ML052560326

Quality Assurance Topical Report, NO-AA-10, Revision 76

ML052560326
Person / Time
Site:	Limerick
Issue date:	09/07/2005
From:	AmerGen Energy Co, Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NO-AA-10, Rev 76
Download: ML052560326 (160)

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am* CMOr I cmnZrvn Exelon Generation Company, LLC AmerGen Energy Company, LLC QUALITY ASSURANCE TOPICAL REPORT (QATR)

NO-AA-10 Revision 76 Exelon Nuclear Corporate Headquarters 4300 Winfield Road Warrenville, IL 60555

/

Standard Quality Assurance Topical Report (NO-AA-10)- Revision 76 Transmittal and Summary of Changes To: All Site Document Control Centers The Quality Assurance Topical Report (QATR) has been revised to relocate Limerick Technical Specification administrative requirements with respect to the Plant Operations Review Committee (PORC) and Nuclear Review Board (NRB), the program/procedure review and approval requirements, and the record retention requirements into the appropriate locations in the QATR. In addition, ANSI N18.1 - 1971 was added to Appendix C because previous versions of Appendix C did not identify ANSI N18.1 -1971 as a quality standard even though sites such as Byron and Braidwood are committed to it for certain aspects of the training and qualification program. Other minor editorial changes such as a clarification with respect to the definition of audit" were also incorporated. These changes do not change or modify any commitments previously approved by the NRC.

The specific changes are as follows:

Several sections of the QATR were revised to facilitate the relocation of several Limerick requirements. The NRC approved a request by Limerick Generating Station, Units 1 & 2 (Reference TAC Nos.

MC2739 and MC2740) to relocate administrative requirements from the Technical Specifications into the Quality Assurance Topical Report (QATR). To perform this relocation, the Commission issued Amendment no. 176 to Facility Operating License No. NPF-39 and Amendment no. 138 to Facility Operating License No. NPF-85 for the Limerick Generating Station, Units 1 & 2. These amendments relocate several Technical Specifications (TSs) from Section 6, 'Administrative Controls" to the QATR. Specifically the amendments relocate the Plant Operations Review Committee (PORC) and Nuclear Review Board (NRB) requirements, the program/procedure review and approval requirements, and the record retention requirements. (this relocation was being performed consistent with the rules stipulated in NRC Administrative Letter no. 95-06 which addresses the relocation of Tech Spec administrative requirements to the licensee quality assurance program). This relocation resulted in the following revisions to the QATR:

o Chapter 1 - Added Limerick specific paragraph no. 2.7 to relocate PORC and NRB administrative requirements from the Limerick Tech Specs to the QATR Page 1 of 3

Standard Quality Assurance Topical Report (NO-AA-10)- Revision 76 Transmittal and Summary of Changes o Chapter 5 - Added Limerick specific paragraph no. 2.4 to relocate Program/Procedure Review and Approval requirements from the Limerick Tech Specs to the QATR o Chapter 17 - Added Limerick specific paragraph no. 2.8 to relocate Record Retention requirements from the Limerick Tech Specs to the QATR Appendix A paragraph no. 2.8.3 was revised to include a description of the quality assurance program for the Quad Cities ISFSI SSCs. The requirements duplicate current QA program requirements for Dresden Station. Quad Cities SSCs associated with the ISFSI are categorized as Category A, B, or C in accordance with NUREG/CR-6407, "Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety."

Appendix C, Paragraph no. 1.1 was revised to state that the Exelon Nuclear Quality Assurance Program (QAP) complies with the Training and Qualification requirements of three (3) different versions of the applicable ANSI standard as noted in the site specific UFSAR on a site by site basis.

- ANSI N18.1 -.1971, 'Selection and Training of Nuclear Power Plant Personnel"

- ANSI / ANS 3.1 -1978, 'American National Standard for Selection and Training of Nuclear Power Plant Personnel"

- ANSI /ANS 3.1 -1981, "Selection, Qualification and Training of personnel for Nuclear Power Plants" Previous versions of Appendix C did not identify ANSI N18.1 -1971 as a quality standard even though sites such as Byron and Braidwood are committed to it for certain aspects of the training and qualification program.

Appendix D revised the definition of the term audit to delete that portion of the definition which stated that the term audit was synonymous with 'assessment". This revision results in a consistent definition of the term audit with respect to the QATR, the assessment procedure and the audit procedure. The phrase that implied that audit was synonymous with "assessment" was eliminated from the QATR in a revision to chapter 18 that occurred during revision 73 of the QATR.

Page 2 of 3

Standard Quality Assurance Topical Report (NO-AA-10)- Revision 76 Transmittal and Summary of Changes Q-y( = > a_

Ronald C. Washington / Date Nuclear Oversight Evaluator

,g/2 V/a; 25 Approved By: Nuclear Oversight and Programs Director Page 3of3

EXELON NUCLEAR POLICY EXELON NUCLEAR POLICY POLICY STATEMENT The Quality Assurance Topical Report (QATR), NO-AA-10, is the highest tiered document that assigns major functional responsibilities for either plants owned or operated by Exelon Generation Company, LLC and AmerGen Energy Company, LLC (AmerGen) collectively. Implementing documents assign more specific responsibilities and tasks and define the organizational interfaces involved in conducting activities and tasks within the scope of this Plan. These requirements apply to those organizations and positions, which manage and perform activities within its scope.

The Company organization is structured on the basis that the attainment of the objectives of this Plan relies on those who manage, perform, and support the performance of activities within the scope of this plan. Assurance of this attainment relies on those who have no direct responsibility for managing or performing the activity.

The Company will maintain and operate its nuclear plants in a manner that will ensure the health and safety of the public and our workers. All facilities shall be at a minimum compliance with the requirements on the Code of Federal Regulations, NRC Operating Licenses, and the applicable laws and regulations of the state and local governments.

2. APPLICABILITY All Company personnel who work directly, or indirectly, for the Company are responsible for the achievement of quality in their work. Accordingly, all Company personnel and its contractors engaged in supporting nuclear generation activities shall comply with the requirements of our Quality Assurance Program (QAP).

Revision 76 Page 1 Page of II I of Revision 76

TABLE OF CONTENTS CHAPTER 1, ORGANIZATION

1. SCOPE ............. 1

2. REQUIREMENTS ........... 1 2.1. Organization.......................................................................................................1 2.2. Corporate Organization ................................................. 1 2.2.1. Chairman and Chief Executive Officer ................................................. 2 2.2.2. President, Exelon Generation Company [Exelon Corporation] ........................... 2 2.2.3. President and Chief Nuclear Officer [President & Chief Nuclear Officer -

Amergen] ............................... 2 2.3. Site Organization ................................ 7 2.4. Decommissioning Site Organization ............................... 11 2.4.1. Dresden Unit 1............................... 11 2.4.2. Zion ............................... 12 2.5. Responsibility ............................... 12 2.6. Authority ............................... 12 2.7. Review and Audit (Limerick Specific Only)............................... 13 CHAPTER 2, QUALITY ASSURANCE PROGRAM

1. SCOPE ............ 1

2. REQUIREMENTS ............. 1 2.1. General ............................... 1 2.2. Supplier's Quality Assurance Program ............................... 1 2.3. Planning ............................... 2 2.4. Program Description ............................... 2 2.5. Indoctrination & Training ............................... 2 2.6. Program Review ............................... 3 2.7. Quality Assurance Manual ............................... 3 CHAPTER 3, DESIGN CONTROL

1. SCOPE ............................... 1

2. REQUIREMENTS....................................................................................................1 2.1 General ............................... 1 2.2 Design Input ............................... 1 2.3 Design Process ............................... 2 2.4 Design Analyses ............................... 2 2.5 Design Verification ............................... 3 2.5.1 Extent of Design Verification ............................... 3 2.5.2 Design Reviews ............................... 4 Page 1 of 8 Revision 76

TABLE OF CONTENTS 2.6 Change Control .................................................... 4 2.7 Design Errors .................................................... 5 2.8 Interface Control .................................................... 5 2.9 Vendor Design Control ....................................................5 2.10 Modifications ................................................... 6 2.11 Documentation and Records ....................................................6 CHAPTER 4, PROCUREMENT DOCUMENT CONTROL

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. General ................................ 1 2.2. Content of Procurement Documents ................................ 1 2.2.1. Scope of Work ................................ 1 2.2.2. Technical Requirements ................................ 1 2.2.3. Quality Assurance Program Requirements ................................ 1 2.2.4. Non-conformances ............................... 2 2.2.5. Documentation Requirements ............................... 2 2.2.6. Spare and Replacement Parts ................................ 2 2.3. Procurement Document Review ................................ 2 2.4. Procurement Records ................................ 3 CHAPTER 5, INSTRUCTIONS, PROCEDURES, AND DRAWINGS

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. General .................................................... 1 2.2. Preparation and Review .................................................... 1 2.3. Procedures and Programs .................................................... 2 2.3.1. Technical Review and Control .................................................... 2 2.3.2. On-site Qualified Technical Review (Dresden Unit 1) ....................................... 4 2.4 Program/ Procedure Review and Approval (Limerick Specific Only) .............. 5 CHAPTER 6, DOCUMENT CONTROL

1. SCOPE ............ 1

2. REQUIREMENTS ............. 1 2.1. General ................ 1 2.2. Reviews..............................................................................................................1 2.3. Controlled Documents ................ 2 2.4. Control Measures ................ 2 2.5. Document Changes ................ 3 Page 2 of 8 Revision 76

TABLE OF CONTENTS CHAPTER 7, CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES 1.SCOPE ........... 1 2 .REQUIREMENTS ............. 1 2.1. Supplier Selection .............................................. 1 2.1.1. General .............................................. 1 2.1.2. Methods .............................................. 1 2.2. Bid Evaluations .............................................. 2 2.3. Supplier In-Process Control .............................................. 2 2.3.1. General .............................................. 2 2.3.2. In-Process Control and Verification Planning .............................................. 2 2.3.3. Programmatic Verification .............................................. 3 2.3.4. Supplier and Verification of Supplier Performance Records ............................... 3 2.3.5. Control of Procurement Changes .............................................. 3 2.4. Acceptance of Purchased Items and Services .............................................. 4 2.4.1. General .............................................. 4 2.4.2. Acceptance by Receiving Inspection .............................................. 4 2.4.3. Acceptance by Source Verification .............................................. 4 2.4.4. Acceptance by Certificate of Conformance........................................................5 2.4.5. Acceptance by Post Installation Testing .............................................. 5 2.4.6. Acceptance of Services Only .............................................. 5 2.4.7. Commercial Grade Items .............................................. 6 2.5. Presence of Documentary Evidence .............................................. 6 2.6. Spare or Replacement Items .............................................. 7 2.6.1. Procurement from Other Utilities .............................................. 7 2.6.2. Maintenance or Modification .............................................. 7 CHAPTER 8, IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS 1.SCOPE ............ 1 2.REQUIREMENTS ............. 1 2.1. General ................ 1 2.2. Traceability.........................................................................................................1 2.3. Identification Methods ................ 1 2.4. Transfer of Markings ................ 2 2.5. Limited Life Items ................ 2 2.6. Stored Items ................ 2 Page 3 of 8 Revision 76

TABLE OF CONTENTS CHAPTER 9, CONTROL OF SPECIAL PROCESSES

1. SCOPE ............ 1

2. REQUIREMENTS ............. 1 2.1. General ................................ 1 2.2. Process Control ................................ 1 2.3. Special Processes .................. 1:

1 2.4. Personnel Qualification ................... 2 2.5. Special Process Records ................... 3 CHAPTER 10, INSPECTION

1. SCOPE ............ 1

2. REQUIREMENTS ............. 1 2.1. General ............................. 1 2.2. Inspection Plans ............................. 1 2.3. Inspection Personnel and Qualification ............................. 2 2.4. Inspection Process ............................. 2 2.5. In-Service Inspections ............................. 3 2.6. Independent Verification ............................. 3 CHAPTER 11, TEST CONTROL

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. General ................................ 1 2.1.1. Testing Program .... 1.....................

2.1.2. Test Procedures ................................ 1 2.2. Instrumentation and Control ................................ 4 2.3. Electrical Tests ................................ 5 2.4. Mechanical Tests .... 5.....................

2.5. Physical and Chemical Tests ............................... 5 2.6. Surveillance Tests ............................... 6 2.7. Maintenance or Major Procedure Change ................................ 6 CHAPTER 12, CONTROL OF MEASURING AND TEST EQUIPMENT

1. SCOPE ............ 1

2. REQUIREMENTS ............ I1 2.1. General .

2.2. Control................................................................................................................1 2.3. Labeling..............................................................................................................2 Page 4 of 8 Revision 76

- W TABLE OF CONTENTS 2.4. Accuracy .............................. 2 2.5. Traceability and Interval .............................. 2 2.6. Certified M&TE .............................. 2 2.7. Corrective Actions .............................. 3 2.8. Vendor Control .............................. 3 2.9. Commercial Devices ............................. 3 2.10. Calibration Records .............................. 3 CHAPTER 13, HANDLING, STORAGE, AND SHIPPING

1. SCOPE ............ 1

2. REQUIREMENTS ............. 1 2.1. General ... 1...................

2.2. Special Equipment and Environments .............................. 1 2.3. Classification of Items .............................. 1 2.4. Special Handling Tools and Equipment .............................. 2 2.5. Marking and Labeling .............................. 2 2.6. Storage...............................................................................................................2 CHAPTER 14, INSPECTION, TEST, AND OPERATING STATUS

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. General ................... 1 2.1.1. Procedures ................... 2 2.2. Operating Status ................... 2 2.2.1. Release for Maintenance ................... 2 2.2.2. Preparation for Work ................... 2 2.2.3. Temporary Modifications ................... 3 2.2.4. Return to Service ................... 3 CHAPTER 15, NONCONFORMING MATERIALS, PARTS, OR COMPONENTS

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. General ....................... 1 2.1.1. Supplier Nonconforming Items ...................... 1 2.2. Identification ....................... 2 2.3. Segregation ...................... 2 2.4. Disposition ... 2...................2 2.4.1. Control... 2.................

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TABLE OF CONTENTS 2.4.2. Evaluation ... 2......................

2.4.3. Personnel ... 3......................

2.4.4. Documentation ... 3......................

2.4.5. Repaired, Reworked, or Scrapped Items ................................ 3 CHAPTER 16, CORRECTIVE ACTION

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. General ............................... 1 2.2. Conditions Adverse to Quality ............................... 1 2.2.1. Significant Conditions Adverse to Quality............................... 1 2.3. Verification and Follow-up ............................... 2 2.4. Evaluation and Qualification ............................... 3 2.5. Documentation and Reporting ............................... 3 CHAPTER 17, QUALITY ASSURANCE RECORDS

1. SCOPE ............. 1

2. REQUIREMENTS ............. 1 2.1. Program ................................ 1 2.2. Administration ................................ 1 2.3. Receipt and Transmittal ................................ 2 2.4. Storage and Preservation ................................ 2 2.5. Safekeeping and Classification ................................ 2 2.6. Retention and Disposition ............................... 2 2.7. Plant Operating Records ................................ 3 2.7.1. Records and / or Logs, 5-Year Retention ................................ 3 2.7.2 Lifetime Records ................................ 4 2.8. Record Retention (Limerick Specific Only) ............................... 4 CHAPTER 18, ASSESSMENTS

1. SCOPE ............. 1

2. REQUIREMENTS ........... 1 2.1. Assessments - General .................. 1 2.1.1. Scheduling .................. 1 2.1.2. Preparation.........................................................................................................1 2.1.3. Personnel ................... 2 2.1.4. Performance .................. 2 2.1.5. Reporting and Follow-up .................. 2 2.1.6. Records .................. 3 Page 6 of 8 Revision 76

TABLE OF CONTENTS 2.2. Vendor Assessments ..................................... 3 2.3. Independent Management Assessment ...................................... 3 APPENDIX A, AUGMENTED QUALITY 1.SCOPE .1 2 .REQUIREMENTS .1 2.1. Health Physics and ALARA (As Low As Reasonably Achievable) .

2.2. Transport of Radioactive Waste .

2.3. Services .2 2.4. Fire Protection .2 2.5. Station Blackout (Dresden and Quad Cities) .2 2.6. Augmented Quality Requirements for Dresden 1, Peach Bottom 1, and Zion 2 2.6.1 Augmented Quality Requirements for Zion Station's Important to Defueled Condition Structure, Systems, Components, and activities. 3 2.7. Repairs and Alterations .5 2.7.1. State of Illinois .6 2.8. Dry Cask Storage System .7 2.8.1. Peach Bottom Atomic Power Station (PBAPS) .7 2.8.2. Oyster Creek Nuclear Generating Station (OCNGS) .7 2.8.3. Dresden Station / Quad Cities Station(s). 7 2.9 Emergency Planning. 7 2.10 Security. 7 APPENDIX B, ASSESSMENT FREQUENCY 1.TABLE .1 APPENDIX C, CODES, STANDARDS, AND GUIDES 1.1. Codes and Standards 1 1.2. Regulatory Guides 1 1.3. Clarifications and Exceptions .2 1.3.1. Limerick (LGS) and Peach Bottom Atomic Power Station (PBAPS) . 2 1.3.2. Oyster Creek (OCNGS) and Three Mile Island (TMI) Stations .10 1.3.3. Clinton Power Station (CPS) .20 APPENDIX D, DEFINITIONS 1.SCOPE .1 2 .GLOSSARY OF TERMS .1 APPENDIX E, CONTROL OF RADIOACTIVE WASTE OR MATERIALS (SITE SPECIFIC)

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TABLE OF CONTENTS

1. SCOPE ............... 1

2. REQUIREMENTS.........................................................................................................1 2.1. General .1 2.2. Three Mile Island/Oyster Creek .1 2.3. Clinton Power Station .3 2.3.1. Radioactive Waste/Augmented MD"Systems .3 2.3.2. Packaging and Transportation of Radioactive Waste .3 APPENDIX F, GRADED APPROACH (SITE SPECIFIC)

1. SCOPE . . 1

2. REQUIREMENTS .. 1 2.1. General ................................................ 1 2.2. Quality Classification ................................................ 1 2.2.1. Nuclear Safety Related or Augmented Quality Items ......................................... 2 2.2.2. QATR Scope Activities ................................................ 2 APPENDIX G, SUPPLEMENTAL APPLICATIONS (SITE SPECIFIC)

I.SCOPE..1

2. REQUIREMENTS .. 1 2.1. Clinton Power Station (CPS) .

2.1.1. Environmental .1 2.1.2. Fire Protection .2 2.1.3. Security .3 Page 8 of 8 Revision 76

ORGANIZATION CHAPTER 1

1. SCOPE This chapter identifies those portions of the Company organization as it applies to the Quality Assurance Program (QAP), and defines the responsibility and authority for establishing, executing, and verifying its implementation. The responsibility for the program is retained and executed by the Company exclusively.

Organizational responsibilities are described for assuring that activities affecting quality are prescribed and implemented by documented instructions, procedures, and drawings. The achievement of quality in the performance of quality related activities are the responsibility of each individual in support of nuclear operations.

The requirements and commitments contained in the QAP are mandatory and must be implemented, enforced, and adhered to by all individuals and organizations.

2. REQUIREMENTS Note: Minor variations may occur between the titles contained herein and those used in practice. Equivalent AmerGen positions are described with brackets. Specific position descriptions may be contained in approved Company documents.

2.1. Organization The organizational structure of the Company consists of corporate functions, and the nuclear facilities. Organizational titles for the quality assurance functions described are identified in Company policies and procedures.

Lines of authority and responsibility are established from the highest management level through intermediate levels to the implementing personnel. The responsibility, authority, and relationships of the various personnel and organizations are documented and maintained current.

The authority to accomplish the quality assurance functions described herein may be delegated to the incumbent's staff as necessary to fulfill the identified responsibilities.

Revision 76 Page I ofl7 Page 1 of 17 Revision 76

ORGANIZATION CHAPTER 1 2.2. Corporate Organization 2.2.1. Chairman and Chief Executive Officer The Chairman and Chief Executive Officer (CEO), Exelon Corporation, is responsible for overall corporate policy and provides executive direction and guidance for the corporation as well as promulgates corporate policy through the Company 's senior management staff.

2.2.2. President, Exelon Generation Company [Exelon Corporation]

The President, Exelon Generation, is responsible for Exelon Generation policy and provides executive direction and guidance for Exelon Generation as well as promulgates corporate policy through Exelon Generation senior management staff.

Overall responsibility for the implementation of the QAP is delegated to the President and Chief Nuclear Officer, Exelon Nuclear.

2.2.3. President and Chief Nuclear Officer [President & Chief Nuclear Officer -

AmerGen]

The President and Chief Nuclear Officer (CNO) reports to the President of Exelon Generation and has overall responsibility for the safe and reliable operation of the Company's nuclear stations. This is the senior executive responsible for setting and implementing policies, objectives, expectations, and priorities to ensure activities are performed in accordance with QAP and other requirements. The following management positions and committees report to the CNO:

1. The Chief Operating Officer (COO) is responsible to provide management oversight and support of the day-to-day operations of the stations for the safe and efficient operation of the nuclear fleet in compliance with the QAP. The COO is responsible for planning, organizing, and directing and controlling the operations, maintenance and improvement of the nuclear facilities. This position participates in the formulation of nuclear group strategy and policy, and provides leadership and direction to implement industry best practices. The following management positions report to the COO:

- A management position responsible for MidAtlantic operations provides management oversight and support of the day-to-day operations of the MidAtlantic stations. This position implements policies, goals, and objectives, in accordance with the QAP and other requirements, to assure the safe and reliable operation of the MidAtlantic nuclear stations This position participates in the formulation of nuclear group strategy and policy, and provides leadership and direction to implement industry best practices.

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ORGANIZATION CHAPTER 1

- A management position responsible for MidWest operations provides management oversight and support of the day-to-day operations of the MidAtlantic stations. This position implements policies, goals, and objectives, in accordance with the QAP and other requirements, to assure the safe and reliable operation of the MidAtlantic nuclear stations This position participates in the formulation of nuclear group strategy and policy, and provides leadership and direction to implement industry best practices.

- A management position for operations support who is accountable for defining standard programs and processes, delivering effective services and support, providing technical oversight of program implementation, and supporting the deployment and sharing of best practices throughout the nuclear organization in accordance with the QAP and other requirements, as applicable. Reporting to this position is a staff of management, administrative, and technical personnel. Functional areas of responsibilities include:

- outages, training, security, chemistry, industrial safety, maintenance and work control, operations, radiation protection, radioactive waste, fuel handling.

2. The management position responsible for engineering &technical services provides oversight and support and is accountable for defining standard programs, processes, policies, procedures, delivering effective services and support, providing technical oversight of program implementation, and supporting the deployment and sharing of best practices throughout the nuclear organization in accordance with the QAP, regulatory requirements, and the ASME Code. Reporting to this position is a staff of management, administrative, and technical personnel. Functional areas of responsibility include;

- engineering that provides support to the nuclear stations, design authority under the ASME Code, configuration management programs, special processes, and generic programs for technical and regulatory issues. A support staff provides the necessary discipline and expert support for setting technical policy, developing design standards, and performing engineering discipline reviews. This staff develops and supports common approaches for technical and regulatory engineering issues, as well as develops and coaches engineers. Corporate procurement engineering provides overall coordination and guidance of the nuclear organization's procurement engineering process and technical operations. This includes parts evaluation, upgrading of stock material, equivalent item evaluation, and examination and testing in accordance with the applicable ASME Code and Federal Regulations Revision 76 of 17 Page 3 of 17 Revision 76

ORGANIZATION CHAPTER 1

- laboratory services for implementing metrology related programs including calibration and maintenance of measuring and test equipment, technical services.

- nuclear fuels management providing BWR/PWR nuclear fuel procurement and fabrication services, technical support to monitor fuel reliability and certain in-core components, design and licensing analyses for core reloads, safety analyses, and high level waste strategy. This position is responsible for reactivity management oversight and corporate support of reactor operations to ensure safe and reliable plant operations, as the manager of nuclear materials, and for controls and reports associated with special nuclear material accountability.

- project management

3. The management position responsible for Nuclear Oversight (NOS) activities is independent of production and assures that an appropriate QAP is established, maintained, and effectively executed throughout the nuclear organization. This position provides overall direction for the implementation of the QAP and for the effective implementation of quality assurance functions that verify activities affecting safety-related functions. The management position responsible for NOS must meet the educational and experience requirements of ANSI/ANS 3.1.

A staff of supervisory, administrative, and technical personnel supports assessment and quality verification. Functional responsibilities include:

- employee concern program activities.

- establishing quality assurance practices and policies.

- independent assessment and quality verification activities.

- initiating stop work, ordering unit shutdown, or request any other actions deemed necessary to avoid unsafe plant conditions or a significant violation of the QAP.

- initiating, trending, and recommending solutions for deficiencies identified by NOS.

- maintaining a trained and qualified staff of personnel within the NOS organization.

- maintenance and approval of revisions to the Quality Assurance Topical Report (QATR) and the program for employee concerns.

- overseeing nuclear site NOS activities.

- participation in joint membership groups.

- periodic assessments to determine that the Quality Assurance Policy is being carried out.

- periodic review of the independent assessment program.

- periodically apprising the President and CNO and the Nuclear Safety Review Board of the status of the quality assurance aspects at Company Page 4of 17 Revision 76

ORGANIZATION CHAPTER 1 facilities and immediately apprise them of significant problems affecting quality.

- settling disputes between NOS and other organizations.

- the certifying authority for NOS assessment personnel.

- the internal assessment program.

- the management assessment program.

- verifying implementation of solutions for significant conditions adverse to quality identified by NOS.

A. Reporting to the management position responsible for NOS is a management position responsible for performance assessment activities at the sites. This position is responsible to prioritize and communicate common quality issues to appropriate senior management including the resolution of these issues. A position responsible for implementation of site level NOS activities reports through this management position.

B. Also reporting to the management position responsible for NOS is a management position responsible for auditing and programs.

Functional areas of responsibility include:

- maintaining the regulatory required compliance auditing program.

- managing the conduct of supplier assessments, audits, or surveys (including their sub-tier suppliers) as required.

Verifies that supplier quality assurance programs comply with Company requirements and has the authority and responsibility for QA activities applicable to supplier evaluation including, stop work as deemed necessary when a violation of the QAP is identified.

- establishing, maintaining, and interpreting Company quality assurance policies and procedures.

- providing training on quality assurance subjects.

- establishing the requirements for assessment/auditor and inspector certification.

- controlling and maintaining the QATR.

- provides an offsite point of contact for station Quality Verification personnel if assistance is necessary for quality verification activities.

- managing implementation of the program for employee concerns.

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ORGANIZATION CHAPTER 1

4. A management position responsible for licensing and regulatory affairs provides organizational support and management oversight of the stations to ensure prompt and proper disposition of regulatory issues, develops regulatory positions and advises senior management on priorities and activities affecting regulatory issues at the nuclear sites. Other responsibilities include developing policies and standardized processes and procedures for the maintenance of the licensing basis, the preparation of submittals to the NRC and other regulatory organizations, the dissemination of regulatory and operational experience information, NSRB, and the administration of the Corrective Action Program, periodically conducting an independent effectiveness review of NSRB activities (not to exceed 2 years) and providing overall direction and management oversight for environmental issues. Functional areas of responsibility include:

- a management position for emergency planning is responsible for providing overall direction and management oversight.

5. The Nuclear Safety Review Board (NSRB) is an offsite committee that reports to and advises the President and CNO of the results of their independent oversight of plant operations related to safe operation of the station and the Company's nuclear program relative to nuclear safety. The NSRB is responsible for the independent safety review function and functions in accordance with written procedures and instructions which delineates committee composition, responsibility, authority, member qualifications, meeting frequency, subjects to be reviewed, reporting requirements, and administrative controls under which the board operates. The NSRB:

- conducts independent reviews of station performance and operations to determine if the facility is being operated and maintained in a manner that promotes safety and provides feedback to the organization on suggested improvements.

- focuses primarily in the areas of Operations, Maintenance, Engineering, Plant Support, Regulatory and Nuclear Oversight, or other matters relating to safety.

- reviews station materials and activities and advises the CNO and management responsible for NOS on the following activities:

- any issue potentially affecting the safe operation of the facility.

- station nuclear safety performance determined by discussion and interviews with station and Exelon Nuclear individuals, plant tours, oversight of meetings, and review of documents distributed for NSRB review.

- effectiveness of the station program for oversight including audits, assessments, and self-assessments.

- corrective actions for degraded or non-conforming conditions involving violations of the NRC license requirements, plant Revision 76 6 of 17 Page 6 of 17 Page Revision 76

ORGANIZATION CHAPTERI1 ORGANIZATION CHAPTER 1 transients or forced shutdowns, or the submission of a Licensee Event Report (LER).

- oversight of activities of the on-site safety review function.

6. The management position responsible for business operations provides integrated support to senior management and the nuclear sites for all business functions. Reporting to this position is a staff of supervisory, administrative, and technical personnel. Functional areas of responsibility includes:

- business planning and process improvement.

- records management.

- communications.

- decommissioning activities that include the safe storage and handling of irradiated spent nuclear fuel including operations and maintenance.

Supply and information technology are no longer functional areas exclusively within the nuclear organizational structure but now support the entire Exelon Corporation. The management position responsible for business operations no longer has direct responsibility for these functional areas; however, this management position will supply oversight and governance for the functional areas of supply and information systems as they apply to Exelon Nuclear. The oversight and governance of these functional areas is performed to ensure that organizational and functional responsibilities and reporting relationship to the management position responsible for all nuclear activities, the CNO, is maintained within the requirements stated within the QATR. This includes all regulatory requirements committed to by the QATR. The management position responsible for business operations supplies oversight and governance for:

- management and supervision of information systems related services and activities including the software quality assurance program (DTSQA). This includes the creation, acquisition, the enhancement of computer hardware, communication, and software systems to support operational requirements.

- the Exelon Nuclear supply function including the establishment of priorities and providing operational control of the purchase of non-fuel goods and services required for nuclear operations. This organization is also responsible for the areas of material procurement, services procurement, supply programs, inventory management, and investment recovery.

