ML051960048

ISFSI Annual Reporting of Changes to the Quality Assurance Program Revision 27 to the Dominion Nuclear Connecticut. Inc. Quality Assurance Program Topical Report

ML051960048
Person / Time
Site:	Millstone
Issue date:	07/13/2005
From:	Christian D Dominion Nuclear Connecticut
To:	Document Control Desk, NRC/FSME
References
05-411
Download: ML051960048 (39)

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Dominion Nuclear Connecticut, Inc.

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I<i)pc I,crry Road K , I [ L I - ~ o I - L ~ , (:I 06385 July 13, 2005 U.S. Nuclear Regulatory Commission Serial No. 05-41 1 Attention: Document Control Desk NLOSnJS Rev0 Washington, DC 20555-0001 Docket Nos. 50-245 50-336 50-423 72-47 License Nos. DPR-21 DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 1 . 2 AND 3 AND ISFSI ANNUAL REPORTING OF CHANGES TO THE QUALITY ASSURANCE PROGRAM REVISION 27 TO THE DOMINION NUCLEAR CONNECTICUT. INC.

QUALITY ASSURANCE PROGRAM TOPICAL REPORT MILLSTONE POWER -

STATION In accordance with 10 CFR 50.54(a), Dominion Nuclear Connecticut, Inc. (DNC) submits Revision 27 of the Quality Assurance Program (QAP) Topical Report for your records.

A summary of the changes incorporated in this revision of the QAP Topical Report is outlined in Attachment 1, arranged in sequence coinciding with the report sections.

Attachment 2 is a complete replacement version of the revised QAP Topical Report with changes shown in bold italics.

Please note that the DNC Quality Assurance Program Topical Report is shown as Revision 27, effective July 1, 2005, as the changes submitted in the attached revision have been processed in accordance with 10 CFR 50.54(a)(3).

Should you have any questions regarding this submittal, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.

Very truly yours, David A. Christian Senior Vice President and Chief Nuclear Officer Attachments: (2)

Commitments made by this letter: None

Serial No.05-411 Docket Nos. 50-245,50-336, 50-423,72-47 MPS QA Topical Update Page 2 of 2 cc: Mr. S. J. Collins Region 1 Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. A. B. Wang NRC Project Manager, MPS-1 U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 7 E l 11555 Rockville Pike Rockville, MD 20582-2738 Mr. R. J. Prince NRC Inspector, MPS-1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses NRC Senior Project Manager, MPS-2 U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 C2 11555 Rockville Pike Rockville, MD 20582-2738 Mr. G. F. Wunder NRC Senior Project Manager, MPS-3 U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 B3A 1 1555 Rockville Pike Rockville, MD 20582-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Attachment 1 Annual Reporting of Changes to the Quality Assurance Program Revision 27 to the Dominion Nuclear Connecticut, Inc.

Quality Assurance Program Topical Report Millstone Power Station Summary of Changes Millstone Power Station Units 1 , 2 and 3 and ISFSI Dominion Nuclear Connecticut, Inc.

U.S. Nuclear Regulatory Commission Attachment 1/Page 1 of 3 I Section Summarv Description of Changes 0 No changes from Revision 26 to Revision 27.

0 No changes from Revision 26 to Revision 27.

0 No changes from Revision 26 to Revision 27.

Statement 0 No changes from Revision 26 to Revision 27.

QAP 1.0 0 QA Topical Change Request 04-05 modified the QAP to eliminate the term surveillance as it relates to a specific documented record of observed work performed since Nuclear Oversight does not perform surveillances.

0 QA Topical Change Request 04-06 modified the QAP to eliminate the ISEG (Independent Safety Engineering Group) function performed by Station Nuclear Safety (Consistent with NRC SER to Tennessee Valley Authority, dated August 26, 1999, TAC #s MA5105, MA5106, MA5107, MA5054, MA5055, MA5056).

0 QA Topical Change Request 05-01 modified the QAP to identify who will designate an appropriately qualified individual to fulfill the role of the Radiation Protection Manager and not define the specific positions that fulfill this role.

QAP 2.0 0 QA Topical Change Request 04-05 modified the QAP to eliminate the term surveillance as it relates to a specific documented record of observed work performed since Nuclear Oversight does not perform surveillances.

a QA Topical Change Request 05-02 modified the QAP to correctly reflect the responsibilities of Nuclear Oversight for the oversight of vendors quality assurance programs versus Supply Chain Management and to eliminate the term audit as a responsibility for SCM.

0 No changes from Revision 26 to Revision 27.

0 No changes from Revision 26 to Revision 27.

0 QA Topical Change Request 04-05 modified the QAP to eliminate the term surveillance as it relates to a specific documented record of observed work performed since Nuclear Oversight does not perform surveillances.

I QAP 6.0 0 No changes from Revision 26 to Revision 27.

0 No changes from Revision 26 to Revision 27.

0 No changes from Revision 26 to Revision 27.

QA Topical Change Request 05-03 modified the QAP to correctly reflect the responsibilities of Nuclear

U.S. Nuclear Regulatory Commission Attachment 1/Page 2 of 3 r Section Summarv Description of Changes I QAP 10.0 Engineering in assuring the training, testing, and certification of all the Non-Destructive Examination Personnel (NDE) versus Nuclear Oversight and the use of generic terminology for codes, specifications, and standards.

No changes from Revision 26 to Revision 27.

No changes from Revision 26 to Revision 27.

QA Topical Change Request 05-04 modified the QAP to eliminate the need for authorization by the onsite review committee of the basis of acceptance for M&TE calibrations when the calibration of the equipment is not against standards that have an accuracy of at least four times the required accuracy of the equipment being calibrated.

I QAP 13.0 No changes from Revision 26 to Revision 27.

No changes from Revision 26 to Revision 27.

No changes from Revision 26 to Revision 27.

No changes from Revision 26 to Revision 27.

QAP 17.0 No changes from Revision 26 to Revision 27.

No changes from Revision 26 to Revision 27.

I Appendix A No changes from Revision 26 to Revision 27 IAppendix B No changes from Revision 26 to Revision 27.

No changes from Revision 26 to Revision 27.

QA Topical Change Request 04-05 modified the QAP to eliminate the term surveillance as it relates to a specific documented record of observed work performed since Nuclear Oversight does not perform surveillances. The definition of surveillance was changed with the adoption of the NQA-1 definition of surveillance to define the term as it is used in the QAP Topical Report.

QA Topical Change Request 04-08 modified the QAP to add an exception (#21) for the Quality Assurance audit schedule to allow a 25% extension to the frequency of most audits (excluding those mandated by the Code of Federal Regulations) and delete an exception (#16) which allowed a 90-day grace period to the 24 tAppendix F month frequency for audits (Consistent with the NRC SER to North Anna Units 1 & 2 and Surry Units 1 & 2, dated March 1,1994, TAC #s M87225, M87226, M87142, and M87143).

QA Topical Change Request 04-06 modified the QAP to eliminate the ISEG (Independent Safety Engineering Group) function performed by Station Nuclear Safety (Consistent with NRC SER to Tennessee Valley Authority, dated August 26,1999, TAC #s MA5105, MA5106, MA5107, MA5054, MA5055, MA5056).

U.S. Nuclear Regulatory Commission Attachment 1/Page 3 of 3 I I Section Summarv Description of Chanqes Appendix G 0 QA Topical Change Request 05-01 modified the QAP to identify who will designate an appropriately qualified individual to fulfill the role of the Radiation Protection Manager and not define the specific positions that fulfill this role.

0 QA Topical Change Request 05-05 modified the QAP to update this Appendix due to changes in Unit 1s Administrative section of the Defueled Technical Specifications and Unit 2 & 3s Administrative Controls section of the Technical Specifications.

