ML21309A111: Difference between revisions
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# | {{Adams | ||
| number = ML21309A111 | |||
| issue date = 10/26/2021 | |||
| title = Portland General Electric Co., Nuclear Quality Assurance Program for Trojan Independent Spent Fuel Storage Installation (10 CFR 72) Operations and Radioactive Material Packaging and Transportation (10 CFR 71) Activities, Revision 30 | |||
| author name = | |||
| author affiliation = Portland General Electric Co | |||
| addressee name = | |||
| addressee affiliation = NRC/NMSS | |||
| docket = 07200017 | |||
| license number = | |||
| contact person = | |||
| case reference number = VPN-006-2021 | |||
| document type = Quality Assurance Program | |||
| page count = 37 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:ENCLOSURE Ill TO VPN-006-2021 PROPOSED REVISION 30 TO PGE-8010, "PORTLAND GENERAL ELECTRIC (PGE) NUCLEAR QUALITY ASSURANCE PROGRAM FOR TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (10 CFR 72) OPERATIONS AND RADIOACTIVE MATERIAL PACKAGING AND TRANSPORTATION (10 CFR 71) ACTIVITIES" (Copy of entire QA Program Containing Clean Version of the Proposed Revision 30 with Sidebars Annotated) | |||
PORTLAND GENERAL ELECTRIC (PGE) | |||
NUCLEAR QUALITY ASSURANCE PROGRAM FOR PGE-8010 TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (10 CFR 72) | |||
OPERATIONS AND RADIOACTIVE MATERIAL PACKAGING AND TRANSPORTATION (10 CFR 71) ACTIVITIES Revision 30 Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 | |||
PGE NUCLEAR QUALITY ASSURANCE PROGRAM FOR PGE-8010 TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (10 CFR 72) | |||
OPERATIONS AND RADIOACTIVE MATERIAL PACKAGING AND TRANSPORTATION (10 CFR 71) ACTIVITIES Approval: ___ ______ ____ __ _ | |||
ISRC Member Responsible for Managing Nuclear Oversight Resources Approval: _______________ _ | |||
Corporate Executive Responsible for Trojan Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 11 Date Date Revision 30 | |||
TABLE OF CONTENTS TITLE PAGE................................................................................................................................... i AP PROV AL PAGE........................................................................................................................ ii TABLE OF CONTENTS............................................................................................................... iii LIST OF EFFECTIVE PAGES..................................................................................................... iv POLICY STATEMENT.................................................................................................................. v PROGRAM 1.0 ORGANIZATION...................................................................................................... 1 1-6 2.0 QUALITY ASSURANCE PROGRAM.....................................................................2 2-3 3.0 DESIGN CONTROL.......................................................................................................... 3-1 4.0 PROCUREMENT DOCUMENT CONTROL................................................................... 4-1 5.0 INSTRUCTIONS, PROCEDURES, AND DRAWINGS.................................................. 5-1 6.0 DOCUMENT CONTROL.................................................................................................. 6-1 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES..... 7 7-2 8.0 IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND COMPONENTS................................................................................................................. 8-1 9.0 CONTROL OF SPECIAL PROCESSES........................................................................... 9-1 10.0 INSPECTION................................................................................................................... 10-1 11.0 TEST CONTROL............................................................................................................. 11-1 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION.................................................................................................... 12-1 13.0 HANDLING, STORAGE, AND SHIPPING................................................................... 13-1 14.0 INSPECTION, TEST, AND OPERATING STATUS..................................................... 14-1 15.0 NONCONFORMING MATERIAL, PARTS, OR COMPONENTS............................... 15-1 16.0 CORRECTIVE ACTION................................................................................................. 16-1 17.0 QUALITY ASSURANCERECORDS................................................................... 17-1 2 18.0 AUDITS............................................................................................................................ 18-1 GLOSSARY................................................................................................................... Gl Gl-4 111 Revision 30 | |||
PGE NUCLEAR QUALITY ASSURANCE PROGRAM List of Effective Pages Page Revision i (title page) 30 11 30 111 30 lV 30 V | |||
30 1-1 through 1-6 30 2-1 through 2-3 30 3-1 28 4-1 30 5-1 30 6-1 30 7-1 and 7-2 30 8-1 30 9-1 28 10-1 30 11-1 30 12-1 30 13-1 30 14-1 30 15-1 30 16-1 30 17-1 and 17-2 30 18-1 30 Gl-1 through Gl-4 30 lV Revision 30 | |||
PORTLAND GENERAL ELECTRIC COMPANY NUCLEAR QUALITY ASSURANCE PROGRAM POLICY STATEMENT Portland General Electric Company implements a Quality Assurance (QA) Program which directs quality-related activities at the Trojan Independent Spent Fuel Storage Installation (ISFSI). | |||
This QA Program complies with and applies to Important-to-Safety activities conducted under Title 10, Code of Federal Regulations, Part 72, Subpart G, "Quality Assurance for Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste." These activities include managerial and administrative controls used to ensure safe operation of the ISFSI. | |||
This QA Program also complies with and applies to Important-to-Safety activities conducted under 10 CFR 71, Subpart H, "Quality Assurance for Packaging and Transportation of Radioactive Material." | |||
The approval of this document commits the Portland General Electric Company to the requirements of the QA Program described herein and its successful implementation. Portland General Electric Company personnel, authorized contractors and consultants who perform quality-related and/or Important-to-Safety functions are responsible for complying with the requirements of this QA Program. | |||
Changes to the QA Program must be approved by the Nuclear Regulatory Commission, the ISFSI Safety Review Committee member assigned the management oversight function for Nuclear Oversight resources, and the Corporate Executive Responsible for Trojan prior to implementation. | |||
V Corporate Executive Responsible for Trojan (Date) | |||
Revision 30 | |||
1.0 ORGANIZATION | |||
==1.1 INTRODUCTION== | |||
Portland General Electric Company (PGE or Company), as a licensee under the purview of 10 CFR 72 and 10 CFR 71, is responsible for the establishment and execution of this Nuclear Quality Assurance Program (hereafter referred to as the QA Program) for activities conducted in support of the Trojan Independent Spent Fuel Storage Installation (ISFSI) that affect the functions of structures, systems, and components (SSCs) and conduct of services that are important to safety. These activities include managerial and administrative controls used to ensure safe operation of the ISFSI, as well as the performance of functions associated with assuring that the QA Program is effectively implemented. Pursuant to 10 CFR 72.142 and 10 CFR 71.103, the purpose of this chapter is to delineate the authorities, responsibilities, and interfaces of persons and organizations performing activities in support of spent fuel storage and/or radioactive material transport at the Trojan ISFSI that affect the functions of SSCs that are important to safety. | |||
1.2 ASSIGNMENT OF FUNCTIONAL RESPONSIBILITIES Figure 1.0-1 illustrates the functional authorities, responsibilities, and interfaces of persons and organizations performing activities that are governed by and/or required to effectively implement the QA Program. The functional responsibilities indicated in Figure 1.0-1 are further described below. | |||
1.2.1 CORPORA TE EXECUTIVE RESPONSIBLE FOR TROJAN The Corporate Executive Responsible for Trojan has overall authority and responsibility for nuclear safety at the facility, and is responsible for promulgating PGE's QA policies; maintaining a continuing involvement in QA matters; maintaining management controls for effectively implementing applicable QA Program elements; and resolution of disputes between organizational elements that may arise related to quality-related activities. | |||
The ISFSI Manager and the ISFSI Safety Review Committee (ISRC) ultimately report to the Corporate Executive Responsible for Trojan. However, additional management positions may be appointed between the ISFSI Manager and the Corporate Executive Responsible for Trojan to provide additional organizational flexibility of administrative functions. The Corporate Executive Responsible for Trojan will remain the highest-level responsible manager for the implementation ofthis QA Program. The ISFSI Manager maintains overall responsibility for day-to-day ISFSI operations and has a direct line of communication to the Corporate Executive Responsible for Trojan regardless of the organization structure for all matters regarding 1-1 Revision 30 | |||
implementation of this QA Program. PGE employees, ISFSI Staff personnel and/or contractors, agents, or consultants providing Nuclear Oversight services, including establishing and/or implementing the QA Program, also ultimately report to the Corporate Executive Responsible for Trojan when conducting (1) audits ofISRC activities; and/or (2) the biennial audit of past QA audits ofISFSI activities that have been performed pursuant to Chapter 18 of this QA Program. | |||
1.2.2 ISRC The ISRC performs review and audit functions as required by the ISFSI Safety Analysis Report, and advises the Corporate Executive Responsible for Trojan on matters relating to the safe storage of spent nuclear fuel. As the ISRC ultimately reports to the Corporate Executive Responsible for Trojan, ISRC review and audit functions are independent of the ISFSI line organization responsibilities. | |||
With the exception of audits of ISRC activities and/or the biennial audit of past QA audits of ISFSI activities, which as indicated in Section 1.2.1 are the responsibility of the Corporate Executive Responsible for Trojan, the ISRC is responsible for ensuring the conduct of QA audits of ISFSI activities pursuant to Chapter 18 of this QA Program. The ISRC also ensures that the status and adequacy of QA Program implementation is assessed biennially. This assessment should include reviews of audits, inspections, and other sources of QA Program performance. | |||
1.2.3 NUCLEAR OVERSIGHT Nuclear Oversight services are provided as needed by qualified PGE employees, contractors, agents, and/or consultants. These resources report directly to a designated ISRC Member as detailed below. | |||
1.2.3.1 ISRC Member Responsible for Managing Nuclear Oversight Resources One ISRC Member ultimately reports to and is designated by the Corporate Executive Responsible for Trojan as the position having the authority and responsibility for maintaining and implementing the QA Program. This individual directs Nuclear Oversight resources in the overall implementation of the QA Program, including oversight and evaluation of work that is assigned to Nuclear Oversight resources to verify the adequate and effective implementation of the QA Program. The ISRC Member responsible for managing Nuclear Oversight resources, together with the Corporate Executive Responsible for Trojan, is responsible for approving revisions to the QA Program. | |||
Nuclear Oversight resources report directly to this ISRC Member, unless the Nuclear Oversight resources are conducting audit(s) of ISRC activities or are conducting the biennial audit of Nuclear Oversight internal QA audit activities that have been performed pursuant to Chapter 18 1-2 Revision 30 | |||
ofthis QA Program. In these instances, the auditing resources report directly to the Corporate Executive Responsible for Trojan. This organizational structure ensures that persons assigned responsibility for assuring effective implementation of any portion of the QA Program (e.g., review and audit functions) have direct access to levels of management, and the required authority and organizational freedom, as necessary to perform required functions. | |||
The ISRC Member responsible for managing Nuclear Oversight resources must be knowledgeable of the QA Program; 10 CPR 72, Subpart G; and 10 CPR 71, Subpart H, and maintain up-to-date knowledge of applicable regulatory guides, codes, and standards related to Trojan ISPSI QA. Qualifications of this individual must include eight years of experience in the field of QA or equivalent number of years of nuclear plant and/or fuel storage facility experience in a supervisory position or a combination of the two. Graduation from a four-year accredited engineering or science college or university may be substituted for four years of this experience. | |||
At least one year of this experience shall be nuclear power plant and/or fuel storage facility experience in the implementation of an approved QA Program. | |||
1.2.3.2 Nuclear Oversight Resources Nuclear Oversight resources include contractors, agents, 1 and/or consultants who are independent of the ISPSI line organization. The primary role of Nuclear Oversight resources is to conduct audits of ISPSI activities in accordance with Chapter 18 of this QA Program. These resources may also augment the ISPSI Staff in performance of other QA/QC activities, including the performance of audits of ISRC activities or the biennial audit of past QA audits of ISPSI activities that have been performed pursuant to Chapter 18 ofthis QA Program; source and receipt inspections, surveillances or audits of contractors and suppliers of quality-related items; QC inspections; and/or procurement document/record reviews. | |||
Nuclear Oversight resources are under the management direction of the ISRC Member responsible for managing Nuclear Oversight resources, unless the Nuclear Oversight resources are conducting audit(s) ofISRC activities or are conducting the biennial audit of past QA audits ofISPSI activities that have been performed pursuant to Chapter 18 of this QA Program. In these instances, the auditing resources report directly to the Corporate Executive Responsible for Trojan. These auditing resources must be individuals other than those that performed the ISRC activity or conducted the internal audit(s) being audited. | |||
