered course typically entitled " Station Nuclear Engineer."
Typical subject matter includes:
- 1. Reactor Behavior
- 2. Control Rods
- 3. Shutdown Margins 4 Technical Specifications 51
- 5. Fuel Warranty Operation Provisions
- 6. Core Flow
- 7. Thermal Limit Calculations
- 8. Fuel Failure
- 9. Preconditioning Interim Operating Management Recommendation
- 10. Water Chemistry 13.2.2.4 Ceneral Emolovee Training. All persons permanently employed at STPECS and who require unescorted access to the protected area are trained in the following arcas commensurate with their job duties:
- 1. General Description of STP'dGS
- 2. General Procedures and/or Instructions l
- 3. Security Program 4 Industrial Safety Program
- 7. Quality Assurance Program 13.2-7 Amendment 51 l
- 8. Radiological Health and Safety Program Certain training requirements may be waived if an individual has successfully '
completed a similar pregram at another plant or facility. Temporary mainte- '
nance and service personnel shall be trained in the areas listed above to the extent necessary to assure safe execution of their duties, 13.2.2.5 Fire Protection Trainine. Fire protection training is conduct-ed in accordance with the guidelines of the SRP (NUREG-0800), Section 13.2.2.11.6; 10CFR50, Appendix R; and Branch Technical Position, CMEB 9.5.1 Section C.3.d.1. This training includes classroom instruction, hands-on fire extinguishing, and plant drills. This program includes, but is not limited to, the following.
13.2.2.5.1 Fire Brinade Team Members:
- 1. Initial Training Initial instruction in the topics listed below is provided to each indi-vidual prior to assignment as a fire brigade member. The instruction includes such areas as:
- a. Identification of the location and types of fire hazards that could produce fires within the plant, including identification of the toxic and corrosive characteristics of the products of combustion; 51 b.
Identification of the location of installed and portable fire fight-in5 equipment in each area and familiari.,ation with the layout of the plart. including access and egress routes. Initial training may be general in nature with more detail presented in retraining ses-sions; c.
Proper use of types the following available equipment and the correct method of fighting of fire: electrical, cable and cable trays, hydrogen, flammable liquids, vaste/ debris, and file records; d.
Proper use of protective equipment including breathing, communica-tion, lighting, and portable ventilation equipment;
- e. General review of the format and use of preplans with particular emphasis on what equipment should be used in particular areas.
Detailed reviews shall be conducted during retraining sessions; f.
1 j
Delineation of responsibilities and duties when working with offsite fire departments; i
- g. The proper method of fighting fires inside buildings and tunnels, l
- 2. Retraining Retraining shall be provided to all fire brigade members on a regularly l scheduled banis of not less than four sessions a year, with each session to be repeated at least once every 2 years. Instruction shall be provid-ed by qualified individual knowledgesble and experienced in fighting the fires that could occur in the plant. Retraining sessions shall be 13.2-8 Amendment 51
D STP FSAR utilized for covering preplans including equipment use and entrance and egress routes.
- 3. Practice Sessions Practice sessions shall be held for fire brigade members to familiarize them with the proper methods of fighting various types of fires, with practice in extinguishing actual fires, and in the use of protective equipment includirg emergency breathing apparatus. These sessions shall be conducted so as not to endanger safety-related equipment and shall be conducted at least once per year.
- 4. Drills At 3 year intervals, a randomly selected, unannounced drill shall be critiqued by qualified individuals independent of the HL&P staff. A copy of the report from such individuals shall be available for NRC review.
- a. The simulated use of equipment for the various situations and types of fires which could reasonably occur in safety-related areas;
- b. Conformance, where possible, to the established fire preplans;
- c. Operation of fire fighting equipment, where practical, including self-contained breathing apparatus, communication equipment, and portable and installed ventilation equipment.
Drills shall be performed at least once per quarter for each shift fire bri-gade. At least one drill per year for each shift fire brigade shall be unan- 51 nounced. Unannounced drills shall be scheduled a minimum of four weeks apart.
At least one drill per year for each shift fire brigade shall be conducted on the backshift. Drills should be planned and conducted to established training objectives and critiqued to determine how well the training objectives were met. This critique should, as a minimum, assess: fire alarm effectiveness; response time; selection, placements, and use of equipment; the fire brigade leaders direction of the fire fighting effort; and each fire brigade member's response to the emergency.
A drill shall be conducted annually which includes offsite fire department participation. Additionally or simultaneously, an annual plant evacuation drill shall be conducted.
The initial fire protection training program shall be completed prior to re-ceipt of fuel at the site. Sufficient fire protection drills shall be per-formed immediately prior to fuel receipt to provide assurance that the plant staff is adequately trained to cope with fire-related emergencies.
