ML20032C341

Evaluation of North Anna Power Station, Oct,1981

ML20032C341
Person / Time
Site:	North Anna
Issue date:	10/31/1981
From:	INSTITUTE OF NUCLEAR POWER OPERATIONS
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ML20032C333	List: ML20032C332 ML20032C341
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NUDOCS 8111090694
Download: ML20032C341 (36)

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EVALUATION of NORTil ANNA POWER STATION Virginia Electric and Power Company I

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October 1981 hhhhg O

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NORTil ANNA (1981)

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SUMMARY

INTRODUCTION The Institute of Nuclear Power Operations (INPO) conducted its first evaluation of Virginia Electric and Power Company's (VEPCO) North Anna Fower Station during the weeks of May 18 and 26,1981. North Anna Power Station Units 1 and 2 consist of two Westinghouse pressurized water reactors of 918 Mwe and 939 Mwe respectively. The station is located on the southern shore of Lake Anna in Louisa County, approximately forty miles north of Richmond, Virginia. Com-mercial operation commenced in June 1978 for Unit 1 and in December 1980 for Unit 2.

PURPOSE AND SCOPE INPO conducted an evaluation of site activitics to make an overall determination of plant operating safety, evaluate management systems and controls and identify areas needing improvement. Information was assembled from discus-sions, interviews, observations and review of plant documents.

The team examined station organization and administration, training, operations, maintenance, radiation protection and chemistry activities, and on-site technical support. Corporate activities were not included in the scope of the evaluation, except as an incidental part of the evaluation. As a base for the evaluation, INPO used its own expcrience in best practices within the industry and written evaluation criteria furnished to the plant in advance. The evaluation standards are high, and the findings and recommendations are not limited to minimum safety concerns.

DETERMINATION Within the scope of the evaluation, the team determined the station is being safely operated. The following beneficial practices and accomplishments were noted:

o an aggressive solid radioactive waste reduction program has led to a very low volume of waste generation o the state of cle5mliness and low surface contamination in the auxiliary building and the radioactive waste area o the low man-rem exposure level for the year 1980 o the chemical performance testing program o the practice of joint control board walk down provides an excellent method for ensuring the current status of operating equipment is known and understood by oncoming shift personnel

NORTil ANNA (1981)

Page 2 o the administrative burden on first-line supervisors and shift personnel has been reduced by the maintenance service group and the ooerations administrative assistants o the attitude and enthusiasm of management Improvements were recommended for a number of general conditions. The most significant are listed below:

o the present level of licensed operator staffing is impacting on efforts to achieve a five-shift schedule and on operator training and retraining o the shortage of training staff is limiting the ability to effectively conduct non-licensed operator initial training and licensed operator initial and requalificat'on training o the large number of annunciator alarms present during plant operations could detract from the operators' ability to detect abnormal conditions as they occur

.I Specific evalustion findings and recommendations are contained in the accom-panying DETAILS, and information of an administrative nrture is included in the I

ADMINISTR ATIVE APPENDIX.

These findings were presented at an exit meeting at the station on May 29,1981.

Recommendations accompanying each finding are intended to augment Virginia Electrie and l'ower Company efforts to achieve the highest possible standards in its nuclear operations. Certain findings may reflect multiple deficiencies within a particular area. indicating a need to consider the underlying issues. Therefore, in addressing these findings and recommendations, the company also should look beyond immediate correction of the specific deficiencies.

To follow the timely completion of the improvements included in the responses, INPO requests written notification of status six months from the date of this report.

The evaluation team appreciates the cooperation received from all levels of the Virginia Electric and Power Company.

E. P. Wilkinson President I

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1 NORTH ANNA (1981)

VIRGINIA ELECTRIC AND POWER COMPANY Response Summary The Institute of Nuclear Power Operations' (INPO) evaluation of North Anna I

Power Station is one of many industrywide appraisals designed to improve the operation of commercial nuclear power stations beyond established regulatory requirements.

VEPCO fully supports this industry effort and the rigid criteria used to make the evaluation.

While the results of this evaluation showed that some areas at the station need improvement,INPO determined that North Anna "is being operated safely."

The INPO findings and improvement recommendations provided insights that will aid V2PCO in improving overall operations o. North Anna and Surry.

VEPCO has already implemented programs that will eventually increase the number of licensed operators at North Anna. For instance, VEPCO recently awarded college scholarships to eight high school graduates so that they can take the first steps toward becoming licensed VEPCO control room operators.

Increased staffing is in progress to provide additional training and retraining of control room operators. Also, future reactor operators will be trained on a new I

North Anna control room simulator scheduled for full operation by December 1983. Operators in the past have been trained on VEPCO's Surry control room simulator.

Many activated annunciator alarms alert operators to conditions that are not always indicative of serious or impending problems.

Control room warning I

devices At North Anna are being evaluated by VEPCO in an engineering study scheduled for completion January 1,1982. VEPCO realizes that fewer warning devices in an actuated condition in the control room may make it easier for operators to perform their duties and to be alerted to important conditions.

VEPCO looks forward to the INPO evaluation of Surry Power Ltation later this year.

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Page 4 DETAILS This portion of the report includes the detailed findings. It is composed of six sections, one for each of the major evaluation areas. Each section is headed by a I

summary describing the scope of the evaluation and the overall finding in that area. The summary is followed by the specific findings, recoinmendations and utility responses related to each of INPO's evaluation procedures. An item that relates to a criterion that has not been included in INPO procedures but is I

generally recognized as a desirable, accepted technique of industry and manage-ment is listed as " General Criterion." The evaluation procedures used are listed in the ADMINISTRATIVE APPENDIX.

ORG ANIZATION AND ADMINISTRATION Seven performance areas were evaluated in this section.

These included objectives, organiMion structure, administrative controls, quality programs, I

industrial safety, t 2ipment surveillance and personnel qualifications. North Anna management has recognized many of the problems acted by the team and is addressing a number of the more important ones. Ilowever, some areas need further improvement.

OBJECTIVES I

(INPO Procedure OA-101, Revision 2)

An evaluation was performed to determine how effectively goals and objectives are disseminated throughout all levels of the station and how effective these goals and objectives are in conveying intended operational and maintenance purposes.

Areas reviewed included specific goals in use, management goals issued to all personnel and measurement of attainment of goals and objectives.

Finding (Criteria A through E)

Although goals and objectives have been initiated at the corporate level I

and issued to the station manager, they have not been published or utilized to establish written department goals and objectives.

Recommendation Use the goals and objectives issued by orporate management to develop writte.. goals and objectives for imp.ementation by departments at the station.