With this organizational structure, Nuclear Oversight auditing resources are ensured to be independent of the Trojan ISPSI representatives performing quality-related activities. As such, Nuclear Oversight resources have the authority and independence to identify quality problems; initiate, recommend, or provide solutions to quality problems through designated channels; and 1 Agents may include PGE employees outside the Trojan ISFSI organization. | |||
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verify implementation of solutions to quality problems. To control deviations from QA Program requirements, PGE personnel, ISFSI staff, contractors, agents, and/or consultants providing Nuclear Oversight services have the authority and responsibility to initiate stop work orders, as necessary, for any condition adverse to quality that has occurred or is developing. | |||
Nuclear Oversight resources provides feedback and consultation to Trojan ISFSI staff inquiries regarding implementation of this QA Program. | |||
1.2.3.3 Additional PGE Senior Management Administrative Support While the Corporate Executive Responsible for Trojan is ultimately responsible for the effective implementation of the QA Program at the Trojan ISFSI, additional Director or Manager positions may be appointed in the PGE corporate organizational structure between the ISFSI Manager and Corporate Executive which may provide additional administrative support to Trojan to provide organizational flexibility of administrative functions. In all cases, the ISFSI Manager maintains overall responsibility for day-to-day ISFSI operations. | |||
1.2.4 ISFSI ORGANIZATION 1.2.4.1 ISFSI Manager The ISFSI Manager is responsible for the day-to-day implementation of the QA Program. The ISFSI Manager ultimately reports to the Corporate Executive Responsible for Trojan. However, additional management positions may be appointed between the ISFSI Manager and the Corporate Executive Responsible for Trojan to provide additional organizational flexibility of administrative functions. The ISFSI Manager maintains overall responsibility for day-to-day ISFSI operations and has a direct line of communication to the Corporate Executive Responsible for Trojan regardless of the organization structure for all matters regarding implementation of this QA Program. | |||
At least biennially, the ISFSI Manager shall review and document the status and adequacy of the parts of the QA Program they are executing and submit it to the ISRC and Corporate Executive Responsible for Trojan. | |||
1.2.4.2 ISFSI Staff The ISFSI Staff reports to the ISFSI Manager. Responsibilities, qualifications, and training required for ISFSI staff personnel performing quality-related activities are detailed in the Trojan ISFSI SAR and associated implementing procedures. ISFSI Staff personnel shall not be used to perform (Chapter 18) audits ofISFSI activities. Appropriately trained and qualified ISFSI Staff personnel (which may include corporate and/or contracted support personnel) may perform 1-4 Revision 30 | |||
audits of ISRC activities or the biennial audit of past QA audits of ISFSI activities that have been performed by Nuclear Oversight resources pursuant to Chapter 18 of this QA Program. In the performance of these audits, the ISFSI Staff audit personnel ultimately report to the Corporate Executive Responsible for Trojan. Audit teams must be comprised of individuals other than those that performed the ISRC activity or conducted the internal audit(s) being audited. | |||
Appropriately trained PGE and ISFSI Staff personnel knowledgeable of QA/QC practices and concepts may also perform quality-related receipt inspections; source inspections, surveillances or audits of contractors and suppliers of quality-related items; QC inspections; and/or quality-related procurement document/record and procedure reviews. Individuals performing procurement document/record and/or procedure review activities must be someone other than those that originated the document/record or procedure revision being reviewed. Individuals performing inspection activities must be someone other than those that perform or supervise the performance of the work/activity being inspected. | |||
1.2.5 CORPORA TE EXECUTIVES RESPONSIBLE FOR SUPPORT ORGANIZATIONS Corporate executives with responsibility for nuclear support activities shall assure that their assigned managers implement the QA Program, as applicable. | |||
1.2.5.1 PGE Corporate Managers of Nuclear Support Organizations Managers of nuclear support organizations that perform quality-related activities, such as records control services, are responsible for ensuring that procedures that implement the applicable portions of the QA Program are established, implemented, and maintained. | |||
At least biennially, the PGE corporate managers of nuclear support organizations shall review and document the status and adequacy of the parts of the QA Program they are executing and submit it to the ISRC and Corporate Executive Responsible for Trojan. | |||
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CORPORATE EXECUTIVE RESPONSIBLE FOR TROJAN I | |||
I I | |||
MANAGEMENT ADMINISTRATIVE ISFSI SAFETY REVI EW (OPTIONAL) | |||
COMMITTEE (ISRC) r- -- -- | |||
ISRC Member Responsible for I | |||
Managing Nuclear Oversight I | |||
I Resources | |||
: MANAGER, I | |||
ISFSI I | |||
NUCLEAR OVERSIGHT RESOURCES ISFSI STAFF I ISFSI STAFF PERSONNEL OR NUCLEAR OVERSIGHT RESOURCES WHEN PERFORMING AUDITS OF ISRC ACTIVITIES OR BIENNIAL AUDIT OF I | |||
CHAPTER 18 AUDITS I | |||
I CORPORATE OR CONTRACT SUPPORT Quality Assurance (limited to those activities that may be performed by ISFSI Staff per Section 1.2.42) | |||
Quality Control Radiation Protection Records Engineering Maintenance Security Licensing Environmental Purchasing Trojan ISFSI and QA Program Implementation Functional Organization Figure 1.0-1 1-6 Direct Indirect Revision 30 | |||
2.0 QUALITY ASSURANCE PROGRAM 2.1 PURPOSE Pursuant to 10 CFR 72.144 and 10 CFR 71.105, this chapter describes the QA Program for the ISFSI as specified in 10 CFR 72, Subpart G, and for radioactive material packaging and transportation activities as specified in 10 CFR 71, Subpart H. This chapter also defines the applicability of the QA Program including training necessary to assure its proper implementation and effectiveness. | |||
Pursuant to 10 CFR 72.144(e) and 71.105(d), the ISFSI Manager shall review the status and adequacy of the quality assurance program at established intervals. Management of other PGE departments participating in the Trojan quality assurance program must regularly review the status and adequacy of that part of the quality assurance program which they are executing and submit it to the ISRC and Corporate Executive Responsible for Trojan. | |||
2.2 QUALITY ASSURANCE PROGRAM 2.2.1 GENERAL The QA Program assures that the QA requirements for the ISFSI as specified in 10 CFR 72 and for radioactive material packaging and transportation activities as specified in 10 CFR 71 are satisfied. With regard to the ISFSI QA Program requirements of 10 CFR 72, the requirements of the QA Program apply to the design, fabrication, construction, testing, operation, modification, and decommissioning of the SSCs of the ISFSI that are important to safety, and to the managerial and administrative controls used to ensure safe operation of the ISFSI. Specific important-to-safety ISFSI SSCs and a detailed listing of quality-related activities are designated in and maintained in accordance with controlled procedure(s). These SSCs and activities governed by this QA Program, collectively referred to as "quality-related" items, are further described as follows: | |||
ISFSI SSCs classified as important to safety (ITS); | |||
Security Plan Implementing Procedures; Radiation Protection Program; Packaging radioactive material for transport pursuant to 10 CFR 71; Calibration of ISFSI monitoring instruments as specified in the ISFSI SAR; and Managerial and administrative controls to ensure safe operation of the ISFSI. | |||
With regard to the QA Program requirements of 10 CFR 71, the requirements of the QA Program apply to the procurement, maintenance, repair, and use of important-to-safety radioactive material packaging for transport as specified in 10 CFR 71 (NRC program 2-1 Revision 30 | |||
approval 71-0327). All other 10 CFR 71 activities (i.e., design, fabrication, assembly, testing, and modification of important-to-safety radioactive material packaging) are not performed by PGE, but rather are satisfied by obtaining certifications from packaging suppliers that these activities are conducted in accordance with an NRC-approved QA Program. | |||
The QA Program provides requirements for obtaining objective evidence that all SSCs classified as important to safety are in conformance with the design specifications, test specifications, and criteria established for the ISFSI and its components. Controls are established over activities affecting the quality of materials and components as necessary to ensure conformance to the approved design of the ISFSI (pursuant to 10 CFR 72 requirements), and of each individual package used for the transport ofradioactive material (pursuant to 10 CFR 71 requirements). | |||
QA requirements and procedures are based on the following considerations concerning the complexity and proposed use ofISFSI SSCs, and of the radioactive material transportation package and its components. | |||
(1) | |||
The impact of malfunction or failure of the item on safety; (2) | |||
The design and fabrication complexity or uniqueness of the item; (3) | |||
The need for special controls over and QA oversight of processes and equipment; | |||
( 4) | |||
The degree to which functional compliance can be demonstrated by inspection or test; and (5) | |||
The quality history and degree of standardization of the item. | |||
2.2.2 QUALITY-RELATED PROCEDURES Procedures cover quality-related aspects of administration and control-implemented by PGE, including the implementation of QA Program elements applicable to the ISFSI and to the use of packaging for radioactive material transportation pursuant to 10 CFR 71. The procedures document the policies and instructions necessary to fulfill the intent of the QA Program. They also include standard forms, lists, and checkoffs used in documenting the audits, inspections, certifications, and reviews. | |||
Where appropriate, the procedures assure that activities affecting quality are performed under suitably controlled conditions. Controlled conditions include the use of appropriate equipment, suitable environmental conditions for performing the activity, and adequate cleanliness, handling, and storage to assure that required prerequisites for the given activity have been satisfied. | |||
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2.2.3 TRAINING As detailed further in the Trojan ISFSI SAR, the training program provides for indoctrination and training of personnel performing quality-related activities as necessary to assure that suitable proficiency is achieved and maintained. | |||
2-3 Revision 30 | |||
3.0 DESIGN CONTROL 3.1 PURPOSE Pursuant to 10 CFR 72.146, this chapter describes controls to assure that ISFSI design requirements affecting quality-related items are correctly translated into ISFSI design documents. This chapter does not apply to packaging radioactive material for transport, since PGE is not authorized to and does not design 10 CFR 71 radioactive material transportation packages. | |||
3.2 GENERAL PGE does not perform design work affecting Trojan ISFSI SSCs classified as important to safety. Rather, all quality-related design work, including engineering calculations, design change control, and independent design verification, is performed by a qualified contracted design/engineering company under its own approved QA Program and procured in accordance with approved procedures and Chapters 4 and 7 of this QA Program. | |||
Pursuant to Trojan ISFSI Technical Specification 5.1.1, design changes shall be approved by the ISFSI Manager prior to implementation. Procedural measures are established to assure that proposed design changes received from contracted suppliers are evaluated to determine if a change to the ISFSI license is required, and that appropriate personnel are notified of design modifications that may affect the performance of their duties. | |||
3-1 Revision 28 | |||
4.0 PROCUREMENT DOCUMENT CONTROL 4.1 PURPOSE Pursuant to 10 CFR 72.148 and 10 CFR 71.109, this chapter describes the preparation, review, approval, and control of procurement documents pertaining to ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) quality-related items and services to assure the inclusion of applicable quality assurance requirements. | |||
4.2 PROCUREMENT DOCUMENT CONTROL PROGRAM Applicable procurement requirements for quality-related items and services are specified or referenced in procurement documents. Measures are established to assure that, to the extent necessary, contractors or subcontractors provide a QA Program consistent with the applicable provisions of 10 CFR 72, Subpart G. In addition, measures are established to assure that the applicable requirements of 10 CFR 71 are included or referenced in documents for procurement ofradioactive material packaging and/or associated services, and that packages and procedures for use of these packages have been authorized by the NRC and documented in the NRC Certificate of Compliance. | |||
Procurement requisitions and supplements thereto are reviewed for adequacy by personnel other than those that originated the requisition and/or supplements, and who are knowledgeable of QA practices and concepts. Nuclear Oversight resources may be consulted for quality assurance requirements in the procurement documents. | |||
Procurement documents are reviewed and approved by the ISFSI manager or his designee. | |||
Approved procurement documents are submitted to Corporate PGE purchasing or designee for procurement. | |||
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5.0 INSTRUCTIONS, PROCEDURES, AND DRAWINGS 5.1 PURPOSE Pursuant to 10 CFR 72.150 and 10 CFR 71.111, this chapter describes measures which will assure that activities affecting quality-related items and services associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) are delineated, controlled, implemented, and accomplished through utilization of approved and documented instructions, procedures, or drawings. | |||
