ML17263A351

Rev 18 to QA Program for Station Operation.

ML17263A351
Person / Time
Site:	Ginna
Issue date:	12/31/1992
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A350	List: ML17263A349 ML17263A351
References
NUDOCS 9308110400
Download: ML17263A351 (116)

Text

ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT Revision 18 to:

Quality Assurance Program for Station Operation DOCKET NO. 50-244 December, 1992 0 930806 9308iiADO~K pDR 05000ggg pg~

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C TABLE OF CONTENTS Section Title Pacae QUALITY ASSURANCE PROGRAM FOR STATION OPERATION Quality Assurance Program 2 ~ Organization

3. Design Control 10 4 ~ Procurement Document Control 13

5. Instructions, Procedures and Drawings 14

6. Document Control 16 7 ~ Control of Purchased Material, Equipment 18 and Services

8. Identification and Control of Materials, 22 Parts and Components Control of Special Processes 24

10. Inspection 25 Test Control 27

12. Control of Measuring and Test Equipment 28

13. Handling, Storage and Shipping 29

14. Inspection, Test and Operating Status 30

15. Nonconforming Materials, Parts and Components 31

16. Corrective Action 32

17. Quality Assurance Records 34

18. Audits 35 Revision 18 December 1992

LIST OF TABLES Table Number Title Pacae Quality Assurance Program 38 Procedures Subject Listing 4-1 Procurement Document Requirements 59 18-1 Audit List 60 LIST OF FIGURES Fi ure Number Title Pacae 2-1 Management Organization 2-2 Quality Performance Organization 65 2-3 Nuclear Production Division 66 Organization Electric Transmission and Distribution 67 Organization 2-5 Technical Services Division 68 Organization 2-6 Ginna Station Review and Audits 69 Functions Revision 18 December 1992

'I UALITY ASSURANCE PROGRAM FOR STATION OPERATION

1. 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 10 CFR 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 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, Electric Transmission and Distribution, 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 Revision 18 December, 1992

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 l-l provides a listing of the subjects and a short description of the subject matter which is con-tained in the 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 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 classifica-tion 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 imple-mented and enforced. Personnel responsible for performing activities affecting quality are trained and indoctrinated in the requirements, purpose, scope, and implementation of 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.

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In addition to training in quality assurance, each depart-ment 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 operators, as necessary. As appropriate personnel 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 Selec-tion and Training."

b. NRC Regulatory Gui'de 1.28, Revision 2, "Quality Assur-ance 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."

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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."

gi 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."

Note: When record storage facilities are not designed in accordance with the requirements of Regulatory Guide 1.88, duplicate records are kept in two separate storage locations in separate buildings which are physically isolated from each other.

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

m. 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.

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

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Or anization The major organizations participating in the Quality Assur-ance Program are Purchasing, Technical Services, Ginna Nuclear Production, Electric Transmission and Distribution, Quality Performance, 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 Department Manger, Quality Performance Manager, Quality Assurance Department 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 Department Superintendent, Electric Substations Department Department Superintendent, Electric Laboratory and Telecommunications 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.

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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.

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 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 modification, plant maintenance, and fire protection activities in accordance with the requirements of the Quality Assurance Program.

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The Superintendent, Ginna Production reports to the Plant Manager, Ginna Station, and is responsible for operations, health physics and chemistry, refueling, results and tests,

! Ginna computer systems, technical engineering, surveillance testing and operational assessment in accordance with the requirements of the quality assurance 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, 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 INPO 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 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 Revision 18 December, 1992

support. In addition, he provides support to Nuclear Engineering Services to assist in administration and training associated with procedure changes and to provide coordination for generating responses to audits and inspections.

The Department 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 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.

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 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 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 Revision 18 December, 1992

I, safety-related material, equipment and services are properly qualified, and they are responsible for conducting audits and surveillances at these suppliers'acilities. In ad-dition, 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. He is responsible for providing functional 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.