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Response

Written goals and objectives that will support the station and corporate goals and objectives will be established at the departmental level by Jar.uary 1982.

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Page 5 ORGANIZATION STRUCTURE (INPO Procedure OA-102, Revision 2)

The evaluation team examined the plant organization to determine if it supports safe and efficient operation.

Areas reviewed included applicability of the organization diagrams in effect, position descriptions for station personnel, I

methods used to evaluate the performance of individuals, supervisors' authority, assignment of backup personnel for key positions and overall staffing level.

Finding (Criterion A)

The organizational diagram used by the plant and approved by corporate personnel is not formally published nor is it in agreement with the Technical Specifications.

A change to update the Technical Specifi-cations was appreved by the NRC by letter on May 29,1981.

Recommendation The latest approved organizational structure should be incorporated into I

the organizational diagrams and publications to reflect actual reporting lines in effect.

Response

I Adininistrative Procedure 1.0, Station Organization and Responsibility, was revised to reflect the approved organization.

ADMINISTRATIVE CONTROLS (INPO Procedure OA-103, Revision 2)

I An evaluation was performed to determine the effectiveness of the controls for administrative functions.

Areas reviewed included completeness, flexibility, level of administrative actions and effectiveness of the administrative control progra ms.

Finding (General Criterion) lg Administrative procedures need to be updated to refleet current person-

'g nel assignments and their designated responsibilities. Some procedures need updating to incorporate administrative controls currently in use.

Recommendation

,I Incorporate current personnel assignments and responsibilities into ap-propriate administrative procedures, and update procedures as required to reqect actuhl functions and controls in effect.

Response

I Current personnel assignment in the administrative procedures will be updated and corrected when Administrative Procedure 1.0 was revised.

The Nuclear Power Station Quality Assurance Manual is currently being revised to reflect actual functions and controls in effect and should be complete by January 1,1982.

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Page6 QUALITY PROGRAMS (INPO Procedure OA-104, Revision 5)

An evaluation was performed to determine if quality programs are in effect to provide sufficient monitoring and auditing capabilities to promote safe, efficient I

plant operations and performance. Areas reviewed included management con-trols, approved quality assurance and quality control programs and organization, self-auditing capability, effectiveness and extent of the programs and corrective actions.

Finding (Criterion B)

Quality programs are employed only for required safety-related systems I

and a few non-safety-related items. A majority of the balance of the plant is not under a quality program such as periodic testing, quality control or performance testing programs.

Recommendation Expand the various quality programs in a graduated manner to encompass the balance-of-plant major equipment in order to improve reliability and plant performance.

Response

The importance of quality programs in all phases of nuclear station operations is recognized. Many safety-related programs are in use on a I

stationwide basis. Among these are the maintenance reporting system, approved operating and maintenance procedures, and the preventive maintenance program.

VEPCO maintains it has sufficient quality programs for the balance-of-plant systems.

INPO Comment INPO considers it important that quality programs not be limited in their application to safety-related systems as defined by Technical Specifica-tions.

Ifigher standards similar to some of those applied to safety-related systems should also be applied, in a graduated manner, to selected balance-of-plant equipments and systems in order to improve reliability.

'I INDUSTRIAL SAFETY (INPO Procedure OA-106, Revision 3)

The team examined the industrial safety program to determine if management is

'g clearly committed to industrial safety, the program is supported at all levels of 5

the station staff and the program is effective in minimizing safety hazards and accidents.

Finding (Criterion D)

The published safety precautions and work practices need to be expanded to include precautions to be taken for entry into tanks or confined spaces and requirements for use of respiratory equipment.

Recommendation Publish safety precautions to cover the two specific areas in the finding, and conduct general employee training in these practices.

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Response

Management recognized this deficiency and was in the process of planning a formal program to minimize the hazards of confined spaces and the proper use of respiratory protection. As an interim measure, more information and instruction will be disseminated to the employees until the formal program is implemented. This effort will be accelerated with the goal of implementation of the formal program by January 1, 1982.

I SURVEILLANCE PROGRAM (INPO Procedure OA-107, Revision 3)

An evaluation was performed to determine if a surveillance program existed and whether it accomplished the required surveillance inspection and testing. Areas reviewed included procedures addressing all areas of surveillance, acceptance criteria, out-of-range reporting requirements, timely completion requirements, management control systems and actions to correct deficiencies.

I Finding (Criterion D)

In the past some required periodic tests were missed or were completed after scheduled due dates. This control problem has been recognized, and as a first priority for the Technical Services Department, steps have been initiated to prevent missing required tests.

Recommendation Complete procedure development to improve controls and to ensure timely completion of required surveillance testing.

Response

Procedure development has been completed.

I PERSONNEL QUALIFICATIONS (INPO Procedure OA-108, Revision 2)

The team examined the methods used to establish qualification requirements for each job position, ensure positions are filled with qualified personnel and ensure a program for periodic review'of the requirements is in effect.

Finding All criteria in this area were met.

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I NORTH ANNA (1981)

Page 8 TRAINING AND QUAIAFICATION, I

The team evaluated training organization, administration and resources. Train-ing programs for the licensed operators, non-licensed operators, shift technical I

advisors and instrumentation and control technicians were also tevaluated.

Positive features noted were that the facility has a comprehensive instrumenta-tion and control technician training program, and it:e corporate personnel section is in the process of completing a job and task analysis,for the purpose of I

developing and revising training programs. Ilowever, opportunities for improve-ment exist in some areas.

TRAINING ORGANIZATION (INPO Procedure TQ-201, Revision 0)

I The team examined the on-site training organization to determine if a clently defined organization exists that is staffed with qualified personnel and if it is capable of accomplishing all assigned training tnAs.

Finding (Criteria B and D)

Thc training group staff size needs to be increased to ensure all assigned I

responsibilities can be efficiently met.

Recommendation A review of manpower needs for the training staff should be performed, and additional staff members added as necessary.

Response

A review of training manpower needs has been completed and submitted to the corporate office for review. Additional staff has been authcrized.

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TRAINING ADMINISTRATION (INPO Procedure TQ-202, Revision 0)

The team evaluated training program administration to determine if the organi-zational functions necessary to initiate and control personnel qualification programs are accomplished in a well-defined, coordir.ated and effective manner.

Finding (Criterion C)

I A periodic evaluation of training staff effectiveness is needed to encure it is accomplishing the program objectives and_ that instruction is effective.