5.2 INSTRUCTIONS, PROCEDURES, AND DRAWINGS Activities affecting quality shall be accomplished in accordance with approved and documented instructions, procedures, or drawings. Instructions and procedures that describe activities affecting quality include the necessary limits and tolerances on material, equipment, processes, and specifications for activities associated with quality-related items and services. Instructions and procedures also prescribe special controls, processes, test equipment, tools, and skills to attain the required quality, and requirements for documentation and/or verification of quality by inspection and test. Also included are appropriate qualitative and quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished. Nuclear Oversight resources may be consulted for quality assurance requirements in the instructions, procedures, and drawings. | |||
5-1 Revision 30 | |||
6.0 DOCUMENT CONTROL 6.1 PURPOSE Pursuant to 10 CFR 72.152 and 10 CFR 71.113, this chapter describes methods for review, approval, distribution, and control of documents and changes thereto which affect quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71 ). | |||
6.2 DOCUMENT CONTROL PROGRAM Written procedures are available which provide for the preparation, review, and approval of documents requiring control. | |||
These procedures identify the appropriate qualified individuals or groups responsible for determining that appropriate quantitative and qualitative criteria are included in documents describing quality-related activities and for verifying that these criteria have been satisfactorily met. Procedures also require that documents are approved for implementation by appropriate levels of management and changes to the documents are reviewed and approved by the same organizations as the original unless another responsible organization is designated by the governing procedure. Approved changes are included in controlled documents prior to implementation of the change. | |||
Procedures shall ensure that documents are distributed in a timely manner to appropriate locations and are available for use by personnel performing prescribed activities. | |||
Master lists or equivalent document control systems are established to identify the current revision of controlled documents. These lists are available for use by cognizant personnel to preclude the use of superseded documents. | |||
Quality-related procedures, including contractor procedures to be used onsite for quality-related work, are reviewed by personnel other than those that prepared the procedure or procedure revision, and who are knowledgeable of QA practices and concepts. Nuclear Oversight resources may be consulted for quality assurance requirements in such procedures. | |||
Temporary changes to quality-related documents may be made and implemented if a procedural method has been established to control the review and approval of the temporary changes. | |||
6-1 Revision 30 | |||
7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES 7.1 PURPOSE Pursuant to 10 CFR 72.154 and 10 CFR 71.115, this chapter describes the measures for selection and evaluation of procurement sources for quality-related items and services associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) and for verification activities to assure that specified requirements are met. | |||
7.2 QUALITY ASSURANCE PROGRAM EVALUATION PGE purchase orders/contracts for quality-related items or services are placed with contractors, suppliers, and service organizations who have been evaluated by designated Nuclear Oversight resource personnel for the applicable quality system level. Procedures govern the selection of procurement sources. | |||
The effectiveness of the control of quality by contractors and suppliers shall be assessed at intervals consistent with the importance, complexity, and quantity of the product or service. | |||
Quality-related items and services procured from a contractor, supplier, or service organization for which a quality assurance program is required but has not been reviewed or accepted may be utilized by PGE when additional compensatory controls such as source inspection, special receipt instructions, and/or testing are imposed. These additional controls shall be documented and approved by the ISFSI Manager. Nuclear Oversight resources may be consulted for the determination of such additional controls. | |||
7.2.1 SOURCE INSPECTION, SOURCE SURVEILLANCE, AND AUDIT OF CONTRACTORS AND SUPPLIERS OF QUALITY-RELATED ITEMS The designated Nuclear Oversight resource personnel or ISFSI staff personnel with appropriate qualifications are responsible for assuring source inspections, surveillances, or audits of suppliers are performed as necessary. | |||
7.3 RECEIPT INSPECTION Receipt inspection of quality-related items is performed to assure that the requirements of the procurement documents have been met. | |||
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Accepted items are appropriately marked, removed from the inspection area, and located in a controlled storage area until use. | |||
Documentary evidence that items conform to the procurement document requirements shall be available at the ISFSI site prior to installation or use. | |||
7-2 Revision 30 | |||
8.0 IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND COMPONENTS 8.1 PURPOSE Pursuant to 10 CFR 72.156 and 10 CFR 71.117, this chapter describes measures for the identification and control of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to assure they can be traced to associated documents and to prevent the use of incorrect or defective material, parts, and components. | |||
8.2 GENERAL Quality-related items and subassemblies are identified ( on the item or on records traceable to the item) in such a manner as to allow traceability to the appropriate quality documentation. The location and method of identification are selected to prevent affecting the function or quality of the item. | |||
When an item is subdivided, required identification markings will be transferred to each part or reflected in the records. | |||
When several parts are joined in fabrication, a list of parts and corresponding identification documents will accompany the assembly, as necessary. This documentation will include, as applicable, heat, lot, serial or part numbers, material certifications, weld or braze qualifications, test reports, NDE records, fabrication travelers, and other documentation to provide the bases for determining the acceptability of the assembly and its component parts. | |||
Proper identification of materials, parts, and components is verified and documented at receipt inspection or prior to release for fabrication, assembly, shipping, or installation. Nuclear Oversight resources may be consulted for determination of requirements associated with identification and control of materials, parts, and components. | |||
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9.0 CONTROL OF SPECIAL PROCESSES 9.1 PURPOSE Pursuant to 10 CFR 72.158, this chapter describes the methods for the control of special processes relative to quality-related items associated with the ISFSI (10 CFR 72). This chapter does not apply to radioactive material transportation packages, since PGE is not authorized to and does not fabricate 10 CFR 71 radioactive material transportation packages. | |||
9.2 SPECIAL PROCESS CONTROL PROGRAM PGE does not perform special processes involving Trojan ISFSI SSCs classified as important to safety. Rather, all quality-related special processes are performed by a qualified contracted company under its own approved QA Program and procured in accordance with approved procedures and Chapters 4 and 7 of this QA Program. | |||
9-1 Revision 28 | |||
10.0 INSPECTION 10.1 PURPOSE Pursuant to 10 CFR 72.160 and 10 CFR 71.121, this chapter establishes and describes the methods for the inspection of quality-related items and activities associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) to assure their acceptability. | |||
10.2 GENERAL Inspections are performed in accordance with written, approved inspection plans and/or inspection procedures, to verify that quality-related items and processes conform to documented instructions, procedures, and drawings for accomplishing the activity. | |||
Inspection programs are implemented through procedures which provide for preparation, review, and approval of inspection plans and procedures and provide for establishing mandatory hold points for witness by inspection. Inspection plans are approved by the ISFSI Manager or designee. Nuclear Oversight resources may be consulted for quality assurance requirements applicable to inspections. | |||
Inspections shall be performed by Nuclear Oversight resources or by qualified ISFSI Staff individuals other than those who performed or directly supervised the activity being inspected. | |||
If direct inspection of items is impossible or disadvantageous, indirect control by monitoring processing methods, equipment, and personnel shall be provided. Both inspection and process monitoring shall be provided when control is inadequate without both. | |||
10-1 Revision 30 | |||
11.0 TEST CONTROL 11.1 PURPOSE Pursuant to 10 CFR 72.162, this chapter describes the controls for testing required to demonstrate satisfactory performance of quality-related items associated with the ISFSI (10 CFR 72). This chapter does not apply to radioactive material transportation packages, since PGE is not authorized to and does not perform testing of 10.CFR 71 radioactive material transportation packages. | |||
Tests within the scope of this chapter include but are not limited to tests required by modifications and/or maintenance of SSCs classified as important to safety. These tests are performed to verify that an item will perform satisfactorily in service. | |||
11.2 TEST CONTROL PROGRAM 11.2.1 GENERAL The work package for maintenance or modifications to quality-related items identifies those tests necessary to demonstrate satisfactory performance of the affected equipment. | |||
Measures are established to assure that test procedures incorporate the applicable requirements of 10 CFR 72 and the acceptance limits contained in the ISFSI license. Each test procedure is prepared and reviewed in accordance with applicable design documents, codes, and specifications. Nuclear Oversight resources may be consulted for quality assurance requirements applicable to tests. | |||
The procedures shall include provisions for assuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions. | |||
11.2.2 TEST DOCUMENTATION Test results are documented, evaluated, and their acceptability determined by qualified personnel. | |||
11-1 Revision 30 | |||
12.0 CONTROL OF MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION 12.1 PURPOSE Pursuant to 10 CFR 72.164 and 10 CFR 71.125, this chapter describes the provisions for the control of portable measuring and testing equipment and installed instrumentation utilized in the inspection, testing (10 CFR 72 only), and monitoring of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71). | |||
12.2 MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION CONTROL PROGRAM 12.2.1 GENERAL PGE does not perform calibration of Trojan ISFSI installed instrumentation and/or portable measuring and test equipment. Rather, all quality-related calibration is performed by qualified contracted calibration facility(ies) under its/their own approved QA Program and procured in accordance with approved procedures and Chapters 4 and 7 of this QA Program. Instruments are calibrated at intervals consistent with the instrument manufacturer's guaranteed repeatability and the user's experience. | |||
The control of portable measuring and test equipment and installed instrumentation is implemented by specific procedures or instructions that describe calibration control and recall frequency requirements. Instruments, tools, gages, and fixtures used in quantitative measurement are uniquely identified, indicate calibration status, appear on a controlled list, are traceable to the national standards or natural constants, and are included in the calibration program. Nuclear Oversight resources may be consulted for quality assurance requirements associated with calibration of installed instrumentation and/or portable measuring and test equipment. | |||
12.2.2 DEFECTIVE OR OUT-OF-CALIBRATION MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION When portable measuring or test equipment or installed instrumentation is found to be out of calibration, out of tolerance, or when its repair or replacement is required, an investigation is conducted and documented to determine the validity of previous inspection or test results and to determine the acceptability of those items previously inspected or tested. | |||
12-1 Revision 30 | |||
13.0 HANDLING, STORAGE, AND SHIPPING 13.1 PURPOSE Pursuant to 10 CFR 72.166 and 10 CFR 71.127, this chapter describes measures for the control of the handling, storage, shipping, cleaning, and preservation of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to preclude damage, loss, or deterioration. | |||
13.2 HANDLING, STORAGE, SHIPPING, CLEANING, AND PRESERVATION PROGRAM 13.2.1 GENERAL On receipt of quality-related items, compliance with special requirements for protective environments is verified and documented by qualified personnel responsible for quality-related receipt inspection. | |||
Items are stored in a manner to protect against damage, degradation, or misuse. | |||
Quality-related items are handled, stored, preserved, or protected in accordance with codes and standards as specified in implementing procedures. Nuclear Oversight resources may be consulted for quality assurance requirements associated with receipt, handling, preservation, and protection of quality-related items. | |||
13.2.2 HANDLING OF QUALITY-RELATED ITEMS Procedures or instructions will be used to ensure that handling equipment, cranes, and rigging are examined and tested prior to performing critical lifts of quality-related items. | |||
13.2.3 HANDLING, STORAGE, AND 10 CFR 71 TRANSPORTATION OF RADIOACTIVE MATERIALS Personnel with specific radiation protection training and qualification are responsible for establishing administrative controls and requirements for handling, storing, and 10 CFR 71 packaging/transportation of radioactive materials. These requirements are established in implementing procedures. | |||
13-1 Revision 30 | |||
14.0 INSPECTION, TEST, AND OPERATING STATUS 14.1 PURPOSE Pursuant to 10 CFR 72.168 and 10 CFR 71.129, this chapter provides measures for the identification of the inspection, test, and operating status of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to preclude bypassing of requirements and inadvertent operation. | |||
