ML17309A535

Rev 19 to QA Program for Station Operation.

ML17309A535
Person / Time
Site:	Ginna
Issue date:	12/31/1993
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17309A534	List: ML17309A533 ML17309A535
References
NUDOCS 9401110034
Download: ML17309A535 (232)

Text

ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT Revision 19 to:

Quality Assurance Program for Station Operation DOCKET NO. 50-244 December, 1993 p 10034 R nDaCK'OSO0OZOO PDR'

TABLE OF CONTENTS Section Title Pacae QUALITY ASSURANCE PROGRAM FOR STATION OPERATION Quality Assurance Program I

2. Organization

3. Design Control 10 Procurement Document Control 13

5. Instructions, Procedures .and Drawings . 14

6. Document Control 16

7. Control of Purchased Material, Equipment 18 and Services Identification and Control of Materials, 22 Parts and Components Control of Special Processes 23 Inspection Test Control 25

12. Control of Measuring and Test Equipment 27.

13. Handling, Storage and Shipping 28

14. Inspection, Test and Operating Status 29

15. Nonconforming Materials, Parts and Components 30

16. Corrective Action 31

17. Quality Assurance Records 33

18. Audits Revision 19 December 1993

LIST OF TABLES Table Number Title Pacae Quality Assurance Program 37 Procedures Subject Listing 4-1 Procurement Document Requirements 58 Audit List 59 LIST OF FIGURES Fi ure Number Title Pacae Management Organization 63 2-2 Quality Performance Organization Nuclear Production Division 65 Organization i.- Gas and Electric Distribution Division Organization 66 Technical Services Division 67 Organization Ginna Station Review and Audits 68 Functions Revision 19 December 1993

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UALITY ASSURANCE PROGRAM FOR STATION OPERATION

l. ualit Assurance Pro ram The Quality Assurance Program has been developed by the Rochester Gas and Electric Corporation to assure safe and reliable operation. of the R. E. Ginna Nuclear Power Plant.

This program applies to all activities affecting the safety related functions of the 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. These quality affecting activities include operation, maintenance, repair, inservice inspection, procurement, refueling, modif ication, test and inspection. In addition, the Quality Assurance Program applies to the activities associated with the packaging of licensed radioactive materials to be shipped in accordance with lOCFR Part 71 excluding fabrication and .design of shipping casks.

The basic Rochester Gas and Electric Corporation quality assurance policy is established by the Chairman of the Board, President and Chief Executive Officer. This policy is implemented under the overall direction of the Senior Vice President, Production and Engineering through the:

Department Manager, Quality Performance; Vice President-Ginna Nuclear Production; the Plant Manager-Ginna Station; Division Manager-Technical Services and Chief Engineer; and heads of other supporting departments.

The program is governed by a Ginna Station Quality Assurance Manual whi'ch contains the requirements and assignment of responsibilities for implementation .of the program. The manual is prepared, reviewed,- and maintained by Quality Performance and approved by the Senior Vice President, Production and Engineering.

The program is implemented through Quality Assurance/Quality Control, Ginna Station,'uclear Engineering Services, Production Division Tx'aining, Materials Engineering and Inspection Services, Gas and Electric Distribution Division, and Purchasing procedures. These procedures are prepared, approved and maintained by the responsible organization and reviewed by Quality Performance. In addition to its procedure review, Quality Performance assures procedure adequacy through audits and surveillances of a sample of procedures in use. These procedures are reviewed for adequacy at least once every two years by the responsible organization. Table 1-1 provides a listing of the subjects Revision 19 December, 1993

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and a short. description of the subject matter which is contained in each procedure.

Organizational interfaces are defined and controlled by sections of the Quality Assurance Manual. Organizational responsibilities are described in Section 2.

The Quality Assurance Program covers all existing Seismic Category I and Class 1E structures, systems, and components, including their foundations and supports. Activities affecting the quality of these structures, systems, and components are controlled to an extent consistent with their safety significance. A detailed listing of the structures, systems and components covered by the Quality Assurance Program and based on Section 3.2 of the Updated Final Safety Analysis Report, is contained in a controlled database. The criteria for determining if the quality assurance program applies are reviewed by Quality. Performance.

Details of the water-and-steam-containing system boundaries are contained on system flow drawings; Modifications or additions to existing structures, systems, and components are designated the, same seismic classification as the existing system. New structures, systems, and components are designated a seismic classification in accordance with the guidelines in USNRC Regulatory Guide 1.29, Revision 3.

Supervisory personnel are indoctrinated in quality assurance policies, manuals, and procedures to 'assure they understand'hat these are mandatory requirements which must be implemented and enforced. Personnel responsible for performing activities affecting quality are trained and indoctrinated in the requirements, purpose, scope, and implementation of applicable quality related program manuals and procedures. Refresher sessions are held periodically.

Retraining may be required whenever a new procedure is issued or a major revision is made to an existing procedure.

Training of personnel not in the Quality Performance organization is the responsibility of, each. department performing an activity affecting quality. Quality Performance assists in establishing training requirements and assures that personnel are trained by auditing training.

Xn addition to training in quality assurance, each department conducts training, including on-the-job training, to the extent necessary to assure that personnel are Revision 19 December, 1993

qualified for their primary work assignments.

The Vice President, Ginna Nuclear Production is responsible for the formal training, qualification, licensing, and re-qualification of operators, as necessary. As appropriate, personnel granted unescorted access to Ginna Station are trained in radiation protection, plant safety and security.

The Nuclear Safety Audit and Review Board is required to review the status and adequacy of the Quality Assurance Program at least once every two years to assure that it is meaningful and is effectively complying with corporate policy and 10CFR50, Appendix B. This review consists of audits or a review equivalent to an audit performed by company personnel or outside organizations.

The Quality Assurance Program is designed to meet the requirements of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants." The program conforms to the following NRC Regulatory Guides and ANSI Standards:

a. NRC Regulatory Guide 1.8, Revision 1, "Personnel Selection and Training".

b. NRC Regulatory Guide 1.28, Revision 2, "Quality Assurance Program Requirements (Design and Construction) ".

C. AEC Regulatory Guide 1.30, Revision 0, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment".

d. AEC Regulatory Guide 1.33, Revision 0, "Quality Assurance Program Requirements (Operation)," and regulatory staff comments and supplementary guidance contained in the document entitled "Guidance on Quality Assurance Requirements During the Operations Phase of Nuclear Power Plants", Revision 0 dated October 1973 (Orange Book Revision -0)

e. AEC Regulatory Guide 1.37, Revision 0, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants".

f. NRC Regulatory Guide 1.38, Revision 2, "Quality Revision 19 December, 1993

0 Assurance Requirements for, Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants".

g ~ NRC Regulatory Guide l.39, Revision 2, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants".

NRC Regulatory Guide 1.58, Revision 1, "Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel".

NRC Regulatory Guide l.64, Revision 1, "Quality Assurance Requirements for the Design of Nuclear Power Plants NRC Regulatory Guide 1.74, Revision 0, "Quality Assurance Terms and Definitions".

k. NRC Regulatory Guide 1.88, Revision 2, "Collection, Storage and Maintenance of Nuclear Power Plant Records".

NRC Regulatory Guide l.ll6, Revision O-R, "Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems".

NRC Regulatory Guide 1.123, Revision 1, "Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants".

n. NRC Regulatory Guide 1.144, Revision 1, "Auditing of Quality Assurance Programs for Nuclear Power Plants" except that supplier audit frequencies and performance evaluations are as described in the Quality Assurance Manual.

NRC Regulatory Guide 1.146, Revision 0, "Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants".

anization The major organizations participating in the Quality Assurance Program are Purchasing, Technical Services, Ginna Nuclear Production, Gas and Electric Distribution Division, Quality Performance, the Plant Operations Review Committee, and the Nuclear Safety Audit and Review Board. Figure 2-l is an organizational chart showing these organizations and Revision 19 December, 1993

0 their relationship to the corporate organization.

Positions responsible for the principal elements of the quality assurance program are:

Chairman of the Board, President and Chief Executive Officer Senior Vice President, Production and Engineering Vice President, Ginna Nuclear Production Division Manager, Technical Services and Chief Engineer Department Manager, Nuclear Engineering Services Department Manager, Quality Performance Manager, Quality Assurance Manager, Production and Engineering Systems Department Manager and Purchasing Agent, Materials Management Plant Manager, Ginna Station Superintendent, Ginna Support Services Superintendent, Ginna Production Department Manager, Production Division Training Manager, Nuclear Assurance Division Manager, Systems Engineering and Design Division Manager, Rochester Construction and Maintenance Department Manager, Distributive Information Systems Support Manager, Materials Engineering and Inspection Services In addition to the above individuals, two advisory groups are utilized to review and audit plant operations. These groups are the Plant Operations Review Committee and the Nuclear Safety Audit and Review Board. The Plant Operations Review Committee acts in an advisory capacity to the Plant Manager, Ginna Station and the Nuclear Safety Audit and Review Board advises the Senior Vice President, Production and Engineering. The qualifications of members and the responsibilities of these organizations are described in Section 6.0, Technical Specifications, Appendix A to the Full Term Operating License No. DPR-18.

The Chairman of the Board, President and Chief Executive Off'icer of the Rochester Gas and Electric Corporation dir'ected the establishment of the Quality Assurance Program and issued the governing policy statement. He has established the Nuclear Safety Audit and Review Board to review and audit plant operations. The Chairman of the Nuclear Safety Audit and Review Board is responsible to the Chairman of the Board, President and Chief Executive Officer Revision 19 December, 1993

on all activities of the Nuclear Safety Audit and Review Board.

The Senior Vice President, Production and Engineering reports to the Chairman of the Board, President and Chief Executive Officer and has corporate responsibility for operation of Ginna Station in accordance with applicable regulatory requirements. Xn addition, he has overall responsibility and authority for directing the Quality

. Assurance Program and shall be responsible for the approval of the Quality Assurance Manual. He is responsible for establishing the policies and requirements necessary to assure safe and reliable operation of Ginna Station. He is also responsible for those items delineated in Section 6.0, Technical Specifications.

The Vice President, Ginna Nuclear Production is responsible to the Senior Vice President, Production and Engineering for directing Ginna Nuclear Production activities and those support activities associated with Nuclear Engineering Services; Production Division Training, and Corporate Radiation Protection.

The Plant Manager, Ginna Station is responsible to the Vice President, Ginna Nuclear Production for the. overall on-site safe operation of Ginna Station. He is responsible for: the performance of all Ginna Station quality affecting activities in accordance with the. requirements of the quality assurance program; providing qualified personnel these activities. in accordance with approved to'erform drawings, specifications, and procedures; those items delineated in Section 6.0, Technical Specifications; and assuring- that significant conditions adverse to quality are identified and corrected.

The Superintendent, Support Services reports to the Plant Manager, Ginna Station and is primarily responsible for the performance of plant maintenance and scheduling activities in compliance with the requirements of the Quality Assurance Program.

The Superintendent, Ginna Production reports to the Plant Manager, Ginna Station, and is -responsible for operations, health physics and chemistry, refueling, minor and temporary modifications, fire protection, results and tests, Ginna computer systems, technical engineering and surveillance testing in compliance with the requirements of the quality assurance program.

Revision 19 December, 1993

The Plant Manager, Ginna.Station and Superintendents are assisted by other designated staff members, Figure 2-3, in the implementation of certain Quality Assurance Program requirements at the plant. These staff members are assigned responsibility for testing, procurement,, storage of material and equipment, operation and test status control, calibration and control of measuring and test equipment, operating experience assessment, maintenance of 'material handling equipment, and control of all activities involving operation; maintenance, repair, refueling and modification.

The Department Manager, Production Division Training is responsible to the Vice President, Ginna Nuclear Production for maintaining and implementing an Institute of Nuclear Power Operations accredited, training program and, in conjunction with Materials Engineering and Inspection Services, for providing trained and qualified welders, riggers and crane operators to support nuclear related.

activities.

The Department Manager, Nuclear Engineering Services is responsible to the Vice President', Ginna Nuclear Production for designing and 'constructing major modifications in accordance with applicable design bases, regulatory requirements, codes and standards and for nuclear fuel management. As requested by Ginna Station, he is responsible for reviewing unique maintenance and repair procedures for major equipment and providing technical support. He is also responsible for tracking and preparing corrective action report and commitments action tracking report summaries.

The Division Manager, Technical Services and Chief Engineer is responsible to the Senior Vice President, Production and Engineering for directing activities in support of Ginna Station. These activities include long range planning for.

low level radwaste disposal strategies, personnel support for Ginna Station maintenance activities, records retention,

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document control, chemistry and environmental requirements support.

The Manager, Production and Engineering Systems is responsible to the Division Manager, Technical Services and .

Chief Engineer for providing records management and document control support services for nuclear related activities.

The -Department Manager, Quality Performance is responsible to the Senior Vice President, Production and Engineering for Revision 19 December, 1993

0 establishing the overall Quality Assurance Program. He is responsible for assuring that all planned and systemati'c actions necessary to provide adequate confidence that Ginna Station will operate safely and reliably are established and fol'lowed. He provides management with objective information concerning quality, independent of the individual or group directly responsible for performing the specific activity.

He has the authority and organizational freedom to assure all necessary quality'ctivities are performed. In addition, he is responsible for special processes and the inservice inspection program. He is responsible for, maintaining a staff, Figure 2-2, for the conduct of staff training and for directing its activities. The staff assists in the preparation and maintenance of the Quality Assurance Manual and applicable corrective action report summaries.

The Manager, Quality Assurance reports to the Department Manager, Quality Performance.. He and the Quality Assurance Staff are responsible for formulating corporate quality assurance policy and for assuring its implementation. This

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includes writing Quality Assurance policies,'ssuring that.

the program satisfies the requirements of 10CFR50, Appendix B, and..for maintaining the total program up to 'date. The Manager, Quality Assurance is also responsible for establishing and implementing a comprehensive audit and surveillance program, as well as reviewing administrative procedures of the organizations participating in the Quality Assurance Program. The staff is also responsible for auditing and surveillance of aspects of the Qual,ity

.Assurance Program. They are responsible .for assuring that proper codes, standards, and quality requirements are specified in design, procurement and installation documents.

They are responsible for assuring that the suppliers, of safety-related material, equipment and services are properly qualified, maintaining a listing of qualified suppliers and for conducting audits and surveillances at these In addition, the staff assists the Manager, suppliers'acilities.

Quality Assurance, in the preparation of the audit schedule and audit status reports.

The Manager, Quality Assurance is a graduate, engineer with at least six years of responsible experience, of which at least two years are in quality assurance and at least three years in the design or operation of nuclear power plants.

The Manager, Materials Engineering and Inspection Services is responsible to the Department Manager, Quality Revision 19 December, 1993

Performance for the development and qualification of procedures utilized for special processes. He is responsible for providing functi'onal guidance and direction for those methods. He is responsible for establishing the Inservice Inspection Program and for coordinating changes thereto. He is also responsible for the routine maintenance of lifting and handling equipment and for the testing and evaluation of Ginna Station materials. He is responsible

'or supporting training and qualification of welders, riggers and crane operators.

The Manager, Nuclear Assurance reports to the Department Manager, Quality Performance and is responsible for assuring that station activities affecting quality are prescribed and carried out in accordance with approved drawings, specifications, and procedures. He is a member of the Plant Operations Review Committee and delegates the day to day quality assurance and quality control planning and work monitoring responsibilities to his staff of Quality Control Engineers, Foreman and QC Inspectors. The Quality Control Engineers are responsible for the review of design and installation documents and for the review of plant procedures which involve maintenance, repair, refueling, modification, and testing. .Nuclear Assurance is 'responsible for assuring performance of verification inspection activities and assuring that. inspection requirements are included in approved procedures and work packages. This includes the receipt inspection of incoming materials, parts and components and the processing of nonconformance reports.

The Nuclear Assurance Quality Control Inspectors also perform compliance oriented surveillance of nuclear:related activities.

The Department Manager and Purchasing Agent, Materials Management is responsible for the procurement of materials, services, and components, from qualified suppliers,. in accordance with applicable commercial, technical, and quality requirements.

The Division Manager, Rochester Construction and Maintenance is responsible for providing a staff, Figure 2-4, to perform routine maintenance and testing services for Ginna Station meters and relays. He is also responsible for providing laboratory testing of some electrical equipment and devices.

The Division Manager, System Engineering and Design is responsible for providing a staff, Figure 2-4, to perform relay engineering services. He is responsible for design, Revision 19 December, 1993

modification and construction activities at Station 13A and for supporting the Nuclear Engineering Services design and construction activities at Ginna. He is also responsible for coordinating and for providing support documentation for any design modifications initiated within the Gas and Electric Distribution Division.

The Department Manager, Distributive Information Systems Support is responsible for suporting interdepartmental communications .

Desi n Control Design activities are performed by Rochester Gas and-Electric Corporation personnel or are subcontracted to organizations providing services to Rochester Gas and Electric.

Nuclear Engineering Services is responsible for the design.

and control of design activities (including design interfaces) for major modifications of structures, systems

,or components.

Augmenting this effort is the design and technical support

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provided by, the System Engineering and Design Division for

.the systems and equipment. which Gas and Electric Distribution Division is responsible for. maintaining. In this regard they support Nuclear, Engineering Services for design of safety related modifications.

Ginna Station is responsible for the design and control of design activities for Minor modifications of. structures, systems, or components. Ginna Station is also responsible for classifying station. originated modifications as either" Major or Minor. Nuclear Engineering Services reviews and concurs with modifications being. classified as Minor. Minor modifications typically involve (1) component changes which involve vendor design and are limited to the extent that the change does not impact existing performance requirements, (2) additions within Seismic Category I buildings which perform no safety functions and'hich neither interface with Seismic Category I or Class 1E items nor whose failure could reduce the functioning of any safety related component required for safe shutdown of the plant to an unacceptable level, (3) changes to a safety related system determined not to be major (e.g., vents, drains, alarms, indicating lights, etc.) .

Revision 19 December, 1993

Design control is implemented by means of procedures which include: design considerations, design review requirements; internal and external interface control considerations; design document review, approval, distribution, control, and revision requirements; and corrective action. Design considerations include, as appropriate: physics, stress, materials, thermal, hydraulic, radiation and accident analyses; appropriate design bases, codes, standards and regulations; acceptability for operation, maintenance and repair; acceptance and rejection criteria; and quality standards and other quality assurance requirements. Design verification utilizes various methods such as formal design reviews, alternate calculations, or tests; as appropriate, to. assure the adequacy of the design.

I The design of plant modifications is verified by an engineer other than the one who performed the original design. For Major modification design, this may be done by Nuclear Engineering Services design engineers or consulting engineers as requested. For Minor modification station design, this may be done by Ginna Station, Nuclear Engineering Services design engineers or consulting.

engineers, as appropriate.

Spare or replacement parts must at least meet the original equipment's technical and quality requirements. For plant modifications, standard, "off-the-shelf", commercial or previously approved materials, parts, and equipment are selected and reviewed for suitability of application by a design engineer.

Changes to a modification design are normally reviewed and approved in* accordance with the same procedures as the original modification design. Supplemental procedures are established for the review and approval of field changes.

In general, design changes including field, changes, are reviewed and approved by the. organizations or individuals that performed, reviewed and approved the original"design.

Where this is not practical,'ther responsible design organizations or individuals are designated, provided they have access to pertinent background information and are competent in the specific design area.

Design verification and field change systems are methods utilized to detect, document and correct design process errors and deficiencies. In addition, the corrective action system, described in Section 16, is utilized to control and document corrective action to preclude recurrence of those

-ll-Revision 19 December, 1993

design process errors and deficiencies which are considered to be a significant condition adverse to quality.

Quality Assurance is responsible for assuring that, design control procedures, whether the work is done by Rochester Gas and Electric or by other organizations, are prepared and implemented and incorporate appropriate design control practices, checks, and reviews. Design control procedures are reviewed to assure that an independent verification is performed.

Production and Engineering Systems, Nuclear Engineering Services and Ginna Station are responsible for establishing measures for the proper control of design documents and revisions thereto, to assure that distribution is to responsible individuals and in a timely manner to prevent inadvertent use of superseded. design information. The measures include the use of document revision levels, document transmit tais, release stamps, field change request forms and distribution lists.

Design documents are collected, stored, and maintained in accordance with Section 6 an'd 17, as appropriate. Design documents include design criteria, analyses, specifications, drawings, design review records, and changes thereto.

Quality Performance, through preparation assistance and/or review, assure the proper inclusion of quality standards in the design of major and minor modifications. Quality Performance is also responsible for assuring that adequate test, examination and inspection requirements are included in specifications. The Manager, Quality Assurance reviews and approves any deviations from quality standards when they occur.

-Plant modifications are controlled by means of applicable Ginna Station, Nuclear Engineering Services, Gas and Electric Distribution Division, Materials Engineering and Inspection Services, Production Division Training and Quality Assurance/Quality Control procedures. These procedures provide for the preparation, review, and approval of design documents, safety analyses, and plant modification procedures. Plant modifications are reviewed by the Plant Operations Review Committee and Nuclear Safety Audit and Review Board as required by Section 6.0, Technical Specifications.

Revision 19 December, 1993

Procurement Document Control Procurement document control applies to the control of procurement documents for materials, parts, components, and services required to perform quality affecting activities.

Such documents may be prepared by Rochester Gas and Electric or by a contractor and include puxchase requisitions, purchase orders, service agreements, contracts, specifications, and drawings.

Procurement of materials, 'parts, components, and services is initiated by department staff personnel. .Procurement procedures require that organizations preparing procurement documents consider and include, as appropriate, the items listed in Table 4-1.

Procurement documents, including those requesting spare or replacement parts,.initiated at Ginna Station are reviewed by Quality Performance and approved by the designated Ginna Station supervision. Procurement documents initiated in Nuclear Engineering Services, Materials Engineering and Inspection Services, Gas and Electric Distribution Division and Quality Assurance/Quality Control are reviewed by ..

Quality Performance and approved by designated departmental supervision.

.Evidence of review -and approval of procurement documents is recorded on the documents and identifies to Purchasing a procurement method which will ensure'hat the selected supplier is capable of providing thd item or service in accordance with the requirements of the procurement documents. Considerations used in selecting a supplier and for determining the corresponding procurement method are described in Section 7.

