ML20210A041

Rev 20,change 10 to Northeast Util QA Program Tr

ML20210A041
Person / Time
Site:	Millstone
Issue date:	07/15/1999
From:	NORTHEAST NUCLEAR ENERGY CO.
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MP-02-OST-BAP01, NUDOCS 9907220011
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• NDS Document Transmittal #152279 7/13/99 To: Nuclear Regulatory Commission Addressee Unique # 140 Document Control Desk ROUTINE distribution Washington, D.C. 20565 The following documents have been revised. You are currently on distribution for these documents. Verify that all documents are included in this distribution set.

DOCUMENT REV COPlES MP-02-OST-BAP01, CH10 20 1 controned copys 34 9907220011 99o71s PDR ADOCK 05000245 P PDR -

Sign and return this form as soon as received to: Diane ONeil x2451, NDS/CDL, 8433-1, Millstone or FAX (860) 444-5711.

Signature Date:

\

N:rthat Utilities System j

U Memo 7/12/99 028-PRG-99 TO: Northeast Utilities Quality Assurance Program Topical Report Controlled Copyholders

~

FROM: R. Fletcher *

SUBJECT:

NUQAP Topical Report Revision 20, Change 10 (Document No. MP-02-OST-BAP01 Enclosed is change number 10 to NUQAP revision 20 that was SORC approved on 7/7/99.

/~ Please replace the entire contents of existing QAP 1.0,2.0,3.0,7.0,12.0,15.0,16.0,18.0, b] Policy Statement, Appendix B, C, D, E, F, G and Table of Contents with the enclosed sections.

Change 10 changes are in bold anditalics with a revision bar in the right margin. The footer of the affected section willinclude a reference to change 10 Insert the summary of changes document in the front of your manual.

If you have any questions, contact R. Fletcher at X4350 Attachments; .

l

1. Summary of changes incorporated as part of revision 20, change 10.

Enclosure:

1. Change 10 to the Northeast Utilities Quality Assurance program Topical Report revision 20.

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6 [ N:rthea:t j Utilities System Memo 7/12/99 028-PRG-99 TO: Northeast Utilities Quality Assurance Program Topical Report Controlled Copyholders

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- FROM: R. Fletcher -

SUBJECT:

NUQAP Topical Report Revision 20, Change 10 (Document No. MP-02-OST-BAP01 Enclosed is change number 10 to NUQAP revision 20 that was SORC approved on 7/7/99.

Please replace the entire contents of existing QAP 1.0,2.0,3.0,7.0,12.0,15.0,16.0,18.0, Policy Statement, Appendix B, C, D, E, F, G and Table of Contents with the enclosed sections.  !

Change 10 changes are in bold anditalles with a revision bar in the right margin. The footer of the affected section will include a reference to change 10 j insert the summary of changes document in the front of your manual.

If you have any questions, contact R. Fletcher at X4350 Attachments, .

1. Summary of changes incorporated as part of revision 20, change 10.

Enclosure:

1. Change 10 to the Northeast Utilities Quality Assurance program Topical Report revision 20.

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. l TABLE OF CONTENTS g NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

( I TOPICAL REPORT- MILLSTONE POWER STATION w/

Table of Contents Abstract Policy Statement introduction Quality Assurance Program QAP -1.0 Organization QAP 2.0 Quality Assurance Prcgram l QAP 3.0 Design Centrol 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 i QAP 8.0 identification and Control of Materials, Parts and Components QAP 9.0 Control of Special Processes v- QAP10.0 Inspection ,

QAP11.0 Test Control QAP7.0 Control of Measuring and Testing Equipment QAP;3.0 Handling, Storage, and Shipping QAP14.0 Inspection, Test, and Operating Status l QAP15.0 Nonconforming Materials, Parts, Components, or Services QAP16.0 Corrective Action QAP17.0 Quality Assurance Records QAP18.0 Audits Appendices A Ca tegory I Structures, Systems, and Components B QL alification and Experience Requirements l C Regulatory Guide and ANSI /IEEE Standard Commitments D Glossary of Quality Assurance Terms E Program Exceptions l F Administrative Controls G Technical Specification Position Cross Reference t