13.2.2.5.2 Fire Brigade Team Leaders: The fire brigade team leaders and two brigade team members shall receive sufficient training in or have knowl-edge of plant safety-related systems to understand the potential effects of fire and fire suppressants on safe shutdown capability. They shall also re-ceive special instruction in directing and coordinating fire-fighting activi-ties, i
13.2-9 Amendment 51
- n. - . .
STP FSAR 13.2.2.5.3 Fire Protection Personnel: Appropriate fire protection per-
- sonnel shall be introduced to a program of specialized training. Instruction includes the following topics:
- 1. Analysis of building layout and system design with respect to fire pro-tection requirements, including consideration of potential hazards asso-ciated with postulated design basis fires; 2.
Design systems; and maintenance of fire detection, suppression, and extinguishing
- 3. Fire protection techniques and procedures;
- 4. Training and manual fire fighting techniques and procedures for plant personnel and the fire brigade.
13.2.2.5.4 Other Station Emolovees: At least once per year site employ-ees shall be provided instruction on procedures for reporting fires. Security personnel shall be instructed in entry procedures for offsite fire depart-ments, crowd control, and reporting potential fire hazards observed when tour-ing the facility.
Shift personnel shall be instructed in the actions expected of them in assisting the fire brigade in the event of a fire. Any or all of this training may be accomplished as part of the General Employee and/or Emer-gency Plan Retraining Programs.
Contract personnel, temporary employees, and visitors who are authorized una.scorted access to the plant shall be given instruction to familiarize them 51 with the plant evacuation signals, evacuation routes, and procedures for re-porting fires, 13.2.2.5.5 Offsite Fire Denartments: Training shall be made available to local fire departments fires at STPEGS. This training regarding operational precautions when fighting shall include an awareness of the need for radiological STPEGS.
protection of personnel and the special hazards associated with 13.2.2.5.6 Construction Personnel: Training for construction personnel should locatinginclude instruction evacuation routes. in reporting fires, responding to alarms, and 13.2.3 Applicable NRC Documents The applicable portions of the NRC regulations, Regulatory Guides (RCs) and reports plant listed below personnel. will be used in providing guidance in the training of 13.2.3.1 10CRF50. " Licensing of Production and Utilization Facilities".
13.2.3.2 10CRF55. " Operators' License".
13.2.3.3 10CFR19. " Notices, Instructions and Reports to Workers; Inspections".
13.2.3.4 RG 1.8. " Personnel Selection and Training", see Table 3.12-1 for applicable revision number.
13.2-10 Amendment 51
STP FSAR 13.2.3.5 NUREG-0654 " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plan and Preparedness in support of Nuclear Power Plants".
13.2.3.6 RG 1.120. " Fire Protection Guidelines for Nuclear Power Plants", see Table 3.12-1 for applicable revision number.
13.2.3.7 RC 8.2, " Guide for Administrative Practices in Radiation Moni-toring", Revision 0.
13.2.3.8 RG 8.8, "Information Relevant to Maintaining Occupational Radi-ation Exposure As Low As Is Reasonably Achievable (Nuclear Power Reactors)",
Revision 3.
13.2.3.9 RG 8.10. Operating Philosophy for Maintaining Occupational Exposures As Low As Is Reasonably Achievable", Revision 1-R.
51 13.2.3.10 NUREG-0731, " Guidelines for Utility Management Structure and Technical Resources" (Draft report for interim use and comment, September 1980).
13.2.3.11 RG 8.29. " Instruction Concerning Risks From Occupational Radiation Exposure", Revision 0.
13.2.3.12 NUREG-0737. " Clarification of TMI Action Plan Statements" 13.2.3.13 ANS/ ANSI 3.1-1981. " Standard for Qualification and Training of Personnel for Nuclear Power Plants.
13.2.3.14 NRC Harold Denton I.etter. (03/80) to All Power Reactor Appli-cants and Licenses, " Qualifications of Reactor Operators".
13.2.3.15 ANSI /ANS-18.1-1971. " Standard for Qualification and Training of Personnel for Nuclear Power Plants".
1 .
l l
13.2-11 Amendment 51
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? 13.4 REVIEW AND AUDIT s
HL&P has provided for a review and audit program that meets the requirements of Section 4 of ANS 3.2-1982. This program is part of the overall administra-tive control and quality assurance (QA) program and is described in the Oper- I ations Quality Assurance Plan (OQAP). The review and audit program consists of an independent review program, an onsite review program, and an audit and surveillance program. The procedures that control the audit and review pro-gram, along with the organization units that implement them, are described l27 below.