After purchase requisitions, service agreements, contracts, specifications, and drawings have received the required reviews and approvals, a purchase order is issued by Purchasing to the selected .supplier and controlled as described in Section 7. These documents are maintained by Purchasing, by the originating department, and/or by the receiving locations, as appropriate, until procurement is completed.

Under no circumstances are purchasing requirements altered (except for quantity or pricing) during order placement unless review and concurrence is obtained from those who were required to review, concur, with, and approve the Revision 19 December, 1993

original documents as described above. Changes or revisions to procurement documents are subject to the same review and approval requirements as the original documents.

Originating department technical review of procurement documents includes verification of applicable regulatory, code and design requirements. Quality Performance review of the above includes checks to verify proper inclusion of the quality standards, quality assurance program requirements, method of procurement and the applicable .acceptance.

criteria. Ginna Station reviews procurement documents for spare or replacement parts to determine similarity, compatibility, and acceptance criteria of the original design. Quality Performance also reviews procurement documents for spare or replacement parts for adequacy of the quality requirements.

Instructions Procedures and Drawin s Each Rochester Gas and Electric company organization, involved in quality related activities, is responsible for developing, reviewing, approving, and implementing procedures as required to implement the Quality Assurance Program. These procedures cover'ctivities such as document control, training of personnel, and responsibilities and duties of personnel'uality Performance reviews these procedures for inclusion of quality assurance program

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requirements. Table 1-1 provides a summary of the subject matter contained in the procedures which are used to implement. the quality assurance program.'rocurement, documents require suppliers and contractors to have appropriate instructions, procedures, specifications, and drawings.

Ginna Station is responsible for providing and implementing instructions and procedures associated with operation, maintenance, repair, in-service inspection, refueling, procurement, modification and testing. This includes instructions and procedures listed in USAEC Regulatory Guide 1. 33 for administrative control; general plant operation; startup, operation, and shutdown of safety related systems; correction of abnormal, of f normal, or alarm conditions; response to emergencies and other significant events; radioactivity control; control of measuring and test equipment; chemical and radiochemical control; and fuel handling and refueling. Ginna Station is responsible for appropriate changes to such documents upon receipt of regulatory directives, instructions from Revision 19 December, 1993

Rochester Gas and Electric management, or the completion of plant modifications. Ginna Station is also responsible for the preparation and issuance of those minor modification design documents not provided by Nuclear Engineering Services or the equipment supplier.

Gas and Electric Distribution Division is responsible for the preparation and implementation of relay inspection and testing procedures as required to direct detailed inspections and testing activities for which they are responsible. Gas and Electric Distribution Division also assists in the preparation of routine relay maintenance and testing procedures used by their personnel in the annual Ginna Station protective relay surveillance program.

Nuclear Engineering Services is responsible for providing approved specifications and drawings for major modifications and for minor modifications when necessary. These documents require those performing the work to obtain, understand, and

,comply with appropriate procedures, specifications and .

drawings. Engineering has established procedures for revising drawings and specifications.. These procedures cover updating of as-built drawings after .plant modifications and .the revision, 'approval, distribution, and control of all drawings and specifications.

Quality Performance is responsible for: preparing and implementing inspection procedures utilized for detailed inspection activities for Ginna Station; providing and implementing procedures for audit and surveillance related activities; and providing and implementing instructions and procedures associated with special processes, and inspection of cranes and handling equipment routine'aintenance as well as materials testing and inservice inspection.

Persons preparing, reviewing and approving documents are responsible for assuring that specificatio'ns, instructions, procedures, and drawings include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished and assuring that the documents are kept current.

Indoctrination and training of personnel is provided by the responsible organizations to ensure that quality affecting activities are conducted in accordance with established documents'n addition, Quality Performance department assessment as described in Section 10 and Section 18 are used to verify that commitments are being addressed and Revision 19 December, 1993

quality affecting activities are being performed in accordance with approved instructions, procedures and drawings.

Document Control Procedures are established to control the issuance of procedures, instructions, drawings, and.specifications.

Standard document control requirements are contained in the Quality Assurance Manual. The Plant Manager, Ginna Station is responsible for the control of all documents issued by Ginna Station personnel. Gas and Electric Distribution Division and Production Division Training are responsible for the control of documents issued by their respective organizations. Production and Engineering Systems controls the distribution of controlled. manuals issued for the other organizations performing activities which implement Assurance Program (Table 1-1). Each organization this'uality controlling documents has a separate procedure to control

documents in accordance with the requirements of the'uality Assurance Manual.

The Quality Assurance Manual designates responsibilities and defines requirements for the preparation, review and .

approval of documents. Each department, responsible for an activity is responsible for providing the necessary review and approval of instructions, procedures or drawings to.

assure that they are. adequate, and include appropriate qualitative and quantitative requirements. Nuclear Assurance Quality Control representatives, who are assigned to support departmental maintenance, repair, refueling and modification activities, are respon'sible for reviewing, prior to use; governing procedures to assure quality assurance requirements are included. The Plant Operations Review Committee has the, responsibility for reviewing Ginna Station procedures prior to their approval as required by Section 6.0, Technical Specifications. Detailed inspection, test and examination procedures used by qualified personnel require the review and concurrence of the responsible technical person associated with that activity. Ginna Station, Nuclear Engineering Services, Material. Engineering and Inspection Services, Purchasing, Production Division Training and Gas and Electric Distribution Division quality assurance implementing procedures (Table 1-1) require the review of Quality Performance and the approval of the appropriate department supervisor.

Quality Assurance/Quality Control procedures are approved by Revision 19 December, 1993

the Department Manager, Quality Performance or designee.'he Quality Assurance Manual requires that documents be controlled as appropriate, considering the type of document involved, its importance to safety, and the intended use of the document. It identifies the difference between controlled and uncontrolled copies of the same document; includes the method for identifying holders of, controlled copies; requires that only controlled copies of a document be used for official purposes; requires that lists of effective revisions be issued periodically; requires lists of document holders to be maintained by the distributors; and requires that distributors transmit controlled documents using approved forms internally and externally.

Types of documents which are controlled include. Technical Specifications, UFSAR, Quality Assurance Manual, procedures (such as engineering, purchasing, repair, maintenance, test, calibration, fuel. handling, modification, and administrative), specifications and drawings. Suppliers of materials, equipment, and services under an approved 10CFR50 Appendix B supplier quality assurance program are. required in procurement documents to provide for control, of documents, including manufacturing, inspection and testing instructions.

The Quality Assurance Manual further requires that each organization provide in its procedures for measures: to assure that documents are available when. required; to properly review and approve documents such as procedures, instructions, specifications and drawings to provide the same reviews and approvals for changes to documents as was required of the original document; to require that organiza-tions which review and approve documents .have access to pertinent information and adequate knowledge of the original document intent; to'ssure that approved changes are promptly transmitted for incorporation into documents; and to assure that obsolete or superseded documents are eliminated from the system and not used.

Quality Performance is responsible for review and concurrence of procurement documents for all procuring organizations and, therefore, procurement document control

=-requirements.

Quality Performance is responsible for review and assessment of document control systems to assure adequate systems are implemented.

Revision 19 December, 1993

0 Control of Purchased Material E ui ment and Services Procurement documents, supplier selection, planning for item or service acceptance, control of supplier performance and acceptance of items and services are five major means used in controlling purchased material, equipment and services.

All procurement is conducted in accordance with procurement documents as stated in Section 4. All reviews, inspections, surveillances, and audits are conducted by personnel who are competent in establishing whether or not a supplier is capable of providing acceptable, quality planning by the procuring organizations consists products'rocurement of determining the methods to be used for acceptance of the item or service and the requirements for control of the supplier performance. Source inspection (surveillance),

certificate of conformance, receipt inspection and post installation test are methods which are considered for item acceptance.. Receipt inspection is utilized in the acceptance of all items. In lieu of these methods, acceptance of services is based on either or a combination of: (1) surveillance of the activity and (2) review of objective evidence for conformance to .the procurement document requirements (i.e. certifications, stress reports etc.) . The extent of the acceptance methods and associated verification activities will vary depending upon the relative importance and complexity of the purchased item or service and the supplier's past performance.

Consideration for the control of supplier performance includes the necessity for document submittals or surveillance, and.under what situation the supplier is to report nonconformances.

Results. of. the planning are incorporated in the procurement documents.

Selection of a supplier is based on the evaluation of its capability to provide the item or services in accordance with the requirements of the procurement documents. 'The evaluation, which is accomplished during procurement planning, determines the necessity for the supplier selection to be made from the approved suppliers list.

Purchasing utilizes the approved suppliers list as the selection source for those suppliers found to have a satisfactory quality assurance program. The evaluation guidelines for source selection considers the item complexity, method(s) of acceptance and for a replacement Revision 19 December, 1993

item, whether the source is to be restricted to the original supplier. For engineered and off-the-shelf items procured from suppliers required to have a quality assurance program, supplier selection is made from the approved suppliers lists or one who is in the process of being added to a list, after having its capability evaluated to purchaser satisfaction.

Items or services, which meet industry standards and are typically utilized in applications other than nuclear, may be purchased from suppliers not listed on the approved suppliers list, provided that item acceptance can be based on acceptance of standard commercial quality which is supplemented, as necessary, with source surveillance, pre-or post-installation tests, receipt tests, commercial supplier test reports, commercial supplier certificates, or receipt inspection. Items or services which have nuclear quality requirements which normally require the supplier to implement a quality assurance program but for which no such supplier can be practicably utilized may also be purchased from suppliers not listed on the approved suppliers list,.

provided that verification of nuclear quality can be accomplished by methods such as source surveillance, pre- or post-installation tests, receipt tests, supplier test reports, supplier certificates, or receipt inspection as approved by Quality Assurance. Departmental procedures establish guidelines for source selection evaluations and for documenting the results through indication of. the corresponding procurement method. The purchase requisition will also identify the source when replacement parts are to be procured, from the original equipment supplier.

Addition of a supplier 'to the approved suppliers list is based on satisfactory evaluation of the supplier,'s quality assurance program by Quality Assurance.

For engineered items, Nuclear Engineering Services or Ginna Station are responsible for evaluating the overall design or manufacturing capability of the supplier including his particular technical ability to produce the design, service, item, or component delineated in the, procurement documents.

As part of this review, the supplier'.s design capabilities, machinery capabilities, handling capabilities, testing facilities, service capabilities, and experience are .

reviewed.

Quality Assurance is responsible for evaluating the supplier's overall quality assurance organization and program in accordance with applicable codes, standards, applicable parts of 10CFR50 Appendix B, and Rochester Gas Revision 19 December, 1993

and Electric Corporation requirements. The review includes consideration of: company organization, quality assurance personnel qualifications, review and control of design documents, manufacturing procedures, quality assurance procedures, calibration practices, acceptance criteria, required quality assurance records and their retention, and quality assurance requirements and controls imposed by the supplier on his subcontractors. Supplier evaluation is conducted by means of procedures or checklists which identify applicable regu1atory or code quality assurance requirements.,

Ginna Station, Quality Performance and Gas and Electric Distribution Division evaluate the suppliers of inspection, test, and calibration services which they intend to use.

The departments responsible for performing supplier evaluations shall document their results in reports which discuss areas investigated, findings, and conclusions..

Measures are established by Nuclear Engineering Services, Ginna Station and Quality Assurance to control supplier performance for engineered items. These measures typically include the processing of change information, surveillance of supplier activities and the control of documents exchanged with the supplier. In addition, each department procuring off-the-shelf items or services establishes similar measures for the control of supplier performance.

With the exception of processing change information, the need for and applicable extent of purchaser controls of the supplier are determined during procurement planning.

Quality Assurance is responsible-for determining and documenting the degree of supplier surveillance (including review, inspection, or audit) required during design, fabrication, inspection, testing, and shipping,, and for providing the required surveillance. The objective of.

supplier surveillance is to provide a sampling review of the supplier's quality assurance program implementation and of product conformance with respect to the purchase order requirements. For complex engineered items, Quality Assurance and Nuclear Engineering Services are responsible for joint development of surveillance plans in advance of surveillance trips to identify areas to be reviewed.

The results of the surveillance trip are documented by means of inspection sheets or trip reports which are distributed to the Manager, Quality Assurance, and the department which Revision 19 December, 1993

e I

initiated the procurement. When a deviation from purchase order requirements is noted, the Quality Assurance representative has the authority to inform the vendor that a particular item is unacceptable,. to issue a nonconformance report or to stop work, if necessary.

Quality Performance is responsible for surveillance of Ginna Station site contractors to assure that they meet all technical and quality requirements. The reporting and documenting of contractor surveillance is managed in a manner similar to supplier surveillance.

The verification methods for the acceptance of items and services are specified on the attached procurement control form during procurement planning and the purchase requisition preparation.

Department supervision is responsible for receiving and storing items pending their acceptance. Upon receipt, .the department stockkeeper logs the item,, places a "hold" tag on

.the item, and notifies Quality Performance that the item has arrived.

Quality Performance is responsible for receipt inspection at.

Ginna 'Station upon delivery of items and associated services for maintenance, repair, modification, and refueling. This inspection includes the use of written procedures or checklists to verify that the items and services conform to the procurement documents (if this has not been performed by source inspections) and that documentary evidence of, conformance is'vailable at the plant prior to installation or use. Documentary evidence sufficient toidentify the codes, standards or specifications met by the .purchased material, equipment, and services is retained. In the event.

a final source inspection, for the acceptance is conducted prior to receipt by RG&E, Quality Performance performs an inspection for shipping damage or lost parts and a document check to assure that the required documentation has been reviewed and is complete. A receiving inspection checklist is completed for all items received to document the extent of the inspection performed, including the documents checked, and the inspection results.

If the item and documentation are adequate, Quality Performance labels the item as "Accepted", files the documentation and receipt inspection results, and releases the item for storage or use. If the item is nonconforming or the documentation is unsatisfactory, Quality Performance Revision 19 December, 1993

initiates controls on the item in accordance with Section l5.

All items issued must bear an acceptance tag or label and have documentation to support the acceptability of the item.

In the event the traceability is lost or the documentation review is unsatisfactory, the item becomes nonconforming and may not be released for use.

Identification and Control of Materials Parts and Com onents The identification and control of materials, parts, and components is accomplished in accordance with written requirements and applies to material, parts, or components in any stage of fabrication., storage, or installation.

Identification and control requirements are established by either*an existing procedure or requirements documents which are prepared during the planning stages of a project. The identification and control requirements cover items such as:

traceability to associated documents such as drawings, specifications, purchase orders, manufacturing test. data and inspection documents, and physical and chemical mill test reports; specification of the degree of identification to preclude a degradation of the item's functional capability or quality; and the proper identification of materials, parts, and components prior to release, for manufacturing, shipping, construction, and installation.

Nuclear Engineering Services, Ginna Station and are responsible for 'assuring that drawings and Quality'erformance specifications contain appropriate requirements for the identification and control of materials, parts, or components, as appropriate. Suppliers are required to assure that all required documentation for an item is properly identified and related to the item.. Each item is required to be physically .identified, either by marking on the item or by tags. Physical identification by purchase order number is used to the maximum. extent possible for relating an item at any time to applicable documentation. to Identification is either. on the item or records traceable the item. Where physical identification is impractical, physical separation, procedural control, or other appropriate means are employed.

The Plant Manager, Ginna Station is responsible for maintaining identification and control of materials, parts, or components received, stored, installed, and used at the Revision 19 December, 1993

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p

plant in accordance with approved procedures. The responsible supervision of other departments which receive material that is to be stored away from the plant are responsible for establishing procedures for identification and control and for maintaining identification and control of material, parts, or components, stored or used in their area of responsibility.

In the event that traceability is lost for a specific item, it is handled as nonconforming material and deviations and waivers are controlled and documented in accordance with Section 1S.

Control of S ecial Processes Written procedures are established to control special processes, such as welding, heat treating, and nondestructive examination to assure compliance with applicable codes, standards, and design specifications.

Qualification of personnel and special process procedures comply with the requirements of applicable codes and standards. When special process qualification requirements are not included in existing codes and standards, they are described in procedures which give details of the special process, the personnel qualification requirements, the equipment necessary, and the special process qualification requirements.

Initiators of procurement activities are responsible for requiring suppliers, in procurement documents, to control special processes in accordance with the above requirements.

Quality Performance personnel are responsible for reviewing procurement documents to ensure that .requirements for control of special processes are included.

Rochester Gas and Electric procedures for special processes are prepared, reviewed, and approved by Materials Engineering and Inspection Services. Special process procedures submitted by suppliers and contractors are reviewed and concurred with by Materials Engineering and Inspection Services.

The Manager, Nuclear Assurance and Ginna Station Maintenance Managers are responsible for assuring that personnel performing special processes under their cognizance are qualified and are using qualified procedures in accordance with applicable codes, specifications, and standards.

Within the Quality Performance Department, the Manager, Revision 19 December, 1993

Materials Engineering and Inspection Services is responsible for the qualification of NDE personnel and procedures. The Manager, Materials Engineering and Inspection Services is responsible for the qualification of welding procedures.

The Manager, Materials Engineering and Inspection Services along with the Department Manager, Production Division Training are responsible for the training and qualification of welders, riggers and crane operators used for nuclear related activities. Records for personnel and procedures to demonstrate that required qualifications have been obtained and kept current are maintained by Production and Engineering Systems.

Quality Performance performs surveillance, inspections, and audits of special processes performed by Rochester Gas and Electric or contractors to, assure effective compliance with procedures.

Ins ection Procedures prepared for the control of activities include inspection requirements and hold points as required by drawings, instructions, requirements documents, specifications, codes, standards, or regulatory requirements. For clarification and. to. distinguish from preventive maintenance 'inspections, the following controls are"'associated with the quality assurance'unction inspections and referred to as verification inspections.

Instructions for conducting detailed verification inspections are contained in inspection procedures.. These inspection procedures and all supporting specifications and drawings are provided to inspection personnel for use prior to performing the inspection. Inspections and hold points are utilized to verify conformance of materials, parts, appurtenances, components, processes or structures to .

• predetermined quality. requirements. Inspection procedures include the identification of quality characteristics to,be inspected, a description of the method of inspection to be used, the identification of the group responsible for performing the inspection, the .acceptance and rejection criteria, the requirements for the recording of inspection .

results, and the requirements for providing evidence of completion and certification of the inspection activity.

Verification inspections are performed by qualified inspection personnel who are independent of the personnel performing the work. Outside contractors are required by procurement documents to have and follow similar procedures and to use independent inspectors. Inspectors are Revision 19 December, 1993

k J

sufficiently trained to adequately evaluate the activity they are inspecting.

Quality Performance personnel are responsible for assuring performance of verification inspections, as required, during plant operation, maintenance, repair, in-service inspection, refueling, modification, and testing when the work is performed by Rochester Gas and Electric personnel. The adequacy of inspections not directly performed by Quality Performance personnel will be assessed on a sample basis through the QA/QC surveillance program. Inspection equipment is calibrated and controlled in accordance with Section 12. Calibration status is verified by inspection personnel prior to performing an inspection operation.

In the event an inspection of processed material or products is impossible or impractical, indirect control by monitoring processing methods; equipment, and personnel is provided.

Both inspection and process monitoring are required when control is inadequate without both.

Quality Performance is responsible for verifying .adequate inclusion of inspection requirements in specifications.

The Manager, Nuclear Assurance is responsible for assuring that adequate inspection requirements and hold points are included'in maintenance, repair, refueling, modification and testing instructions and procedures and related fabrication processes. He is also responsible. for the assignment of qualified personnel required for the performance of verification inspections and quality, control surveillances of quality affecting activities.

the exception'of that which pertains to Pump and Valve

'ith Testing, the Manager, Materials Engineering and Inspection Services is responsible for establishing the requirements, for. the Inservice Inspection Program. Nuclear Engineering Services is responsible for establishing the requirements for the Inservice Pump and Valve Testing Program. The program for inservice inspection of the reactor coolant system and other safety related systems is contained in Section 4.2, Technical Specifications.

Test Control Checks or testing performed to verify the adequacy of corrective or preventive maintenance shall be performed to approved instructions, procedures, or drawings. Whenever Revision 19 December, 1993

testing is required to demonstrate that a material, part, component, or system will. perform satisfactorily in service, a test program is instituted employing written and approved procedures which are in accordance with basic requirements established'in Technical Specifications, drawings, instructions, procurement documents, specifications, codes, standards, and regulatory requirements. The test program requires the identification, control, and documentation of all tests, and the preparation of written procedures required for satisfactory accomplishment of the testing.

Together the written procedures and checklists for the testing program include: necessary test equipment and calibration requirements; material requirements; test personnel requirements; prerequisite plant and equipment conditions; limiting conditions; detailed performance instructions for the testing method and test equipment instrumentation; acceptance and rejection criteria; instructions for disposition of deviations; data collection requirements; and test result approval.

The Plant Manager, Ginna Station is responsible for the station test program, which, includes the surveillance. test program required by Section 4.0, Technical Specifications.

Nuclear Engineering Services, is responsible. for preparing

'test procedures and performing testing associated with modifications. I Test procedures are prepared by the plant staff, reviewed by the Plant Operations Review Committee and Quality Performance, and approved'y the Plant Manager, Ginna Station'. The Plant Manager, Ginna Station .is responsible for the correct and timely performance of the required, tests utilizing written and approved procedures. When contractors are employed for tests, the contractor is required to perform testing in accordance with their approved quality assurance program requirements. All test results are required to be documented, reviewed, and approved by those responsible for performing the test.

When requested by Ginna Station, Gas and Electric Distribution Division performs test activities to determine the cause of protective relay malfunctions. These test activities are performed in accordance with approved procedures by qualified personnel.

Nuclear Engineering Services and Quality Performance are responsible .for assuring that required tests for major Revision 19 December, 1993

0 modifications are included in specifications. Nuclear Engineering Services and Gas and Electric Distx'ibution Division assistance in the preparation of modification-related test procedures may be provided'to the Ginna Station staff. The Ginna Station Technical Manager is responsible for the adequate inclusion of test requirements in minor modification design documents and for reviewing tqodification-related test results for, acceptability to design requirements. Reviews of minor modification design by Quality Performance verifies adequate inclusion of test requirements.