Supply establishes policies, common administrative controls and processes to ensure compliance with applicable requirements and effective use of resources.

7. A management position responsible for licensing projects including special projects and new technology.

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ORGANIZATION CHAPTER 1

8. A management position responsible for project development.

2.3. Site Organization A management position for each nuclear site reports through the applicable management position responsible for each designated operating group including the MidAtlantic and the Midwest and is responsible for overall plant nuclear safety and the implementation of the Company's QAP. This position is also responsible for the station compliance with its NRC operating license, governmental regulations, and ASME Code requirements. Day to-day direction and management oversight of activities associated with the safe and reliable operation of a nuclear station is provided. The following site management positions report to this position:

2.3.1. The management position responsible for plant operations assures the safe, reliable, and efficient operation of the plant within the constraints of applicable regulatory requirements, operating license, and the QAP. Supervisory direction is provided for the Technical Review Program, including approval of individuals as technical reviewers, and the Plant Operations Review Committee (PORC). During periods that exceed three months, when unavailable, responsibility is designated in writing to an established alternate who satisfies the experience requirements of this position.

Functional areas of responsibility include:

- Management position(s) for maintenance are responsible for the performance of corrective, predictive and preventive maintenance, cleanliness controls and modification installation of mechanical and electrical equipment and instrumentation in accordance with the QAP and other requirements. A staff of supervisory, technical, administrative, and contract personnel supports day-to-day maintenance of equipment within their functional area.

- Management position(s) responsible for project management and control of work coordinate, administer, execute, and monitor daily and outage work schedules. This position is also responsible for material management and site supply, which coordinates parts requirements, specifies and evaluates parts, procures all materials for the site, ships and receives material, and controls the onsite inventory. The site supply chain provides and coordinates scope and priority for station procurement engineering efforts.

- chemistry activities, laboratory and system processes, related procedures and programs.

- environmental services.

- health physics/radiological protection.

- operations and support including:

- a management position responsible for safe, reliable, and efficient plant operations within the constraints of the operating license and regulatory requirements. This position is also responsible for the development and Revision 76 Page 8 Page of 17 8 of 17 Revision 76

ORGANIZATION CHAPTER 1 implementation of appropriate controls in accordance with the QAP and other requirements.

- management position(s) responsible for operations shift crews and administration, direction and supervision of operating staff. This position is also responsible for routine plant operations activities and evolutions that are performed within the constraints of the operating license, the QAP, and other requirements. Typically this position is the senior individual on site who holds a Senior Reactor Operator license.

- management position(s) responsible for the day-to-day operation of the nuclear unit(s) ) including reactor engineering and overall command and control of shift activities including operations of the radioactive waste system.

- management position(s) responsible for supervision for control of work and of the plant and field supervision that coordinates and/or assists in the control of shift operations. This position directs control room personnel, field operations, has the primary responsibility for authorizing removal and restoration of systems to support maintenance activities and holds a Senior Reactor Operator License.

- a management position responsible for advisory technical support to shift management in the areas of thermal hydraulics, reactor engineering and plant analysis with regards to the safe operations of the facility. In addition, this position shall meet the qualifications as specified by the NRC.

- radioactive waste.

- radiological environmental monitoring.

- security.

2.3.2. The management position for engineering and design has the responsibility and authority for day-to-day engineering support activities, develops and maintains engineering programs, policies, procedures, and provides engineering services in accordance with the QAP. A staff of supervisory, technical, and administrative personnel supports maintenance activities. Functional areas of responsibility include:

- design engineering.

- document control.

- engineering administration.

- modifications and their implementation.

- plant configuration control.

- quality assurance records management.

- system engineering.

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ORGANIZATION CHAPTER 1

- system testing.

- technical support.

2.3.3. The management position responsible for regulatory assurance maintains an interface and liaison between the station and federal and state regulators and is also responsible for the overall administration of the station's corrective action program and associated activities. Functional responsibilities include:

- emergency preparedness 2.3.4. The management position responsible for training provides direction, control, and overall supervision of personnel as required by regulations and training for all site personnel as required. Functional areas of responsibility include:

- learning services.

- maintenance technical training.

- operations training.

2.3.5. The Plant Operations Review Committee (PORC) is a multi-disciplined committee responsible for review of activities that affect nuclear safety, reports to, and advises the management position responsible for plant operation on matters related to nuclear safety. The PORC shall ensure that plant activities are conducted safely and do not require NRC review and approval prior to implementation or changes to the Technical Specifications. The PORC functions in accordance with written instructions which delineate committee composition, responsibility, authority, member qualifications, meeting frequency, subjects to be reviewed, reporting requirements, and administrative controls under which the group operates.

2.3.6. The management position responsible for site NOS activities reports to the management position responsible for NOS through the NOS management position responsible for performance assessment. This position has the organizational freedom and authority to identify problems, has a reporting relationship with the senior management position responsible for overall plant nuclear safety, and ensures compliance with QAP and nuclear safety requirements.

Significant safety or quality issues requiring escalated action will be directed through the management position responsible for NOS to the President and CNO.

Functional responsibilities include:

- authority and responsibility to escalate matters.

- approving the agenda, checklist, findings, and report of each assessment.

- conducting independent assessments of line and support activities and safety reviews.

- identify changes to the quality assurance program.

- initiate, trend and recommend solutions for deficiencies identified by NOS.

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ORGANIZATION CHAPTER 1

- maintain a suitably trained and qualified staff.

- monitoring day-to-day station activities.

- provide NOS management periodic reports on the status and adequacy of the QAP.

- quality verification inspections.

- promptly communicate significant issues to NOS and appropriate site management.

- stop work or request any other actions to avoid unsafe plant conditions.

2.3.7. The Company uses a three-tiered approach to accomplish the oversight of safety which are:

- A collection of program elements for implementing and/or reviewing areas of quality of plant operations and nuclear safety. These elements include system performance monitoring, review of operating experience information, operability evaluations, and reviews of changes to technical specifications and final safety analysis reports that affect design bases. Specific guidance is contained in applicable procedures and programs.

- A NOS staff who assesses and performs quality verification inspection aspects of Company activities within the scope of the QATR relating to safety.

This provides for an overview of activities affecting or potentially affecting safety.

- A NSRB which is an off-site committee that reports to and advises the President and Chief Nuclear Officer, Exelon Nuclear, of the results of independent oversight of plant operation relative to nuclear safety.

- In lieu of the collection of program elements for implementing and/or reviewing areas of quality of plant operations and nuclear safety as described above, the Independent On-site Safety Review Group (IOSRG) at Oyster Creek and Three Mile Island Nuclear Stations will perform the Independent Safety Engineering function required by NUREG 0737. A description of this function as implemented at Oyster Creek and Three Mile Island is described in Appendix C of this QATR.

2.3.8. Oyster Creek The organizational structure at the Oyster Creek station is consistent with that described in section 2.3.1 through 2.3.7 with the following exceptions:

The management position responsible for plant operations described in section 2.3.1 includes the functional responsibility for coordination, administration, execution, and monitoring of on-line work schedules.

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ORGANIZATION CHAPTERI1 ORGANIZATION CHAPTER 1 The management position responsible for training as described in section 2.3.4 includes the functional responsibility for emergency preparedness.

The management position responsible for plant outages includes the functional responsibility for coordination, administration, execution, and monitoring of outage work schedules.

The management position responsible for business support includes the functional responsibility for:

- business operations

- information technology

- materials management

- site supply

- document control

- records management 2.4. Decommissioning Site Organization Similar to the operating sites, the following positions are responsible for management oversight, directing, and implementing appropriate controls to maintain the site within the requirements and constraints applicable to a permanently shutdown station or unit (or those stations or units not under the control of an NRC approved decommissioning plan), and to ensure the safe storage of spent nuclear fuel.

2.4.1. Dresden Unit I The management position for Dresden Unit 1 has the day-to-day responsibility for decommissioning activities and for the operation and maintenance of structures and systems required for the safe storage of spent nuclear fuel. Activities of decommissioning work groups are managed and monitored to ensure that there is no adverse safety impact on the unit prior to execution. This position is also responsible for supporting the station in assuring that activities are performed within the constraints of the Decommissioning Technical Specifications (DTS) and in accordance with the QAP, as applicable.

2.4.2. Zion The management position responsible for operations and engineering for Zion Station is responsible for engineering support and the operation of dedicated systems required for the safe storage of spent nuclear fuel. Activities of decommissioning work groups are managed and monitored to ensure that there is Revision 76 12 of Page 12 of 1717 Revision 76

ORGANIZATION CHAPTERI1 ORGANIZATION CHAPTER 1 no adverse safety impact on the unit prior to execution. This position is also responsible for supporting the station in assuring that activities are performed within the constraints of the DTS and in accordance with the QAP, as applicable.

2.6. Responsibility Each holder of position as identified in this Chapter, has the responsibility for the scope and effective implementation of the QAP and may delegate all or part of the activities of planning, establishing, and implementing the QAP to others, but retains the responsibility for the program's effectiveness.

The Company is responsible for ensuring that the applicable portion(s) of the QATR is properly documented, approved, and implemented before an activity within the scope of the QAP is undertaken by the Company or by others.

Personnel performing NOS assessment functions for the Company have the responsibility, authority, organizational freedom, and sufficient independence from cost and schedule to:

- assure that further processing, delivery, installation, or use is controlled until proper disposition of a nonconformance, deficiency, or unsatisfactory condition has occurred.

- identify quality problems.

- initiate, recommend, or provide solutions to quality problems through designated channels.

- initiate stop work, order unit shutdown, or request any other actions deemed necessary to avoid unsafe plant conditions or a significant violation of the QAP

- verify implementation of solutions for significant conditions adverse to quality.

The Company may delegate certain phases of the work to non-company labor and contracted services, which act as the Company's agents in assigned areas. They shall work to a Company accepted quality program (or in accordance with the Company's program) under overall site direction and document their organization and any delegated responsibilities necessary to establish, execute, and verify their quality program. The Company may also assign the authority for certification and stamping in accordance with the ASME Code.

2.6. Authority When the Company delegates responsibility for planning, establishing, or implementing any part of the overall QAP, sufficient authority to accomplish the assigned responsibilities is delegated. Regardless of delegation, the Company retains responsibility.

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ORGANIZATION CHAPTER 1 2.7 Review and Audit (Limerick Specific Only) 2.7.1 Plant Operations Review Committee (PORC) (Limerick Specific Only)

Function The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.

Composition The Plant Operations Review Committee is composed of nine (9)regular members from the Limerick Generating Station staff. Members shall collectively have experience in the following areas:

- Plant Operations

- Engineering

- Maintenance

- Instrumentation and Controls

- Planning

- Radiation Safety

- Chemistry

- Regulatory Assurance Members shall meet the requirements of ANSI/ANS 3.1-1978, Section 4.7, for the applicable required experience and be appointed in writing by the Plant Manager.

The Chairman and alternate Chairmen of the PORC shall be drawn from the PORC members and appointed in writing by the Plant Manager.

Alternates All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.

Meeting Frequency The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.

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ORGANIZATION CHAPTER 1 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

Responsibilities The PORC shall be responsible for:

1. Review of (1)Administrative Procedures and changes thereto, (2) new programs or procedures required by Limerick Technical Specification. 6.8 and requiring a 10 CFR 50.59 evaluation, and (3) proposed changes to programs or procedures required by Limerick Technical Specification. 6.8 and requiring a 10 CFR 50.59 evaluation;

2. Review of all proposed tests and experiments that affect nuclear safety;

3. Review of all proposed changes to Appendix A Technical Specifications;

4. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety;

5. DELETED.

6. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board;

7. Review of all REPORTABLE EVENTS;

8. Review of unit operations to detect potential hazards to nuclear safety;

9. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Vice President, Limenck Generating Station, Plant Manager or the Chairman of the Nuclear Review Board;

10. Review of the Security Plan and implementing procedures and submittal of recommended changes to the Nuclear Review Board; and

11. Review of the Emergency Plan and implementing procedures and submittal of the recommended changes to the Nuclear Review Board.

12. Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board.

13. Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

14. Review of the Fire Protection Program and implementing procedures and the submittal of recommended changes to the Nuclear Review Board.

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ORGANIZATION CHAPTERI1 ORGANIZATION CHAPTER 1 The PORC shall:

- Recommend in writing to the Plant Manager approval or disapproval of items considered under QATR Chapter 1, paragraph nos. 2.7.1.1, 2.7.1.2, 2.7.1.3 and 2.7.1.4 prior to their implementation.

- Render determinations in writing with regard to whether or not each item considered under QATR Chapter 1, paragraph nos. 2.7.1.2, 2.7.1.3, 2.7.1.4, 2.7.1.5, and 2.7.1.6 requires NRC approval pursuant to 10 CFR 50.59.

- Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Limerick Generating Station and the Nuclear Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Limerick Technical Specification. 6.1.1.

Records The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the Vice President, Limerick Generating Station, Plant Manager, and the Nuclear Review Board.

2.7.2 Nuclear Review Board (NRB) (Limerick Specific Only)

Function The NRB shall function to provide independent review and audit of designated activities in the areas of:

1. Nuclear power plant operations,

2. Nuclear engineering,

3. Chemistry and radiochemistry,

4. Metallurgy,

5. Instrumentation and control,

6. Radiological safety,

7. Mechanical and electrical engineering, and

8. Quality assurance practices.

The NRB shall report to and advise the Senior Vice President and Chief Nuclear Officer on those areas of responsibility pertaining to NRB Review and Audits.

Composition The Chairman, members, and alternates of the NRB shall be appointed in writing by the Chief Nuclear Officer, and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas identified in QATR Chapter 1, Revision 76 Page of 17 16 of Page 16 17 Revision 76

ORGANIZATION CHAPTER 1 paragraph nos 2.7.2.1 through 2.7.2.8. The NRB shall be composed of no less than eight and no more than 12 members.

The members and alternates of the NRB will be competent in the area of Quality Assurance practice and cognizant of the Quality Assurance requirements of 10 CFR Part 50, Appendix B. Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them.

Alternates All alternates shall be appointed in writing by the NRB Chairman to serve on a continuing basis. They shall receive correspondence sent to NRB members with regard to NRB activities and shall be invited to attend all NRB meetings. Alternates shal vote only in the absence of those members for whom they are the alternate.

Consultants Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB.

Meeting Frequency The NRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.

Quorum The quorum of the NRB necessary for the performance of the NRB review and audit functions of these Technical Specifications shall consist of the Chairman or a designated alternate and at least four but not less than one half of the voting NRB members. No more than a minority of the quorum shall have line responsibility for operation of the facility.

Review DELETED. The information from this section is located in the Limerick UFSAR.

Audits DELETED. The information from this section is located in the Limerick UFSAR.

Records Records of NRB activities shall be prepared, approved, and distributed as indicated below:

- Minutes of each NRB meeting shall be prepared, approved, and forwarded to the Senior Vice President and Chief Nuclear Officer within 14 days following each meeting.

- Reports of Reviews shall be prepared, approved, and forwarded to the Senior Vice President and Chief Nuclear Officer within 14 days following completion of the review.

- Audit reports shall be forwarded to the Corporate Officer(s) and management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

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QUALITY ASSURANCE PROGRAM CHAPTER 2 QUALITY ASSURANCE PROGRAM CHAPTER 2

1. SCOPE The purpose of this chapter is to define how the Company's QAP applies to those activities such as design, procurement, fabrication, installation, modification, maintenance, repair, refueling, operation, inspection, and tests related to systems, structures, and components. The QAP also applies to certain non-safety related structures, systems, components and activities to a degree consistent with their importance to safety. Policies, directives, procedures, guidelines, manuals, or instructions shall be reviewed, approved, distributed, and revised in accordance with administrative procedures.

2. REQUIREMENTS 2.1. General The QAP comprises all those planned and systematic actions necessary to provide adequate confidence that structures, systems, and components will perform satisfactorily in service. Quality assurance includes quality verification, which comprises the examination of those physical characteristics of material, structure, component, or system which provide a means to control the quality of the material, structure, component, or system to predetermined requirements.

All persons and organizations involved in activities in support of the nuclear sites and governed by this program are responsible for implementing the requirements of this manual.

The QAP is based upon 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." The requirements of 10CFR50.54, "Conditions of License," 10CFR50.55(a), "Codes and Standards,"

10CFR50.59, "Changes, Test, and Experiments," 10CFR50 Appendix A, uGeneral Design Criteria for Nuclear Power Plants," 10CFR50 Appendix R, "Fire Protection Programs for Nuclear Power Plants," are included in the basis for the QAP.

The requirements of 10CFR21, Reporting of Defects and Non-Compliance,"

IOCFR71, Subpart H, "Quality Assurance for Packaging and Transportation of Radioactive Material," and 10CFR72, Subpart G, "Quality Assurance for Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste," are also included. The Company is committed to carrying out the provisions of various NRC regulatory guides and industry standards which further define Quality Assurance Program requirements (see attached Appendix C).

2.2. Supplier's Quality Assurance Program The applicable Quality Assurance requirements of 10CFR50, Appendix B, as noted in Appendix C, are invoked on vendors, suppliers, or contractors through procurement document requirements.

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QUALITY ASSURANCE PROGRAM CHAPTER 2 2.3. Planning Planning establishes the systematic, sequential progression of actions to meet the defined requirements. The Company documents these plans in appropriate communications, approvals, instructions, and procedures. Activities described in the QAP are accomplished under controlled conditions that include appropriate equipment, qualified personnel, suitable environment, and use of appropriate procedures.

2.4. Program Description The Company's total program for providing administrative controls and quality assurance is incorporated in many diverse documents. The Company's nuclear document hierarchy describes the implementation of the QAP. Approved implementing procedures and instructions are written to the extent necessary to implement the quality requirements of 10CFR50 Appendix B. Line, staff, administrative, and quality oversight organizations issue and control these implementing procedures. All activities affecting quality are described in sufficient detail to assure quality.

2.5. Indoctrination & Training Formal indoctrination and training programs for personnel performing or verifying activities within the scope of this Plan are established and maintained. A training organizational element is established and staffed with qualified instructors and is responsible for planning, scheduling, developing and providing training to Company personnel. The indoctrination and training programs are established by on-site and by off-site organizational units responsible for the performance or verification of activities within the scope of the QAP.

Indoctrination, training, and qualification programs are established such that:

- personnel responsible for performing quality-affected activities are instructed as to the purpose, scope, and implementation of the quality-related manuals, instructions, and procedures.

- personnel verifying activities affecting quality are trained and qualified in the principles, techniques, and requirements of the activity being performed.

- formal training and qualification programs documentation includes the objective, content of the program, attendees, and date of attendance.

- proficiency tests are given to those personnel performing and verifying activities affecting quality, and the acceptance criteria are developed to determine if individuals are properly trained and qualified.

- certificate of qualification clearly delineates the specific functions personnel are qualified to perform and the criteria used to qualify personnel in each function.

- proficiency of personnel performing and verifying activities affecting quality is maintained by re-training, re-examining, re-qualifying, and/or re-certifying as determined by management or program commitment.

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QUALITY ASSURANCE PROGRAM CHAPTER 2 QUALITY ASSURANCE PROGRAM CHAPTER 2 2.6. Program Review The effectiveness of the QAP and its implementation is periodically reviewed by various organizations at various levels. The results of these reviews are documented in reports to senior management for evaluation and corrective action is initiated as required. The effectiveness of the QAP is evaluated and reported by NOS through the monitoring, assessment, and inspection functions.

Other organizational elements provide additional information/ evaluations as requested.

2.7. Quality Assurance Manual This Quality Assurance Manual (QAM) contains the Company's QAP. The QAM is made available to NRC, Company personnel, the Authorized Nuclear Inspector, and other regulatory authorities. The Company submits revisions to the QAP document (as a topical report) to the NRC for acceptance.

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DESIGN CONTROL CHAPTER 3 DESIGN CONTROL CHAPTER 3

1. SCOPE The purpose of this chapter is to establish the requirements and control measures for assuring design bases and regulatory requirements are correctly translated into design documents. The scope of design control covers all phases of engineering design, including: identification of design inputs (criteria and bases); identification and control of design interfaces; production of design documents, calculations and analyses; procurement related engineering and design verification.

2. REQUIREMENTS 2.1. General The Company has overall responsibility for design and design control activities including, preparing, reviewing, approving, and verifying design documents related to the plant's structures, systems, and components within the scope of the QAP. Additionally, the Company is responsible for reactor core design analysis, core design specifications and design reviews, for nuclear fuel and in-core components.

Qualified personnel perform detailed design activities or review and control design work involving electrical, mechanical, structural, and instrumentation and control designs. Design activities are conducted to written procedures that include consideration of quality standards, quality assurance requirements, suitability of material parts, equipment, and processes, control of design interfaces, analytical or testing requirements, design basis, and configuration management.

2.2. Design Input The Company has the responsibility to properly translate applicable safety analysis reports, regulatory requirements, ASME Code requirements, and design bases into specifications, drawings, procedures and instructions. The Company is responsible for electrical, mechanical, structural, instrumentation and control; nuclear engineering activities involved in nuclear station modifications, and also maintains a configuration management program.

Design inputs, such as design bases, performance requirements, regulatory requirements, codes, and standards shall be identified and documented. Their selection shall be reviewed and approved by the responsible design organization. The design input shall be specified and approved in a timely manner and be to the level of detail necessary to provide a consistent basis for making design decisions, accomplishing design verification, and evaluating design changes. Changes from approved design inputs, including the reason for the changes shall be identified, approved, documented, and controlled.

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DESIGN CONTROL CHAPTER 3 DESIGN CONTROL CHAPTER 3 2.3. Design Process The Company is responsible for design changes, performs detailed design activities, and issues design documents in accordance with approved procedures. The responsible design organization shall prescribe and document design activities in a timely manner and to the level of detail necessary to permit verification that the design meets requirements.

Included in this scope of activities are considerations for field design engineering, fire hazards, human factors, physics, seismic, stress, compatibility of materials, application of special process, associated computer programs, thermal, hydraulic, ALARA and radiation factors, the safety analysis accident scenarios, and accessibility for in-service inspection, maintenance and repairs, and quality standards. Design documents shall be adequate to support facility design, construction, and operation. Selection of the appropriate quality standards shall be documented, reviewed and approved.

Reasons for changes from specified quality standards, shall be identified, documented, approved and controlled. Design methods, materials, parts, equipment, and processes that are essential to the function of the structure, system, or component shall be selected and reviewed for suitability of application. Applicable industry experience, as set forth in reports or other documentation, shall be made available to cognizant design personnel.

The final design output documents and approved changes thereto shall be relatable to the design input by documentation in sufficient detail to permit design verification. The final design shall identify assemblies and/or components that are part of the item being designed. If materials, parts, equipment, or processes are different from the published supplier information, these differences shall be documented.

Commercially standard (catalog items) materials, parts, or equipment, which have been previously approved for different applications, are reviewed for suitability in the design process.

2.4. Design Analyses Design analyses shall be performed in a planned, controlled, and documented manner. Design analysis documents shall be legible and suitable for reproduction, filing, and retrieval. They shall be sufficiently detailed as to purpose, method, assumptions, design input, references, and units such that a person technically qualified in the subject can review, understand the analysis, and verify the adequacy of the results without recourse to the originator.

Calculations shall be identified for retrievability by subject including structure, system, component, originator, reviewer, and date or by other unique identifiers.

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DESIGN CONTROL CHAPTER 3 DESIGN CONTROL CHAPTER 3 Computer programs shall be controlled to assure that changes are documented and approved. Verification shall be required for changes to previously verified computer programs including evaluation of the effects of these changes as specified below.

Computer programs may be utilized for design analysis without individual verification of the program for each application provided:

- the computer program has been verified to show that it produces correct solutions for the encoded mathematical model within defined limits for each parameter employed.

- the encoded mathematical model has been shown to produce a valid solution to the physical problem associated with the particular application.

2.5. Design Verification Design control measures shall be applied to verify the adequacy of design, such as by one or more of the following:

- performance of design reviews.

- use of alternate calculations.

- performance of qualification tests.

The results of design verification shall be documented including the identification of the verifier. Design verification shall be performed by competent individual(s) other than those who performed the original design but may be from the same organization. This verification may be performed by the originator's supervisor, provided the supervisor did not specify a singular design approach, rule out certain design considerations, did not establish the design inputs used in the design, or the supervisor is the only individual in the organization competent to perform the verification. Cursory supervisory reviews do not satisfy the intent of design verification.

Verification shall be performed in a timely manner. Design verification, for the stage of design activity accomplished, shall be performed prior to release for procurement, manufacture, construction, or release to another organization for use in other design activities provided sufficient data exists. Any unverified portion of the design shall be identified and controlled. In all cases the design verification shall be completed prior to relying upon the component, system, structure, or computer program to perform its function.

2.5.1. Extent of Design Verification The extent of the design verification required is a function of the importance to safety, the complexity of the design, the degree of standardization, the state of the art, and the similarity with previously proven designs.

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DESIGN CONTROL CHAPTER 3 DESIGN CONTROL CHAPTER 3 Where the design has been subjected to a verification process, the process need not be duplicated for identical designs. For each application the applicability of standardized or previously proven designs for design inputs shall be verified.

Known problems affecting the standard or previously proven designs and their effects on other features shall be considered. The original design and associated verification shall be adequately documented and referenced in subsequent applications.

Design verification shall be required for changes to previously verified designs.

This includes evaluation of the effects of those changes on the overall design and on any affected design analyses.

2.5.2. Design Reviews Verification consists of a check of design adequacy by such methods as design reviews, use of alternate calculations or methods, or performance of verification or qualification testing. The method, or combination of methods, used to verify a design will be selected on a case-by-case basis Acceptable verification methods include one or more of the following items:

- alternate calculations using alternate methods that verify the correctness of original calculations or analyses.

- critical design reviews providing assurance that the final design is correct and satisfactory.

- where design adequacy is to be verified by qualification tests, the tests are dentified.

2.6. Change Control Changes to final designs, field changes, modifications to operating facilities, and nonconforming items dispositioned use-as-is or repair shall be justified and subject to design control measures commensurate with those applied to the original design.

These measures shall include assurance that the design analyses for the structure, system, or components are still valid. A 10CFR50.59/72.48 review is performed for changes to the facility.

Changes shall be approved by the same affected groups or organizations, which reviewed and approved the original design documents. In the case where the original organization is no longer responsible for design approval, then a new responsible design organization shall be designated. The designated organization shall have demonstrated competence in the specific design area of interest and have an adequate understanding of the requirements and intent of the original design.

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DESIGN CONTROL CHAPTER 3 When a design change is approved, other than by revision to the affected design documents, measures shall be established to incorporate, where appropriate the change into these documents. Plant personnel will be made aware of design changes/modifications, which may affect the performance of their duties. Where a significant design change is necessary because of an incorrect design, the design process and verification procedure shall be reviewed and modified as necessary.

2.7. Design Errors The Company detects deficiencies or errors in design or in the design quality assurance program by:

- actual failure during operation.

- assessments.

- design verification measures.

- other means.

- personnel using the design documents.

- tests conducted.

2.8. Interface Control Design interfaces shall be identified and controlled. The Company shall coordinate design efforts among the participating organizations. Interface controls shall include the assignment of responsibility and the establishment of procedures among participating design organizations. Controls shall be for the review, approval, release, distribution and revision of documents involving design interfaces. Design information transmitted across interfaces shall be documented and controlled.

2.9. Vendor Design Control The Company reviews and accepts the specifications and drawings for electrical, mechanical, instrumentation, nuclear and structural material, equipment, and erection work, prepared by the Architect Engineer and NSSS Supplier. The purpose of these reviews is to verify inclusion of inspection, testing and acceptance criteria.

The Architect Engineer's evaluation of fabricator and erector's detailed designs, drawings, and work instructions are reviewed for reasonableness and completeness. Audits are conducted by the company for design review systems of architect engineers, nuclear fuel, and NSSS suppliers.

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DESIGN CONTROL CHAPTER 3 DESIGN CONTROL CHAPTER 3 The Company assures that:

- personnel certifying ASME Section III design activities are qualified Registered Professional Engineers in accordance with ASME Section 1II, Appendix XXIII.

- architect engineers and NSSS suppliers maintain procedures to assure that their personnel certifying ASME Section III design activities are qualified Registered Professional Engineers in accordance with ASME Section III, Appendix XXIII.

The Company provides qualified personnel to review and approve the resolution of non-conformances relating to electrical, mechanical, instrumentation and structural portions of the plant and to evaluate discrepant modification test results for operating plants.

2.10. Modifications The Company performs modifications that may affect the function of safety-related structures, systems, or components in a manner to assure quality at least equivalent to that specified in original design bases and requirements, materials specifications, and inspection requirements.

2.11. Documentation and Records The Company notifies jurisdictional authorities of the location of ASME Code related permanent records. Design documentation and records which provide evidence that the design and design verification process were performed in accordance with the requirements of this chapter, shall be stored and maintained.

Documentation of design analyses shall include the following:

- statement of the objective of the analyses.

- list of design inputs and their sources.

- results of literature searches or other applicable background data.

- list of assumptions and indication of those that must be verified as the design proceeds.

- list of any computer calculation and the bases for its use.

- review and approval.

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PROCUREMENT DOCUMENT CONTROL CHAPTER 4

1. SCOPE This Chapter identifies the requirements for preparation, review, approval, release, and retention of procurement documents.

2. REQUIREMENTS 2.1. General The Company establishes measures for the preparation, review, and approval of procurement documents for those items and activities within the scope of the QATR. Procurement documents at all tiers include or reference the appropriate regulatory, technical, and quality requirements necessary to assure adequate quality. These requirements include reference to 10CFR21 when applicable.

2.2. Content of Procurement Documents Procurement documents at all tiers include the following items as deemed necessary by the Company.

2.2.1. Scope of Work Procurement documents describe the scope of the items or services to be furnished by a supplier. For those items that are important to plant safety, applicable requirements should be specified in the procurement document.

2.2.2. Technical Requirements The Company establishes measures in controlled procedures to; specify technical requirements by reference to the appropriate specific drawings, specifications, codes, standards, regulations, procedures, or instructions, including revisions thereto that describe the items or services to be furnished.

