ML17263A351
| ML17263A351 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/31/1992 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A350 | List: |
| 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 9308ii 05000ggg 0 930806
. pDR ADO~K pDR pg~
C
Section TABLE OF CONTENTS Title Pacae 2 ~
3.
4 ~
5.
6.
QUALITY ASSURANCE PROGRAM FOR STATION OPERATION Quality Assurance Program Organization Design Control Procurement Document Control Instructions, Procedures and Drawings Document Control 10 13 14 16 7 ~
8.
10.
12.
13.
14.
15.
16.
17.
18.
Control of Purchased Material, Equipment and Services Identification and Control of Materials, Parts and Components Control of Special Processes Inspection Test Control Control of Measuring and Test Equipment Handling, Storage and Shipping Inspection, Test and Operating Status Nonconforming Materials, Parts and Components Corrective Action Quality Assurance Records Audits 18 22 24 25 27 28 29 30 31 32 34 35 Revision 18 December 1992
LIST OF TABLES Table Number 4-1 18-1 Title Quality Assurance Program Procedures Subject Listing Procurement Document Requirements Audit List Pacae 38 59 60 LIST OF FIGURES Fi ure Number 2-1 2-2 2-3 Title Management Organization Quality Performance Organization Nuclear Production Division Organization Pacae 65 66 Electric Transmission and Distribution 67 Organization 2-5 2-6 Technical Services Division Organization Ginna Station Review and Audits Functions 68 69 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.
Revision 18
- December, 1992
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
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 ~
b.
NRC Regulatory Guide 1.8, Revision 1, "Personnel Selec-tion and Training."
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." Revision 18
- December, 1992
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.
m.
NRC Regulatory Guide 1.116, Revision O-R, "Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems."
NRC Regulatory Guide 1.123, Revision 1, "Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants."
n.
NRC Regulatory Guide 1.144, Revision 1, "Auditing of Quality Assurance Programs for Nuclear Power Plants" except that supplier audit frequencies and performance evaluations are as described in the Quality Assurance Manual.
0 ~
NRC Regulatory Guide 1.146, Revision 0, "Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants."
Revision 18
- December, 1992
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.
Revision 18
- December, 1992
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.
Revision 18
- December, 1992
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
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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
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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
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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
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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. Revision 18
- December, 1992
~ 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. Revision 18
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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. Revision 18
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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 acceptance criteria of the, original design.
Quality Performance also reviews procurement documents for spare or replacement parts for adequacy of the quality requirements.
Instructions Procedures and Drawin s Each Rochester Gas and Electric company organization, involved in quality related activities, is responsible for developing, reviewing, approving, and implementing procedures as required to implement the Quality Assurance Program.
These procedures cover 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. Revision 18
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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
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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
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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
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same reviews and approvals for changes to documents as was required of the original document; to require that organiza-'ions which review and approve documents have access to pertinent information and adequate knowledge of the original document intent; to assure that approved changes are promptly transmitted for incorporation into documents; and to assure that obsolete or superseded documents are eliminated from the system and not used.
Quality Performance is responsible for review and concurrence of procurement documents for all procuring organizations and, therefore, procurement document control requirements.
Quality Performance is responsible for review and assessment of document control systems to assure adequate systems are implemented.
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
'h suppliers list provided that item acceptance can be based on acceptance of standard commercial quality which is supplemented, as necessary, with source surveillance, pre-or post-installation tests, receipt tests, commercial supplier test reports, commercial supplier certificates, or receipt. inspection.
Items or services which have nuclear quality requirements which normally require the supplier to implement a quality assurance program but for which no such supplier can be practicably utilized may also be purchased from suppliers not listed on the approved suppliers list provided that verification of nuclear quality can be accomplished by methods such as source surveillance, pre-or post-installation tests, receipt tests, supplier test
- reports, supplier certificates, or receipt inspection as approved by Quality Assurance.
Departmental procedures establish guidelines for source selection evaluations and for documenting the results through indication of the corresponding procurement method.