Control of Measurin and Test' ui ment The calibration and control system for measuring and test equipment includes calibration procedures, establishment of calibration frequencies, and maintenance and control requirements of measuring and test instruments, tools, gauges, shop standards, and nondestructive test. equipment which are to be. used in the measurement, inspection, and.

monitoring of components, systems, and structures.

Calibration procedures include step-by-step methods for .

calibration and requirements for. instrument accuracy.

Calibration frequency is based on required accuracy, degree of usage, stability characteristics, manufacturer's recommendations; experience, and other conditions affecting measurement capability.

Control of measuring and test equipment requires: a recall system assuring timely calibration of equipment; a system providing unique identification of equipment, traceability to calibration. test data, and identification of the next calibration date on the equipment;..a..system providing traceability of shop standards to nationally recognized standards (where national standards do not exist, procedures contain instructions to document the basis for calibration) and periodic revalidation of shop standards; a system providing for records to be maintained which indicate the complete status of all items under the calibration system including the maintenance, calibration results, abnormalities, and last and future calibration dates; and a system controlling the purchase requirements of new equip-,

ment to be entered into the calibration and control system including requirements for accuracy, stability, and repeatability under normal use conditions. In the event a measuring instrument (i.e. shop or field standard) is found out of calibration,an'investigation is conducted to determine the validity of previous measurements.

Revision 19 December, 1993

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The Plant Manager, Ginna Station is responsible for the procedures and program required to assure control and calibration of measuring and test equipment at Ginna Station in accordancel'.with the above requirements. Instruments specified in Section 4.1, Technical Specifications, are included in the program. Tools, gauges, and instruments necessary for maintenance, inspection, and test are calibrated and controlled in accordance with station procedures. Measuring, test or inspection equipment used by Nuclear Assurance Quality Control is included in the program.

P The Manager, Materials Engineering and Inspection Services and, Division Manager, Rochester Construction and Maintenance are responsible for establishing a program and the preparation of procedures for the control and calibration of measuring and test equipment used by their respective organizations.

13. Handlin Stora e and Shi in Ginna Station Supervision is responsible for developing and implementing procedures for the handling, storage, shipping, preservation, and cleaning of material and equipment delivered to or located at Ginna Station. Gas and Electric Distribution Division, and Materials Engineering and Inspection Services are responsible for preparing and implementing procedures for the handling, storage, shipping, "

preservation, and cleaning of material and equipment delivered to or located in their "work areas. In addition, the Manager, Materials Engineering and Inspection Services .

is responsible for preparing and implementing procedures for the routine maintenance and .inspection of lifting and handling equipment. Under normal circumstances, manufacturer's specific-written instructions and recommendations and purchase specification requirements are invoked for cleanliness, preservation, special handling, and storage with respect to. environmental requirements. In the

. absence of, or in addition to, specific manufacturer requirements, the management may invoke additional requirements in accordance with department. procedures.

The Department Manager, Nuclear Engineering Services or Plant Manager, Ginna Station are responsible for specifying in procurement documents and in engineering specifications that written procedures be used, as appropriate, for the handling, shipping, storage, cleaning, and preservation of materials and equipment procured for major modifications.

Revision 19 December, 1993

These procedures are prepared by contractors, by the station staff, or by. staff members of Gas and Electric Distribution Division as appropriate. Rochester Gas and Electric procedures are reviewed and approved as described in Section 6.

Xn the preparation of procurement documents, department procedures, and contractor procedures, consideration of handling, shipping, storage, cleanliness, and preservation is given to all material and equipment throughout various stages of manufacturing and installation prior to operational acceptance.

Quality Performance, Ginna Station and Nuclear Engineering Services are responsible for review of engineering-specifications to assure that proper handling, storing, and shipping requirements have been specified. Quality Performance is responsible for assessment of handling, storage, and shipping .activities by suppliers, Rochester Gas and Electric personnel, and contractors.

ns ection Test and 0 eratin Status Equipment or systems not ready for normal service are clearly"identified by use of tags, control. logs,. and other suitable means to indicate the status in a positive manner.

The identification is sufficient to positively indicate the status .of the particular equipment or system being isolated.

The Plant Manager, Ginna Station is, responsible for indicating the status of operating equipment or systems to be removed from service for maintenance, repair, or modification in accordance with the approved Electric System Operating Rules. The Plant Manager designates personnel who have station holding authority.

Personnel who have station holding authority are responsible for directing the status change of equipment and systems in accordance with the approved station holding procedures.

System status is indicated through the use of hold tags, block tags and corresponding control logs.

Equipment or system inspection and test status are indicated by use of test tags, labels, or work inspection and test status sheets. Written procedures control .the use of hold tags, test tags, and labels.

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Systems, components, and equipment which are found to be unacceptable during or after testing are clearly identified.

Fuel handling operations involving, fuel assemblies or other radioactive sources are identified and controlled by the use of tags, stamps, or other suitable means.

Maintenance, repair, or modification of components, systems, or structures utilizes procedures, travelers, data sheets, instructions or checklists to indicate status of the work, inspections or tests and corresponding acceptance or rejection for a particular component, system, or structure.

These job control forms are prepared by the job supervisor and reviewed by Nuclear Assurance Quality Control personnel and maintained at a designated control location to indicate the status and the completion of required inspections and tests.

Quality Performance monitors the status change of Ginna Station activities for their implementation of approved procedures and'ssures that inspection. results are properly documented, Material Engineering and Inspection the procedures for implementing the inspection Services.'stablishes status sheets utilized during inservice inspection.

Nonconformin Materials Parts and Com onents Procedures are. established for the control, evaluation and disposition of deficient material, parts, and components.

Materials, parts, or components which do,not conform to the.

drawing or specification requirements are identify'.ed, controll'ed and reported. RGEE personnel are responsible for initiating nonconformance reports and initiating dispositions. Nuclear Assurance Quality Control personnel are responsible for inspecting and approving closeout- of nonconformance reports. Prior to installation or .use, nonconforming items generally remain in a hold area until an approved disposition has been implemented. Nonconforming items may be released for installation- to meet critical fabrication schedules provided controls are established to prevent inadvertent use prior to implementing the nonconformance disposition. After installation, nonconforming items are identified and controlled until approved disposition has been implemented.

Nonconformances identified .at a supplier's facility and reported- to RGEE, which have supplier recommended dispositions of use-as-is, or repair, are normally processed Revision 19 December, 1993

by the department originating the procurement.

Organizations which specify the requirement being dispositioned are responsible for reviewing and approving the supplier recommended disposition.

Items are repaired and reworked in accordance with approved procedures and current drawings. The repair or rework must be verified as acceptable, by an inspection of the affected item or process which is at least equal to the original inspection method.

Items which are accepted "use-as-is" are fully documented

.with the drawing or specification requi'rement and technical justification for acceptances All such items are approved prior to use by the cognizant organization having responsibility for the requirement. In addition, those "use-as-is" nonconformances which also deviate from a Design Criteria requirement, shall require additional approval of the Senior Vice President; Production and Engineering.

Nuclear Assurance Quality Control personnel provide nonconformance status information periodically. Quality Performance and other. organizations analyze nonconformance report data for.'adverse trends and provide periodic reports to management. Adverse trends form a basis for supplier re-

- evaluation or for other corrective action.

Corrective Action Conditions adverse to quality are those conditions which compromise confidence that a structure, system or component at Ginna Station will perform satisfactorily in, service.

Significant conditions adverse to quality are those conditions which, if uncorrected, could affect the health safety of the public, seriously affect the ability to 'nd operate the plant in a safe manner, represent a serious breakdown in activity controls, or will require a major.

effort to restore capability to perform specified. functions.

Conditions adverse to quality shall be promptly identified and reported to supervision. The condition adverse to quality shall be identified, corrected and evaluated to-determine if a significant. condition adverse to quality exists.

When a significant condition adverse to quality at Ginna Station is identified, the Corrective Action Coordinator is Revision 19 December, 1993

responsible for evaluating the effect of continuing the activity. If continuing the activity would obscure or preclude identification and correction of the deficiency, continuing the activity would increase the extent of the deficiency or lead to an unsafe condition, stop work action is taken.

The Manager Nuclear Assurance has authority to stop work on maintenance, repair, inservice inspection, refueling, modification, testing or inspection deficiencies at Ginna Station, as well as other locations.

Quality Performance may recommend stop work action to the Plant Manager, Ginna Station on operating deficiencies.

The Manager, Quality Assurance has the authority to stop work for conditions identified in Purchasing, Nuclear Engineering Services, Materials Engineering and Inspection

. Services, Gas and Electric Distribution Division or cognizant supplier associations.

For significant conditions adverse to quality, affected RGSE management shall review initiated reports to. determine causes and develop corrective action plans to resolve the identified concerns and preclude recurrence'f, the significant condition adverse to quality involves a design deficiency or the recommended corrective action involves a design change, the review of the condition adverse to

'quality includes Nuclear Engineering Services or Ginna Station design personnel, as 'appropriate.

The Corrective Action Coordinator assures root cause determination and corrective action plans. are developed to resolve the identified concern and to preclude recurrence.

Cognizant nuclear supervision reviews each Corrective Action Report initiated. at Ginna Station and may recommend additional corrective action does not result in adequate if the action already taken resolution.

The Plant Operations Review Committee CAR Subcommittee reviews all corrective action reports to assure that the cause of the condition has been determined and that corrective'ction has been taken to preclude repetition.

Corrective action summary reports are submitted to departmental supervision to keep them aware of significant conditions adverse to quality, related causes and corrective Revision 19 December, 1993

action being taken. Senior Management is advised of the causes and actions of the more significant Corrective Action Reports.

Quality Assurance provides additional assurance of the corrective action program effectiveness through semi-annual audits and periodic surveillances.

ualit Assurance Records Quality Assurance is responsible for establishing the basic requirements for quality assurance record retention and maintenance. Production and Engineering Systems, as directed by the Division Manager,, Technical Services and Chief Engineer, is responsible for,.the retention and maintenance of records. Quality Performance, Purchasing, Nuclear Engineering Services, and Gas and Electric

. Di'stribution Division departments are responsible for forwarding the records they initiate to the appropriate

'Production and Engineering Systems record retention locations. Each organization generating records is responsible for preparation,, review, approval, and implementation of specific quality assurance .record procedures for their areas of responsibility in, accordance with these requirements. The records which fall within quality assurance record requirements include those records

required by Section 6.10 of the Technical Specifications and the Quality Assurance Program. All records associated with

~

the operation, maintenance, repair, inservice inspection,

~

refuel'ing, modification, inspection and testing systems, and components covered by the of'tructures, quality assurance program are included.

Records initiated at Ginna Station include operating logs; the results of inspections, tests, and the monitoring of plant activities; drawings, procurement documents and material analyses; calibration procedures. and reports; and Nonconformance and Corrective Action Reports. Records of the qualification of personnel, procedures, and equipment for special processes and the results of reviews are maintained at the appropriate Production and Engineering Systems record retention location.

Inspection and test records contain a description of the type of test or inspection activity, evidence of completion of the activity, results, the name of the inspector or data recorder, the acceptance or rejection of the activity, and a record of any nonconformances.

Revision 19 December, 1993

The requirements and responsibilities for record accessibility and transmittal are described in the Quality Assurance Manual sections as appropriate. Requirements and responsibilities for'reparation, inspection, identification, review, storage, retrieval, maintenance, and the retention of quality assurance records are in accordance with applicable quality assurance record procedures, codes, standards, and procurement documents. Records are available to authorized personnel.

Removal of records from storage is documented and accountability is maintained by the responsible record control activity.

Records. are either stored in record storage .facilities"which are designed to prevent destruction of records due to fire, flooding, theft, and deterioration by temperature or humidity conditions; or, duplicate records are kept .in two separate storage locations in separate buildings which .are physically isolated from each other.'ecord keeping .procedures provide for receiving, classifying, indexing, labeling, and preparing records for storage. The procedures establish retention- requirements, accessibility, control of obsolete record destruction, and control for issuance and return of all records; Production and Engineering Systems is responsible for maintaining plant operating records as. required in Section 6.10, Technical Specifications.

Production and Engineering Systems is also responsible for.

maintaining off-si'te prepared design records, such as specifications, drawings, design review reports, and design control documentation; 'quality assurance records, .such as audit reports and surveillance reports; purchasing records, such as supplier qualifications, bid evaluations, and purchase orders.'udits Compliance with all aspects of the Quality Assurance Program and the effectiveness of the program is determined by audits and surveillances of all organizations performing quality affecting activities. Quality Assurance is responsible for conducting audits of those organizations and. activities involved in the quality assurance program on a planned, periodic basis. Audit intervals are based on the status. and Revision 19 December, 1993

safety importance of activities being performed, as well as group performance and related management concerns.

Table 18-1 is a list of the audits with activities to be examined for each. Frequencies are based on the level of activity in each area. Audit schedules are established to assure that each of the activities is audited at the frequency specified in Section 6.0. Technical Specifications. Additional audits or surveillances are conducted as required by special conditions, circumstances or to address management concexns.

Each audit requires the development of an audit plan to provide information about the audit, such as the functional areas to be audited, the names of those .who will perform the audit, the scheduling arrangements, and the method of reporting findings and recommendations. Audit planning and .

performance utilize performance based techniques that will facilitate effectiveness assessments as well as compliance verification. The audits are performed in accordance 'with written procedures or checklists by appropriately trained personnel not having direct responsibilities in the areas being audited.

Audit results are documented and reported to the supervisor and division head having responsibility in the area audited and the Nuclear Safety Audit and Review Board. Within a specified period of time, the person having supervisory

-

responsibility in the; area audited is required to review the audit results, take necessary action to correct the deficiencies identified by the audit, and document and report the corrective action.

Quality Assurance is responsible for developing audit-plans and audit checklists, designating and training audit personnel,,and conducting audits.

Audits may be conducted by Quality Assurance engineers or other qualified personnel, such as technical specialists from other company departments and outside consultants.

Audits of major contractors, subcontractors, and suppliers are conducted during the early stages of design and procurement, as required, to evaluate their quality assurance program for compliance with all aspects of the procurement documents. Audits are conducted, as required, to assure that major contractors, subcontractors, and suppliers are auditing their suppliers'uality assurance Revision 19 December, 1993

programs in accordance with procurement documents. During the project or procurement process additional audits are performed, as required, to assure all quality assurance program requirements are properly implemented in accordance with procurement documents.

Quality Performance performs regular analyses of audit and Quality Assurance surveillance results to evaluate quality trends. Results of these analyses are provided to management for their regular review.

Revision 19 December, 1993

Table 1-1 Quality Assurance Program Procedures Subject Listing Appendix B ualit Assurance ualit Control Procedures Criteria Xndoctrination of Quality Assurance/Quality Control and Supervisory Personnel Training of Quality Assurance/Quality Control Personnel Management Review of the Quality Assurance Program Periodic Review of Quality Assurance/Quality Control Procedures Planning and Reporting Results for QA/QC Subcommittee Meetings Quality Assurance/Quality Control Group Organization and Responsibilities Quality Assurance Review of Rochester Gas and Electric Design Criteria Quality .Assurance Review and Approval of Field Change- IXI Reguests and Review of ECN's Quality Assurance Review of Rochester Gas and .IXI Electric Engineering Specifications Preparation, Review and Approval of Quality Verification .III Specifications Computer Software Product Evaluation Quality Assurance, Review of Computer Software Production Evaluations Master Software Index Requisitioning. Quality Assurance/Qual'ity Control Services

'Quality Review of Rochester Gas and Electric Procurement Documents Preparation, Review and Approval of Rochester Gas and Electric Q.A. Specifications Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B ualit Assurance ualit Control Procedures Criteria Preparation, Review and Approval of Ginna Station Quality Assurance Manual Preparation, Review and Approval'f Quality Assurance/Quality Control Procedures Preparation, Review and Approval of the Quality Control group Verification Inspection Program Procedures Revision and Control of the QA Program for Station Operation Review of Nuclear Directives Review of Departmental Procedures VI Preparation,'eview and Approval. of Procedure VI Deviation Requests by Quality Assurance/Quality Control Evaluation of Suppliers by Quality Assurance VII Supplier Surveillance Control of Supplier Performance VII Quality Assurance Evaluation of Bids VII Conducting Commercial Grade Supplier Surveys VII Evaluation of Commercial Suppliers by Quality VII Assurance Document Deficiency Reports VII Establishment and Maintenance of Qualified VII Suppliers List Establishment and Maintenance of the Commercial VII Grade Supplier List Verification Inspection Program Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B ualit Assurance ualit Control Procedures Criteria Qualification of Inspection Personnel Quality Assurance Nonconformance Processing XV Corrective Action Reports XVI Quality Assurance Commitments and Action Items XVI Review of Ginna Maintenance Work .Order Packages XVI Identified Deficiency Reports, XVI Records Turnover Plan XVII Qualification of Audit/Survey Personnel ,XVIII Audit Scheduling and Planning XVIII Performance of Quality Assurance Audits XVIII Reporting and Follow-Up of Audit Findings XVIII Conduct of Quality Assurance During and in XVIII Follow-Up of NSARB Audits Response to Audits and Surveillance XVIII Qualifications of Surveillance Personnel XVIII Review of Audit Program XVII Auditing of the Nuclear Emergency Response Plan XVXI Performance Based Surveillance. Program XVIII Availability and Use of INPO and NRC Inspection/ XVIII Assessment Reports in Audit and QA Surveillance Quality Assurance Planning Guides XVIII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Materials En ineerin Ins ection Services Criteria Indoctrination and Training Materials Engineering and Inspection Services Organization and Responsibilities Preparation, Review and Approval of Purchase IV Requisitions and Related Procurement Documents Quality Materials Engineering and Inspection Services Procedures Quality Materials Engineering and Inspection Services Procedure Deviation Request Preparation, Review and Approval of Material Handling Equipment Instructions Preparation, Review and Approval of Materials Engineering Laboratory Test Procedures Control and Distribution of Documents. Regulating VI Safety Related Activities Control of Purchased Materials , VII Preparation, Review and Approval of Supplier VII Evaluation Control of Purchased Services VII Welding Procedure Preparation Review and Approval Welding Procedure Qualification IX Heat Treating Procedures IX Welder Qualification and Currency IX Nondestructive Examination Procedures IX Nondestructive Examination Procedures Manual IX Nondestructive Examination Personnel Qualification IX Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Materials En ineerin Ins ection Services Criteria Qualification of Visual Examination Personnel IX Erosion/Corrosion Program IX General Brazing Procedures Preparation and Approval IX General Brazing Procedures Qualification IX Inservice Inspection Program and Plans ASME Section XI Repair, Replacement and Modification Procedure Incorporating Ginna Modifications into Inservice Inspection Program Duties of the ANII Tests conducted by MEIS Laboratories XI Requesting MEIS Laboratories Services XI Test Personnel Qualifications Vendor. Tests under MEIS Direction . XI.

Calibration and Control of Nondestructive XII Examination Instruments Inspection and Maintenance of Material Handling . XIII.

Equipment Overhead and Gantry Cranes XIII Inspection and Maintenance of Portable Lifting XIII and Handling Equipment Underhung Cranes, Jib Cranes and Monorail Systems XIII Slings and Related Apparatus XIII Classification and Training of Material Handling XIII Equipment Personnel Revision 19 December, 1993

,

0 0

Table 1-1 (cont'd)

Appendix 8 Materials En ineerin Ins ection Services Criteria Mobile Hydraulic Cranes XIII Inspection and Maintenance of Jacks, Hydraulic Rams XIII and Cylinders Forklift Loading Forks XIII Inspection of Designated Monorails XIII Training and Qualification of Crane Operators XIII Lifting Devices in the Containment Vessel XIII Pre-Shipment Inspection of Radioactive Material XIII Shipping Containers Nonconformance Reports. XV Initiating and Responding to Corrective Action XVI Reports

'uality Materials Engineering and, Inspection XV.II.

Services Records Response to Audits XVII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Ginna Quality Assurance Program Implementation Fire Watch Training R.E. Ginna Training Plan Ginna Station Training General Employee Training Temporary Employee Training Hazardous/Mixed Waste Emergency Response Trainipg Operator Training Responsibilities R.E. Ginna Health Physics Orientation Program Fire Brigade Training Radiation Protection Technician Entry Level Requirements, Responsibilities, and Training

~

Chemistry Technician Entry .Level Requirements, Responsibilities, and Training

~

Maintenance Training Program Ginna Station Administrative and Engineering Staff Responsibilities Ginna Station Management Responsibilities XI Physics and Chemistry Section Organization, 'ealth and Responsibilities Support Services Organization and Responsib'ilities Operations Section Organization and Responsibilities Technical Section Organization and Responsibilities Material and Procurement Section Organization XI and Responsibilities Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Operational Assessment Section Ginna Station Staff Responsibilities for Fire Prevention Ginna Modification Project Organization Plant Operations Review Committee Operating Procedure Radiation Emergency Plan Implementing Procedure Committee Emergency Procedures Committee (EPC)

Ginna Standard Nomenclature XI Preparing and Dispositioning of Technical Staff.

Request Control of Station Modification Station Modif'ication Classification and Review Station Modification Planning Control XXI Station Modification Installation and Acceptance Station Modification Completion Preparation, Review &. Approval of Design Input Documents for Minor Modifications Component Classification Request/Reanalysis, XII Evaluation of Parts to Determine 'Safety Classification XXI Preparation, Review and Approval of. Safety Analysis Preparation, Review, Approval and Distribution of Design Output and Design Review Documents for Minor Modifications Technical Evaluation Revision 19 December, 1993

0 Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Preparation of Configuration Data Change Forms Computer Software Product Evaluation Control of Procurement Documents Prepared at IV Ginna Station Evaluation of Commercial Grade Items for Safety IV Related Applications Evaluation of Items for In-Storage Maintenance IV Requirements Plant Procedures Preparation and Classification t

V Plant Procedure Content and Format Requirements V Emergency and Abnormal. Operating Procedures Writers'uide-Operating Procedures Writers'uide "Health Physics and Chemistry Procedures Writers'uide Plant Procedure Adherence Requirements Emergency and Abnormal Operating Procedures Users'.