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, specifica-tions, and procedures. He is a member of the Plant Operations Review Committee and delegates the day to day quality assurance and 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 Revision 18 December, 1992

accordance with applicable commercial, technical, and quality requirements. He maintains a listing of qualified suppliers determined through an evaluation made by Purchasing, Nuclear Engineering Services, Quality Assurance and the other involved departments as appropriate.

The Department Superintendent, Electric Laboratory and Telecommunications is responsible for providing a staff, Figure 2-4, to perform routine maintenance and testing services for Ginna Station meters. He is also responsible for providing laboratory testing of some electrical equipment and devices.

The Department Superintendent, Electric Substations Department is responsible for providing a staff, Figure 2-4, to perform relay engineering, maintenance and testing 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. He is also responsible for coordinating and for providing support documentation for any design modifications initiated within the Electric Transmission and Distribution Division.

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 Electric Substations Department for the systems and equipment for which Electric Transmission and Distribution 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 Revision 18 December, 1992

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 level, (3) changes to a safety related system determined not 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, control, and revision requirements; and corrective action. Design con-siderations 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 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 pre-viously 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.

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~ F 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 com-petent. 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 re-visions there-to, 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.

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.

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Plant modifications are controlled by means of applicable Ginna Station, Nuclear Engineering Services, Electric

) Transmission and Distribution, 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 Committe'e and Nuclear Safety Audit and Review Board as required by Section 6.0, Technical Specifications.

4 ~ 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 proce-dures 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, Electric Transmission and Distribution 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 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.

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After purchase requisitions, service agreements, contracts, specifications, and drawings have received the required re-views 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 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, compati-bility, and acceptancealsocriteria of the, original design.

procurement documents for Quality Performance reviews 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 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 provides 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.

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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, off 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 Roches-ter 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.

Electric Transmission and Distribution is responsible for the preparation and implementation of relay inspection and testing procedures as required to direct detailed inspec-tions and testing activities for which they are responsible.

Electric Transmission and Distribution '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 associated with major modifications and when minor modifications necessitate drawings or specifications. 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 Revision 18 December, 1992

4 ~

activities; and 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 assessments, as described in Section 10 and Section 18, are used to verify that commitments are being addressed and quality affecting activities are being performed in accordance with approved instructions, procedures and drawings.

Document Control Procedures are established to control the issuance of pro-cedures, 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. Electric Transmission and Distribution 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 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 Revision 18 December, 1992

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 tech-nical person associated with that activity. Ginna Station, Nuclear Engineering Services, Material Engineering and Inspection Services, Purchasing, Production Division Training and Electric Transmission and Distribution 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 the Department Manager, Quality Performance or designee.

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 con-trolled 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.

r 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.'uppliers 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 Revision 18 December, 1992

same reviews and approvals for changes to documents as was required of the original document; to require that which review and approve documents have access to organiza-'ions 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.

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 products.

Procurement planning is utilized by the procuring organiza-tions for determining the methods to be used for acceptance of the item or service as well as requirements for the control of the supplier performance. Source inspection (surveillance), certificate of conformance, receipt inspec-tion and post installation test are methods which are considered for item acceptance with receipt inspection 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 procure-ment document requirements (i.e. certifications, stress reports etc.). The extent of the acceptance methods and as-sociated verification activities will vary and be a function of the relative importance and complexity of the purchased item or service and the supplier's past performance.

Revision 18 December, 1992

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 the procurement planning, determines the necessity for the supplier selection to be 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 item, 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 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

'h 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.

Revision 18 December, 1992

Addition of a supplier to the approved suppliers list is based on satisfactory evaluation of the supplier's capability by Quality Assurance, Purchasing and other departments, as appropriate.

For engineered items, Nuclear Engineering Services is 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 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 regulatory or code quality assurance requirements.

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

The departments responsible for performing supplier evalu-ations shall document their results in reports which discuss areas investigated, findings, and conclusions. As applicable, concurrence of Purchasing, Nuclear Engineering Services, Quality Performance, Ginna Station and Electric Transmission and Distribution is required to place a supplier on the qualified suppliers'ist. One organization can remove a supplier from the list without concurrence of the others.