The procurement documents identify test, inspection and acceptance requirements as appropriate. These documents identify as appropriate special instructions and requirements for such activities as design, material and component identification, fabrication, special process controls, cleaning, erecting, packaging, handling, shipping, and extended storage.

2.2.3. Quality Assurance Program Requirements Measures are established, in controlled procedures, to ensure the appropriate technical and quality requirements are established, by qualified personnel, for the material, equipment, and services purchased from vendors, suppliers, or contractors.

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PROCUREMENT DOCUMENT CONTROL CHAPTER 4 Any changes to these requirements require prior approval by the Company.

Each vendor, supplier, or contractor has an acceptable quality assurance program, which is consistent with applicable regulatory requirements for the item or service.

The Nuclear Oversight Vendor Audit Group (NOVA) maintains a controlled list of evaluated suppliers that are audited on a triennial basis. The evaluated list of such vendors, suppliers, and contractors is described in controlling procedures for the appropriate safety classification except for procurement from other licensees that has a NRC approved quality program.

Procurement documents require the vendors to incorporate quality assurance program requirements in sub-tier procurement documents and allow right of access to the vendors, sub-tier vendors, and contractors facilities and records for inspection or audit by the Company or designated representative.

2.2.4. Non-conformances The Company procurement documents specify the requirements for reporting and approving the disposition of supplier non-conformances. "Use as is" or "Repair" requires approval of the supplier disposition by the appropriate Company representative.

2.2.5. Documentation Requirements The procurement documents shall identify, at all tiers, the documentation required to be submitted for information, review, and approval including the time requirements for submittal. The Company procurement documents require the supplier to maintain specific quality assurance documents including retention times and disposition requirements.

2.2.6. Spare and Replacement Parts The procurement documents require the identification of appropriate spare and replacement parts or assemblies and the appropriate delineation of the technical and quality assurance related data required for ordering these parts or assemblies. These spare parts and replacement items are at least equivalent to the original design requirements or those specified by a properly reviewed and approved revision.

2.3. Procurement Document Review Measures are established in controlled procedures to ensure the appropriate technical and quality requirements are established for the material, equipment, and services purchased from vendors, suppliers, or contractors prior to release for bid and contract award.

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PROCUREMENT DOCUMENT CONTROL CHAPTER 4 These documented reviews, including changes to the specification or purchase order, ensure the technical and quality requirements are correctly stated, inspectable, and controllable and have adequate acceptance and rejection criteria and are prepared, reviewed, and approved in accordance with QAP requirements.

Review of the exceptions or changes requested by the supplier shall be analyzed to ensure they do not change or impact the technical or quality requirements and are incorporated in to the procurement documents, prior to the supplier proceeding, using the same review and approval process as appropriate except for commercial terms and editorial changes.

Personnel who have access to pertinent information and who have an adequate understanding of the requirements and intent of the procurement documents shall perform reviews required by this chapter.

2.4. Procurement Records.

Records as required by the procurement documents or the QATR are retained in the Company's department files, vendor files, or both locations.

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INSTRUCTIONS, PROCEDURES, AND CHAPTER 5 DRAWINGS

1. SCOPE Activities governed by the Company's QAP shall be performed as directed by documented instructions, procedures, and drawings appropriate for the activity.

The requirements for the use of these procedures shall also be prescribed in writing. These instructions, procedures, and drawings shall include responsibilities and acceptance criteria as applicable or appropriate for the activity.

Those participating in any activity shall be aware of and use the proper and current revision of instructions, procedures, drawings, and engineering requirements for performing the activity. Procedures may include reference to vendor equipment manuals, design drawings and specifications, prerequisites, special precautions, and the delineation of work to be performed. Equipment Manuals and manufacturers instructions shall be readily available for use.

2. REQUIREMENTS 2.1. General Operation, maintenance, or modification of equipment shall be preplanned and performed in accordance with written procedures that are appropriate to the circumstances and that conform to applicable codes, standards, specifications, and criteria. Documents identify and specify the content of records to be generated in conducting the activity. The establishment and execution of quality procedures shall be used by the station staff or those under their direction, for operating, maintenance, modifications, in-service inspection, refueling, and stores activities.

Temporary procedures may be issued to provide guidance in unusual situations that are not within the scope of the normal procedures. Temporary procedures shall be subject to review and approval, and shall include designation of the time period during which they may be used. In the event of an emergency not covered by an approved procedure, authorized personnel shall provide appropriate direction to minimize personnel injury and damage to the facility and to protect the health and safety of plant personnel and the general public.

2.2. Preparation and Review Procedures shall be prepared, reviewed, approved, and used as prescribed in writing, and shall contain step by step instructions in the degree of detail necessary for qualified individuals to perform the required function or task.

Where appropriate, these procedures will include checklists containing the necessary attributes to be observed or measured.

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INSTRUCTIONS, PROCEDURES, AND CHAPTER 5 DRAWINGS These documents shall include or reference appropriate quantitative or qualitative acceptance criteria for determining that prescribed activities have been satisfactorily accomplished.

The procedures will be independently reviewed and evaluated by other involved company organizations with interface responsibilities and the comments forwarded to the issuing department.

2.3. Procedures and Programs Review and approval of site procedures are performed in accordance with technical specification requirements as delineated in the Technical Review or Station Qualified Review (SQR) programs.

2.3.1. Technical Review and Control

1. Procedures required by a station's Technical Specifications and other procedures which affect nuclear safety, as determined by the manager responsible for station operation, and changes thereto, other than editorial or typographical changes, shall be reviewed as follows prior to implementation, except as noted in item 5 (below).

- Each procedure or procedure change shall be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change. This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary.

If deemed necessary, the reviews shall be performed by the qualified review personnel of the appropriate discipline(s).

- Applicable Administrative Procedures recommended by Regulatory Guide 1.33 shall be submitted to the Plant Operations Review Committee (PORC) as applicable, for review prior to implementation. The PORC shall recommend approval or disapproval based on their review.

- Review of procedures or procedure changes to those procedures, that describe the means for controlling or operating structure, systems, and/or components as described in the UFSAR, will include a review to determine if NRC review and approval is necessary prior to the implementation of the procedure activity.

This review is based on the review of a written 10CFR50.59172.48 review and evaluation prepared by qualified individual(s), or documentation that a 10CFR50.59/72.48 evaluation is not required. The PORC and the NSRB shall review and recommend approval of items requiring NRC review and approval prior to station approval for implementation. NRC approval shall also be obtained prior to station approval for implementation.

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INSTRUCTIONS, PROCEDURES, AND CHAPTER 5 DRAWINGS

- Department head approval authority shall be as specified in station procedures.

- Written records of reviews performed in accordance with this specification shall be prepared and maintained.

- Editorial and typographical changes shall be made in accordance with station procedures.

2. Technical reviewers shall advise their supervisors and/or PORC on all matters related to nuclear safety that are identified during reviews. The reviewer shall be other than the originator. The reviewer shall determine if additional cross-disciplinary reviews are required to ensure all applicable technical disciplines are included. This review shall ensure technical accuracy, compliance with regulatory requirements, and shall verify the originator's determination of whether items reviewed constitutes a change to the Technical Specifications, Operating License, or if NRC review and approval is required prior to implementation.

3. Technical reviewers shall be qualified to perform technical reviews based on the individual's training, experience, and knowledge level. Technical reviewers, assigned the responsibility for reviewing 10CFR50.59/72.48 reviews and evaluations, shall receive training in this process. Technical reviewers shall be qualified to perform this function and meet the experience requirements per applicable standards. Personnel shall have expertise in one or more of the following disciplines as appropriate, for the subject or subjects being reviewed:

- chemistry

- instrumentation and controls

- mechanical and electrical systems

- nuclear power plant technology

- radiological controls

- reactor engineering

- reactor operations

4. Technical reviews shall be documented and records maintained.

5. Temporary Changes Temporary changes to procedures required by 2.3.1.1 (above) may be made provided:

- the intent of the original procedure is not altered.

- the change is approved by two members of the plant management staff knowledgeable in the areas affected by the procedures, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

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INSTRUCTIONS, PROCEDURES, AND CHAPTER 5 DRAWINGS

- the change is documented, reviewed, and approved in accordance with 2.3.1 (above) within 14 days of implementation.

2.3.2. On-site Qualified Technical Review (Dresden Unit 1)

A Qualified Technical Reviewer shall conduct thorough reviews of the documents specified below. Persons performing these reviews shall be knowledgeable in the subject area being reviewed. Qualified technical reviews must be completed prior to implementation of proposed activities.

1. Qualified Technical Reviewers shall be individuals without direct responsibility for the document under review; these reviewers may be from the same functionally cognizant organization as the individual or group performing the original work.

2. Qualified Technical Reviewers shall have at least 5 years of professional experience and either a Bachelor's degree in Engineering or the Physical Sciences or shall have equivalent qualifications evaluated on a case by case basis and approved by the manager responsible for decommissioning activities. The appointment of Qualified Technical Reviewers shall be documented.

3. A Qualified Technical Reviewer shall independently review the following subjects:

- Proposed changes to the license, technical specifications, or bases.

- Proposed changes to the programs required by the Technical Specifications to verify that such changes do not involve a change to the Technical Specifications and will not require NRC review and approval as defined in 10CFR50.59/72.48.

- 1 OCFR50.59 evaluations for changes in the facility as described in the De-fueled Safety Analysis Report (DSAR), changes in procedures as described in the DSAR, and tests or experiments not described in the DSAR to verify that such actions do not involve a change to the Technical Specifications or will not require NRC review and approval as defined in 10CFR50.59.

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INSTRUCTIONS, PROCEDURES, AND CHAPTER 5 DRAWINGS 2.4 Program/ Procedure Review and Approval (Limerick Specific Only)

All programs and procedures required by Limerick Technical Specification 6.8 shall be reviewed and approved as described below.

1. Each new program, procedure, or change thereto shall be independently reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in the functional area affected but is not the individual preparer. The SQR may be from the same organization as the preparer. The SQR shall render a determination in writing of whether or not cross-disciplinary review of a new program, procedure, or change thereto is necessary. If necessary, such review shall be performed by appropriate personnel.

2. Each new program, procedure, or change thereto shall be reviewed by the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that program or procedure, and the review shall include a determination of whether or not a 10 CFR 50.59 evaluation is required.

3. If a 10 CFR 50.59 evaluation is not required, the new program, procedure, or change thereto shall be approved by the responsible Director or Manager or the Plant Manager prior to implementation.

Administrative Procedures shall be reviewed by PORC prior to approval.

Administrative Procedures, Security Plan Implementing Procedures, and Emergency Plan Implementing Procedures shall be approved by the Plant Manager or his designated alternate in accordance with Limerick Technical Specification 6.1.1.

4. If the responsible Director or Manager determines that a new program, procedure, or change thereto requires a 10 CFR 50.59 evaluation, the responsible Director or Manager shall render a determination in writing of whether or not the new program, procedure, or change thereto requires NRC approval pursuant to 10 CFR 50.59, and shall forward the new program, procedure, or change thereto with the associated 10 CFR 50.59 evaluation to PORC for review.

If NRC approval is required, obtain NRC approval prior to implementation of the new program, procedure, or change.

5. Personnel recommended to be SQRs shall be approved and designated as such by the PORC Chairman. The responsible Director or Manager shall ensure that a sufficient complement of SQRs for their functional area is maintained in accordance with Administrative Procedures. The SQRs shall meet or exceed the qualifications described in Section 4.4 of ANSI/ANS 3.1-1978.

6. Temporary procedure changes shall be reviewed and approved in accordance with QATR Chapter 5, paragraph no. 2.4.7.

Records documenting the activities performed under paragraph nos. 2.4.1 through 2.4.6 shall be maintained in accordance with Limerick specific requirements identified in Chapter 17 of the QATR.

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INSTRUCTIONS, PROCEDURES, AND CHAPTER 5 DRAWINGS

7. Temporary changes to procedures identified in Limerick Technical Specification 6.8.1 may be made provided:

a. The intent of the original procedure is not altered;

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and

c. The change is documented, reviewed by an SQR in accordance with QATR Chapter 5, paragraph no. 2.4.1, and approved by either the Plant Manager or his designated alternate in accordance with Limerick Technical Specifcation no. 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation.

8. Each procedure of Limerick Technical Specification 6.8.1, and changes thereto, and any other procedure or procedure change that the Plant Manager determines to affect nuclear safety, shall be reviewed and approved in accordance with QATR Chapter 1, paragraph no. 2.7.1 and/or QATR Chapter 5, paragraph no.

2.4, as appropriate, prior to implementation. Each procedure of Limerick Technical Specification 6.8.1 shall also be reviewed as set forth in Administrative Procedures.

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DOCUMENT CONTROL CHAPTER 6 DOCUMENT CONTROL CHAPTER 6

1. SCOPE Measures shall be established to control and coordinate the classification, review, approval, issuance, revision, and change of documents that prescribe methods or provide the technical and/or quality requirements for activities and items within the scope of this program. These measures shall ensure that such documents are reviewed for adequacy, approved for release and use, and distributed to the location where the activity is performed

2. REQUIREMENTS 2.1. General The Company document control process ensures that procedures are reviewed and approved before initial use. The Company has in place programmatic controls, which ensure that procedures are technically and administratively correct before use. These programmatic controls ensure that procedures are reviewed and revised as needed, when pertinent source material is changed, when the plant design is changed, or when deficiencies are identified and corrected. Provisions shall be established to ensure that infrequently used procedures are reviewed prior to use, unless they have been reviewed within the previous two years. Except as noted in Appendix C, periodic biennial review requirements are satisfied by implementation of several processes and programs. These processes and programs provide the programmatic controls that ensure the required reviews are accomplished and include the following:

- Commitment Management and Tracking Process.

- Integrated Reporting/Corrective Action Program.

- Operational Experience Feedback Program.

- Plant Modification Program.

- Procedure Feedback Process.

- Technical Specification and Updated Final Safety Analysis Report Revision Programs.

- Vendor Information Program.

2.2. Reviews The company has also established provisions to ensure that the following reviews are conducted:

- inspection, identification of inspection personnel, and documentation of inspection results.

- maintenance, modification, and inspection procedures are reviewed by qualified personnel, knowledgeable in quality assurance disciplines.

- necessary inspection requirements, methods, and acceptance criteria have been identified.

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DOCUMENT CONTROL CHAPTER 6 DOCUMENT CONTROL CHAPTER 6 2.3. Controlled Documents Written document control procedures shall be established to provide for the control of approved documents. Documents that are controlled include, but are not limited to, the following items:

- as-built drawings.

- calibration procedures.

- computer codes and software.

- corrective action reports.

- design specifications.

- emergency operating procedures.

- engineering calculations.

- inspection and test reports.

- nonconformance reports.

- NOS procedures.

- operating procedures.

- purchase orders and related documents.

- safety analysis reports.

- supplier audit and surveillance procedures.

- technical specifications (station and Independent Spent Fuel Storage Installation)

- temporary and emergency procedure changes.

- topical reports.

- work instructions and procedures.

2.4. Control Measures The Company document control process includes the following document control measures:

- coordinating and controlling interface documents.

- distributing documents approved for issuance in accordance with updated and current distribution lists.

- establishing document control procedures to assure that proper documents are accessible and are being used.

- establishing lists of documents controlled by organizations involved with activities affecting quality.

- establishing procedural requirements for the protection of safeguards information

- identifying and assuring that proper documents are used in performing activities affecting quality.

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DOCUMENT CONTROL CHAPTER 6 DOCUMENT CONTROL CHAPTER 6

- identifying qualified individuals or organizations responsible for preparing, reviewing, approving and issuing documents, including revisions.

- recalling or identifying obsolete documents.

2.5. Document Changes The Company document control process ensures changes to documents are reviewed and approved by the same organizations that performed the original review and approval, unless delegated to another responsible organization. The reviewing organization has access to pertinent background data or information upon which to base their approval. To avoid a possible omission of a required review, the Company document control process includes provisions to control minor changes.

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CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES .I

1. SCOPE The Company establishes measures to assure the quality of purchased material, equipment and services conform to procurement document requirements for items contained within the QATR.

2. REQUIREMENTS 2.1. Supplier Selection 2.1.1. General The Company establishes measures to assure that purchased material, equipment, and services conform to the procurement documents for safety related and ASME code specifications as appropriate. This assurance is accomplished by controlling both the selection of procurement sources and acceptance of the product at the source and/or upon receipt at the appropriate location.

The company procedures, which address the procurement process and receipt and storage of material and equipment, clearly define the responsibilities and interfaces between the line requisitioning organization, engineering, supply and quality assurance.

2.1.2. Methods The Company establishes measures for evaluation and selection of procurement sources and must be completed prior to the award of contract. These measures include one or more of the following:

- evaluation of the supplier's history of providing an identical or similar product that performs satisfactorily in actual use.

- supplier's current quality records supported by documented qualitative and quantitative information that can be objectively evaluated.

- supplier's technical and quality capability of meeting the applicable quality requirements of 10CFR50 Appendix B as determined by a direct evaluation of its facilities and personnel and the implementation of its quality assurance program.

- review and evaluation of audits, surveys, and inspections conducted by other utilities, or American Society of Mechanical Engineers (ASME).

The Company documents and files the results of these measures and maintains an evaluated list of suppliers.

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CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES 2.2. Bid Evaluations The Company reviews and evaluates bids and awards contracts using written procedures and documents the results. The Company designates individuals or organizations to review bids to assure that they conform to the procurement document requirements and the supplier has the appropriate technical ability, Quality Program, production capability, personnel, and acceptable past performance to supply the product or service. The Company obtains commitments to resolve unacceptable quality conditions identified as part of the bid evaluation before award of the contract and ensure exceptions and alternatives do not impact the technical or quality requirements.

2.3. Supplier In-Process Control 2.3.1. General The Company establishes measures to interface with and to verify supplier performance. These measures include the following items:

- establishing an understanding between the Company and the supplier of the provisions and specifications contained in the procurement documents.

- establishing a method of document information exchange between the Company and the supplier.

- establishing the extent of source surveillance and inspection activities.

- identifying and processing necessary change information.

- requiring the supplier to identify planning techniques, tests, inspections, and processes to be used in fulfilling procurement document requirements.

- reviewing supplier documents that are generated or processed during activities fulfilling procurement requirements.

2.3.2. In-Process Control and Verification Planning The Company and the supplier, establish as appropriate, notification points, including hold and witness points and incorporate into the appropriate documents based upon the complexity and scope of the item or service. When required by the procurement document or specification, surveillances and evaluations at the supplier's facility are conducted to verify continued compliance with the quality assurance requirements of the procurement documents.

Qualified individuals or its agents accomplish source inspections at the supplier's facility to verify that the procurement item or service is being supplied in accordance with the requirements of the procurement documents.

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CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES Such inspections, examinations or tests are accomplished in accordance with written procedures, plans, and/or checklists containing or referencing appropriate acceptance criteria. Upon acceptance by source verification, the Company furnishes documented evidence of acceptance to the receiving destination of the item, to the purchaser, and to the supplier.

2.3.3. Programmatic Verification The Company or its agents verify the effectiveness of the supplier's quality program by survey, audit or surveillance. Verification is performed at intervals consistent with the importance to safety, complexity and quality of the product or services furnished. Activities are witnessed or observed and the results documented when source verification is performed.

The Company conducts audits per the requirements established in Chapter 18 or reviews audits performed by other license holders as defined in procedures.

The results of these audits are used to support the maintenance of the list of evaluated suppliers. Verification activities are conducted as early as practicable so that subsequent activities do not prevent disclosure of deficiencies. The Company's verification activities do not relieve the supplier of its responsibility for quality verification.

2.3.4. Supplier and Verification of Supplier Performance Records The Company establishes methods to control, handle and approve supplier documents. Suppliers submit their documents per procurement requirements.

Acceptance criteria is used for the acquisition, processing, and record evaluation of technical inspection and test data.

The Company records activities to verify supplier conformance with the requirements of procurement documents. Source surveillances, procurement plans, inspections, audits, surveys, receiving inspections, non-conformance dispositions, waivers and corrective actions concerning supplier activities are documented. This documentation is used to determine the supplier's quality assurance program effectiveness.

2.3.5. Control of Procurement Changes The Company documents changes to procurement documents involving technical or quality assurance matters. These changes are subjected to the same review and approval process as the original procurement document except for commercial terms and conditions and editorial changes.

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CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES 2.4. Acceptance of Purchased Items and Services 2.4.1. General Upon receipt the applicable materials, parts, and components are controlled.

Qualified inspection personnel are responsible for inspecting, releasing, and maintaining the inspection status of purchased material and equipment. After receipt inspection, the purchased material is placed in a controlled storage area or issued for installation or further work.

2.4.2. Acceptance by Receiving Inspection The Company uses approved procedures to accept purchased items and services. Acceptance of an item or service from a supplier includes certificate of conformance, source verification, receiving inspection or post installation testing at the plant location or a combination thereof. Items are inspected during receipt using approved procedures and checklists.

The Company does receiving inspections using procedures and inspection instructions to verify conformance to the specified requirements, using objective evidence to check such features as: complete documentation and visual inspection of: proper configuration; identification; dimensional, physical and other characteristics; freedom from shipping damage; and cleanliness. Items, which can not meet the purchase order requirements, will be segregated and controlled as defined in the applicable procedures.

The Company coordinates the review of supplier documentation with the receiving inspection when procurement documents require such documentation to be furnished prior to the receiving inspection. Source verification and audit activities are factored into the receipt inspection activities as appropriate.

2.4.3. Acceptance by Source Verification The Company considers acceptance by source verification when the item or service is:

- vital to plant safety; or

- difficult to verify quality characteristics after delivery; or

- complex in design, manufacture, and test.

Source verification shall be implemented in accordance with plans to perform inspections, examinations, or tests at pre-determined points. Upon acceptance by source verification, the Company furnishes documented evidence of acceptance to the receiving destination of the item, to the purchaser, and to the supplier.

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CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES 2.4.4. Acceptance by Certificate of Conformance The supplier's certificate of conformance attests the product or service provided is in accordance with the procurement documents is reviewed during source and/or receipt inspections to verify compliance. This document provides the purchase order number; codes, standards or other specifications required to be met in the purchase order. Requirements which cannot be met must be included with an explanation why and a means to resolve the non-conformances. A person who is responsible for quality assurance function attests to this certificate The validity of a supplier's certificate of conformance is ascertained through any of the following methods source inspection, independent inspection agency, receipt inspections, surveillance, testing of hardware, quality assurance audits or surveillances at intervals commensurate with the suppliers past performance.

Inspection and test activities verify that the hardware performs in accordance with applicable technical requirements and serve to demonstrate that the hardware meets the requirements stated in a certificate of conformance.

The results of the source and/or receipt inspections, the acceptability of supplier furnished documentation, and the resulting determination of conformance or nonconformance is documented.

2.4.5. Acceptance by Post Installation Testing When post-installation testing is used, the Company and the supplier mutually establish post-installation test requirements and acceptance documentation.

Acceptance by this method is satisfactory when performed following the accomplishment of at least one preceding method and when:

- it is difficult to verify the quality characteristics of the item without it being installed and in use; or

- the item requires an integrated system checkout or test with other items to verify its quality characteristics; or

- the item cannot prove its ability to perform its intended function except when in use.

2.4.6. Acceptance of Services Only In cases involving procurement of services only, the Company accepts the service by any of the following methods:

- technical verification of data produced.

- surveillance, audit, survey, or assessment of the activity.

- review of objective evidence for conformance to the procurement document requirements such as certifications, stress reports, etc.

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CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES In lieu of the above the Company performs a receiving inspection for items arriving back onsite that were sent offsite for repair, testing, or rework.

2.4.7. Commercial Grade Items Where the safety related design utilizes commercial grade items, the following requirements are a permissible alternative for acceptance, to other requirements of this Chapter:

1. An approved design document identifies the commercial grade item. (An alternate commercial grade item may be applied, provided the cognizant design organization provided verification that the alternate commercial grade item will perform the intended function and will meet design requirements applicable to both the replaced item and its application.)

2. The Company performs source evaluation and selection, where determined necessary, based on complexity and importance to safety.

- commercial grade dedication plans for use in a safety related applications state responsibility for 10CFR21 requirements.

- the Company identifies commercial grade items in the purchase order by the supplier's published product description.

3. One or a combination of the following methods shall be utilized to provide reasonable assurance that the item meets the acceptance criteria for the characteristics identified to be verified for acceptance:

- acceptable supplier/item performance records.

- commercial grade survey of the supplier.

- source verification.

- special test(s) or inspection(s) or both.

4. After receipt of a commercial grade item, the Company determines the following:

- damage was not sustained during shipment.

- documentation, as applicable to the item, was received and is acceptable.

- inspection and/or testing are accomplished, as required by the purchaser, to assure conformance with the manufacturer's published requirements.

- the item received was the item ordered.

2.5. Presence of Documentary Evidence Documented evidence that material or equipment conforms to procurement requirements is present at the site before use or installation. This documentary evidence is traceable to the item and shall be retained at the nuclear power plant Revision 76 of 7 Page 66 of 7 Revision 76

CONTROL OF PURCHASED MATERIAL, CHAPTER 7 EQUIPMENT, AND SERVICES site and shall be sufficient to identify the specific requirements such as codes, standards, or specifications met by the purchased material and equipment.

2.6. Spare or Replacement Items Procedures control the procurement, storage and issuance of materials and components including spare and replacement parts. Procurement documents for these items identify the appropriate technical and quality related requirements. The Company purchases spare parts and replacement items, equipment and components to at least the original design requirements or those specified by a properly reviewed and approved revision.

Where the QA requirements of the original item cannot be determined, qualified individuals conduct an engineering evaluation to establish appropriate requirements and controls. This evaluation insures that interfaces, interchangeability, safety, fit and function are not adversely affected or are contrary to applicable regulatory or ASME Code requirements. The evaluators document their results.

Where the company procured the original item with no specifically identified quality assurance program requirements, or from an Original Equipment Manufacturer/Supplier (OEM/OES) who no longer is on a list of evaluated suppliers identical (like-for-like) items may be similarly procured from the OEM/OES through the use of procurement plans.

In such cases, the Company conducts a joint technical engineering and quality assurance documented evaluation to established requirements and controls to assure at least equivalent product performance. The evaluation shall assure that interfaces, interchangeability, safety, fit and function are not adversely affected or are not contrary to applicable regulatory or ASME Code requirements.

2.6.1. Procurement from Other Utilities Purchases of safety related items can be made from other utilities who have had an NRC approved QA Program in effect at the time of their procurement and receipt and such utility has maintained a quality system program for storage, handling, and maintenance with documented traceability to the manufacturer of the items.

Certificates-of-Conformance to the above requirements and associated required documentation are provided.

2.6.2. Maintenance or Modification The Company performs maintenance or modifications that may affect the function of safety related structures, systems, or components in a manner to assure quality at least equivalent to that specified in original design bases and requirements, materials specifications, and inspection requirements.

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IDENTIFICATION AND CONTROL OF CHAPTER 8 MATERIALS, PARTS, AND COMPONENTS

1. SCOPE Controls are established to assure that only correct and accepted items are used or installed. Identification shall be maintained on the items or in documents traceable to the items, or in a manner, which assures that identification is established and maintained.

2. REQUIREMENTS 2.1. General The Company establishes measures for the identification and control of materials, parts and components, including partially fabricated assemblies, and assures that only correct and accepted items are used or installed. Identification is maintained on the items or in documents traceable to the items. Physical identification shall be used to the maximum extent possible.

Provisions are in place to maintain markings, which could be damaged during shipping or handling or deterioration due to environmental exposure. Provisions are also established to control nonconforming items and maintain parts, material, and equipment in storage traceable to quality assurance documents.

2.2. Traceability Items within the scope of the QAP shall be identified, so that they can be traced to the appropriate documentation, which provides objective evidence that the technical and quality requirements are met.

Responsible organizations document and maintain identification and traceability of items from initial receipt, throughout fabrication, installation, and use of the items such as: subassemblies, components, equipment numbers, part numbers, serial number, heat treatment number, batch or lot numbers.

When installed material or equipment is removed for maintenance, repair, or modification, control measures are implemented to ensure proper identification and traceability is maintained. Before use or installation of an item, the installer verifies that identification has been maintained.

2.3. Identification Methods Identification is on the item where practicable. Identification is clear, unambiguous and indelible. Identification does not affect the fit, function, quality, and service life of the item. If the item cannot be practicably marked, the Company uses records traceable to the item for identification.

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IDENTIFICATION AND CONTROL OF CHAPTER 8 MATERIALS, PARTS, AND COMPONENTS If physical identification is either impractical or insufficient for proper control, the Company controls an item by physical separation, procedural control or other appropriate means.

2.4. Transfer of Markings Prior to cutting or dividing material, each new piece shall be marked with the same traceability markings of the original piece to ensure that the traceability of the material is maintained. These markings shall not be obliterated or hidden by surface treatment or coatings unless other means of identification are substituted. The Company independently verifies proper identification of each piece.

2.5 Limited Life Items The Company identifies and controls items having limited life to preclude use of items whose shelf life or operating life has expired.

2.6 Stored Items The Company uses procedures to assure proper control of identification for items in storage.

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CONTROL OF SPECIAL PROCESSES CHAPTER 9 CONTROL OF SPECIAL PROCESSES CHAPTER 9

1. SCOPE Processes affecting quality of items or services shall be controlled. Special processes that control or verify quality, shall be performed by qualified personnel, using qualified procedures, in accordance with specified requirements and are properly documented and evaluated. These requirements are defined in codes, standards, specifications, or special instructions. The quality of such processes is assured through reliance on operator skill and in-process control. Examples of special processes include, but are not limited to welding, heat treating, chemical cleaning, and non-destructive examination (NDE).

2. REQUIREMENTS 2.1. General The Company organization directing work during repair, replacement, modification, or in-service inspection (151) activities is responsible for controlling special processes. Special process controls are assured through independent assessment and inspection activities.