Guide Procedure Control Procedure Control-New Procedures Procedure Control-Permanent Changes VI Procedure Control-Temporary Changes VI Procedure Control-Periodic Review VI Procedure Control-Index VI Procedure Control of Emergency and Abnormal Procedures Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Procedure Control - Amendments to Licensing VI Documents and Changes to the Facility Procedure Change Control 10CFR 50 '9 Review Emergency and Abnormal Operating Procedure Support Documentation Control Procedure Distribution Vj Control of Construction Documents VI Vendor Manual Control Program Vj Vendor Manual Information/Discrepancy/Incorpor'ation VI Request.

Drawing Change Request VI Conditional Release Program VII Receipt and Acceptance of Materials/Parts Vjj Control of Purchased Services VII Inventory Control of Material, Parts and Components at Ginna Station Identification and Marking of Accepted Material, VIII Parts, and Components

. Bulk Storage of Combustible'Materials and Their Use VIII Trailer Admittance Requirements VIII Control of Consumable Materials at 'Ginna Station VIII Control of Welding Nondestructive Examination Control IX Welding Equipment Performance Verifications Revision 19 December, 1993

0 Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Open Flame,, Welding and Grinding Permit (Hot Work Permit) IX Control of Inservice Inspection Activities ASME Section XI Repair, Replacement and Modification Procedure for Ginna Station Electrical Preventive Maintenance Program Environmentally, Qualified Equipment Maintenance Program Mechanical Preventive Maintenance Program for X Rotating 'Equipment Equipment Inspection and Lubricant List Valve Preventive Maintenance Program X Condenser Inservice Inspection Program Preventive Maintenance Program for Plant Security X Equipment Performance of Tests. XI Qualification and Certification of Test. Personnel=

Test Tag Control Program Calibration, Test, Check and Replacement. Surveillance Program for Instrumentation and Equipment Important to Safety XI Ginna Station Surveillance Schedule XI Inservice Testing of Pumps and Valves Calibration and Control of Test Equipment XII Maintenance and Inspection of Material Handling Equipment XIII Revision 19 December, 1993

0 Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Control of Material Handling and Handling Equipment XIII Storage and Preservation of Materials and Equipment at Ginna Station XIII Control of Heavy Loads at Ginna Station XIII Control of Heavy Loads for the Containment Overhead Crane XIII Control of Heavy Loads for the Auxiliary Building Overhead Crane XIII Control of Heavy Loads for the 7 1/2 Ton Screenhouse Crane XIII Control of Heavy Loads for Jib Cranes in.

Containment XIII Control of Heavy Loads in Safety-Related Areas XIII Housekeeping Control XIII, .

Station Holding Rules XIV Bypass of Safety Function of Jumper Control XIV Operational Assessment .Program -XIV Effectiveness Evaluation of the Operational Assessment Program XIV Installation -and Removal of Temporary Cables XIV.

Control of .Temporary Modifications XIV Installation, Removal and Control of Scaffolding XIV

'Installation and Removal of Temporary Fluid System Provisions XIV

'Program to Prevent Degradation of Reactor Coolant Pressure Boundary XIV Revision 19 December, 1993

0 Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Independent Verification XIV Control of Nonconforming Items XV Nonconformance Reports XV Corrective Action Reports XVI Root Cause Analysis XVI Overview of the Ginna Station Work Control System XVI Work Request/Trouble Report Initiation XVI Work Order Initiation XVI Work Order Planning XVI Work Ord'er Scheduling XVI Work Order Execution XVI Post Maintenance Testing XVI Work Order Close Out XVI Work Order Processing After Hours XVI Work Control System Performance Indicators XVI Station Work Authorization Request XVI Safety Classification of Mainten'ance Work Activities XVI Identified Deficiency Reports XVI Ginna Records XVII Records Storage Facilities and Equipment XVII Special Nuclear Material Inventory and Record

'equirements XVII Maintenance History Program XVII Ginna Station Response to Internal Audits XVII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Indoctrination and Training Engineering Department Organization and Responsibilities Ginna Modification Project Organization Preparation, Review and Approval of Design Input Documents Preparation, Review and Approval of Design Analyses Preparation; Review and Approval of Engineering Drawings - III Review and Approval of Engineering .. III ',

.'reparation, Specifications Preparation, Review and Approval of Design Verification,:

Integrated Design Process Preparation, Review and Approval of, Safety Analyses Review and Approval of Architect Engineer or ~

III Design Documents 'onsultant Preparation, Review and Approval of Field'hange Requests Preparation, Review and Approval of Engineering Change Notices

'. XII Review. of the Classification of Station Modifications Preparation, Review, and Approval of CAD Piping and IIX Instrumentation Drawings Preparation, Review and Disposition of Drawing Change Requests ALARA/ Radiation Safety Design'Review Revision 19 December, 1993

'k Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Preparation, Review and Approval of Appendix R Conformance Verifications Preparation, Review, and Approval of the Environmental Qualification Data Electrical'quipment Summary Form EEQ-1 and IEEE 323-1974 Waiver .

Authorization Form EEQ-2 Review, Approval and Implementation of Changes to the Safety Assessment System Software Engineering Computer Software Documentation and Control Human. Factors Review of. Control Room and Local I I I,.

Control Panel Modifications 'mergency Preparation, Review and Approval of PAID Database IIX and Configuration Data Change Forms Erosion/Corrosion Control Monitoring Program for Carbon Steel Piping Preparation, Review and Approval .of Changesto the .

Updated Final Safety Analysis Report ASME Section XI Repair, Replacement and Modification Program Implementation

'. Component Safety Classification Drawing Review Process, Component Safety Classification Component IIX Classification Form Component Safety Classification Request/Re-Analysis System, Structure,. or .Component Safety Classification III" Criteria Preparation, Review and Approval of CAD Electrical Drawings Revision 19 December, 1993

i Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Requests for Nuclear Engineering Services Preparation, Review and Approval of Procurement IV Documents for Purchases Covered by the QA. Program Evaluation of Commercial Grade Items for Safety IV Related Applications Evaluation of Quality Verification Items for Safety IV Significant Applications Preparation, Review, and Approval of Engineering Procedures Review, and Approval of Engineering V'reparation, Procedure Deviation Request Distribution and Control of Documents by VI the Control Number Method Distribution and Control of Documents by Project . .. . VI Correspondence Procedures Preparation, Review,and Approval of Supplier Evaluations VII Review and Approval of Vendor Design and Manufacturing .. VII Technical Documents Preparation, Review and'pproval of Bid Requests, Bid, VII Evaluations and Recommendations for Award Engineering Review of Nonconforming Materials, Parts VX or Components Initiating and Responding to Corrective Action Reports XVI Processing Identified Deficiency Reports XVI Documenting and Reporting Potential Conditions XVI Adverse to Quality Performing "Substantial Safety Hazard" Evaluations XVI for 10CFR21 Reportability Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Records XVII Records Turnover Plan XVII Engineering Response to Internal Audits XVIII Revision 19 December, 1993

Table 1-1 (cont',d)

Appendix B Purchasin Procedures Criteria Periodic Review of Purchasing Procedures Indoctrination and Training of Purchasing Personnel Purchasing Department Organization and Responsibilities Preparation, Review, Approval and Issuance of IV Purchase Orders and Changes to Purchase Orders Requests for Bids and Bid Evaluation IV Purchasing Procedures Purchasing Procedure Deviation Request V Supplier Evaluation VII Supplier Material Deficiency Processing XV Supplier Corrective Action Reporting XV1 Purchasing Response.to Corrective, XVI Action Reports and Corrective Action Reporting Purchasing Records and Turnover Plan XVII Purchasing Response to Audits XVIII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Production Division Trainin Procedures Criteria Indoctrination and Training Production Division Training Organization and Responsibilities Operations and Technical Training Organization and Responsibilities Training Systems Organization and Responsibilities'aintenance Training Organization and Responsibilities Curriculum Committee Organization and Responsibilities Software Quality Assurance Program Preparation, Review and Approval of Quality Training Procedures Review and'pproval of Training V'reparation, Procedures, Guidelines, and Policies

~ ~

Preparation, Review and Approval of Nuclear V, Training Programs Style Guide for Training Procedure Development Nuclear Training Procedure Revision Training Change Request/Notice Control .and Distribution of Production. Division VI Training Documents Training Programs for Crane Operators and Riggers XIII Corrective Action XVI Nuclear Production Division Training XVII Records Management Production Division Training Response to QA Audits XVIII Revision 19 December, 1993

Table 1-1 (cont'd)

Gas and Electric Distribution Division Procedures Appendix B Criteria Quality Assurance Program Implementation for Gas and Electric Distribution Division Department Indoctrination and Training of Gas and Electric Distribution Division Personnel Gas and Electric Distribution Division Organization Design/Modification Activities Control at Ginna Station Design/Modification Activities Control at Station 13A and on Circuit 751, Equipment and Line Control of Procurement Documents for Purchased IV Parts, Components and Services Preparation, Review and Approval of Electric V Transmission and Distribution Procedures Preparation and Approval of Laboratory Test Procedures Preparation and Approval of Electric Meter and .

Laboratory Calibrate.on Schedules Preparation and Approval of Electric Substation Department V Relay Test Schedules Preparation and Approval of Electric Transmission and V Distribution Deviation Requests Control of Gas and.Electric Distribution Division VI.

Procedures Control and Distribution of Electric Meter and Laboratory VI Department and Laboratory Test Procedures Control of Electric Meter and Laboratory Department-Calibration Services Control of Electric Substations Department Relay VI Test Schedule Revision 19 December, 1993

0 Table 1-1 (cont'd)

, Gas and Electric Distribution Division Procedures Appendix B Criteria Supplier Technical Evaluation VII Receipt and Acceptance of Instrumentation and VII Standards Equipment ..

Control of Purchased. Services for Electric Meter and Lab VII Identification and Control of Materials, Parts and VIII Components Surveillance at the Gas and Electric Distribution Division. X Division Performance of Tests at Ginna Station  : XI Personnel'I Performance of Tests at the Electrical Laboratory Qualification of Test and Control of Test Instruments XII, XI'alibration Nonconforming Parts and:Components and Processing of Corrective Action Reports .XVI 'nitiating Control of Quality Assurance Records .XVII Gas and Electric Distribution Division Response to Audits.'VIII.

Revision 19 December, 1993

TABLE 4-1 Procurement Document Re uirements Items to be considered for inclusion in procurement documents include:

1. Sco e of Work - Detailed statement of the work to be performed.

2. Technical Re uirements by reference to specific drawings; specifications, codes, regulations; procedures or instructions, including, revisions, that describe the items or services to be furnished. Also identified shall be test, inspection and acceptance requirements, and any'special .

requirements for such activities as designing, identification, fabrication, cleaning, erecting,. packaging, handling, shipping, extended storage and shelf life.

• 3 ualit Assurance Pro ram Re uirements - which require. the.

supplier to have a documented quality assurance progiam that ~

implements portions or all of lOCFR50 Appendix B as well as

~

applicable quality assurance program requirements of other nationally recognized codes and standards. Also included shall be the requirement that the supplier incorporate appropriate quality assurance program requirements. in subtier procurement documents.

Ri ht of Access - to include the facilities and records of.- - .

the supplier for source inspection .and audit. by the Purchaser or'parties designated by =the purchaser. . Also included shall be provisions for the identification of witness, and hold points and the minimum time of advance .notice'.,

• 5. Documentation. Re uirements Submittal approval and retention requirements for documents such as quality assurance manuals, special process and test procedures, materials records, calculations and analyses.

• 6. Nonconformance - Requirements-for reporting .and;disposition of nonconformance to procurement requirements' Items reviewed by Quality Assurance or Quality Control.

Revision 19 December, 1993

Table 18-1 Audit List Audit Title Audit To ic Areas Corrective Action Corrective Action associated with deficiencies occurring in facility, equipment, structures, systems or methods of operation.

Operational Assessment Nonconformance Control

• Outage Activities Refueling and Special Nuclear Material-ISI Implementation IST Program and Implementation Surveillance Test and LCOs Maintenance Modification Installation Safety Security Radiation Protection and ALARA

• Health Physics, Chemistry 'and Radwaste Shipping and Process Radwaste Control Program and implementing procedures Radioactive Effluents and Offsite Dose Calculation" Manual and implementing procedures Radiation Protection and ALARA HP/Chemistry Measuring and Text Equipment Chemistry Program Radiological Environmental Monitoring Program

+Fire and Safety Fire Protection Program and implementing procedures Fire Protection and Loss Prevention Program Revision 19 December, 1993

Table 18-1 (con't)

Audit List Audit Title Audit To ic Areas Independent Inspections and Audits Fire Systems Fire Surveillance Fire Brigade Training Fire Brigade Equipment Safety Program Housekeeping Instructions, Procedures, Drawing Control and Document Control Vendor Manual Control Procedure Control Records Control ~

Security Security Plan and Implementing procedures Guard Training and Qualification Fitness for Duty Program

• Operations Limiting Conditions for Operation.

Surveillance Testing Operator Performance Operations Administration PORC Activities NSARB Activities Materials Engineering and ISI Program Inspection Services NDE Qualifications Welding Qualifications MHE Program Miscellaneous QA Controls

• Maintenance and Testing Preventive Maintenance Program Planning and Scheduling Work Order Implementation Post-Maintenance Testing Work Order Closeout and Equipment History Control of Measuring and Test Equipment Revision 19 December, 1993

Table 18-1 (con't)

Audit List Audit Title Audit To ic Areas Technical Specification Surveillance Nuclear Emergency Response Plan Nuclear Emergency Response Plan and Procedures Offsite Agency Interface Response Personnel Training Emergency Information Plan Training/performance and Licensed Operator qualifications of the Auxiliary, Operator operating and technical staff Chemistry Technician Maintenance Radiation Protection Technician Results and Test Technician QC Inspector Shift Technical Advisor Technical Staff and Managers Engineering Department Training General, Employee Training Procurement Procurement Evaluations Procurement Document Control Control of Purchased Items and Services Handling, Storage, and Shipping Hazardous Material Control Program Configuration Control Major Modification Design Minor Modification Design Installation Planning Control of As-Built Configuration Licensing Activities Temporary Modifications Revision 19 December, 1993

i Table 18-1 (con't)

Audit List Audit Title Audit To ic Areas Gas and Electric Systems Engineering and Distribution Division Design Rochester Construction and Maintenance Distributive Information Systems Support

• Noted audits will also address relevant activities to .verify conformance of facility operat'ion to all provisions contained in Technical Specifications and 'appl'icable license conditions..

Revision 19 December, 1993

R.E. GINNA NUCLEAR POWER PLANT MANAGEMENTORGANIZATION CHART UNES OF COMMUNCATIQN UNES OF SU~ AND ADMIMSTRATION CHAIRMANOF THE BOARD, PRESDEMT AND CHIEF EXECUTIVE OFFCER SEMR SENIOR VCE SENIOR VCE VICE PRESDENT PRESDENT, PRESIDEMT, GAS & ELECTRIC PRODUCTON AND CONTR OI.LER IXSmlBVTKW ENGWEERWG & CHIEF AND CUSTOMER FINANCIAL SERVICES OFFCER VCE PRESDENT DMSON MANAGERTECHNCAL VCE PRESDENT NSARB VCE EMPLOYEE SERVICES AMO GINNANUCLEAR PRES DENT, RELATIONS. CHIEF ENGINEER PRODUCTION SECRETARY PUBUC AFFAIRS DEPARTMENT AND AND MATERIAL MANAGER MANAGER DIRECTOR DEPARTMENT TREASURER MANAGEMENT PRODVCilON CORPORATE MANAGER QUAUTY PERFORMANCE ANO RADIATION PRODUCTION DEPARTMENT DIVISON DIVISON ENGWEERING PROTECTION DMSON MANAGER MANAGER MANAGER SYSTEMS .-TRAINING PROJECT RSK SYSTEM ROCHESTER MANAGEMENT CORPORATE MANAGEMENT ENGINEERIHG CONSTRUCTION RECORDS HEALTH TRAIMWG AND DESGN AND MANAGEMENT, PHYSCS AND SERVICES MAINTENANCE NUCLEAR IXRECTOR TECH NCAL QUAUTY EMERGENCY OF SECURITY WFORMATlOM ASSURANCE CENTER,CNS, PLANNWG PROCVREMENT, WFORMATKW DEPARTMENT DEPARTMENT DEPARlllEMT SUPERVISOR ENGWEERWG, SERVICES &

MANAGER MANAGER MANAGER DEPARTMENT PLANT NUCLEAR AIXXT& DMSON SYSTEM IXSTRIBIflIVE METER AND MANAGER MANAGER SECURIlY SVRVBLLANCE SYSTEMS DESGN INFORMATION tAB HUCLEAR GWNA SERVICES ENGWEERWG SYSTEMS OPERATIONS ENGWEERING STATION SECURITY SUPPORT SERVCES SERVICES FIELD & SHOP ENVIRONMENTAL c RBAY ELECTRC FABRCAllON SC ENCE, SERVCES LABORATORY DESGM, STATION ENGINEERWG COMMVNCAIIONS METER CHEIIISTRY CONSTR UCTCN, OPERATlONS.

OPERATIONS SERVICES AND MAINTENANCE, QVAUIYc RESEARCH & FUEL KP &

LABORATORY COHTROL AND MANAGEMENT& CHEMISTRY DEVELOPMENT EMIPLOYEE SERVICES QUAUlY TECHNICAL COMmOL, RELATIONS ENGINEERING SUPPORT TECHNICAL DEPARTMENT SERVCES SERVICES SUPPORT, IOWAGER TESTING, OVERHEAD MANAGER MATERIAL CON SIR VCDOM MATERIALS CONTROL, AND ENGWEERWG PROCUREMENT, MAINTENANCE- AMD FIRE EAST INSPECTION PROTECTION, SERVCES SAFETY, MODIFCATIOM, CONSTR UCilON OPERATING RBAYTEST EXPERIENCE &

ENGWEERWG. COMPVTER SYSTEMS MHE ISNP.

SERVCES FIGURE 2-1

QUALITYPERFORMANCE ORGANIZATION DEPARTMENT MANAGER QUALITY PERFORMANCE MANAGER MANAGER MANAGER QUALITY QUAI ITY NUCLEAR MATERIALS PERFORMANCE ASSURANCE ASSURANCE ENGINEERING SENIOR 8 INSPECTION ANALYST

- SERVICES QUALITY QUALITY QUALITY MATERIAL8 STAFF ASSURANCE CONTROL CONTROL MATERIAL ENGINEERS ENGINEERS FOREMAN HANDLING ENGINEERS 8 FOREMEN STAFF TECHNICIANS 8

INSPECTORS FIGURE 2-2

GINNA NUCLEAR PRODUCTION ORGANIZATION VCE PRESDEMT 0 INNA NUCLEAR PRODUCTION BUDGET AND COST PLANT MANAGER DEPARlMENT DEPARTlIENT OINNASTATION MANAGER MANAGER NUCLEAR PRODVCllON NVISON ENGINEKRINO TRAJNINO SERVCES SV PERINTENDENT NITIALUCENSED DESGM GINNASUPPORT OPERATOR I

SERVCES CONSTRUCTION OPERATOR REOUAL I UCEN SINO OPERAllONS OPERATINO PlhNNINO d AUX OPERATOR CORPORATE HEALTH EXPERIENCE ECHE DVUNO FUEL MANAGEMENT PHYSICS HEALTH PHYSCS d STA INITIAL CHEMISTRY MATERIALS MAINTENANCE TECHNCAL SUPPORT NUCLEAR PROCUREMENT SYSTEMS STA REOVAL SERVCES EMERGENCY TECHNCAL PLANNINO ENGINEERING MAINTENANCERULE CHEMISTRY TECH PROJECT COMPUTER SYSTEMS RAD PROTKCIIOM ELECTRCAL ANO ldC TECH MAINTENANCE CONTRACT RAD MKCHANCAL PROTECTION TECH MAINTENANCE ELECTRCAL MAINTENANCE MECHANCAL MAINTENANCE r0 UI Id C TECHNXXAM RdT TECHNCIAM LO lA FIGURE 2-3

GAS AND ELECTRIC DISTRIBUTION DIVlSION SENIOR VICE PRESIDENT GAS AND ELECTRIC DISTRIBUTION AND CUSTOMER SERVICES DIVISION MANAGER DIVISION MANAGER SYSTEM ENGINEERING ------ ~------------- ~ ~ 0~

ROCHESTER AND DESIGN CONSTRUCTION .

AND MAINTENANCE DEPARTMENTMANAGER DEPARTMENT MANAGER QUALITY DEPARTMENT MANAGER DEPARTMENT MANAGER SYSTEM DESIGN DISTRIBUTIVE SERVICES METER AND LAB OVERHEAD ENGINEERING INFORMATION COORDINATOR OPERATIONS CONSTRUCTION AND SYSTEMS SUPPORT MAINTENANCE- EAST SUBSTATIONS RELAY ENGINEERING ENGINEERING COMMUNICATIONS ELECTRIC LABORATORY CONSTRUCTION METER SERVICES RELAYTEST OPERATIONS NOTE: Chart Is abbreviated to show only key positions involved In Implementing the QA program and therefore, does not show all positions In the division.