14.2 INSPECTION, TEST, AND OPERATING STATUS PROGRAM 14.2.1 INSPECTION AND TEST STATUS Procedures are established to indicate the status of inspections and tests performed on quality-related items. | |||
ISFSI or other designated personnel are responsible for maintaining sufficient knowledge of tests or inspections in progress to control ISFSI and/or radioactive material transportation package activities. | |||
14.2.2 OPERATING STATUS The operating status of SSCs classified as important to safety that are found to have nonconformances is identified using tags, if appropriate, under the direction of ISFSI or other designated personnel to prevent inadvertent operation. Prior to the removal from service of SSCs classified as important to safety, ISFSI Manager permission to change status is given and documented in accordance with procedures to assure that the removal will not have an adverse effect on safe ISFSI operations. Nuclear Oversight resources may be consulted for quality assurance requirements associated with inspection, test, and operating status activities. | |||
14-1 Revision 30 | |||
15.0 NONCONFORMING MATERIAL, PARTS, OR COMPONENTS 15.1 PURPOSE Pursuant to 10 CFR 72.170 and 10 CFR 71.131, this chapter describes measures for documentation, control, and disposition of nonconforming quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to prevent their inadvertent use or installation. | |||
15.2 NONCONFORMING MATERIAL CONTROL PROGRAM 15.2.1 GENERAL Items that deviate from approved specifications, codes, drawings, or other applicable documents are considered as nonconforming. | |||
Procedures govern the use of nonconformance reports for identification, control, disposition of nonconforming items, and notification of affected organizations. | |||
Unless such controls are not feasible, nonconforming items are identified with appropriate tags and segregated to indicate their unacceptable status until the nonconformance is properly dispositioned. If this is not feasible, other methods are established to identify and control the nonconforming items. | |||
15.2.2 WORK PACKAGE A work package may be used in lieu of a nonconformance report in accordance with implementing procedures when nonconforming items are identified which can be restored to the original design requirements under a "rework" disposition. | |||
15.2.3 NONCONFORMANCE REPORT Trojan ISFSI management reviews and approves nonconformance report dispositions. Nuclear Oversight resources may be consulted for the review and disposition of nonconforming items. | |||
"Use as is" or "modify" dispositions require the review and approval of designated engineering support personnel. Tags associated with a nonconformance report are removed only by authorized personnel. | |||
15-1 Revision 30 | |||
16.0 CORRECTIVE ACTION 16.1 PURPOSE Pursuant to 10 CFR 72.172 and 10 CFR 71.133, this chapter describes the corrective action measures to assure that conditions adverse to quality associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) are identified, evaluated, and corrected. | |||
16.2 CORRECTIVE ACTION PROGRAM Procedures govern the use of corrective action requests (CARs) to assure that conditions adverse to quality are identified and corrected in a timely manner. | |||
Any individual has the authority and responsibility to report a condition adverse to quality to their manager or supervisor who will assure that it is or has been documented on a CAR. | |||
CARs documenting significant conditions adverse to quality require determination of cause and corrective actions taken to preclude repetition. Nuclear Oversight resources may be consulted for the identification, evaluation, and corrective actions particularly those applicable to significant conditions adverse to quality. | |||
Copies of CARs which identify significant conditions adverse to quality are distributed to appropriate levels of management for information and review. | |||
16-1 Revision 30 | |||
17.0 QUALITY ASSURANCE RECORDS 17.1 PURPOSE In accordance with 10 CFR 72.174 and 10 CFR 71.135, this chapter describes measures for the identification, retention, and retrievability of records associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) which furnish documentary evidence of the quality of items or activities affecting quality. | |||
17.2 QUALITY ASSURANCE RECORDS CONTROL PROGRAM PGE Corporate Manager for record control services is responsible for ensuring that procedures that implement the applicable portions of the Trojan QA Program are established, implemented, and maintained. | |||
In addition to the records required by the definition of Quality Assurance Records in the Glossary of this QA Program, ISFSI records required by 10 CFR 72.30, 72.48, 72.72, 72.80, 72.154, and 72.174 shall be maintained. ISFSI records pertaining to the design, fabrication, erection, testing, maintenance, and use of SSCs important to safety shall be maintained by or under the control of PGE for the applicable durations specified in 10 CFR 72. | |||
In addition to the records required by the definition of Quality Assurance Records in the Glossary of this QA Program, the records must include the instructions, procedures, and drawings required by 10 CFR 71.111. These records shall be retained for three years beyond the date when PGE last engages in 10 CFR 71 radioactive materials packaging and transportation. If any portion of the written procedures or instructions is superseded, PGE shall retain the superseded material for three years after it is superseded. | |||
Records should be identifiable to specific systems, structures, and components, when applicable. | |||
Documents which are designated as quality assurance records shall be legible, accurate, and completed as appropriate for the work accomplished. Records are indexed, including as a minimum retention times and location of the records within the record system, to provide for retrieval without undue delay. Nuclear Oversight resources may be consulted for the requirements associated with the control and management of quality records. | |||
Prior to final transmittal of quality assurance records to permanent storage, the originating organization shall be responsible for maintaining quality assurance record controls. | |||
17-1 Revision 30 | |||
The majority ofISFSI quality assurance records are ultimately scanned and stored as electronic images on two redundant, electronic media storage systems housed at two separate locations. | |||
Quality assurance records in electronic format (e.g.,.pdf format) may be directly filed and stored on the electronic media storage systems. Selected quality assurance records on other media ( e.g., | |||
paper hardcopies, microfilm, DVDs) are ultimately filed and maintained in a Permanent Records Storage Facility. | |||
17-2 Revision 30 | |||
18.0 AUDITS 18.1 PURPOSE In accordance with 10 CFR 72.176 and 10 CFR 71.137, this chapter describes the audit program utilized to verify the implementation, adequacy, and effectiveness of the QA Program for the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71). | |||
18.2 AUDIT PROGRAM 18.2.1 GENERAL Audit schedules are established to meet applicable regulatory requirements and are based on the safety importance of the activities to be audited. | |||
Audits shall be performed in accordance with written procedures using a check list or an annotated procedure which details the areas to be evaluated. | |||
Audit results shall be documented. These results shall be reviewed by management having responsibility in the area audited. | |||
Follow-up action, including re-audit of deficient areas, shall be taken where indicated. | |||
18.2.2 AUDIT PERSONNEL Auditors are appropriately trained and qualified to assure competence for performing the required audits. Nuclear Oversight resources have overall responsibility for performing planned and periodic audits of ISFSI activities. To ensure organizational independence, ISFSI Staff personnel shall not perform audits of ISFSI activities. External audits may be performed by either designated Nuclear Oversight resources or by properly qualified ISFSI Staff personnel. | |||
Similarly, Nuclear Oversight resources or appropriately trained and qualified ISFSI Staff personnel may perform audits ofISRC activities or the biennial audit of audits of the ISFSI performed by Nuclear Oversight resources pursuant to this chapter. To ensure organizational independence in the performance of these audits, the audit team members ultimately report directly to the Corporate Executive Responsible for Trojan. Audit teams must be comprised of individuals other than those that performed the ISRC activity or conducted the internal audit(s) being audited. | |||
18-1 Revision 30 | |||
GLOSSARY Audit: An activity which determines through investigation, review, and objective evidence, the adequacy of, and adherence to, established procedures, instructions, specifications, codes, standards, or other applicable contractual and licensing requirements, and the effectiveness of implementation. | |||
Calibration: The process by which measuring or test equipment is checked against standards of equal or higher accuracy and adjusted as necessary to assure its compliance with designated specifications. | |||
Conditions Adverse to Quality: Departures from specified quality-related requirements, such as failures, malfunctions, deficiencies, deviations, defective material or equipment, and nonconformances. | |||
Corrective Action: Action taken to correct conditions adverse to quality and to preclude repetition of significant conditions adverse to quality. | |||
Design Documents: Specifications, drawings, calculations, and analyses associated with design changes and modifications that define technical requirements. | |||
Documents Requiring Control: Documents requiring control contain written or pictorial information describing, defining, specifying, reporting, or certifying activities, requirements, procedures, or results. As a minimum, these include design specifications; procurement documents; drawings; QA Program; procedures; ISFSI Safety Analysis Report; manufacturing, inspection, maintenance, modification, design change and testing instructions; nonconformance reports; as-built packages; and other documentation affecting quality-related items. | |||
Examination: An element of inspection consisting of investigation of materials, components, supplies, and services to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gauging, and measurement. | |||
Identification: A means by which material, equipment, or parts can be traced to their associated quality documentation through the use of heat number, lot number, serial number, part number, purchase order nwnber, or other appropriate means. | |||
Gl-1 Revision 30 | |||
Inspection: An element of quality control which by means of examination, observation, or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes, or structures to predetermined quality requirements. | |||
Measuring and Test Equipment: Devices or systems used to calibrate, measure, gauge, test, or inspect in order to control or acquire data to verify conformance to specified requirements. | |||
Measuring and Test Equipment does not include permanently installed instrumentation nor does it include test equipment used for preliminary checks where data obtained will not be used to determine acceptability or verify conformance to established criteria. | |||
Modification: A planned change in facility design or operation accomplished in accordance with the requirements and limitations of applicable codes, standards, procedures, specifications, licenses, and predetermined safety restrictions. | |||
Modify (termed "repair" in ANSI N45.2.10): The disposition applied to nonconforming items which are restored to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original requirement. | |||
Nonconformance: A deficiency in characteristic, documentation, or procedure which renders the quality of an item or activity unacceptable or indeterminate. | |||
Out of Tolerance: see Tolerance below. | |||
Permanent Records Storage Facility: A Permanent Records Storage Facility is an environmentally controlled room or vault with controlled access which provides protection of quality assurance records from fire, theft, flood, and deterioration. | |||
Procedure: A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materials to be used, and sequence of operation. | |||
Procurement Documents: Those purchase requisitions, release letters, letters of intent, bid specifications, contracts, purchase orders, specifications, or other documents which provide contractual basis for procurement actions. They identify and define the requirements which items or services must meet in order to be acceptable to the purchaser. | |||
Purchased Services: Purchased services are services procured by PGE to support quality-related items. Examples include design analysis, evaluations, reviews, audits, calibration, and data reduction. | |||
Gl-2 Revision 30 | |||
Quality Assurance (QA): All those planned and systematic actions necessary to provide adequate confidence that an item or facility will perform satisfactorily in service. | |||
Quality Assurance Records: Those records which provide documentary evidence of the quality of items and/or activities affecting quality. A document is considered a QA record when the document is complete, valid, legible, and adequately identifiable to the item or activity involved. | |||
Documents shall be considered valid records only if stamped, initialed, signed, or otherwise authenticated and dated by authorized personnel. A record is completed when the final review signature or other authentication is placed on the document or on a documentation package containing multiple documents. QA records include the following: design records, records of use, and the results of reviews, inspections, tests, audits, monitoring of work performance, and materials analyses. The records must include closely related data such as qualifications of personnel, procedures, and equipment. Inspection and test records must, at a minimum, identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any noted deficiencies. The records must include the procedures that establish the records retention program. | |||
Quality Requirements: Quality requirements include, but are not limited to, such items as test, inspection, and acceptance criteria and any special instructions and prerequisites for such activities as designing, identification, fabrication, cleaning, erecting, packaging, handling, shipping, and extended storage. | |||