2.2. Process Control Instructions, procedures, drawings, checklists, or other appropriate means control processes. Process controls specify the prerequisite steps, processing details, conditions to be maintained during the process, equipment requirements, inspection and test requirements, acceptance criteria, and record requirements. Controlling includes:

- maintenance and retention of records.

- personnel qualification.

- procedure development and qualification.

- procedure implementation.

- qualification of equipment.

2.3. Special Processes Measures shall be established and documented to assure that special processes are accomplished under controlled conditions in accordance with applicable codes, standards, applications criteria, regulatory requirements and commitments, and other special requirements including the use of qualified personnel and procedures. Special processes are controlled by instructions, procedures, drawings, checklists, travelers, or other appropriate means.

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CONTROL OF SPECIAL PROCESSES CHAPTER 9 CONTROL OF SPECIAL PROCESSES CHAPTER 9 Special process controls specify the preparatory steps, processing details, conditions to be maintained during the process, equipment requirements, inspection and test requirements, acceptance criteria, and record requirements.

Special process procedures are written and qualified in accordance with applicable requirements. Special process procedures are reviewed and approved as follows:

- coating and ASME Code concrete placement procedures are reviewed and approved by the appropriate Company organizations.

- Company heat treating, welding, brazing, and other non-NDE procedures are reviewed and approved by Engineering.

- Company NDE procedures are reviewed and approved by the appropriate Company Level 111.

- contractor, subcontractor,Section III, Xl, and other ISI-related NDE procedures are reviewed and approved by the Company NDE Level Ill.

- the responsible Company engineering organization reviews contractor and subcontractor special process procedures.

When permitted by applicable requirements, the Company may direct contractors or subcontractors to use Company special process procedures. The Company assures that qualification of Company, contractor, and subcontractor ASME Code NDE procedures is verified by the Authorized Inspection Agency (AIA). When there is a specific reason to question whether special process procedure requirements are being met, the Company, or the AIA may require re-evaluation of the procedure before work may proceed.

For special processes not covered by the existing codes or standards, or when the quality requirements of an item exceed the requirements of established codes or standards, the necessary qualifications of personnel, procedures and equipment shall be defined in the procedure.

2.4. Personnel Qualification Company, contractor, and subcontractor personnel performing special processes are trained, tested, qualified, or certified in accordance with a procedure that meets applicable requirements. When permitted by applicable requirements, the Company may qualify and control contractor and subcontractor personnel.

The Company assures that qualification of Company, contractor, and subcontractor ASME Code NDE personnel is verified by the AIA. When there is a specific reason to question the ability of an individual performing special processes, the Company, or the AIA may require re-evaluation before that individual will be permitted to resume work. Individuals failing any retest will be removed from applicable operations pending re-qualification.

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CONTROL OF SPECIAL PROCESSES CHAPTER 9 CONTROL OF SPECIAL PROCESSES CHAPTER 9 The appropriate NDE Level IlIl is responsible for personnel and procedure development and qualification to ASME Code requirements for nondestructive examination. This position holder is qualified and certified in accordance with ASNT SNT-TC-1A / ASNT CP-189 and may designate qualified deputies for certification of personnel and procedures, and final Company authority of the interpretation of any NDE indication that has been recorded by a Level II Examiner or by a NDE contractor's Level IlIl examiner.

Training and certification of personnel associated with nondestructive examination are carried out in accordance with the requirements of ASME NQA-1 and ASME Section Xl. A Level IlIl certified person administers all ASME Code examination activities.

2.5. Special Process Records Special process records provide evidence that special processes were performed in accordance with approved procedures by qualified personnel.

These records are retained by the Company or by the contractor or subcontractor as required by procurement documents. Records are maintained for currently qualified personnel, processes, and equipment for each special process.

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INSPECTION CHAPTER 10 INSPECTION CHAPTER 10

1. SCOPE The Company plans and executes an inspection program to verify that activities affecting the quality of safety-related structures, systems, and components conform to documented requirements. For modification and non-routine maintenance activities, inspections are conducted in a manner similar (i.e.

frequency, type and personnel performing such inspections) to those associated with construction phase activities. The independent inspections described in this Chapter are not intended to dilute or replace the clear responsibility of the first line supervisors for the quality of work performed under their supervision or personnel performing the activity.

2. REQUIREMENTS 2.1. General The Company establishes controls for coordination and execution of inspection plans. Company quality verification organizations or other qualified organizations are responsible for implementation of established inspection plans. If an inspection plan includes inspections by personnel other than those in a quality verification organization, the inspection requirements, personnel qualification criteria, and inspector independence will be accepted by the responsible quality organization prior to implementation.

2.2. Inspection Plans The Company prepares documented inspection plans. These inspection plans are applied when the activity is started. The inspection plans may be separate documents or an integral part of approved instructions, procedures or drawings.

Related codes, standards, specifications and design documents are used to develop the inspection plans. Procedures used for documenting inspection plans are selectively reviewed, as appropriate, by NOS to assure that necessary verification points and inspection criteria are included. The plans identify:

- acceptance criteria.

- activities to be inspected.

- inspection characteristics.

- inspection techniques/equipment (including accuracy requirements).

- provisions for inspection and test status.

- provisions for the recording of inspection results.

- qualification requirements.

- responsible organizations.

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INSPECTION CHAPTER 10 INSPECTION CHAPTER 10 2.3. Inspection Personnel and Qualification A qualification program is established and documented to conform to applicable codes, standards, or licensing requirements. Qualifications and certifications are kept current.

Qualified personnel perform inspections. Inspectors with valid certifications perform inspections for acceptance. Inspectors are independent of those who perform or directly supervise the activity being inspected. On-the-Job training inspections shall be performed under the direct supervision of qualified personnel.

Second line supervisory personnel may conduct inspection of operating activities or other qualified personnel not assigned first line supervisory responsibility for the conduct of the work. Operating activities are defined as work functions associated with normal operations of the plant, routine maintenance, and certain technical services routinely assigned to the onsite operating organization.

2.4. Inspection Process Inspections are performed using approved instructions, procedures, process sheets, travelers, or checklists and applicable drawings.

- Inspections are performed for each work or operating activity where necessary to verify quality. Where inspection sampling is used to verify the acceptability of a group of items, the sampling procedure shall be based on recognized standard practices.

- Process monitoring may be used when inspection of processed material or products is impossible or impractical. When necessary, to ensure quality throughout the duration of the process, both inspection and process monitoring will be systematically used to verify conformance to requirements.

- ~When inspections must be performed before work can continue, hold points are established in appropriate documents. Consent to waive hold points are recorded prior to continuation of work. When inspection is desired, but not mandatory before work can continue, witness points are established. Completion of hold and witness points is documented.

- When acceptance criteria are not met, corrected areas are re-inspected.

Changes to, or rework of, an item after inspection requires re-inspection of the affected areas. Such inspections are documented in the Corrective Action Program.

- A final evaluation is performed. Inspection results are reviewed to confirm that required inspections and quality records have been completed, identified non-conformances have been resolved and the item conforms to specified requirements. Engineering, Maintenance, Operations or Quality Verification approves final acceptance of the item.

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INSPECTION CHAPTERI10

- Inspection records are of sufficient detail to confirm completion and, as a minimum, identify:

- authorized individual approving results.

- date of inspection.

- inspector/Data recorder.

- item inspected.

- M&TE used.

- reference to action taken in connection with identified non-conformances.

- results or acceptability.

- type of observation.

- When the inspection activity is performed using a separate procedure, the procedure and its revision is recorded.

2.5. In-Service Inspections A program for the required ISI/IST inspection of completed systems, structures and components shall be planned and executed by or for the organization responsible for the operation of the plant to assure that plant components perform satisfactorily under all operating conditions.

Inspection methods shall be established and executed to applicable codes, standards and regulations, including baseline examinations and subsequent periodic examinations, which continue through the life of the plant in accordance applicable technical specifications.

2.6. Independent Verification Independent verifications are conducted by qualified personnel using approved procedures. Characteristics to be verified and methods to be employed shall be specified. Verification results and unacceptable conditions identified shall be documented. Verifications shall be performed by persons other than those who performed or directly supervised the work being verified. Personnel must have qualifications of greater than or equal to the activity being verified.

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TEST CONTROL CHAPTERI11 TEST CONTROL CHAPTER 11

1. SCOPE A documented test program shall be established in accordance with applicable technical specifications, license conditions, and design documents to assure that all testing required demonstrating that the structures, systems, or components within the scope of this QAP will perform satisfactorily in service.

2. REQUIREMENTS 2.1. General 2.1.1. Testing Program The Company establishes and controls a test program to assure that design and performance criteria have been satisfied and assures that testing does not adversely affect the safe operation of the plant. The test program includes, as appropriate, procedures to ensure those structures, systems, subsystems, and components will perform in service. Testing is conducted by appropriately trained and qualified personnel. The extent of testing shall be based on the complexity of the modification, replacement, or repair. The test program covers all required tests including:

- operational tests.

- production tests.

- prototype qualification tests.

- tests during design.

- tests during fabrication.

- the demonstration of satisfactory performance following plant maintenance and modifications or procedural changes.

- those tests required by plant maintenance or modifications.

2.1.2. Test Procedures The program uses written test procedures which include the requirements and acceptance limits from applicable design documents. The Company reviews and approves test procedures and changes to test procedures, including changes that alter test sequence, in a similar manner to the original.

The organization responsible for the design of the item to be tested establishes the test requirements and acceptance criteria. Test requirements and acceptance criteria are based upon specified requirements contained in applicable design or other pertinent documents. Test requirements include specific characteristics to be tested.

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TEST CONTROL CHAPTER 11 TEST CONTROL CHAPTER 11 The Company specifies specific test methods when they must be employed, uses written procedures or checklists, and documents the status of equipment both before and after testing.

The Company may use appropriate sections of related documents, such as ASTM methods, supplier manuals, equipment maintenance instructions, or approved drawings or travelers with acceptance criteria in lieu of specially prepared written test procedures. Such documents must include adequate instructions to assure the required quality of work. Test and inspection procedures contain:

- a description of objectives.

- acceptance criteria or limits contained in applicable design or other source documents, such as vendor's literature, engineering drawings or plant specifications that will be used to evaluate results.

- any special equipment or calibrations required to conduct the test or inspection.

- responsibilities.

- instructions or checklists used to verify or document that affected plant systems are arranged in their correct lineup and for restoring the system to the condition consistent with the normal operating status.

- limiting conditions.

- prerequisites for, or checks to be made prior to performing the tests or inspections including any special conditions to be used to simulate normal or abnormal operating conditions.

- data documentation is in compliance with test procedures.

- equipment to be tested is properly released for testing.

- inspections and tests are done under suitable environmental conditions.

proper calibrated inspection and test instruments are used.

- retention control of test data documentation is adequate.

- test or inspection requirements contained in applicable design documents.

Where tests and inspections are to be witnessed, the procedure identifies hold points or witness points in the testing sequence to permit witnessing. The procedure requires appropriate approval for the test to continue beyond the designated hold point.

1. Prerequisites Prerequisites include the following, as applicable:

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TEST CONTROL CHAPTER 11 TEST CONTROL CHAPTER 11

- appropriate test equipment.

- calibrated instrumentation in accordance with Chapter 12, "Control of Measuring and Test Equipment."

- condition of test equipment and the item to be tested.

- provisions for data acquisition.

- suitable environmental conditions.

- trained personnel.

Procedures ensure that prerequisite steps for equipment testing have been or will be performed. Such steps include:

- completion of necessary construction maintenance and modification activities.

- formal release for testing.

- measures to preserve equipment status.

- prior testing.

- safety precautions.

A detailed prescribed physical inspection of equipment components and facilities is performed to ensure readiness for operation. Typical inspection items include:

- calibration of instruments.

- cleanliness.

- lubrication.

- presence of safety devices.

- setting of limit switches.

2. Schedule Schedules are provided to assure that all necessary tests are performed and properly evaluated on a timely basis. Testing is scheduled so that the safety of the plant is never dependent on the performance of an untested system.

3. Test Results and Records Appropriate Company personnel evaluate test results to assure conformance with design and performance requirements. Inspection and test results are documented in a test report or data sheet. Each report identifies the following:

- acceptability of the test.

- actions taken to correct the deviations noted.

- any deviation of test results from acceptance criteria (nonconformance).

- as-found condition.

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TEST CONTROL CHAPTER 11

- as-left condition.

- completion date and other significant dates and times.

- data sheets completed during the tests.

- documents that provide acceptance criteria.

- identification of the conditions encountered which were not anticipated.

- identity of inspector or tester.

- item to which it applies.

- location where testing was performed or where test samples were taken.

- measuring and test equipment used.

- person evaluating test results.

- procedures or instructions followed in performing the task.

- test procedures.

- test results.

2.2. Instrumentation and Control The Company tests instrumentation and control channels to assure that they are properly calibrated. In addition, specific tests are performed at critical levels such as "set points" in a manner simulating the approach toward the set point.

These calibrations are made with the devices in their normal positions if the calibration is dependent upon location or attitude.

Testing determines that a proper response is obtained over the operating range of the device. It gives particular attention to verifying independence and dependence, as appropriate, of the elements of the systems. Calibration documentation includes indicating the date and identity of the person that performed the calibration.

The Company prepares and documents installation, inspection and test procedures and work instructions for instrumentation and electrical equipment.

These documents are kept current and revised as necessary to assure that installation, inspections and tests are performed in accordance with latest information. They include as appropriate:

- approvals.

- data report forms.

- -frequency of inspection or test.

- identification of test equipment and date for required re-calibration where required for interpretation of test results.

- inspection and test acceptance limits.

- inspection and test equipment required.

- inspection and test objectives.

- installation specifications.

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TEST CONTROL CHAPTERII1

- precautions to avoid component or system damage during testing or inspection.

- prerequisites.

- sequence of tests (if applicable).

- sequential actions to be performed.

2.3. Electrical Tests Electrical tests include as appropriate:

- continuity tests, short circuit tests, polarity and rotational tests

- control system tests including indicating meters, recorders, transducers, targets and lamps, annunciators and alarms, controls and interlocks

- insulation resistance measurements as specified

- over potential (HIPOT) tests as specified. Overpotential tests conform to the applicable codes and standards. The manufacturer's recommendations are considered.

- voltage breakdown tests on liquid insulation 2.4. Mechanical Tests The Company performs mechanical tests to ascertain that electric and/or instrumentation components or systems can withstand system pressure ratings.

As a minimum, the Company applies such tests to pressure sensing and transmitting devices operating in steam, hydraulic, and vacuum systems and their hydraulic or pneumatic interconnecting piping or tubing and associated instruments.

Pressurized equipment that is part of electrical apparatus such as heat exchangers, circulating systems, actuating systems, and electric and instrumentation containment penetrations are likewise tested if site assembled or fabricated. Tests are conducted after the assembly is complete even though the components may have been tested previously. These tests are performed in accordance with the applicable codes and standards.

2.5. Physical and Chemical Tests Physical and chemical tests, in accordance with the applicable codes, include, as appropriate:

- chemical analysis of fluids for oxygen or moisture content and purity.

- radiation sensitivity testing to confirm that radiation sensor and controlling devices is properly functioning.

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TEST CONTROL CHAPTER 11 TEST CONTROL CHAPTER 11 2.6. Surveillance Tests The Company's test program covers surveillance testing during the operational phase to provide assurances that failures or substandard performance do not remain undetected and that the required reliability of safety related systems is maintained.

2.7. Maintenance or Major Procedure Change The Company performs tests following plant modification or significant changes in operating procedures to confirm that the modification or changes produce expected results. These tests also demonstrate that the change does not produce an unsafe operating condition.

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CONTROL OF MEASURING AND TEST CHAPTER 12 EQUIPMENT

1. SCOPE Measures and responsibilities are established to assure tools, gauges, instruments, and other Measuring and Testing Equipment (M&TE) used in activities affecting quality are properly controlled, calibrated, and adjusted at specified periods to maintain accuracy within specified limits. Measures shall also be established for the control of permanently installed instrument and control devices.

2. REQUIREMENTS 2.1. General Power Labs is responsible for the governance of M&TE for Exelon plants. This includes the establishment of calibration practices, intervals, accuracy requirements, certification/de-certification, and equivalency decisions (except where accuracy is impactive non-conservatively), as well as the resolution of technical issues regarding M&TE calibration.

The engineering organizations are responsible for decisions regarding the acceptability of changes to M&TE specifications where accuracies are less conservative than those currently established. The engineering organization performs M&TE equivalency calculations for these items to assure associated specifications are consistent with plant design, test procedures, and accuracy requirements (excluded are analytical chemistry and radiochemistry instruments).

The stations are responsible for the control and maintenance of calibrated M&TE for the station. The stations are also responsible for the control of station analytical chemistry instrumentation, radiochemistry instrumentation, and standard solutions.

2.2. Control A control program specifies how M&TE are stored, handled, and used. As a minimum the following items are addressed:

- administrative controls (including equipment marking and traceability to calibration records).

- certification requirements.

- damaged or suspect M&TE.

- environmental restrictions.

- items not requiring certification.

- M&TE selection.

- out of tolerance resolution.

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CONTROL OF MEASURING AND TEST CHAPTER 12 EQUIPMENT

- personnel qualifications.

- repairs and maintenance.

- status and usage history.

2.3. Labeling Equipment shall be suitably marked to indicate calibration status. Where neither labeling nor coding is practical, procedures shall provide for monitoring of records to ensure control.

2.4. Accuracy Calibration of M&TE should be against reference standards that have an accuracy of at least four times the required accuracy of M&TE. Calibration of reference standards will be against hierarchical standards more accurate than the reference standards calibrated. When this is not possible, standards must have an accuracy that assures the M&TE is within the required tolerance, and that the basis for acceptance is documented and authorized by responsible management.

2.5. Traceability and Interval M&TE is calibrated against and traceable to certified standards having valid relationships to nationally recognized standards. Where national standards do not exist, provisions are established to document the basis for calibration.

Calibration intervals are established for all M&TE and the Company program specifies how this interval is established.

2.6. Certified M&TE Certified M&TE is required where measurements with specific accuracy/tolerance requirements are delineated:

- calibration of other M&TE.

- environmental monitoring.

- safety-related and applicable ASME applications.

- technical Specification related applications (including balance of plant systems).

- verification of design parameters.

Certified M&TE is not required when measurements do not require specific accuracy or when commercial devices (such as rulers, tape measures, levels) provide adequate accuracy. Electronic stopwatches are not required to be calibrated.

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CONTROL OF MEASURING AND TEST CHAPTER 12 EQUIPMENT 2.7. Corrective Actions When M&TE is found to be out-of-tolerance, an evaluation is made of its previous uses to determine corrective action. Suspect equipment is identified and segregated to prevent inadvertent use.

2.8. Vendor Control Vendors supplying calibration services are on the Company's approved suppliers list.

2.9. Commercial Devices Control measures are not required for rulers, tape measures, levels, and other such commercial devices, if such equipment provides adequate accuracy.

2.10. Calibration Records M&TE calibration records contain, as a minimum:

- as found/as left condition.

- calibration data.

- calibration procedure used.

- calibration results.

- equipment location.

- established accuracy.

- individual performing calibration.

- last calibration date.

- next calibration date.

- out of tolerance notification.

- repairs (if any).

- serial number.

- standards used.

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HANDLING, STORAGE, AND SHIPPING CHAPTER 13

1. SCOPE The Company establishes measures to control and specify special protective conditions in accordance with an item's design and procurement requirements, as necessary, to prevent damage or deterioration of materials, components, and systems during handling, packaging, preservation, storage, and shipping.

2. REQUIREMENTS 2.1. General The Company uses written procedures or instructions for cleaning, packaging, shipping, storage, preservation, and to specify detailed requirements for access to storage areas, housekeeping, and removal of items from storage. Procedures include provisions for inspection, examination, testing and documentation.

These procedures specify special protective conditions necessary to prevent damage, deterioration or loss before and after receipt of materials, equipment, special nuclear material, and radioactive wastes.

Procurement documents or the vendor's quality program specifies the establishment of controls, to assure through the use of shipping procedures to provide protection during loading and transit and inspections, that items are delivered in acceptable condition.

2.2. Special Equipment and Environments When required, the Company:

- provides special equipment and special protective environments

- specifies special equipment (such as containers, shock absorbers and accelerometers)

- specifies special protective environments (such as inert gas atmosphere, specific moisture content levels and temperature levels)

- verifies the maintenance of special equipment and special protective environments 2.3. Classification of Items Levels and methods of storage are classified to minimize the possibility of damage, deterioration, or contamination of items. This is based on the important physical characteristics and the importance to safety and reliability of the item.

This classification considers the manufacturer's requirements.

The Company packages, ships, receives, stores, and handles items according to established manufacturers requirements or the Company's' prescribed level.

When a package or assembly contains items of different levels, the Company classifies it to the highest level designated for any of the items contained.

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HANDLING, STORAGE, AND SHIPPING CHAPTER 13 2.4. Special Handling Tools and Equipment The Company inspects and tests special handling tools and equipment using procedures at specified time intervals to verify adequate maintenance. The Company provides special handling procedures and instructions for items that are susceptible to handling damage. These procedures delineate acceptable techniques, necessary qualifications and precautions for maintenance and use.

Operators of special handling and lifting equipment have experience or are trained in their usage.

2.5. Marking and Labeling The Company establishes instructions for marking and labeling to identify, maintain, and preserve an item, including indication of the presence of special environments or the need for special controls.

Consumable materials such as chemicals, reagents, and lubricants maintained in storerooms and warehouses are controlled procedurally by an inventory control system, which includes provisions for identifying storage requirements and shelf lives by commodity, when applicable. Disposal of commodities whose shelf life has expired is addressed and controlled by procedures.

2.6. Storage Periodic monitoring is performed to assure that storage areas are being maintained in accordance with applicable requirements. Access to storage areas shall be controlled and limited. Cleanliness and good housekeeping practices shall be enforced at all times in the storage areas. Fire protection measures commensurate with the type of storage area shall be provided and maintained .

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INSPECTION, TEST, AND OPERATING CHAPTER 14 STATUS

1. SCOPE Measures shall be established and documented to identify inspection, test, and operating status of structures, systems, and components in the scope of this QAP. Such measures shall provide means for assuring that required inspections and tests are performed and that the acceptability of items with regard to inspections and tests performed is known throughout procurement, installation, and operation in order to preclude inadvertent bypassing or altering the sequence of such inspections and tests.

2. REQUIREMENTS 2.1. General The Company uses markings, tags, stamps, routing cards, labels, forms, inspection records, or other means to identify the operating status of plant equipment. This identification helps avoid inadvertent bypassing of the inspections and tests required prior to its use.

In cases where documentary evidence is not available to confirm that an item has passed required inspections and tests, that item shall be considered nonconforming. An operability determination for the nonconforming item with timeliness commensurate with the potential safety significance of the issue is performed. The operability determination is focused on whether the non-conforming item is capable of performing or supporting its specified functions of prevention or mitigation as described in the current licensing basis and will result in the determination of continued plant operation. If operability is assured based on this prompt determination, plant operation can continue while an appropriate corrective action program is implemented to restore qualification of the non-conforming item.

Control procedures describe the use of such tags, stamps, routing cards, labels, forms, inspection records, and other methods. The authority for application and removal of tags, markings, labels and stamps is specified. Tagging, labeling, color-coding, physical separation, or using an inventory system identifies acceptable or unacceptable items for installation.

The Company:

- clearly identifies and documents all temporary connections, such as jumpers and bypass lines, and temporary set points of control equipment to allow restoration before placing the item in service.

- conditionally releases items for installation pending subsequent correction of any non-conformances.

- indicates the date the item was placed in the acceptable or unacceptable installation status.

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INSPECTION, TEST, AND OPERATING CHAPTER 14 STATUS

- maintains records, marks equipment to indicate calibration status, and identifies test equipment found out of calibration.

2.1.1. Procedures The Company uses procedures for control of equipment to maintain personnel and reactor safety and to avoid unauthorized operation of equipment. These procedures require control measures such as locking or tagging to secure and identify equipment in a controlled status. The procedures require independent verifications, where appropriate, to ensure that necessary measures, such as equipment tagging, have been done correctly.

2.2. Operating Status 2.2.1. Release for Maintenance Operating personnel, including a senior reactor operator, as applicable, may grant permission to release plant systems or equipment for maintenance or surveillance testing. Prior to granting permission, such operating personnel:

- verify that the equipment or system can be released.

- determine how long it may be out of service.

- determine what functional testing or redundant systems are required prior to and during the out-of-service period.

The Company documents such permission. The Company uses independent verification to the extent necessary to ensure that the proper system was removed from service. The Company considers the degraded protection available when one subsystem of a redundant safety system has been removed for maintenance or surveillance testing.

2.2.2. Preparation for Work After permission has been granted to take the equipment out of service, measures provide for protection of equipment and workers. The Company clearly identifies the status of equipment and systems at any location where the equipment can be operated. The Company enforces strict control measures for such equipment. The operating staff can easily identify equipment, which is in other than normal conditions.

In addition to the requirements of the technical specifications, conditions to be considered in preparing equipment for maintenance or surveillance testing include, for example:

- electrical hazards.

- entry into closed vessels.

- establishment of a path for decay heat removal.

- handling hazardous materials.

- hazardous atmospheres and ALARA considerations.

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INSPECTION, TEST, AND OPERATING CHAPTER 14 STATUS

- method of emergency core cooling.

- shutdown margin.

- temperature and pressure of the system.

- valves between work and hazardous materials.

- venting, draining, and flushing.

When entering a closed system, the Company prevents the entry of extraneous material and removes foreign material before re-closing the system. Appropriate personnel inform control room supervision of changes in equipment status, including temporary modifications, and the effects of such changes.

2.2.3. Temporary Modifications The Company controls temporary modifications, such as temporary bypass lines, electrical jumpers, lifted electrical leads, and temporary trip point settings with approved procedures. These procedures include requirements for the period of time when the temporary modification is in effect. They also include a requirement for:

- an independent verification by a second person of the proper installation or removal of the temporary modification, or

- a functional test which conclusively proves the proper installation or removal of the temporary modification.

The Company maintains a log or other documented evidence for the current status of such temporary modifications. The Company reviews temporary modifications periodically to assess their continued need and propriety.

2.2.4. Return to Service When equipment is ready to be returned to service, operating personnel place the equipment in operation and verify and document its functional acceptability.

The Company assures return to normal conditions using approved procedures, including:

- removal of electrical jumpers.

- removal of signals used during testing.

- returning valves, breakers, or switches to proper start-up or operating positions.

- assuring that all alarms, which are indicative of inoperative status, are cleared.

A second qualified person verifies proper alignment of equipment unless:

- all equipment, valves and switches involved in the activity can be proven to be in their correct alignment by functional testing without adversely affecting the safety of the plant, or

- such verification would result in significant radiation exposure.

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INSPECTION, TEST, AND OPERATING CHAPTER 14 STATUS The person who performs verifications (independent or concurrent) is qualified to perform such tasks. When placed into service, equipment receives additional surveillance during the run-in period. The on-duty supervisor responsible for the unit formally accepts equipment, which is returned to service.

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NONCONFORMING MATERIALS, CHAPTER 15 PARTS, OR COMPONENTS

1. SCOPE Controls shall provide for identification, evaluation, segregation when practical, disposition of nonconforming items, and for notification to affected organizations.

Items that do not conform to specified requirements shall be controlled to prevent inadvertent installation or use.

2. REQUIREMENTS 2.1. General Nonconforming items are processed in accordance with the corrective action program and / or documented procedures. The Company uses written procedures to identify and control items, services or activities that do not conform to requirements. These procedures address the:

- disposition of nonconforming items.

- documentation of identified nonconformances.

- identification of nonconforming items.

- notification of affected organizations.

- operability determination of the SSC with the identified nonconforming condition

- segregation of nonconforming items.

Implementation of these procedures prevents the inadvertent use, operation, or unauthorized installation of nonconforming items.

2.1.1. Supplier Nonconforming Items The Company and its suppliers establish and document measures for the identification, control and disposition of items and services that do not meet procurement document requirements. These measures provide for:

- a review of nonconforming items.

- supplier notification to the Company of a nonconformance. These notifications include a supplier recommended disposition (e.g. "use - as -

is" or "repair") and technical justification. The supplier submits nonconformances to the Company for approval if:

- the supplier has violated a technical or material requirement, or

- the supplier has violated a requirement in supplier documents, which have been approved by the Company, or

- the supplier cannot correct the nonconformance by continuation of the original manufacturing process or by rework, or Revision 76 Page 1 I of4 of 4 Revision 76

NONCONFORMING MATERIALS, CHAPTER 15 PARTS, OR COMPONENTS

- the item does not conform to the original procurement requirement even though the item can be restored to a condition such that the capability of the item to function is unimpaired.

- Company disposition of supplier recommendations.

- verification of disposition for nonconformances.

- maintenance of records for supplier nonconformances.

2.2. Identification The Company identifies nonconforming items by marking, tagging, or other methods, which do not adversely affect the end use of the item. The identification is legible and easily recognizable.

2.3. Segregation When practical, the Company segregates nonconforming items by placing them in a clearly identified and designated hold area until properly dispositioned.

When segregation is impractical or impossible due to physical conditions such as size, weight or access limitations, other precautions are employed to preclude inadvertent use of a nonconforming item.

2.4. Disposition 2.4.1. Control Nonconforming characteristics shall be reviewed and recommended dispositions of nonconforming items shall be proposed and approved in accordance with documented procedures. Further processing, delivery, installation, or use of a nonconforming item shall be controlled pending an evaluation and an approved disposition by authorized personnel.

2.4.2. Evaluation The Company has responsibility for resolution of nonconformances in accordance with written procedures. Where ASME Code requirements are involved, the Authorized Inspection Agency reviews and accepts or rejects the disposition and justification. Engineering provides technical justification and independent review of nonconformances dispositioned as repair or use-as-is.

For items under a contractor's direct control, the Company may delegate to the contractor the authority to perform a technical evaluation of nonconformances, if the contractor has an acceptable procedure for handling nonconforming items.

Where the Company delegates such authority, the contractor is responsible for establishing that:

- all actions fall within the requirements set by the Company.

- an accepted nonconformance meets the design intent.