The purchase requisition will also identify the source when replacement parts are to be procured from the original equipment supplier. 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 have documentation to support In the event the traceability review is unsatisfactory, the may not be released for use.
acceptance tag or label and the acceptability of the item.
is lost or the documentation item becomes nonconforming and 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.
In addition, those "use-as-is" nonconformances which also deviate from a Design Criteria requirement shall require additional approval of the Senior Vice President, Production and Engineering.
Nuclear Assurance Quality Control personnel provide nonconformance status information periodically.
Quality Performance and other organizations analyze nonconformance report data for adverse trends and 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 if a significant condition adverse to quality exists.
When a significant condition adverse to quality at Ginna Station is identified, the Corrective Action Coordinator is Revision 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.
If the significant condition adverse to quality involves a design deficiency or the recommended corrective action involves a design
- change, the review of the condition adverse to quality includes Nuclear Engineering Services or Ginna Station design personnel, as appropriate.
The Corrective Action Coordinator assures root cause determination and corrective action plans are developed to resolve the identified concern and to preclude recurrence.
The Plant Operations Review Committee reviews all Corrective Action Reports initiated at Ginna Station and may recommend additional corrective action if the action already taken does not, result in adequate 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 III Specifications
) Computer Software Product Evaluation Quality Assurance, Review of Computer Software Production Evaluations
( Master Software Index Requisitioning Quality Assurance/Quality Control Services IV Quality Review of Rochester Gas and Electric Procurement Documents, IV Preparation, Review and Approval of Rochester Gas and Electric Q.A. Specifications IV Revision 18
- December, 1992
Table 1-1 (cont'd) ualit Assurance ualit Control Procedures Appendix B
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 Deviation Requests by Quality Assurance/Quality Control VI Evaluation of Suppliers by Quality Assurance VII Supplier Surveillance Control of Supplier Performance VII VII Quality Assurance Evaluation of Bids Conducting Commercial Grade Supplier Surveys VII VII Evaluation of Commercial Suppliers by Quality Assurance VII Document Deficiency Reports
~ Verification Inspection Program
) Qualification of Inspection Personnel
( Quality Assurance Nonconformance Processing
( Corrective Action Reports VII X
XV XVI Revision 18
- December, 1992
Table 1-1 (cont'd) ualit Assurance ualit Control Procedures Appendix B Criteria
) Quality Assurance Commitments and Action Items
) Review of Ginna Maintenance Work Order Packages Identified Deficiency Reports
( Records Turnover Plan
( Qualification of Audit/Survey Personnel Audit Scheduling and Planning Performance of Quality Assurance Audits Reporting and Follow-Up of Audit Findings Conduct of Quality Assurance During and in Follow-Up of NSARB Audits
~
~
~
~
~
Response
to Audits and Surveillance Qualifications of Surveillance Personnel
( Review of Audit Program
( Auditing of the Nuclear Emergency
Response
Plan
~ Performance Based Surveillance Program Availability and Use of INPO and NRC Inspection/
Assessment Reports in Audit and QA Surveillance
[ Quality Assurance Plinning Guides XVI xvx XVI XVII XVIII XVIII XVIII XVIII xvxxx XVIII XVIII XVII XVII XVIII XVIII XVIII Revision 18
- December, 1992
Table 1-1 (cont'd)
Materials En ineerin Ins ection Services Appendix B
Criteria Indoctrination and Training Materials Engineering and Inspection Services Organization and Responsibilities Preparation, Review and Approval of Purchase Requisitions and Related Procurement Documents IV 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 Safety Related Activities