Radiation Protection: Radiological controls applied to radiation areas, radiation services, or radiation-producing machines consistent with the requirements of 10 CFR 19, 10 CFR 20, and 10 CFR 72. | |||
Reject: The disposition applied to nonconforming items which are unsuitable for their intended purpose, but which may be feasible to return to the supplier as salvage for replacement or credit, or feasible to scrap. | |||
Rework: The disposition applied to nonconforming items which are made to conform to a prior specified requirement by completion, remachining, reassembly, or other corrective means. | |||
Significant Condition Adverse to Quality: A departure from specified requirements is considered to be a significant condition adverse to quality if the condition appears to be an event which (1) requires reporting in 24 hours or less in accordance with the ISFSI License, 10 CFR 20, or 10 CFR 72.75; (2) requires reporting in accordance with 10 CFR 21 ; or (3) involves a significant breakdown in the QA Program implementation. | |||
Gl-3 Revision 30 | |||
Stop Work: The authority that permits immediate stoppage of quality-related activities such as design, procurement, fabrication, inspection, testing, or removal. | |||
Source Surveillance: A review, observation, or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture. (ANSI N.45.2.10) | |||
Testing: The determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, environmental, or operating conditions. | |||
Tolerance: Permitted deviation between the declared value of a quantity and the measured value. | |||
An "Out of Tolerance (OOT)" condition is typically identified by the entity evaluating the "as found" condition of the measuring and test equipment (M&TE) prior to calibration. (Based on ISO 17025) | |||
Use As Is: A disposition applied to nonconforming items which do not meet all specified requirements but do safely and reliably meet their intended purpose. | |||
Gl-4 Revision 30}} | |||
Revision as of 04:42, 26 June 2025
| ML21309A111 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 10/26/2021 |
| From: | Portland General Electric Co |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| VPN-006-2021 | |
| Download: ML21309A111 (37) | |
Text
ENCLOSURE Ill TO VPN-006-2021 PROPOSED REVISION 30 TO PGE-8010, "PORTLAND GENERAL ELECTRIC (PGE) NUCLEAR QUALITY ASSURANCE PROGRAM FOR TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (10 CFR 72) OPERATIONS AND RADIOACTIVE MATERIAL PACKAGING AND TRANSPORTATION (10 CFR 71) ACTIVITIES" (Copy of entire QA Program Containing Clean Version of the Proposed Revision 30 with Sidebars Annotated)
PORTLAND GENERAL ELECTRIC (PGE)
NUCLEAR QUALITY ASSURANCE PROGRAM FOR PGE-8010 TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (10 CFR 72)
OPERATIONS AND RADIOACTIVE MATERIAL PACKAGING AND TRANSPORTATION (10 CFR 71) ACTIVITIES Revision 30 Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204
PGE NUCLEAR QUALITY ASSURANCE PROGRAM FOR PGE-8010 TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (10 CFR 72)
OPERATIONS AND RADIOACTIVE MATERIAL PACKAGING AND TRANSPORTATION (10 CFR 71) ACTIVITIES Approval: ___ ______ ____ __ _
ISRC Member Responsible for Managing Nuclear Oversight Resources Approval: _______________ _
Corporate Executive Responsible for Trojan Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 11 Date Date Revision 30
TABLE OF CONTENTS TITLE PAGE................................................................................................................................... i AP PROV AL PAGE........................................................................................................................ ii TABLE OF CONTENTS............................................................................................................... iii LIST OF EFFECTIVE PAGES..................................................................................................... iv POLICY STATEMENT.................................................................................................................. v PROGRAM 1.0 ORGANIZATION...................................................................................................... 1 1-6 2.0 QUALITY ASSURANCE PROGRAM.....................................................................2 2-3 3.0 DESIGN CONTROL.......................................................................................................... 3-1 4.0 PROCUREMENT DOCUMENT CONTROL................................................................... 4-1 5.0 INSTRUCTIONS, PROCEDURES, AND DRAWINGS.................................................. 5-1 6.0 DOCUMENT CONTROL.................................................................................................. 6-1 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES..... 7 7-2 8.0 IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND COMPONENTS................................................................................................................. 8-1 9.0 CONTROL OF SPECIAL PROCESSES........................................................................... 9-1 10.0 INSPECTION................................................................................................................... 10-1 11.0 TEST CONTROL............................................................................................................. 11-1 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION.................................................................................................... 12-1 13.0 HANDLING, STORAGE, AND SHIPPING................................................................... 13-1 14.0 INSPECTION, TEST, AND OPERATING STATUS..................................................... 14-1 15.0 NONCONFORMING MATERIAL, PARTS, OR COMPONENTS............................... 15-1 16.0 CORRECTIVE ACTION................................................................................................. 16-1 17.0 QUALITY ASSURANCERECORDS................................................................... 17-1 2 18.0 AUDITS............................................................................................................................ 18-1 GLOSSARY................................................................................................................... Gl Gl-4 111 Revision 30
PGE NUCLEAR QUALITY ASSURANCE PROGRAM List of Effective Pages Page Revision i (title page) 30 11 30 111 30 lV 30 V
30 1-1 through 1-6 30 2-1 through 2-3 30 3-1 28 4-1 30 5-1 30 6-1 30 7-1 and 7-2 30 8-1 30 9-1 28 10-1 30 11-1 30 12-1 30 13-1 30 14-1 30 15-1 30 16-1 30 17-1 and 17-2 30 18-1 30 Gl-1 through Gl-4 30 lV Revision 30
PORTLAND GENERAL ELECTRIC COMPANY NUCLEAR QUALITY ASSURANCE PROGRAM POLICY STATEMENT Portland General Electric Company implements a Quality Assurance (QA) Program which directs quality-related activities at the Trojan Independent Spent Fuel Storage Installation (ISFSI).
This QA Program complies with and applies to Important-to-Safety activities conducted under Title 10, Code of Federal Regulations, Part 72, Subpart G, "Quality Assurance for Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste." These activities include managerial and administrative controls used to ensure safe operation of the ISFSI.
This QA Program also complies with and applies to Important-to-Safety activities conducted under 10 CFR 71, Subpart H, "Quality Assurance for Packaging and Transportation of Radioactive Material."
The approval of this document commits the Portland General Electric Company to the requirements of the QA Program described herein and its successful implementation. Portland General Electric Company personnel, authorized contractors and consultants who perform quality-related and/or Important-to-Safety functions are responsible for complying with the requirements of this QA Program.
Changes to the QA Program must be approved by the Nuclear Regulatory Commission, the ISFSI Safety Review Committee member assigned the management oversight function for Nuclear Oversight resources, and the Corporate Executive Responsible for Trojan prior to implementation.
V Corporate Executive Responsible for Trojan (Date)
Revision 30
1.0 ORGANIZATION
1.1 INTRODUCTION
Portland General Electric Company (PGE or Company), as a licensee under the purview of 10 CFR 72 and 10 CFR 71, is responsible for the establishment and execution of this Nuclear Quality Assurance Program (hereafter referred to as the QA Program) for activities conducted in support of the Trojan Independent Spent Fuel Storage Installation (ISFSI) that affect the functions of structures, systems, and components (SSCs) and conduct of services that are important to safety. These activities include managerial and administrative controls used to ensure safe operation of the ISFSI, as well as the performance of functions associated with assuring that the QA Program is effectively implemented. Pursuant to 10 CFR 72.142 and 10 CFR 71.103, the purpose of this chapter is to delineate the authorities, responsibilities, and interfaces of persons and organizations performing activities in support of spent fuel storage and/or radioactive material transport at the Trojan ISFSI that affect the functions of SSCs that are important to safety.
1.2 ASSIGNMENT OF FUNCTIONAL RESPONSIBILITIES Figure 1.0-1 illustrates the functional authorities, responsibilities, and interfaces of persons and organizations performing activities that are governed by and/or required to effectively implement the QA Program. The functional responsibilities indicated in Figure 1.0-1 are further described below.
1.2.1 CORPORA TE EXECUTIVE RESPONSIBLE FOR TROJAN The Corporate Executive Responsible for Trojan has overall authority and responsibility for nuclear safety at the facility, and is responsible for promulgating PGE's QA policies; maintaining a continuing involvement in QA matters; maintaining management controls for effectively implementing applicable QA Program elements; and resolution of disputes between organizational elements that may arise related to quality-related activities.
The ISFSI Manager and the ISFSI Safety Review Committee (ISRC) ultimately report to the Corporate Executive Responsible for Trojan. However, additional management positions may be appointed between the ISFSI Manager and the Corporate Executive Responsible for Trojan to provide additional organizational flexibility of administrative functions. The Corporate Executive Responsible for Trojan will remain the highest-level responsible manager for the implementation ofthis QA Program. The ISFSI Manager maintains overall responsibility for day-to-day ISFSI operations and has a direct line of communication to the Corporate Executive Responsible for Trojan regardless of the organization structure for all matters regarding 1-1 Revision 30
implementation of this QA Program. PGE employees, ISFSI Staff personnel and/or contractors, agents, or consultants providing Nuclear Oversight services, including establishing and/or implementing the QA Program, also ultimately report to the Corporate Executive Responsible for Trojan when conducting (1) audits ofISRC activities; and/or (2) the biennial audit of past QA audits ofISFSI activities that have been performed pursuant to Chapter 18 of this QA Program.
1.2.2 ISRC The ISRC performs review and audit functions as required by the ISFSI Safety Analysis Report, and advises the Corporate Executive Responsible for Trojan on matters relating to the safe storage of spent nuclear fuel. As the ISRC ultimately reports to the Corporate Executive Responsible for Trojan, ISRC review and audit functions are independent of the ISFSI line organization responsibilities.
With the exception of audits of ISRC activities and/or the biennial audit of past QA audits of ISFSI activities, which as indicated in Section 1.2.1 are the responsibility of the Corporate Executive Responsible for Trojan, the ISRC is responsible for ensuring the conduct of QA audits of ISFSI activities pursuant to Chapter 18 of this QA Program. The ISRC also ensures that the status and adequacy of QA Program implementation is assessed biennially. This assessment should include reviews of audits, inspections, and other sources of QA Program performance.
1.2.3 NUCLEAR OVERSIGHT Nuclear Oversight services are provided as needed by qualified PGE employees, contractors, agents, and/or consultants. These resources report directly to a designated ISRC Member as detailed below.
1.2.3.1 ISRC Member Responsible for Managing Nuclear Oversight Resources One ISRC Member ultimately reports to and is designated by the Corporate Executive Responsible for Trojan as the position having the authority and responsibility for maintaining and implementing the QA Program. This individual directs Nuclear Oversight resources in the overall implementation of the QA Program, including oversight and evaluation of work that is assigned to Nuclear Oversight resources to verify the adequate and effective implementation of the QA Program. The ISRC Member responsible for managing Nuclear Oversight resources, together with the Corporate Executive Responsible for Trojan, is responsible for approving revisions to the QA Program.
Nuclear Oversight resources report directly to this ISRC Member, unless the Nuclear Oversight resources are conducting audit(s) of ISRC activities or are conducting the biennial audit of Nuclear Oversight internal QA audit activities that have been performed pursuant to Chapter 18 1-2 Revision 30
ofthis QA Program. In these instances, the auditing resources report directly to the Corporate Executive Responsible for Trojan. This organizational structure ensures that persons assigned responsibility for assuring effective implementation of any portion of the QA Program (e.g., review and audit functions) have direct access to levels of management, and the required authority and organizational freedom, as necessary to perform required functions.
The ISRC Member responsible for managing Nuclear Oversight resources must be knowledgeable of the QA Program; 10 CPR 72, Subpart G; and 10 CPR 71, Subpart H, and maintain up-to-date knowledge of applicable regulatory guides, codes, and standards related to Trojan ISPSI QA. Qualifications of this individual must include eight years of experience in the field of QA or equivalent number of years of nuclear plant and/or fuel storage facility experience in a supervisory position or a combination of the two. Graduation from a four-year accredited engineering or science college or university may be substituted for four years of this experience.
At least one year of this experience shall be nuclear power plant and/or fuel storage facility experience in the implementation of an approved QA Program.