LINES OFAUINORllY LINES OF COMMUNICATION FIGURE 2-4

TECHNICAL SERVICES DIVISION ORGANIZATION DIVISION MANAGER TECHNICAL SERVICES AND CHIEF ENGINEER MANAGER DEPARTMENT MANAGER PRODUCTION MANAGER DIVISIONAL AND GENERAL SERVICES ENGINEERING ENGINEERING SYSTEMS SERVICES MANAGER DIVISION MANAGER FOSSIL . PROJECT SHOP SYSTEMS ENVIRONMENTAI ENGINEERING MANAGEMENT OPERATIONS SCIENCE SERVICES RECORDS HYDRO MANAGER MANAGEMENT MANAGER ENGINEERING FIELD CHEMISTRY SERVICE FOSSIL/HYDRO SERVICES FACILITY OPERATION SYSTEMS ENGINEERING SUPERVISOR MANAGER TECHNICAL ENVIRONMENTAL REAL ESTATE ADMINISTRATIVE INFORMATION LABORATORY MANAGEMENT SERVICES AND CENTER PROJECT SENIOR PLANNING ENVIRONMENTAL ANALYST MANAGER RESEARCH 8 INSPECTION/LAND DEVELOPMENT SURVEY AND PROGRAM BUILDING SERVICES FIGURE 2-5

G IN NA STATION REVIEW AND AUDIT FUNCTIONS NSARB QUALITY PORC PERFORMANCE T T T TECHNICAL MATERIALS GAS AND PURCHASING GENERAL NUCLEAR GINNA STATION SERVICES ENGINEERING ELECTRIC MAINTENANCE ENGINEERING DIVISION AND DISTRIBUTION SERVICES INSPECTION DIVISION SERVICES REVIEW AUDITS FIGURE 2-6

l ATTACHMENT 2 ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT Revision 19 to:

Quality Assurance Program for Station Operation DOCKET NO. 50-244 December, 1993

'

P

TABLE OF CONTENTS Section Title Pacae QUALITY ASSURANCE PROGRAM FOR STATION OPERATION Quality Assurance Program

2. Organization

3. Design Control Procurement Document Control 14

5. Instructions, Procedures and Drawings 16 Document Control

7. Control of Purchased Material, Equipment 20 and Services

8. Identification and Control of Materials, Parts and Components Control of Special Processes 26 Inspection 27 Test Control 28

12. Control of Measuring and Test Equipment 30

13. Handling, Storage and Shipping 31 Inspection, Test and Operating Status 32

15. Nonconforming Materials, Parts and Components 33

16. Corrective Action

17. Quality Assurance Records 36 18., Audits 38 Revision 19 December 1993

UALITY ASSURANCE PROGRAM FOR STATION OPERATION ualit Assurance Pro ram The Quality Assurance Program has been developed by the Rochester Gas and Electric Corporation to assure safe and reliable operation of the R. E. Ginna Nuclear Power Plant.

This program applies to all activities affecting the safety related. functions of the 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. These quality affecting activities include operation, maintenance, repair, inservice inspection, procurement, refueling, modification, test and inspection. In addition, the Quality Assurance Program applies to the activities associated with the packaging of" licensed radioactive materials to be shipped in accordance with lOCFR Part 71 excluding fabrication and design of shipping casks'he basic Rochester Gas and Electric 'Corporation quality assurance policy is, established by. the Chairman of the Board, President 'and"Chief Executive Officer. This policy is implemented under the overall direction of the Senior Vice President, Production and Engineering through the:

Department Manager, Quality Performance; Vice President-Ginna Nuclear Production; the Plant Manager-Ginna Station; Division Manager-Technical Services and Chief Engineer; and heads of other supporting departments.

The program is governed by a.Ginna Station Quality Assurance Manual which contains the requirements and assignment of responsibilities for implementation of the program. The manual is prepared, reviewed, and maintained by Quality Performance and approved by the Senior Vice President, Production and Engineering.

The program is implemented through Quality Assurance/Quality Control, Ginna Station, Nuclear Engineering Services, Production Division Training, Materials Engineering and Inspection Services(,:-:,Gas,t',:'and::.':;:lBlectrac.,',";,'Das't'ai'butao'nj!

", 'an'"'pure asrng Diva~ii'~fief procedures. These procedures are prepared, approved and maintained by the responsible organization and reviewed by Quality Performance. In addition to its procedure review, Quality Performance assures procedure adequacy through use.

audits and surveillances of a sample of procedures in

-

These procedures are reviewed for adequacy at least once every two years by the responsible organization.

Revision 19 December, 1993

Table l-l provides a listing of the subjects and a short description of the subject matter which is contained in ~

Ka.ch:-:.'procedures Organizational interfaces are defined and controlled by sections of the Quality Assurance Manual. Organizational responsibilities are described in Section 2.

The Quality Assurance Program covers all existing Seismic Category l and Class 1E structures, systems, and components, including their foundations and supports. Activities affecting the quality of these structures, systems, and components are controlled to an extent consistent with their safety significance. A detailed listing of the structures, systems and components covered by the Quality Assurance Program and,based on Section 3.2 of the Updated Final Safety Analysis Report, is contained in a controlled database. The criteria for determining if the quality assurance program applies are reviewed by Quality Performance.

Details of -the water-and-steam-containing system boundaries are contained on system flow drawings.

Modifications or additions to existing structures,.systems, and components are designated the same seismic classification .as the existing system. New structures, systems,. and components are designated a seismic classification in accordance with the guidelines in USNRC Regulatory Guide 1.29, Revision 3.

Supervisory personnel are indoctrinated in quality assurance policies, manuals, and procedures to assure .they understand, that these are mandatory requirements which must be implemented and .enforced. Personnel responsible for performing activities affecting quality are trained and indoctrinated in the requirements, purpose, scope,and implementation of ajj3.'fegb3ygj.,quality related program manuals and procedures. Refre'sher" sessions are held periodically.

Retraining may be required whenever a new procedure is issued or a major revision is made to an existing procedure.

Training of personnel not in the Quality Performance organization is the responsibility of each department performing an activity affecting quality. Quality Performance assists in establishing training requirements and assures that personne3, are trained by auditing training.

Revision 19 December, 1993

In addition to training in quality assurance, each department conducts training, including on-the-job training, to the extent necessary to assure that personnel are qualified for their primary work assignments.

The Vice President, Ginna Nuclear Production is responsible for the formal training, qualification, licensing, and re-qualification of o erators, as necessar . As ap ro riate, personnel 'g'@Ag't'8'i9':'..,gpiiier548@'iePes'i~tc! $ 8 j;::i trained in radiation protection, plant safety and'"security.

The Nuclear Safety Audit and Review Board is required to review the status and adequacy of the Quality Assurance Program at least once every two years to assure that it is meaningful and is effectively complying with corporate policy and 10CFR50, Appendix B. This review consists of audits or a review equivalent to an audit performed by company personnel or outside organizations.

The Quality Assurance Program is designed to meet the requirements of Title 10 of the Code of Federal Regulations, Part 50, Appendix B,,"Quality Assurance Criteria for Nuclear Power Plants." The program conforms to the following NRC Regulatory Guides and ANSI Standards:

a. NRC Regulatory Guide 1.8, Revision 1, "Personnel Selection and Training".

b. NRC Regulatory Guide 1.28, Revision 2, "Quality Assurance Program Requirements (Design and Construction) ".

C. AEC Regulatory Guide 1.=30, Revision 0, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment".

d. AEC Regulatory Guide 1;33, Revision 0, "Quality Assurance Program Requirements (Operation)," and regulatory staff comments and supplementary guidance contained in: the document, entitled "Guidance on Quality Assurance Requirements During the Operations Phase of Nuclear Power Plants", Revision 0 dated October 1973 (Orange Book - Revision 0)

Revision 19 December, 1993

0 AEC Regulatory Guide 1.37, Revision. 0, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants".

NRC Regulatory Guide 1.38, Revision 2, "Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants".

NRC Regulatory Guide 1.39, Revision 2, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants".

h. NRC Regulatory Guide 1.58, Revision 1, "Qualification of Nuclear, Power Plant Inspection, Examination and Testing Personnel".

NRC Regulatory Guide 1.64, Revision 1, "Quality Assurance Requirements for the Design of Nuclear Power Plants."

j. NRC Regulatory Guide 1.74, Revision 0, "Quality Assurance Terms and Definitions" ~

k. NRC Regulatory Guide 1.88, Revision 2, "Collection, Storage and Maintenance of Nuclear Power Plant Records".

NRC Regulatory Guide 1.116, Revision O-R, "Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment .and Systems".

NRC Regulatory Guide 1.123, Revision 1, "Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants".

n. NRC Regulatory Guide 1.144, Revision 1, "Auditing of Quality Assurance Programs for Nuclear Power Plants" except that supplier audit frequencies and performance evaluations are as described in the Quality Assurance Manual.

Revision 19 December, 1993

0 0

e

o. NRC Regulatory Guide 1.146, Revision 0, "Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants".

Or anization The major organizations participating in the Quality Assurance Program are Purchasinq, Technical Services, Ginna production ~ggasj!and":"."::::El'ectrwcl!'S'distr'r'hut'aozj!Xfi!lfi~8xp~A

"," " 'ua "i 'rea OimanCe,

'uclear y

the Plant Operations Review Committee, and the Nuclear Safety Audit and Review Board. Figure 2-1 is an organizational chart 'showing these organizations and their relationship to the corporate organization.

Positions responsible for the principal elements of the quality assurance program are:

Chairman of the Board, President and Chief Executive Officer Senior Vice President, Production and Engineering Vice President, Ginna Nuclear Production Division Manager, Technical Services and Chief Engineer Department Manager, Nuclear Engineering Services piphx;:tgjig.j:.:Nieige',i": Quality Pi r ormance Manager, Quality Assurance Production and Engineering Department Manager and, Purchasing Agent, Materials Management Plant Manager, Ginna Station Superintendent, Ginna Support Services Superintendent, Ginna Production Department Manager, Production Division Training Mana er, Nuclear Assurance Piijry',eao 9 zv'i!eron:::;:!Man'ager'~~Ra'ahii'eL e+rLonereuti.,:Li>ai'i~<:::aii'0

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In addition to the above individuals, two advisory groups are utilized to review and audit plant operations. These groups are the Plant Operations Review Committee and the Nuclear Safety Audit and Review Board. The Plant Operations Review Committee acts in an advisory capacity to the Plant Manager, Ginna Station and the Nuclear Safety Audit and Review Board advises the Senior Vice President, Production and Engineering. The qualifications of members and the responsibilities of these organizations are described in Section 6.0, Technical Specifications, Appendix A to the Full Term Operating License No. DPR-18.

The Chairman of the Board, President and Chief Executive Officer of the Rochester Gas and Electric Corporation directed the establishment of the Quality Assurance Program and issued the governing policy statement. He has established the Nuclear Safety Audit and Review Board to review and audit plant operations: The Chairman of the Nuclear Safety Audit and Review Board is responsible to the Chairman of the Board, President.and Chief Executive Officer on all activities of the Nuclear Safety Audit and Review Board.

The Senior Vice President, Production and Engineering reports to the Chairman of the Board, President and Chief Executive Officer and has corporate responsibility for operation of Ginna Station in .accordance with applicable regulatory requirements. In addition, he has overall responsibility and authority for directing the Quality Assurance Program and shall be responsible for the approval of the Quality Assurance Manual. He is responsible for establishing the policies and requirements necessary to assure safe and reliable operation of Ginna Station. He is also responsible for those items delineated in Section 6.0, Technical Specifications.

The Vice President, Ginna Nuclear Production is responsible to the Senior Vice President, Production and Engineering for directing'Ginna Nuclear Production activities and those support activities associated with Nuclear Engineering Services, Production Division Training, and Corporate Radiation Protection.

Revision 19 December, 1993

The Plant Manager, Ginna Station is responsible to the Vice President, Ginna Nuclear Production for the overall on-site safe operation of Ginna Station. He is responsible for: the performance of all Ginna Station'uality affecting activities in accordance with the requirements of the quality assurance program; providing qualified personnel to perform these activities in accordance with approved drawings, specifications, and procedures; those items delineated in Section 6.0, Technical Specifications; and assuring that significant conditions adverse to quality are identified and corrected.

The Superintendent; Support Services reports to the Plant Manager, Ginna Station and is primarily responsible for the performance of The Superintendent, Ginna Production, reports to the Plant Manager, Ginna Station, and is responsible for operations, health physi'cs and. chemistry, refueling, Lf'rrs,."lip'r'oLeptieng!::

results and tests, Ginna computer systems, man0 rj a8n

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a nghineex'g'age'an,:,!sary'a'i'<ilia'nceii'teat'ingle'h requirements o'"t "e qutalrtty 'assuran'ce. program The Plant Manager, Ginna Station and Superintendents, are assisted by other designated staff members, Figure 2-3; in the implementation of certain Quality Assurance Program requirements at the plant. These staff members are assigned responsibility for testing, procurement, storage of material and equipment, operation and test status control, calibration and control of measuring and test equipment, op'ei',:aPiixg~7exper'i'eniaaiaipsm'enba) maintenance of material handTing .equipment, and control of all activities involving operation, maintenance, repair, refueling and modification.

The Department Manager, Production Division Training is responsible to the Vice President, Ginna Nuclear Production for maintaining and implementing an ximrzev~s~Ssa."'"y ""wreais c..em., gsesex~~sc .qxyasaga, ,iaG+i~i

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Mraa"teiials Eangineering 'and Inspection Services, for providing trained and qualified welders, riggers and crane operators to support nuclear related activities.

Revision 19 December, 1993

The Department Manager, Nuclear Engineering Services is responsible to the Vice President, Ginna Nuclear Production for designing and constructing major modifications in accordance with applicable design bases, regulatory requirements, codes and standards and for nuclear fuel management. As requested by Ginna Station, he is responsible for reviewing unique maintenance and repair procedures for major equipment and providing technical support. He is also responsible for tracking and preparing corrective action report a udice CLaertilf&A tl:: ac~tictiiigX!~8,: Ckangf summaries .

The Division Manager, Technical Services and Chief Engineer is responsible to the Senior Vice President, Production and Engineering for directing activities in support of Ginna Station. These activities include long range planning for low level radwaste disposal strategies, personnel support for Ginna Station maintenance activities, records retention, document control, chemistry and environmental requirements support..

Production and Engineering Systems is responsible to the Division Manager, Technical Services and Chief Engineer for providing records management and document control support services for nuclear related activities.

The Department Manager, Quality Performance is responsible to the Senior Vice President, Production and Engineering for establishing the overall Quality Assurance Program. He is responsible for assuring that all planned and systematic actions necessary to provide adequate confidence that Ginna Station will operate safely and reliably are established and followed. He provides management with objective information concerning quality, independent of the individual or group directly responsible for performing the specific activity.

Revision 19 December, 1993

0 He has the authority and organizational freedom to assure all necessary quality activities are performed. In addition, he is responsible, for special processes and the inservice inspection program. He is responsible for maintaining a staff, Figure 2-2, for the conduct of staff training and.for directing its activities. The staff assists in the preparation and maintenance of .the Quality Assurance Manual and applicable corrective action report summaries.

The Manager, Quality Assurance reports to the Department Manager, Quality Performance. He and the Quality Assurance Staff are responsible for formulating corporate quality assurance policy and for assuring its implementation. This includes writing Quality Assurance policies, assuring that the program satisfies the requirements of.lOCFR50, Appendix B, and for maintaining the total program up to date. The Manager, Quality Assurance is also responsible for establishing and implementing a comprehensive audit and surveillance program, as well as reviewing administrative procedures of the organizations participating in the Quality Assurance Program. The staff is also, responsible for auditing and surveillance of aspects of the Quality Assurance Program. They are responsible for assuring that proper codes, standards, and quality requirements are specified in design, procurement and installation documents.,

They are responsible for assuring that the suppliers of safety-related material, equipment and services are properly qualified Q!'itig'iA't'i5+xygPi::::!3!9,':::itgBgFo'ggggfiliigke6:::guy@'3!jyiiand at these suppliers'acilities In addition, the staff assists the Manager, Quality Assurance, in the preparation of the audit schedule and audit status reports.

The Manager, Quality Assurance is a graduate engineer with at least six years of responsible experience, of which at least two years are in quality assurance and at least three years in the design or operation of nuclear power plants.

The Manager, Materials Engineering and Inspection Services is responsible to the Department Manager, Quality Performance for the development and qualification of procedures utilized for special processes.

Revision 19 December, 1993

He is responsible for providing functional guidance and direction for those methods.'e is responsible for establishing the Xnservice Xnspection Program and for coordinating changes thereto. He is also responsible for the routine maintenance of lifting and handling equipment and for the testing and evaluation of Ginna Station mater'is is I ~sH~e,:',::,:::s~!re8ponsa

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The Manager, Nuclear Assurance reports to the Department Manager, Quality Performance and is responsible for assuring that station activities affecting quality are prescribed and carried out in accordance with approved drawings, specifications, and procedures.gj4He is a member of the Plant Operations Review Committee and delegates the day to day quality assurance andPq'uaX!it@,,control planning and work monitoring responsibilities to his staff of Quality Control Engineers, Foreman and QC Xnspectors. The Quality Control Engineers are responsible for the review of design and installation documents and for the review of plant procedures which involve maintenance, repair, refueling, modification, and testing. Nuclear Assurance is responsible for assuring performance of verification inspection i activities and assuring that inspection requirements are included in approved procedures and work packages. This includes the receipt inspection of incoming materials, parts and components and the processing of nonconformance reports.

The Nuclear Assurance Quality Control Xnspectors also perform compliance oriented surveillance of nuclear ~elated activities.

The Department Manager and Purchasing Agent, Materials Management is responsible for the procurement of materials, services, and components, from qualified suppliers, in accordance with applicable commercial, technical, and quality requirements.

Revision 19 December, 1993

I He is also responsible for providing laboratory testing of some electrical equipment and devices'hhg:"

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Design is resposns'i.ble for"'providing a s'tsaffs", P'i.gure 2-4, to perf'orm relay engineering services. He is responsible for design, modification and construction activities at Station 13A and for supporting the Nuclear Engineering Services design and construction activities at Ginna.p::;-:NikTj'is><alppji ejsi'ons'abTpgfc'ig, FOTSDQD~$ <CO'.t.XQ~A's.':x

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Desi n Control Design activities are performed by Rochester Gas and Electric Corporation personnel or are subcontracted to organizations providing services to Rochester Gas and Electric.

Nuclear Engineering Services is responsible for the design and control of design activities (including design interfaces) for major modifications of structures, systems or components.

Augmenting this effort is the design and technical support provided by the ui ment which

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Revision 19 December, 1993

Ginna Station is responsible for the design and control of design activities for Minor modifications of structures, systems, or components. Ginna Station is also responsible for classifying station originated modifications as either Major or Minor. Nuclear Engineering Services reviews and concurs with modifications being classified as Minor. Minor modifications typically involve (1) component changes which involve vendor design. and are limited to the extent that the change does not impact existing performance requirements, (2) additions within Seismic Category I buildings which perform no safety functions and which neither interface with Seismic Category I or Class 1E items nor whose failure could reduce the functioning of any safety related component required for safe, shutdown of the plant to an unacceptable (3) changes to a safety related system determined not 'evel, to be major (e.g., vents, drains, alarms, indicating lights, etc.) .

Design control is implemented by means of procedures which include: design considerations, design review requirements; internal and external interface control considerations; design document review, approval, distribution,'ontrol, and revision requirements; and corrective action. Design considerations include, as appropriate: physics, stress, materials, thermal, hydraulic, radiation and accident analyses; appropriate design bases, codes, standards and regulations; acceptability for operation, maintenance and repair; acceptance and rejection criteria; and quality standards and other quality assurance requirements. Design verification utilizes. various methods such as formal design reviews, alternate calculations, or tests, as appropriate, to assure the adequacy of the design.

The design of plant modifications is verified by an engineer other than the one who performed the original design. For Major modification design, this may be done by Nuclear Engineering Services design engineers or consulting engineers as requested. For Minor modification station design, this may be done by Ginna Station, Nuclear Engineering Services design engineers'r consulting engineers, as appropriate.

Spare or replacement parts must at least meet the original equipment's technical and quality requirements. For plant modifications, standard, "off-the-shelf", commercial or previously approved materials, parts, and equipment are selected and reviewed for suitability of application by a design engineer.

Revision 19 December, 1993

Changes to a modification design are normally reviewed and approved in accordance with the same procedures as the original modification design. Supplemental procedures are established for the review and approval of field changes.

In general, design changes including field changes, are reviewed and approved by the organizations or individuals that performed, reviewed and approved the original design.

Where this is not practical, other responsible design organizations or individuals are designated, provided they have access to pertinent background information and are competent in the specific design area.

Design verification and field change systems are .methods utilized to detect, document and correct design process errors and deficiencies. In addition, the corrective action system, described in Section 16, is utilized to control and document corrective action to preclude recurrence of those design process errors and deficiencies which are 'considered

, to be a significant condition adverse to quality.

Quality Assurance is responsible for assuring that design control procedures, whether the work is done by Rochester Gas and Electric or by other organizations, are prepared and implemented and incorporate appropriate design control practices, checks, and reviews. Design, control procedures are reviewed to assure that an independent verification is performed.

Production and Engineering Systems, Nuclear Engineering Services and Ginna Station are responsible for establishing measures for the proper control of design documents and revisions Were~a.:44ex$ 5@, to assure. that distribution is to responsible individuals and in a timely manner to prevent inadvertent use of superseded design information. The measures. include the use of document revision levels, document transmittals, release stamps, field change request forms and distribution lists.

Design documents are collected, stored, and .maintained in accordance with Section 6 and 17, as appropriate. Design documents include design criteria, analyses, specifications, drawings, design review records, and changes thereto.

Revision 19 December, 1993

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Quality Performance, through preparation assistance and/or review, assure the proper inclusion of quality standards in

-the design of major and minor modifications. Quality Performance is also responsible for assuring that adequate test, examination and inspection. requirements are included in specifications. The Manager, Quality Assurance reviews and approves any deviations from quality standards when they occur.

Ginna x.rp Plant modifications are controlled by means of applicable Station, Nuclear Engineering Services,fi8i'Sillery

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safety analyses, and plant modification procedures. Plant modifications are reviewed by the Plant 'Operations. Review Committee and Nuclear Safety Audit and Review Board as required by Section 6.0, Technical Specifications.

Procurement Document Control Procurement document control applies to the control of-procurement documents for materials, parts, components,,and services required to perform quality affecting activities.

Such documents may be prepared by Rochester Gas and Electric or by a contractor and include purchase requisitions, purchase orders, service agreements, contracts.,

specifications, and drawings.

Procurement of materials, parts, components, and services is initiated by department staff personnel. Procurement procedures require that organizations preparing procurement documents consider and include, as appropriate, the items listed in Table 4-1.