Attachment 2 Annual Reporting of Changes to the Quality Assurance Program Revision 27 to the Dominion Nuclear Connecticut, Inc.

Quality Assurance Program Topical Report Millstone Power Station Millstone Power Station Units 1, 2 and 3 and ISFSI Dominion Nuclear Connecticut, Inc.

TABLE OF CONTENTS QUALITY ASSURANCE PROGRAM (QAP)

TOPICAL REPORT - MILLSTONE POWER STATION Table of Contents Abstract Policy Statement Introduction Quality Assurance Program QAP 1.0 Organization QAP 2.0 Quality Assurance Program QAP 3.0 Design Control QAP 4.0 Procurement Document Control QAP 5.0 Procedures, Instructions and Drawings QAP 6.0 Document Control QAP 7.0 Control of Purchased Material, Equipment and Services QAP 8.0 Identification and Control of Materials, Parts and Components QAP 9.0 Control of Special Processes QAP1O.O Inspection QAPI 1.O Test Control QAP12.0 Control of Measuring and Testing Equipment QAP13.0 Handling, Storage, and Shipping QAP14.0 Inspection, Test, and Operating Status QAP15.0 Nonconforming Materials, Parts, Components, or Services QAP16.0 Corrective Action QAP17.0 Quality Assurance Records QAP18.0 Audits Appendices A. Category I Structures, Systems, and Components B. Qualification and Experience Requirements C. Regulatory Guide and ANSVIEEE Standard Commitments D. Glossary of Quality Assurance Terms E. Program Exceptions F. Administrative Controls G. Technical Specification Position Cross Reference QAP Table of Contents Rev.: 27 Date: 07/01/05 Page 1 of 1

ABSTRACT QUALITY ASSURANCE PROGRAM (QAP)

TOPICAL REPORT - MILLSTONE POWER STATION Dominion Nuclear Connecticut Inc., the licensee, has assumed, and is implementing, a comprehensive Quality Assurance Program for the Millstone Power Station to assure conformance with established regulatory requirements set forth by the Nuclear Regulatory Commission (NRC) and accepted Industry standards. The participants in this Quality Assurance Program assure that the design, fabrication, procurement, construction, testing, operation, refueling, maintenance, repair and modification of Millstone Power Station nuclear units including the decommissioning of Unit 1 and the Independent Spent Fuel Storage Installation (ISFSI) are performed in a safe and effective manner.

This Quality Assurance Program (QAP) Topical Report complies with the requirements set forth in Appendix B of 10 CFR 50, and 10 CFR 72, along with applicable sections of the Safety Analysis Report (SAR) for each license application, the Defueled Safety Analysis Report (DSAR) for Unit 1, and the FSAR for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. The QAP is responsive to the United States NRC Regulatory Guide 1.70, which describes the information required to be presented in the Quality Assurance section of the SARs for Millstone operating Units 2 and 3.

This QAP applies to Millstone Power Station, and to associated support services. This QAP is also established, maintained, and executed with regard to radioactive material transport packages as allowed by 10 CFR 71.lOl(f). Quality Assurance provisions for Fire Protection activities are detailed in the Fire Protection Program.

This QAP applies in its entirety to all activities affecting the safety-related functions of structures, systems, and components in the Millstone Power Station nuclear units and the ISFSI. Safety-Related structures, systems, and components for Millstone Units 2 and 3 are functionally identified in Appendix A of this QAP and are designated Category I by the licensee. Applicability of Appendix A to each FSAR is addressed by existing nuclear unit specific design bases and licensing commitments, and also as specifically identified in each Final Safety Analysis Report (FSAR) addressing Section 3.2.1 of Regulatory Guide 1.70. Safety Related structures, systems, and components for Millstone Unit 1 are defined in the DSAR. Safety Related and Important-to-Safety structures, systems, and components for Millstones ISFSI are defined in the FSAR for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. This QAP is also applicable in its entirety to materials, equipment, parts, consumables, and services designated as Category I. This QAP is applicable to other quality programs including Anticipated Transient Without Scram (ATWS) Quality Assurance, which is applicable to MP-2 only (MP-3 commits to Generic Letter 85-06) and to Electrical Equipment Qualification (EEQ), as defined by licensee commitments. Portions of this QAP are also applicable to Fire Protection Quality Assurance (FPQA), and Radwaste Quality Assurance (RWQA), which are delineated in applicable program manuals and procedures. This QAP is also applicable to Station Blackout Quality Assurance (SBOQA) as identified in licensing commitments and delineated in applicable implementing procedures. Quality Assurance provisions for primary chemistry laboratory activities are detailed in the licensees Nuclear Chemistry Laboratory Quality Assurance Manual.

This QAP is committed to utilize the guidance obtained from the regulatory documents and their endorsed standards identified in Appendix C of this QAP Topical Report.

QAP - Abstract Rev. 27 Date: 07/01/05 Page 1 of 1

POLICY STATEMENT QUALITY ASSURANCE PROGRAM (QAP)

TOPICAL REPORT - MILLSTONE POWER STATION This Quality Assurance Program (QAP) Topical Report has been developed to achieve quality assurance in all activities affecting the safe operation of Millstone Power Station. The policies, requirements and tasks contained in this program description have been developed to achieve quality assurance during activities that apply to the design, fabrication, procurement, construction, testing, operation, refueling, maintenance, repair and modification of Millstone Power Station nuclear units, the ISFSI and the decommissioning of Unit 1.

Dominion Nuclear Connecticut, Inc. (the licensee) procedures which implement this program are described in various manuals.

This QAP applies in its entirety to all activities affecting the safety-related functions of structures, systems, and components of Millstone Power Station. Safety-Related structures, systems and components are functionally identified in Appendix A for Millstone Units 2 and 3 of this QAP and are designated Category I by the licensee. Applicability of Appendix A to each FSAR is addressed by existing nuclear unit specific design bases and licensing commitments, and also as specifically identified in each FSAR addressing Section 3.2.1 of Regulatory Guide 1.70. Safety Related structures, systems, and components for Millstone Unit 1 are defined in the DSAR. This QAP is also applicable in its entirety to materials, equipment, parts, consumables, and services designated as Category I. This QAP is also applicable in its entirety to the design, fabrication, construction, testing, operation, maintenance, modification, and decommissioning of Safety Related and Important-To-Safety ISFSI structures, systems, and components as identified in Section 3.4 of the FSAR for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. This QAP is also applicable to other quality programs including Anticipated Transient Without Scram (ATWS) Quality Assurance, which is applicable to MP-2 only (MP-3 commits to Generic Letter 85-06), and to Electrical Equipment Qualification (EEQ), as defined by licensee commitments. Portions of this QAP are also applicable to Fire Protection Quality Assurance (FPQA), and Radwaste Quality Assurance (RWQA) which are delineated in applicable program manuals and procedures. This QAP is also applicable to Station Blackout Quality Assurance (SBOQA) as identified in licensing commitments and delineated in applicable implementing procedures. Quality Assurance provisions for primary chemistry laboratory activities are detailed in the licensees Nuclear Chemistry Laboratory Quality Assurance Manual.

The development and overall responsibility for this program lies with the President and Chief Operating Officer of Dominion Nuclear Connecticut, Inc., as delegated by the Chief Executive Officer - Dominion Nuclear Connecticut, Inc. The President and Chief Operating Officer -

Dominion Nuclear Connecticut, Inc. has delegated the necessary responsibility and authority to the Senior Vice President - Nuclear Operations and Chief Nuclear Officer (SVPKNO) -

Dominion Nuclear Connecticut, Inc. Corporate authority is delegated to the Manager - Nuclear Oversight for the preparation and administration of this QAP Topical Report. Individual Vice Presidents are responsible for the implementation of their portion of this program. Audits of this program are the responsibility of the Manager - Nuclear Oversight.