1.2.3.2 Nuclear Oversight Resources Nuclear Oversight resources include contractors, agents, 1 and/or consultants who are independent of the ISPSI line organization. The primary role of Nuclear Oversight resources is to conduct audits of ISPSI activities in accordance with Chapter 18 of this QA Program. These resources may also augment the ISPSI Staff in performance of other QA/QC activities, including the performance of audits of ISRC activities or the biennial audit of past QA audits of ISPSI activities that have been performed pursuant to Chapter 18 ofthis QA Program; source and receipt inspections, surveillances or audits of contractors and suppliers of quality-related items; QC inspections; and/or procurement document/record reviews.
Nuclear Oversight resources are under the management direction of the ISRC Member responsible for managing Nuclear Oversight resources, unless the Nuclear Oversight resources are conducting audit(s) ofISRC activities or are conducting the biennial audit of past QA audits ofISPSI activities that have been performed pursuant to Chapter 18 of this QA Program. In these instances, the auditing resources report directly to the Corporate Executive Responsible for Trojan. These auditing resources must be individuals other than those that performed the ISRC activity or conducted the internal audit(s) being audited.
With this organizational structure, Nuclear Oversight auditing resources are ensured to be independent of the Trojan ISPSI representatives performing quality-related activities. As such, Nuclear Oversight resources have the authority and independence to identify quality problems; initiate, recommend, or provide solutions to quality problems through designated channels; and 1 Agents may include PGE employees outside the Trojan ISFSI organization.
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verify implementation of solutions to quality problems. To control deviations from QA Program requirements, PGE personnel, ISFSI staff, contractors, agents, and/or consultants providing Nuclear Oversight services have the authority and responsibility to initiate stop work orders, as necessary, for any condition adverse to quality that has occurred or is developing.
Nuclear Oversight resources provides feedback and consultation to Trojan ISFSI staff inquiries regarding implementation of this QA Program.
1.2.3.3 Additional PGE Senior Management Administrative Support While the Corporate Executive Responsible for Trojan is ultimately responsible for the effective implementation of the QA Program at the Trojan ISFSI, additional Director or Manager positions may be appointed in the PGE corporate organizational structure between the ISFSI Manager and Corporate Executive which may provide additional administrative support to Trojan to provide organizational flexibility of administrative functions. In all cases, the ISFSI Manager maintains overall responsibility for day-to-day ISFSI operations.
1.2.4 ISFSI ORGANIZATION 1.2.4.1 ISFSI Manager The ISFSI Manager is responsible for the day-to-day implementation of the QA Program. The ISFSI Manager ultimately reports to the Corporate Executive Responsible for Trojan. However, additional management positions may be appointed between the ISFSI Manager and the Corporate Executive Responsible for Trojan to provide additional organizational flexibility of administrative functions. The ISFSI Manager maintains overall responsibility for day-to-day ISFSI operations and has a direct line of communication to the Corporate Executive Responsible for Trojan regardless of the organization structure for all matters regarding implementation of this QA Program.
At least biennially, the ISFSI Manager shall review and document the status and adequacy of the parts of the QA Program they are executing and submit it to the ISRC and Corporate Executive Responsible for Trojan.
1.2.4.2 ISFSI Staff The ISFSI Staff reports to the ISFSI Manager. Responsibilities, qualifications, and training required for ISFSI staff personnel performing quality-related activities are detailed in the Trojan ISFSI SAR and associated implementing procedures. ISFSI Staff personnel shall not be used to perform (Chapter 18) audits ofISFSI activities. Appropriately trained and qualified ISFSI Staff personnel (which may include corporate and/or contracted support personnel) may perform 1-4 Revision 30
audits of ISRC activities or the biennial audit of past QA audits of ISFSI activities that have been performed by Nuclear Oversight resources pursuant to Chapter 18 of this QA Program. In the performance of these audits, the ISFSI Staff audit personnel ultimately report to the Corporate Executive Responsible for Trojan. Audit teams must be comprised of individuals other than those that performed the ISRC activity or conducted the internal audit(s) being audited.
Appropriately trained PGE and ISFSI Staff personnel knowledgeable of QA/QC practices and concepts may also perform quality-related receipt inspections; source inspections, surveillances or audits of contractors and suppliers of quality-related items; QC inspections; and/or quality-related procurement document/record and procedure reviews. Individuals performing procurement document/record and/or procedure review activities must be someone other than those that originated the document/record or procedure revision being reviewed. Individuals performing inspection activities must be someone other than those that perform or supervise the performance of the work/activity being inspected.
1.2.5 CORPORA TE EXECUTIVES RESPONSIBLE FOR SUPPORT ORGANIZATIONS Corporate executives with responsibility for nuclear support activities shall assure that their assigned managers implement the QA Program, as applicable.
1.2.5.1 PGE Corporate Managers of Nuclear Support Organizations Managers of nuclear support organizations that perform quality-related activities, such as records control services, are responsible for ensuring that procedures that implement the applicable portions of the QA Program are established, implemented, and maintained.
At least biennially, the PGE corporate managers of nuclear support organizations shall review and document the status and adequacy of the parts of the QA Program they are executing and submit it to the ISRC and Corporate Executive Responsible for Trojan.
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CORPORATE EXECUTIVE RESPONSIBLE FOR TROJAN I
I I
MANAGEMENT ADMINISTRATIVE ISFSI SAFETY REVI EW (OPTIONAL)
COMMITTEE (ISRC) r- -- --
ISRC Member Responsible for I
Managing Nuclear Oversight I
I Resources
- MANAGER, I
ISFSI I
NUCLEAR OVERSIGHT RESOURCES ISFSI STAFF I ISFSI STAFF PERSONNEL OR NUCLEAR OVERSIGHT RESOURCES WHEN PERFORMING AUDITS OF ISRC ACTIVITIES OR BIENNIAL AUDIT OF I
CHAPTER 18 AUDITS I
I CORPORATE OR CONTRACT SUPPORT Quality Assurance (limited to those activities that may be performed by ISFSI Staff per Section 1.2.42)
Quality Control Radiation Protection Records Engineering Maintenance Security Licensing Environmental Purchasing Trojan ISFSI and QA Program Implementation Functional Organization Figure 1.0-1 1-6 Direct Indirect Revision 30
2.0 QUALITY ASSURANCE PROGRAM 2.1 PURPOSE Pursuant to 10 CFR 72.144 and 10 CFR 71.105, this chapter describes the QA Program for the ISFSI as specified in 10 CFR 72, Subpart G, and for radioactive material packaging and transportation activities as specified in 10 CFR 71, Subpart H. This chapter also defines the applicability of the QA Program including training necessary to assure its proper implementation and effectiveness.
Pursuant to 10 CFR 72.144(e) and 71.105(d), the ISFSI Manager shall review the status and adequacy of the quality assurance program at established intervals. Management of other PGE departments participating in the Trojan quality assurance program must regularly review the status and adequacy of that part of the quality assurance program which they are executing and submit it to the ISRC and Corporate Executive Responsible for Trojan.
2.2 QUALITY ASSURANCE PROGRAM 2.2.1 GENERAL The QA Program assures that the QA requirements for the ISFSI as specified in 10 CFR 72 and for radioactive material packaging and transportation activities as specified in 10 CFR 71 are satisfied. With regard to the ISFSI QA Program requirements of 10 CFR 72, the requirements of the QA Program apply to the design, fabrication, construction, testing, operation, modification, and decommissioning of the SSCs of the ISFSI that are important to safety, and to the managerial and administrative controls used to ensure safe operation of the ISFSI. Specific important-to-safety ISFSI SSCs and a detailed listing of quality-related activities are designated in and maintained in accordance with controlled procedure(s). These SSCs and activities governed by this QA Program, collectively referred to as "quality-related" items, are further described as follows:
ISFSI SSCs classified as important to safety (ITS);
Security Plan Implementing Procedures; Radiation Protection Program; Packaging radioactive material for transport pursuant to 10 CFR 71; Calibration of ISFSI monitoring instruments as specified in the ISFSI SAR; and Managerial and administrative controls to ensure safe operation of the ISFSI.
With regard to the QA Program requirements of 10 CFR 71, the requirements of the QA Program apply to the procurement, maintenance, repair, and use of important-to-safety radioactive material packaging for transport as specified in 10 CFR 71 (NRC program 2-1 Revision 30
approval 71-0327). All other 10 CFR 71 activities (i.e., design, fabrication, assembly, testing, and modification of important-to-safety radioactive material packaging) are not performed by PGE, but rather are satisfied by obtaining certifications from packaging suppliers that these activities are conducted in accordance with an NRC-approved QA Program.
The QA Program provides requirements for obtaining objective evidence that all SSCs classified as important to safety are in conformance with the design specifications, test specifications, and criteria established for the ISFSI and its components. Controls are established over activities affecting the quality of materials and components as necessary to ensure conformance to the approved design of the ISFSI (pursuant to 10 CFR 72 requirements), and of each individual package used for the transport ofradioactive material (pursuant to 10 CFR 71 requirements).
QA requirements and procedures are based on the following considerations concerning the complexity and proposed use ofISFSI SSCs, and of the radioactive material transportation package and its components.
(1)
The impact of malfunction or failure of the item on safety; (2)
The design and fabrication complexity or uniqueness of the item; (3)
The need for special controls over and QA oversight of processes and equipment;
( 4)
The degree to which functional compliance can be demonstrated by inspection or test; and (5)
The quality history and degree of standardization of the item.
2.2.2 QUALITY-RELATED PROCEDURES Procedures cover quality-related aspects of administration and control-implemented by PGE, including the implementation of QA Program elements applicable to the ISFSI and to the use of packaging for radioactive material transportation pursuant to 10 CFR 71. The procedures document the policies and instructions necessary to fulfill the intent of the QA Program. They also include standard forms, lists, and checkoffs used in documenting the audits, inspections, certifications, and reviews.
Where appropriate, the procedures assure that activities affecting quality are performed under suitably controlled conditions. Controlled conditions include the use of appropriate equipment, suitable environmental conditions for performing the activity, and adequate cleanliness, handling, and storage to assure that required prerequisites for the given activity have been satisfied.
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2.2.3 TRAINING As detailed further in the Trojan ISFSI SAR, the training program provides for indoctrination and training of personnel performing quality-related activities as necessary to assure that suitable proficiency is achieved and maintained.
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3.0 DESIGN CONTROL 3.1 PURPOSE Pursuant to 10 CFR 72.146, this chapter describes controls to assure that ISFSI design requirements affecting quality-related items are correctly translated into ISFSI design documents. This chapter does not apply to packaging radioactive material for transport, since PGE is not authorized to and does not design 10 CFR 71 radioactive material transportation packages.
3.2 GENERAL PGE does not perform design work affecting Trojan ISFSI SSCs classified as important to safety. Rather, all quality-related design work, including engineering calculations, design change control, and independent design verification, is performed by a qualified contracted design/engineering company under its own approved QA Program and procured in accordance with approved procedures and Chapters 4 and 7 of this QA Program.
Pursuant to Trojan ISFSI Technical Specification 5.1.1, design changes shall be approved by the ISFSI Manager prior to implementation. Procedural measures are established to assure that proposed design changes received from contracted suppliers are evaluated to determine if a change to the ISFSI license is required, and that appropriate personnel are notified of design modifications that may affect the performance of their duties.
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4.0 PROCUREMENT DOCUMENT CONTROL 4.1 PURPOSE Pursuant to 10 CFR 72.148 and 10 CFR 71.109, this chapter describes the preparation, review, approval, and control of procurement documents pertaining to ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) quality-related items and services to assure the inclusion of applicable quality assurance requirements.
4.2 PROCUREMENT DOCUMENT CONTROL PROGRAM Applicable procurement requirements for quality-related items and services are specified or referenced in procurement documents. Measures are established to assure that, to the extent necessary, contractors or subcontractors provide a QA Program consistent with the applicable provisions of 10 CFR 72, Subpart G. In addition, measures are established to assure that the applicable requirements of 10 CFR 71 are included or referenced in documents for procurement ofradioactive material packaging and/or associated services, and that packages and procedures for use of these packages have been authorized by the NRC and documented in the NRC Certificate of Compliance.