Recommendation I

A program of formal, periodic evaluations of the training staff should be established. The principal objective of this program should be to provide-a means of moritoring performance that can lead to improved instructor I

and program effectiveness.

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Response

VEPCO recognizes that a program of evaluating the training staff and monitoring performance is a valuable tool in upgrading training program effectiveness. This process is being secomplished to some extent, and a more formal program will be established by January 1,1982.

I TRAINING RESOURCES

(!NPO Procedure TQ-205, Revision 0)

The team _' examined the training facilities, equipment and materials necessary for the delivery of high quality training for nuclear plant personnel.

Finding All criteria in this area wac met.

I LICENSED OPERATOR REQUALIFICATION TRAINING UNPO Procec'ure TQ-223, Revision 0)

The team examined the licensed operator requalification training to determine if an effective program exists to maintain a high level of knowledge and skill in individuals licensed as reactor or senior reactor operators.

Finding (Criterion F)

The licensed opdator requalification program needs to be expanded to include a comprehensive oral examination to monitor the licensed operator's knowledge and skills required for job proficiency.

Recommendation The licensed operator requalification program should include a strue-I tured oral examination conducted at least annually. The oral evaluation should be directed toward determining the licensed operator's capability to analyze and respond to abnormal or emergency plant conditions.

Response

The 1982 licensed operator requalification program will include a strue-tured oral examination. The oral exams will be given on an annual basis.

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Page 10 SilIFT TECIINICAL ADVISOR TRAINING (INPO Procedure TQ-224, Revision 0)

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In this area, an evaluation was performed to determine if the shift technical advisors have the tr81ning necessary to enhance plant operational safety by I

providing effective technical assistance to the operating shift personnel during normal, abnormal and emergency operating conditions.

Finding I

All criteria in this area were met.

f NON-LICENSED OPERATOR TRAINING W

UNPO Procedure TQ-242, Revis:on 2)

The team examined the training program and training practices used to initially I

qualify non-licensed operator candidates and to maintain and improve the qualifications of existing non-licensed operators.

I Finding (Criterion C)

The program content needs to include initial classroom training in power plant fundamentals. The job analysis project VEPCO currently has in progress also indicates a need for such training.

I Recommendation The non-licensed operator training program should be restructured to include classroom training on power plant fundamentals and plant I

systems.

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Response

The task analysis project for non-licensed operator training has been completed and recommendations made. One of the major findings of the task analysis is the need for initial classroom training. The program is now being reviewed to determine the best means of restructuring the E

content to accomplish the recommendations of the task analysis. It is 3

management's goal to implement the restructured training program by May 1,1982.

LICENSED OPERATOR TRAINING (INPO Procedure TQ-24.s, Revision 2)

In this area, the team examined the training program and training practices used to initially qualify reactor and senior reactor operator candidates to operate the nuclear plant reliably and safely.

Finding All criteria in this area were met.

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Page 11 OPERATIONS Operations activities were evaluated in the areas of organization and administra-tion, tagout practices, conduct of shift operations, procedures, plant status controls, facilities and equipment, and shift turnover.

It was noted that Operations Department personnel are experienced, dedicated to safety and productivity and exhibit a positive attitude toward their duties.

I Throughout the evaluation several good practices were observed such as the joint control operator walk down of the control board at shift change, the utilization of Operations Department administrative assistants for reducing shift clerical I

workload and the convenient location of instrumentation required during plant transients within the primary control area. Overall facility operation is good in the areas evaluated; however, several areas in need of improvement were ident!fied.

OPERATIONS ORGANIZATION AND ADMINISTRATION (INPO Procedure OP-301, Revision 3)

An evaluation was performed te determine if a clearly defined operations

,I orgamzation exists and if assignment of responsibilities and authority are adequate for timely accomplishment of required tasks. Areas reviewed included organizational structure, job descriptions, shift administrative assignments, written and oral instructions and orders, and miscellaneous administrative pro-grams.

Finding (Criterion C)

The Operations Superintendent and Assistant Operations Superintendent have adequate authority to accomplish operational tasks, but consider-able overtime is necessary to accomplish these tasks. Additionally, not enough management personnel are available to rotate as the on-call duty superintendent, a task that is primarily being performed by the Opera-tions Superintendent and his assistant. The limited number of senior licensed personnel makes it difficult for the senior reactor operators to I

attend license requalification classes and complete training and outage license responsibilities while maintaining required shift coverage.

Recommendation Evaluate the operations staff workload to determine whether re-distribu-tion of their present tasks or additional personnel is required. Expand the present on-call duty superintendent list to include other qualified I

department heads. Take steps to increase the number of senior reactor operators (SRO).

Response

It is recognized that the Operations Superintendent and his staff are I

placed under heavy burdens due to the limited number of SROs. One of the major goals of station management is to increase the number of SROs in the near future. Presently SRO candidates are in training, and I

additional enndidates are expected to be selected and started in training before the end of the year. The on-call duty roster will be expanded as additional SROs are qualified and licensed to perform these functions.

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TAGOUT PRACTICES (INPO Procedure OP-302, Revision 2)

Ir. this area, the team examined the formal tagout procedure to determine if it is highly respected and understood by the plant staff, senior reactor operator (SRO) approval is required for removal of safety-related equipment from service, I

double verification is required of safety-related manual valves that do not have control room indication, a second verification of taggeci equipment takes place, tag coloring and numbering is not confusing and the clearance log is periodically I

reviewed.

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Finding (Criterion A)

Changes in service status of eech component selected for a system tagout need to be approved by a licensed senior reactor operator prior to making the change.

Recommendation Review and revise clearance instructions to require an SRO to review and aporove status changes to individual compenents prior to making changes.

Instruct all responsible operations personnel in 'the revised practices.

Response

An SHO is now formally required to review and approve the tagout record prior to implementation.

2.

Finding (Criterion F)

Tags used in the plant are sometimes confusing due to the numerous construction turnover and test tags that remain on operating equipment.

These tags are identical in color to plant clearance and special nrder I

tags.

Recommendation Review the use of all types of tags and remove those that serve no useful

'g purpose.

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Response

Tags referenced in this finding are those that were used during pre-operational phases of the plant. These tags were under administrative E

control, but now have no further value. The tags are being removed.

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Finding (Criterion G)

The periodic review and audit of outstanding electrical and mechanical tagouts should be expanded to include a physical review of installed

'g clearance tags.

3 Recommendation Expand the present program and train operators to include physical auditing of outstanding clearances for proper tag attachment, proper I

positioning of equipment, removal of unauthorized tags and adequacy of each tagout in effect.