Procurement documents, including those requesting spare or replacement parts, initiated at Ginna Station are reviewed by Quality Performance and approved by the designated Ginna Station supervision. Procurement documents initiated in Nuclear Engineering Services, Materials Engineering and Inspection Services, Gaa":::,,~h'kaid.:':';,:El'gcYi3'4':,"'Da'ptxxbutxori-.::.!P'iy ipibn3(pand Qual ity Performance and approved by designated departmental supervision.

Revision 19 December, 1993

Evidence of review and approval of procurement documents is recorded on the documents and identifies to Purchasing a procurement method which will ensure that the selected supplier is capable of providing the item or service in accordance with the requirements of the procurement documents. Considerations used in selecting a supplier and for determining the corresponding procurement method are described in Section 7.

After purchase requisitions, service agreements, contracts, specifications, and drawings have received the required reviews and approvals, a purchase order is issued by Purchasing to the selected supplier and controlled as described in Section 7."'hese documents are maintained by Purchasing, by the originating department, and/or by the.

receiving locations, as appropriate, until procurement is completed.

Under no circumstances are purchasing requirements altered (except for quantity. or pricing) during order placement unless review and concurrence is obtained from those who were required to review, concur with, and approve the original documents as described above. Changes or rev'isions to procurement documents are subject to the same review and approval requirements as the original documents.

Originating department technical review of procurement documents includes verification of applicable regulatory,.

code and design requirements. Quality Performance review of the above includes checks to verify proper inclusion of the quality standards, quality assurance p~~gram requirements, method of procurement and the applicable acceptance criteria. Ginna Station reviews procurement documents for spare or replacement parts to determine similarity, compatibility, and acceptance criteria of the original design. Quality Performance also reviews procurement documents for spare or replacement parts for adequacy of the quality requirements.

Revision 19 December, 1993

instructions Procedures and Drawin s Each Rochester Gas and Electric company organization, involved in quality related activities, is responsible for developing, reviewing, approving, and implementing procedures as required to implement the Quality Assurance Program. These procedures cover activities such as document control, training of personnel, and responsibilities and duties of personnel. Quality Performance reviews these procedures for inclusion of quality assurance program requirements. Table 1-1 prov&des a summary of the subject matter contained in the procedures which are used to implement the quality assurance program. Procurement documents require suppliers and contractors to have appropriate instructions, procedures, specifications, and drawings.

Ginna Station is responsible for providing and implementing instructions and procedures associated with operation, maintenance, repair, in-service inspection, refueling, procurement, modif ication and testing. This'ncludes instructions and procedures listed in USAEC Regulatory Guide 1.33 for administrative control; general plant operation; startup, operation, and shutdown of safety related systems; correction of abnormal, of f normal, or alarm conditions; response to emergencies and other significant events; radioactivity control; control of measuring and test equipment; chemical and radiochemical control; and fuel handling and refueling. Ginna Station is responsible for appropriate changes to such documents upon receipt of regulatory directives, instructions from Rochester Gas and Electric management, or the completion of plant modifications. Ginna Station is also responsible. for the preparation and issuance of those minor modification design documents not provided by Nuclear Engineering Services or the equipment supplier.

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also assists in the preparation of routine relay mai,ntenance and testing procedures used by their personnel in the annual Ginna Station protective relay surveillance program.

Revision 19 December, 1993

0 Nuclear Engineering Services is responsible ' for. providing approved specifications and drawings -'.lpga major modifications and for minor modifications when <aiam 4g4$ $ j~. -These documents require those performing the work'"Fo obtain, understand, and comply with appropriate procedures, specifications and drawings. Engineering has established procedures for revising drawings and specifications. These procedures cover updating of as-built drawings after plant modifications and the revision, approval, distribution, and control of all drawings and specifications.

Quality, Performance is responsible for: preparing and implementing inspection procedures utilized for detailed inspection activities for Ginna Station; providing and implementing procedures for audit and surveillance related activities; providing and implementing instructions and procedures associated with special processes, routine maintenance and inspection of cranes and handling equipment as well as materials testing and inservice inspection.

Persons preparing, reviewing and approving documents are responsible for assuring that specifications, instructions, procedures, and drawings include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished and assuring that the documents are kept current.

Indoctrination and training of personnel is provided by the responsible organizations to ensure that quality affecting activities are conducted in accordance with established documents. In addition, Quality Performance department assessment as described in Section 10 and Section 18 are used to verify that commitments are being addressed and affecting activities are being performed in 'uality accordance with approved instructions, procedures and drawings.

Document Control Procedures are established to control the'ssuance of procedures, instructions, drawings, and specifications.

Revision 19 December, 1993

Standard document control requirements are contained in the Quality Assurance Manual. The Plant Manager, Ginna Station is responsible for the control of all documents issued by Ginna Station ersonnel.

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Production and Engineering Systems controls the distribution of controlled manuals issued for the other organizations performing activities which implement this Quality Assurance Program (Table 1-1) . Each organization controlling documents has a separate procedure to control documents in accordance with the requirements of the Quality Assurance Manual.

The Quality Assurance Manual designates responsibilities and defines requirements for the preparation, review and approval of documents. Each department responsible for an activity is responsible for providing the necessary review and approval of instructions, procedures or drawings to assure that they are adequate, and include appropriate qualitative and quantitative requirements. Nuclear Assurance Quality Control representatives, who are assigned to support departmental maintenance, repair, refueling and modification activities, are responsible for reviewing, prior to use, governing procedures to assure quality assurance requirements are included. The Plant Operations Review Committee has the responsibility for 'reviewing Ginna Station procedures prior to their approval as required by Section 6.0, Technical .Specifications. Detailed inspection, test and examination procedures used by qualified personnel require the review and concurrence of the responsible technical person associated with that activity. Ginna Station, Nuclear Engineering Services, Material Engineering and Xnspection Services, Purchasing, Production Division

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" ""'" """assurance""'i.mp "emen ing procedures (Table 1-1) require the review of Quality Performance and the approval of the appropriate department supervisor.

Quality Assurance/Quality Control procedures are approved by the Department Manager, Quality Performance or designee.

Revision 19 December,, 1993

The Quality Assurance Manual requires that documents be controlled as appropriate, considering the type of document involved, its importance to safety, and the intended use of the document. It identifies the difference between controlled and.uncontrolled copies of the same document; includes the method for. identifying holders of controlled copies; requires that only controlled copies of a document be used for official purposes; requires that lists of effective revisions be issued periodically; requires lists of document holders to be maintained by the distributors; and requires that distributors transmit controlled documents using approved forms internally and externally.

Types of documents which are controlled include Technical Specifications, UFSAR, Quality Assurance Manual, procedures (such as engineering, purchasing, repair, maintenance, test, calibration, fuel handling, modification, and

, administrative)., specifications and drawings. Suppliers of materials, equipment, and services under an approved 10CFRSO

. Appendix B supplier 'quality assurance program are required in procurement documents to provide for control of documents, including -manufacturing, inspection and testing instructions.

The Quality Assurance Manual further requires that each organization provide in its procedures for measures: to assure that documents are available when required; to properly review and approve documents such as procedures, instructions, specifications and drawings to provide the same reviews and approvals for changes to documents as was required of the original document; to require that organiza-tions which review and approve documents have access to pertinent information and adequate knowledge of the original document intent; to assure that approved changes are promptly transmitted for incorporation into documents; and to assure that obsolete or superseded documents are eliminated from the system and not used.

Quality Performance is responsible for review and concurrence of procurement documents for all procuring organizations and, therefore, procurement document control requirements.

Quality Performance is responsible for review and assessment of document control systems to assure adequate systems are implemented.

Revision 19 December, 1993

Control of Purchased Material E ui ment and Services Procurement documents, supplier selection, planning for item or service acceptance, control of supplier performance and acceptance of items and services are five major means used in controlling purchased material, equipment and services.

All procurement is conducted in accordance with procurement documents as stated in Section 4. All reviews, inspections, 1,'~

surveillances, and audits are conducted by personnel who are competent in establishing whether or not a supplier is capable of providing acceptable, quality products.

organizations!c'oTI's'i's%'i of determining the methods to be used for acceptance of the'tem or service and the requirements for control of the supplier performance. Source inspection (surveillance), certificate of conformance, receipt inspection and post installation test are '

methods which are considered for item acceptance ge'c8apg either or a combination of: (1) surveillance of the activity and (2) review of objective evidence for conformance to the p'rocurement document requirements (i.e.

certifications, stress reports etc;). The extent of the acceptance methods and associated verification activities will vary Bep'endtn9'!::::!up'od the relative importance and complexity of the pur~cTVased iHem or service and the supplier's past performance.

Consideration for the control of supplier performance includes the necessity for document submittals or surveillance, and under what situation the supplier is to report nonconformances.

Results of the planning are incorporated in the procurement documents.

Selection of a supplier is based on the evaluation of its capability to provide the item or services in accordance evaluation, which is accomplished during planning, determines the necessity for the supplier

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with the requirements of the procurement documents. The procurement selection to be mi8a from the approved suppliers list.

Revision 19 December, 1993

Purchasing utilizes the approved suppliers list as the selection source for those suppliers found to have a satisfactory quality assurance program. The evaluation guidelines for source selection considers the item complexity, method(s) of acceptance and for a replacement item,F-'-,;:viPggh'eg if- the source is to be restricted to the original supplier. For engineered and off-the-shelf items procured from suppliers required to have a quality assurance program, supplier selection is i'i'de"from the approved suppliers lists or one who is in" the process of being added to a list, after having its capability evaluated to purchaser satisfaction. Items or services, which meet industry standards and are typically utilized in applications other than nuclear, may be purchased from suppliers not listed on the approved suppliers list((

provided that item acceptance can be based on acceptance of

,standard commercial quality which is supplemented, as necessary, with source surveillance, pre- or post-installation tests, receipt tests, commercial supplier test reports, commercial supplier certificates, or receipt inspection. Items or services which have nuclear quality requirements whi'ch normally require the supplier to implement a quality assurance program but for which no such supplier can be practicably utilized may also be purchased from suppliers not listed on the approved suppliers listg provided that verification of nuclear quality can be accomplished by methods such as source surveillance, 'pre- or post-installation tests, receipt tests, supplier test reports, supplier certificates, or receipt inspection as approved by Quality Assurance. Departmental procedures establish guidelines for source selection evaluations and for documenting the results through indication of the corresponding procurement method. The purchase requisition will also identify the source when replacement parts. are to be procured from the original equipment supplier.

Addition of a supplier to the approved suppliers list is based on satisfactory evaluation of the supplier's I

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Revision 19 December, 1993

For engineered items, Nuclear Engineering Services ke o':.

Qiana.::St5gion!.-:,a'x'e responsible for evaluating the or manufacturing capability of the supplier including overall'esign his particular technical ability to produce the design, service, item, or component delineated .in the procurement documents. As part of this review, the supplier's design capabilities, machinery capabilities, handling capabilities, testing facilities, service capabilities, and experience are reviewed.

Quality Assurance is responsible for evaluating the supplier's overall quality assurance organization and program in accordance with applicable codes, standards, applicable parts of .10CFR50 Appendix B, and Rochester Gas and Electric Corporation requirements. The review includes consideration of: company organization, quality assurance personnel qualifications, review and control of design documents, manufacturing procedures, quality assurance calibration practices, acceptance criteria, .'rocedures, required quality assurance records and their retention, and quality assurance requirements and controls imposed by the supplier on his subcontractors. Supplier evaluation is conducted by means of procedures or checklists which identify applicable regulatory or code quality assurance requirements.

Ginna Station, Quality Performance and~GY8'".':;@ridj)gp!ic'CWg~~p evaluate the suppliers of inspection, test, and calibration services which they intend to use.

The departments responsible for performing supplier evaluations shall document their results, in reports which discuss areas investigated, findings, and conclusions.

Revision 19 December, 1993

These measures typically include the processing of change information, surveillance of supplier activities and the control of documents exchanged with the supplier. In addition, each department procuring off-the-shelf items or services establishes similar measures for the control of supplier performance. ,With the exception of processing change information, the need for and applicable extent of purchaser controls of the supplier are determined during procurement planning.

Quality Assurance is responsible for determining and documenting the degree of supplier surveillance (including review, inspection,. or audit) required during design; fabrication, inspection, testing, and shipping, and for providing the required surveillance. The objective of supplier surveillance is to provide a sampling review of the supplier's quality assurance program implementation and of product conformance with respect to the purchase order requirements. For complex engineered items, Quality

-

Assurance and Nuclear Engineering Services-are responsible for joint development of surveillance plans in advance of surveillance trips to identify areas to be reviewed.

The results of the surveillance trip are documented by means of inspection sheets or trip reports which are distributed to the Manager, Quality Assurance, and the department which initiated the procurement. When a deviation from purchase order requirements is noted, the Quality Assurance representative has the authority to inform the vendor that a particular item is unacceptable, to issue a nonconformance report , or to stop work, if necessary.

Quality- Performance is responsible for surveillance of Ginna Station site contractors to assure that they meet all technical and quality requirements. The reporting and documenting of contractor surveillance is managed in a manner similar to supplier surveillance.

The verification methods for the acceptance of items and services are specified on the attached procurement control form during procurement planning and the purchase requisition preparation.

Revision 19 December, 1993

Department supervision is responsible for receiving and storing items pending their acceptance., Upon receipt, the department stockkeeper logs the item, places a "hold" tag on the item, and notifies Quality Performance that the item has arrived.

Quality Performance is responsible for receipt inspection at Ginna Station upon delivery of items and associated services for maintenance, repair, modification, and refueling. This inspection includes the use of written procedures or checklists to verify that the items and services conform to the procurement documents (if this has not been performed by source inspections) and that documentary evidence of conformance is available at the plant prior to installation or use. Documentary evidence sufficient to identify the codes, standards or specifications met by the purchased material, equipment, and services is retained. In the event a final source inspection for the acceptance is conducted prior to receipt by RGGE, Quality Performance performs an inspection for shipping damage or lost parts and a document check to assure that the required documentation has been reviewed and is complete. A receiving inspection checklist is completed for all items received to document the extent of the inspection performed, including the documents checked, and the inspection results.

If the item and documentation are adequate, Quality Performance labels the item as "Accepted", files the documentation and receipt inspection results, and.releases the item for storage or use. If the item is nonconforming or the documentation is unsatisfactory, Quality Performance initiates controls on the item in accordance with Section ls.

All items issued must bear an acceptance tag or label and have documentation to support the acceptability of the item.

In the event the traceability is lost or the documentation review is unsatisfactory, the item becomes nonconforming and may not be released for use.

Identification and Control of Materials Parts and Com onents The identification and control of materials, parts, and components is accomplished in accordance with written requirements and applies to material, parts, or components in any stage of fabrication, storage, or installation.

Revision 19 December, 1993

Identification and control requirements are established by either an existing procedure or requirements documents which are prepared during the planning stages of a project. The identification and control requirements cover items such as:

traceability to associated documents such as drawings, specifications, purchase orders, manufacturing test data and inspection documents, and physical and chemical mill test reports; specification of the degree of identification to preclude a degradation of the item's functional capability or quality; and the proper identification of materials, parts, and components prior to release for manufacturing, shipping, construction, and installation.

Nuclear Engineering Services@~8iiii'ai84%b'i'>and Quality Performance are responsible for assuring that drawings and specifications contain appropriate requirements for the identification and control of materials, parts, or components, as appropriate. Suppliers are required to assure that all required documentation for an item is properly identified and related to the item. Each item is required to be physically identified, either by marking on the item or by tags. Physical identification by purchase order number is used to the maximum extent. possible for relating an item at any time to applicable documentation.

Identification is either on the item or records traceable to the item. Where physical identification is impractical, physical separation, procedural control, or other appropriate means are employed.

The Plant Manager, Ginna Station is responsible for maintaining identification and control of materials, parts, or components received, stored, installed, and used at the plant in accordance with approved procedures.FS The responsible supervision of other departments which receive material:;44'y8 which is to be stored away from the. plant are.

responsibl'e "for establishing procedures for identification and control and for maintaining identification and control of material, parts,'r components, stored or used in their area of responsibility.

In the event that traceability is lost for a specific item, it is handled as nonconforming material and deviations and waivers are controlled and documented in accordance with Section 15.

Revision 19 December, 1993

Control of S ecial Processes Written procedures are established to control special processes, such as welding, heat treating, and nondestructive examination to assure compliance with applicable codes, standards, and design specifications.

Qualification of personnel and special process procedures eemykkee Fo'mply',,::".":with the requirements of applicable codes and standaids.'Shen special process qualification requirements are not included in existing codes and standards, they are described in procedures which give details of the special process, the p'ersonnel qualification requirements, the equipment necessary, and the special process qualification requirements.

Initiators of procurement activities are responsible for requiring suppliers, in procurement documents, to control special processes in accordance with the above requirements.

Quality Performance personnel're responsible for reviewing procurement documents to ensure that requirements for control of special processes are included.

Rochester Gas and Electric procedures for special processes are prepared, reviewed, and approved by Materials Engineering and Inspection Services. Special process procedures submitted by suppliers and contractors are reviewed and concurred with by Materials Engineering and Inspection Services.

The Manager, Nuclear Assurance and Ginna Station Maintenance Managers are responsible for assuring that personnel performing special processes under their cognizance are qualified and are using qualified procedures in accordance with applicable codes, specifications, and standards.

Within the Quality Performance Department, the Manager, Materials Engineering and Inspection Services is responsible for the qualification of NDE personnel and procedures. The Manager, Materials Engineering and Inspection Services is responsible for the qualification of welding procedures ca@

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procedures to dern'onstrate that required qualifications have been obtained and kept current are maintained by Production and Engineering Systems.

Revision 19 December, 1993

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Quality Performance performs surveillance, inspections, and audits of special processes performed by Rochester Gas and Electric or contractors to assure effective compliance with procedures.

Ins ection Procedures prepared for the control of activities include inspection requirements and hold points as required by drawings, instructions, requirements documents, specifications, codes, standards, or regulatory requirements. For clarification and to distinguish from preventive maintenance inspections, the following controls are associated with the quality assurance function inspections and referred to as verification inspections.

Instructions for conducting detailed verification inspections are contained in inspection procedures. These inspection procedures and all supporting specifications and

.drawings are provided to-inspection personnel for-use prior to performing the inspection. Inspections and hold points are. utilized to verify conformance of materials, parts, appurtenances, components, processes or structures to predetermined quality requirements. Inspection'procedures include the identification of quality characteristics to be inspected, a description of the method of inspection to be used, the identification of the group responsible for performing the inspection, the acceptance and rejection criteria, the requirements for the recording of inspection results, and the requirements for providing evidence of completion and certification of the inspection activity.

Verification inspections are performed by qualified inspection personnel who are independent of the personnel performing the work. Outside contractors are required by procurement documents to have and follow similar procedures and to use independent inspectors. Inspectors are sufficiently trained to adequately evaluate the activity they are inspecting.

Quality Performance personnel are responsible for assuring performance of verification inspections, as required, during plant operation, maintenance, repair, in-service inspection, refueling, modification, and testing when the work is performed by Rochester Gas and 'Electric personnel. The adequacy of inspections not directly performed by Quality Performance personnel will be assessed on a sample basis through the QA/QC surveillance program. Inspection equipment is calibrated and controlled in accordance with Section l2. Calibration status is verified by inspection Revision 19 December, 1993

personnel prior to performing an inspection operation.

In the event an inspection of processed material or products is impossible or impractical, indirect control by monitoring processing methods, equipment, and personnel is provided.

Both inspection and process monitoring are required when control is inadequate without both.

Quality Performance is responsible for verifying adequate inclusion of inspection requirements in specifications. I The Manager, Nuclear Assurance is responsible for assuring that adequate inspection requirements and hold points are included in maintenance, repair, refueling, modification and testing instructions and procedures and related fabrication processes. He is also responsible for the assignment of qualified personnel required for the performance of verification inspections and quality control surveillances of quality affecting activities.

With the exception of that which pertains to Pump and Valve Testing, the Manager, Materials Engineering and Inspection Services is responsible'for establishing the requirements for the Inservice Inspection Program. Nuclear is responsible for establishing the requirements Engineering'ervices for the Inservice Pump and Valve Testing Program. The program for inservice inspection of the reactor coolant i system and other safety related systems is contained in Section 4.2, Technical Specifications.

11. Test Control Checks or testing performed to verify the adequacy of corrective or preventive maintenance shall be performed to approved instructions, procedures, or drawings. Whenever testing is required to demonstrate that a material, pa'rt, component, or system will perform satisfactorily in service,'

test program is instituted employing written and ap'proved procedures which are in accordance with basic requirements established in Technical Specifications, drawings, instructions, procurement documents, specifications, codes, standards, and regulatory requirements. The test program requires the identification, control, and documentation of all tests, and the preparation of written procedures required for satisfactory accomplishment of the testing.

Together the written procedures and checklists for the testing program include: necessary test equipment'and calibration requirements; material requirements; test Revision 19 December, 1993

personnel requirements; prerequisite plant and equipment conditions;-limiting conditions; detailed performance instructions for the testing method and test equipment instrumentation; acceptance and rejection criteria; instructions for disposition of deviations; data collection requirements; and test result approvals The Plant Manager, Ginna Station is responsible for the

.station test program, which includes the surveillance test program required by Section 4.0, Technical Specifications

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ÃRvVN'est procedures are prepared by the plant staff, reviewed by the Plant Operations Review Committee and Quality Performance, and approved by the Plant Manager, Ginna Station. The Plant Manager, Ginna Station is responsible for the correct and timely performance of the required tests

.utilizing written and approved procedures.. When contractors are employed for tests, the contractor is required to perform testing in accordance with Re gh8)PjpP'pV5V88 quality assurance program requirements. "'A'll test results are required to be documented, reviewed, and approved by those responsible for performing the test..

When requested by Ginna Station,

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test activities'" "o 'e erm'i'ne'" cause" o"'io" e'c'""ive re ay malfunctions. These test activities are performed in accordance with approved procedures by qualified personnel.