Procurement requisitions and supplements thereto are reviewed for adequacy by personnel other than those that originated the requisition and/or supplements, and who are knowledgeable of QA practices and concepts. Nuclear Oversight resources may be consulted for quality assurance requirements in the procurement documents.
Procurement documents are reviewed and approved by the ISFSI manager or his designee.
Approved procurement documents are submitted to Corporate PGE purchasing or designee for procurement.
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5.0 INSTRUCTIONS, PROCEDURES, AND DRAWINGS 5.1 PURPOSE Pursuant to 10 CFR 72.150 and 10 CFR 71.111, this chapter describes measures which will assure that activities affecting quality-related items and services associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) are delineated, controlled, implemented, and accomplished through utilization of approved and documented instructions, procedures, or drawings.
5.2 INSTRUCTIONS, PROCEDURES, AND DRAWINGS Activities affecting quality shall be accomplished in accordance with approved and documented instructions, procedures, or drawings. Instructions and procedures that describe activities affecting quality include the necessary limits and tolerances on material, equipment, processes, and specifications for activities associated with quality-related items and services. Instructions and procedures also prescribe special controls, processes, test equipment, tools, and skills to attain the required quality, and requirements for documentation and/or verification of quality by inspection and test. Also included are appropriate qualitative and quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished. Nuclear Oversight resources may be consulted for quality assurance requirements in the instructions, procedures, and drawings.
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6.0 DOCUMENT CONTROL 6.1 PURPOSE Pursuant to 10 CFR 72.152 and 10 CFR 71.113, this chapter describes methods for review, approval, distribution, and control of documents and changes thereto which affect quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71 ).
6.2 DOCUMENT CONTROL PROGRAM Written procedures are available which provide for the preparation, review, and approval of documents requiring control.
These procedures identify the appropriate qualified individuals or groups responsible for determining that appropriate quantitative and qualitative criteria are included in documents describing quality-related activities and for verifying that these criteria have been satisfactorily met. Procedures also require that documents are approved for implementation by appropriate levels of management and changes to the documents are reviewed and approved by the same organizations as the original unless another responsible organization is designated by the governing procedure. Approved changes are included in controlled documents prior to implementation of the change.
Procedures shall ensure that documents are distributed in a timely manner to appropriate locations and are available for use by personnel performing prescribed activities.
Master lists or equivalent document control systems are established to identify the current revision of controlled documents. These lists are available for use by cognizant personnel to preclude the use of superseded documents.
Quality-related procedures, including contractor procedures to be used onsite for quality-related work, are reviewed by personnel other than those that prepared the procedure or procedure revision, and who are knowledgeable of QA practices and concepts. Nuclear Oversight resources may be consulted for quality assurance requirements in such procedures.
Temporary changes to quality-related documents may be made and implemented if a procedural method has been established to control the review and approval of the temporary changes.
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7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES 7.1 PURPOSE Pursuant to 10 CFR 72.154 and 10 CFR 71.115, this chapter describes the measures for selection and evaluation of procurement sources for quality-related items and services associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) and for verification activities to assure that specified requirements are met.
7.2 QUALITY ASSURANCE PROGRAM EVALUATION PGE purchase orders/contracts for quality-related items or services are placed with contractors, suppliers, and service organizations who have been evaluated by designated Nuclear Oversight resource personnel for the applicable quality system level. Procedures govern the selection of procurement sources.
The effectiveness of the control of quality by contractors and suppliers shall be assessed at intervals consistent with the importance, complexity, and quantity of the product or service.
Quality-related items and services procured from a contractor, supplier, or service organization for which a quality assurance program is required but has not been reviewed or accepted may be utilized by PGE when additional compensatory controls such as source inspection, special receipt instructions, and/or testing are imposed. These additional controls shall be documented and approved by the ISFSI Manager. Nuclear Oversight resources may be consulted for the determination of such additional controls.
7.2.1 SOURCE INSPECTION, SOURCE SURVEILLANCE, AND AUDIT OF CONTRACTORS AND SUPPLIERS OF QUALITY-RELATED ITEMS The designated Nuclear Oversight resource personnel or ISFSI staff personnel with appropriate qualifications are responsible for assuring source inspections, surveillances, or audits of suppliers are performed as necessary.
7.3 RECEIPT INSPECTION Receipt inspection of quality-related items is performed to assure that the requirements of the procurement documents have been met.
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Accepted items are appropriately marked, removed from the inspection area, and located in a controlled storage area until use.
Documentary evidence that items conform to the procurement document requirements shall be available at the ISFSI site prior to installation or use.
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8.0 IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND COMPONENTS 8.1 PURPOSE Pursuant to 10 CFR 72.156 and 10 CFR 71.117, this chapter describes measures for the identification and control of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to assure they can be traced to associated documents and to prevent the use of incorrect or defective material, parts, and components.
8.2 GENERAL Quality-related items and subassemblies are identified ( on the item or on records traceable to the item) in such a manner as to allow traceability to the appropriate quality documentation. The location and method of identification are selected to prevent affecting the function or quality of the item.
When an item is subdivided, required identification markings will be transferred to each part or reflected in the records.
When several parts are joined in fabrication, a list of parts and corresponding identification documents will accompany the assembly, as necessary. This documentation will include, as applicable, heat, lot, serial or part numbers, material certifications, weld or braze qualifications, test reports, NDE records, fabrication travelers, and other documentation to provide the bases for determining the acceptability of the assembly and its component parts.
Proper identification of materials, parts, and components is verified and documented at receipt inspection or prior to release for fabrication, assembly, shipping, or installation. Nuclear Oversight resources may be consulted for determination of requirements associated with identification and control of materials, parts, and components.
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9.0 CONTROL OF SPECIAL PROCESSES 9.1 PURPOSE Pursuant to 10 CFR 72.158, this chapter describes the methods for the control of special processes relative to quality-related items associated with the ISFSI (10 CFR 72). This chapter does not apply to radioactive material transportation packages, since PGE is not authorized to and does not fabricate 10 CFR 71 radioactive material transportation packages.
9.2 SPECIAL PROCESS CONTROL PROGRAM PGE does not perform special processes involving Trojan ISFSI SSCs classified as important to safety. Rather, all quality-related special processes are performed by a qualified contracted company under its own approved QA Program and procured in accordance with approved procedures and Chapters 4 and 7 of this QA Program.
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10.0 INSPECTION 10.1 PURPOSE Pursuant to 10 CFR 72.160 and 10 CFR 71.121, this chapter establishes and describes the methods for the inspection of quality-related items and activities associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) to assure their acceptability.
10.2 GENERAL Inspections are performed in accordance with written, approved inspection plans and/or inspection procedures, to verify that quality-related items and processes conform to documented instructions, procedures, and drawings for accomplishing the activity.
Inspection programs are implemented through procedures which provide for preparation, review, and approval of inspection plans and procedures and provide for establishing mandatory hold points for witness by inspection. Inspection plans are approved by the ISFSI Manager or designee. Nuclear Oversight resources may be consulted for quality assurance requirements applicable to inspections.
Inspections shall be performed by Nuclear Oversight resources or by qualified ISFSI Staff individuals other than those who performed or directly supervised the activity being inspected.
If direct inspection of items is impossible or disadvantageous, indirect control by monitoring processing methods, equipment, and personnel shall be provided. Both inspection and process monitoring shall be provided when control is inadequate without both.
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11.0 TEST CONTROL 11.1 PURPOSE Pursuant to 10 CFR 72.162, this chapter describes the controls for testing required to demonstrate satisfactory performance of quality-related items associated with the ISFSI (10 CFR 72). This chapter does not apply to radioactive material transportation packages, since PGE is not authorized to and does not perform testing of 10.CFR 71 radioactive material transportation packages.
Tests within the scope of this chapter include but are not limited to tests required by modifications and/or maintenance of SSCs classified as important to safety. These tests are performed to verify that an item will perform satisfactorily in service.
11.2 TEST CONTROL PROGRAM 11.2.1 GENERAL The work package for maintenance or modifications to quality-related items identifies those tests necessary to demonstrate satisfactory performance of the affected equipment.
Measures are established to assure that test procedures incorporate the applicable requirements of 10 CFR 72 and the acceptance limits contained in the ISFSI license. Each test procedure is prepared and reviewed in accordance with applicable design documents, codes, and specifications. Nuclear Oversight resources may be consulted for quality assurance requirements applicable to tests.
The procedures shall include provisions for assuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions.
11.2.2 TEST DOCUMENTATION Test results are documented, evaluated, and their acceptability determined by qualified personnel.
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12.0 CONTROL OF MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION 12.1 PURPOSE Pursuant to 10 CFR 72.164 and 10 CFR 71.125, this chapter describes the provisions for the control of portable measuring and testing equipment and installed instrumentation utilized in the inspection, testing (10 CFR 72 only), and monitoring of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71).
12.2 MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION CONTROL PROGRAM 12.2.1 GENERAL PGE does not perform calibration of Trojan ISFSI installed instrumentation and/or portable measuring and test equipment. Rather, all quality-related calibration is performed by qualified contracted calibration facility(ies) under its/their own approved QA Program and procured in accordance with approved procedures and Chapters 4 and 7 of this QA Program. Instruments are calibrated at intervals consistent with the instrument manufacturer's guaranteed repeatability and the user's experience.
The control of portable measuring and test equipment and installed instrumentation is implemented by specific procedures or instructions that describe calibration control and recall frequency requirements. Instruments, tools, gages, and fixtures used in quantitative measurement are uniquely identified, indicate calibration status, appear on a controlled list, are traceable to the national standards or natural constants, and are included in the calibration program. Nuclear Oversight resources may be consulted for quality assurance requirements associated with calibration of installed instrumentation and/or portable measuring and test equipment.
12.2.2 DEFECTIVE OR OUT-OF-CALIBRATION MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION When portable measuring or test equipment or installed instrumentation is found to be out of calibration, out of tolerance, or when its repair or replacement is required, an investigation is conducted and documented to determine the validity of previous inspection or test results and to determine the acceptability of those items previously inspected or tested.
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13.0 HANDLING, STORAGE, AND SHIPPING 13.1 PURPOSE Pursuant to 10 CFR 72.166 and 10 CFR 71.127, this chapter describes measures for the control of the handling, storage, shipping, cleaning, and preservation of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to preclude damage, loss, or deterioration.
13.2 HANDLING, STORAGE, SHIPPING, CLEANING, AND PRESERVATION PROGRAM 13.2.1 GENERAL On receipt of quality-related items, compliance with special requirements for protective environments is verified and documented by qualified personnel responsible for quality-related receipt inspection.
Items are stored in a manner to protect against damage, degradation, or misuse.
Quality-related items are handled, stored, preserved, or protected in accordance with codes and standards as specified in implementing procedures. Nuclear Oversight resources may be consulted for quality assurance requirements associated with receipt, handling, preservation, and protection of quality-related items.
13.2.2 HANDLING OF QUALITY-RELATED ITEMS Procedures or instructions will be used to ensure that handling equipment, cranes, and rigging are examined and tested prior to performing critical lifts of quality-related items.
13.2.3 HANDLING, STORAGE, AND 10 CFR 71 TRANSPORTATION OF RADIOACTIVE MATERIALS Personnel with specific radiation protection training and qualification are responsible for establishing administrative controls and requirements for handling, storing, and 10 CFR 71 packaging/transportation of radioactive materials. These requirements are established in implementing procedures.
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14.0 INSPECTION, TEST, AND OPERATING STATUS 14.1 PURPOSE Pursuant to 10 CFR 72.168 and 10 CFR 71.129, this chapter provides measures for the identification of the inspection, test, and operating status of quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to preclude bypassing of requirements and inadvertent operation.
14.2 INSPECTION, TEST, AND OPERATING STATUS PROGRAM 14.2.1 INSPECTION AND TEST STATUS Procedures are established to indicate the status of inspections and tests performed on quality-related items.
ISFSI or other designated personnel are responsible for maintaining sufficient knowledge of tests or inspections in progress to control ISFSI and/or radioactive material transportation package activities.