Revision 18 December, 1992

Measures are established by Nuclear Engineering Services 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 initiated the procurement. When a deviation from purchase order requirements is noted, the Quality Assurance represen-tative, 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 18 December, 1992

A 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 15.

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 Revision 18 December, 1992

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 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 main-taining identification and control of materials, parts, or components received, stored, installed, and used at the plant in accordance with approved procedures. The responsible supervision of other departments which receive material which 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 noncon'forming material and deviations and waivers are controlled and documented in accordance with Section 15.

Revision 18 December, 1992

C '

'ontrol of S ecial Processes Written procedures are established to control special pro-cesses, 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 complies 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 per-forming special processes under their cognizance are quali-fied 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 and the training and qualification of welders. 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.

Revision 18 December, 1992

'ns ection Procedures prepared for the control of activities include inspection requirements and hold points as required by drawings, instructions, requirements documents, specifi-cations, 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 personnel prior to performing an inspection operation.

Revision 18 December, 1992

P

~5

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.

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 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.

Revision 18 December, 1992

1 7 klkk

" 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, 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; instruc-tions 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 and testing associated with modifications.

Test 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 its 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, Electric Transmission and Distribution performs test activities to determine the cause of protective relay malfunctions. These test activities are performed in accordance with approved procedures by qualified personnel.

Revision 18 December, 1992

I .

t

Nuclear Engineering Services and Quality Performance are responsible for assuring that required tests for major modifications are included in specifications. Nuclear Engineering Services and Electric Transmission and Distribution 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 modification-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 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. Calibra-tion 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 trace-ability 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 equipment to be entered into the calibration and control system including require-ments 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 Revision 18 December, 1992

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 cali-bration of measuring and test equipment at Ginna Station in accordance 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 cali-brated and controlled in accordance with station procedures.

Measuring, test or inspection equipment used by Nuclear Assurance Quality Control is included in the program.

The Manager, Materials Engineering and Inspection Services and, Department Superintendent, Electrical Laboratory and Telecommunications 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.

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. Electric Transmission and Distribution, and Materials Engineering and Inspection Services areresponsible 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, manufac-turer'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 is responsible for specifying in procurement documents and in engineering specifications that written procedures be used, as appropriate, for the handling, shipping, storage, clean-ing, and preservation of materials and equipment procured Revision 18 December, 1992

for major modifications. These procedures are prepared by contractors, by the station staff, or by staff members of Electric Transmission and Distribution as appropriate.

Rochester Gas and Electric procedures are reviewed and approved as described in Section 6.

In the preparation of procurement documents, department procedures, and contra'ctor 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 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 indicat-ing the status of operating equipment or systems to be removed from service for maintenance, repair, or modifica-tion 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.

Revision 18 December, 1992

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 rejec-tion 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 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. RG&E 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 RG&E, which have supplier recommended dispositions of use-as-is, or repair, are normally processed

-3 1-Revision 18 December, 1992

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 requirement and technical justification for acceptance. All such items are approved prior to use by the cognizant organization having responsi-bility for the requirement. deviate In addition, those "use-as-is" from a Design Criteria nonconformances which also 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 process 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 and safety of the public, seriously affect the ability to operate the plant in a safe manner, represents 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 exists.

if a significant condition adverse to quality When a significant condition adverse to quality at Ginna Station is identified, the Corrective Action Coordinator is Revision 18 December, 1992

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.

Quality Performance Supervision 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, Electric Transmission and Distribution or cognizant supplier associations.

For significant conditions adverse to quality, corrective action processes shall ensure affected RGGE management review initiated reports to determine causes, develop corrective action plans, resolve the identified concerns and preclude recurrence.

to quality involves a If the significant condition adverse 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.

The Plant Operations Review Committee reviews all Corrective Action Reports 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 action 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 18 December, 1992

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 Electric Transmission and Distribution 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, main-tenance, repair, inservice inspection, refueling, modifica-tion, 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.