QAP Policy Statement Rev. 27 Date: 07/01/05 Page 1 of 2

Any revisions or additions shall be approved by affected departments prior to the incorporation of such changes into the program. Final approval of revisions or additions to this Policy Statement rests with the Senior Vice President - Nuclear Operations and Chief Nuclear Officer (SVP/CNO) -

Dominion Nuclear Connecticut, Inc.

See Signed Copy Next Page Senior Vice President - Nuclear Operations and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

QAP Policy Statement Rev. 27 Date: 07/01/05 Page 2 of 2

Any revisions or additions shall be approved by affected departments prior to the incorporationof such changes into the program. Final approval of revisions or additions to this Policy Statement rests with the Senior Vice President- Nuclear Operations and Chief Nuclear Officer (SVP/CNO) -

Dominion Nuclear Connecticut, Inc.

Senior Vice President- Nuclear Operations and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

QAP Poky Statement Rev. 27 Date: 07/01/05 Page 2 of 2

INTRODUCTION QUALITY ASSURANCE PROGRAM (QAP)

TOPICALREPORT - MILLSTONE POWER STATION This Quality Assurance Program (QAP) Topical Report contains the quality assurance requirements which are relevant to the safety of Millstone Power Station. This QAP Topical Report consists of three parts:

1. Introduction, which defines the purpose of the Topical Program and summarizes its scope and applicability;

2. The QAP, which is applicable in its entirety to all activities affecting the safety-related functions of structures, systems, and components in the Millstone Power Station nuclear units and ISFSI. Safety-Related structures, systems, and components for Millstone Units 2 and 3 are functionally identified in Appendix A of this QAP and are designated Category I by the licensee, Dominion Nuclear Connecticut, Inc. Applicability of Appendix A to each FSAR is addressed by existing nuclear unit specific design bases and licensing commitments, and also as specifically identified in each FSAR addressing Section 3.2.1 of Regulatory Guide 1.70. Safety Related structures, systems, and components for Millstone Unit 1 are defined in the DSAR. Safety Related and Important To Safety structures, systems, and components for Millstones ISFSI are defined in the FSAR for the standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. This QAP is also applicable in its entirety to materials, equipment, parts, consumables, and services designated as Category I. This QAP is applicable to other quality programs including Anticipated Transient Without Scram (ATWS) Quality Assurance, which is applicable to MP-2 only (MP-3 commits to Generic Letter 85-06),

and to Electrical Equipment Qualification (EEQ), as defined by licensee commitments.

This QAP is also applicable to Station Blackout Quality Assurance (SBOQA) as identified in licensing commitments and delineated in applicable implementing procedures. Portions of this QAP are also applicable to Fire Protection Quality Assurance (FPQA) and Radwaste Quality Assurance (RWQA), which are delineated in applicable program manuals and procedures.

3. Appendices, which provide supporting statements and tabulations.

This QAP Topical Report has been prepared to document that a quality assurance program has been established and implemented to assure that adequate quality requirements are being complied with to safeguard licensee employees, contracted personnel and the public during the life of the Millstone Power Station nuclear units and ISFSI. In addition, there are other programs to safeguard licensee employees, contracted personnel, and the public.

The controls which implement the actions identified in this QAP are procedures and instructions which delineate actions and steps necessary to accomplish quality requirements. Procedures and instructions are written by groups, divisions, departments, branches, or sections which have the responsibility for implementing actions as assigned by this QAP. Quality procedures and revisions thereto are reviewed by and concurred with by Nuclear Oversight in accordance with QAP 2.0, Quality Assurance Program and QAP 5.0, Procedures, Instructions, and Drawings.

QAP Introduction Rev. 27 Date: 07/01/05 Page 1 of 2

This QAP is responsive to applicable codes, Nuclear Regulatory Commission regulatory requirements, accepted industrial standards and revisions thereto. Provisions are established to update this QAP Topical Report in accordance with revisions to codes, standards and regulatory requirements, and to inform cognizant personnel to implement appropriate action to assure the highest standard of quality is achieved for structures, systems, components, and services for the Millstone Power Station nuclear units and ISFSI.

See Signed Copy Next Page Manager - Nuclear Oversight QAP Introduction Rev. 27 Date: 07/01/05 Page 2 of 2

This QAP is responsive to applicable codes, Nuclear Regulatory Commission regulatory requirements, accepted industrial standards and revisions thereto. Provisions are established to update this QAP Topical Report in accordance with revisions to codes, standards and regulatory requirements, and to inform cognizant personnel to implement appropriate action to assure the highest standard of quality is achieved for structures, systems, components, and services for the Millstone Power Station nuclear units and ISFSI.

QAP Introduction Rev. 27 Date: 07/01/05 Page 2 of 2

1.O ORGANIZATION 1.I INTRODUCTION This section describes the organizations involved in the operation and technical support of Millstone Power Station (MPS). In addition, this section describes the responsibilities governed by the Quality Assurance Program (QAP) Topical Report.

Qualifications for key personnel are found in the unit Technical Specifications and Appendix B of this QAP, Qualification and Experience Requirements.

NOTE In the remainder of QAP 1.0, the text describes functions that support Millstone Power Station, unless otherwise specified. Units 2 and 3 are operational. Unit 1 is defueled and in a decommissioning mode. Applicable regulations and standards are addressed throughout the QAP as appropriate.

ORGANIZATlON The Chief Executive Officer - Dominion Nuclear Connecticut, Inc. has ultimate responsibility and overall authority for the Dominion Nuclear Connecticut, Inc. nuclear program, and has delegated the necessary responsibility and authority for all Nuclear Operations to the President and Chief Operating Officer - Dominion Nuclear Connecticut, Inc. who has delegated the necessary responsibility and authority to the Senior Vice President - Nuclear Operations and Chief Nuclear Officer (SVPKNO) -

Dominion Nuclear Connecticut, Inc.

KEY MANAGEMENT RESPONSIBILITIES AND AUTHORITY 1.3.1 The Senior Vice President - Nuclear Operations is the Corporate individual responsible to the Senior Vice President - Nuclear Operations and Chief Nuclear Officer (SVPKNO) - Dominion Nuclear Connecticut, Inc. for the operations of the Nuclear Stations and ISFSI. He has overall responsibility for implementing the quality assurance program for the operational phase of the Nuclear Stations.

1.3.2 Site Vice President - Millstone The Site Vice President - Millstone has been delegated the necessary responsibility and authority for the management and direction of all activities related to the operation of Millstone Power Station and ISFSI by the SVP/CNO - Dominion Nuclear Connecticut, Inc. The Site Vice President -

Millstone has overall responsibility for construction, operation, maintenance, modification, quality assurance and implementation of this QAP at Millstone Power Station. The following licensing basis positions report directly to Site Vice President - Millstone:

0 Director - Nuclear Station Operations & Maintenance 0 Director - Nuclear Station Safety & Licensing QAP - 1.O Rev. 27 Date: 07/01/05 Page 1 of 13

I.3.3 Director - Nuclear Station Operations & Maintenance Director - Nuclear Station Operations & Maintenance is responsible for establishing common policies and standards pertaining to the operating units and ISFSI, the safe operation and maintenance of the units, including the decommissioning and related activities for Unit 1, for services in support of the station, and implementation of this QAP. The Director - Nuclear Station Operations & Maintenance is responsible for maintaining compliance with requirements of the Operating License and Technical Specifications as well as applicable federal, state and local laws, regulations and codes. The following departments report directly to the Director - Nuclear Station Operations & Maintenance:

0 Nuclear Operations 0 Nuclear Maintenance 0 Nuclear Site Services 0 Nuclear Outage and Planning Nuclear Training and Supply Chain Management (Site) are matrixed to the Director - Nuclear Station Operations & Maintenance.