14.2.2 OPERATING STATUS The operating status of SSCs classified as important to safety that are found to have nonconformances is identified using tags, if appropriate, under the direction of ISFSI or other designated personnel to prevent inadvertent operation. Prior to the removal from service of SSCs classified as important to safety, ISFSI Manager permission to change status is given and documented in accordance with procedures to assure that the removal will not have an adverse effect on safe ISFSI operations. Nuclear Oversight resources may be consulted for quality assurance requirements associated with inspection, test, and operating status activities.
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15.0 NONCONFORMING MATERIAL, PARTS, OR COMPONENTS 15.1 PURPOSE Pursuant to 10 CFR 72.170 and 10 CFR 71.131, this chapter describes measures for documentation, control, and disposition of nonconforming quality-related items associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) to prevent their inadvertent use or installation.
15.2 NONCONFORMING MATERIAL CONTROL PROGRAM 15.2.1 GENERAL Items that deviate from approved specifications, codes, drawings, or other applicable documents are considered as nonconforming.
Procedures govern the use of nonconformance reports for identification, control, disposition of nonconforming items, and notification of affected organizations.
Unless such controls are not feasible, nonconforming items are identified with appropriate tags and segregated to indicate their unacceptable status until the nonconformance is properly dispositioned. If this is not feasible, other methods are established to identify and control the nonconforming items.
15.2.2 WORK PACKAGE A work package may be used in lieu of a nonconformance report in accordance with implementing procedures when nonconforming items are identified which can be restored to the original design requirements under a "rework" disposition.
15.2.3 NONCONFORMANCE REPORT Trojan ISFSI management reviews and approves nonconformance report dispositions. Nuclear Oversight resources may be consulted for the review and disposition of nonconforming items.
"Use as is" or "modify" dispositions require the review and approval of designated engineering support personnel. Tags associated with a nonconformance report are removed only by authorized personnel.
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16.0 CORRECTIVE ACTION 16.1 PURPOSE Pursuant to 10 CFR 72.172 and 10 CFR 71.133, this chapter describes the corrective action measures to assure that conditions adverse to quality associated with the ISFSI (10 CFR 72) and/or radioactive material packaging and transportation (10 CFR 71) are identified, evaluated, and corrected.
16.2 CORRECTIVE ACTION PROGRAM Procedures govern the use of corrective action requests (CARs) to assure that conditions adverse to quality are identified and corrected in a timely manner.
Any individual has the authority and responsibility to report a condition adverse to quality to their manager or supervisor who will assure that it is or has been documented on a CAR.
CARs documenting significant conditions adverse to quality require determination of cause and corrective actions taken to preclude repetition. Nuclear Oversight resources may be consulted for the identification, evaluation, and corrective actions particularly those applicable to significant conditions adverse to quality.
Copies of CARs which identify significant conditions adverse to quality are distributed to appropriate levels of management for information and review.
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17.0 QUALITY ASSURANCE RECORDS 17.1 PURPOSE In accordance with 10 CFR 72.174 and 10 CFR 71.135, this chapter describes measures for the identification, retention, and retrievability of records associated with the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71) which furnish documentary evidence of the quality of items or activities affecting quality.
17.2 QUALITY ASSURANCE RECORDS CONTROL PROGRAM PGE Corporate Manager for record control services is responsible for ensuring that procedures that implement the applicable portions of the Trojan QA Program are established, implemented, and maintained.
In addition to the records required by the definition of Quality Assurance Records in the Glossary of this QA Program, ISFSI records required by 10 CFR 72.30, 72.48, 72.72, 72.80, 72.154, and 72.174 shall be maintained. ISFSI records pertaining to the design, fabrication, erection, testing, maintenance, and use of SSCs important to safety shall be maintained by or under the control of PGE for the applicable durations specified in 10 CFR 72.
In addition to the records required by the definition of Quality Assurance Records in the Glossary of this QA Program, the records must include the instructions, procedures, and drawings required by 10 CFR 71.111. These records shall be retained for three years beyond the date when PGE last engages in 10 CFR 71 radioactive materials packaging and transportation. If any portion of the written procedures or instructions is superseded, PGE shall retain the superseded material for three years after it is superseded.
Records should be identifiable to specific systems, structures, and components, when applicable.
Documents which are designated as quality assurance records shall be legible, accurate, and completed as appropriate for the work accomplished. Records are indexed, including as a minimum retention times and location of the records within the record system, to provide for retrieval without undue delay. Nuclear Oversight resources may be consulted for the requirements associated with the control and management of quality records.
Prior to final transmittal of quality assurance records to permanent storage, the originating organization shall be responsible for maintaining quality assurance record controls.
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The majority ofISFSI quality assurance records are ultimately scanned and stored as electronic images on two redundant, electronic media storage systems housed at two separate locations.
Quality assurance records in electronic format (e.g.,.pdf format) may be directly filed and stored on the electronic media storage systems. Selected quality assurance records on other media ( e.g.,
paper hardcopies, microfilm, DVDs) are ultimately filed and maintained in a Permanent Records Storage Facility.
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18.0 AUDITS 18.1 PURPOSE In accordance with 10 CFR 72.176 and 10 CFR 71.137, this chapter describes the audit program utilized to verify the implementation, adequacy, and effectiveness of the QA Program for the ISFSI (10 CFR 72) and/or radioactive material transportation packages (10 CFR 71).
18.2 AUDIT PROGRAM 18.2.1 GENERAL Audit schedules are established to meet applicable regulatory requirements and are based on the safety importance of the activities to be audited.
Audits shall be performed in accordance with written procedures using a check list or an annotated procedure which details the areas to be evaluated.
Audit results shall be documented. These results shall be reviewed by management having responsibility in the area audited.
Follow-up action, including re-audit of deficient areas, shall be taken where indicated.
18.2.2 AUDIT PERSONNEL Auditors are appropriately trained and qualified to assure competence for performing the required audits. Nuclear Oversight resources have overall responsibility for performing planned and periodic audits of ISFSI activities. To ensure organizational independence, ISFSI Staff personnel shall not perform audits of ISFSI activities. External audits may be performed by either designated Nuclear Oversight resources or by properly qualified ISFSI Staff personnel.
Similarly, Nuclear Oversight resources or appropriately trained and qualified ISFSI Staff personnel may perform audits ofISRC activities or the biennial audit of audits of the ISFSI performed by Nuclear Oversight resources pursuant to this chapter. To ensure organizational independence in the performance of these audits, the audit team members ultimately report directly to the Corporate Executive Responsible for Trojan. Audit teams must be comprised of individuals other than those that performed the ISRC activity or conducted the internal audit(s) being audited.
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GLOSSARY Audit: An activity which determines through investigation, review, and objective evidence, the adequacy of, and adherence to, established procedures, instructions, specifications, codes, standards, or other applicable contractual and licensing requirements, and the effectiveness of implementation.
Calibration: The process by which measuring or test equipment is checked against standards of equal or higher accuracy and adjusted as necessary to assure its compliance with designated specifications.
Conditions Adverse to Quality: Departures from specified quality-related requirements, such as failures, malfunctions, deficiencies, deviations, defective material or equipment, and nonconformances.
Corrective Action: Action taken to correct conditions adverse to quality and to preclude repetition of significant conditions adverse to quality.
Design Documents: Specifications, drawings, calculations, and analyses associated with design changes and modifications that define technical requirements.
Documents Requiring Control: Documents requiring control contain written or pictorial information describing, defining, specifying, reporting, or certifying activities, requirements, procedures, or results. As a minimum, these include design specifications; procurement documents; drawings; QA Program; procedures; ISFSI Safety Analysis Report; manufacturing, inspection, maintenance, modification, design change and testing instructions; nonconformance reports; as-built packages; and other documentation affecting quality-related items.
Examination: An element of inspection consisting of investigation of materials, components, supplies, and services to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gauging, and measurement.
Identification: A means by which material, equipment, or parts can be traced to their associated quality documentation through the use of heat number, lot number, serial number, part number, purchase order nwnber, or other appropriate means.
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Inspection: An element of quality control which by means of examination, observation, or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes, or structures to predetermined quality requirements.
Measuring and Test Equipment: Devices or systems used to calibrate, measure, gauge, test, or inspect in order to control or acquire data to verify conformance to specified requirements.
Measuring and Test Equipment does not include permanently installed instrumentation nor does it include test equipment used for preliminary checks where data obtained will not be used to determine acceptability or verify conformance to established criteria.
Modification: A planned change in facility design or operation accomplished in accordance with the requirements and limitations of applicable codes, standards, procedures, specifications, licenses, and predetermined safety restrictions.
Modify (termed "repair" in ANSI N45.2.10): The disposition applied to nonconforming items which are restored to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original requirement.
Nonconformance: A deficiency in characteristic, documentation, or procedure which renders the quality of an item or activity unacceptable or indeterminate.
Out of Tolerance: see Tolerance below.
Permanent Records Storage Facility: A Permanent Records Storage Facility is an environmentally controlled room or vault with controlled access which provides protection of quality assurance records from fire, theft, flood, and deterioration.
Procedure: A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materials to be used, and sequence of operation.
Procurement Documents: Those purchase requisitions, release letters, letters of intent, bid specifications, contracts, purchase orders, specifications, or other documents which provide contractual basis for procurement actions. They identify and define the requirements which items or services must meet in order to be acceptable to the purchaser.
Purchased Services: Purchased services are services procured by PGE to support quality-related items. Examples include design analysis, evaluations, reviews, audits, calibration, and data reduction.
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Quality Assurance (QA): All those planned and systematic actions necessary to provide adequate confidence that an item or facility will perform satisfactorily in service.
Quality Assurance Records: Those records which provide documentary evidence of the quality of items and/or activities affecting quality. A document is considered a QA record when the document is complete, valid, legible, and adequately identifiable to the item or activity involved.
Documents shall be considered valid records only if stamped, initialed, signed, or otherwise authenticated and dated by authorized personnel. A record is completed when the final review signature or other authentication is placed on the document or on a documentation package containing multiple documents. QA records include the following: design records, records of use, and the results of reviews, inspections, tests, audits, monitoring of work performance, and materials analyses. The records must include closely related data such as qualifications of personnel, procedures, and equipment. Inspection and test records must, at a minimum, identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any noted deficiencies. The records must include the procedures that establish the records retention program.
Quality Requirements: Quality requirements include, but are not limited to, such items as test, inspection, and acceptance criteria and any special instructions and prerequisites for such activities as designing, identification, fabrication, cleaning, erecting, packaging, handling, shipping, and extended storage.
Radiation Protection: Radiological controls applied to radiation areas, radiation services, or radiation-producing machines consistent with the requirements of 10 CFR 19, 10 CFR 20, and 10 CFR 72.
Reject: The disposition applied to nonconforming items which are unsuitable for their intended purpose, but which may be feasible to return to the supplier as salvage for replacement or credit, or feasible to scrap.
Rework: The disposition applied to nonconforming items which are made to conform to a prior specified requirement by completion, remachining, reassembly, or other corrective means.
Significant Condition Adverse to Quality: A departure from specified requirements is considered to be a significant condition adverse to quality if the condition appears to be an event which (1) requires reporting in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less in accordance with the ISFSI License, 10 CFR 20, or 10 CFR 72.75; (2) requires reporting in accordance with 10 CFR 21 ; or (3) involves a significant breakdown in the QA Program implementation.
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Stop Work: The authority that permits immediate stoppage of quality-related activities such as design, procurement, fabrication, inspection, testing, or removal.
Source Surveillance: A review, observation, or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture. (ANSI N.45.2.10)
Testing: The determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, environmental, or operating conditions.
Tolerance: Permitted deviation between the declared value of a quantity and the measured value.
An "Out of Tolerance (OOT)" condition is typically identified by the entity evaluating the "as found" condition of the measuring and test equipment (M&TE) prior to calibration. (Based on ISO 17025)
Use As Is: A disposition applied to nonconforming items which do not meet all specified requirements but do safely and reliably meet their intended purpose.
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