) Control of Purchased Materials Preparation, Review and Approval of Supplier Evaluation VI VII VII Control of Purchased Services Welding Procedure Preparation Review and Approval Welding Procedure Qualification Heat Treating Procedures Welder Qualification and Currency Nondestructive Examination Procedures Nondestructive Examination Procedures Manual Nondestructive Examination Personnel Qualification VII IX IX IX IX IX IX IX Revision 18
- December, 1992
1
Table 1-1 (cont'd)
Materials En ineerin Ins ection Services Appendix B
Criteria
) Qualification of Visual Examination Personnel Erosion/Corrosion Program
( General Brazing Procedures Preparation and Approval
( General Brazing Procedures Qualification Inservice Inspection Program and Plans IX IX IX IX X
ASME Section XI Repair, Replacement and Modification Procedure X
Incorporating Ginna Modifications into Inservice Inspection Program Duties of the ANII l Tests conducted by MEIS Laboratories
) Requesting MEIS Services Laboratories Test Personnel Qualifications e
[ Vendor Tests under METS Direction Calibration and Control of Nondestructive Examination Instruments X
XI XI XI XI XII Inspection and Maintenance of Material Handling Equipment XIII Overhead and Gantry Cranes XIII Inspection and Maintenance of Portable Lifting and Handling Equipment XIII Underhung Cranes, Jib Cranes and Monorail Systems Slings and Related Apparatus XIII XIII Classification and Training of Material Handling Equipment Personnel XIII Revision 18
- December, 1992
Table 1-1 (cont'd)
Materials En ineerin Ins ection Services Appendix B
Criteria Mobile Hydraulic Cranes Inspection and Maintenance of Jacks, Hydraulic Rams and Cylinders XIII XIII Forklift Loading Forks Inspection, of Designated Monorails Training and Qualification of Crane Operators Lifting Devices in the Containment Vessel Pre-Shipment Inspection of Radioactive Material Shipping Containers
) Nonconformance Reports Initiating and Responding to Corrective Action Reports Quality Materials Engineering and Inspection Services Records
[ Response to Audits XIII XIII XIII XIII XIII XV XVI XVII XVII Revision 18
- December, 1992
1
Ginna Procedures Table 1-1 (cont'd)
Appendix B 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
Ginna Procedures Table 1-1 (cont'd)
Appendix B
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
Ginna Procedures Table 1-1 (cont'd)
Appendix B Criteria Preparation of Configuration Data Change Forms Computer Software Product Evaluation Control of Procurement Documents Prepared at Ginna Station IV Evaluation of Commercial Grade Items for Safety Related Applications IV Evaluation of Items for In-Storage Maintenance Requirements
) Plant Procedures Preparation and Classification Plant Procedure Content and Format Requirements IV 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 Procedure Control-Temporary Changes Procedure Control-Periodic Review Procedure Control-Index Procedure Control of Emergency and Abnormal Procedures VI VI VI VI Revision 18
- December, 1992
Ginna Procedures Table 1-1 (cont'd)
Appendix B
Criteria Procedure Control Amendments to Licensing Documents and Changes to the Facility VI Procedure Change Control 10CFR 50.59 Review VI Emergency and Abnormal Operating Procedure Support Documentation Control VI Procedure Distribution
) Control of Construction Documents
) Vendor Manual Control Program Vendor Manual Information/Discrepancy/Incorporation Request VI VI VI VI Drawing Change Request Conditional Release Program I Receipt and Acceptance of Materials/Parts Control of Purchased Services VI VII VII VII Inventory Control of Material, Parts and Components at Ginna Station VII Identification and Marking of Accepted Material,
- Parts, and Components VIII Bulk Storage of Combustible Materials and Their Use Trailer Admittance Requirements Control of Consumable Materials at Ginna Station
) Control of Welding
( Nondestructive Examination Control
) Welding Equipment Performance Verifications VIII VIII VIII IX IX IX Revision 18
- December, 1992
0 0
Ginna Procedures Table 1-1 (cont'd)
Appendix B
Criteria Open Flame, Welding and Grinding Permit (Hot Work Permit)
IX Control of Inservice Inspection Activities ASME Section XI Repair, Replacement and Modification Procedure for Ginna Station Electrical Preventive Maintenance Program Environmentally Qualified Equipment Maintenance Program Mechanical Preventive Maintenance Program for Rotating Equipment Equipment Inspection and Lubricant List Valve Preventive Maintenance Program Condenser Inservice Inspection Program X
Preventive Maintenance Program for Plant Security
~
~
~
Equipment Performance of Tests