1.3.4 Director - Nuclear Station Safety & Licensing Director - Nuclear Station Safety & Licensing is responsible for implementation of this QAP. The following departments report directly to the Director - Nuclear Station Safety & Licensing:

0 Nuclear Procedures & Document Administration 0 Radiological Protection & Chemistry 0 Nuclear Organizational Effectiveness Emergency Preparedness, Protection Services and Information Technology are matrixed to the Director - Nuclear Station Safety & Licensing.

Nuclear Training, Emergency Preparedness, and Protection Services all report to the Vice President - Nuclear Support Services in the Nuclear Business Unit. Security is part of Protection Services. Nuclear Engineering reports to the Vice President - Nuclear Engineering and Services in the Nuclear Business Unit.

1.3.5 Director - Nuclear Oversight The Director - Nuclear Oversight is the corporate individual responsible for the effective performance of Nuclear Oversight. Overall responsibility for the Millstone QAP has been delegated to the Manager - Nuclear Oversight by the SVPKNO - Dominion Nuclear Connecticut, Inc. The Director - Nuclear Oversight is the corporate individual responsible with the necessary authority and responsibility for the following:

0 Overall direction of the quality assurance program QAP 1.O Rev. 27 Date: 07/01/05 Page 2 of 13

0 Development and implementation of policies, plans, requirements, procedures, and conduct of audits The Director - Nuclear Oversight (NO) is responsible for determining the necessity for escalation activities for Audit Findings.

1.3.6 Manager - Nuclear Oversight The Manager - Nuclear Oversight reports to the Director - Nuclear Oversight and is responsible to the Director - Nuclear Oversight for the effective performance of Millstone Nuclear Oversight. The Manager - Nuclear Oversight acts as advisor to the Site Vice President - Millstone and the SVP/CNO - Dominion Nuclear Connecticut, Inc. on items related to nuclear quality and safety at the Millstone Power Station and ISFSI. Overall responsibility for the Millstone QAP has been delegated to the Manager -

Nuclear Oversight by the SVP/CNO - Dominion Nuclear Connecticut, Inc.

The Manager - Nuclear Oversight has the necessary authority and responsibility for the following:

0 Direction of the Millstone quality assurance program 0 Development and implementation of Millstone policies, plans, requirements, procedures, and audits a Verification to assure compliance with 10CFR50 Appendix B and other regulatory requirements a Verification of the implementation of the QAP Topical Report requirements 0 Preparation and issuance of the QAP Topical Report 0 Identification of quality problems 0 Recommendations for solutions to quality problems and verification of the implementation of the solutions Verification is performed through a planned program of audits and inspections by Nuclear Oversight. The Manager - Nuclear Oversight provides objective evidence to management of the performance of quality activities independent of the individual or group directly responsible for performing the specific activity.

The Manager - Nuclear Oversight has the authority and organizational freedom to verify activities affecting quality. This is performed independent of undue influences and responsibilities for schedules and costs.

In order to implement these responsibilities, the Manager - Nuclear Oversight is provided Stop Work authority whereby helshe can suspend unsatisfactory work and control further processing or installation of non-conforming materials. The authority to stop work is assigned to Nuclear Oversight personnel and delineated in an approved procedure.

QAP - 1.0 Rev. 27 Date: 07/01/05 Page 3 of 13

1.3.7 Nuclear Maintenance Nuclear Maintenance is responsible for on-line maintenance, cost and scheduling, installation, maintenance, alterations, adjustment and calibration, replacement and repair of plant electrical and mechanical equipment, and instruments and controls. Responsibilities include scheduling of surveillances required by Technical Specifications, establishing standards and frequency of calibration for instrumentation and ensuring instrumentation and related testing equipment are properly used, inspected and maintained. Nuclear Maintenance is also responsible for directing and coordinating maintenance activities for the ISFSI.

1.3.8 Nuclear Operations Nuclear Operations is responsible for operations, including fire protection. The Manager - Nuclear Operations is responsible for the safe and efficient operation of the units including Unit 1, which is in a decommissioned mode, and the ISFSI. During accident situations, if currently holding an active license on the unit (Senior Reactor Operator (SRO) for Unit 2 or 3, or Certified Fuel Handler (CFH) for Unit 1 related responsibilities, the Manager - Nuclear Operations may relieve the Shift Manager of the responsibility of directing the licensed Control Room operators. The following groups report to the Manager

- Nuclear Operations:

0 Unit Nuclear Operations 0 Nuclear Operations Support 0 Nuclear Operations Work Control 1.3.9 Unit Nuclear Operations The Unit Nuclear Operations groups report to the Manager - Nuclear Operations.. Each group includes the following key supervisory positions:

0 Supervisor - Nuclear Shift Operations 0 Shift Manager(s) 0 Unit Supervisor(s)

Unit 2 Nuclear Operations is responsible for operations regarding the Unit 1 Spent Fuel Pool Island and auxiliary systems. The transfer of Unit 1 operations responsibility to Unit 2 Nuclear Operations does not impact the capability of Unit 2 Operators to perform their duties, including day-to-day functions and accident and transient mitigation.

1.3.9.1 Supervisor - Nuclear Shift Operations The Supervisor - Nuclear Shift Operations provides general supervision for the operation of the respective unit, and coordinates unit operations with maintenance, work management, and other groups. As stipulated in Technical Specifications or in Appendix B, either the Manager - Nuclear Operations or the Supervisor - Nuclear Shift Operations holds an appropriate license QAP - 1.0 Rev. 27 Date: 07/01/05 Page 4 of 13

on the Unit (SRO for Unit 3 and SRO and CFH for Unit 2). Unit 2 Operations is responsible for operations regarding the Unit 1 Spent Fuel Pool Island and auxiliary systems. The Supervisor - Nuclear Shift Operations assures the safe and efficient operation of the assigned unit in accordance with applicable licenses, operating instructions and procedures, emergency procedures and safety rules and regulations. During accident situations, if currently holding an active license on the unit (SRO for Unit 3 and Unit 2, CFH for Unit 2 responsibilities for Unit 1 Spent Fuel Pool and related systems), the Supervisor - Nuclear Shift Operations may relieve the Shift Manager of the responsibility of directing the licensed Control Room operators.

1.3.9.2 Shift Managers The Shift Managers report to the Supervisor - Nuclear Shift Operations and are responsible for the Control Room command function. The Shift Manager holds an appropriate license on the unit (SRO for Unit 3; SRO and CFH for Unit 2). The Shift Manager directs and supervises the operation of the unit. Administrative functions that detract from or are subordinate to the management responsibility for assuring the safe operation of the plant are delegated to other operational personnel not on duty in the Control Room. Unit 2 Control Room provides control and supervision of Unit 1 activities.

During accident situations, unless properly relieved, the Shift Manager remains in the Control Room and directs the activities of the licensed operators. The Shift Manager has direct authority to shut down the respective unit if, in the Shift Managers opinion, serious abnormal conditions exist. A Unit 3 Shift Manager fulfills the facility staff requirements of the Shift Supervisor for the Unit 3 Technical Specifications.

1.3.9.3 Unit Supervisor The Unit Supervisor holds an appropriate license on the unit (SRO) and supervises the operators in the Control Room. The Unit Supervisor directs activities of the licensed Control Room operators, and may operate the controls of equipment and piping systems from the Control Room, or alternate station control location. Unit 2 Control Room provides control and supervision of activities on Unit 1.

1.3.9.4 Control Operators Control Operators for Millstone Units 2 and 3 hold a Reactor Operator or Senior Reactor Operator license on the unit. The Control Operators are responsible to perform the following duties:

0 Start up, operate, and shut down nuclear plant equipment QAP 1.0 Rev. 27 Date: 07/01/05 Page 5 of 13

including, but not limited to, as applicable to the Units status, reactor, reactor auxiliaries, turbine generator unit and its auxiliaries as necessary to satisfy system requirements or station conditions. (Unit 1 is decommissioned.)