- ASME Code items meet the requirements of the ASME Code.

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NONCONFORMING MATERIALS, CHAPTER 15 PARTS, OR COMPONENTS

- personnel performing the evaluation meet the requirements of section 2.4.3 below.

When a technical evaluation has not been delegated to a supplier, the Company makes a technical evaluation of all pertinent data relating to the nonconformity, including the cause, where known, and the corrective action either taken or planned to prevent recurrence per the corrective action program. The Company retains the responsibility for the satisfactory resolution of supplier nonconformances.

2.4.3. Personnel Personnel having expertise in the pertinent discipline determine whether a nonconforming item may be accepted "as - is," may be repaired to an acceptable condition, or must be rejected. These personnel have adequate competence and knowledge necessary to make this evaluation and have access to pertinent background information.

2.4.4. Documentation The Company identifies nonconforming items and documents their disposition (e.g. use - as - is, reject, repair, or rework). Each disposition is technically justified and traceable to each item. Appropriate documentation is retained.

Nonconformances to design requirements that are dispositioned as "use - as -

is" or 'repair" is subject to design control measures commensurate with those applied to the original design. The Company technically justifies dispositions designated "use - as - is," and "repair" to assure that the final condition of any nonconforming item meets applicable code requirements and will not adversely affect the safety, operability, or maintainability of the item, or of the component or system in which it is installed. The 'as - built" records, if such records are required, reflect the accepted deviation.

If the nonconformance can be corrected after installation, the item may be released for installation on a conditional release basis. The Company documents the authority and technical justification for the conditional release of the item and makes it part of the documentation.

2.4.5. Repaired, Reworked, or Scrapped Items The Company re-examines repaired or reworked items using procedures and the original acceptance criteria unless the nonconforming item's disposition has established alternate acceptance criteria. Items that have been corrected are re-inspected or re-tested as required by the approved disposition.

The area of inspection may be confined to the area of the nonconformance.

When it has been determined that the corrected item is satisfactory, the status of the item is changed to "acceptable" and an appropriate entry is made in the documentation after acceptance is determined.

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NONCONFORMING MATERIALS, CHAPTER 15 PARTS, OR COMPONENTS The Company scraps, discards or transfers to training usage a nonconforming item that cannot be corrected or accepted "as - is." Nonconforming items that are being used for training must be permanently identified and marked to prevent inadvertent or inappropriate use of the item.

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CORRECTIVE ACTION CHAPTER 16

1. SCOPE This Chapter describes the Company program to identify and correct conditions adverse to quality.

2. REQUIREMENTS 2.1. General The Company implements a Corrective Action Program to promptly identify and correct items or occurrences that are adverse to quality or might adversely affect the safe operation of a nuclear generating station. These items or occurrences are screened for reportability, operability, Part 21, etc. The Company makes a thorough investigation of occurrences and identifies corrective action to prevent recurrence of an event, as appropriate. Events may include reactor trips, failed equipment, personnel errors, and procedural infractions. Measures are taken to assure that the cause of any significant condition adverse to quality is determined and takes corrective action to prevent recurrence.

2.2. Conditions Adverse to Quality Measures are established to assure that conditions adverse to quality are identified and corrected. Examples of conditions adverse to quality are provided in procedures. Examples include failures, malfunctions, adverse trends, deficiencies (including programmatic), deviations, defective material, design errors, equipment, and nonconformance to specified requirements.

An independent review body reviews violations, deviations and reportable events that require a report to the NRC in accordance with regulatory requirements and company procedures. This includes the review of results of any investigations made and the recommendations resulting from such investigations. These include items such as:

- events, as defined in applicable site technical specifications.

- significant operating abnormalities or deviations from normal or expected performance of plant safety-related structures, systems, or components.

- violations of applicable codes, regulations, orders, technical specifications, license requirements or internal procedures or instructions having safety significance.

2.2.1. Significant Conditions Adverse to Quality In cases of significant conditions adverse to quality the cause of the condition is determined and documented, resolution determined and documented, and corrective action taken and documented to preclude recurrence.

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CORRECTIVE ACTION CHAPTER 16

1. Procurement The Company uses procedures that include methods for the identification of conditions adverse to quality and for timely corrective action. The Company requires individual vendors and their contractors to include corrective action measures in their quality assurance programs. In cases of significant conditions adverse to quality that arise during the procurement process, the Company uses procedures to describe the method used to:

- identify and document deviations and non-conformances.

- review and evaluate the conditions to determine the cause, extent and measures needed to correct and prevent recurrence.

- report the conditions and corrective action to the appropriate levels of management.

- implement and maintain required corrective action.

2. Plant Hardware Malfunctions The causes of malfunctions are determined, evaluated, and recorded, as appropriate. Experience with the malfunctioning equipment and similar components are reviewed and evaluated to determine if a replacement component of the same type can be expected to perform the function reliably. If evidence indicates that common components in safety-related systems have performed unsatisfactorily, corrective measures are planned prior to replacement or repair of all such components.

Appropriate procedures are revised in a timely manner to prevent recurrence of equipment malfunction or abnormal operation.

3. Incorrect Design When a significant design change is necessary because of an incorrect design, the Company reviews and modifies the design process and verification procedures, as appropriate. In cases of significant or recurring deficiencies (or errors), the Company follows written procedures to correct the deficiency (or error), determine the cause and make changes in the design process and the QAP to prevent similar types of deficiencies (or errors) from recurring.

2.3. Verification and Follow-up The Company verifies completion of corrective actions for maintenance, repair, refueling, operation activities, completion of corrective action taken for assessment deficiencies (including programmatic), and performs assessments of site corrective action. The Company tracks and verifies completion of corrective action taken for independent assessment findings and approves the completion of corrective actions.

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CORRECTIVE ACTION CHAPTER 16 Trending and assessment results are evaluated to assure that corrective measures are implemented effectively and that actions to prevent recurrence are effective as appropriate. The Company also requires contractors and vendors to follow-up on corrective action commitments within their quality programs.

The Company regularly reviews and analyzes records to:

- assure that the causes of a nonconformance and the corrective action have been clearly described.

- assure that authorized Company personnel have evaluated the overall effect resulting from the use of nonconforming items.

- determine whether corrective measures will preclude recurrence.

2.4. Evaluation and Qualification Personnel performing the evaluation function are responsible for considering the cause and the feasibility of corrective action to assure that the necessary quality of an item is not deteriorated. Where it is determined that the cause cannot be corrected immediately, the due date of corrective action will be determined during the review and evaluation. Evaluation may indicate the need for investigations to assure that corrective measures are considered complete and may also indicate that the nature of the deficient condition is minor and does not require corrective action.

Qualified personnel are responsible for determining the root cause(s) of an event and developing recommendations to preclude recurrence. These personnel report the results of their determination to appropriate station personnel and Company management.

2.5. Documentation and Reporting The Company documents the identification of significant conditions adverse to quality, the cause of the condition, the corrective action taken, and reports these items to the appropriate levels of management, NSRB, and as applicable, PORC, If the identified issue is not an indication of a significant failure in any portion of the QAP, the Company does not require reporting to management.

Reports are made immediately if prompt corrective action is required. Formal reports are filed with the appropriate regulatory agency, when required. Reports of investigations include a detailed description of the occurrence, the findings of the investigation, and the recommended corrective measures. The Company notifies the rest of the nuclear industry of significant events with generic implications and its circumstances to help preclude a similar event occurring at another plant.

The Company keeps records to identify incidents (e.g., major damage, personal injury, major schedule delays.), non-conforming items, unfavorable conditions, programmatic deficiencies identified in assessment reports, significant equipment failures, and malfunctions that occur during station operation.

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CORRECTIVE ACTION CHAPTER 16 The Company tracks the completion of corrective actions for conditions adverse to quality and maintains records of their resolution. Parts or all of this system may be electronically monitored and electronic records may be used as the sole record of such a system.

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QUALITY ASSURANCE RECORDS CHAPTER 17 QUALITY ASSURANCE RECORDS CHAPTER 17

1. SCOPE The Company establishes and implements a program which defines requirements and responsibilities for identification, generation, collection, compilation, storage, maintenance, retention, and retrieval of records necessary to provide evidence of quality in design, fabrication, installation, inspection, testing, and operating activities.

2. REQUIREMENTS 2.1. Program The records program provides for:

- administration.

- receipt and transmittal.

- storage and preservation ( includes temporary and permanent records)

- safekeeping and classification.

- retention and disposition.

2.2. Administration Authority and responsibility for record control activities are delineated in procedures. Records are administered through a system, which includes an index of record type, retention period, and storage location. Distribution of records shall be controlled in accordance with written procedures. Measures are established for replacement, restoration, or substitution of lost or damaged records.

Records are legible, accurate, complete, identifiable, and retrievable. Records are considered valid and complete when dated and stamped, initialed, signed, or otherwise authenticated. Corrections, revisions, or supplements to completed records are reviewed and approved by an authorized individual in the originating organization. Such changes are dated and stamped, initialed, signed, or otherwise authenticated including the use of electronic approval and authorization.

Records may be stored in electronic media provided that the process for managing and storing data is documented in procedures that comply with applicable regulations. Media used for the retention of records include (but are not limited to): microform, compact disk-recordable (CD-R), and magnetic media including videotape, computer tape, optical disks, and hard disk storage.

Electronic records retention must be an integral component of the Corporate Records Management Program, approved by the management position responsible for Nuclear Generation records. The format used must be capable of producing legible, accurate, and complete documents during the required retention period. Electronic approval and authorization procedures are Page I of 5 Revision 76

QUALITY ASSURANCE RECORDS CHAPTER 17 established to assure that only those persons authorized grant the required approvals.

2.3. Receipt and Transmittal A system for receipt control of records is established. Receipt control is required for records transferred between Company locations, vendors and the Company, and from Company department files to final storage locations. Systems are established to transfer records between Company locations and between vendors and the Company. Records transferred from Company department files to a final storage location are also under such systems. The system of receipt control of records for permanent or temporary storage includes inventory of transmitted records, receipt acknowledgment, and control of records during receipt.

2.4. Storage and Preservation Record storage facilities are established and maintained in a manner that minimizes the risk of damage or destruction. Interim storage provisions shall be established to properly maintain and protect records until they are permanently transferred to record storage facilities for retention. Records may be kept by suppliers and maintained on an available basis for a specified period of time.

Storage and Preservation systems provide for:

- assignment of responsibilities.

- attachment in binders, folders, or envelopes for storage in steel file cabinets or on shelving in containers.

- control and accountability of records removed.

- damage from natural disasters such as winds, floods, and fires.

- following manufacturer recommendations for special recording media.

- protection from environmental conditions such as high and low temperatures and humidity.

- protection from infestation of insects, mold, or rodents etc.

- special processed records such as radiographs, photographs, negatives, microfilm, and magnetic media to prevent damage from excessive light, stacking, electromagnetic fields, temperature and humidity.

2.4.1. Temporary Storage Measures are established for temporary storage of records when required by an organization's procedures for activities such as; for processing, review, or use.

These measures require that these records are stored in a 1-hour fire rated container and that a maximum allowable storage time limit is specified.

2.5. Safekeeping and Classification Measures are established to prevent access to records by unauthorized personnel. These measures guard against theft and vandalism. Records are classified and retained in accordance with applicable regulations.

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QUALITY ASSURANCE RECORDS CHAPTER 17 2.6. Retention and Disposition Record retention periods are established to meet regulatory, UFSAR, and License requirements. The most stringent retention period is implemented when multiple requirements exist.

Record retention requirements for Limerick Generating Station are also defined in Technical Specifications. Records are dispositioned at the end of the prescribed retention period.

2.7. Plant Operating Records 2.7.1. Records and/or Logs, 5-Year Retention Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years. These items apply to Braidwood, Byron, Clinton, Dresden, LaSalle, Limerick, Peach Bottom (including the Independent Spent Fuel Storage Installation), and Quad Cities Stations unless otherwise noted:

- records of normal plant operation, including power levels and periods of operation at each power level.

- records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements of the Technical Specifications (and Fire Protection Program at Clinton) are being met. All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded.

- records of physics tests and other tests pertaining to nuclear safety.

(Braidwood, Byron, Dresden, LaSalle, Peach Bottom, Quad Cities)

- records of changes to procedures required by a station's Technical Specifications and other procedures, which affect nuclear safety, as determined by the management position holder responsible for plant operation.

- shift manager/engineers' logs (Braidwood, Byron, Dresden, LaSalle, Quad Cities)

- records of principal maintenance activities, including inspection and repair, (and replacement for Braidwood, Byron, Limerick and Peach Bottom) regarding principal items of equipment pertaining to nuclear safety.

- by-product material inventory records and records of sealed source and fission detector leak tests and results (Braidwood, Byron, Clinton, Limerick, Peach Bottom and Zion).

- by-product material inventory records and source leak test results (Dresden, Clinton, and Quad Cities).

- records of changes made to the equipment or reviews of tests and experiments to comply with 10CFR50.59 (Dresden and Quad Cities).

- records of changes made to the procedures as required by Technical Specifications and the Operational Requirements Manual (Clinton).

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QUALITY ASSURANCE RECORDS CHAPTER 17 QUALITY ASSURANCE RECORDS CHAPTER 17

- reportable events required by 10CFR50.73 and 10CFR72.216 as applicable (Clinton 10CFR50.73 only, Limerick and Peach Bottom).

- records of radioactive shipments (Limerick) 2.7.2. Lifetime Records Lifetime records are those that are specified by applicable regulations, standards, codes, and licensing basis documents.

2.8 Record Retention (Limerick Specific Only) 2.8.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

2.8.2 The following records shall be retained for at least 5 years:

- Records and logs of unit operation covering time interval at each power level.

- Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.

- All REPORTABLE EVENTS.

- Records of surveillance activities, inspections, and calibrations required by Technical Specifications.

- Records of changes made to the programs and procedures required by Limericl Technical Specification 6.8.

- Records of radioactive shipments.

- Records of sealed source and fission detector leak tests and results.

- Records of annual physical inventory of all sealed source material of record.

2.8.3 The following records shall be retained for the duration of the unit Operating License:

- Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

- Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.

- Records of radiation exposure for all individuals entering radiation control areas.

- Records of gaseous and liquid radioactive material released to the environs.

- Records of transient or operational cycles for those unit components identified in Limerick Technical Specification Table 5.6.1-1.

- Records of reactor tests and experiments.

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QUALITY ASSURANCE RECORDS CHAPTER 17

- Records of training and qualification for current members of the unit staff.

- Records of inservice inspections performed pursuant to Technical Specifications.

- Records of quality assurance activities required by the Operational Quality Assurance Manual not listed in QATR Chapter 17; paragraph no. 2.8.2.

- Records of reviews performed for changes made to procedures or equipment of reviews of tests and experiments pursuant to 10 CFR 50.59.

- Records of meetings of the PORC and the NRB.

- Records of the service lives of all snubbers including the date at which the service life commences and associated installation and maintenance records.

- Records of analysis required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

- Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

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ASSESSMENTS/AUDITS CHAPTER 18 ASSESSMENTSIAUDITS CHAPTER 18

1. SCOPE A documented, comprehensive system consisting of regulatory audits and performance assessments of the Company and its vendors are conducted to verify QAP compliance, adequacy, and effectiveness. Audits and assessments are conducted in accordance with written procedures and to the requirements of ASME NQA-1 to evaluate the assessed organization and to assure completion of required corrective actions, commitments, or improvements and determine effectiveness in meeting program objectives.

2. REQUIREMENTS 2.1. Assessments and Audits - General 2.1.1. Scheduling The internal audit program is conducted on a performance driven frequency that is commensurate with the status and importance of the activity to be completed but does not exceed 24-months. Internal audit frequencies required by regulation that are different than the 24-month period are indicated within Appendix B, "Assessment Frequency." Assessment frequencies are determined based on a consideration of the risk and consequences with respect to the activities being assessed.

A grace period of 90 days may be applied to this 24-month audit frequency. This grace period will not allow the 24-month period to be reset forward. Ifthe 90-day grace period is applied to an audit frequency to complete a particular activity this completion date does not become the new starting date for the next 24-month audit period. However, if an activity is completed earlier than the scheduled 24-month period, the date of early completion becomes the new start date for the next 24-month audit period.

Planned and comprehensive performance assessment activities are conducted to assure that safety related functions are fully evaluated. Internal assessment activities are performed to a schedule that includes assessment areas and frequencies. The management position responsible for NOS, or designated staff member(s), approves them. Schedules are reviewed semi-annually and revised accordingly to assure that coverage is maintained current.

2.1.2. Preparation A documented plan or an agenda identifies an audit or assessment scope, requirements, audit and/or assessment personnel, activities to be evaluated, organizations to be notified, applicable documents, and schedule. An approved checklist or procedure for each scheduled audit and/or assessment identifies the quality and technical elements of the area or items to be evaluated.

Audit/Assessment plans, agendas, checklists, and procedures as applicable are Revision 76 Page 1 Page of 3 I of 3 Revision 76

ASSESSMENTS/AUDITS CHAPTER 18 prepared in advance under the direction of an Audit/Assessment Team Leader (ATL).

2.1.3. Personnel Experienced and qualified personnel perform assessments and audits and are familiar with written procedures, standards, and processes applicable to the area being evaluated. Assessment and audit personnel shall have sufficient authority and organizational freedom to make the assessment and audit process meaningful and effective and shall not have direct responsibilities in the areas to be assessed. They shall have access to the plant records necessary to fulfill their function.

The Assessment/Audit Team Leader shall organize and direct audits/assessments and ensure the team collectively has the required experience or training for the activities to be evaluated. Technical Specialists may supplement the team to provide additional experience and competence.

2.1.4. Performance Performance assessments are conducted to assess specific activities, processes, and records on the basis of their impact and importance relative to safety, reliability, and functionality with respect to risks and consequences.

Assessments can be focussed on areas most in need of improvement.

Audits and assessments are initiated early to assure effective quality assurance during design, procurement, manufacturing, construction, installation, inspection, testing, and operations. Additional unscheduled audits and assessments may also be performed at various stages of activities, based on the nature and safety significance of the work being done; to verify continued adherence to and effectiveness of the quality systems. Objective evidence shall be examined to the extent necessary to determine that a quality program is being effectively implemented.

2.1.5. Reporting and Follow-up An audit report includes the description of the audit scope, identification of the team and personnel contacted during audit activities, a summary of results (including a statement on effectiveness of the QAP elements), and a description of each finding. The ATL shall sign the audit report for which he or she is responsible.

Audit and Assessment results are documented and distributed to the management position responsible for NOS, and to the appropriate managerial level of the organization having responsibility for the area or activity assessed.

Findings or deficiencies requiring prompt corrective action are reported immediately to the management of the assessed organization.

Findings, deficiencies and recommendations of each audit and assessment shall be reported to appropriate site management and the management position Revision 76 of Page 22 of 3 Page 3 Revision 76

ASSESSMENTS/AUDITS CHAPTER 18 responsible for NOS. All findings of noncompliance with NRC requirements, and any significant nuclear safety or quality issues requiring escalated action, will be directed through the management position responsible for NOS to the President and CNO in accordance with procedural requirements.

Responsible management shall take the necessary actions to correct findings identified in the assessment/audit. They will identify the corrective action to be taken, actions that will prevent recurrence, and a schedule for implementing these actions. Responses to audit and assessment findings are reviewed for adequacy.

Follow-up verification of the completion of scheduled corrective action commitments are performed by NOS to assure findings or adverse conditions are corrected in accordance with procedural requirements. Follow-up action of previous deficient areas or adverse conditions (including re-audit) is taken to verify that corrective action has been completed, is effective, implementation continues, and is properly documented, when indicated.

2.1.6. Records Audit and Assessment results are documented and reports are generated and retained. Associated documentation is on file at the appropriate location.

Personnel qualification records for assessment and audit team members are established, maintained, and reviewed.

2.2. Vendor Audits Assessments, audits, or surveys of vendors and their sub-tier suppliers are performed to a pre-established schedule. Audits are performed on a triennial basis. Documented supplier performance monitoring is performed in accordance with approved procedures as an acceptable alternate to the performance of the annual evaluation of suppliers. The management position responsible for audits and programs or his designee, shall review and approve the assessment/audit/survey schedule and checklists, and sign reports. Schedules are reviewed semi-annually and revised accordingly to assure that suppliers are assessed, audited, or surveyed as required.

Assessment program requirements are imposed on suppliers by appropriate contract or procurement documents. The Company's active participation in nuclear industry assessments provides an alternative means to fulfilling its responsibility for examining supplier activities.

2.3. Independent Management Assessment A periodic assessment (not to exceed 24 months) of the status and adequacy of the QAP is performed by an independent organization to assure that assessments are being accomplished to program requirements. The management position responsible for NOS submits the results of this assessment to the President and CNO.

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AUGMENTED QUALITY APPENDIX A AUGMENTED QUALITY APPENDIX A

1. SCOPE It is the Company's policy to assure a high degree of availability and reliability for its nuclear plants while ensuring the health and safety of the public and its workers. Therefore, the Quality Assurance Program is applied in a graded manner to certain areas and activities that are not clearly defined as safety related. The Company calls this application Augmented Quality. Augmented Quality includes systems and components that are subject to the requirements of ASME Code Sections: I "Power Boilers," IV "Hot Water Heaters," and VilI

'Non-fired Pressure Vessels" (see sub-section 2.7. below). This appendix applies to all sites unless otherwise noted below or in Appendices B through G.

2. REQUIREMENTS The Company applies the following augmented quality requirements to certain systems, structures, components (SSC), and activities that are not safety related to a degree consistent with their importance to safety. Unless otherwise noted:

- routine audits are performed of the program's content and implementation.

- deficiencies are addressed in accordance with the corrective action program.

program records of audits and reviews are maintained as required.

2.1. Health Physics and ALARA (As Low As Reasonably Achievable)

The Company develops, documents, and implements a radiation protection program sufficient to ensure compliance with the provisions of 10CFR20. The Company uses, to the extent practical, procedures and engineering controls based on sound radiation protection principles to achieve occupational doses and doses to the public that are as low as reasonably achievable.

2.2. Transport of Radioactive Waste When the Company contracts with vendors to transport radioactive waste in NRC approved shipping packages, it meets the requirements of 10CFR71, Subpart H. The Company assures that this service is procured from an organization with a QA program and if applicable, includes a NRC licensed transport system. Loading, surveying, closure, placarding, and inspections are conducted in accordance with written procedures and instructions.

Transport casks and trailers are inspected before release in accordance with Department of Transportation (DOT) 49CFR.

Shipping manifests, including final radiation surveys, are completed and retained. Radioactive waste shipments not meeting the requirements for NRC approved packaging, shall meet the requirements of DOT 49CFR.

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AUGMENTED QUALITY APPENDIX A AUGMENTED QUALITY APPENDIX A 2.3. Services The Company procures services from qualified suppliers. It is not necessary that these suppliers have a quality assurance program approved by the licensee, however, suppliers should provide a quality assurance program that includes the quality assurance program elements presented in Reg. Guide 4.15, and routinely provide program data summaries sufficiently detailed to permit evaluation of the program for the following areas:

- meteorology.

- Offsite Dose Calculation Manual.

- radiological environmental monitoring.

2.4. Fire Protection 10CFR50 Appendix A, General Design Criteria (GDC) 3 requires that the Company's nuclear facilities have an established fire protection program that provides fire protection features such that the adverse effect of fires on structures, systems and components important to safety is minimized. The quality assurance program established for these fire protection SSCs ensures that design, procurement, instruction, procedures, drawings, inspection, installation, testing, maintenance, operations, nonconforming Items, corrective Action, records, audits and administrative controls meet the applicable Quality Assurance quidelines as described in the applicable edition of Branch Technical Position (BTP) 9.5-1 for each Exelon site. Engineering determines what fire protection SSCs protect Structures, Systems, and Components important to safety. Engineering also establishes the requirements for the design, procurement, fabrication, installation and/or modification of these fire protection SSCs. Routine testing of fire protection systems assures reliability. All other fire protection equipment and supplies will be of commercial quality, in accordance with National Fire Protection Association (NFPA) guidelines.

2.5. Station Blackout (Dresden and Quad Cities)

Dresden and Quad Cities stations procured and installed additional non-safety related equipment to achieve the redundancy required by 10CFR50.63. Quality Assurance requirements for Dresden and Quad Cities are implemented in accordance with Regulatory Guide 1.155 (Station Blackout). Replacement and consumable parts and supplies are classified non-safety related in accordance with original specifications and are procured as commercial items. Routine testing of Station Blackout (SBO) SSCs assures the necessary redundancy is maintained. SBO SSC reliability is monitored in accordance with the Station's Maintenance Rule program.

2.6. Augmented Quality Requirements for Dresden 1, Peach Bottom 1, Zion Dresden 1, Peach Bottom 1, and Zion 1 & 2 have ceased commercial operation and will ultimately be decommissioned. Staffing, qualification of personnel, and organization will be in accordance with the Dresden 1 and Zion De-fueled Page 2of 8 Revision 76

AUGMENTED QUALITY APPENDIX A Technical Specifications (DTS) and De-fueled Safety Analysis Reports (DSAR),

and the Peach Bottom 1 Updated Final Safety Analysis Report (UFSAR) and Technical Specifications.

Select SSCs at Zion are considered non-safety related but uImportant-to-De-fueled-Condition (ITDC)" as defined in the DSAR. Procurement of parts and components will be in accordance with this non-safety related but ITDC classification. Changes, tests, and experiments require the application of the design control measures that assure that applicable regulatory requirements, licensing and design bases, and codes and standards are correctly translated into specifications, procedures and instructions. These design control measures will include a review and evaluation in accordance with 10CFR50.59/72.48, except design verification. The originator's supervisor, providing the supervisor did not specify a singular design approach or rule out certain design considerations, may perform design verifications.

Except for inspections or examinations required for ASME repairs and replacements, station personnel may perform inspections provided they are experienced, task-qualified journeymen or supervisors who did not supervise the activity being inspected. Nuclear Oversight will monitor this activity through periodic overview.

Timeliness of corrective actions is prioritized commensurate with the safety significance. Sufficient records of maintenance and modification activities will be maintained to evaluate failures, perform root cause analysis, if applicable, and determine appropriate corrective actions and to meet the requirements of the applicable DSAR or Peach Bottom Unit 1 UFSAR. Audits are conducted of maintenance of shutdown facilities and decommissioning activities at least annually until the termination of license with the exception of Peach Bottom 1, which is conducted on a biennial frequency.

2.6.1 Augmented Quality Requirements for Zion Station's Important to the Defueled Condition Structure, Systems, Components, and activities The following augmented quality requirements will be applied to non-safety related Important to Defueled Condition (ITDC) Structure, Systems, Components (SSCs), and activities as defined in the Defueled Safety Analysis Report (DSAR), and as shown in the following Zion Station Augmented Quality Matrix.

2.6.1.1 Design, Procurement, and Document Control - Measures will be established to assure that applicable regulatory requirements, licensing and design bases, and standards are correctly translated into specification, drawings, procedures, and instructions. Deviations from these requirements and standards will be controlled. Design changes, including field changes, will be subjected to these measures.

2.6.1.2 Instructions, Procedures, and Drawings -Activities affecting ITDC SSCs and activities will be prescribed by documented instructions, procedures, and drawings and will be accomplished in accordance with these documents.

Instructions, procedures, and drawings will include qualitative and quantitative Page 3 of 8 Revision 76

AUGMENTED QUALITY APPENDIX A acceptance criteria for determing that activities, processes, and personnel qualifications have been satisfactorily accomplished.

2.6.1.3 Control of Purchased Material, Equipment, Services, and Nonconforming Items-Measures will be established to ensure that purchased material, equipment, and services conform to procurement documents and that items that do not conform to specified requirements are prevented from inadvertent use or installation.

2.6.1.4 Inspections - Inspections of activities affecting quality will be established and executed to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity.

2.6.1.5 Test Control - Surveillance testing will be established to ensure the SSCs perform satisfactory and commensurate with the importance of its intended function.

2.6.1.6 Control of Measuring and Test Equipment- Measuring and testing devices will be controlled, calibrated and adjusted at specified periods to maintain accuracy.

2.6.1.7 Corrective Action Program -A corrective action program will be maintained to assure that adverse conditions are promptly identified and corrected. For significant adverse conditions, the causes will be determined and corrective action implemented to preclude reoccurrence.

2.6.1.8 Records - Measures will be implemented to maintain records for activities affecting ITDC SSCs and the storage of nuclear fuel per established record retention periods.

2.6.1.9 Audits - A documented audit will be conducted on a frequency not to exceed 12 months to verify compliance with the requirements of this section and other applicable requirements. Audits will include a review of freeze protection, as appropriate.

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AUGMENTED QUALITY APPENDIX A 2.6.1.10 Zion Station Augmented Quality Matrix Section Section Title c 0.e

.6.1.1 Design Control 2.6.1.1 Procurement X X X X X X 2.6.1.1 Document Control X X X X X X 2.6.1.2 Instructions, Procedures, and X Drawings X X X X X 2.6.1.3 Control of Purchase Material, Equipment &

Services X . X 2.6.1.3 Nonconforming Materials, Parts,

. or Components X XX 2.6.1.4 Inspections X X 2.6.1.5 Test Control X X 2.6.1.6 Control of Measuring &

Test Equipment X .

2.6.1.7 Corrective Action X X X X X X 2.6.1.8 Quality Assurance Records X X X X X X X 2.6.1.9 Audits X X X X X X X X 2.7. Repairs and Alterations The requirements of ASME Code Sections II, V and IX shall be imposed as applicable for the repair or alteration job specific work scope.

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AUGMENTED QUALITY APPENDIX A 2.7.1. State of Illinois Welded repairs and all alterations to non-ISI boilers and pressure vessels, as described in Section 505.2500 of the rules contained in the Illinois Emergency Management Agency (IEMA) Safe Operation of Nuclear Facility Boilers and Pressure Vessels (Part 505), and the repair of pressure relief valves, as described in Section 505.2500(b) are conducted in accordance with Section 505.2500(a)(1)(A) of these rules.