13.4.1 Onsite Review Onsite review activities are performed by the Plant Operations Review Commit-tee (FORC), which is described in Section 6.0 of the Technical Specifications.
13.4.2 Independent Review 13.4.2.1 Nuclear Safety Review Board. Independent review activities are performed by the Nuclear Safety Review Board (NSRB) which is described in Section 6.0 of the Technical Specifications.
13.4.2.2 Independent Safety Engineering Group (ISEG). The ISEC is des-cribed in Section 6.0 of the Technical Specifications.
13.4.3 Audit Program The Nuclear Safety Review Board is cognizant of audits of activities described in Chapter 17. The procedures and organization employed to implement the audit program are discussed in Sections 17.2.2.1 and 17.2.2.4. The HL&P QA staff conducts the audit and surveillance program. The plant QA staff con-ducts audits of operational activities, and the Project Services Division of 51 the QA Department conducts design and procurement audits. Audits are schedul-ed in accordance with a written plan to ensure that all safety-related func-tions are audited within a 2-year period. Qualification of auditors, conducts of the audit, reporting of the audit, and follow-up of audit deficiency correc-tions are centrolled by a written procedure approved by the Manager QA.
Copies of audit reports are distributed to all members of the NSRB.
l l
1 13.4-1 Amendment 51 0 - - ---- -
- 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 Vice President, Nuclear l 20 Plant Operations and to the Nuclear Safety Review Board (NSRB).
- 6. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the NSRB.
- 7. Review of the plant security plan and implementing procedures.
38
- 8. Review of the emergency plan and implementing procedures.
- 9. Review of events requiring 24-hour written notification to the NRC.
13.4.2 Independent Review 13.4.2.1 Nuclear Safety Review Board 15 Independent review activities are performed by the NSRB. The committee is composed of: l 38
- 1. Vice President, Nuclear Engineering and Construction (chairman) l 20
- 2. Manager, Engineering Assurance 30
- 3. Manager, Nuclear Services !
- 4. Manager, Nuclear Licensing 24
- 5. Manager, Nuclear Fuel
- 6. General Manager, Nuclear Engineering 38
- 7. Manager, Quality Assurance lg -
Additional members may be appointed by the chairman. l27 Regular meetings of the NSRB are called by the chairman once per calendar 8 quarter during the initial year of facility operation and at least once per six months thereafter. Special meetings are called by the chairman as he deems necessary. Regular meetings of the NSRB will commence prior to fuel l8 loading for Unit 1 on a date determined by the chairman. Each member of the NSRB will have designated alternates who may attend meetings in place of the 38 regular member. In addition to the chairman, at least three members or their designated alternates must be present for reviews to be conducted.
NSRB meetings and decisions will be documented by meeting minutes that are permanent QA records.
The NSRB shall review the following: 8
- 1. The safety evaluations for (1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of 10CFR50.59, to verify that such actions did not constitute an unreviewed safety question.
13.4-2 Amendment 41
- 2. Proposed changes tc procedures, equipment, or systems that involve an unreviewed safety question as defined in 10CFR50.59.
- 3. Proposed tests or experiments that involve an unreviewed safety question as defined in 10CFR50.59.
- 4. Proposed changes to the Technical Specifications or the operating license.
- 5. Violations of codes, regulations, orders, Technical Specifications, or license requirements having nuclear safety significance.
l38
- 6. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
- 7. All reports sent to the NRC.
- 8. Reports and meeting minutes of the PORC.
13.4.2.2 Independent Safety Engineering Group 15 (This information will te provided in a later amendment.)
13.4.3 Audit Program The Nuclear Safety Review Board is cognizant of audits of activities described in Chapter 17. The procedures and organization employed to implement the 4 l8 audit program are discussed in Sections 17.2.2.1 and 17.2.2.4. The HL&P QA staff conducts the audit and surveillance program. The plant QA staff conducts audits of operational activities, and the Project Services Division l24 of the QA Department conducts design and procurement audits. Audits are scheduled in accordance with a written plan to ensure that all safety-related functions are audited within a 2-year period. Qualification of auditors, conduct of the audit, reporting of the audit, and follow-up of audit defi-ciency co'rrections are controlled by a written procedure approved by the Manager QA. Copies of audit reports are distributed to all members of the NSEB.
13.4-3 Amendment 38
13.5 PIANT l'ROCEDURES Administrative and operating procedures will be utilized by the plant staff in the performance of their duties to ensure that routine operating, off-normal 38 and emergency activities are conducted in a manner that protects the health and safety of the general public and plant personnel, and maintains the relia-bility and integrity of plant equipment.