0 Test, as scheduled, control room instruments and controls.

Unit 1 is decommissioned.

0 Maintain required logs and calculations, observe these logs for indications of faulty operation, and notify the on-duty Unit Supervisor or the Shift Manager of abnormal plant conditions 1.3.9.5 Plant Equipment Operators Plant Equipment Operators are responsible to perform the following duties:

0 Start up, operate, inspect, adjust, and shut down all auxiliary and other various plant equipment 0 Perform or assist with scheduled operational tests 0 Make minor repairs 1.3.10 Nuclear Outage & Planning Nuclear Outage & Planning is responsible for planning online-maintenance and outage activities.

1.3.11 Nuclear Site Services Nuclear Site Services is responsible for project support of the station, including project construction and project controls.

1.3.12 Nuclear Procedures & Document Administration Nuclear Procedures & Document Administration is responsible for nuclear records management and procedures.

1.3.13 Radiological Protection & Chemistry Radiological Protection & Chemistry carries out chemistry and health physics functions and reports to the Director - Nuclear Station Safety and Licensing.

This reporting relationship provides radiation protection functions with sufficient organizational freedom and independence from operating pressures as required by the unit Technical Specifications. The Director - Nuclear Station Safety and Licensing designates an individual that meets the Radiation Protection Manager position qualifications required by the unit Technical Specifications to perform Radiation Protection Manager duties and responsibilities. Radiological Protection & Chemistry includes the following:

0 scheduling and conducting radiological surveys including contamination sample collection 0 determining contamination levels and assigning work restrictions through QAP - 1.O Rev. 27 Date: 07/01/05 Page 6 of 13

radiation work permits 0 maintaining records and reports on radioactive contamination levels 0 administering the personnel monitoring program and maintaining required records in accordance with federal and state codes 0 Chemistry 1.3.14 Nuclear Organizational Effectiveness Nuclear Organizational Effectiveness is responsible for the Corrective Actions Program, the Operating Experience Program and Shift Technical Advisors.

Nuclear Organizational Effectiveness reports directly to the Director - Nuclear Station Safety and Licensing, and is matrixed to the Director - Organizational Effectiveness.

1.3.15 Emergency Preparedness Emergency Preparedness is responsible for development and maintenance of the on-site radiological emergency plan and the development and coordination of required off-site radiological emergency response plan for Millstone Power Station and ISFSI. Emergency Preparedness reports to the Director - Protective Services & Emergency Preparedness and is matrixed to the Director - Nuclear Station Safety & Licensing.

1.3.16 Nuclear Protection Services Nuclear Protection Services is responsible for station protective services, including security, for Millstone Power Station and ISFSI. Nuclear Protection Services reports to the Director - Protective Services & Emergency Preparedness (corporate) and is matrixed to the Director - Nuclear Station Safety & Licensing.

1.3.17 Nuclear Training Nuclear Training is responsible for operator and technical training including ISFSl related training. The operator training group reports to the Director -

Nuclear Training (corporate) to provide sufficient organizational freedom and independence from operating pressures as required by the unit Technical Specifications. Nuclear Training is matrixed to the Director - Nuclear Station Operations and Maintenance.

1.3.18 Nuclear Engineering Nuclear Engineering reports to the Director - Nuclear Engineering. Nuclear Engineering is responsible for design engineering functions, supporting activities, engineering programs, configuration management including design and configuration control and engineering assurance, engineering technical support and systems engineering, including material engineering. The Director - Nuclear Engineering reports to the Vice President - Nuclear Engineering (corporate) and is matrixed to the Site Vice President.

QAP - 1.O Rev. 27 Date: 07/01/05 Page 7 of 13

Nuclear Fuel Engineering reports to the Director - Dominion Nuclear Analysis and Fuel. The group is responsible for engineering activities in safety analysis and nuclear fuel, including probabilistic risk assessment and reactor and radiological engineering. Nuclear Fuel Engineering is matrixed to the Director

- Nuclear Engineering.

1.3.19 Supply Chain Management (SCM)

Supply Chain Management (SCM) is responsible for procurement.

Responsibilities include approval and oversight of vendors that provide quality-related material and services including source and receipt inspection.

Supply Chain Management (SCM) reports to the Director - Dominion Supply Chain Management (Generation). The Supply Chain Site Manager is matrixed to the Director - Nuclear Station Operations & Maintenance.

1.3.20 Information Technology Information Technology is responsible for the Quality Assurance Software Program. Information Technology reports to the Director - Dominion Information Technology Business Account (Generation), and is matrixed to the Director - Nuclear Station Safety & Licensing.

1.4 QUALITY-RELATED RESPONSIBILITIES COMMON TO ALL DEPARTMENT HEADS The head of each department performing quality activities is responsible for:

Administering those activities within their organization which are required by this QAP; Ensuring implementation of the Quality Assurance Program; Establishing and clearly defining the duties and responsibilities of personnel within their organization who perform quality activities; Planning, selecting, and training personnel to meet the requirements of the QAP Topical Report; and Performing and coordinating quality activities within their department and interfacing with the Nuclear Oversight department.

Each individual performing or verifying activities affecting quality is responsible to conduct those activities in accordance with the requirements of this QAP and implementing procedures. These individuals shall have direct access to such levels of management as may be necessary to perform this function.

The responsibility, authority, and organizational relationship for performing quality activities within each organization is established and delineated in the Dominion QAP - 1.O Rev. 27 Date: 07/01/05 Page 8 of 13

Nuclear Connecticut, Inc. organizational charts, policy statements, and written job or functional descriptions.

Vendors may be delegated the execution of quality assurance functions; however, the company shall retain responsibility for this Quality Assurance Program.

1.5 MANAGEMENT QUALITY ASSURANCE REVIEW The Senior Vice President - Nuclear Operations and Chief Nuclear Officer - Dominion Nuclear Connecticut, Inc. is responsible for the assessment of the scope, status, implementation, and effectiveness of the QAP. To meet this responsibility, a team of qualified individuals is appointed to perform a biennial Management Quality Assurance Review. The team is made up of individuals knowledgeable in quality assurance, quality activities, auditing, management responsibilities, and the QAP Topical Report. This review is:

0 A systematic evaluation; 0 pre-planned toward the objective of determining the adequacy of the QAP and its compliance with Appendix B to 10 CFR 50, 10 CFR 72, and other regulatory requirements; and 0 capable of identifying, communicating, and tracking any required corrective action.

The Senior Vice President - Nuclear Operations and Chief Nuclear Officer - Dominion Nuclear Connecticut, Inc. has delegated the responsibility for the Management Quality Assurance Review to the Manager - Nuclear Oversight.

1.6 SPECIFIC QAP RESPONSIBILITIES The Senior Vice President - Nuclear Operations and Chief Nuclear Officer - Dominion Nuclear Connecticut, Inc. resolves all disputes related to the implementation of the QAP for which resolution is not achieved at lower levels within the organization.

1.7 SUCCESSION OF RESPONSIBILITY FOR OVERALL PLANT OPERATION The succession of responsibility for overall plant instructions or special orders, in the event of absences, incapacitation of personnel or other emergencies, is as follows:

0 Site Vice President - Millstone 0 Director - Nuclear Station Operations & Maintenance 0 Manager - Nuclear Operations 0 Licensed Supervisor - Nuclear Shift Operations designated by Site Vice President - Millstone 0 Shift Manager (SRO) 0 Licensed Unit Supervisor (SRO)

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1.8 ORGANIZATION CHARTS NOTE The following organization charts are incorporated by reference in the Emergency Plan - Millstone Power Station. Changes to these organization charts require an effectiveness review in accordance with 10 CFR 50.54 (9).