Nuclear Engineering Seivices and Quality Performance are responsible for assuring that required tests for major modifications are included in specifications. Nuclear Engineering Services and I'.:",'.Ga%~ an/~@,":Zl:iat'xiePDji;0'x.xbetjonY":,',Di'mi.a.:ion assistance in the preparatio'n'"of'modification-related test procedures may be provided'to the Ginna Station staff. The Ginna Station Technical Manager is responsible for the adequate inclusion of test requirements in minor modification design documents and for reviewing modification-related test results for acceptability to design requirements. Reviews of minor modification design by Quality Performance verifies adequate inclusion of test requirements.

Revision 19 December, 1993

~

Control of Measurin and Test E ui ment The calibration and control system for measuring and test equipment includes calibration procedures, establishment of calibration frequencies, and maintenance and control requirements of measuring and test instruments, tools, gauges, shop standards, and nondestructive test equipment which are to be used in the measurement, inspection, and monitoring of components, systems, and structures.

Calibration procedures include step-by-step methods for calibration and requirements for instrument accuracy.

Calibration frequency is based on required accuracy, degree of usage, stability characteristics, manufacturer's recommendations, experience, and other conditions affecting measurement capability.

Control of measuring and test equipment requires: a recall system assuring timely calibration of equipment; a system providing unique identification of equipment, traceability

'to calibration test data, and identification of the next calibration date on the equipment; a system providing traceability.of shop standards to nationally recognized standards (where national standards do not exist, procedures conta'in instructions to document the basis. for calibration) and periodic revalidation of shop standards; a system providing for records to be maintained which indicate the complete status of 'all items under the calibration system including the maintenance, calibration results, abnormalities, and last and future calibration dates; and a system controlling the purchase requirements of new equip-ment to be entered into the calibration and control system including requirements for accuracy, stability, and repeatability under normal use conditions. In the event a measuring instrument (i.e. shop or field standard) is found out of calibration, an investigation is conducted to determine the validity of previous measurements.

The Plant Manager, Ginna Station is responsible for the procedures and program required to assure control and calibration of measuring and test equipment at Ginna Station in accordance with the above requirements. Instruments specified in Section 4.l, Technical Specifications, are included in the program. Tools, gauges, and instruments necessary for maintenance, inspection, and test are calibrated and controlled in accordance with station procedures. Measuring, -test or inspection equipment used by Nuclear Assurance. Quality Control is included in the program.

Revision 19 December, 1993

The Manager, Materials Engineering and Inspection Services pap',"O'Ci045@eiparwe responsible the" preparation of procedures for the control and f'r establishing" a program and calibration of measuring and test equipment used by their respective organizations.

13. Handlin Stora e and Shi in Ginna Station Supervision is responsible for developing and implementing procedures for the handling, storage, shipping, preservation, and cleaning of material and equipment delivered to or located at Ginna Station.F':.',-:";:,'4Qg$ Bd:;.;$ 3'@CQXiC sAn" '

Services are responsible for preparing and implementing procedures for the handling, storage, shipping, preservation, and cleaning of material and equipment delivered to or located in their work areas. In addition, the Manager, Materials Engineering and Inspection Services is responsible for preparing and implementing procedures for the routine maintenance and inspection of lifting and handling equipment. Under normal circumstances, manufacturer's specific written instructions and recommendations and purchase specification requirements are invoked for cleanliness, preservation, special handling, and storage with respect to environmental requirements. In the absence of, or in addition to, specific manufacturer requirements, the management may invoke additional requirements in accordance with department procedures.

The Department Manager, Nuclear 'Engineering Services p2 Pj3;:8A'+t:"';::885'Age'X~>'":.;.:,,:,bi@$i':.')8t",,@t4e@~i@wi responsible for speci fying in procurement 8ocuments ance in engineering specifications that written procedures be used, as appropriate, for the handling, shipping, storage, cleaning, and preservation of materials and equipment procured for major modifications.

These procedures are prepared by contractors, by the station staff; or by staff members of pes'i ap'cl,:,,:MB'acigkiiciPDiSBYibi~Ea'on,.'ipxya;:s'i:on as appropriate. Rocbeste r Cars and Electric proce urea are reviewed and approved as described in Section 6.

Revision 19 December, 1993

In the preparation of procurement documents, department procedures, and contractor procedures, consideration of handling, shipping, storage, cleanliness, and preservation is given to all material and equipment throughout various stages of manufacturing and installation prior to operational acceptance.

Quality Performance, Gin%a!,';,SEa'@ion and Nuclear Engineering Services are responsible for review of engineering specifications to assure that proper handling, storing, and shipping requirements have been specified. Quality Performance is responsible for assessment of handling, storage, and shipping activities by suppliers, Rochester Gas and Electric personnel, and contractors.

Ins ection Test and 0 eratin Status Equipment or systems not ready for normal service are clearly identified by use of tags; control logs, and other suitable means to indicate the status in a positive manner.

The identification is sufficient to positively indicate. the status of the particular equipment-or system being isolated. ~

The Plant Manager, Ginna Station is responsible for indicating the status of operating equipment or systems to be- removed from service for maintenance, repair, or modification in accordance with the. approved Electric System Operating Rules. The Plant. Manager designates personnel who have station holding authority.

Personnel who have station holding authority are responsible for directing the status change of equipment and systems in accordance with the approved station holding procedures.

System status is indicated through the use of hold tags, block tags and corresponding control logs.

Equipment or system inspection and test status are indicated by use of test tags, labels, or work inspection and test status sheets. Written procedures control the use of hold tags, test tags, and labels.

Systems, components, and equipment which are found to be unacceptable during or after testing are clearly identified.

Fuel handling operations involving fuel assemblies or other radioactive sources are identified and controlled by the use of tags, stamps, or other suitable means.

Revision 19 December,, 1993

Maintenance, repair, or modification of components, systems, or structures, utilizes procedures, travelers, data sheets, instructions or checklists to indicate status of the work, inspections or tests and corresponding acceptance or rejection for a particular component, system, or structure.

These job control forms are prepared by the job supervisor and reviewed by Nuclear Assurance Quality Control personnel and maintained at a des'.gnated control location to indicate the status and the completion of required inspections and tests.

Quality Performance monitors the status change of Ginna Station activities for their implementation of approved procedures and assures that inspection results are properly documented.. Material Engineering and Inspection Services establishes the procedures for implementing the inspection status sheets utilized during inservice inspection.

Nonconformin Materials Parts and Com onents Procedures are established for the control, evaluation and disposition of deficient material, parts, and components.,

Materials, parts, or components which do not conform to the drawing or specification requirements are identified, controlled and reported. RG6E personnel are responsible for initiating nonconformance reports and initiating dispositions'uclear Assurance Quality Control personnel are responsible for inspecting and approving closeout of nonconformance'reports. Prior to installation or use, nonconforming items generally remain in a hold area until an approved disposition has been implemented. Nonconforming items may be released for installation to meet critical fabrication schedules provided controls are established to prevent inadvertent use prior to implementing the nonconformance disposition. After installation,.

nonconforming items are identified and controlled until approved disposition has been implemented.

Nonconformances identified at a supplier's facility and reported to RG&E, which have'upplier recommended dispositions of use-as-is, or repair, are normally processed by the department originating the procurement.

Organizations which specify the requirement being dispositioned are responsible for reviewing and approving the supplier recommended disposition.

Items are repaired and reworked in accordance with approved procedures and current drawings. The repair or rework must Revision 19 December, 1993

be verified as acceptable. by an inspection of the affected item or process which is at least equal to the original inspection method.

Items which are accepted "use-as-is" are fully documented with the drawing or specification requirement and technical justification for acceptance. All such items are approved prior to use by the cognizant organization having responsibility for the requirement. In addition, those "use-as-is" nonconformances which also deviate from a Design Criteria requirement shall require additional approval of the Senior Vice President, Production and Engineering.

Nuclear Assurance Quality Control personnel provide nonconformance status information periodically. Quality Performance and other organizations analyze nonconformance report data for adverse trends and geeeeee @gpssj5g periodic reports to management. Adverse trends form' basis for supplier re-evaluation or for other corrective action.

Corrective Action Conditions adverse to quality are those conditions which compromise confidence that a structure, system or component at Ginna Station will perform satisfactorily in service.,

Significant conditions adverse to quality are those conditions which, if uncorrected, could affect the health and safety of the public, seriously affect the ability to serious breakdown in activity controls, or will require a major effort to restore capability to perform specified functions.

'Conditions adverse to quality shall be promptly identified and reported to supervision. The condition adverse to quality shall be identified, corrected and evaluated to determine if a significant condition adverse to quality exists.

When a significant condition adverse to quality at Ginna Station is identified, the Corrective Action Coordinator is responsible for evaluating the effect of continuing the activity. If continuing the activity would obscure or preclude identification and correction of the deficiency, continuing the activity would increase the extent of the deficiency or lead to an unsafe condition, stop work action is taken.

Revision 19 December, 1993

%~48.';:-',; Wan'asg8x'.",!!Sip o'l!8<<tK hssuranc'es has authority to stop work: on mai.ntenance, repair, i'nservice inspection, refueling, modify'.cation,,testing or inspection deficiencies at Ginna Station, as well as other locations.

Quality Performance may recommend stop work action to the Plant Manager, Ginna Station on operating deficiencies.

The Manager, Quality Assurance has the authority to stop work for conditions identified in Purchasing, Nuclear Engineering Services, Materials Engineering and Inspection Services, ."',':.6.'8'8)<p6.:

B3:,e~atVi~e':,'!Di~a,:ri~biti:ae!,:Sgv'iii.""oD or cognizant supplier'"

ions. ""'ssocia For significant conditions adverse to quality,gjVgeet'i':::,R'96'8

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'o"x88@+v& - tee If the significant condition adverse to quality involves a design deficiency or the recommended corrective action involves a design change, the review of the condition adverse to quality includes Nuclear Engineering Services. or Ginna Station design personnel, as appropriate.

The Corrective Action Coordinator assures root cause determination and corrective action plans are developed to resolve the identified concern and to preclude recurrence.

s'ugix'hei'op reviews eked eac8 Corrective "Action 'Report'""

initi~ated at Ginna Station and may recommend additional corrective action result in adequate if the action already taken does not resolution.

The Plant Operations Review Committee CAR Subcommittee reviews all corrective action reports to assure that the cause of the condition has been determined and that corrective action has been taken to preclude repetition.

Revision 19 December, 1993

Corrective action summary reports are submitted to departmental supervision to keep them aware of significant conditions adverse to quality, related causes and corrective action being taken. Senior Management is advised of the

. causes and actions of the more significant Corrective Action Reports.

Quality Assurance provides additional assurance of the corrective action program effectiveness through semi-annual audits and periodic surveillances.

ualit Assurance Records Quality Assurance is responsible for establishing the basic requirements for quality assurance record retention and maintenance. Production and Engineering Systems, as directed by the Division Manager, Technical Services and Chief Engineer, is responsible for the retention and maintenance of records. Quality Performance, Purchasing, Nuclear Engineering Services,

't and Ga Illan'd':;:!gee'ctrl!OEDi'81'xi'Qllt@otl';':;D'r'v+8!3~on departments are responsible t iotorw a rda'rng hect" re8cords they initiate to the appropriate Production and Engineering Systems record retention locations'ach organization generating records is responsible for preparation, review, approval, and implementation of specific quality assurance record procedures for their areas of responsibility in accordance with these requirements. The records which fall within quality assurance record requirements include those records, required by Section 6.10 of the Technical Specifications and the Quality Assurance Program. All records associated with the operation, maintenance, repair, inservice inspection, refueling, modification, inspection and testing of structures, systems, and components covered by the quality assurance program are included.

Records initiated at Ginna Station include operating logs; the results of inspections, tests, and the monitoring of plant activities; drawings, procurement documents and material analyses; calibration procedures and reports; and Nonconformance and Corrective Action Reports. Records of the qualification of personnel, procedures, and equipment for special processes and the results of reviews are maintained at the appropriate Production and Engineering Systems record retention location.

Revision 19 December, 1993

Inspection and test records contain a description of the type of test or inspection activity, evidence of completion of the activity, results,, the name of the inspector or data recorder, the acceptance or rejection of the activity, and a record of any nonconformances.

The requirements and responsibilities for record accessibility and transmittal are described in the Quality Assurance Manual sections as appropriate. Requirements and responsibilities for preparation, inspection, identification, review, storage, retrieval, maintenance, and the retention of quality assurance records are in accordance with applicable quality assurance record procedures, codes, standards, and procurement documents. Records are available to authorized personnel.

Removal of records from storage is documented and accountability. is maintained by the responsible record control activity.

Records are either stored in record storage facilities which are designed to prevent destruction of records due to fire, flooding, theft, and deterioration by temperature or humidity conditions; or, duplicate records are- kept in two separate storage locations in separate buildings which are physically isolated from each other.

Record keeping procedures provide for receiving, classifying, indexing, labeling, and preparing records for storage. The procedures establish retention requirements, accessibility, control of obsolete record destruction, and control for issuance and return of all records.

Production and Engineering Systems is responsible for maintaining plant operating records as required in Section 6.10, Technical Specifications.

Production and Engineering Systems is also responsible for maintaining off-site prepared design records, such as specifications, drawings, design review reports, and design control documentation; quality assurance records, such as audit 'reports and surveillance reports; purchasing records, such as supplier qualifications, bid evaluations, and purchase orders.

Revision 19 December, 1993

Audits Compliance with all aspects of the Quality Assurance Program and the effectiveness of the program is determined by audits and surveillances of all organizations performing quality affecting activities. Quality Assurance is responsible for conducting audits of those organizations and activities involved in the quality assurance program on a planned, periodic basis. Audit intervals are based on the status and safety importance of activities being performed, as well as group performance and related management concerns.

Table 18-1 is a list of the ((4~~te~:;-%X$'g activities to be on the level of activity in each area. Audit schedules are established to assure that each of the activities are i'i-:

audited at the frequency specified in Section 6 Technical Specifications. Additional audits or surveillances are conducted as required by special conditions, circumstances or to address management concerns.

Each audit requires the development of an audit plan to provide information about the audit, such as the functional areas to be audited, the names of those who will perform the audit, the scheduling arrangements, and the method of reporting findings and recommendations. Audit planning and performance utilize performance based techniques that will facilitate effectiveness assessments as well as compliance verification. The audits are performed in accordance with written procedures or checklists by appropriately, trained personnel not having direct responsibilities in the areas being audited..

Audit results are documented and reported to the supervisor and division head having responsibility in the area audited and the Nuclear Safety Audit and Review Board. Within a specified period of time, the .person having supervisory responsibility in the area audited is required to review the audit results, take necessary action to correct the deficiencies identified by the audit, and document and report the corrective action.

Quality Assurance is responsible for developing audit plans and audit checklists, designating an'd training audit personnel, and conducting audits.

Revision 19 December, 1993

S Audits may be conducted by Quality Assurance engineers or other qualified personnel, such as technical specialists from other company departments and outside consultants.

Audits of major contractors, subcontractors, and suppliers are conducted during the early stages of design and procurement, as required, to evaluate their quality assurance program for compliance with all aspects of the procurement documents. Audits are conducted, as required, to assure that major contractors, subcontractors, and suppliers are auditing their suppliers'uality assurance programs in accordance with procurement documents. During the project or procurement process additional audits are performed, as required, to assure all quality assurance program requirements are properly implemented in accordance with procurement documents.

Quality Performance performs regular analyses of audit and Quality Assurance surveillance results to evaluate quality trends. Results of these analyses are provided to management for their regular review.

Revision 19 December, 1993

Table 1-1 Quality Assurance Program Procedures Subject Listing Appendix B ualit Assurance ualit Control Procedures Criteria Indoctrination of Quality Assurance/Quality Control and Supervisory Personnel Training of Quality Assurance/Quality Control Personnel Management Review of the Quality Assurance Program Periodic Review of Quality Assurance/Quality Control Procedures Planning and Reporting Results for QA/QC Subcommittee Meetings Quality Assurance/Quality Control Group Organization IX and Responsibilities Quality Assurance Review of Rochester Gas and Electric Design Criteria Quality Assurance Review and Approval of 'Field Change Requests and Review of ECN's

~

Quality Assurance Review of Rochester Gas and Electric Engineering Specifications

~

Preparation, Review and Approval of Quality Verification III Specifications Computer Software Product Evaluation IIX Quality Assurance, Review of Computer Software Production Evaluations Master Software Index Requisitioning Quality Assurance/Quality Control IV Services 5 Quality Review of Rochester Gas and IV Electric Procurement Documents Preparation, Review and Approval of Rochester Gas and Electric Q.A. Specifications Revision 19 December, 1993

Cl Table 1-1 (cont'd)

Appendix B ualit Assurance ualit Control Procedures Criteria Preparation, Review and Approval of Ginna Station Quality Assurance Manual Preparation, Review and Approval of Quality Assurance/Quality Control Procedures Preparation, Review and Approval of the Quality Control group Verification Inspection Program Procedures Revision and Control of the QA Program for Station Operation Review of Departmental Procedures VI Preparation, Review and Approval of Procedure VI Deviation Requests by Quality Assurance/Quality Control Evaluation of Suppliers by Quality Assurance VII Supplier Surveillance VII Control of Supplier Performance VII Quality Assurance Evaluation of Bids VII Conducting Commercial Grade Supplier Surveys VII Evaluation of Commercial Suppliers by Quality VII Assurance Document Deficiency Reports VII Verification Inspection Program Revision 19 December, 1993

Qualification of Inspection Personnel Quality Assurance Nonconformance Processing XV Corrective Action Reports XVI Quality Assurance Commitments and Action Items XVI Review of Ginna Maintenance Work Order Packages XVI Identified Deficiency Reports XVI Records Turnover Plan XVII Qualification of Audit/Survey Personnel XVIII Audit Scheduling and Planning XVIII Performance of Quality Assurance Audits XVIII Reporting and Follow-Up of Audit Findings XVIII Conduct of Quality Assurance During and in XVIII Follow-Up of NSARB Audits Response to Audits and Surveillance XVIII Qualifications of Surveillance Personnel XVIII Review of Audit Program XVII Auditing of the Nuclear Emergency Response Plan XVII Performance Based Surveillance Program XVIII Availability and Use of INPO and NRC Inspection/ XVIII Assessment Reports in Audit and QA Surveillance Quality Assurance Planning Guides XV1II Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Materials En ineerin Ins ection Services Criteria Indoctrination and Training Materials Engineering and Inspection Services Organization and Responsibilities Preparation, Review and Approval of Purchase Requisitions and Related Procurement Documents Quality Materials Engineering and Inspection Services Procedures Quality Materials Engineering and Inspection Services Procedure Deviation Request Preparation, Review and Approval of Material

.Handling Equipment Instructions Preparation, Review and Approval of Materials Engineering Laboratory Test Procedures Control and Distribution of Documents Regulating VI Safety Related Activities Control of Purchased Materials VII Preparation, Review and Approval of Supplier VII Evaluation Control of Purchased Services VII Welding Procedure Preparation Review and Approval IX Welding Procedure Qualification IX Heat Treating Procedures IX Welder Qualification and Currency IX Nondestructive Examination Procedures IX Nondestructive Examination Procedures Manual IX Nondestructive Examination Personnel Qualification Revision 19 December, 1993

Cl 0

Table 1-1 (cont'd)

Appendix B Materials En ineerin Ins ection Services Criteria Qualification of Visual Examination Personnel IX Erosion/Corrosion Program IX General Brazing Procedures Preparation and Approval IX General Brazing Procedures Qualification IX Inservice Inspection Program and Plans ASME Section XI Repair, Replacement and Modification Procedure Incorporating Ginna Modifications into Inservice Inspection Program Duties of the ANII Tests conducted by MEIS Laboratories XI Rm Pm~swq~cgqcPyggx w+<'~vg. ~++>Pyb~~ex egmyqqoywyxorgyeq~qygyyegP'Pygmy,~z, gyr<qz~~<gg~sgyr~~~

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Test Personnel Qualifications XI Vendor Tests under MEIS Direction XI Calibration and Control of Nondestructive XII Examination Instruments Inspection and Maintenance of Material Handling XIII Equipment Overhead and Gantry Cranes XIII Inspection and Maintenance of Portable Lifting XIII and Handling Equipment Underhung Cranes, Jib Cranes and Monorail Systems XIII Slings and Related Apparatus XIII Classification and Training of Material Handling XIII Revision 19 December, 1993

Equipment Personnel Table 1-1 (cont'd)

Appendix B Materials En ineerin Ins ection Services Criteria Mobile Hydraulic Cranes XIII Inspection and Maintenance of Jacks, Hydraulic Rams XIII and Cylinders, Forklift Loading Forks XIII Inspection of Designated Monorails XIII Training and Qualification of Crane Operators XIII Lifting Devices in the Containment Vessel XIII Pre-Shipment Inspection of Radioactive Material XIII Shipping Containers Nonconformance Reports XV Initiating and Responding to Corrective Action XVI Reports Quality Materials Engineering and Inspection XVII Services Records Response to Audits XVII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Ginna Quality Assurance Program Implementation Fire Watch Training R.E. Ginna Training Plan Ginna Station Training General Employee Training Temporary Employee Training Hazardous/Mixed Waste Emergency Response Training Operator Training Responsibilities R.E. Ginna Health Physics Orientation Program Fire Brigade Training Radiation Protection Technician Entry Level

'Requirements, Responsibilities, .and Training Chemistry Technician Entry Level Requirements, Responsibilities, and Training Maintenance Training Program Ginna Station Administrative and Engineering Staff Responsibilities ~

Ginna Station Management Responsibilities Health Physics and Chemistry Section Organization and Responsibilities Support Services Organization and Responsibilities Operations Section Organization and Responsibilities Technical Section Organization and Responsibilities Material and Procurement Section Organization and Respon'sibilities Revision 19 December, 1993

S Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Operational Assessment Section Ginna Station Staff Responsibilities for Fire Prevention Ginna Modification Project Organization Plant Operations Review Committee Operating Procedure Radiation Emergency Plan Xmplementing Procedure Committee Emergency Procedures Committee (EPC)