) Qualification and Certification of Test Personnel Test Tag Control Program XI XI XI Calibration, Test, Check and Replacement Surveillance Program for Instrumentation and Equipment Important to Safety Ginna Station Surveillance Schedule XI XI Inservice Testing of Pumps and Valves l
Calibration and Control of Test Equipment Maintenance and Inspection of Material Handling Equipment XI XII XIII Revision 18
- December, 1992
0
Ginna Procedures Table 1-1 (cont'd)
Appendix B
Criteria Control of Material Handling and Handling Equipment Storage and Preservation of Matenials and Equipment at Ginna Station XIII 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 Housekeeping Control Station Holding Rules Bypass of Safety Function of Jumper Control Operational Assessment Program XIII XIII XIV XIV XIV Effectiveness Evaluation of the Operational Assessment Program XIV Installation and Removal of Temporary Cables Control of Temporary Modifications Installation, Removal and Control of Scaffolding XIV XIV 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
Ginna Procedures Table 1-1 (cont'd)
Appendix B Criteria Independent Verification Control of Nonconforming Items Nonconformance Reports Corrective Action Reports Root Cause Analysis Overview of the Ginna Station Work Control System Work Request/Trouble Report Initiation Work Order Initiation Work Order Planning Work Order Scheduling Work Order Execution Post Maintenance Testing Work Order Close Out XIV XVI XVI XVI XVI XVI XVI XVI XVI Work Order Processing After Hours Work Control System Performance Indicators Station Work Authorization Request Safety Classification of Maintenance Work Activities Identified Deficiency Reports Ginna Records Records Storage Facilities and Equipment Special Nuclear Material Inventory and Record Requirements
) Maintenance History Program
) Ginna Station Response to Internal Audits XVI XVI XVI XVI XVI XVII XVII XVII XVII XVII Revision 18
- December, 1992
Table 1-1 (cont'd)
Nuclear En ineerin Services Procedures Appendix B
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)
Preparation, Review and Approval of Appendix R Conformance Verifications Appendix B
Criteria 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)
Nuclear En ineerin Services Procedures Appendix B
Criteria Requests for Nuclear Engineering Services Preparation, Review and Approval of Procurement Documents for Purchases Covered by the QA Program IV Evaluation of Commercial Grade Items for Safety Related Applications IV Evaluation of Quality Verification Items for Safety Significant Applications Preparation,
- Review, and Approval of Engineering Procedures
[ Preparation,
- Review, and Approval of Engineering Procedure Deviation Request Distribution and Control of Documents by the Control Number Method IV VI 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 Technical Documents VII Preparation, Review and Approval of Bid Requests, Bid Evaluations and Recommendations for Award VII Engineering Review of Nonconforming Materials, Parts or Components VX Initiating and Responding to Corrective Action Reports Processing Identified Deficiency Reports XVI XVI Documenting and Reporting Potential Conditions Adverse to Quality Performing "Substantial Safety Hazard" Evaluations for 10CFR21 Reportability XVI XVI Revision 18
- December, 1992
Table 1-1 (cont'd)
Nuclear En ineerin Services Procedures Appendix B
Criteria Records
[ Records Turnover Plan
) Engineering
Response
to Internal Audits XVII XVII XVIII Revision 18
- December, 1992
Table 1-1 (cont'd)
Purchasin Procedures Appendix B Criteria Periodic Review of Purchasing Procedures Indoctrination and Training of Purchasing Personnel Purchasing Department Organization and Responsibilities Preparation, Review, Approval and Issuance of Purchase Orders and Changes to Purchase Orders IV Requests for Bids and Bid Evaluation Purchasing Procedures Purchasing Procedure Deviation Request Supplier Evaluation Establishment and Maintenance of Qualified Suppliers List Establishment and Maintenance of the Commercial Grade Supplier List IV VII VII VII Supplier Material Deficiency Processing Supplier Corrective Action Reporting Purchasing
Response
to Corrective Action Reports and Corrective Action Reporting
( Purchasing Records and Turnover Plan Purchasing
Response
to Audits XV XVI XVII XVIII Revision 18
- December, 1992
,0
Table 1-1 (cont'd)