13.5.1 Administrative Procedures 13.5.1.1 Conformance With Regulatory Guide 1.33. Regulatory Guide 1.33 Revision 2 will be used as a guide for the preparation of plant administrative policies and procedures. The requirements of this guide will be met for those l20 systems and components indicated in Section 3.2, to which 10CFR50 Appendix B requirements are applied.
13.5.1.2 Preparation of Procedures. Safety-related operations will be conducted by detailed written and approved procedures. Safety-related Admin- 51 strative procedures will be reviewed by the Plant Operations Review Committee 2 (PORC). The Plant Manager will issue the procedures after his final review Q441 1 and approval. Procedure preparation and review is an ongoing effort throughout the life of the plant. Operating procedures required to load fuel 51 will be completed approximately six months prior to fuel load.
13.5.1.3 Procedures.
- 1. Conduct of Operations: The responsibilities and authorities of station operating personnel will be determined through administrative procedures in the form of conduct-of-operations procedures. As a minimum, these procedures will establish the following:
- a. Responsibility and authority of the Reactor Operator to manipulate controls which directly affect core reactivity and/or the manipu-lation of apparatus and mechanisms other than controls which may ,
affect the reactivity or power level of a reactor, including a reactor trip if he deems it necessary. He is also assigned the L responsibility for knowing what safety-related equipment and systems l
have limits and setpoints specified in the plant Technical Specifi-cations or Operating Procedures. 33
- b. Responsibility and authority of the Shift Supervisor (SRO) for lic-ensed activities at the unit under his control. There may be addi-tional operating personnel on shift holding senior reactor operator licenses, but the Shift Supervisor is delineated the authority of the senior reactor oparator, pursuant to ICCFR50.54(1). In the event of the Shift Supervisor's absence, this authority will be designated to another SRO in writing.
- c. Requiremen,ts for the presence of a licensed reactor operator or senior reactor operator "at the controls" at all times during the operation of a unit, pursuant to 10CFR50.54(k). Requirements for l
l l
1 l
13.5-1 Amendment 51 l
l
[
, STP FSAR the presence of a licensed senior reactor operator at the facility pursuant to 10CFR50.54(m). The. area of the control room designated as "at the controls" will be specified.
- d. Requirements that no one is permitted to manipulate facility con-trols which affect reactivity who is not a licensed reactor operator or senior reactor operator, except for license trainees operating under the direction of a licensed operator, pursuant to 10CFR50.54(1). Procedures require that all station personnel oper-ating plant apparatus and mechanisms (other than controls) which may affect the reactivity or power level of a unit must notify and obtain the consent of the reactor operator prior to initiating such action, pursuant to 10CFR50.54(j) .
- e. Responsibilities and authorities of the operating shift pursuant to ANSI /ANS 3.2-1982, Section 5.2.
- f. Procedures for shift relief and turnover pursuant to NUREG-0694,
.TMI-Related Requirements for New Operating Licenses, item I.C.2.
- g. Limits on working hours pursuant to NUREG-0737, Clarification of TMI Action Plan Requirements, item I.A.l.3 as modified by Generic Letter 82-12.
- h. Procedures for control room access pursuant to NUREG-0694, item I.C.4.
38
- 1. Procedure for the feedback of operating information pursuant to NUREG-0737, item I.C.S.
j.
Procedures for verifying the correct performance of operating act-ivities pursuant to NUREG-0737, item I.C.6.
- k. Controls governing crane operations including requirements that crane operators who operate cranes over fuel pools be qualified and conduct themselves pursuant to the guidelines of ANSI B30.2-1976, Chapter 2-3.
- 2. Equipment Control: Authorization for release of safety-related equipment or systems for maintenance will be granted by designated operating per-sonnel holding a senior reactor operator license. Such authorization will be documented and will be based upon verification that the equipment or system may be taken out of service, how long it may remain out of service, and to what degree redundant safety systems may be degraded by removing the equipment. After permission has been granted to remove equipment from service, it will be isolated to provide protection for plant personnel and equipment. When entry into a closed system is requir-ed, control measures will be established to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed. Equipment tagging will be utilized to secure and identify equipment in a controlled status. Temporary modifications, such as tem-porary bypass lines, electrical jumpers, lifted electrical leads, 13.5-2 Amendment 51
STP FSAR and temporary trip settings will be performed and documented in accor-dance with approved procedures. When equipment is ready to be returned to service, operating personnel will place the equipment in operation and verify and document its functional acceptability. Pursuant to ANSI /ANS 3.2-1982, safety-related equipment will have proper alignment indeper- 38 dently verified by a second qualified person or functional testing unless such verification would result in significant radiation exposure.