Response

I Administrative controls will be reviewed and revised to require periodic audit and physical review of installed tags. These controls will be in effect by December 1,1981.

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Page 13 CONDUCT OF SillFT OPERATIONS (INPO Procedure OP-303, Revision 3).

The conduct of shift operations was evaluated to determine if operator activi-ties, the operating environment and operator aids support safe and efficient E

operation of the plant. Areas reviewed included operator activities, station 5

cleanliness and order, response to abnormal conditions, logkeeping practices, reliability of control room instrumentation and operator awareness of plant conditions.

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Finding (Criterion B)

The control room is generally clean. Ilowever, loose items and debris were found in li.nited access areas, and books of procedures were found on control consoles.

Recommendation Improve and maintain housekeeping in the less acecnible areas in the control room. increase management attention in identifying and cor-recting deficiencies.

Response

VEPCO recognizes control room order as a problem due to the physical siza restrictions and arrangement. Some relief of this situation is forth-coming with the Technical Support Center, in that certain functions may I

then be carried on outside of the control room. Station management is focusing their attention on these problems, and increased emphasis will be placed on the day-to-day management of the control room.

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Finding (Criterion C)

An effective program is needed to identify periodically and take I

remedial action for continuously alarming annunciators.

Recommendation To enhance the operator's awareness of chaN;ing conditions, implement a I

program to reduce or climinate alarms that remain lit during norn.nl operation.

Response

.g Abnormal conditions on annunciator panels in the control room and other g

locations are a ecmbination of many factors, including design, mainte-nance, and abncemal operational sequences. The annunciator system was not designed as a blackboard concept; increfore, redesigning the system to achieve such a concept would be a tremendous undertaking due to the' many interdependent systems and functions.

Some of the abnormal alarm conditions may be corrected by change of setpoints and/or prompt maintenance. Attention to these annunciator problems has increased I

recently so normal maintenance procedures can be utilized to resolve some of these problems. Also, an engineering study will be initiated to seek resolutions to those alarms that require more than normal mainte-I nance practices. INPO will be notified ot' the status of improvements in VEPCO's follow on responses six months after the date of this report.

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Finding (Criterion J)

Control room operators are sometimes distracted by non-operations personnel traffic in the controlled zone.

Recommendation increase management attention as needed to reduce unnecessary traffic I

in the control zone.

Response

Management efforts are being directed toward reducing the control room traffic by minimizing maintensnee personnel entries and other unre-I quired entries.

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Finding (General Criterion)

The quality of control room drawing reproductions needs to be improved to enhance readability, g

Recommendation 3

Prepare more readable control room drawings.

Response

Problems with control room drawings have been recognized. Many prints I

have already been replaced with t=tter reproductions. The Operations Department administrative staff has been instructed to maintain these prints in good condition.

I USE OF FROUEDURES (INPO Procedure OP-304, Revision 2)

Usa cf procedures was evalented to determine if management policies exist for requiring their use, proccdures are clearly written and properly utilized and a system for revision and control is in effect.

Finding All criteria in this area were met.

lI PLANT STATUS CONTROLS (INPO Procedure OP-305, Revision 2)

The team reviewed plant status controls to determine if controls are in effect to ensure equipment and system availability is adequate for safe operation, and if operating personnel are aware of the status of all equipment under their control.

1.

Finding (General Criterion)

Notes, drawings and procedures that are not formally authorized or controlled are located on control panels and throughout the plant.

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Page 15 Recommendation A policy should be established to control all operating aids posted on I

control panels or equipment to ensure the aids in use remain current and reflect approved operating information.

Response

I A policy has been established to control operating aids and ensure that such aids are approved before installation, installed in a professional manner and are kept current.

2.

Finding (General Criterion)

Special Order Tags are presently being used for other than their intended I

short-term use. Tags remain on equipment in the plant for long periods pending resolution of changes of the equipment's operating status.

Reconsmendation I

Develop a program to periodically review and assess the status of equipment being operated in other than the normal operating condition.

Take appropriate action to reduce the time these tags remain in effect.

Response

The Special Order Tags have been reviewed since the evaluation and corrective actions taken. Administrative control of the review of these tags will be improved. The administrative control has been issued.

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OPERATIONS FACILITIES AND EQUIPMENT (INPO Procedure OP-306, Revision 2)

The evaluation team examined the operations facilities and equipment to determine if equipment is accessible for operation, programs are in effect to maximize equipment availability, the working environment contributes to overall

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efficiency and safety of plant operations, and communication equipment and watch stations are adequate.

Finding All criteria in this area were met.

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I SIIIFT TURNOVER (INPO Procedure OP-307, Revision 1)

An evaluation was performed to determine if continuous, correct understanding of station conditions is maintained at all shift positions.

Areas reviewed included programs and policies controlling shift turnove, turnover checklists,

. I, operating panel reviews and review of station activities in progress or planned.

Finding (Criterion B)

I The senior reactor operator and control room operator (CRO) checklists are not always completed jointly, as intended.

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Page 16 Recommendation Use the existing checklists and procedures in the manner intended to ensure important items are not overlooked.

Response

Management will emphasize the importance of completing the SRO/CRO turnover checklist jointly, as it is prescribed by administrative procc-dure, and ensure that its implementation is correctly accomplished.

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I Page 17 MAINTENANCE I

Organization and administration of the Maintenance Department and the Instru-ment Group of the Technical Services Department, preventive maintenance, I

maintenance procedures, the work control system, maintenance history, control of test and measuring equipment, control of special processes, and maintenance facilities and equipment were reviewed. The maintenance and instrument areas I

are well managed, and the departments are adequately staffed to accomplish all normally assigned tasks.

The departments have excellent procedures for accomplishment of maintenance activities. Many excellent practices were noted that reduce administrative and clerical burdens on plant staff, including the use of minicomputers to track personnel qualification, test equipment due dates and similar support activities. Some areas were noted where improvements should be made. These areas are discussed further in the specific evaluation areas.

MAINTENANCE ORGANIZATION AND ADMINISTRATION (INPO Procedure MA-401, Revisica 3)

An evaluation was performed to determine how effectively the maintenance organization and its administrative programs function to enhance performance of maintenance responsibilities. Items reviewed included organizational structure, organization size, training, use of position descriptions and various applicable personnel-related programs. Of particular note, the utilization of a maintenance services group within the Maintenance Department has reduced the administra-tive burden on first-line supervisors, allowing these foremen to spend more time monitoring job activities. Also of. note, the " step" training program appears to be an excellent mechanism for development of technical skills.