Production Division Trainin Procedures Appendix B 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 Training Documents VI Training Programs for Crane Operators and Riggers Corrective Action XIII XVI Nuclear Production Division Training Records Management XVII 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
- Parts, Components'and Services IV 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
) Procedures VI Control and Distribution of Electric Meter and Laboratory VI Department and Laboratory Test Procedures Control of Electric Meter and Laboratory Department Calibration Services VI Control of Electric Substations Department Relay Test Schedule VI Revision 18
- December, 1992
I
Table 1-1 (cont'd)
Electric Transmission Procedures and Distribution Appendix B Procedures Criteria Supplier Technical Evaluation Receipt and Acceptance of Instrumentation and Standards Ec{uipment VII VII Control of Purchased Services for Electric Meter and Lab VII Identification and Control of Materials, Parts and Components VIII Surveillance at the Electric Transmission and Distribution X
Division oi Performance of Tests at Ginna Station Performance of Tests 'at the Electrical Laboratory Qualification of Test Personnel Calibration and Control of Test Instruments Nonconforming Parts and Components XI XI XI XII XV Initiating and Processing of Corrective Action Reports Control of Quality Assurance Records
( Electric Transmission and Distribution Response to Audits XVI XVII 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 Corrective Action Audit To ic Areas Corrective Action associated with deficiencies occurring in facility, equipment, structures, systems or methods of operation.
Operational Assessment Nonconformance Control
- Outage Activities Refueling and Special Nuclear Material ISI Implementation IST Program and Implementation Surveillance Test and LCOs Maintenance Modification Installation Safety Security Radiation Protection and ALARA
- Health Physics, Chemistry and Radwaste
- Fire and Safety Radwaste Shipping and Process 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 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, and Document Control Drawing Control Vendor Manual Control Procedure Control Records Control Security
- Operations Security Plan and Implementing procedures Guard Training and Qualification Fitness for Duty Program Limiting Conditions for Operation Surveillance Testing Operator Performance Operations Administration PORC Activities NSARB Activities Materials Engineering and Inspection Services ISI Program 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 Training/performance and qualifications of the operating and technical staff Nuclear Emergency
Response
Plan and Procedures Offsite Agency Interface
Response
Personnel Training Emergency Information Plan Licensed Operator Auxiliary Operator 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 Configuration Control Procurement Evaluations Procurement Document Control Control of Purchased Items and Services Handling, Storage, and Shipping Hazardous Material Control Program 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 and Distribution Electric Mater and Laboratory 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 LINES Of SUPERVISION HA ADIINISTRATION LINES Cf CCASINIICATION CHAIRHAN OF THC SOARD>
PKSIOOIT AND CHItf EXECUTIVE CfFICCR SENIOR VICC tltSIDENT CAS S CLCCTRIC 0ISTlIRUTION AACI CUSTOCN SERVICES SENIOR VICE tktSIOCNT PROOVCTION 0 CNCINCCRINC StNION VICC PKSIXNT>
CONTROLLER S CHICf fINANCIAL OfFICER VICC tKSIDOfl DPLOYCC RELATIONS, PUSLIC AFFAIlS AND HATERIAL HANACDENT VICE tlESIDENT CINNA NUCLEAR tRODVCTION VICL tRLSIDCNT, SKCKTANY~
1KASURCR XPANDENT IMRACER AND PUKHAS INC ACCNT HATCNIALS IWVCDENT DIVISION HANACCR CLCCTRIC TRANQUSSION 0 DISTRIRUTION XPAlhQIT HANACCN DUALITY ttkfONHANCC DIVISION IlANACtk TCCHNICAL SERVICES ANO CHIEF CNCINECN SICCCT AND COST XPARTlCLT HANACCN RISC ANACD>EST OIKCTON Of SCCUN IIV XPARDENT XPAIBlENT SVPCR INTCNXNT QPKR INTCNXNT ELECTRIC LAS ELCCTNIC ANO TCLC SUSSTAT TONS COAANIICATIONS DIVISION HANACCR HATER IALS END IKEk INC 0 INSPECTION SCRVICCS DCPANTIUIT HANACER KSCARCH 4 SCIENCE XPANDCIT HANACCR tlODVCTIOIC 0 ENGINEERINC CYSTCHS OEPARTIENT SARACEN NUCLCAR CNCINECRIIC SERVICES XPARDENT l4ANACKR PRODUCT ION DIVISION 7RAININO
~ w uv..~m CINNA STATION DPLOYKK RCLAT TONS HETER CALISRATION a HAINTCNAKC ANO CLCCTRIC LAS SERVICES OCSICN.