QAP Table of Contents Rev.: 20 Change 10 Date: 7/15/99 Page 1 of 1 l

1 POLICY STATEMENT NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

TOPICAL REPORT- MILLSTONE POWER STATION This Northeast Utilities Quality Assurance Program (NUQAP) Topical Report has been i developed to achieve quality assurance in all. activities affecting the safe operation of the l Millstone Nuclear 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, procuremen+, construction, testing, operation, refueling, maintenance, repair, and modificatioh of the Station's nuclear power plants.

i Northeast Utilities procedures which implement this program are described in various manuals. i This NUQAP applies in its entirety to all activities affecting the safety-related functions of ,

structures, systems, and components. Safety-Re%ted structures, systems and components are j functionallyidentified in Appendix A of this NUQAP and are designated Category I by Northeast Utilities. 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. This NUQAP is also applicablein its entirety l to materials, equipment, parts, consumables, and services designated as Category 1. This NUQAP is also applicable to other quality programs including Anticipated Transient Without ,

Scram (ATWS) Quality Assurance which is applicable to MP-1 and MP-2 only (MP-3 commits to Generic Letter 85-06) and Electrical Equipment Qualification (EEQ) as defined by NU commitments. Portions of this NUQAP are also applicable to Fire Protection Quality Assurance (FPQA), Station Blackout Quality Assurance (SBOQA) and Radwaste Quality Assurance ,

(RWQA) which are delineated in applicable program manuals and procedures. Quality J Assurance provisions for primary chemistry laboratory activities are detailed in the Northeast Utilities Nuclear Chemistry Laboratory Quality Assurance Manual.

The development and overall responsibility for this program lies with the President and CEO-NNECO, as delegated by the Chairman, President and Chief Executive Officer of Northeast Utilities. IndividualVice Presidents are responsible for the implementation of their portion of this program. Audits of this program are the responsibilityof the Vice Pres / dent- NuclearOversight and RegulatoryMalts/ Recovery Officer - Nuclear Oversight.

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 President and CEO-NNECO.

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1.0 ORGANIZATION

1.1 INTRODUCTION

This section describes the organizations involved in the operation and technical support of Millstone Nuclear Power Station (MNPS). In addition, this section describes ths responsibilities governed by the Northeast Utilities (NU) Quality Assurance Program (NUQAP). Qualifications for key personnel are found in the unit Technical Specifications and Appendix B,

" Qualification and Experience Requirements."

NOTE in the remainder of QAP 1.0, references are made to station - wide functions that apply to all three units unless indicated otherwise. Where specified, some text appIles specifically to Units 2 and 3, or to Unit 1. In either case, Units 2 and 3 organizations may supply services to, or use services from, the Unit 1 organization, with appropriate controls. Unit 1 is defueled andin a decommissioning mode.

1.2 ORGANIZATION The Chairman, President and Chief Executive Officer (CEO) of NU has ultimate responsibility and overall authority for the NU nuclear program, and is the Chairman of Northeast Nuclear Energy Company (NNECO), the licensed operator of Millstone Units 1, 2 and 3. The Chairman of NNECO has delegated the necessary responsibility and authority for all nucleer operations to the President and CEO-NNECO. In addition, Northeast Utilities Service Company (NUSCO) provides certain support services to NNECO. The Fresident and CEO-NNECO is also the President-Generation Group of NUSCO.

1.3 KEYMANAGEMENTRESPONSIBILITIES AND AUTHORITY 1.3.1 Senior Vice President and CNO-Millstone (SVP & CNO)

The SVP & CNO has been delegated by the President and CEO-NNECO the necessary responsibility and authority for the management and direction of all activities related to the operation of MNPS. The SVP & CNO has overall responsibility for engineering, construction, operation, maintenance, modification and quality assurance including this NUQAP, at MNPS. The following report directly to the SVF & CNO:

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• Vice President (VP)-Nuclear Operations QAP 1.0 Rev.20 Change 10 Date: 7/15/99 Page 1 of 17

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• VP-Engineering Services VP-Site Services VP-Human Services VP-Nuclear Oversight and Regulatory Affairs (NORA) and Recovery Officer - Ntsclear Oversight (RONO) 1.3.2 VP-Nuclear Operations (Units 2 and 3)