Finding All criteria in this area were met.

PREVENTIVE M AINTENANCE (INPO Procedure M A-402, Revision 2)

An evaluation was performed to determine the effectiveness of the maintenance effort in enhancing equipment reliability and performance.

Areas reviewed I

included governing procedures; equipment included in the program; type and frequency of preventive maintenance; and effectiveness of program coordination and control.

An excellent preventive maintenance program is implemented for most plant equipment, and only a small backlog of deferred preventive maintenance items exists.

Finding (Criterion C)

Criteria that define equipment to be included in the preventive mainte-

'I nance program are needed.

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I NCRTII ANNA (1981)

Page 18 Recommendation Establish criteria defining which equipment should be placed in the I

preventive maintenance program.

Response

It is agreed that criteria should be formally established that define the boundaries and expand the existing preventive maintenance program, as required. The program criteria will be formally developed and imple-mented by January 1,1982.

I M AINTEN ANCE PROCEDURES (INPO Procedure MA-403, Revision 3)

I An evaluation was performed to assess the existence and adequacy of mainte-nance procedures and vendor manuals for safety-related and critical balance-of-plant wcrk activities. Items reviewed included activities governing procedures, methods of procedure development and revision and control of procedures.

3 Finding E

All criteria of M A-403 were met.

WORK CONTROL SYSTEM (INPO Procedure M A-404, Revision 3)

An evaluation.was performed to determine the effectiveness of the work control

-I system. System functions were checked to determine if they promote adequate identification of potential work; define and authorize work to be performed by the maintenance groups; provide for planning, scheduling and control of actual I

work; and have a mechanism to input the maintenance results into an equipment history file for future evaluation.

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Finding (Criterion B)

'W The control room maintenance request (MR) logs (one for each unit) were not fully complete and up-to-date. As a result, operators were some-times unable to identify work requested or to determine action or response to requests.

Recommendation These logs, which are kept by the control room operators, should be accurately maintained or a substitute system employed for tracking operations group maintenance.

Response

The work control system for the operations group will be enhanced.

I VEPCO expects to be able to assign an operations maintenance coordina-tor who will be involved in maintenance tracking and scheduling by June 1932.

I NORTH ANNA (1981)

I Page 19 2.

Finding (Criterion C)

The " emergency" classification for work requests, which permits expe-I dited handling and review, is being used for work that does not appear to be of an emergency nature. Some work requests were assigned both a

" routine priority" and an " emergency" classification.

Recommendation Ensure individuals responsible for classifying work requests understand and exercise their responsibilities so that the " emergency" classification I

is properly used.

Response

Steps have been tanen and are successful at reducing the number of

" emergency" work requests. The Planning Department, which controls the administration of the maintenance reporting program, has issued guidelines on the use of " emergency" MRs, and has instituted an avenue of immediate response to those repairs that require quick approval but I

should not be classed " emergency."

I M AINTENANCE HISTORY

. I (INPO Procedure M A-405, Revision 3)

An evaluaticn was performed to determine if maintenance history records are retained and used to improve equipment reliability and performance. Items reviewed included assessment of equipment included in the programs, content and accessibility of records, history review, evaluation methods, and procedures for program implementation.

Finding All criteria of M A-405 were met.

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CONTROL AND CALIBRATION OF TEST EQUIPMENT AND I

INSTRUMENTATION (INPO Procedure M A-406, Revision 2)

An evaluation was performed to assess the adequacy and effectiveness of I

methods used for calibration and control of test and measuring equipment.

Methods used for identifying, calibrating, storing, issuing and using measuring and test equipment were examined. Procedures establishing and governing the calibration program and existing caliteration records were also reviewed.

Finding All criteria of MA-406 were met.

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Page 20 CONTROL OF SPECIAL PROCESSES (INPO Procedure M A-407, Revision 1)

An evaluation was performed to determine if adequate controls exist for welding and nondestructive testing. ' Areas of review included training, qualification, certification of personnel, administrative controls, and control of materials and equipment.

Finding (Criterion D)

I A program of periodic maintenance of welding equipment is needed.

Recommendation Periodic maintenance of welding machines should be implemented to I

ensure their safety and reliability, and periodic adjustments should be made to ensure that required equipment p-formance can be achieved.

Response

A periodic maintenance program for welding equipment will be devel-oped and implemented by January 1,1982.

MAINTENANCE FACILITIES AND EQUIPMENT (INPO Procedure M A-408, Revision 2)

I An evaluation was performed to determine if available facilities and equipment contribute to the effective performance of maintenance activities.

Areas reviewed included quantity, type and condition of tools and equipment; size and location of tool storage areas; adequacy of work and office spaces; and the cleanliness and orderliness of maintenance facilities.

Finding (Criteria A and C)

I Instrument Group supervisors need additional office space.

o Maintenance Department and Instrument Group shops are crowded.

o o In the weld shop area, welding booth ventilation needs improve-ment.

Personnel locker space provided in the clean change room is not o

convenient to the shop area and generally was not used.

jg lg It is recognized that a new mechanical and electrical maintenance l

j facility is being built to address most of these problems.

Recommendation l

Continue construction of the new facility as planned. Provide additional l

space for Instrument Group supervisors and personnel to provide ade-l3 quate office, work and personal space.

ll Repme The new maintenance facility in under construction at this time and is expected to be ready,for use by the end of the year. This facility will provide the neerled welding shop with adequate ventilation, as well as l

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NORTH ANNA (1981)

Page 21 office space for foremen and supervisors.

An evaluation is now in progress to determine the best method to utilize the space remaining in the old mechanical area.

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Page 22 RADIATION PROTECTION AND CIIEMISTRY I

Radiation Protection and Chemistry were evaluated by reviewing the perform-ance of radiological protection training, personnel dosimetry, external and internal radiation exposure, radioactive effluent and solid radioactive waste, contamination control and chemistry.

This portion of the evaluation was primarily an examination of plant programs as they function under normal (non-outage) conditions.

For conditions evaluated, the plant's radiological protection and chemistry programs are adequate to protect the plant workers, the general public and the environment.

Several good programs were observed in radiological protection and chemistry.

There included a comprehensive initial training program for radiological protec-tion technicians, the radioactive decontamination program, the radioactive waste volume reduction program, control of bulk chemicals and solvents, and the chemistry performance testing program.

Areas where the plant needs to improve are in the performance of their radiological protection and chemistry programs. The most significant problem areas included protection of personnel from airborne radioactivity and protection of personnelin the high-level instrument calibration facility.