TECH SLPPORT>
lOTATINC COUIPICNT HAINTCNANCC RGAY TEST S CONSTRXTION SERVICCS HATERIALS CNC INCCR INC
NX>
ISI 0 1SN: INSP SKRVICCS DUALITY CONTROL HO DUALITY CNC I NEER INC SERVICCS DUALITY ASQAIAKE PNOCINDENT, CNCINCCNINC, ANIT 0 QRVCILLANCE SERVICCS CNVIINIOCNTAL SCICNCC S LASONATONV OEHISTNY
- SERVICES, KSCAKH S DEVCLOtieC SUPENVISOk PRODUCT IWIACDCITT StlVICCS DUALIIV
- SCRVICCS, PROJECT HANACDCNT
- SERVICCS, aWrk. SERV. ~
RECORDS HANACDENT >
TCCNICAL INfORHATION CENTER, DGS, INFORHATION
- SCRVICCS, DIVISION SYSTCHS DEPARTMENT SUPCN INTCNXNT OCHERAL HAINTCNANCC fltLD0 SHOP FASNICATION StkVICKS
- OCSICN, CONSTRUCTION>
LICCNSINC>
ILL HANACDCNT 0 TCCHNICAL SERVICES TRAININC SERVICES OIRCC'TOR CORtORATK kADIATION PROTECTION CORPORATE HEALTH PHYSICS NO NVCLCAR DERCCNCY PLANNINC STAT!ON OPERATIONS, HAINTENANCC~
HP 0 OSMSTRY
- CONTROL, TCCHNICAL
- QPPORT, TCST INC, HATERIAL CON'TROL.
PROGH DENT, LIASON CNC INECN INC, FISC PROTECTION S SAFETY.
OPERATIONAL ASSESSCNT ~
CCAPVTCR CYSTDTS QFCRVISON M@LEAR SECURITY Figure 2-1
EQUALITY PERFORNANCE ORGANIZATION DEPARTHEHT HANAGER QUALITY PERFORNAHCE NANAGER QUALITY ASSURANCE HAHAGER NUCLEAR ASSURANCE NANAGER NATERIALS EHGINEERIHG 8I INSPECTION SERVICES QUALITY PERFORNANCE SENIOR AHALYST QUALITY ASSURANCE EHGINEERS QUALITY CONTROL ENGINEERS QUALITY COHTROL FOREHAN NATERIAL 4 NATERIAL HAHDLIHG ENGINEERS 4 FOREHEH STAFF STAFF TECHNICIANS G INSPECTORS STAFF Figure 2-2
GINNA NUCLEAR PRODUCTION ORGANIZATION VICE PRESIDENT GINNA NUCLEAR PRODUCTION BUDGET AHD COST DIRECTOR CORPORATE RADIATION PROTECTION CORPORATE HEALTH PHYSICS NUCLEAR ENERGEHCY PLANNIHG SUPERIHTEHDENT 6IHHA PRODUCTION OPERATIONS HEALTH PHYSICS 5 CHENISTRY TECHNICAL ENGINEERING OPERATIONAL ASSESSNENT CONPUTER SYSTEHS OUTAGE PLANHING PLANT HANAGER GINNA STATION CORRECTIVE ACTION SAFETY NATERIALS Ea PROCUREHENT SUPERINTENDENT GIHNA SUPPORT SERVICES NECHANICAL NAINTENANCE ELECTRICAL AHD I!LC tlAINTEHANCE HAIHTENANCE PLANHIKG 4 SCHEDULING FIRE PROTECTION HODIFI CATION SUPPORT DEPARTNENT NANAGER PRODUCTION DIVISION TRAINING INITIAL LICEHSED OPERATOR OPERATOR REQUAL AUX OPERATOR STA INITIAL STA REQUAL CHENISTRY TECH RAD PROTECTION TECHNICIAN CONTRACT RADIATION TECH ELECTRICAL NAINT.