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 18 December, 1992

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.

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 Revision 18 December, 1992

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

Table 18-1 is a list of the activities to be examined by audit in each of the'udits. Frequencies are based on the level of activity in each area. Audit schedules are estab-lished to assure that each of the activities are audited at the frequency specified in Section 6.0. Technical Speci-fications. 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 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 procure-ment, 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 Revision 18 December, 1992

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 18 December, 1992

I 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 I 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 Requests and Review of ECN's

~

Quality Assurance Review of Rochester Gas and

~

Electric Engineering Specifications

~ ~ ~ ~

Preparation, Review and Approval of Quality Verification Specifications III

) Computer Software Product Evaluation Quality Assurance, Review of Computer Software Production Evaluations

(

Master Software Index Requisitioning Quality Assurance/Quality Control IV Services Quality Review of Rochester Gas and IV Electric Procurement Documents, Preparation, Review and Approval of Rochester Gas and IV Electric Q.A. Specifications Revision 18 December, 1992

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 X

)

Qualification of Inspection Personnel

(

Quality Assurance Nonconformance Processing XV

(

Corrective Action Reports XVI Revision 18 December, 1992

Table 1-1 (cont'd)

Appendix B ualit Assurance ualit Control Procedures Criteria

) Quality Assurance Commitments and Action Items XVI

) Review of Ginna Maintenance Work Order Packages xvx 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 xvxxx 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 Plinning Guides XVIII Revision 18 December, 1992

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 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 IX Revision 18 December, 1992

1 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 X ASME Section XI Repair, Replacement and X Modification Procedure Incorporating Ginna Modifications into Inservice Inspection Program Duties of the ANII X l Tests conducted by MEIS Laboratories XI

) Requesting MEIS Services Laboratories XI Test Personnel Qualifications e

XI

[

Vendor Tests under METS 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 18 December, 1992

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 18 December, 1992

1 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 Responsibilities Revision 18 December, 1992

ll 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 Preparing and Dispositioning of Technical Staff Request Control of Station Modification Station Modification Classification and Review Station Modification Planning Control

(

)

Station Modification Installation and Acceptance Station Modification Completion Preparation, Review & Approval of Design Input Documents for Minor Modifications Component Classification Request/Reanalysis 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 18 December, 1992

I, L

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 Plant Procedure Content and Format Requirements 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'uide Procedure Control Procedure Control-New Procedures Procedure Control-Permanent Changes VI Procedure Control-Temporary Changes VI Procedure Control-Periodic Review Procedure Control-Index VI Procedure Control of Emergency and Abnormal Procedures VI Revision 18 December, 1992

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 50.59 Review VI Emergency and Abnormal Operating Procedure Support VI Documentation Control Procedure Distribution VI

) Control of Construction Documents VI

) Vendor Manual Control Program VI Vendor Manual Information/Discrepancy/Incorporation VI Request Drawing Change Request VI Conditional Release Program VII I Receipt and Acceptance of Materials/Parts VII Control of Purchased Services VII Inventory Control of Material, Parts and Components VII 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 IX

(

Nondestructive Examination Control IX

)

Welding Equipment Performance Verifications IX Revision 18 December, 1992

0 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 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 XI 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 l

Calibration and Control of Test Equipment XII Maintenance and Inspection of Material Handling Equipment XIII Revision 18 December, 1992

0 Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Control of Material Handling and Handling Equipment XIII Storage and Preservation of Matenials 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 18 December, 1992

8 ~

0

Table 1-1 (cont'd)

Appendix B Ginna Procedures Criteria Independent Verification XIV Control of Nonconforming Items Nonconformance Reports Corrective Action Reports XVI Root Cause Analysis Overview of the Ginna Station Work Control System 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 18 December, 1992

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

)

Preparation, Review and Approval of Engineering 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 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 Instrumentation Drawings Preparation, Review and Disposition of Drawing Change Requests 41 ALARA/ Radiation Safety Design Review Revision 18 December, 1992