Offsite Vice President/ Directors are shadowed to denote corporate reporting positions. Dotted lines represent matrixed relationships for site related communication and administrative purposes.

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Organizational Relationship Chief Executive Officer -

of Functional Groups Having Quality Functions for Millstone Dominion Nuclear Power Station Connecticut Inc.

President and Chief Operating Officer -

Dominion Nuclear Connecticut I

r I

Senior Vice President - Nuclear Operations and Chief Nuclear Officer - Dominion Nuclear Connecticut Inc. I I

Senior Vice President -

Nuclear Operations I

I I

-1 Analysis & Fuels I

Manager -

Nuclear Oversight c I I

II I

I I

Director -

Nuclear Station Operations III I

I Director -

Nuclear Station I 1 I :- I Director -

Nuclear Engineering I

Manager - Nuclear 1I Fuel Engineering I

8 Maintenance Safety & Licensing QAP - 1.0 Figure 1.O Rev. 27 Date: 7/01/05 Page 11 of 13

Organizational Relationship of Functional Groups Having Quality Functions for Millstone Power Director -Nuclear Station Station Nuclear Operations 8 Maintenance Operations &

Nuclear Nuclear Manager - Nuclear Nuclear Site Services Outage & Planning Operations Maintenance Nuclear Training I

Manager -

Nuclear Training 1

Supervisor - Nuclear Shift 1I Supervisor - Nuclear Shift I1 I

1

[ Nuclear Operations Opl? Op;T Nuclear Operations WorkControl Shift Manager (s) Shift Manager (s)

Supply Chain Unit Supervisor (s) Unit Supervisor (s)

Management ..

(Site)

QAP - 1.0 Figure 1.I Rev. 27 Date: 7/0 1/05 Page 12 of 13

Organizational Relationship of Functional Groups Having Quality Functions for Millstone Power Station - Safety & Licensing Director -Nuclear Station Safety & Licensing Radiological Nuclear Procedures 8. Nuclear Organizational .......... Protection Document Administration Effectiveness and Chemistry

............. Nuclear Protection Emergency .....

Services Preparedness I

Information Technology I Security Business Account Information Technology I .....

QAP - 1.O Figure 1.2 Rev. 27 Date: 7/01/05 Page 13 of 13

2.0 QUALITY ASSURANCE PROGRAM 2.1 GENERAL REQUIREMENTS The company has established a Quality Assurance Program (QAP) for the Millstone Power Station which complies with the criteria of 10CFRSO, Appendix B, and follows the regulatory documents and their endorsed ANSVIEEE standards identified in Appendix C with exceptions as identified in Appendix E. The quality assurance requirements set forth in the attached Policy Statement, supplemented by quality assurance procedures, provide the primary basis of this program and the companys policy with regard to quality assurance for the Millstone Power Station nuclear units and ISFSI. This QAP Topical Report is established to accomplish the required level of quality in activities carried out throughout the life of the Stations operating nuclear power plants, the ISFSI and the decommissioning of Unit 1.

This QAP applies in its entirety to all activities affecting the safety-related functions of structures, systems and components of the Millstone Power Station nuclear units and the ISFSI. Safety-Related structures, systems and components for Millstone Units 2 and 3 are functionally identified in Appendix A of this QAP and are designated Category I by the company. Applicability of Appendix A to each FSAR is addressed by existing Nuclear Unit specific Design Bases and Licensing commitments, and also as specifically identified in each FSAR addressing Section 3.2.1 of Regulatory Guide 1.70. Millstone Unit 1 Safety-related structures, systems and components are defined in the DSAR. Safety Related and Important-tosafety structures, systems and components for Millstones ISFSI are defined in the FSAR for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. This QAP is also applicable in its entirety to materials, equipment, parts, consumables and services designated Category I.

This QAP applies to other quality programs including Anticipated Transient Without Scram (ATWS) Quality Assurance, which is applicable to MP-2 only (MP-3 commits to Generic Letter 85-06), and to Electrical Equipment Qualification (EEQ), as defined by company commitments. This QAP is also applicable to Station Blackout Quality Assurance (SBOQA) as identified in licensing commitments and delineated in applicable implementing procedures. Portions of this QAP are also applicable to Fire Protection Quality Assurance (FPQA) and Radwaste Quality Assurance (RWQA),

which are delineated in applicable procedures. .

The Materials, Equipment, and Parts List (MEPL) Program is the process used to evaluate, determine and assign the appropriate quality assurance classification (Safety related or augmented quality) to structures, systems, components, parts, materials, activities and consumables. For quality software, the Software Quality Assurance (SQA) Program provides instructions to classify software and describe the appropriate level of documentation that is warranted for software used to support those functions of structures, systems, and components that are affected by the QAP.

The requirements of this QAP are implemented by the company which operates Millstone Power Station, and their vendors performing activities affecting quality QAP 2.0 Rev. 27 Date: 07/01/05 Page 1 of 6

structures, systems, and components of the Stations nuclear power plants and ISFSI.

Procedures define the required indoctrination and training of personnel performing activities affecting quality, as necessary, to assure that suitable proficiency is achieved and maintained.

Training sessions are documented. The content of the training sessions is described, attendees and attendance date indicated, and the results (e.g.,

examination results) of the training sessions recorded, as applicable.

Periodic program review of the status and adequacy of this QAP is accomplished by Nuclear Oversight audits, surveillances and inspections, by offsite review committee reviews, and by the independent review team which performs the biennial Management Quality Assurance Review described herein and in QAP 1.O, Organization, Section 1.5. Organizations outside the company are required to review the status and adequacy of that part of this QAP for which they have been delegated responsibility.

2.2 IMPLEMENTATlON 2.2.1 GOALS AND OBJECTIVES The goals of this QAP are to maintain quality levels in an effective and efficient manner and to assure a high degree of functional integrity and reliability of Station nuclear power plant quality and ISFSI structures, systems, and components. To meet these goals, the following objectives of this QAP have been defined:

a. Define, through procedures, the quality activities that apply to design, fabrication, procurement, construction, testing, operation, refueling, repair, maintenance and modification of the Station nuclear power plants and ISFSI;

b. Establish, assign, and document the responsibilities for the conduct of those activities affecting quality structures, systems, and components;

c. Establish confidence that (a) quality activities for the Station nuclear power plants are performed consistent with the companys policies and (b) quality activities are performed by qualified personnel, and are verified through a system of audits, surveillances, and inspections of those organizations with quality responsibilities;

d. Apprise the Site Vice President - Millstone and the Senior Vice President -

Nuclear Operations & Chief Nuclear Officer - Dominion Nuclear Connecticut, Inc. of unresolved problems and trends which could have a significant effect on nuclear power plant and ISFSI safety.

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2.2.2 PROGRAM D0CUMENTATI0N This QAP defines the companys nuclear policies, goals, and objectives, and is used as guidance for the development of the various division, department, branch, or section procedures. Revisions to this QAP shall be made as needed to reflect current requirements and descriptions of activities prior to implementation. These revisions shall be made in accordance with a company Procedure.

Revisions to this QAP, which reduce commitments previously accepted by the NRC, are submitted to the NRC for review and approval prior to implementation.

Revisions which do not reduce previously accepted commitments are periodically submitted to the NRC as required by 10 CFR 50.54 (a)(3);

10 CFR 50.55 (f)(3); 10 CFR 50.71(e) and (f) and 10 CFR 72.70.

Quality procedures are developed by the departments performing quality activities. These procedures are reviewed for concurrence by the departments which are responsible for implementing portions of these procedures and are approved by the initiating department. Nuclear Oversight reviews other department quality procedures for compliance with this QAP through its audit program. Changes to procedures are subjected to the same degree of control as that utilized in the preparation of the original document.