- 3. Maintenance Control: Maintenance or modification of plant equipment will be performed in accordance with written procedures, documented instruc-tions, approved drawings, or appropriate sections of related vendor mat-erials which provide adequate guidance to assure the required quality of the work. Those skills normally possessed by qualified maintenance per-sonnel will not require detailed, step-by-step written procedures.
Procedures utilized for maintenance or modification which may affect the l20 functioning of safety-related structures, systems, or components will be reviewed by the PORC to ensure that the equipment is returned to a state of quality at least equivalent to that specified originally.
- 4. Surveillance Schedule: Surveillance testing will be prescribed by admin- l38 istrative procedures to ensure that the reliability of plant safety-re-lated structures, systems, and components is maintained in accordance l 20 with station Technical Specifications. The Management Services Manager i will be responsible for establishing, maintaining and implementing a l 38 master plant surveillance schedule.
51
- a. The Reactor Operations Superintendent will be responaible for en-l 38 suring the performance of operational surveillance and testing in accordance with the master surveillance schedule. 13
- b. The Maintenance Superintendent will be responsible for ensuring the performance of instrumentation, electrical and mechanical equipment surveillance and testing respectively in accordance with the master surveillance schedule. 38
- c. The Chemical Operations and Analysis Superintendent will be respon-sible for ensuring the performance of chemical analysis and chemical operation surveillance and testing in accordance with the master 13 surveillance schedule.
- d. The Health and Safety Services Manager will be responsible for en- l 38 suring the performance of radiation monitoring surveillance and testing in accordance with the master surveillance schedule. 13
- e. The Technical Support Superintendent will be responsible for ensur-ing the performance of en5 1 neering surveillance and testing in ac-cordance with the master surveillance schedule.
- 5. Logbook Control: Administrative procedures will prescribe the usage, control, and number of logbooks. These procedures will establish pro- 38 visions for the preparation and retention of the logbooks including res-pansibility for maintaining logbooks and storing them at specified loca-tions.
13.5-3 Amendment 51 l
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\ _ _ - - - . . . - _ - . . . . - - - .~-
- 6. Temporary Procedures: Temporary administrative procedures may be issued during the operational phase of the station for the performance of activ- 38 ities which are of a nonrecurring nature. Such activities may include such items as:
- a. Direction of operations during testing, refueling, maintenance, and modifications.
- b. Guidance in unusual situations not within the scope of the normal procedures,
- c. Ensuring orderly and uniform operations for short periods when the plant, a system, or a component of a system is performing in a man-ner not covered by existing, procedures, Limitations involved in the use of the temporary procedure, such as the time interval during which it is in force, will be clearly stated on the procedure. Safety-related temporary Administrative procedures will be reviewed by the PORC. l 51
- 7. Fire Control Procedures: Administrative procedures will be used for preventing, detecting, suppressing, and extinguishing plant fires. These l 38 administrative procedures will describe:
- a. The method for reporting a fire
- b. The method for obtaining permits for cutting, welding, and open flame work
- c. The method for controlling the movement of combustible material within the plant
- d. The relationships of the fire fighting command with the plant staff, outside fire departments, and construction forces
- e. The establishment of a fire watch
- f. The organization and duties of the fire brigade 13.5.2 Operating and Maintenance Procedures 13.5.2.1 Control Room Operating Procedures. Operating activities which may affect the proper functioning of tha station's safety-related systens, or 38 components will be performed in accordance with approved written procedures.
These procedures will provide a preplanned method of conducting operations of l systems in order to eliminate errors due to on-the-spot analyses and judg-l ments. Procedures will be sufficiently detailed so that qualified individ-uals, can perform the required functions without direct supervision. Written procedures cannot cover all possible contingencies and therefore must contain a certain degree of flexibility. The plant operating procedures that will be prepared initially are identified below.