1 Table 1-1 (cont'd)

Appendix B 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 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 Emergency Control Panel Modifications Preparation, Review and Approval of P&ID Database and Configuration Data Change Forms Erosion/Corrosion Control Monitoring Program 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 Drawings Revision 18 December, 1992

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 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 Approval 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 18 December, 1992

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 18 December, 1992

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 Supplier Evaluation VII Establishment and Maintenance of Qualified VII Suppliers List Establishment and Maintenance of the Commercial VII Grade Supplier List Supplier Material Deficiency Processing XV Supplier Corrective Action Reporting XVI Purchasing Response to Corrective Action Reports and Corrective Action Reporting

(

Purchasing Records and Turnover Plan XVII Purchasing Response to Audits XVIII Revision 18 December, 1992

,0 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 18 December, 1992

Table 1-1 (cont'd)

Electric Transmission Procedures and Distribution Appendix B Procedures Criteria Quality Assurance Program Implementation for Electric Transmission and Distribution Department

( Indoctrination and Training of Electric Transmission and Distribution Personnel Electric Transmission and Distribution 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

) Transmission and Distribution Procedures Preparation and Approval of Laboratory Test Procedures Preparation and Approval of Electric Meter and Laboratory Calibration Schedules Preparation and Approval of Electric Substation Department V Relay Test Schedules Preparation and Approval of Electric Transmission and Distribution Deviation Requests Control of Electric Transmission and Distribution VI

)

Procedures Control and Distribution of Electric Meter and Laboratory VI Department and Laboratory Test Procedures Control of Electric Meter and Laboratory Department VI Calibration Services Control of Electric Substations Department Relay VI Test Schedule Revision 18 December, 1992

I

Table 1-1 (cont'd)

Electric Transmission Procedures and Distribution Appendix B Procedures Criteria Supplier Technical Evaluation VII Receipt and Acceptance of Instrumentation and VII Standards Ec{uipment Control of Purchased Services for Electric Meter and Lab VII Identification and Control of Materials, Parts and VIII Components Surveillance at the Electric Transmission and Distribution X 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 oi Nonconforming Parts and Components XV Initiating and Processing of Corrective Action Reports XVI Control of Quality Assurance Records XVII

(

Electric Transmission and Distribution Response to Audits XVIII Revision 18 December, 1992

I

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

1. Sco e of Nork 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 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.

Revision 18 December, 1992

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 18 December, 1992

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 18 December, 1992

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 18 December, 1992

Table 18-1 (con't)

Audit List Audit Title Audit To ic Areas Electric Transmission Electric Mater and Laboratory and Distribution Electric Substations

• Noted audits will also address relevant activities to verify conformance of facility operation to all provisions contained in Technical Specifications and applicable license conditions.

Revision 18 December, 1992

l'%

'P

R.E. GINNA NUCLEAR POMER PLANT MANAGEMENT ORGANIZATION CHART CHAIRHAN OF THC SOARD>

LINES Of SUPERVISION HA ADIINISTRATION PKSIOOIT AND CHItf EXECUTIVE CfFICCR LINES Cf CCASINIICATION SENIOR SENIOR VICE tktSIOCNT StNION VICC tltSI DENT PROOVCTION 0 CNCINCCRINC VICC PKSIXNT>

CAS S CLCCTRIC CONTROLLER S 0 ISTl I RUT I ON f CHICf INANCIAL AACI CUSTOCN OfF ICER SERVICES VICC tKSIDOfl DPLOYCC RELATIONS, VICE tlESIDENT CINNA NUCLEAR tRODVCTION SKCKTANY 1KASURCR