VP-Nuclear Operations is responsible for establishing common policies and standards pertaining to the operating units, the safe operation and maintenance of the units, andimplementation of this NUQAP. The VP-Nuclear Operations is responsible for maintaining conopliance with requirements of the Operating License and Technical Specifications as well as applicable federal, state and locallaws, regulations and codes. The following report directly to the VP-Nuclear Operations:

• Statfor, Director (Units 2 and 3)

• Work Mattagement(Units 2 and 3)

Maintenance (Units 2 and 3) 1.3.3 VP-Engineering Services VP-Engineering Services is responsible for providing engineering p services to support the operating units (Units 2 and 3), and Q implementation of this NUQAP. The following report directly to the VP-Engineering Services:

• Design Engineering

• Nuclear Engineering

• Plant Engineering 1.3.4 VP-Site Services VP-Site Services is responsible for site services in support of the station, and implementation of this NUQAP. The following report directly to the VP-Site Services:

• Site Services

• Nuclear Materials and Document Management

• Unit 1 GeneralManager 1.3.5 VP-Human Services The VP-Human Services is responsible for emergency planning and nuclear training, andimplementation of this NUQAP. The followirag report direcdy to the VP-Human Services.

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• Nuclear Training Services

• Emergency Planning \

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O The VP-Human Services is also responsible for the employee 0 concerns program and human services, and for these two responsibilities, the VP-Human Services reports to the President and CEO-NNECO.

1.3.6 VP-Nuclear Oversight and Regulatory Affairs (NORA) and Recovery Officer- Nuclear Oversight (RONO)

, VP-NORA and RONO is a dual position responsible for the effective performance of Nuclear Oversight and Regulatory Affairs functions.

The VP-NORA/RONO acts as advisor to the SVP & CNO and President and CEO-NNECO on items related to nuclear quality and safety at the station. Overall responsibility for the NUQAP has been delegated to the VP-NORA/RONO by the SVP & CNO. These responsibilities include:

• Direction of the quality assurance program

• Development and implementation of policies, plans, requirements, procedures, and audits

• VerlHcation to assure compliance with 10CFR50 Appendix B and other regulatory requirements

• VerlHcation of the implementation of the NUQAP TopicalRepost requirements The following report directly to the VP-NORA/RONO:

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• Director-Nuclear Oversight 1.3.7 Director-Nuclear Oversight The VP-NORA/RONO has delegated to the Director-Nuclear Oversight the necessary authority and responsibility for the following:

• Preparation and issuance of the NUQAP Topical Report

• VeriRcation of the implementation of NUQAP requirements and of compliance with 10CFR50 Appendix B and other regulatory requirements

• Identification of qualityproblems

• Recommendations or solutions to quality problems and veriRcation of the implementation of the solutions

• Independent Safety Engineering and Operating Experience programs Verification is performed through a' planned program of audits, surveillances and inspections by Nuclear Oversight. The Director.

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.

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'e O The Director-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. l In order to implement these responsibilities, the Director-Nuclear Oversight is provided "Stop Work" authority whereby he/she can l 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 approvedprocedure.

1.3.8 Station Director (Units 2 and3) l The Station Director is responsible for operations, nuclear safety, j chemistry, and radiation protection activities. The Station Directoris '

responsible for the safe and efficient operation of the units. During accident situadons, if currently holding an active SRO license on the unit, the Station Director may relieve the Shift Manager of the i responsibility of directing the licensed Control Room operators.  !

The following report to the Station Director:

• Assistant Station Director-Safety (Units 2 and 3)

• Unit Operations (Units 2 and 3)

O Radiation Protection and Waste Services (Units 2

• i and 3) l 1.3.9 Work Management (Units 2 and 3)

The Work Management group is responsible for on-line maintenance, cost and scheduling, and outage activities. .

Responsibilities include the scheduling of surveillances required by Technical Specifications. Unit 1 has a separate group for this function.

1.3.10 Maintenance (Units 2 and 3)

The Maintenance group is responsible for installation, maintenance, alterations, adjustment and calibration, replacement and repair of plant electrical and mechanical equipment, and instruments and controls. Responsibilities include establishing standards and frequency of calibration for instrumentation and ensuring instrumentation and related testing equipment are properly used, inspected and maintained. Unit 1 has a separate group for this function.