Ginna Standard Nomenclature XI Preparing and Dispositioning of Technical Staff Request Control of Station Modification Station Modification Classification and Review IIX Station Modification Planning Control Station Modification Installation and Acceptance Station Modification Completion Preparation, Review 8 Approval of Design Input Documents for Minor Modifications Component Classification Request/Reanalysis IXI Evaluation of Parts to Determine Safety Classification Preparation, Review and Approval of Safety Analysis Preparation, Review, Approval and Distribution of Design Output and Design Review Documents for Minor Modifications Technical Evaluation Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Preparation of Configuration Data Change Forms Computer Software Product Evaluation Control of Procurement Documents Prepared at Ginna Station Evaluation of Commercial Grade Items for Safety IV Related Applications Evaluation of Items for In-Storage Maintenance IV Requirements Plant Procedures Preparation and Classification Plant Procedure Content and.Format Requirements Emergency and Abnormal Operating Procedures Writers'uide Operating Procedures Writers'uide Health Physics and Chemistry Procedures Writers.'uide V

Plant Procedure Adherence Requirements Emergency and Abnormal Operating Procedures Users'uide Procedure Control Procedure Control-New Procedures Procedure Control-Permanent Changes Procedure Control-Temporary Changes Procedure Control-Periodic Review VI Procedure Control-Index Procedure Control of Emergency and Abnormal Procedures VI Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Qinna Procedures Criteria Procedure Control - Amendments to Licensing Documents and Changes to the Facility Procedure Change Control 10CFR 50.59 Review VI Emergency and Abnormal Operating Procedure Support VI Documentation Control Procedure Distribution VI Control of Construction Documents VI Vendor Manual Control Program Vendor Manual Information/Discrepancy/Incorporation VI Request Drawing Change Request VI Conditional Release Program VIX Receipt and Acceptance of Materials/Parts VII Control of Purchased Services VII Inventory Control of Material, Parts and Components VIX at Qinna Station Xdentification and Marking of Accepted Material, VIII Parts, and Components Bulk Storage of Combustible Materials and Their Use =

VIIX Trailer Admittance Requirements VIIX Control of Consumable Materials at Ginna Station VIII Control of Welding IX Nondestructive Examination Control Welding Equipment Performance Verifications Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Open Flame, Welding and Grinding Permit (Hot Work Permit) IX Control of Inservice Inspection Activities ASME Section XI Repair, Replacement and Modification Procedure for Ginna Station Electrical Preventive Maintenance Program Environmentally Qualified Equipment Maintenance Program Mechanical Preventive Maintenance Program for Rotating Equipment Equipment Inspection and Lubricant List X Valve Preventive Maintenance Program Condenser Inservice Inspection Program Preventive Maintenance Program for Plant Security Equipment Performance of Tests XI Qualification and Certification of Test Personnel XI Test Tag Control Program Calibration, Test, Check and Replacement Surveillance Program for Instrumentation and Equipment Important to Safety XI Ginna Station Surveillance Schedule XI Inservice Testing of Pumps and Valves XI Calibration and Control of Test Equipment XII Maintenance and Inspection of Material Handling Equipment XIII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Control of Material Handling and Handling Equipment XIII Storage and Preservation of Materials and Equipment at Ginna Station XIII Control of Heavy Loads at Ginna Station XIII Control of Heavy Loads for the Containment Overhead Crane XIII Control of Heavy Loads for the Auxiliary Building Overhead Crane XIII Control of Heavy Loads for the 7 1/2 Ton Screenhouse Crane XIII Control of Heavy Loads for Jib Cranes in Containment XIII Control of Heavy Loads in Safety-Related Areas XIII Housekeeping 'Control XIII Station Holding Rules XIV Bypass of Safety Function of Jumper Control XIV Operational Assessment Program XIV Effectiveness Evaluation of the Operational Assessment Program XIV Installation and Removal of Temporary Cables XIV Control of Temporary Modifications XIV Program Pressure Provisions'IV Installation, Removal and Control of Scaffolding Installation and Removal of Temporary Fluid System to Prevent Degradation of Reactor Coolant Boundary XIV XIV Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Independent Verification XIV Control of Nonconforming Items XV Nonconformance Reports XV Corrective Action Reports XVI Root Cause Analysis XVI Overview of the Ginna Station Work Control System XVI Work Request/Trouble Report Initiation XVI Work Order Initiation XVI Work Order Planning XVI Work Order Scheduling XVI Work Order Execution XVI Post Maintenance Testing XVI Work Order Close Out XVI Work Order Processing After Hours XVI Work Control System Performance Indicators XVI Station Work Authorization Request XVI Safety Classification of Maintenance Work Activities XVI Identified Deficiency Reports XVI Ginna Records XVII Records Storage Facilities and Equipment XVII Special Nuclear Material Inventory and Record Requirements XVII Maintenance History Program XVII Ginna Station Response to Internal Audits XVII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Indoctrination and Training Engineering Department Organization and Responsibilities I

Ginna Modification Project Organization Preparation, Review and Approval of Design Input Documents Preparation, Review and Approval of Design Analyses III Preparation, Review and Approval of Engineering Drawings III Preparation, Review and Approval'f Engineering Specifications Preparation,'eview and Approval of Design. Verification Integrated Design Process Preparation, Review and Approval of Safety Analyses Review and Approval of Architect Engineer or Consultant Design Documents Preparation, Review and Approval of Field Change Requests Preparation, Review and Approval of Engineering Change Notices Review of the Classification of Station Modifications Preparation, Review,and Approval of CAD Piping and Instrumentation Drawings Preparation, Review and Disposition of Drawing Change Requests ALARA/ Radiation Safety Design Review Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Preparation, Review and Approval of Appendix R Conformance Verifications Preparation, Review and Approval of the Electrical Equipment Environmental Qualification Data Summary Form EEQ-1 and XEEE 323-1974 Waiver Authorization Form EEQ-2 Review, Approval and Implementation of Changes to the Safety Assessment System Software Engineering Computer Software Documentation and Control Human Factors Review of Control Room and. Local XII Emergency Control Panel Modifications Preparation, Review and Approval of PAID Database and Configuration Data Change Forms Erosion/Corrosion Control Monitoring Program y for Carbon Steel Piping Preparation, Review and Approval of Changes to.the Updated Final Safety Analysis Report ASME Section XI Repair, Replacement and Modification Program Implementation Component Safety Classification Drawing Review Process Component Safety Classification Component Classification Form Component Safety Classification Request/Re-Analysis System, Structure, or Component Safety Classification Criteria Preparation, Review and Approval of CAD Electrical XII Drawings Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Requests for Nuclear Engineering Services Preparation, Review and Approval of Procurement . IV Documents for Purchases Covered by the QA Program Evaluation of Commercial Grade Items for Safety IV Related Applications Evaluation of Quality Verification Items for Safety IV Significant Applications Preparation, Review, and Approval of Engineering Procedures Preparation, Review, and Approval of Engineering Procedure Deviation Request Distribution and Control of Documents by the Control Number Method Distribution and Control of Documents by Project

~

VI Correspondence Procedures Preparation, Review and Approval

~

of Supplier Evaluations VII Review and Approval of Vendor Design and'Manufacturing VII Technical Documents Preparation, Review and Approval of Bid Requests, Bid VII Evaluations and Recommendations for Award Engineering Review of Nonconforming Materials, Parts or Components Initiating and Responding to Corrective Action Reports XVI Processing Identified Deficiency Reports XVI Documenting and Reporting Potential Conditions XVI Adverse to Quality Performing "Substantial Safety Hazard" Evaluations XVI for 10CFR21 Reportability Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Nuclear En ineerin Services Procedures Criteria Records XVII Records Turnover Plan XVII Engineering Response to Internal Audits XV1II Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Purchasin Procedures Criteria Periodic Review of Purchasing Procedures Indoctrination and Training of Purchasing Personnel Purchasing Department'rganization and Responsibilities Preparation, Review, Approval and Issuance of IV Purchase Orders and Changes to Purchase Orders Requests for Bids and Bid Evaluation XV Purchasing Procedures Purchasing Procedure Deviation Request Supplier Evaluation VIX Supplier Material Deficiency Processing XV Supplier Corrective Action Reporting XVI Purchasing Response to Corrective XVI Action Reports and Corrective Action Reporting Purchasing Records and Turnover=Pl'an XVII Purchasing Response to Audits XVIII Revision 19 December, 1993

Table 1-1 (cont'd)

Appendix B Production Division Trainin Procedures Criteria Indoctrination and Training Production Division Training Organization and Responsibilities Operations and Technical Training Organization and Responsibilities Training Systems Organization and Responsibilities Maintenance Training Organization and Responsibilities Curriculum Committee Organization and 'Responsibilities Software Quality Assurance. Program Preparation, Review and Approval of Quality Training Procedures Preparation, Review and Approval of Training Procedures, Guidelines, and Policies Preparation, Review and Approval of Nuclear Training Programs Style Guide for Training Procedure Development Nuclear Training Procedure Revision Training Change Request/Notice Control and Distribution of Production Division VI Training Documents Training Programs for Crane Operators and Riggers XIII Corrective Action XVI Nuclear Production Division Training XVII Records Management Production Division Training Response to QA Audits XVIII Revision 19 December, 1993

Table 1-1 (cont'd)

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Design/Modification Activities Control. at Ginna Station Design/Modification Activities Control at Station 13A and on Circuit 751, Equipment and Line Control of Procurement Documents for Purchased Parts, Components and Services Preparation, Review and Approval of Electric Transmission and Distribution Procedures Preparation and Approval of Laboratory Test Procedures Preparation and Approval of Electric Meter and V Laboratory Calibration Schedules Preparation and Approval of Electric Substation'Department V Relay Test Schedules Preparation and Approval of Electric Transmission and Distribution Deviation Requests Procedures Control and Distribution of Electric Meter and Laboratory VI Department and Laboratory Test Procedures Revision 19 December, 1993

Table 1-1 (cont'd)

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Criteria Control of Electric Meter and Laboratory Department Calibration Services Control of Electric Substations Department Relay VI Test Schedule

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Supplier Technical Evaluation VII Receipt and Acceptance of Instrumentation and VII Standards Equipment Control of Purchased Services for Electric Meter and Lab VII Identification and Control of Materials, Parts and VIII Components

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Division Performance of Tests at Ginna Station XI Performance of Tests at the Electrical Laboratory XI Qualification of Test Personnel XI Calibration and Control of Test Instruments XII Nonconforming Parts and Components XV Initiating and Processing of Corrective Action Reports XVI Control of Quality Assurance Records XVII Kai'%EKE%<iii?;:<iÃtÃNii ib~i?.~e':re'v'iVi4~:%<?<<yo??8'N%%W!~eiir5'i~??::"'~"HNUFx'60-Revision 19 December, 1993

TABLE 4-1 Procurement Document Re uirements Items to be considered for inclusion in procurement documents include:

1. Sco e of Work Detailed statement of the work to be performed.

2. Technical Re uirements - by reference to specific drawings, specifications, codes, regulations, procedures or instructions, including revisions, that describe the items or services to be furnished. Also identified shall be test, inspection and acceptance requirements, and any special requirements for such activities as designing, identification, fabrication, cleaning, erecting, packaging, handling, shipping, extended storage and shelf life.

• 3 ualit Assurance Pro ram Re irements which require the supplier to have a documented quality assurance program that implements portions or all of 10CFR50 Appendix B as well as applicable quality assurance program requirements of other nationally recognized codes and standards. Also included shall be the requirement that the supplier incorporate appropriate quality assurance program requirements in subtier procurement documents.

• 4. Ri ht of Access to include the facilities and records of the supplier for source inspection and audit by the Purchaser or parties designated by the purchaser. Also included shall be provisions for the identification of witness and hold points and the minimum time of advance notice.

• 5. Documentation Re uirements Submittal approval and retention requirements for documents such as quality assurance manuals, special process and test procedures, materials records, calculations and analyses.

• 6. Nonconformance Requirements for reporting and disposition of nonconformance to procurement requirements.

• - Items reviewed by Quality Assurance or Quality Control.

-'61-Revision 19 December, 1993

Table 18-1 Audit List Audit i i Title Corrective Action Audit To ic Areas Corrective Action associated with deficiencies occurring in facility, equipment, structures, systems or methods of operation.

Operational Assessment Nonconformance Control

• Outage Activities Refueling and Special Nuclear Material ISI Implementation IST Program and Implementation Surveillance Test and LCOs Maintenance Modification Installation Safety Security Radiation Protection and ALARA

• Health Physics, Chemistry and Radwaste Shipping and Process Radwaste Control Program and implementing procedures Radioactive Effluents and Offsite Dose Calculation Manual and implementing procedures Radiation Protection and ALARA HP/Chemistry Measuring and Text Equipment Chemistry Program Radiological Environmental Monitoring Program

• Fire and Safety Fire Protection Program and implementing procedures Fire Protection and Loss Prevention Program Revision 19 December, 1993

Table 18-1 (con')

Audit List i

Audit i Title Audit To ic Areas Independent Inspections and Audits Fire Systems Fire Surveillance Fire Brigade Training Fire Brigade Equipment Safety P'rogram Housekeeping Instructions, Procedures, Drawing Control Document Control 'nd-Vendor Manual Control Procedure Control Records Control Security Security Plan and Implementing procedures Guard Training and Qualification Fitness for Duty Program

• Operations Limiting Conditions for Operation Surveillance Testing Operator Performance Operations Administration PORC Activities NSARB Activities Materials Engineering and ISI Program Inspection Services NDE Qualifications Welding Qualifications MHE Program Miscellaneous QA Controls

• Maintenance and Testing Preventive Maintenance Program Planning and Scheduling Work Order Implementation Post-Maintenance Testing Work Order Closeout and Equipment History Control of Measuring and Test Equipment Revision 19 December, 1993

Table 18-1 (con')

Audit List 1

i Audit i Title Audit To ic Areas Technical Specification Surveillance Nuclear Emergency Response Plan Nuclear Emergency Response Plan and Procedures Offsite Agency Interface Response Personnel Training Emergency Information Plan Training/performance and Licensed Operator qualifications of the Auxiliary Operator operating and technical staff Chemistry Technician Maintenance Radiation Protection Technician Results and Test Technician QC Inspector Shift Technical Advisor Technical Staff and Managers Engineering Department Training General Employee Training Procurement Procurement Evaluations Procurement Document Control Control of Purchased Items and Services Handling, Storage, and Shipping Hazardous Material Control Program Configuration Control Major Modification Design Minor Modification Design Installation Planning Control of As-Built Configuration Licensing Activities Temporary Modifications Revision 19 December, 1993

e R.E. GINNA NUCLEAR POWER PLANT MANAGEMENTORGANIZATION CHART UNES OF COMMUMCATIOM CHAIRMANOF THE 8OARD, PRESDENTAND UNES OF SVPERVISON ANDADMINISTRATCH CHIEF EXECVAVEOFFCER SEMOR SEMOR VCE SENOR VCE VICE PRESDENT PRESDEMl; PRES DENT, OAS 4 ELECTRC Og PRODUCTION AND CONTROLLER DtSTRI8VAON ENDWEERINQ 4 CHtEF AND CVSTOMER INANCIAL

~

SERVCE8 ~

OFFCER VCE PRESDENT VICE PRESDENT L~ MSARS EMPLOYEE OINNA NUCLEAR RBATIONS, PRODVCAOM PU8UC AFFAIRS DEPARTMEMT AND MATERIAL MANAGER MANAGER MANAGER DEPARTMENT MANAGEMENT OUAUlY DIVNIONAL PRODUCAON MANAGER PERFORMANCE 8BlVCES AND PRODVCAOH DIVISON DIVISON ENQWEERINO DIVISON MANAGER MANAGER SYSTEMS TRAINWG IIANAQER SYSTEM ROCHESTER OUALAY ENGWEERWO CONSTRUCTION ASSURANCE RECORDS HEALTH AND DESGM AND MANAGEMENT, PHYSCS AND MAINTENANCE TECHMCAL NUCLEAR OUAUTY WFORMATION EMERGENCY ASSURANCE CENTER,CMIS, PIANNWO PROCVREMEMT, WFORMATIOM DEPARTMENT DEPARlllENT DEPARTMENT ENOWEERWO, MANAGER MANAGER MANAGER 8ERVCES 4 DEPARTMENT PLANT AUDIT4 DMSOM SYSTEM DISTRISVAVE METER AND MANAGER LIAMAQER SURVEILLANCE SYSTEMS NVCLEAR OWNA oooo' DESGM IMFORMAllON IAS SERVCES ENQWEERINO SYSTEMS OPERATIONS ENOWEKRWQ STATION SUPPORT 8ERVCES MANAGER FIELD 4 SHOP ENNRONMENTAL RELAY ELECTRX: NUCLEAR FASRCAllON SCIENCE, COMMUNKAllONS ASSVRANCK SERVCES IASORATORY SQN, STATION ENGINE ERWQ METER CHEMISTRY COMSTRVCAOM. OPERAllONS, OPERATES SERVCES AND UCBtSNQ, MAtNTKNINCE, OUALIIY RESEARCH 4 FUEL HP 4 LASORATORY CONTROL AND DEVELOPMENT MANAGEMENT 4 CHEMISTRY EMPLOYEE SERVICES OVALAY TECHNCAL COMTROI RBAllONS ENGINEERWO SUPPORT TKCHNCAL DEPARTMENT SERVCES SERVCES SUPPORT, MANAGER TESTWQ, OVERHEAD MANAGER MATKRLAL CONSTRV CADM MATERIALS OOHTROL, AND ENQWEKRWG PROCUREMEMT, MAIMIKNANCE AND FIRE EAST INSPECTION PROTECAON, SERVCES SAFETY, LIODIFCATXOM, CONSTRUCAON OPERATWO RBAYTEST MATERIALS EXPERIENCE 4 ENQWEERINQ, COMPVIKR SYSTKMS MHE ISNP.

SKRVICES FIGURE 2-1

QUALITYPERFORMANCE ORGANIZATION DEPARTMENT MANAGER QUALITY PERFORMANCE MANAGER MANAGER MANAGER QUALITY QUALITY NUCLEAR MATERIALS PERFORMANCE ASSURANCE ASSURANCE ENGINEERING SENIOR

& INSPECTION ANALYST SERVICES QUALITY QUALITY QUALITY MATERIAL8 STAFF ASSURANCE CONTROL CONTROL MATERIAL ENGINEERS ENGINEERS FOREMAN HANDLING ENGINEERS 8 FOREMEN STAFF TECHNICIANS INSPECTORS FIGURE 2-2

GINNA NUCLEAR PRODUCTION ORGANIZATION VCK PRE SCENT 0WNA NUCLEAR PROOUCTCW PLIHT MAHAOBt OWNA STATCW WAlALLCEHSKD OPBtATOR OPERATOlt ItKOVAL OPERATWO PLAHNWO A AUXOPBIATOR BIPERIEHCE SCHKOUUHO STA WTIIAL MATKltlALS MNNTBINCE PROCUREMENT SYSTEMS STA REOUAL SAFETY MNNTKNAICKItULE CHKNSTRV TECH PltOIKCT ltAD PltOTKCllOH ELKCTRCALAHD IAC TECH MNNTBIANCK CONIIIACTltAD MKCHAHCAL ~ ROTECTCH TKCH MNNTEHAHCE KLECTltCAL MAlNTB4AHCK MKCHAHCAL MNNTENAHCE QC TKCHIlCIAH RAT TKCIPICW<

FlGURE 2-3

I GAS AND ELECTRIC DISTRIBUTION DIVISION SENIOR VICE PRESIDENT GAS ANO ELECTRIC DISTRIBUTION ANO CUSTOMER SERVICES DMSION MANAGER OMSION MANAGER SYSTEM ENGINEERING ROCHESTER

~ 0 ~ OOOJOOOtSOS ~

AND DESIGN CONSTRUCllON AND MAINTENANCE DEPARTMENT MANAGER DEPARTMENT MANAGER QUALITY DEPARTMENT MANAGER DEPARTMENT MANAGER SYSTEM DESIGN DISTRIBUTIVE SERVICES METER AND LAB OVERHEAD ENGINEERING INFORMATION COORDINATOR OPERATIONS CONSTRUCllON ANO SYSTEMS SUPPORT MAINTENANCE EAST SUBSTATIONS RELAY ENGINEERING ENGINEERING COMMUNICATIONS ELECTRIC LABORATORY CONSTRUCTION METER SERVICES RELAYTEST OPERATIONS NOTE: Chart la abbreviated to ahow only key OoaNona InvohRed In Implementing the QA program and therefore, doea not ahow aa poaltkea In th UN ES OF AVTNORllY USES OF COMMUNICATION FIGURE 2Q

TECHNICAL SERVICES DIVISION ORGANIZATION DIVISION MANAGER TECHNICAL SERVICES AND CHIEF ENGINEER MANAGER DEPARTMENT MALINGER PRODUCTION MANAGER DIVISIONAL AND GENERAL SERVICES ENGINEERING ENGINEERING SYSTEMS SERVICES MANAGER DIVISION MANAGER FOSSIL PROJECT SHOP SYSTEMS ENVIRONMENTAL ENGINEERING MANAGEMENT OPERATIONS SCIENCE SERVICES RECORDS HYDRO MANAGER MANAGEMENT MANAGER ENGINEERING FIELD CHEMISTRY SERVICE FOSSIUHYDRO SERVICES FACILITY OPERATION SYSTEMS ENGINEERING SUPERVISOR MANAGER TECHNICAL ENVIRONMENTAL REAL ESTATE ADMINISTRATIVE INFORMATION LABORATORY MANAGEMENT SERVICES AND CENTER PROJECT SENIOR PLANNING ENVIRONMENTAL ANALYST MANAGER RESEARCH 8c INSPECTION/LAND DEVELOPMENT SURVEY AND PROGRAM BUILDING SERVICES FIGURE 2-5

Ill 1I

GINNA STATION REVIEW AND AUDIT FUNCTIONS NSARB QUALITY PORC PERFORMANCE TECHNICAL MATERIALS GAS AND PURCHASING GENERAL NUCLEAR GINNA STATION SERVICES ENGINEERING ELECTRIC MAINTENANCE ENGINEERING DIVISION AND DISTRIBUTION SERVICES INSPECTION DIVISION SERVICES REVIEW AUDITS FIGURE 2

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