Each Vice President and Director is responsible for implementation of this QAP within their organization which includes individual departmental procedure requirements applicable only to their respective activities. In addition, they are responsible for the preparation, approval, and distribution of those instructions, operating procedures, testing procedures, or other instructions where further guidance is necessary.

2.2.3 STRUCTURES, SYSTEMS AND COMPONENTS This QAP applies to all activities affecting the safety-related functions of the structures, systems and components as addressed in the Safety Analysis Reports (SARs). Safety-Related structures, systems, and components are functionally identified in Appendix A for Units 2 and 3 and also as specifically identified in each FSAR addressing Section 3.2.1 of NRC Regulatory Guide 1.70. Unit 1 Safety-Related structures, systems, and components are defined in the DSAR. ISFSI Safety-Related structures, systems, and components are defined in the FSAR for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel.

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For structures, systems and components covered by the ASME Code, the companys procedures describe the measures taken to assure that the quality assurance requirements contained in the code are supplemented by the specific guidance of the applicable regulatory guides and endorsed ANSI standards listed in Appendix C.

For structures, systems and components, regulatory commitments and the companys procedures describe the measures taken to assure that the quality assurance requirements are met.

The degree of control over activities affecting quality structures, systems, and components is consistent with their importance to safety. Such controls include use of appropriate equipment, establishment of suitable environmental conditions, and assurance that all prerequisites for a given activity have been satisfied. This QAP provides controls over special processes and skills necessary to attain the required quality, and the need for verification of quality by inspection and test.

Nuclear Oversight and applicable company technical organizations jointly determine and identify the extent quality assurance controls are applied to quality structures, systems, and components. The quality assurance controls are in conformance with this QAP, which complies with the 18 criteria set forth in Appendix B to 10 CFR 50.

2.2.4 PARTICIPATING ORGANIZATIONS The organization for Millstone Power Station activities affecting the quality of structures, systems, and components is identified in QAP 1.0, Organization, which also briefly describes assigned responsibilities.

Nuclear Oversight is responsible for: a) the development, coordination, and administrative control of this QAP including coordination of Nuclear Oversight procedure review and approval and b) assuring issuance of this QAP Topical Report as a controlled document (as described in QAP 6.0, Document Control). Procedure reviews shall be performed in accordance with QAP 5.0, Procedures, Instructions, and Drawings.

The company requires that its approved vendors performing quality activities invoke upon their subvendors, via purchase orderskontracts, requirements for a quality assurance program to meet the applicable criteria of Appendix B to 10 CFR 50, including the applicable elements of the regulatory guides and their endorsed ANSIAEEE standards identified in Appendix C. However, the company retains overall responsibility for the Millstone Power Station Quality Assurance Program. The specific quality activities performed by these organizations are specified in the procurement documents. Nuclear Oversight is responsible for the review and approval of these vendors quality assurance programs prior to initiation of contracted activities.

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The object of the review is to verify that these vendors have an adequate quality assurance program to meet applicable requirements of I 0 CFR 50, Appendix B.

In addition to the initial review, Supply Chain Management (SCM) is responsible for the subsequent performance, as appropriate, of surveillances and inspections of approved vendors quality assurance programs to assure continued implementation of quality requirements.

Supply Chain Management (SCM) assures that the quality assurance programs of vendors that perform quality activities are periodically reviewed to assure that the vendors are implementing adequate programs. Evaluation, review, and monitoring of vendor quality programs is conducted in accordance with section QAP 7.0, Control of Purchased Material, Equipment and Services.

Vendors may be delegated the execution of quality assurance functions by Contract. These Contracts are reviewed and approved in accordance with this QAP. These vendors may be contracted to perform quality activities under their approved quality assurance program or directly under the requirements of this QAP.

2.2.5 INDOCTRINATION AND TRAINING A program is established and maintained for quality assurance indoctrination and training which provides confidence that the required level of personnel competence and skill is achieved and maintained in the performance of quality activities. Quality procedures delineate the requirements for an indoctrination program to assure that personnel responsible for performing quality activities are instructed in the purpose, scope, and implementation of quality procedures and that compliance to these documents is mandatory. Each Department is responsible for assuring assigned personnel who perform quality activities have been appropriately indoctrinated and trained.

Nuclear training programs shall be developed and implemented to provide training for all individuals attached to or associated with the Station nuclear power plants and ISFSI. Additional guidance is established in the companys procedures.

Procedures describe the nuclear training program requirements which assure that:

a. Documentation of formal training and qualification programs includes the objective, content of the program, attendees, date of attendance; and results (e.g., examination results), as applicable.

b. Proficiency of personnel performing and verifying activities affecting quality is established and maintained. Personnel proficiency is established and maintained by training, examination/testing, and/or QAP 2.0 Rev. 27 Date: 07/01/05 Page 5 of 6

certification based upon the requirements of the activity. Acceptance criteria are developed to determine if individuals are properly trained and qualified;

c. Certificates or other documentation of qualification clearly delineate the specific functions personnel are qualified to perform and the criteria used to qualify personnel in each function.

This program also requires the head of each department to be responsible for a training plan which assures that personnel performing quality activities are trained in the principles and techniques of the activity being performed.

2.2.6 MANAGEMENT PARTICIPATION Millstone Power Station Vice President and Directors are responsible for implementing this QAP within their organization. The Manager - Nuclear Oversight will assist in development, coordination, and review of the program.

The Senior Vice President - Nuclear Operations & Chief Nuclear Officer -

Dominion Nuclear Connecticut, Inc. assures that a management review of this QAP is conducted on a biennial basis by an independent team to assess the scope, status, implementation, and effectiveness, and to assure compliance with NRC licensing commitments. Senior Vice President - Nuclear Operations & Chief Nuclear Officer - Dominion Nuclear Connecticut, Inc. has delegated the responsibility for the management review to the Manager - Nuclear Oversight.

Actions considered by the Management Quality Assurance Review may include, but are not limited to:

a. Review of selected procedures and documents;

b. Verification of the implementationof selected procedural requirements;

c. Review of past audit results and other inspection/review results such as those from previous Management Quality Assurance Reviews, the NRC or other departments.

The Management Quality Assurance Review's findings of deficiencies and recommendations for program improvement are forwarded to the Senior Vice President - Nuclear Operations & Chief Nuclear Officer -

Dominion Nuclear Connecticut, Inc. who shall assure appropriate corrective action is taken.

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3.0 DESIGN CONTROL 3.1 GENERAL REQUIREMENTS This QAP provides measures to assure that the applicable design requirements, such as design bases, regulatory requirements, codes, technical standards and quality standards, are identified in design documents which are reviewed, approved and controlled in accordance with procedures. Such measures include review for suitability of application of materials, equipment, parts and processes that are essential to the functions of quality structures, systems, and components.

Changes to, and deviations from, specified requirements are identified, documented and controlled.

Nuclear Engineering is responsible for controlling design work, administering design control activities (including design interface) and design modifications for quality structures, systems, and components.

The responsibility for administration of the design control program for the Millstone Power Station nuclear power plants and ISFSI rests with Nuclear Engineering. The division of responsibilities and jurisdictional boundaries for design control program implementation are set forth in company procedures. Although other organizations may be delegated the task of establishing and executing the design control program or any part thereof, Nuclear Engineering shall retain overall responsibility for the program. The applicable requirements of this QAP shall be imposed on other organizations delegated the task of establishing or executing the design control program in accordance with QAP 4.0, Procurement Document Control and QAP 7.0, Control of Purchased Material, Equipment and Services.