HECHANICAL NAINT.
ILC TECHNICIAN RKT TECHNICIAN TECH STAFF AHD NWAGERS TRAIHIHG COURSES DEPARTNENT NAHAGER NUCLEAR ENGINEERING SERVICES DESIGH CONSTRUCTION LICENSING FUEL NWAGEHENT TECHHICAL SUPPORT SERVICES Figure 2-3
ELECTRIC TRANSMISSION AND DISTRIBUTION DIVISION DIVISION NANAGER ELECTRIC TRANSNISSION 4 OISTRIBUTION I
I OEPARTNENT SUPERINTEKOENT ELECTRIC LABORATORY 4 TEL ECONNUNI CATION 5 GAS A ELECTRIC HETER OPERATIONS OEPARTNENT SUPERINTENOENT ELECTRIC SUBSTATIONS LABORATORY SERVICES QUALITY SERVICES COO ROINATOR CONSTRUCTION RELAY TEST NANAGER EHGINEERIHG NANAGER SUBSTATION NAINTENANCE Vlr.0 M 00
'LD lO HOTE: Chart Is abbrevIated to shm only key posItIons Involved fn tnplenenttng QA progran and therfore, does not she(
all posItIons
)n the dIvIsIon.
Figure 2-4 ENGINEERING
. QUALITY SERVICES NAINTENANCE ANO TEST TRAVELIHG OPERATORS
0
TECHNICAL SERVICES DIVISION ORGANIZATION DIVISION NANAGER TECHNICAL SERVICES AHO CHIEF EHGINEER P5 Qo I
I OEPARTNENT SUPERINTENDENT GEHERAL NAIHTEHAHCE Nanager Shop Operations Nanager Field Service Operations Nanager Adainistrative Services and Project Planning Nanager Inspection/Land Survey and Building Services DEPARTMENT NAHAGER PRODUCTION AHD ENGINEERING 5YSTENS Division Systeas Records Nanageaent Fossil/Hydro systens Technical Infornat ion Center DEPARTHENT NANAGER RESEARCH 4 SCIEHCE Nanager Environoental Science Nanager Chenistry Services Supervisor Environnental Laboratory Senior Environnental Analyst Research 4
Oevelopaent Prograa DEPARTMENT. NANAGER GENERAL EKGIHEERING SERVICES Fossil Engineering Hydro Engineering Facility Engineering Real Estate Nanagement SUPERVISOR PROJECT NANAGENENT SERVICES Project Nanagewent Services Oocunent Preparation 4
Secretarial Services Duality Services Npo0 M oo M
Figure 2-5
'GINHA STATION REVIEW AND AUDIT FUNCTIONS NSARB I
I QUALITY PERPORMANCE PORC
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TECHNXCAL SERVICES DIVISION MATERIALS ENGINEERING AND INSPECTION SERVXCES ELECTRIC TRANSMXSSXON DZSTRXBUTION PURCHAS XNG NUCLEAR ENGINEERING SERVICES GZNNA STATION.
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AUDITS Figure 2-6
'4
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