RADIATION PROTECTION AND CHEMISTRY ORG ANIZATION AND ADMINISTRATION (INPO Procedure RC-501, Revision 1)

An evaluation was performed to determine the effectiveness of the management of the radiological protection and chemistry programs and to ensure that plant personnel possess the knowledge and skills to perform their job in a competent manner.

!g 1.

Finding (Criterion D)

! 5 A formal training program, utilizing classroom instruction, needs to be implemented for chemistry technicians.

Presently, the training of l

chemistry technicians is confined to on-the-job training and self-study.

It was noted that a formal classroom training program is under develop-ment.

l Recommendation i

Complete the development of the classroom chemical technician training l

program.

Response

The chemistry technician training program is now a formalized on-the-job and self-study program that includes end-of-step tests and on-the-job demonstration of task proficiency. The program is being changed to include formal classroom training. Plans are to begin implementation of the classroom phase in 1982, with all technicians completing the training by aanuary 1,1983.

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Page 23 2.

Finding A formal retraining program is needed for radiological protection and I

chemistry technicians to maintain and improve their knowledge and skills.

Recommendation A retraining program for chemistry and radiological protection techni-cians should be developed and implemented.

Response

A formal retraining and replacement program for chemistry and health physics technicians is now in the conceptual stages and should be developed by January 1,1982. The program will be implemented in 1982 with all technicians completing retraining by the end of the year.

PERSONNEL DOSIMETRY (INPO Procedure RC-503, Revision 2)

An evaluation was performed to determine the effectiveness of the plant's dosimetry program in accurately measuring and recording occupational radiation exposures.

Finding (Criterion D)

Only one set of radiation exposure records is maintained for presently employed personnel.

These records are maintained in non-fireproof filing cabinets in a temporary trailer. It was notcd that a computerized data handling system has been purchased, and the health physics organi-zation has plans to incorporate the radiation exposure records into the system.

Recommendation The radiation exposure records should be placed on the computerized data handling system. Two separate sets of these records should be maintained; for example, one set should be on computer disks and a second set on paper in fireproof storage.

Response

A computerized data management system is currently being imple-mented in the llcalth Physics Department. This system will provide the mechanism to readily duplicate active exposure history records for storage in the station records building.

Duplicate records and their maintenance will be accomplished by January 1,1982.

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Page 24 RADIATION SURVEILLANCE AND CONTROL (INPO Procedure RC-504, Revison 2)

An evaluation was performed to determine if the plant's routine surveillance program effectively minimizes the contamination of the plant, equipment and personnel. In addition, this program was evaluated to ensure adequate surveil-lance data was available to indicate changes in plant radiation and contamination levels that might be indicative of potential problems.

Finding All criteria in this area were met.

WASTE AND DISCHARGE CONTROL (INPO Procedure Fn-505, Revision 2)

An evaluation was performed to determine if a system of controls exists to minimize the generation of radioactive waste, reduce the likelihood of having an inadvertent release, and detect the presence of contamination in systems where there should be none.

Finding All criteria in this area were met.

RADIOLOGICAL SURVEY EQUIPMENT CONTROL AND CALIBRATION (INPO Procedure RC-506, Revision 2)

An evaluation was performed to ensure control and calibration of radiation survey equipment are adequate.

Finding All criteria in this area were met.

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PERSONNEL IIEALTII PIIYSICS INDOCTRIN ATION (INPO Procedure RC-507, Revision 2)

An evaluation was performed to determine the effectiveness of the plant's health physics indoctrination program in providing assurance that plant employees have the knowledge and skills necessary to implement radiological protection prac-tices associated with their work.

Finding l

All criteria in this area were met.

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Page 25 PROCESS WATER CONTROLS (INPO Procedure RC-508, Revision 2)

An evaluation was made to determine if chemistry parameters are being controlled within established specifications, and to determine if there is a program to prevent corrosive materials freu being put into or placed in contact with systems materials.

Finding All criteria in this area were met.

IIEALTil PIIYSICS FACILITIES AND EQUIPMENT (INPO Procedure RC-509, Revision 2)

The chemistry and health physics facilities were evaluated to determine if they are adequate to support safe and efficient plant operation.

Finding All criteria in this area were met.

RESPIRATORY PROTECTION PROGRAM (INPO Procedure RC-511, Revision 2)

An evaluation was performed to dewrmine if the respiratory protection program is protecting workers from internal radiation exposure.

1.

Finding (General Criterion)

The plant's records show a number of whole body counts with positive indications of I-133 and 1-131, some greater than 25 percent of the maximum permissible body burden. This internally deposited radioactiv-ity apparently was caused by maintenance personnel being allowed to work in the containment at power without respiratory protection.

Recommendation Procedures that address the use of airborne respiratory protection l

systems should be developed to reduce exposure of individuals to high airborne radioiodine levels.

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Procedures will be resised by November 1,1981 to require respiratory protection when entering the containment under vacuum. During the interim before the formal procedure revision, the use of respirators in the containment is being required by administrative means.

Certain conditions may prohibit the use of self-contained breathing apparatus that may require other protective m easures, such as stay times.

Examples of such conditions may be work that must be performed on scaffolding or ladders, in small confined places or in high radiation areas.

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Page 26 These conditions require evaluations of all safety and radiation hazards to be performed and appropriate actions taken. The use of stay times in an airborne radioactive enviconment will be minimized.

2.

Finding (General Criterion)

Plant procedures require baseline and annual internal monitoring for plant employees. A review of the plant's records showed a need for closer adherence to this procedure in that severa' employees had not a

received baseline or annus1 internal monitoring.

Recommendation The system used to ensure that personnel receive the required internal monitoring should be improved.

Response

An extensive review of whole body count records was conducted to identify those individuals requiring baseline or follow-up bionssay evalua-tions. Identified individuals have received their evaluations. Procedural requirements for whole body counting will be reviewed and revised by December 1,1981 if reqdred.

RADIATION EXPOSURE REDUCTION GOALS (INPO Procedure RC-538. Revision 0)

An evaluation was performed to determine the effectiveness of the plant's program to minimize personnel radiation exposure (ALAR A).

1.

Finding (Criteria B and C)

Although the plant's Radiological Protection Department is involved in job planning to reduce external radiation exposure, radiation exposure reduction goals are needed for specific jobs, for outages or for the total annual collective man-rem.

Recommendation A plant ALAR A program should include occupational radiation exposure goals for each significant exposure job, each outage and for a year's period. The program should also specify that exposure trends during a job be followed, the effectiveness of minimizing exposure be evaluated at the conclusion of the job, and lessons learned be incorporated into future jobs.