The interface controls, both internal and external, for organizations performing design work for quality structures, systems, and components are identified and implemented in accordance with procedures. This identification includes those organizations providing criteria, designs, specifications and technical direction.

Measures are applied to verify the adequacy of design. The extent of design verification is specified and documented by the responsible organization. The individuals performing design verification should not (1) have immediate supervisory responsibility for the individual performing the design, (2) have specified a singular design approach, (3) have ruled out certain design considerations, or (4) have established the design inputs for the particular design aspect being verified. The independent design verification should not dilute or replace the responsibility of the supervisors for the quality of work performed under their supervision. Where changes to previously verified designs have been made, design verifications are required for the change, including evaluation of the effects of those changes on the overall design. Design verification may be accomplished by testing. Tests to demonstrate adequacy under adverse design conditions shall comply with the requirements of QAP 11.0, Test Control. Design errors and deficiencies which adversely affect quality structures, systems, and components in the design process are documented and appropriate corrective action is taken.

These design errors and deficiencies are documented in accordance with design QAP 3.0 Rev. 27 Date: 07/01/05 Page 1 of 5

change procedures or as defined in QAP 15.0, Nonconforming Material, Parts, Components, or Services and/or QAP 16.0, Corrective Action.

3.2 IMPLEMENTATION Nuclear Engineering is responsible for the design, design review, engineering approval of design changes, design evaluation and design control for the units and ISFSI. Although some portion of the design process may be delegated to other organizations, Nuclear Engineering has the responsibility for overall design and final engineering decisions and design control of quality structures, systems, and components.

Nuclear Oversight performs audits, surveillances, and inspections, as appropriate, to verify that company processes are effectively complying with this QAP and procedural requirements for design control. Additionally, audits, surveillances and inspections are performed, as appropriate, to verify that vendors are effectively complying with their quality assurance program requirements for design control.

3.2.1 DESIGN PROCESS Design control measures are applied to design analyses, such as, reactor physics, stress, thermal, hydraulic, nuclear radiation, accident and seismic analyses; compatibility of materials; accessibility for in-service inspection, maintenance, and repair; and delineation of acceptance criteria for inspections and test. Measures established to control design documents are described in QAP 6.0, Document Control.

Program procedures and instructions define the method of implementing design control measures. These measures require that applicable design requirements, such as, design bases, regulatory requirements, codes and standards, are translated into specifications, drawings, procedures or instructions. Procedures and instructions further require that appropriate quality standards are specified and included in design documents.

Materials, equipment, parts and processes, including standard off the shelf commercial or previously approved items essential to quality functions are selected and reviewed for suitability of application. The basis for selection may include industry standards, material and prototype hardware testing programs, and design review.

Procedures assure that a documented check is performed to verify the accuracy and completeness of design drawings and specifications before release for procurement, fabrication or construction. Design drawings receive a documented check to verify dimensional accuracy.

Design drawings and specifications issued for design changes are reviewed for completeness and accuracy before release to operations, in accordance with design control procedures.

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Procedures describe the provisions to assure that design drawings and specifications are prepared, reviewed and approved in accordance with company requirements and that the documents contain the necessary quality assurance requirements, such as inspections and test requirements, acceptance requirements, and the extent of documenting inspection and test results.

3.2.2 DESIGN CHANGE CONTROL Procedures and instructions governing design change control during modifications to the Station nuclear plants and ISFSI, the control of discrepant or deficient design conditions, and the reporting of unsatisfactory performance provide for the identification of the need for design changes and a documented method to control these changes, Design and specification changes are subject to design control measures commensurate with those applied during the original design as amended by applicable design or licensing basis changes.

An independent review and approval of design changes is performed by the organization that conducted the original design reviews, unless such review is performed by the company or another qualified organization delegated by the company to perform this function.

Proposed design change modifications are submitted to the appropriate Nuclear Engineering management for processing and review. This review includes the appropriate on-site review committee(s) as required by applicable procedures. If the change involves a quality structure, system or component, the change shall be reviewed by qualified engineering personnel for technical adequacy. Reviews of the 10CFR50.59 and 10CFR72.48 evaluations associated with proposed design changes are performed by the offsite review committee. The sequence of the offsite review committee review depends upon the determination of whether a license amendment (for Unit 1, also an unreviewed decommissioning question), is involved (i.e., in accordance with ANSI N18.7, if a proposed change in the facility requires a license amendment then the offsite review committee review is conducted prior to submittal of the proposed change to the NRC for review and the issuance of a license amendment for its implementation).

The combination of these independent reviews by the on-site review committee(s) and the offsite review committee is performed to assure that:

a. the adequacy of the proposed change is substantiated;

b. changes that require a license amendment are properly identified and handled per 10CFR50.59, and 10CFR72.48; (for Unit 1, unreviewed decommissioning questions are properly identified and handled per 10CFR50.82);

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c. nuclear safety requirements have been addressed.

Errors and deficiencies in design, including the design process, that could adversely affect quality structures, systems, and components are documented and corrective action is taken in accordance with QAP 15.0, Nonconforming Materials, Parts, Components, or Services and/or QAP 16.0, Corrective Action.

Notification of design changes are transmitted to responsible plant personnel prior to implementation and as part of the design change package close out. Procedures describe this notification which assures that personnel are made aware of design change modifications which may affect the performance of their duties.

3.2.3 DESIGN INTERFACE CONTROL Procedures and instructions identify design interface controls and the resolution of design interface questions during modifications to the station nuclear power plants and ISFSI.

3.2.4 INDEPENDENT DESIGN VE RI FI CAT1ON Original designs and design modifications are reviewed for adequacy and the sign-off performed by a person other than the originator of the design.

The originators supervisor may perform this independent review only if the supervisor: (1) did not specify a singular design approach, (2) did not establish the design inputs or rule out certain design considerations, (3) is the only individual in the organization competent to perform the review.

Where the supervisor performs the design review, the next level of management shall fulfill the supervisors responsibilities. Design verification is documented in accordance with procedures or instructions.

Simplified calculations or computer programs may be utilized as alternate means of design verification. When design verification is performed by testing, the tests are performed using procedures, which specify the authority and responsibility of design verification personnel.

Responsibility for design adequacy and evaluation is retained by Nuclear Engineering.

Design verification (if other than by qualification testing) is normally completed prior to release for procurement, fabrication, and construction, or release to another organization for use in other design activities. For those cases where design verification cannot be completed prior to release for procurement, fabrication, and construction, procedures assure that design verification is completed prior to the point when the installation is declared operational.

Procedures describe the requirements which assure the following when testing is considered as an alternate method of design verification:

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a. Specifications or procedures provide criteria that specify when verification should be by test.

b. Prototype, component or feature testing is performed as early as possible prior to installation of plant equipment, or prior to the point when the installation is declared operational.

c. Verification by test performed under conditions that simulate the most adverse conditions as determined by analysis.

Particular emphasis is placed on assuring that designs are in conformance with applicable codes, and on selecting the proper design verification or checking method. Procedures and instructions provide the requirements and necessary controls for design verification. These controls include a review to assure that design characteristics can be controlled, verification that there is adequate accessibility for inspection or test, and that inspection and test acceptance criteria are incorporated.

Documentation of reviews is provided.

Procedures include requirements which identify the responsibility of design verifiers, the areas and features to be verified, and the extent of the documentation.

Procedures assure that procedural control is established for design documents that reflect the commitments of the nuclear unit or ISFSI FSAWDSAR. These procedural controls vary for design documents which receive formal design verification by several disciplines or organizations, and those which can be reviewed by a single individual.

The specific design documents and specialized reviews are determined and used as required by the design changes and modifications.

Procedures are established to assure that verified computer programs are certified for a specific use.

The company is responsible for assuring that the design documents generated by vendors for the Station nuclear power plants and ISFSI are technically correct, approved, and maintained.

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