13.5-4 Amendment 51 -
l
- 1. System Operating Procedures System operating procedures will provide instructions for alignment. l38 energizing, filling, venting, draining, starting up, shutting down, and/or changing modes of operation as well as other operating instruc-tion s '. Safety-related operating procedures will be prepared for the systems and equipment listed below: 44
- b. Control Rod Drive System
- c. Residual Heat Removal System
- e. Containment
- 1) Maintaining Integrity
- 2) Ventilation System
- 3) Containment Cooling System
- f. Atmosphere Cleanup Systems
- g. Fuel Storage Pool Purification and Cooling System 38
- h. Main Steam System
- 1. Pressurizer Pressure and Spray Control Systems
- j. Feedwater System (Feedwater pumps to steam generator)
- k. Auxiliary Feedvater System
- 1. Essential Cooling Water System
- m. Chemical and Volume Control System (including Letdown / Purification System)
- n. Mechanical Auxiliary Building Heating and Ventilation System
- o. Control Room and Electrical Auxiliary Building Heating and Ventilation Systems
- p. Fuel Handling Building Heating and Ventilation System
- q. Instrument Air System
- r. Electrical Systems i
I 13.5-5 Amendment 44
- 1) Offsite (circuits between the offsite transmission network and
. the onsite Class 1E distribution eystem)
- 2) Onsite a) Class 1E Emergency Power Sources b) Class lE AC Distribution System 38 c) Class 1E DC Distribution System
- s. Nuclear Instrumentation System
- t. Reactor Control and Protection System
- u. Hydrogen Recombiner
- 2. General Operating Procedure
~
General operating procedures will provide instructions for operating the station as a whole during major evolutions or steady state conditions.
The following is a minimum list of plant general operating procedures to be prepared initially,
- a. Cold Shutdown to Hot Standby
- b. Hot Standby to Minimum Load
- c. Operation at Hot Standby
- d. Turbine Startup and Synchronization of Generator 38
- e. Power Operation
- f. Shutdown to Hot Standby
- g. Hot Standby to Cold Shutdown
- h. Preparation for Refueling
- i. Refueling and Core Alterations
- 3. Off-Normal Operating Procedures Off-normal operating procedures will provide the necessary instrutions for restoring an operating variable to its normal controlled value when it departs from its range or to restore normal operating conditions following a perturbation which could potentially degrade into an emer-gency or violate plant technical specifications if proper action were not taken. Each procedure will identify the symptoms of the off-normal condition, automatic actions that may occur, and the appropriate immediate and subsequent operator actions to be taken. The following is a minimum list of plant off-normal operating procedures to be prepared initially.
13.5-6 Amendment 38
- a. Loss of Open Loop Cooling System
- b. Loss of Closed Loop Cooling System
- c. Main Transformer Off-Normal
- d. Auxiliary Transformer Off-Normal
- e. Standby Transformer Off-Normal
- f. Plant Electrical System Off-Normal
- g. Loss of Charging Capability
- h. Degradation of Main Condenser Vacuum
- i. Malfunction of the Reactor Coolant Makeup System
- j. Dropped or Stuck Rod 38
- k. Malfunction of Rod Control System
- 1. Loss of Main Feedwater
- m. Generator Cooling of Seal Oil Trouble
- n. Loss of Residual Heat Removal While Shutdown
- o. High Primary System Activity
- p. Loss of Automatic Pressurizer Control
- q. Turbine Load Rejection
- r. High Turbine Vibration
- 4. Emergency Operating Procedures Emergency operating procedures will provide the necessary instructions to guide operations during conditions which might lead to injury of plant personnel or the general public and which might possibly lead to the release of radioactivity in excess of established limits. These procedures will be symptom oriented and designed to maintain the critical safety functions of the plant. HL&P is a participant in the Westinghouse Owners Group (WOG) and will use the Emergency Response Guidelines developed by the WOG in response to NUREG-0737, Item I.C.1 as a basis for 38 the STP Emergency Operating Procedures. Thus, the STP Emergency Operating Procedures will comply with the intent of NUREG-0737. Item I.C.1 and NUREG-0660. Items I.C.8 and I.C.9. In addition, the STP Emergency Operating Procedures will meet the intent of NUREG-0799. The following is a minimum list of plant emergency operating procedures to be prepared initially.
13.5-7 Amendment 38
- a. Loss of Core Coolant Flow
- b. . Loss of Secondary Coolant Flow
- c. 38 Steam Generator Tube Rupture
- d. Loss of Offsite Power 0
- e. Control Room Inaccessibility
- f. Dropped or Damaged Fuel Assembly
- g. Loss of Reactor Coolant
- h. Loss of Secondary Coolant 38 i Loss of Condenser Vacuum
- j. Loss of Instrument Air
- k. Reactor Trip
- 1. Loss of Essential Cooling Water
- m. 38 Loss of Residual Heat Removal Shutdown Cooling
- n. Loss of Component Cooling Water System
- 5. Annunciator F.esponse Procedures Annunciator response procedures will specify operator actions necessary to respond to an abnormal condition as indicated by an alarm. These procedures will include alarm setpoints, probable causes, automatic actions, immediate manual actions, supplementary actions, and applicable references. In order to ensure that control room annunciator response procedures are readily accessible for reference, an annunciator response guide will be employed to permit easy retrieval. The procedures will be i grouped within the guide by annunciator panel number. The procedures will be further subdivided by row and column number upon each panel so that the response procedure for any annunciator may be quickly located.