Response

Exposure reduction goals for specific jobs during outages and total annual collective man-rem projections are an integral part of a compre-hensive ALARA program.

VEPCO is developing a comprehensive I

ALARA program. Program development on the ALARA project will continue throughout this year, with implementation at the station scheduled for January 1,1982.

NORTII ANNA (1981)

Page 27 2.

Finding (General Criterion)

The high-range portable instrument calibration facility is laid out in such a manner that the operator might receive unnecessary exposure if the 130-curie source is inadvertently left in the calibrate position while the operator adjusts the instrument.

Recommendation Additional safeguards should be installed to warn the operator when the calibration source is in the calibrate position. A suitable device to serve this purpose could be a radiation level monitor with a visual or audible alarm.

Response

Additional safeguards will be established by June 1,1982.

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Page 23 TECHNIC AL SUPPORT I

On-site engineering support was evaluated in the areas of organization and administration, engineering functions performed, nuclear operating experience evaluation, plant design changes and reactor engineering.

The Technical Services Group has a well written and well understood set of procedures and programs, especially in the area of design change control. The quality assurance (QA) manual is noteworthy in its practical orientation to the technical user. However, improvements should be made in the implementation of the design change program. Significant effort should be devoted to timely completion of the design change packages. In addition, while the Technical Services Group is adequately staffed with generally knowledgeable personnel, they need a training program that ensures maintenance of their knowledge and that will uniformly ensure each member's technical proficiency.

TECHNICAL SUPPORT ORGANIZATION AND ADMINISTRATION I

(INPO Procedur:3 TS-701, Revision 1)

The organization and staffing of on-site engineering support were evaluated.

I The capabdity to perform all assigned duties and responsibilities, along with a thorough knowledge of them, and training to maintain and enhance engineering skills were examined.

Finding (Criterion D)

Training for Technical Services Group engineers and management per-sonnel needs to be augmented in that, aside from attendance at industry I

conferences, selected STA training, and other similar sessions by some department personnel, training is not routinely provided for personnel within this group. A plan and commitment for training each member of the Technical Services Group is needed.

Recommendation The training needs of the engineering and management personnel of the Technical Services Group should be determined on an individual basis.

This determination should be based upon a review of position functions, education, and experience. A plan and commitment should be made for accomplishing the training determined to be needed.

I Reyme A management commitment has been made to accomplish training for the Technical Services Group, based on individual needs and allocation of resources. Members of the Technical Services Engineering Group will be trained in 1982 in either SRO, STA, or basic systems training programs.

A plan for accomplishing this training will be developed by December 1, 1981.

NORTH ANNA (1981)

Page 29 ENGINEERING SUPPORT (INPO Procedure TS-702, Revision 2)

Engineering support functions were evaluated specifically regarding plant per-formance monitoring, communication with other support groups providing engi-neering assistance to the plant, control of important documents and the adequacy of engineering support facilities.

1.

Finding (Criterion A)

I Although plant performance monitoring on some systems has been performed in the past, plant performance improvements could be achieved through a more complete and better organized program.

Recommendation Select or develop a plant performance improvement program.

The program should incl"de data analysis of appropriate monitored variables, corrective action identification and implementation. Responsibilities should be defined for all phases of the program and personnel organized as needed to accomplish effective plant performance monitoring.

Response

The Performance and Test Engineering Grouo is presently aeveloping a program to make routine surveillances on both primary and secondary plant performance. This program will utilize both walkdown evaluetions of equipment performance, supplemented by local measurements where appropriate, and overall computerized performance calculations based on "on-line" plant data.

This surveillance program is already partially implemented and is expected to be completed by January 1,1982.

2.

Finding (Criterion C)

Improvements are needed in keeping important documents current.

Examples of such documents include the system description manuals and training manuals.

Recommendation Identify documents in need of change. Implement administrative con-trols to keep important documents current. Include in this effort a review of design changes which have not been reflected in appropriate i

l documentation.

Also give consideration to each of the important l

documents listed in the QA manual, Section 3, paragraph 5.3.4.

Respcnse The station is implementing a prograin that will govern technical l

l manuals as documents under controlled distribution. This program will be fully implemented by January 1,1982. Other documents such as the FSAR, Technical Specifications, Nuclear Power Station Quality Assur-ance Manual, and Administrative Procedures have been urder controlled distribution.

The design change program and its related document review is now undergoing study to improve the procedure to revise documents involved in a design change. (Results of this study will be forwarded to INPO upon completion.)

I NORTli ANNA (1981)

Page 30 NUCLEAR OPERATING EXPERIENCE EVALUATION PROGRAM (INPO Procedure TS-703, Revision 1)

An evaluation was performed of the programs in place for review of both in-house and industrywide events. The purpose was to determine if all operating experiences are evaluated properly and appropriate actions taken.

Finding (Criterion B)

Operating experienaes, in particular, INPO/NSAC Significant Operating I

Experience Reports (SOERs) and their attendant recommendations, need a more thorough review. Improvements are needed in actions to assign the recommended corrective action to appropriate plant persor.nel.

Recommendation INPO/NSAC SOERs 80-1 through 80-6 and 81-1 through 81-10 should be reviewed for applicability. For each of those determined to be appli-cable, each recommendation should be reviewed, apropriate action determined and that action tracked to completion. Similar review and action should be taken for each subsequently issued SOER. Describe the action taken or planned with regard to each recommendati7n in the response to this report.

Response

SOERs are sent by INPO to VEPCO for review. The Director - Safety Evaluation and Control assigns a member of his staff to review each SOER, determine applicability, and enter the applicable SOERs into an appropriate log for follow-up. Applicable SOERs are periodically moni-tored for action taken.

All SOERs to date have been reviewed and applicable items tracked for action. (Many of the SOERs received were, in fact, processed before the evaluation took place).

SOERs are one of many inputs into the operational event review function of Safety Evaluation and Control (SEC). This group coordinates with the station Safety Engineering Staff (SES).

SEC procedures govern the review process.

INPO Comment INPO acknowledges that, for this evaluation, corporate activities regard-ing SOERs were not reviewed. Ilowever, the evaluation team did not find evidence at the station that SOER recommendatius were being implemented. In VEPCO's follow on responses six monti s after the date of this report, it is requested that a summary of the status of each SOER recommendation be provided.

PLANT MODIFICATIONS (INPO Procedure TS-704, Revision 1)

The program for processing plant design changes was evaluated to determine if they are implemented in a timely manner while maintaining the quality of plant systems, structures and components. Review of proposed modifications, prioriti-zation and tracking of the modifications, testing and verification of installation and closcout of the design change package were examined.