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• t 1.3.11 Design Engineering 4 The Design Engineering group is responsible for design engineering functions, supporting activities, and engineering programs. The Unit 1 organization will share responsibility for certain systems shared between Unit 1 and Units 2 or 3.

1.3.12 Nuclear Engineering I

The Nuclear Engineering group is responsible for engineering ,

activities in configuration management, safety analysis, and nuclear  !

fuel. These activities include probabilistic risk assessment, radiological and radwaste engineering, design and configuration controland engineering assurance.

1.3.13 PlantEngineering The Plant Engineering group is responsible for engineering technical support and systems engineering, including reactor and material engineering.

1.3.14 Site Services  !

The Site Services group is responsible for services in support of the O station, including security and fire protection.

1.3.15 Nuclear Materials and Document Management The Nuclear Materials and Document Management group is responsible for nuclear records management and procurement. l Responsibilities include approval and oversight of vendors that l provide quality-related material and services including source and receiptinspection.

1.3.16 Unit 1 General Manager The Unit 1 General Manager is responsible for the safe and efficient decommissioning of Unit 1, including operations, engineering, nuclear safety, radiation protection, maintenance and associated support services. The following report to the Unit 1 General Manager:

• Director-Unit 1 Operations

• Unit 1 Decommicsloning

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l 1.3.16.1 Director-Unit 1 Overstions O The Director-Unit 1 Operations is responsible for the safe ,

and efficient operation of Unit 1 in its decommissioning i mode. The Director-Unit Operations is also responsible for 1 work management, maintenance, health physics, and radiological waste. The Manager-Health Physics fulfills the

" Health Physics Manager" position qualifications required by the Unit 1 Technical Specifications.

1.3.16.2 Unit 1 Decommissionina The Unit 1 Decommissioning group is responsible for planning and executing the decommissioning of Unit 1, including associated engineering. The Unit 1 organization will share responsibility for certain systems shared between Unit 1 and Units 2 or 3.

1.3.16.3 Unit 1 Nuclear Safety and Reaulatory Affairs The Unit 1 Nuclear Safety and Regulatory Affairs group is i responsible for licensing and other activities in support of Unit 1 decommissioning.

1.3.17 Nuclear Training Services The Nuclear Training Services group is responsible for operator and technical training. The operator training group reports directly to the Director-Nuclear Training Services to provide sufHclent organizational freedom and independence from operating pressures as required by the unit Technical SpeclHcations.

1.3.18 EmergencyPlanning The Emergency Planning group 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 plans.

1.3.19 Assistant Station Director-Safety (Units 2 and 3)

The Assistant Station Director-Safety is responsible for the

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corrective actions program, procedures, and the shift technical advisors.

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1.3.20 Unit Operations The Unit Operations groups report to the Station Director (Units 2 and 3) or to the Director - Unit 1 Operations (Unit 1). Each group includes the following key supervisorypositions:

• Manager-Operations

• Assistant Manager-Operations

• Shift Manager (s)

• Unit Supervisor (s) 1.3.20.1 Manaaer-Ocerations and Assistant Manaaer-Ocerations The Manager-Operations provides general supervision for the operation of the respective unit, and coordinates unit operations with maintenance, work management, and other groups. As stipulatedin Technical Specifications or in Appendix B, the Manager-Operations or the Assistant Manager - Operations holds an appropriate license on the Unit (SRO on Units 2 and 3, Certified Fuel Handler on Unit 1). The Manager-Operations assures the safe and efHcient operation of the assigned unit in accordance with applicable licenses, operating instructions and procedures, emergency procedures and safety rules and O regulations. During accident situations, if currently holding an active SRO license on the unit, the Manager.

Operations may relieve the Shift Manager of the responsibility of directing the licensed Control Room operators. The Manager-Operation: delegates the necessary authority and responsibility fcr various duties to the Assistant Manager-Operations.

1.3.20.2 Shift Mannaer The Shift Managers report to the Assidant Manager-

[ Operations and are responsible for the Control Room l

command function. The Shift Manager holds an appropriate license on the unit (SRO on Units 2 and 3, Certified Fuel Handler on Unit 1). 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.