The annunciator response guide will be maintained in the control room.
The Reactor Operations Superintendent will be responsible for maintaining the guide up-to-date. Since the number of these annunciator response procedures is so large, they will not be listed in the FSAR.
- 6. Temporary Operating Procedures Temporary operating procedures will provide instructions for plant operations which are of a nonrecurring nature such as: the directf.on of activities during special testing or maintenance; guidance in unusual situations not within the scope of normal procedures; assuring orderly and uniform operations for short periods of time when the station, a i
system, or component is performing in a manner not covered be existing procedures; or when modifications are made such that portions of the existing procedures do not apply.
13.5-8 Amendment 38 L
STP FSAR 13.5.2.2 Other Procedures. Maintenance and other activities which may
- affect the proper functioning of the station's safety-releted structures, systems, or components will be performed in accordance wi*.h approved written procedures. These procedures will provide a preplanned method of conducting activities in order to eliminate errors. They will be sufficiently detailed i so that qualified individuals can perform the required functions without 151 direct supervision. However, written procedures cannot cover all contingencies and therefore must contain a certain degree of flexibility. The l51 general character and objectives of these procedures are described below.
- 1. Radiation Protection Procedures Radiation protection procedures will, along with design shielding, limit the exposure of plant personnel to airborne radioactivity and radiation during plant operation and maintenance. They will be incorporated into the Plant Procedures Manual by the Health and Safety Services Manager and l51 his staff prior to initial plant startup. These procedures will include personnel access control, air-monitoring program, routine radiological h8 surveys, and the utilization of portable instrumentation. Use of these procedures, along with a careful monitoring program, a personnel training program, proper work procedures, and the use of special equipment, will ensure that plant personnel receive less than the radiological exposure limits presented in 10CFR20.
- 2. Emergency Preparedness Procedures Information concerning these procedures is presented in the South Texas Project Emergency Plan. 24
- 3. Instrument And Control Procedures Instrument and Control procedures will provide detailed instructions for the proper maintenance, testing, and adjustment of all safety-related instrumentation and control systems, and the calibration of measuring and test equipment used in activities affecting the quality of these safety-related systems. They will ensure measurement accuracies adequate 12 0 to maintain plant safety-related parameters within safety limits. The I plant Instrument and Control (I&C) Section under the supervision of the 38 I6C supervisor, will be responsible for developing and implementing these procedures.
- 4. Chemical Analysis Procedures lI3 Chemical analysis procedures will provide instructions to control chemistry - and radiochemistry-related activities. They will be devel- 38 oped and implemented by the Plant Chemical Analysis Section under 13 supervision of the Chemical Analysis Supervisor. These procedures will be incorporated into the Plant Procedures Manual and will include such instructions as: the nature and frequency of sampling and analysis to be performed; prescribed limits for coolant quality; limitations on concen-trations of corrosive agents which could become sources of radiation hazards; and treatment and control of radioactive wastes and control of radioactive calibration sources.
13.5-9 Amendment 51 t
- 5. Radioactive Waste Ifanagement Procedures Procedures for the operation of the Radwaste Processing Systems will, in conjunction with the plant Radiation Protection Procedures, provide for l 38 the control, treatment, and management of radioactive wastes on the plant site. These procedures will be developed and implemented by the Plant Chemical Operations Section under supervision of the Chemical Operations 38 Supervisor.
- 6. Electrical and Mechanical Maintenance Procedures 38 Electrical and Mechanical Maintenance Procedures will provide detailed instructions, where applicable, to ensure that electrical and mechanical work is performed safely, correctly, and in accordance with prescribed radiation protection measures. These procedures will be prepared and implemented by the Electrical and Mechanical Maintenance Sections under l38 the supervision of the Electrical Maintenance Supervisor and Mechanical Maintenance Supervisor respectively. 13
- 7. Material Control Procedures Information concerning these procedures is presented in Section 17.2.
- 8. Plant Security Procedures Information concerning these procedures is presented in the South Texas Project Security Procedures 24
- 9. Fire Protection Procedures Fire protection procedures will be written to ensure a coordinated effort in preventing, detecting, suppressing, and extinguishing plant fires.
Included will be:
- a. Housekeeping practices
- b. General instructions for plant personnel in the event of a fire
- c. Procedures for maintenance, testing, and calibration of the fire detection system '
- d. Procedures for using fire water systems, portable fire fighting equipment and other installed fire suppression systems
- e. Classification and methods of combatting fires
- f. Instructions for fighting fires in various plant areas 13.5-10 Amendment 38
STP FSAR Figure 13.5-1 has been deleted.