Section 505.2500(a)(1)(A) requires that the Company apply an approved Quality Assurance (QA) Program to such repairs and alterations and describe how it is applied. The following describes the Company's application of these rules.

- The Company has a QA Program that is reviewed and accepted by the NRC. In addition, the QA Program is reviewed and accepted by an accredited Authorized Inspection Agency. Authorized Inspectors are present at each of the Company's plants while ASME Code work is in progress.

- Chapter 1 of this QA Program describes the authority and responsibilities of the organization. It also describes the retention of responsibility by the Company when repair and modification activities are subcontracted.

- Chapter 3 requires that design and changes to designs be defined, documented, and controlled.

- Chapter 5 requires that all work be accomplished in accordance with documented instructions and procedures and be subject to appropriate process controls. Specifically, the Company uses the Nuclear Work Request (NWR) to authorize, track, and control work in the plant. The NWR system includes provisions for specifying when work is ASME Code related and is not limited to any particular section of the ASME Code. It further provides for detailed instructions to accomplish the work. This includes the need for qualified inspectors, qualified welders, qualified procedures, special processes, required documentation, approved drawings, and post-maintenance/post-modification testing. NWRs marked as ASME Code work is offered to the Authorized Inspector for the insertion of hold and witness points.

- Chapters 4, 7, 8, and 13 address the procurement, receiving, handling, storage, disbursement, and marking of materials. Implementing procedures establish traceability of materials to the procurement and receiving processes and provide assurance that only ASME Code acceptable materials are utilized. Any specific requirements for heat traceability will be in accordance with the applicable sections of the ASME Code being used.

- Chapter 9 details the controls for special processes while Chapter 10 details those for inspection. This includes the requirement for the use of independent, qualified inspectors and examiners when required by the ASME Code, and invokes the Company's Special Processes and Procedures Manual (SPPM). The SPPM is also reviewed and accepted by the Authorized Inspection Agency.

Page 6 of 8 Revision 76

AUGMENTED QUALITY APPENDIX A

- Chapters 6 and 17 require that documents and records be generated and maintained to satisfy the requirements of the ASME Code and the Jurisdiction.

- Chapter 18 provides for overview and audit of ASME Code activities.

Repairs and alterations performed as described above meet the requirements of the approved QA Program and meet the requirements of the IEMA B&PV rules; regardless of the safety classification of the boiler or pressure vessel or pressure relief valve being repaired.

2.8. Dry Cask Storage System 2.8.1. Peach Bottom Atomic Power Station (PBAPS)

Peach Bottom quality assurance program requirements are performed in accordance with the applicable 10CFR72.212 report which invokes the NRC approved 10CFR50 Appendix B quality assurance program as described in this QATR.

2.8.2. Oyster Creek Nuclear Generating Station (OCNGS)

The OCNGS quality assurance program requirements are performed in accordance with the applicable 10CFR72.212 report which invokes the NRC approved 10CFR50 Appendix B quality assurance program as described in this QATR.

2.8.3. Dresden / Quad Cities Station(s)

The ISFSI SSCs that are important to safety are categorized as Category A, B, or C in accordance with NUREG/CR-6407, "Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety." Per 10CFR72, Subpart G, the QATR applies to the ISFSI SSCs and activities consistent with their importance to safety as follows:

See classification table on next page.

2.9. Emergency Planning Requirements with respect to audits and records for Emergency Preparedness are described in an Emergency Plan that meets the requirements of 10CFR50.47.

2.10. Security Requirements with respect to audits and records for Security are controlled for each station by an NRC approved Station Security Plan that is prepared and implemented in accordance with the requirements contained in 10CFR73.55.

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AUGMENTED QUALITY APPENDIX A AUGMENTED QUALITY APPENDIX A Important to Safety SSCs Category Chapter Title A Organization 1 M M R (Roles and Responsibilities)

Quality Assurance Program 2 M M NR (Subchapters 3.1, 3.4, 3.5, and 3.6) 3 Design Control M M R 4 Procurement Document Control M R NR 5 Instructions, Procedures, and Drawings M M R 6 Document Control M M R 7 Control of Purchase Material, Equipment, and M R R Services 8 Identification and Control of Materials, Parts, and M R R Components _-

9 Control of Special Processes M M R 10 Inspections M M R Test Control 11 M M R (Design, Fabrication, Installation, and Maintenance) 12 Control of Measuring, and Test Equipment M M R 13 Handling, Storage, and Shipping M R NR 14 Inspection, Test, and Operating Status M M NR 15 Nonconforming Materials, Parts, or Components M M R 16 Corrective Action M M R 17 Quality Assurance Records M M R 18 Audits M M R (M) Mandatory = Indicates the Appendix B QA Program shall be used.

(R) Recommended = Indicates application of the applicable quality assurance criterion may benefit the user.

The Engineering organization shall determine the extent of application required for the SSCs in question.

(NR) Not Required = Indicates that little benefit has been identified or no regulatory basis has been found to require application of applicable QA criteria. Imprudent use of this criterion may add unnecessary burden.

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ASSESSMENT FREQUENCY APPENDIX B ASSESSMENT FREQUENCY APPENDIX B Internal assessments shall be conducted on a performance driven frequency, not to exceed 24 months or at the frequencies indicated below, in accordance with the Company's QAP. Assessments shall include the following safety-related functions as applicable:

ASSESSMENT FREQUENCY

a. The conformance of unit operation to provisions contained within the technical specifications and 24 Months applicable license conditions.

b. The adherence to procedures, training, and qualification of the station staff. 24 Months

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, components, or method of operation that affect 24 Months nuclear safety.

d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix 24 Months B of 10CFR50.

e. The fire protection programmatic controls including the implementing procedures (by qualified Nuclear 24 Months Oversight personnel).

f. The fire protection equipment and program implementation, including loss prevention, utilizing either a qualified offsite licensee fire protection engineer or an outside, independent fire protection 24 Moth consultant. An outside, independent fire protection onts consultant shall be used at least every second year.

g. The Radiological Environmental Monitoring Program (REMP) and its results. 24 Months

h. The Offsite Dose Calculation Manual (ODCM) and implementing procedures. 24 Months Revision .76 Page 1I off22 Page Revision 76

ASSESSMENT FREQUENCY APPENDIX B

i. The Process Control Program (PCP) and implementing procedures for the solidification of radioactive wastes. 24 Months

j. The performance of activities required by the Company QAP for effluent and environmental monitoring. 24 Months

k. Randomly selected procedures to ensure that the programmatic control processes used to assure that procedures are technically and administratively correct 24 Months prior to use are resulting in timely and accurate procedure revisions.

I. The Security Plan and implementing procedures (Reference 10CFR50.54(p)(3)(ii) for lesser frequency 12 Months requirements).

m. The Emergency Plan and implementing procedures (Reference 10CFR50.54(t)(1)(ii) for lesser frequency 12 Months requirements).

n. NSRB activities at a frequency not to exceed 5-years. 60 Months

o. The conformance of Spent Fuel Storage Installation operation to provisions contained within the technical specifications and applicable license conditions and results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, 24 Months components, or methods of operation affecting nuclear safety (Dresden, Oyster Creek, and Peach Bottom only).

p. Access Authorization Program (10CFR73.56) 24 Months (Initial Audit frequency is 12 months and at least 24 months thereafter)

q. Personnel Access Data System (PADS) 24 Months (10CFR73.56)

(Initial Audit frequency is 12 months and at least 24 months thereafter)

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CODES, STANDARDS, AND GUIDES APPENDIX C CODES, STANDARDS, AND GUIDES APPENDIX C 1.1. Codes and Standards The QAP takes into account the need for special controls, processes, test equipment, tools, and skills necessary to attain the required quality and the need for the verification of quality by inspection and test. The Codes and Standards listed below represent a listing of quality assurance codes and standards used to define the quality assurance program. A general listing of quality assurance related codes and standards, such as: ASME B&PV, ANSI, AWS, and IEEE used throughout Exelon/AmerGen at each nuclear site can be found in the applicable site specific Updated Final Safety Analysis Reports (UFSARs). The UFSAR should be referenced to identify site-specific commitments (including dates and/or addendas) with respect to these codes and standards. This Quality Assurance Program (QAP) complies with the quality requirements of the following codes and standards as indicated in site specific UFSARs unless otherwise noted in sub-section 1.3 (the UFSAR may address position specific exceptions or clarifications on a site by site basis).

- ANSI N18.1 - 1971, "Selection and Training of Nuclear Power Plant Personnel"

- ANSI / ANS 3.1 -1978, 'American National Standard for Selection and Training of Nuclear Power Plant Personnel"

- ANSI / ANS 3.1 -1981, "Selection, Qualification and Training of personnel for Nuclear Power Plants"

- ANSI N18.7-1976 /ANS 3.2, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants."

(Applicable to Limerick, Oyster Creek, TMI, and Clinton Only)

- ANSI N18.7-1972 "Administrative Controls for Nuclear Power Plants during the Operational Phase" (Applicable to Peach Bottom Only)

- ANSI / ANS 3.2 - 1988, ""Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants."

(Applicable to Braidwood, Byron, Dresden, LaSalle, and Quad Cities Only)

- ASME NQA-1 (1994) (Revision and Consolidation of ASME NQA-1-1989 and ASME NQA-2-1989 Editions) "Quality Assurance Requirements for Nuclear Facility Applications" Part I, "Basic Requirements and Supplementary Requirements for Nuclear Facilities" 1.2. Regulatory Guides The applicable site specific Updated Final Safety Analysis Report (UFSAR) should be referenced to identify site-specific commitments with respect to the Regulatory Guides listed in this section. The QAP also complies with the regulatory positions of the following Regulatory Guides and additional programmatic quality requirements unless otherwise noted in sub-section 1.3.

- 1.8 , "Personnel Qualification and Training."

Revision 76 Page I of Page 1 21 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C 1.26, "Quality Group Classification and Standards for Nuclear Power Plants."

1.28 , "Quality Assurance Program Requirements for Design and Construction."

1.29, 'Seismic Design Classification."

1.30, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment."

1.31, "Control of Ferrite Content in Stainless Steel Weld Material" 1.33, "Quality Assurance Program Requirements."

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

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

1.39, "Housekeeping Requirements for Water Cooled Nuclear Power Plants."

1.68, "Pre-Operational and Initial Start-Up Test Programs for Water Cooled Reactors."

1.94, "Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Steel during the Construction Phase of Nuclear Power Plants."

1.116 , "Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems."

1.142 , "Safety Related Concrete Structures for Nuclear Power Plants."

1.143, "Design Guidance for Radioactive Waste Management SSCs Installed in Light Water-Cooled Nuclear Power Plants."

4.15, "quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment."

1.3. Site Specific Clarifications and Exceptions 1.3.1. Limerick (LGS) and Peach Bottom Atomic Power Station (PBAPS)

1. Regulatory Guide 1.28, Revision 3, August 1985, "Quality Assurance Program Requirements - Design and Construction". Endorses ANSI/ASME NQA-1-1983.

LGS/PBAPS shall comply with Regulatory Guide 1.28, August 1985 and ANSI/ASME NQA-1 -1994, except for the following alternatives.

A. NQA-1, Supplement 2S-3, Supplementary Requirements for the Qualification of Quality Assurance Program Audit Personnel, Sub-section 3.3, Audit Participation.

NQA-1, Supplement 2S-3, Sub-section 3.3 (ANSI N45.2.23, Sub-section 2.3.4), Prospective Lead Auditors shall demonstrate their Page 2 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C ability to effectively implement the audit process and effectively lead an audit team. This process is described in written procedures that provide for evaluation and documentation of the results of this demonstration. A prospective Lead Auditor shall have participated in at least one nuclear oversight audit within the year preceding the individual's effective date of qualification. Upon successful demonstration of the ability to effectively implement the audit process and effectively lead audits, and having met the provisions of NQA-1, Supplement 2S-3, the individual may be certified as being qualified to lead audits. LGS/PBAPS was granted this alternative by NRC SER dated 6/26/97, to this requirement. (ANSI N45.2.23 section 2.3.4, uAudit Participation" was replaced by NQA-1-1994, Supplement 2S-3, Sub-section 3.3,"Audit Participation").

2. Regulatory Guide 1.30, August 1972, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electrical Equipment." Endorses ANSI N45.2.4-1972.

LGS/PBAPS shall comply with Regulatory Guide 1.30, August 1972, and ANSI N45.2.4-1972, except for the following alternatives.

A. ANSI N45.2.4, Section 1.1, Scope - An alternate to classification of Class I and IE electric power, instrumentation, and control equipment is to apply the requirements of this standard to LGS safety-related items (those instruments, equipment, and systems that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public).

B. ANSI N45.2.4, Section 3, Pre-construction Verification - Subsection (3) requires the checking of records of protective measures maintained during storage for conformance to storage requirements.

ANSI N45.2.2-1978, Section 6.4, Control of Items in Storage, requires inspection and examination during the storage period. The responsibility for these inspections rests with Materials Management.

Compliance with these requirements for checking of records is assured through the auditing and quality verification programs conducted NOS Department personnel along with the monitoring of Materials Management activities by Materials Management supervision.

C. ANSI N45.2.4, Section 7, Data Analysis and Evaluation - A program for processing, reviewing, and analyzing electrical equipment and instrumentation inspection and test data for acceptability is provided in the administrative procedures which govern the repair, maintenance, and testing of electrical equipment and instrumentation. Maintenance is controlled through the use of a work request form that has provisions for cognizant personnel sign-off after completion of the work. Functional testing and calibration procedures include provisions for review, analysis of data, and approval by signature of cognizant personnel.

Page 3 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C D. ANSI N45.2.4, Section 6.2.1, Equipment Tests - Installed items requiring calibration are controlled through the preventive maintenance computer tracking system. Tags or labels are not affixed to the item to indicate calibration status.

E. ANSI N45.2, Section 9, Item 6, ANSI B31.7-1969, PBAPS follows USAS B31.1.0-1967 since PBAPS Units 2 and 3 were constructed to USAS B31.0.0-1967. (This item applies to PBAPS ONLY).

3. Regulatory Guide 1.33," Quality Assurance Program Requirements, (Operations)," endorses ANSI N18.7.

LGS shall comply with Regulatory Guide 1.33, Revision 2, February 1978, and ANSI N18.7-1976/ANS-3.2, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants"' during the operational phase except for the following clarifications or alternatives.

A. ANSI N18.7-1976/ANS-3.2, Section 5.2.2, Procedure Adherence - The term "supervisor in charge of the shift" means either the Shift Manager or Shift Supervisor.

B. ANSI N18.7-1976/ANS-3.2, Section 5.2.7.1, Maintenance Programs:

1. Emergency maintenance to safety-related equipment (work which must proceed immediately to correct a degraded condition) may be performed concurrent with procedure preparation and documentation of steps actually taken. Such maintenance may be performed with the authorization of designated personnel and subsequent procedure review by the PORC and/or SQR, per Technical Specification requirements.

2. The cause of repetitive malfunctions should be determined; however, it is not practical, and may not be possible, to determine the cause of every malfunction.

C. ANSI N18.7-1976/ANS-3.2, Section 5.2.10, 'Housekeeping and Cleanliness Control".

1. Control measures to prevent contamination with foreign materials will be specified in administrative procedures and will include, as appropriate, access control.

2. Second paragraph, first and second sentences are taken to mean:

"Where needed to prevent contamination...."

D. ANSI N18.7-1976/ANS-3.2, Section 5.2.13, "Procurement and Materials Control" - Item (1) - Administrative procedures shall specify the means for control of procurement of commercially "off-the-shelf" items. The administrative procedures shall describe the receipt inspection, storage, and handling prior to installation and operation.

Revision 76 of 21 Page 4 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C Off-the-shelf (catalog) items are evaluated by qualified personnel for their intended use. The administrative procedures restrict the use of catalog items for only these evaluated applications. The purchase order shall require the vendor to notify the requisitioning organization of a change in an item described in the catalog.

E. ANSI N18.7-1976/ANS-3.2, Section 5.2.13.1, "Procurement Document Control," (second sentence) - QA Program requirements or alternate approved methods will be used to ensure quality. Examples of alternates for suppliers without QA programs include material analysis, sample testing, in-process inspection and monitoring, and design review by LGS/PBAPS.

F. ANSI N18.7-1976/ANS-3.2, Section 5.2.15, 'Review, Approval and Control of Procedures" - The frequency of review of plant procedures is discussed in UFSAR Section 13.5, except for the following alternative.

1. Programmatic controls and processes described in UFSAR Section 13.5 are used to assure that procedures are current.

These controls take the place of scheduled periodic reviews.

PBAPS shall comply with Regulatory Guide 1.33, November 1972, and ANSI N18.7-1972,"Administrative Controls for Nuclear Power Plants"'

during the operational phase except for the following clarifications or alternatives.

G. The programmatic controls and processes found in QATR Chapter 6, Document Control section 2.1, General requirements are used to assure that procedures are current. These controls take the place of scheduled periodic reviews.

At least once every 2 years line organizations that have responsibility for procedures or procedure categories will perform self-assessments of the appropriate components that comprise the procedural development program in accordance with established guidelines. These self-assessments will provide a high degree of confidence maintaining procedures current. In addition, NOS will assess the programs and processes identified above as part of the NOS assessment function.

4. Regulatory Guide 1.37, March 1973, 'Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants." Endorses ANSI N45.2.1-1973.

Decontamination and cleanup of radioactively contaminated systems and components are not included in the scope of this response.

LGS/PBAPS shall comply with Regulatory Guide 1.37, March 1973, and ANSI N45.2.1-1973, except for the following alternatives.

Page5 of21 Rvisin 7 Page 6 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C A. ANSI N45.2.1, Section 3.2, Water Quality Requirements - pH measurements are not required for conductivity values less than or equal to 1 micromho/cm. LGS/PBAPS utilized pH limits of 5.2 to 8.6 at 25 degrees centigrade, uncorrected for C02 , and may apply conductivity measurements in place of total dissolved solids.

B. ANSI N45.2.1, Section 3.1.2, Class B - The flushing velocity may be as specified in other approved documents associated with the maintenance or modification, as well as procurement documents. .

(This item applies to LGS ONLY).

5. Regulatory Guide 1.38, Revision 2, May 1977, "Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants." Endorses ANSI/ASME N45.2.2-1972.

LGS/PBAPS shall comply with Regulatory Guide 1.38, Revision 2, May 1977, and ANSI/ASME N45.2.2-1978), except for the following clarifications or alternatives.

A. ANSI/ASME N45.2.2, Section 2.7, Classification of Items -

LGS/PBAPS does not classify items into the four (4) levels described in this standard. However, the specific guidance and recommendations which are appropriate to each class are applied to those items packaged, shipped, received, stored, and handled through the use of procedures, original specifications, instructions, and drawings, as applicable.

B. ANSI/ASME N45.2.2, Section 3, Packaging, and Section 4, Shipping -

LGS/PBAPS utilizes the packaging and shipping requirements delineated in the original equipment specifications as part of our procurement requirements to suppliers or manufacturers. Those requirements and recommendations of Section 3 and 4 are included in the original specifications as appropriate for the item being procured.

Receipt inspection activities are in accordance with Section 5 of this standard and are sufficient to identify packaging and shipping nonconformances.

C. ANSI/ASME N45.2.2, Section 6, Storage - LGS/PBAPS does not classify items into four (4) levels for storage purposes, as delineated in Section 6.1.2. Stored items are placed in limited access controlled areas, and are segregated with respect to the QA Class of the item(s).

The specific guidance and recommendations which are appropriate to each class are applied to those items stored through the use of procedures, specifications, and manufacturers' recommendations and instructions.

D. ANSI/ASME N45.2.2, Section 6.4.2 (7), Care of Items - The rotating of certain electrical motors in storage, which must be energized to release an electrical brake, will be stored and maintained in Page 6 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C accordance with manufacturers' recommendations. Other motors, which can be rotated without energizing, will be maintained in accordance with the requirements of Section 6.4.2 (7) of the standard.

E. ANSI N45.2.2, Paragraph 6.4.2(5), Care of Items - Space Heaters will be energized on electrical equipment in storage based on the cost/benefit of repairing electrical equipment versus use of heaters.

Predictive maintenance (insulation resistance checks) will be used to identify degraded insulation conditions on electrical equipment in storage where heaters are not utilized.

Additionally PBAPS has the following clarifications and alternatives.

F. ANSI N45.2.2, Paragraph 6.6, Storage Records - Written records shall be prepared that include such pertinent information as storage location, inspection results, and protection (care of items). Personnel access is controlled and limited to Stores Division personnel and visitors who are escorted by Stores Division personnel. (This item applies to PBAPS Only).

G. With regard to Paragraph 7.4, Inspections of Equipment and Rigging, load testing will be performed when feasible. (This item applies to PBAPS Only).

6. Regulatory Guide 1.39, Revision 2, September 1977, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants." Endorses ANSI N45.2.3-1973.

LGS/PBAPS shall comply with Regulatory Guide 1.39, September 1977, and ANSI N45.2.3-1973, except for the following alternatives.

A. ANSI N45.2.3, Section 2.1, Planning - Zone II requirements for clean gloves, shoe covers, and head coverings will be determined by health physics personnel under the radiation protection program and specific requirements listed on the Radiation Work Permit for entry in Zone II areas.

B. ANSI N45.2.3, Section 2.1, Planning - Material accountability for Zones II and IlIl shall be controlled by procedural requirements, periodic inspections, and surveillance of areas for acceptable housekeeping practices. Implementing procedures for activities such as maintenance and modifications require housekeeping and cleanliness inspections of areas and equipment to eliminate foreign materials that may have a detrimental effect. Post maintenance or modification inspections for housekeeping and cleanliness shall be conducted and documented in accordance with administrative controls.

C. ANSI N45.2.3, Section 2.1, Planning - Personnel accountability for Zone IlIl will be controlled as determined by the administrative controls Page 7of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C for locked doors and radiation work permit requirements in lieu of specific access registers.

7. Regulatory Guide 1.94, Revision 1, April 1976, 'Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structure Steel during the Construction Phase of Nuclear Power Plants." Endorses ANSI N45.2.5-1974.

LGS shall comply with Regulatory Guide 1.94, Revision 1, April 1976, and ANSI N45.2.5-1974, except for the following clarification.

A. ANSI N45.2.5-1974 will be implemented by LGS by initiating a procedure, prior to any work, that will assure satisfactory installation, inspection, and testing of structural concrete or structural steel.

PBAPS does not commit to this Regulatory Guide but shall comply with ANSI N45.2-1974, except for the following clarification.

B. ANSI N45.2.5-1974, exclusive of other documents referenced therein, will be implemented through alternate equivalent means prior to placement of any structural steel or concrete at PBAPS Units 2 and 3.

8. Regulatory Guide 1.116, Revision O-R, May 1977, 'Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems." Endorses ANSI N45.2.8-1975.

LGS/PBAPS shall comply with Regulatory Guide 1.116, Revision O-R, May 1977, and ANSI N45.2.8-1975, except for the following alternative:

A. ANSI N45.2.8, Section 2.2, Procedures and Instructions - LGS UFSAR section 13.5 addresses compliance with ANSI N18.7-1976/ANS3.2 and Reg. Guide 1.33, PBAPS Technical Specifications require compliance with Reg. Guide 1.33, Appendix A along with PBAPS commitment to ANSI N18.7-1972. These commitments provide adequate controls for procedures and instructions addressed in this paragraph.

B. ANSI N45.2.8, Section 2.3, Results - LGS commitment to ANSI N18.7-1976/ANS3.2 and PBAPS commitment to ANSI N 18.7-1972 provide adequate guidance for the documentation and review of results of inspection and tests.

C. ANSI N45.2.8, Section 3.4, Physical Condition - LGS/PBAPS responses to ANSI N45.2.1, N45.2.2, and N45.2.13 provide adequate guidance and control for the requirement that mechanical items are in accordance with specified requirements and that the quality has been maintained.

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CODES, STANDARDS, AND GUIDES APPENDIX C

9. Regulatory Guide 1.143, Revision 1, October 1979, "Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants."

LGS shall comply with Regulatory Guide 1.143, Revision 1, October 1979, for major modifications, subject to the exceptions and clarifications listed in LGS UFSAR Table 3.2-1, Note 18.

10. ASTM D3843-93, uStandard Practice for Quality Assurance for Protective Coatings applied to Nuclear Facilities."

LGS/PBAPS shall comply with ASTM D3843-93 for safety-related protective coating work in service level 1 areas during operation with the following additional clarification, exception, and requirement.

A. For coating formulations developed prior to issuance of ASTM D3843-93, service level 1 qualification based on ANSI N5.9 (Revised as ANSI N512-1974) and ANSI N101.2 remains valid.

B. Section 10.1, last sentence - instead of references to ANSI 45.2 and NQA-1, inspections will be documented for record purposes as required by 10CFR50, Appendix B, and by this QA program description.

C. Limitations on use of coatings and cleaning materials which contain elements which could contribute to corrosion, inter-granular cracking, or stress corrosion cracking of safety-related stainless steel will be followed as described in Section C.4 of regulatory Guide 1.54, June 1973.

11. Branch Technical Position (BTP) CMEB 9.5-1:

For modification work performed by the Nuclear Engineering Division during the operations phase, the Nuclear Engineering Division will maintain compliance with the requirements of CMEB 9.5-1 in accordance with Section 9.5.1.

12. ASME Boiler and Pressure Vessel Code Section III - The code year for the Section III B&PV Design Code is found in the applicable site UFSAR.

13. ASME Boiler and Pressure Vessel Code Section Xl - The code year for the Section XI B&PV Inspection Code is found in the applicable site UFSAR.

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CODES, STANDARDS, AND GUIDES APPENDIX C CODES, STANDARDS, AND GUIDES APPENDIX C 1.3.2. Oyster Creek (OCNGS) and Three Mile Island (TMI) Stations

1. Regulatory Guide 1.30, August 1972, "Quality Assurance Requirements for the Installation, Inspection and Testing of Instrumentation and Electric Equipment."

A. The Company shall comply with the Regulatory Position established in this Regulatory Guide in that QA programmatic/administrative requirements included therein shall apply to maintenance and modification activities even though such requirements were not in effect originally. Technical requirements associated with maintenance and modifications shall be the original technical requirements or better (e.g., code requirements, material properties, design margins, manufacturing processes, and inspection requirements).

B. Sections 5.2 and 6.2 of ANSI N45.2.4 list tests which are to be conducted during the construction phase. In lieu of this, the Company utilizes its Engineering and/or Maintenance organizations to establish the need for specific tests or test procedures during the operational phase.

2. Regulatory Guide 1.33, Rev. 2, February 1978, "Quality Assurance Program Requirements (Operation).'

The stations comply with the Regulatory Position of this Guide with the following clarifications:

A. Paragraph 5.2.2 of ANSI N18.7-1976, titled "Procedure Adherence."

In accordance with Section 6.8.3 of the OCNGS and TMI Technical Specifications, temporary changes shall be approved by two members of the Company's management staff qualified as a 50.59 Evaluator/Reviewer who meets the qualification criteria of Technical Specification 6.5.1.14 and knowledgeable in the area affected by the procedure. For changes, which may affect the operational status of facility systems or equipment, at least one of these individuals shall be a member of facility management or supervision holding a Senior Reactor Operator's License on the facility.

B. Paragraph 5.2.15 of ANSI N18.7 - 1976, titled "Review, Approval and Control of Procedures." The third sentence of the third paragraph is interpreted to mean that applicable procedures shall be reviewed following a reportable incident such as an accident, an unexpected transient, significant operator error, or equipment malfunction. In addition, the fourth paragraph is modified to state that the periodic review of procedures shall include the following four elements; a) At least every two years, Nuclear Oversight will assess a representative sample of plant procedures that are used more frequently than every two years.

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CODES, STANDARDS, AND GUIDES APPENDIX C CODES, STANDARDS, AND GUIDES APPENDIX C b) All applicable plant procedures will be reviewed as described in paragraph no. 5.2.15 of ANSI N18.7-1976 as per the noted clarification described for the third sentence of the third paragraph.

c) Plant procedures that have been used at least biennially receive scrutiny by individuals knowledgeable in procedures and are updated as necessary to ensure adequacy during suitable controlled activities.

d) Plant procedures that have not been used for two years will be reviewed before use or biennially to determine if changes are necessary or desirable.

3. Regulatory Guide 1.37, March 16,1973, 'Quality Assurance Requirements for Cleaning Fluids Systems and Associated Components of Water Cooled Nuclear Power Plants. "

The OCNGS and TMI QAP complies with the Regulatory Position of this Guide with the following clarifications:

A. Section 2.1 of ANSI N45.2.1-1973 states that required planning is frequently performed on a generic basis for application to many installations on one or more projects. This results in standard procedures or plans for installation and inspection and testing which meet the requirements of the Standard. Individual plans for each item or system are not normally prepared unless the work operations are unique. However, standard procedures or plans will be reviewed for applicability in each case. Installation plans or procedures are also limited in scope to those actions or activities, which are essential to maintain or achieve the required quality. This is consistent with Section 11, Paragraphs 2 and 3, of ANSI N45.2-1977, which provides for examination, measurement, or testing to assure quality or indirect control by monitoring of processing methods. However, final cleaning or flushing activities will be performed in accordance with procedures specific to the system.

B. Section 3.1.2.1 of ANSI N45.2.1-1973 states that surfaces shall be examined without magnification under a lighting level (background plus supplementary lighting) of at least 100 foot candles. The Company intends to permit the use of neutral 18% gray card with a 1/32" black line for determining acceptability of illumination in lieu of the 100 foot candles.

4. Regulatory Guide 1.38, Rev. 2, May 1977, "Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water Cooled Nuclear Power Plants."

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. CODES, STANDARDS, AND GUIDES APPENDIX C The OCNGS and TMI QAP complies with the Regulatory Position of this Guide with the following modifications or clarifications to ANSI N45.2.2-1 972:

A. Section 2.7, Classification of Items. The four-level classification system for storage of items will be followed, however, the designated classification level may not be explicitly identified on the item. The classification level will, however, be traceable through the procurement documents. Classification differing from Section 2.7 will be considered acceptable provided no degradation is assured; for example, electric motors designed for outside service may be stored in a level C area rather than a level B.