NORTil ANNA (1981)

Page 31 1.

Finding (Criterion C)

An overall, coordinated plant Jesign change prioritization for the de-signers, constructors and reviewers is needed.

Recommendation Establish the responsible authority for assigning and modifying the

'I priority for each design change, provide criteria by which priority is determined, define the method for other groups to input their desired priority, and ensure complete and timely notification to all parties.

Response

Procedures are now under development by the corporate office, with the nuclear stations' input, that will assign engineering and construction responsibilities during the conceptual phases of the proposed design change. Prioritization of the design change is also accomplished during the conceptual stages by station management with assistance from the corporate Technical Analysis and Control and the Safety Evaluation and Control Groups.

2.

Finding (Criteria F and D)

Entries in the jumper log reflect the use of a temporary plant change mechanism to effect permanent changes.

Recommendation Establish a periodic review of the log, and entries found exceeding a specified period of time in the log should be considered for processing as design changes.

Ramme Station engineering will evaluate the jumpers and recommend resolutions by January 1,1982. Administrative requirements will be modified by January 1,1982 to require that engineering evaluations be conducted on the long-standing jumpers that are current at the time of the required quarterly review done by operations.

3.

Finding (Criterion I)

Print and documer.tation revisions necessitated by design changes need I

to be completed and issued in a more timely manner.

Recommendation Print and document revisions related to design changes should be completed before the modified systems are placed in service.

Response

The design change program, as implemented at North Anna, requires that design control engineering make pen and ink changes to significant, affected prints in the control room before the technical review is complete. Completion of the techrV review by engineering is accom-plished prior to declaring the moc:fication operable, per the Technical Specifications.

These procedures are required by chapter 3 of the I

Nuclear Pow er Station Quality Assurance Manual (NPSQAM). The NPSQAM also controls the document review associated with design changes resulting in revisions to the affected documents. As stated in I

the response to the second finding under Engine--ing Support, means are being investigated to make document revisions in a more timely manner.

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Page 32 ON-SITE REACTOR ENGINEERING (INPO Procedure TS-705, Revision 2)

An evaluation was performed to determine if reactor engineering support is provided during all modes of plant operation. Use of procedures, use of the I

computer, dedication to the maintenance of fuel cladding integrity and involve-ment in refueling activities were examined.

Finding (Criterion B)

Reactor engineering software changes need to be controlled by an approved procedure. A procedure has been prepared but has not been approved.

Recommendation Review proposed ADM 51.0, make any necessary changes and implement it.

I.

Response

Preparation of an administrative procedure to control the reactor engineering computer software of the plant computer has been assigned, and preliminary revisions of this procedure have been reviewed. This procedure is expected to be fully implemerded by January 1,1982.

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APPENDIX I

Page1 ADMINISTR ATIVE APPENDIX I.

LISTING OF AREAS EVALUATED ORGANIZATION AND ADMINISTR ATION O A-101 Objectives O A-102 Organization Structure OA-103 Administrative Controls OA-104 Quality Programs OA-106 Industrial Safety OA-107 Surveillance Program O A-108 Personnel Qualifications TR AINING AND QUALIFIC ATION TQ-201 Training Organization TQ-202 Training Administration TQ-205 Training Resources TQ-223 Licensed Operator Requalification Training TQ-224 Shift Technical Advisor Training TQ-242 Non-Licensed Operator Training TQ-243 Licensed Operator Training OPERATlONS l

l OP-301 Operations Organization and Admin %tration OP-302 Tagout Practices OP-303 Conduct of Shift Operations OP-304 Use of Procedures OP-305 Plant Status Controls O P-306 Operations Facilities and Equipment OP-307 Shift Turnover M AINTEN ANCE MA-101 Maintenance Organization and Administration MA-402 Preventive Maintenance M A-403 Maintenance Procedures 3

MA-404 Work Control System

3 MA-405 Maintenance Ilistory MA-406 Control and Calioration of Test Equipment and Instrumentation M A-407 Control of Special Processes MA-408 Maintenance Facilities and Equipment

NORTH ANNA (1981)

APPENDIX Page 2 R ADIATION PROTECTION AND CHEMISTRY RC-501 Radiation Protection and Chemistry Organization and Administration RC-503 Personnel Dosimetry RC-504 Radiation Surveillance and Control RC-505 Waste and Discharge Control RC-506 Radiological Survey Equipment Control and Calibration RC-507 Personnel Health Physics Indoctrination RC-508 Process Water Controls RC-509 Health Physics Facilities and Equipment RC-511 Respiratory Protection Program RC-538 Radiation Exposure Reductiott Goals TECHNIC AL SUPPORT TS-701 Technical Support Organization and Administration TS-702 Engineering Support TS-703 Nuclear Operating Experience Evaluation Pr:> gram TS-704 Plant Modifications TS-705 On-Site Reactor Engineering i

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APPENDIX Page 3 II.

VIRGINIA ELECTRIC AND POWER COMPANY OFFICIALS AND NORTil ANNA POWER STATION PERSONNEL CONTACTED I

Executive Vice President - Power Operations Senior Vice President - Power Operations Vice President - Nuclear Operations Manager, Nuclear Operations and Maintenance Station Manager Director, Safety Evaluation and Control Director, Chemistry and Health Physics Assistant Statian Manager Superintendent, Operations Superintendent, Maintenance Superintendent, Technical Services Superintendent, Projects Supervisor, Nuclear Training Supervisor, llealth Physics Supervisor, Administrative Services Supervisor, Planning and Scheduling Fire Marshai Coordinstor, Training and Safety Chemistry Sepervisor Mechanical Supervisor Instrument Supervisor Engineering Supervisor - Performance and Tests Engineering Supervisor - Design Changes and Projects Engineering Supervisor - Safety Evaluation and Control Senior Engineer - Performance and Tests Maintenance Services Supervisor Mechanical Maintenance Supervisor I

Electrical Maintenance Supervisor Maintenance Coordinator Tool Coatrol Assistant Senior Non-destructive Testing Technician Welding Foreman Welders Mechanical Foreman I

Assistant Instrument Supervisor Senior Nuclear Instrument Technicians Shift Supervisors Control Room Operators - Licensed Control Room Operators - Non-licensed Station Technical Advisor Training Instructors Chemist Senior Chemistry Technicians llealth Physicist Assistant llealth Physics Supervisors IIcalth Physics Technician I

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