Amendment 38
a- -
e 4
ATTACHMENT B
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l Changes Required to Update Portions of FSAR Sections 13.0, 13.1, 13.2, 13.4 and 13.5 Directly Related to Nuclear Program i
Page/Section 13.1-2/13.1.1.1.1.1-2 "Overall direction of all geotechnical, seismological, and geotechnical engineering studies was conducted by B&R, HL&P and/or BEC."
13.1-3/13.1.1.1.1.6 Procurement percent complete is out of date.
13.1-5/13.1.1.2.2 Nuclear Security now reports to the V.P. Nuclear Plant Operations.
13.1-6/13.1.1.2.3.1.2.1 Nuclear Services is no longer responsible for N-Stamp and radioactive waste disposal.
13.1-17/13.1.1.4 also Table 13.1-1 The Safeteam Manager is now L. Guthrie.
13.1-20/13.1.2.2.2 The Operations Supervisor is now titled the " Unit Operations Supervisor."
The Operations Supervisor-Outage / Support is now two positions; Support
- Operations Supervisor and Outage Operations Supervisor.
Each of the above positions has shift supervisors, unit supervisors and operators reporting to them.
13.1-22/13.1.2.2.3 The Chemical Auxiliary Operator position has been eliminated.
13.1-30/13.1.3.2 also Table 13.1-1 The Plant Superintendent position has been filled by J. W. Loesch.
2-Table 13.1-1 The Chemical Operations and Analysis Superintendent is now T. E.
Underwood.
The Chemical Operations and Analysis Superintendent is now titled Chemical Operations & Analysis Manager.
The Technical Support Superintendent is now titled Technical Support Manager.
The Reactor Operations Superintendent is now titled Reactor Operations Manager.
The Maintenance Superintendent is now titled Maintenance Menager.
R. J. Maroni is now Manager, Special Assignments.
The following personnel are to be dropped from the table to be consistent in the Management levels shown in the table:
L. H. Clark, A. W. Harrison, J. A. Blewett, S. Timaraju.
The following personnel are no longer employed or have changed job assignments and will no longer be listed on the table:
M. O. Gaden, M. A. Robinson, J. L. Barker, J. W. Williams New personnel will be added to the table to fill the above positions.
The " Number of Professionals Reporting Directly to Each" column is out of date.
Figure 13.1-3 Nuclear Services:
Delete: Plant and Safety Analysis Reliability Analysis Engineering Support Add: Plant Analysis Thermohydraulic Analysis Fuel Analysis Nuclear Fuel:
Delete: Performance & Engineering Reactor Physics er ----+e-- ---- . - r- - - -
.=
Manager STP:
Delete: Manager Support Services Site Manager Add: Manager Records Management & Doctsnent Control /Information Systems Manager Nuclear Purchasing Project Controller Construction Manager Startup Manager Project Cost and Schedule Manager The Deputy Project Manager should be shown in the same box as the Project Manager.
Group V. P., Nuclear:
Add: Manager Special Assignments Figure 13.1-2A V. P. Nuclear Plant Operations:
Delete: Operations Support Staff l Add: Nuclear Security j
Plant Manager:
Add: Outage Manager Facilities Services Supervisor Change titles as previously noted.
Management Services Manager:
Delete: Security Supervisor Reactor Operations Manager:
Delete: All l Add: Unit _ Operations Supervisor Support Operations Supervisor Outage Operations Supervisor Figure 13.1-28 l
Delete chart and revise as noted in Figure 13.1-2A.
/
Figure 13.1-2C Delete Chemical Auxiliary Operators Figure 13.1-2E The organization diagram will be revised to reflect revised reporting relationships.
Significant changes include the addition of three Maintenance Support Technical Supervisors responsible for Operations, Material Control and Administrative. These supervisors report to the Maintenance Support Supervisor.
Also the Metrology Laboratory is now under the direction of the Metrology Laboratory Supervisor who reports to the Maintenance Manager.
Figure 13.1-2F Word Processing now reports to Administrative Support.
Figure 13.1-2H Training Manager:
4 Add: Staff Specialist Training Manager Staff Training Division:
Add: Construction Training Coordinator Delete: Supervisor General Training Section
- Supervisor Technician Training Section
~
Add: Supervisor Maintenance Training Section Figure 13.1-4 The Technical Services General Supervisor reports to the Manager, Nuclear Assurance
, Figure 13.1-5 Change Air Quality to Air Resources.
Pages 13.4-2 & 13.4-3 Should be deleted.
Page/Section 13.5-3/13.5.1.3 Title changes previously discussed.
I