B. Section 3.2, Levels of Packaging. The four level classification system for packaging of items may not be explicitly used. Standard commercial grade packaging requirements may be specified for commercial grade items.

C. Section 3.6 concerns prevention of halogenated materials from contacting stainless steel or nickel alloy materials. The clarifications applicable to Regulatory Guide 1.37, identified previously, also apply to this section of ANSI N45.2.2.

D. Section 3.7.1 Cleated, sheathed boxes will be used up to 1000 lbs.

rather than 500 lbs. as specified. This type of box is safe for, and has been tested for, loads up to 1000 lbs. Other material standards (i.e.,

FED Spec. PPP-8-601) allow this. Special qualification testing shall be required for loads in excess of 1000 lbs.

E. Section 7.4 states that a system should be established to indicate acceptability of all equipment and rigging after each inspection, specify control of non-conforming lifting equipment, and supplement periodic inspections with special visual and nondestructive examinations and dynamic load tests. In lieu of this, the Company does perform dynamic load tests on new equipment, preventive maintenance on cranes, nondestructive examination of lifting hooks annually, and a visual inspection of lifting equipment prior to use.

F. Appendix A 3.4.2, Inert Gas Blankets. There may be cases involving large or complex shapes for which an inert or dry air purge flow is provided rather than static gas blanket in order to provide adequate protection due to difficulty of providing a leak proof barrier. In these cases a positive pressure purge flow may be utilized as an alternate to apleak proof barrier.

G. Appendix A.3.5.2, Tapes will meet a sulfur limit of 0.30% by weight instead of 0.10% as specified in A.3.5.2 (1)(a). This limit is reasonable based upon the chemical content of commercially available tapes. Tapes will be of a contrasting color rather than "Brightly Colored" as required by A.3.5.1 (3).

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CODES, STANDARDS, AND GUIDES APPENDIX C

6. Regulatory Guide 1.39, Rev. 2, September 1977, "Housekeeping Requirements for Water Cooled Nuclear Power Plants.' Endorses ANSI N45.2.3 - 1973.

The OCNGS and TMI QAP complies with this Guide with the following exception to ANSI N45.2.3-1973.

A. Sections 2.1 and 3.2, OCNGS will not utilize the five level zone designation system referenced in ANSI N45.2.3, but will utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with company policy in the areas of housekeeping, plant and personnel safety, and fire protection. Cleanliness will be maintained consistent with the work being performed, so as to prevent the entry of foreign material into systems within the scope of this Plan.

This will include, as a minimum, documented cleanliness inspections performed immediately prior to system closure. Control of personnel, tools, equipment, and supplies will be established when major portions of the reactor system are opened for inspection, maintenance or repair. Additional housekeeping requirements will be implemented as required for control of radioactive contamination.

B. Section 3.2.3 discusses fire protection. Except for the quality assurance aspects of fire protection, no specific commitments are made in the QATR. As part of other activities, the Company has established positions or commitments relating to fire safety or protection.

6. Regulatory Guide 1.54, June 1973, 'Quality Assurance Requirements for Protective Coatings Applied to Water Cooled Nuclear Power Plants."

The OCNGS and TMI QAP complies with this Guide with the following clarifications:

A. The Company will comply with the Regulatory Position established in this Regulatory Guide in that programmatic/administrative quality assurance requirements included therein shall apply to maintenance and modification activities, even though such requirements were not in effect originally. Technical requirements associated with maintenance and modifications (e.g., code requirements, material properties, design margins, manufacturing processes, and inspection requirements) shall be the original requirements or better.

B. The quality assurance program for protective coatings includes the planned and systematic actions necessary to provide adequate confidence that shop or field coating work for nuclear facilities will perform satisfactorily in service.

C. All protective coatings applied to surfaces within containment, except those noted in 3 below, are tested to demonstrate that they can withstand LOCA conditions. These tests are performed in accordance Page 13 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C with Section 4 of ANSI N101.2, "Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities," under LOCA conditions, which equal or exceed those described in the FSAR.

D. The quality assurance program is applied to protective coatings consistent with the nature and scope of work specified in the Technical Specifications. The following elements are included:

1. Preparation of coatings specifications and procedures for generic coating materials/systems.

2. Review and evaluation of coating manufacturers' demonstration test data and quality assurance measures for control of manufacture, identification, and performance verification of applied coating systems.

3. Review and evaluation of supplier quality assurance measures to control storage and handling, surface preparation, application, touch-up, repair, curing and inspection of the coating systems.

4. Training and qualification of inspection personnel in coatings inspection requirements.

5. Supplier surveillance inspection.

E. The coatings qualification program and the associated quality assurance requirements are necessary only for coatings whose failure or failure mechanism would have a significant effect on safety.

F. Regulatory Guide 1.54 is not imposed for:

1. Surfaces to be insulated.

2. Surfaces "contained" within a cabinet or enclosure (for example, the interior surfaces of ducts).

3. Field repair on any Q-class coated item of less than 30 square inches surface area, such as; cut ends or otherwise damaged galvanizing; bolt heads, nuts, and miscellaneous fasteners; and damage resulting from spot, tack, or stud welding.

4. Field touch-up and repair of larger areas shall be in accordance with item A.

5. Small "production line" items such as small motors, hand wheels, electrical cabinets, control panels, loudspeakers, etc., where special painting requirements would be impracticable.

6. Stainless steel or galvanized surfaces.

7. Coating used for the banding of piping.

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CODES, STANDARDS, AND .0. GUIDES APPENDIX C

8. Strippable coatings used for cleanup.

G. Quality assurance documentation may not be similar to records and documents listed in Sections 7.4 through 7.8 of ANSI N101.4, but will be evaluated to assure that they provide at least the same degree of documentation as required by this standard.

7. Regulatory Guide 1.58, Rev. 1, September 1980, 'Qualifications of Nuclear Power Plant Inspection, Examination, and Testing Personnel.'

The OCNGS and TMI QAP complies with this Guide with the following clarifications:

A. Plant operation personnel may be utilized to perform the visual leakage examinations required by the edition of ASME Section Xl and related codes currently committed to for the conduct of in-service inspections. Such personnel shall be qualified consistent with these ASME Code requirements. The selection and qualification of such personnel shall be prescribed by a procedure(s), which is reviewed and concurred with by Quality Verification.

B. Not all personnel who review and approve inspection and testing procedures, evaluate the adequacy of activities to accomplish the inspection and test objectives, evaluate the adequacy of specific programs used to train and test inspection and test personnel, or certify Level IlIl individuals in specific categories or classes, will be certified as meeting the Level IlIl capability requirements of ANSI N45.2.6-1978 (NQA-1). Rather, these personnel will be determined by management to be fully qualified and competent to perform these functions through, evaluation of their education, experience and training. The basis for the determination will be documented.

8. NRC Regulatory Guide 1.94, Rev. 1, April 1976, "Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel during the Construction Phase of Nuclear Power Plants."

The OCNGS and TMI QAP complies with this Guide with the following clarifications:

A. Programmatic/administrative quality assurance requirements included in the Regulatory Guide shall apply to maintenance and modification activities even though such requirements were not in effect originally.

Technical requirements associated with maintenance and modifications shall be the original requirements or better (e.g., code requirements, material properties, design margins, manufacturing processes, and inspection requirements).

B. Section 5.4 of ANSI N45.2.5-1974 specifies the frequency and method of calibration of automatic cut-off impact wrenches used to make up Revision 76 Page 15 I 5 of 21 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C and inspect high strength bolted connections; and the frequency of calibration of hand held torque wrenches used to inspect high strength bolted connections. Section 5.2.6 of ANSI 18.7 as well as Chapter 12 of the QATR also specify controls for measuring and test equipment.

Sections 5.2.16 of ANSI 18.7-1976, in conjunction with Chapter 12 of the QATR, shall be used in lieu of Section 5.4 of ANSI N45.2.5 to control the frequency of calibration of automatic cut-off impact wrenches and hand held torque wrenches used to make up and/or inspect high strength bolted connections. The method of calibration will be consistent with the manufacturer's recommendation(s).

9. Regulatory Guide 1.123, Rev. 1, July 1977, "Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants."

The OCNGS and TMI QAP complies with this Guide with the following clarifications:

A. Section 4.2.a of ANSI N45.2.13-1976. When evaluation of a supplier is based solely on historical supplier data, these data will primarily include records that have been accumulated in connection with previous procurement actions. Data that includes experience of users of identical or similar products of the prospective supplier and product operating experience will be used if available.

B. Section 10.2.1, Verification of the Validity of Supplier Certificates and the Effectiveness of the Certification System, is as follows: The verification of the validity of supplier certificates and the effectiveness of the certification system are accomplished as an integral part of the total supplier control and product acceptance program, and no separate Company system exists that addresses itself solely to such verification. The degree of verification required will depend upon the type of item or service and their safety importance. The means of verification may include source witness/hold points, source audits, and document reviews; independent inspections at the time of material receipt; user tests on selected commodities, such as concrete' components; and tests on selected components and systems after installation. All of these means verify whether or not a supplier has fulfilled procurement document requirements and whether or not a certification system is effective.

10. Regulatory Guide 1.142, October 1981, "Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments)."

A. The Company shall comply with the Regulatory Position established in this Regulatory Guide as augmented by ANSI N45.2.5, ANSI/ANS 6.4-1977, and ANSI/ACI 318-77 for the design and construction of new Safety Related or Augmented Quality structures, and additions to existing Safety Related or Augmented Quality structures. Inspectors Page 16 of 21 Revision 76

CODES, STANDARDS, AND GUIDES APPENDIX C will be qualified according to either ANSI N45.2.6 or Appendix VI1 of Section 1II, Division 2, of the ASME Boiler and Pressure Vessel Code.

11. Regulatory Guide 1.143, October 1979, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Power Plants."

Since OCNGS and TMI were originally designed and constructed to different classification criteria than those contained in this Guide; the Company will comply with the Regulatory Position of this Guide with the following clarifications:

A. For modifications to existing plant systems, items will be classified by Site Engineering according to the original design basis, or this Guide.

This classification will not degrade the safety of the system being modified.

B. Additions to existing plant systems will be designed and constructed to the same codes, standards, and technical requirements which were originally applied to the system to which the addition is to be made, or more recent versions of these codes, standards, and technical requirements. The addition will not degrade the safety of the system being added to.

C. For new construction, the latest applicable codes will be utilized, unless such utilization would result in hardship or unusual difficulty without providing an equivalent level of safety.

D. Hose may be used in lieu of pipe where the connections are temporary. The anticipated applications of hose would normally be (1) connections to contractor owned skid mounted radioactive waste processing equipment, (2) connections to a non-mounted, frequently-changed component such as a burial liner/HIC, or (3) connections to non-mounted pieces of radioactive waste processing or collection equipment which must be readily removable (e.g., items placed on equipment hatches). The pressure rating of such hoses and connections shall equal or exceed those of the systems or components to which they are connected.

1. Prior to use, the hoses shall be hydro-tested to the appropriate pressure for the system or component to which they will be connected. After installation, they will receive regular hydro-testing or in-service inspections.

2. A 50.59 evaluation is required to justify the use of such hose connections.

12. ASME Boiler and Pressure Vessel Code Section III - The code year for the Section III B&PV Design Code is found in the applicable site UFSAR.

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CODES, STANDARDS, AND GUIDES APPENDIX C

13. ASME Boiler and Pressure Vessel Code Section Xl - The code year for the Section Xl B&PV Inspection Code is found in the applicable site UFSAR.

14. NUREG 0737; Clarification of TMI Action Plan Requirements; Item No.

1.6.1.2; Independent Safety Engineering Group; (Oyster Creek Only)

A. the Independent On-site Safety Review Group (IOSRG) shall be a full-time group of engineers experienced in nuclear power plant engineering, operation and/or technology, independent of the facility staff, and located onsite. The IOSRG shall consist of a Manager responsible for the Nuclear Safety Assessment and staff members who meet the qualifications specified in paragraph no. 14.A.1 below.

Group expertise shall be multidisciplined. The IOSRG shall report to the Director responsible for nuclear quality assurance. The IOSRG shall have access to the facility and facility records as necessary to perform its evaluations and assessments. Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.

1. IOSRG engineers shall have either (1) a Bachelor's Degree in Engineering or appropriate Physical Science and three years of professional level experience in the nuclear power field which may include technical supporting functions or (2) eight years of appropriate experience in nuclear power plant operations and/or technology. Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.

2. Reports of evaluations and assessments that encompass the items listed in paragraph no. 14.B below shall be prepared, approved, and transmitted to the Director responsible for Nuclear Quality Assurance, Vice President - Oyster Creek, the Chief Nuclear Officer and the management positions responsible for the areas reviewed. Records of reviews by the Independent Onsite Safety Review Group will be retained for the duration of the Facility Operating License.

B. The periodic review functions of the IOSRG shall include the following on a selective and overview basis:

1. Evaluation for technical adequacy and clarity of procedures important to the safe operation of the facility

2. Evaluation of facility operations from a safety perspective

3. Assessment of facility nuclear safety programs

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CODES, STANDARDS, AND GUIDES APPENDIX C

5. Any other matter involving safe operation of the nuclear power plant that the manager deems appropriate for consideration

15. NUREG 0737; Clarification of TMI Action Plan Requirements; Item No.

I.B.1.2; Independent Safety Engineering Group; (TMI Only)

A. The IOSRG shall be a full-time group of engineers experienced in nuclear power plant engineering, operations and/or technology, independent of the facility staff, and located onsite. The IOSRG shall consist of a Manager and a minimum staff of 3 members who meet the qualifications of paragraph 15.A.1 below. Group expertise shall be multi-disciplined. The IOSRG shall report to the Director responsible for nuclear quality assurance. In the event of an unanticipated vacancy in the ISORG staff, the number of staff can be two (2) members for a period of not to exceed six (6) months while the vacancy is being filled. The IOSRG shall have access to the unit and unit records as necessary to perform its evaluation and assessments.

Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.

1. IOSRG engineers shall have either (1) a Bachelor's Degree in Engineering or the Physical Sciences and three years of professional level experience in the nuclear power field including technical supporting functions, or (2) eight years of appropriate experience in nuclear power plant operations and/or technology.

Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.

2. Reports of evaluations and assessments that encompass the items listed in paragraph no. 15.B below shall be prepared, approved, and transmitted to the Director responsible for Nuclear Quality Assurance, Vice President - TMI Unit 1, the Chief Nuclear Officer and the management positions responsible for the areas reviewed. Records of reviews by the Independent Onsite Safety Review Group will be retained for the duration of the Operating License.

B. The periodic review functions of the IOSRG shall include the following on a selective and overview basis:

1. Evaluation for technical adequacy and clarity of procedures important to the safe operation of the unit

2. Evaluation of unit operations from a safety perspective

3. Assessment of unit nuclear safety programs

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CODES, STANDARDS, AND GUIDES APPENDIX C

5. Any other matter involving safe operations of the nuclear power plant that the onsite IOSRG manager deems appropriate for consideration 1.3.3. Clinton Power Station (CPS)

1. The CPS QAPD also includes the following sections of the Operations Requirements Manual (ORM) and the Updated Safety Analysis Report (USAR). The specific sections are as follows:

A. ORM Section 6.8.2, Procedures and Programs - Review and Approval B. ORM Section 6.8.3, Procedures and Programs - Temporary Changes C. ORM Section 6.10, Record Retention D. USAR Section 13.4 E. USAR Table 3.2-1

2. Site specific clarifications and exceptions applicable to Clinton Power Station include:

A. ASME Boiler and Pressure Vessel Code Section III - The code year for the Section III B&PV Design Code is found in the CPS USAR.

B. ASME Boiler and Pressure Vessel Code Section Xi - The code year for the Section Xl B&PV Inspection Code is found in the CPS USAR.

C. ASME NQA-1 (1994), "Quality Requirements for Nuclear Facility Applications (Revision and Consolidation of ASME NQA-1-1989 and ASME NQA-2-1989 Editions)."

D. AWS D.1.1: The code year utilized for AWS D.1.1 applications is found in the CPS USAR.

E. IEEE-Standard 323(1974): CPS complies with the 1974 Standard with some code year differences, which are found in the CPS USAR.

F. CPS complies with ANS 3.1 (1978), "Selection, Qualification, and Training of Personnel for Nuclear Power Plants." (Member of the Independent Safety Engineering Group (ISEG) are qualified in accordance with ANS 3.1 (1981).) Specifics for compliance, exceptions and clarifications are found in the CPS USAR.

G. The CPS USAR Section 1.8, 'Conformance to NRC Regulatory Guides", which provides the CPS project position for implementation of regulatory guides, includes additional clarifications and exceptions to the regulatory guides.

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CODES, STANDARDS, AND GUIDES APPENDIX C H. CPS complies with RG 1.8 (Proposed Rev 2), "Personnel Qualification and Training." (Also reference USAR Section 1.8.)

I. CPS complies with Regulatory Guide 1.33, Rev. 2 (February 1978);

'Quality Assurance Program Requirements (Operation)." CPS complies with this guide and with the following additional exception:

1. ANSI N18.7-1976/ANS-3.2, Section 5.2.17 Inspections: During plant operations emergencies, inspections may be performed under the direction of the duty shift manager.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D

1. SCOPE This Appendix consists of definitions for words or phrases found in the QAP and provides a common basis for understanding those words or phrases that may have a different meaning when used elsewhere. All words and phrases are subject to review and revision, as circumstances require. Site specific items are noted.

2. GLOSSARY OF TERMS 2.1. Approval Approval as used herein means by signature or initialing and date by an authorized individual.

2.2. ASME Boiler and Pressure Vessel Code,Section I Refers to ASME Section I, Power Boilers 2.3. ASME Boiler and Pressure Vessel Code,Section III, Division I and Division 2 for Concrete Containment Refers to ASME Section III, Division 1 and Division 2 for Concrete Containment; ASME Section 1II; ASME Code; ASME; or Code.

2.4. ASME Boiler and Pressure Vessel Code,Section IV Refers to ASME Section IV, Heating Boilers 2.5. ASME Boiler and Pressure Vessel Code, Section VilI Refers to ASME Section VIII, Pressure Vessels 2.6. ASME Boiler and Pressure Vessel Code, Section Xi Refers to ASME Section Xi, Rules for In-Service Inspection of Nuclear Power Plant Components.

2.7. Audit A planned and documented activity performed to determine by investigation, examination, or evaluation of objective evidence the adequacy of and compliance with established procedures, instructions, drawings, and other applicable documents, and the effectiveness of implementation. An audit should not be confused with surveillance or inspection activities performed for the sole purpose of process control or product acceptance. I Revision 76 I Page I of 21 Page 1 21 Revision 76 l

DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.8. Audit Team Leader An individual appointed to lead an Audit Team. The Audit Team Leader coordinates the preparation of the audit report.

2.9. Auditor One qualified and authorized to examine quality assurance practices and verify whether requirements are being met.

2.10. Augmented D (CPS Only)

A term applied to those components within the Augmented D boundaries as defined in the engineering specifications. See K-2882, USAR Table 3.2.1, and Appendix C of this manual for scope of requirements and boundaries pertaining to Augmented D.

2.11. Authorized Inspector or Al or ANI As used herein is meant to mean Authorized Nuclear Inspector. An Authorized Nuclear Inspector is an employee of an Authorized Inspection Agency who has qualifications for and has been properly accredited for Division 1 or Division 2.

2.12. Authorized Nuclear In-service Inspector or ANII As used herein is meant to mean the Authorized Nuclear In-service Inspector.

An ANII is an employee of an Authorized Inspection Agency who has qualifications for and has been properly accredited for ASME Section Xi.

2.13. Balance of Plant Generating station items and equipment not designed, furnished or installed as a part of the Nuclear Steam Supply System. Balance of Plant items include safety-related and ASME Code items, such as the containment as well as non safety-related and non-ASME Code items.

2.14. Basic Component "Basic component", when applied to nuclear power reactors means a plant structure, system, component or part thereof necessary to assure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe shutdown condition, or (3) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10CFR1 00.1 1 Chapter 1 (1-1-87), Part 21.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.15. Bid Package The total of drawings, specifications, codes, standards, quality and other requirements that describes the task on which a prospective contractor/supplier will bid.

2.16. Calibration A method of assuring accuracy of gauges and instruments used for measuring and testing by comparing with recognized standards.

2.17. Certificate of Compliance A written statement signed by a qualified person, attesting that the materials or items are in compliance with the purchasing documents.

2.18. Certified Personnel Personnel who have passed a formal training program and a formal proficiency test for special processes such as welding, plating and nondestructive testing.

2.19. Certified Standards Standards of measurement whose accuracy can be traced to standards at the National Institute of Standards and Technology or established standards.

2.20. Certified Material Test Report A document attesting that material is in accordance with specified requirements including the actual results of all required chemical analyses, tests and examinations.

2.21. Change Order A formal award to a vendor or contractor covering revision(s) to the original Purchase Order or Change Order, involving but not limited to quantity, technical requirements, quality assurance requirements or scope of work.

2.22. Change Order Requisition A document describing revisions to be made to the original Purchase Order or subsequent Change Order and which is converted into a Change Order.

2.23. Characteristic Any property or attribute of an item, process or service that is distinct, describable and measurable, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings, which describe the item, process or service.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.24. Code See ASME Boiler and Pressure Vessel Code,Section III or Section Xi, whichever is applicable.

2.25. code A recognized standard for using or processing materials, or for the skill involved in use or processing.

2.26. Cognizant Engineer The engineer assigned a specific task or area of responsibility in the design or testing of a component or system.

2.27. ComEd Commonwealth Edison Company (an Exelon Company).

2.28. Company Level III Chief Level III (NDE) for the Company 2.29. Component ASME Code items such as vessels, concrete containments, piping systems, pumps, valves, core support structures and storage tanks which will be combined with other components to form an assembly or installation of a nuclear power plant.

2.30. Component Identification Number An identification number assigned (where appropriate) to an item for use throughout its lifetime.

2.31. Construction Activities at the building site necessary to erect, inspect and accept a power generating station and its associated installation. This definition applies unless otherwise indicated.

- Construction (ASME Section III Div.1) comprises all activities relating to materials, design fabrication, examination, testing, inspection and certification required in the manufacture and installation of items.

- Construction (ASME Section III Div. 2) includes all those operations required to build the component and its parts in accordance with the Design Drawings and Construction Specification which have been prepared by the Designer (AE).

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DEFINITIONS APPENDIX D Those tests necessary to verify that the installation of each component of a system is complete and complies with the applicable specifications, standards, codes, drawings and engineering information.

2.33. Contract (including purchase order)

A binding agreement between two or more persons or companies.

2.34. Contractor Any organization under contract for furnishing items or services. It includes the terms vendor, supplier, subcontractor, fabricator and sub-tier levels of these where appropriate. A uCode" contractor is a contractor holding a valid ASME Section III Certificate of Authorization.

2.35. Control Point In a sequential operation, a checkpoint at which certain data are taken, inspections are made or approval is required.

2.36. Control Stamp A stamp used to mark a unique identification of inspection or test status upon items, tags, labels, routing cards or records traceable to an item. Control stamp impressions learly identify the person who applied it such that traceability to their authorization is provided.

2.37. Corrective Action Measures taken to rectify conditions adverse to quality, and, where necessary, to preclude repetition.

2.38. Department When a responsibility is given to a department in this Manual it is meant that the department head has the responsibility.

2.39. Design Change Any change in design that may affect functional requirements, operating conditions, safety-, regulatory-, reliability-, and ASME Code-related requirements, performance objectives, plant reliability or design life and would require that affected documentation be changed.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.40. Design Controls Methods for assuring that basic design requirements are formalized and translated into design documents with proper review to assure the scheduled release of a valid design.

2.41. Design Criteria Statements of the form, function and interface requirements within well defined limitations.

2.42. Designer (Division 2)

As used in ASME Code Division 2 construction, the Designer (AE) is the organization responsible for the preparation and completion of the Design Report, design drawings, and construction specifications for applicable items.

2.43. Design Requirements Documents that set the functional requirements, operating conditions, safety requirements, performance objectives, design margins and design life. Included are any special requirements for size, weight, ruggedness, materials, fabrications or constructions, testing, maintenance, operating environments, safety margins and derating factors.

2.44. Design Review An analysis of design with respect to technical adequacy, interface control, inspectability, maintainability and conformance to applicable codes, standards, regulations and design criteria.

2.45. Design Specification A document that sets the functional requirements; design requirements; environmental conditions, including radiation; ASME Code classification; definition of the boundaries; and material requirements. Sufficient detail shall be contained within the document to provide a complete basis for design.

For Section III ASME Code, Division I: A document prepared by the owner or owner's designee which provides a complete basis for construction in accordance with the ASME Code, Section IlIl.

2.46. Desk Survey An evaluation of a supplier's quality control capability made from documented procedures and records of past performance.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.47. Destructive Test A test to determine the properties of a material or the behavior of an item which results in the destruction of the sample or item.

2.48. Deviation A non-conformance. Departure of a characteristic from specified requirements.

2.49. Discrepancy A non-conformance.

2.50. Documentation Any written or pictorial information describing, defining, specifying, reporting or certifying activities, requirements, procedures or results.

2.51. Drawing Manifest A document for transmitting drawings released for construction to an engineering, construction and/or production organization.

2.52. Erector An organization involved in assembling and building equipment or structures at the site.

2.53. Examination Specific actions by qualified personnel using qualified procedures to verify that items and fabrication processes are in conformance with specified requirements.

This term, when used in conjunction with qualification of personnel to perform quality-related activities shall mean a written examination.

2.54. Extended Quality Assurance Program (CPS Only)

The selected use of technical and management controls to improve the operational performance of equipment important to reliable station operation but not included in compliance based quality assurance programs.

2.55. Fabricator An organization involved in the manufacture of equipment.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.56. Fabricator (ASME Section III Div. 2)

The NPT Certificate holder 2.57. Final Safety Analysis Report (FSAR)

A finalization of the preliminary safety analysis report prepared for the Nuclear Regulatory Commission prior to issuance of an operating license.

2.58. First Level Design Review A review conducted by the responsible project engineer within the design agency for a specific design discipline.

2.59. Flow Chart A representation of the sequence of activities such as procurement, fabrication, processing, assembly, inspection and test, or the sequence of individual operations within one or more of those functions.

2.60. Hold Point A designated stopping place during or following a specific activity at which inspection or examination is required before further work can be performed.

2.61. Incident Occurrence of major damage, serious personal injury or significant schedule delay.

2.62. Independent Review Review completed by personnel not having direct responsibility for the work functions under review regardless of whether they operate as a part of an organizational unit or as individual staff members.

2.63. In-service Inspection A mandatory program of examinations, testing, inspections and control of repairs and replacements to ensure adequate safety in maintaining the nuclear power plant and to return the plant to service in a safe and expeditious manner.

2.64. Inspection A phase of quality verification that, by means of examination, observation or measurement, determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.65. Inspection and Test Plan A listing, with optimum sequencing, of all the inspections and tests required to be performed for a specific item, component, structure or service.

2.66. Interface When two or more organizations have responsibilities for accomplishing an activity, the functional relationship that one organization has to the others in completing the activity is called an "interface" relation. One example of interface is when one organization must perform a step, which is a prerequisite to another organization accomplishing its function. Interface can also mean that several organizations accomplishing similar activities are under the coordination control of one organization.

2.67. Interface control Consideration that components and structures are geometrically and functionally compatible and those materials are compatible with both process and environment.

2.68. Item Any level of unit assembly, including structure, system, subsystem, subassembly, component, part or material. When ASME Code items are referenced, this means products constructed under a certificate of authorization and material.

2.69. Jurisdictional Boundaries The physical limits of an ASME Code item, which are identified to determine the applicability of ASME Code rules for that item.

2.70. Lifetime Record A record that meets one or more of the following criteria:

- those that would be of significant value in demonstrating capability for safe operation;

- those that would be of significant value in maintaining, reworking, repairing, replacing, or modifying an item;

- those that would be of significant value in understanding the cause of an accident or malfunction of an item;

- those that provide required baseline data for in-service inspections.

2.71. Like - for - Like Replacement The replacement of an item with an item that is identical in all physical and performance characteristics.

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DEFINITIONS APPENDIX D 2.72. Local Purchase Order A purchase order initiated through the computer by a station for the purchase of only Company Stores Coded items.

2.73. Maintenance Repair, rework, or replacement of a structure, system or component with equipment of the same design, i.e., meeting the same engineering requirements.

2.74. Maintenance/Modification Work Package The complete set of documentation that enables the station to fabricate, examine, test and install ASME and safety related items. The work package consists of the work request, provisions for station traveler, document checklist and maintenance/modification procedures and supporting information such as, but not limited to, approved drawings, design specifications, and special process procedures.

2.75. Material A substance or combination of substances forming components, parts, pieces and equipment. (Intended to include such things as machinery, castings, liquids, formed steel shapes, aggregates and cement.)

When ASME Code material is referenced (this refers to metallic materials) which are manufactured to a SA, SB, or SFA Specification or any other material specification permitted by Section III of the ASME Code. For Division 2, refers to metallic materials, as well as to nonmetallic materials, conforming to the specifications permitted in Section III of the ASME Code.

2.76. Material Supplier An organization which supplies material produced and certified by Material Manufacturers, but does not perform any operations that affect the material except when agreed upon by the Certificate Holder who uses the material in ASME Code construction or when so authorized by a Quality System Certificate (Materials). The Material Supplier may perform and certify the results of tests, examinations, repairs, or treatments required by the material specification that were not performed by the Material Manufacturer.

2.77. Measuring and Test Equipment (M&TE)

Equipment used to quantitatively generate or measure physical or electrical parameters with a known degree of accuracy for the purpose of calibration, inspection, test, or repair of plant mechanical, electrical, or instrument control equipment.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.78. Modification A change to an item made necessary by, or resulting in, a change in design requirements (ASME - NCA 9000). A planned change in plant design or operation and accomplished in accordance with the requirements and limitation of applicable codes, standards, specifications, licenses and predetermined safety restrictions.

2.79. National Standards Standards maintained at or issued by the National Institute of Standards and Technology (NIST) or other designated institutions, and the values for natural physical constants and conversion factors recommended by NIST.