~

VICL tRLSIDCNT, PUSLIC AFFAIlS AND HATER IAL HANACDENT DIVISION HANACCR DIVISION IlANACtk XPARTlCLT CLCCTRIC TCCHNICAL SERVICES HANACCN XPANDENT TRANQUSSION XPAlhQIT HANACCN ANO CHIEF CNCINECN RISC IMRACER AND 0 DISTRI RUT ION DUALITY INC ANACD>EST PUKHAS INC ttkfONHANCC ACCNT HATCNIALS SICCCT AND COST IWVCDENT OIKCTON Of SCCUN IIV XPARDENT SVPCR I NTCNXNT ELECTRIC LAS XPAIBlENT QPKR INTCNXNT ELCCTN I C HANACCR HATER END IALS IKEk INC DCPANTIUIT HANACER KSCARCH XPANDCIT HANACCR tlODVCTIOIC 0 OEPARTIENT SARACEN NUCLCAR XPARDENT l4ANACKR PRODUCT ION

~ w uv ..~m CINNA STATION ANO TCLC SUSSTAT TONS 0 INSPECTION 4 SCIENCE ENGINEER INC CNCINECRIIC DIVISION COAANIICATIONS DIVISION SCRVICCS CYST CHS SERVICES 7RAININO HETER OCSICN. DUALITY HATER I ALS CNVIINIOCNTAL RECORDS OCSICN, TRAININC STAT!ON QFCRVISON PRODUCT S CALI SRAT I ON TECH SLPPORT> ASQAIAKE CNC INCCR > SCICNCC HANACDENT > CONSTRUCTION> SERVICES OPERATIONS, M@LEAR a HAINTCNAKC lOTATINC PNOCINDENT, NX> LASONATONV TCCNICAL LICCNSINC> HAINTENANCC~ SECURITY ANO CLCCTRIC COUIPICNT CNCINCCN INC, ISI 0 OEHISTNY I NfORHAT ION ILL HP 0 LAS SERVICES HAINTCNANCC > ANIT 0 1SN: INSP SERVICES, CENTER, DGS, HANACDCNT 0 OSMSTRY RGAY TEST S QRVC ILLANCE SKRVICCS KSCAKH S DEPARTMENT INFORHAT ION TCCHNICAL OIRCC'TOR CONTROL, CONSTRXT I ON SERVICCS DEVCLOtieC SCRVICCS, CORtORATK TCCHNICAL DPLOYKK SERVICCS DIVISION SERVICES I I kAD AT ON QPPORT, RCLAT TONS SYSTCHS PROTECTION TCST INC, HATER I AL CON'TROL.

SUPENVI SOk CORPORATE PROGH DENT, HEALTH LIASON IWIACDCITT PHYSICS NO CNC INECN INC, StlVICCS SUPCN INTCNXNT NVCLCAR FISC OCHER AL DERCCNCY PROTECTION DUALITY HAINTCNANCC PLANNINC S SAFETY.

CONTROL HO OPERATIONAL DUALITY DUALIIV ASSESSCNT ~

CNC I NEER INC SCRVICCS, CCAPVTCR SERVICCS PROJECT fltLD 0 SHOP CYST DTS HANACDCNT FASNICATION SERV I CCS, StkVICKS aWrk. SERV. ~

Figure 2-1

EQUALITY PERFORNANCE ORGANIZATION DEPARTHEHT HANAGER QUALITY PERFORNAHCE NANAGER HAHAGER NANAGER QUALITY PERFORNANCE QUALITY NUCLEAR NATERIALS EHGINEERIHG SENIOR AHALYST ASSURANCE ASSURANCE 8I INSPECTION SERVICES QUALITY QUALITY QUALITY NATERIAL 4 ASSURANCE CONTROL COHTROL NATERIAL HAHDLIHG STAFF EHGINEERS ENGINEERS FOREHAN ENGINEERS 4 FOREHEH STAFF TECHNICIANS STAFF G INSPECTORS Figure 2-2

GINNA NUCLEAR PRODUCTION ORGANIZATION VICE PRESIDENT GINNA NUCLEAR PRODUCTION BUDGET AHD COST PLANT HANAGER DEPARTNENT DEPARTNENT NAHAGER GINNA STATION NANAGER NUCLEAR PRODUCTION ENGINEERING DIVISION TRAINING SERVICES DIRECTOR SUPERIHTEHDENT CORRECTIVE SUPERINTENDENT CORPORATE 6IHHA PRODUCTION ACTION GIHNA SUPPORT INITIAL LICEHSED DESIGH RADIATION SERVICES OPERATOR PROTECTION SAFETY CONSTRUCTION OPERATOR REQUAL OPERATIONS NATERIALS Ea NECHANICAL LICENSING PROCUREHENT NAINTENANCE AUX OPERATOR CORPORATE HEALTH PHYSICS 5 FUEL NWAGEHENT HEALTH CHENISTRY ELECTRICAL STA INITIAL PHYSICS AHD I!LC TECHHICAL TECHNICAL tlAINTEHANCE STA REQUAL SUPPORT SERVICES NUCLEAR ENGINEERING ENERGEHCY HAIHTENANCE CHENISTRY TECH PLANNIHG OPERATIONAL PLANHIKG 4 ASSESSNENT SCHEDULING RAD PROTECTION TECHNICIAN CONPUTER SYSTEHS FIRE PROTECTION CONTRACT OUTAGE RADIATION TECH PLANHING HODIFI CATION SUPPORT ELECTRICAL NAINT.

HECHANICAL NAINT.

ILC TECHNICIAN RKT TECHNICIAN TECH STAFF AHD NWAGERS TRAIHIHG COURSES Figure 2-3

ELECTRIC TRANSMISSION AND DISTRIBUTION DIVISION DIVISION NANAGER ELECTRIC TRANSNISSION 4 OISTRIBUTION OEPARTNENT GAS A ELECTRIC OEPARTNENT SUPERINTEKOENT HETER SUPERINTENOENT ELECTRIC LABORATORY 4 OPERATIONS ELECTRIC SUBSTATIONS I

TEL ECONNUNI CATION 5 I

LABORATORY QUALITY CONSTRUCTION NANAGER NANAGER SERVICES SERVICES EHGINEERIHG SUBSTATION COO ROINATOR RELAY TEST NAINTENANCE ENGINEERING NAINTENANCE HOTE: Chart Is abbrevIated to shm only ANO TEST key posItIons Involved fn tnplenenttng QA progran and therfore, does not she(

. QUALITY TRAVELIHG Vl all posItIons )n the dIvIsIon. SERVICES OPERATORS r.

0 M 00

'LD lO Figure 2-4

0 TECHNICAL SERVICES DIVISION ORGANIZATION DIVISION NANAGER TECHNICAL SERVICES AHO CHIEF EHGINEER OEPARTNENT DEPARTMENT NAHAGER DEPARTHENT DEPARTMENT. NANAGER SUPERVISOR SUPERINTENDENT PRODUCTION AHD NANAGER GENERAL PROJECT GEHERAL ENGINEERING RESEARCH 4 . EKGIHEERING NANAGENENT NAIHTEHAHCE 5YSTENS SCIEHCE SERVICES SERVICES I

I Nanager Division Nanager Fossil Project Shop Operations Systeas Environoental Engineering Nanagewent Science Services Nanager Records Hydro Field Service Nanageaent Nanager Engineering Oocunent Operations Chenistry Preparation 4 Fossil/Hydro Services Facility Secretarial Nanager systens Engineering Services Adainistrative Supervisor Services Technical Environnental Real Estate Duality and Project Infornat i on Laboratory Nanagement Services Planning Center Senior Nanager Environnental Inspection/Land Analyst Survey and Research 4

• Building Oevelopaent Services Prograa P5 Qo N

po 0

M oo Figure 2-5 M

'GINHA STATION REVIEW AND AUDIT FUNCTIONS NSARB QUALITY PERPORMANCE PORC I

I

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

0 t~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

TECHNXCAL MATERIALS ELECTRIC NUCLEAR GZNNA SERVICES ENGINEERING TRANSMXSSXON PURCHAS XNG ENGINEERING STATION .

DIVISION AND INSPECTION SERVICES SERVXCES DZSTRXBUTION

~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ AUDITS Q

0 M CO Figure 2-6

'4 ~