2.80. Non-compliance A failure to comply with a regulatory requirement 2.81. Nonconformance A nonconformance is a deficiency in characteristic, documentation, or procedure that renders the quality of a structure, system, or component (SSC) or activity unacceptable or indeterminate. Some examples of nonconforming conditions include the following:

- There is failure to conform to one or more applicable codes or standards specified in the UFSAR or procurement documents.

- As-built equipment, or as modified equipment, does not meet UFSAR descriptions or design bases.

- Requirements can not be substantiated with proper documentation.

- Physical defects.

- Test failures.

- Deviation from prescribed processing, inspection, or test procedures.

2.82. Nonpermanent Record A record that is required to show evidence that an activity was performed in accordance with the applicable requirements but do not meet the criteria for a lifetime record.

2.83. NQA -1 (ASME NQA -1)

Quality Assurance Program Requirements for Nuclear Facilities. For ASME Section III activities, NQA - 1 is as modified by the ASME Code.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.84. Nuclear Steam Supply System (NSSS)

That portion of the nuclear generating plant that provides steam from nuclear heat. It includes the reactor, its control systems, main coolant and steam generation systems, fuel handling equipment, emergency core cooling system and other safeguards, associated electrical equipment, instrumentation, spent fuel handling and radioactive waste disposal system.

2.85. Objective Evidence Any statement of fact, information or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, measurements or tests that can be verified.

2.86. Offsite Review Offsite review is the offsite review and investigative function required by the Technical Specifications. Offsite review requirements are satisfied by the Nuclear Safety Review Boards for operating Units.

2.87. Onsite Review Onsite review is the onsite review and investigative function required by the Technical Specifications. Onsite review requirements are satisfied by the Technical Review Program and the Plant Operations Review Committee at the operating plants.

2.88. OperablelOperability A system, subsystem, train, component or device shall be operable or have operability when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s). NOTE: Safe operation of the plant is determined by licensed operators.

2.89. Operational Tests Tests that are performed during the operations of the plant to verify continued satisfactory performance of safety-related structures, systems and components.

2.90. Personnel Access Data System (PADS)

A computerized and restricted access data system used by the domestic commercial nuclear power industry to share information necessary to process the applications of workers for unescorted access to nuclear power plants. This system is intended to meet regulatory requirements mandating that certain information be available to any power reactor licensee by retaining certain access information in a central computer database.

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DEFINITIONS APPENDIX D 2.91. Permanently Installed Instrument and Control Devices The installed plant equipment including computer points used in determining acceptance criteria of Technical Specification surveillances (Category A Instruments for CPS).

2.92. Phased Replacement Where several identical items are to be replaced with a new model, they are replaced a few at a time to allow monitoring of the new items.

2.93. Preliminary Safety Analysis Report (PSAR)

The initial detailed safety evaluation prepared for the U.S. Nuclear Regulatory Commission prior to issuance of the site construction permit. The PSAR delineates design, normal and emergency operation, potential accidents and predicted consequences of such accidents and the means proposed to prevent such accidents and/or reduce their consequences to acceptable levels.

2.94. Pre-Operational Testing Preliminary testing prior to fuel loading and plant operation to assure that construction and installation are complete and to verify design and system functions.

2.95. Procedure A controlled 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, accept/reject criteria and sequence of operations.

2.96. Proprietary Designs Designs engineered, produced and sold by manufacturers in accordance with their criteria and warranty.

2.97. Purchase Requisition The basic document describing a material, component or service that is converted into a purchase order for procurements.

2.98. Quality Assurance All those planned and systematic actions necessary to provide adequate confidence that an item or a facility will perform satisfactorily in service. For the ASME Code, Quality Assurance comprises all those planned and systematic actions necessary to provide adequate confidence that all items designed and constructed are in accordance with the applicable ASME Code.

2.99. Quality Assurance Program (QAP)

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DEFINITIONS APPENDIX D The Quality Assurance Program is the method for complying with the provisions of 10CFR50 Appendix B for nuclear power plant systems, structures, and components that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. The Quality Assurance Program is defined in the Quality Assurance Topical Report and implementing procedures.

2.100. Quality Assurance Topical Report (QATR)

A NRC approved regulatory document that describes quality assurance program elements for the operational phase of nuclear power plants. This term is synonymous with Quality Assurance Program Description (QAPD), Operation Quality Assurance Program (OQAP), and Quality Assurance Manual (QAM).

2.101. Quality Control See Quality Verification 2.102. Quality Receipt Inspection Report A form utilized by station Quality Control to document technical receipt inspection of ASME Code and safety-related items received by the station.

2.103. Quality Related Activities which influence quality of safety-related items or work related to those systems, structures and components as identified in the USAR, Table 3.2-1, including design, purchasing, fabricating, handling, shipping, storing, cleaning, preserving, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling or modifying.

2.104. Quality Verification Those quality assurance examinations and actions that provide a means to control and measure the characteristics of an item, process or facility to determine or establish conformance to acceptance standards and specified requirements.

2.105. Receipt Inspection An inspection which verifies that items are in satisfactory condition, that they match the purchase order requirements and that required documentation accurately reflects the item(s) received. Visual and physical inspection will be performed as necessary to determine the acceptability of the item(s).

2.106. Receiving Inspection Notice (RIN)

A form initiated by the station upon receipt of ASME Code or safety-related items to record inspection for damage, to record receipt of documentation and to notify station Quality Control that item(s) are available for technical receipt inspection.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.107. Record A completed document that:

- furnishes evidence of the quality of items or activities.

- furnishes evidence of compliance with regulations or requirements.

- is required by Technical Specifications.

Included are such related documents as drawings, specifications, procurement documents, procedures, operating logs, and reportable occurrences. Such documents may be originals or reproduced copies.

2.108. Registered Professional Engineer (RPE)

A person competent in the applicable field of design and qualified in accordance with the requirements of ASME Section III, Appendix XXIII.

2.109. Repair The process of restoring a nonconforming characteristic 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 requirements. For ASME Section III items, repair is the process of physically restoring a nonconformance to a condition such that an item complies with ASME Code requirements.

2.110. Request for Bid Invitation made to suppliers or contractors to bid on a specific task for materials, goods and services.

2.111. Request for Purchase A generating station's document originated by foremen, supervisors or department heads that designates the required items and services and delineates the design specifications, applicable codes and standards, as well as, any special requirements. This document is the basis of initiating a Purchase Requisition.

2.112. Resolution (CPS Only)

The process by which a nonconforming item is corrected or determined to adequately perform its design function without adversely affecting safety. The resolution may contain controls or limitations that are to apply until the nonconformance is fully corrected.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.113. Rework The process by which a nonconforming item is made to conform to a prior specified requirement by completion, re-machining, and re-assembling using previously approved procedural requirements. (For ASME Section III, rework is same as repair.)

2.114. Safety-Related Systems, structures and components, which are considered important to safety because they perform safety actions, required to avoid or mitigate the consequences of abnormal operation transients or accidents. In addition, design requirements are placed upon such equipment to assure the proper performance of safety actions, when required (Safety-related items are those designated Seismic Category 1, Safety Class 1, 2, 3, "Other" and Electrical Class 1E as identified in the CPS USAR, Section 3.2).

2.115. Second Level Design Review Independent objective assessment of a design by qualified personnel who have no direct project responsibility for the design.

2.116. Seismic Classification Plant structures, systems and components important to safety which are designed to withstand the effects of a safe shutdown earthquake and remain functional if they are necessary to assure:

- The integrity of the reactor coolant pressure boundary, or

- The capability to shutdown the reactor and maintain it in a safe condition, or

- The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR1 00.

(Plant structures, systems and components, including their foundations and supports, which are designed to remain functional in the event of an SSE are designated as Seismic Category 1 as indicated in Table 3.2-1 of the CPS USAR.)

2.117. Significant Conditions (adverse to quality)

Those violations, deficiencies or events, having safety significance, that are required to be reported in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC; severe operating abnormalities or large deviations from expected plant performance of safety related structures, systems, or components; "events" as described in the plant Technical Specifications; pervasive breakdowns in the quality assurance program; recurring deficiencies or errors that cannot be dispositioned or brought into conformance by established corrective action systems; or violations of the ASME Code that cannot be readily brought into compliance.

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DEFINITIONS APPENDIX D 2.118. Source Acceptance Acceptance made at a vendor's plant prior to shipment of purchased items.

2.119. Source Inspection Inspection carried out at a vendor's plant prior to shipment of purchased items.

2.120. Special Process A process, the results of which are highly dependent on the control of the process or skill of the operator, or both.

2.121. Special Process Procedures Manual A compilation of Company procedures governing nondestructive examination and special processes such as welding and heat-treating.

2.122. Specification A concise set of requirements to be satisfied by a product, material or process.

The set of requirements may, also, indicate the procedure by which one may determine if the given requirements are satisfied.

2.123. Start Up Tests Tests that are performed after initial fuel loading and proceed through several power level plateaus to 100% power.

2.124. Stock Material Material which is or may be used for conversion to an ASME SA, SB, or SFA Specification or allowable ASTM Specification. As used in this Program, Stock Material is that material that has not been produced in accordance with an NCA 3800 QA Program.

2.125. Stop Work Collective term used to describe the following three levels of stopping work activities:

- The stopping of a single or specific work activity by NOS personnel.

- A hold imposed by a Department Head on a department or general work activity.

- A Stop Work Action initiated by the NOS Manager.

2.126. Surveillance Examination of supplier's manufacturing, inspection and test operations and of records of work in progress. This activity is documented.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.127. Survey 2.128. A documented evaluation of an organization's ability to perform activities as verified by a determination of the adequacy of the organization's quality program and by a review of the implementation of that program at the location of work.

2.129. System Safety Classifications (CPS Only)

Structures, systems and components are classified as Safety Class 1, Safety Class 2, Safety Class 3, Safety Class Other or Class 1E in accordance with the importance to Nuclear Safety. Equipment is assigned a specific safety class, recognizing that components within a system may be a differing safety importance. Definitions of various Safety Classes are:

2.129.1. Safety Class I (CPS Only)

Components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal make-up system.

2.129.2. Safety Class 2 (CPS Only)

Structures, systems and components, other than service water systems, that are not Safety Class 1, but are necessary to accomplish the safety functions of:

1. Inserting negative reactivity to shut down the reactor,

2. Preventing rapid insertion of positive reactivity,

3. Maintaining core geometry appropriate to all plant process conditions,

4. Providing emergency core cooling,

6. Providing and maintaining containment,

6. Removing residual heat from the reactor and reactor core, or

7. Storing spent fuel.

2.129.3. Safety Class 3 (CPS Only)

Structures, systems and components that are not Safety Class 1 or Safety Class 2, but whose function is to process radioactive fluids and whose postulated failure would result in conservatively calculated offsite doses that exceed 0.5 rem to the whole body or its equivalent to any part of the body in accordance with Regulatory Guide 1.26.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.129.4. Safety Class "Other" (CPS Only)

Structures, systems and components used in the power conversion or other portions of the facility which have no direct safety function, but which may be connected to or influenced by the equipment within the Safety Classes 1, 2 or 3.

2.129.5. Class IE (CPS Only)

The safety classification of the electric equipment and systems that are essential to emergency reactor shutdown, containment isolation, reactor core cooling and containment and reactor heat removal or otherwise are essential in preventing significant release of radioactive material to the environment. (Structures, systems and component safety classifications and related Quality Assurance Program requirements classifications are summarized in Table 3.2-1 of the CPS USAR.)

2.130. Technical Review (nonconforming item)

A determination as to whether a nonconforming item will be accepted "as is",

reworked, repaired to an acceptable condition or rejected.

2.131. Technical Specification The design and performance criteria and operating limits and principles of an operating license to be observed during initial fuel loading, critical testing, start-up, power operations, refueling and maintenance operations.

2.132. Test Determination of the physical and functional properties of an item by subjecting the item to a set of physical, chemical, environmental or operating conditions.

2.133. Test Plan An outline, narrative description or flow diagram indicating the tests to be performed, the methods to be used and the points in the process where they are to be executed. It may be in the form of a test procedure.

2.134. Traceability The ability to verify the history, location, or application of an item by means of recorded identification.

2.135. USAR Abbreviation for the Updated Safety Analysis Report, which is the document submitted by the Company to the Nuclear Regulatory Commission in accordance with 10CFR50.71.

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DEFINITIONS APPENDIX D DEFINITIONS APPENDIX D 2.136. Use - As - Is A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions to safety and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.

2.137. Variation A nonconformance. Departure of a characteristic from specified requirements.

2.138. Verification The act of confirming, substantiating, assuring, and documenting that a task, element, or condition is implemented in conformance with the specified requirements. Two commonly used type of verification as are described as follows:

- Concurrent Verification is also known as "apart-in-action" because the verification is being done concurrently as the action is implemented.

Concurrent Verification is accomplished when two individuals verify the actions concurrently and apart from each other as they perform the task.

Concurrent verification should be used for any action that if performed incorrectly, could result in an immediate threat to personnel safety, nuclear safety, reliable plant operation, or for an activity that can't be verified after it's completed.

- Independent Verification is also known as "apart-in-time" because the verification occurs at some time after the action has been performed. An independent verification is performed at a later time by a second qualified individual who is not part of the initial job performance checking the actions previously performed by others. Independent verification may be used in cases were actions if done incorrectly, could significantly affect nuclear and personnel safety, regulatory or other issues important to safe and reliable plant operations, but would not result in immediate consequences.

2.139. Witness Points In a sequential operation, a notification to the Company, or its authorized agent, that a phase of work is about to be reached, so that it may be witnessed at a specific time, or in process, to verify acceptable performance of the phase.

V\Atness points may be established in the traveler, procedure or in the course of monitoring the work activity.

2.140. Work Instructions Actions to be completed by personnel while they are performing specific tasks in areas such as material controls and identification and fabrication or installation of equipment.

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DEFINITIONS APPENDIX D 2.141. Workmanship That quality of an item expressing its skillful and artful manufacture, without apparent blemishes.

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CONTROL OF RADIOACTIVE WASTE APPENDIX E OR MATERIALS (SITE SPECIFIC)

1. SCOPE Measures shall be established and documented to assure that the requirements of the Code of Federal Regulations, Title 10, Part 71, Title 10, Part 20, and Title 49, Parts 100 through 199, applicable to the packaging and transporting of radioactive wastes or materials are satisfied

2. REQUIREMENTS 2.1. General It is the Company's to minimize the generation of radioactive waste, consistent with the ALARA concept to minimize personnel exposures and environmental contamination. The elements contained within this appendix apply to Three Mile Island, Oyster Creek, and Clinton Power Station Part 20, requires that a quality control program be implemented to verify compliance with Title 10, Part 61.55 (Waste Classification) and Title 10, and Part 61.56 (Waste Characteristics). This Plan shall be implemented to the extent necessary to assure compliance with those Parts of Title 10, using a graded approach.

Subpart H to 10CFR71 identifies the quality assurance criteria applicable to the control of packaging to be utilized to ship radioactive wastes or materials. The portions of this Plan that relate to the criteria in Subpart H to 10CFR71 describe, to a large extent, the administrative controls and quality requirements to be applied in the control, packaging, and transportation of radioactive waste or material.

2.2. Three Mile Island/Oyster Creek 2.2.1. Procedures and administrative controls shall be developed and implemented to cover the following:

1. Processing of radioactive wastes, including the collection, handling and preparation for shipment of radioactive liquids and solids. These procedures shall be consistent with the ALARA program and shall clearly identify the administrative controls and organizational responsibilities.

2. Training and qualification of personnel operating radioactive waste processing equipment, health physics monitoring, packaging and shipping (which includes Waste Classification and establishment of Waste Characteristics) and other operations deemed appropriate by management.

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CONTROL OF RADIOACTIVE WASTE APPENDIX E OR MATERIALS (SITE SPECIFIC)

3. The activities associated with the packaging of radioactive wastes or materials shall include the proper selection of the receptacles to be used for containing the waste materials, the selection of the shipping containers (structures used to contain and support the receptacle and its contents), establishment of Waste Characteristics, radiological control inspections of the packaging prior to release, proper markings on the outside of the package, and the preparation of shipping papers and certificates. The activities shall be in accordance with 10CFR20, 10CFR61, 10CFR71, and 49CFR.

4. Movement of radioactive wastes or materials within and outside the protected area to assure personnel protection at all times.

5. The shipment of radioactive wastes or materials from the Station shall be in accordance with the regulations of the U.S. Department of Transportation for the transportation of hazardous materials (49CFR) and of the NRC (10CFR71 and 10CFR20).

6. Design, fabrication, assembly, testing, and modification of packaging used for transportation of radioactive waste or material which exceed the limits specified by 10CFR71.10 shall not be performed by the Company.

Such packaging shall be purchased from an outside supplier and shall comply with 10CFR71 and 49CFR. The Company shall review and accept designs of packaging purchased from an outside supplier.

7. The packaging used for transporting of radioactive waste or material, which does not exceed the limits specified in 10CFR71.10, whether purchased from an outside supplier or designed by the Company, shall meet 49CFR.

8. Minimization of the generation of radioactive wastes through training programs, prudent scheduling and use of equipment and personnel, and good housekeeping practices.

2.2.2. The carriers to be used for transporting of radioactive waste or material shall be selected on the basis of their experience, knowledge of DOT regulations, control and maintenance of their equipment and the selection and control of their drivers. The carrier is required to have or shall be supplied documented procedures covering acceptance of radioactive waste or material from a shipper, certification requirements, placarding, storage control, reporting of incidents and security. The Company shall review and accept carrier procedures specified by procurement documents covering the acceptance of radioactive waste or material for shipment.

2.2.3. Operations involving radioactive waste processing or radioactive material shall be controlled to minimize personnel exposures or environmental contamination, consistent with ALARA.

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CONTROL OF RADIOACTIVE WASTE APPENDIX E OR MATERIALS (SITE SPECIFIC) 2.2.4. Operations procedures relating to radioactive waste or material shipping and packaging shall be reviewed by Quality Verification to establish any necessary inspection points.

2.3. Clinton Power Station 2.3.1. Radioactive Waste/Augmented "D" Systems.

QATR Chapters that are applicable to Radioactive Waste/Augmented "D" Systems are 1 through 7, 9 through 11, and 13 through 18. Chapters 8 and 12 do not apply.

1. Chapter 4 - Specification of quality assurance program requirements for suppliers of radioactive waste/augmented D materials, equipment and services shall be on a case-by-case basis. Commercial grade or off-the-shelf items may provide an acceptable level of quality based on the nature of the item. This determination shall be made by Engineering personnel prior to issuance of procurement documents.

2. Chapter 7 - Suppliers providing material, equipment and services for Radioactive Waste/Augmented D shall be subject to source evaluation and surveillance. The extent of imposition of these requirements shall be determined on a case-by-case basis by the design organization responsible for review and approval of the procurement specifications.

Measures shall be established, and appropriate, for examination of products upon delivery.

3. Chapter 9 - Applicable to the qualification of welders and welding procedures (ASME Section IX) for Radioactive Waste systems.

(Pressure boundaries only.)

4. Chapter 10 - Applicable only to inspection of those items and activities affecting Radioactive Waste/Augmented D systems within the quality assurance boundaries as specified in the USAR, Table 3.2-1, and further amplified by the appropriate design drawings.

2.3.2. Packaging and Transportation of Radioactive Material QATR Chapters 1 through 18 are applicable to the packaging and transportation of radioactive material.

1. Chapter 3 - Applicable, design activities are not normally performed by CPS for radioactive material packaging, however, audits of suppliers establish that the design was accomplished under control of an NRC approved QA program.

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CONTROL OF RADIOACTIVE WASTE APPENDIX E OR MATERIALS (SITE SPECIFIC)

2. Chapter 7 - Applicable, measures such as source surveillance and audits of records should be taken as appropriate to ensure that the design and fabrication of packaging were performed under the control of an NRC-approved QA program.

3. Chapter 9 - Applicable, special processes such as welding or nondestructive testing are not normally performed by CPS. However, if packaging requires major repairs necessitating use of special processes, e.g., welding or heat treating, measures shall be established to ensure that the special processes are controlled.

4. Chapter 10 - Applicable, visual inspections shall be performed upon receipt of packaging to ensure compliance with certificates of compliance.

5. Chapter 13 - Applicable, all conditions identified in a certificate of compliance when using packages shall be adhered to.

6. Chapter 16 - Applicable, measures are established for obtaining corrective actions from suppliers and for ensuring that follow-up is documented to verify that corrective actions were implemented and effective.

7. Chapter 17 - Applicable, records showing evidence of delivery of packages to a carrier and proof that all NRC and Department of Transportation (DOT) requirements have been satisfied shall also be retained.

8. Chapter 18 - Applicable, audits are performed on the supplier of packaging to ensure compliance with the certificate of compliance.

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GRADED APPROACH (SITE SPECIFIC) APPENDIX F GRADED APPROACH (SITE SPECIFIC) APPENDIX F

1. SCOPE The Company establishes measures that provide a graded approach to quality at Oyster Creek and Three Mile Island Stations. The extent to which the requirements of this appendix and its associated implementing documents are applied to an item will be based upon the effect of a malfunction or failure of the item on nuclear safety or safe plant operations.

2. REQUIREMENTS 2.1. General The quality requirements for items within the scope of this appendix shall be established using approved procedures. Quality requirements will be established by the responsible organizational element and subject to assessment by Nuclear Oversight.

The need for special controls, and surveillance or maintaining of processes, equipment and of operational activities will be applied consistent with:

- The design and fabrication complexity or uniqueness of the item.

- The degree to which functionality can be demonstrated by inspection or test.

- The quality history and degree of standardization of the item.

The extent to which the requirements of the QATR apply to activities will be based, as a minimum, on Operating License conditions and other plans previously submitted to the NRC for approval, other regulatory commitments as may have been made associated with activities, the text of this Plan, the unit's Technical Specifications, and Appendix C of the QATR.

Such other plans or regulatory commitments include, but are not limited to, those associated with emergency planning, physical plant security, safeguard contingency planning, radiological controls, radiological environmental controls, fire protection, in-service inspection, in-service testing, licensed operator qualification and re-qualification, process control, off-site dose calculation, Shift Technical Advisor training, environmental qualification of electrical equipment, security guard training and qualification, etc.

2.2. Quality Classification The scope of the Company's QATR includes but is not limited to items and activities related to safe nuclear plant operation, protection of personnel, and protection of the public. To ensure consistency in identifying those items and activities within the scope of the QATR, a classification process has been developed and documented. This process relies on the use of the terms "Safety Related," "Augmented Quality," and "QATR Scope."

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GRADED APPROACH (SITE SPECIFIC) APPENDIX F 2.2.1. Nuclear Safety Related or Augmented Quality Items

1. Items within the scope of the QATR are designated as "Nuclear Safety Related" or "Augmented Quality." A quality classification process for Items has been developed. This classification process produces a Component Record List, which identifies the permanent plant structures, systems, and components that are within the scope of the QATR and their specific classification. New Items to which the QATR applies shall be added to the Component Record List subsequent to their installation.

The classification of structures, systems, and components shall be subject to independent design review as part of the classification process.

2. Spare or replacement parts and materials are not necessarily classified the same as the component of which they are a part. Such parts and materials that perform or contribute to the performance of a Safety Related or Augmented Quality function are within the scope of the QATR and classified similar to the component of which it is a part. For procurement of spare or replacement parts which are of a different classification, the classification will be determined by Procurement Engineering. The determinations will be documented, retained, and subject to review and assessment.

3. The classification of items and consumable items (such as chemicals, radwaste liners, diesel fuel, etc.) and the technical and quality requirements will be specified, documented and approved as part of the procurement process.

4. The QATR may be applied to items, other than those designated as "Safety Related" or "Augmented Quality" as specified by Company management.

2.2.2. QATR Scope Activities

1. Activities within the scope of the QATR are designated as within "QATR Scope." Activities that are within the scope are those directly related to nuclear and radiological safety and protection of the public and are delineated below.

2. Support activities within the scope of the QATR are quality classification, operating experience assessment, design, maintenance of environmental and fire protection qualification, nuclear fuel management, procurement, fabrication, handling, shipping, storage, cleaning, erecting, installing, testing, repairing, training, welding, in-service inspection, heat treatment, document control, records management, access authorization and fitness-for-duty.

3. Operational activities within the scope of the QATR are normal, abnormal and emergency operation, chemistry control, core performance monitoring, shift technical advice, equipment control, surveillance testing, in-service testing, maintenance, housekeeping, fire protection, security, Page 2 of 3 Revision 76

GRADED APPROACH (SITE SPECIFIC) APPENDIX F radiological controls, radiological environmental monitoring, radwaste preparation for shipment, radwaste shipment, fuel handling/refueling, technical specification compliance, and emergency preparedness.

4. Assurance activities within the scope of the QATR are assessment (audit, document review, monitoring, survey, and surveillance), inspection, non-destructive examination, and safety review. Individuals who are not directly responsible for managing or performing the work or activity perform assurance activities. Nuclear Oversight personnel perform periodic assessments of the "assurance" activities performed by other organizational elements (e.g. NDE/ISI) to assure effectiveness and adequacy.

5. The above stated activities are controlled through the use of approved documents which are, as a minimum, consistent with the requirements of the QATR, the unit Operating License, specific Regulatory Guides to the extent listed and committed to in Appendix C of the QATR, the Final Safety Analysis Report, and other regulatory requirements and commitments.

6. A specific task associated with the above activities will be classified as within scope of the QATR depending upon:

- Statements within the text and the Regulatory Guides identified in Appendix C of the QATR.

- The relationship of the task to the safe operation of the nuclear plant.

- The relationship of the task to the protection of personnel from the effects of radiation.

- The relationship of the task to protection of the health and safety of the public.

- The relationship of the task to regulatory requirements and commitments.

- Other factors specified by Company management.

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SUPPLEMENTAL APPLICATIONS APPENDIX G (SITE SPECIFIC)

1. SCOPE 10CFR50 Appendix B requires a quality assurance program be established in writing and executed for activities affecting the safety-related function of designated structures, systems and components to an extent consistent with their importance to safety.

2. REQUIREMENTS 2.1. Clinton Power Station (CPS)

The areas of Environmental, Fire Protection, and Security are specifically identified in Table 3.2-1 of the CPS USAR and/or highlighted in several Regulatory Guides that define and clarify its importance to the plant.

2.1.1. Environmental QATR Chapters that are applicable to the Environmental area are 1, 2, 15, 16, and 18. Chapters 3, 9, and 10 do not apply.

1. Chapter 4 - Applicable to procurement of monitoring services to be performed by contractors providing services dealing with radiological data and to radionuclide reference standards used for calibration of radiation measurement systems.

2. Chapter 5 - Applicable to all activities related to carrying out the radiological monitoring program including: sample collection; packaging, shipment and receipt of samples for off-site analysis; procurement, maintenance, storage and use of radioactivity reference standards; calibration and checks of radiation and radioactivity measurement systems; and reduction, evaluation and reporting of data.

3. Chapter 6 - Applicable to procedures and instructions required by Chapter 5.

4. Chapter 7 - Applicable to radionuclide reference standards used for calibration of radiation measurement systems and to radiological monitoring activities (services) provided by contractors.

5. Chapter 8 - Applicable only to radiological sample collection, identification, packaging, shipping, receiving, storage and analysis.

6. Chapter 9 - Applicable to radioactivity measurements of samples, instrument backgrounds, replicate samples and analytical blanks; data reduction and verification; computer program documentation and verification.

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SUPPLEMENTAL APPLICATIONS APPENDIX G (SITE SPECIFIC)

7. Chapter 9 - Applicable to laboratory instruments for radiation and radioactivity measurement, continuous radiological effluent monitoring systems and flow-rate measuring devices associated with radiological effluent monitoring systems.

8. Chapter 13 - Applicable to radiological samples only.

9. Chapter 14 - Applicable to continuous radiological effluent monitoring systems equipment only.

10. Chapter 17 - Applicable to personnel training and qualification; field and in-plant collection of samples; continuous effluent monitoring; sample receipt and laboratory identification; sample preparation and radiochemical processing; radioactivity measurements of samples, instrument backgrounds and analytical blanks; data reduction and verification; instrument calibration and calibration standards; computer program documentation; audits; and corrective action.

2.1.2. Fire Protection QATR Chapters that are applicable to the Fire Protection area are 1 through 7, 10, 11, and 14 through 18. Chapters 8, 9, 12 and 13 do not apply.

1. Chapter 4 - Applicable. Specification of quality assurance program requirements for suppliers of fire protection materials, equipment and services shall be on a case-by-case basis. Commercial grade or off-the-shelf items may provide an acceptable level of quality based on the nature of the item. This determination shall be made by Engineering personnel prior to issuance of procurement documents

2. Chapter 7 - Applicable. Suppliers providing material, equipment and services for fire protection shall be subject to source evaluation and surveillance. The extent of imposition of these requirements shall be determined on a case-by-case basis by the design organization responsible for review and approval of the procurement specifications.

Measures shall be established, as appropriate, for examination of products upon delivery.

3. Chapter 10 - Applicable only to inspection of those items and activities affecting the fire protection system within the quality assurance boundaries as specified in the USAR, Table 3.2-1 and further amplified by the appropriate design drawings.

4. Chapter 17 - Applicable to documents designated as Quality Assurance Records generated in the implementation of the Fire Protection Program and consistent with the requirements identified in Chapter 10 above.

Records are prepared and maintained to furnish evidence that the applicable criteria discussed herein are being met for activities affecting the Fire Protection Program.

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SUPPLEMENTAL APPLICATIONS APPENDIX G (SITE SPECIFIC)

5. Chapter 18 - Applicable. Audits shall be performed and documented to verify compliance with the Fire Protection Program, including design and procurement documents, instructions, procedures and drawings and inspection and test activities.

2.1.3. Security QATR Chapters that are applicable to the Security area are 16 through 18.

Chapters 1 through 15 do not apply.

1. Chapter 17 - Applicable to those records required by the CPS Physical Security Plan.

2. Chapter 18 - Applicable to the physical security of CPS and designated records.

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