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z During accident situations, unless properly relieved, the Shift Manager remains in the Control Room and directs the )

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activities of the licensed operators. The Shift Manager has direct authority to shut down the respective unit if, in the Shift Manager's opinion, serious abnormal conditions exist. A Unit 3 Shift Manager fulfills the facility staff requirements of the Shift Supervisor for the Unit 3 TechnicalSpecifications.

1.3.20.3 Unit Suoervisor The Unit Supervisor holds an appropriate license on the unit (SRO on Units 2 and 3, Certified Fuel Handler on Unit

1) 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 tiic Control Room or alternate station controllocation.

1.3.20.4 Control Ooerators (Units 2 and Unit 3)

Control Operators hold a Reactor Operator or Senior Reactor Operator license on the unit. The Control l Operators are responsible to perform the following duties: '

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• Start up, operate, and shut down nuclear plant equipment including, but not limited to, reactor, reactor auxiliaries, turbine generator unit and its l auxiliaries as necessary to satisfy system requirements or station conditions

• Test, as scheduled, control room instruments and controls

• Maintain required logs and calculations, observe these logs forindications of faulty operation, and notify the on-duty Unit Supervisor or the Shift Manager of abnormal plant conditions 1.3.20.5 Plant Eauloment Ooerators Plant Equipment Operators are responsible to perform the following duties:

• Start up, operate, inspect, adjust, and shut down all auxiliary and other various plant equipment

• Perform or assist with scheduled operational tests

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1.3.21 Radiation Protection and Waste Services (Units 2 and 3)

Radiation Protection and Waste Services group carries out health physics functions and reports to the Station Director to provide sufficient organizational freedom and independence from operating pressures as required by the unit Technical Specifications. The Manager-Radiation Protection and Waste Services fulfills the

" Health Physics Manager" position qualifications required by the Unit Technical Specifications. Radiation protection services include the following:

• scheduling and conducting radiation surveys including contamination sample coIIection e determining cornamination levels and assigning work restrictions through radiation work permits  !

• maintaining records and reports on radioactive contamination levels e administering the personnel monitoring program and maintaining required records in accordance with federal and ,

state codes Radiation Protection and Waste Services is also responsible for radioactive waste services.

1.4 (UALITY-RELATED RESPONSIBILITIES COMMON TO ALL GEPARTMENTHEADS The head of each department performing quality activities is responsible for:

• Administering those activities within their ;

organization which are required by this NUQAP;

• 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 NUQAP Topical Report; and

• Performing and coordinating quality activities within their department and interfacing with the Nuclear Oversight department.

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Each Individualperforming or verifying activities affecting quality is responsible to conduct those activities in accordance with the requirements of this NUQAP andimplementing procedures. Theze 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 NUSCO/NNECO organizational charts, policy stataments, and writtenJob or functional descriptions.

Vendors may be delegated the execution of quality assurance functions; however, NU shall retain responsibility for this Qual'+v Assurance Program.

1.5 ANNUAL MANAGEMENT QUALITY ASSURANCE REVIEW The SVP & CNO is responsible for the assessment of the scope, status, implementation, and effectiveness of the NUQAP. To meet this responsibility, a team of qualiRed individuals is appointed by the SVP &

CNO to perform an annual Management Quality Assurance Review. The tes:n is made up ofindividuals knowledgeable in quality assurance, quality activities, auditing, management responsibilities, and the NUQAP Topical O Report. This reviewis:

• A systematic evaluation; e pre-planned toward the objective of determining the adequacy of the NUQAP and its compilance with Appendix B to 10 CFR 50 and otherregulatoryrequirements;and

• capable of identifying, communicating, and tracking any required corrective action.

1.6 SPECIFIC NUQAP RESPONSIBILITIES The SVP & CNO resolves all disputes related to the implementation of the NUQAP for which resolution is not achieved at lower levels within the organization.

1.7 SUCCESSION OF RESPONSIBILITY FOR OVERALL PLANT OPERATION (Units 2 and 3)

The succession to responsibility for overall plant instructions or special orders, in the event of absences, incapa&tation ofpersonnel or other emergencies, is as follows for Units 2 and 3:

• Vice President-Nuclear Operations

• Station Director lO QAP 1.0  :

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Licensed Manager-Nuclear Operations or Licensed Assistant Manager-O'

• Operations designated by Vice President-Nuclear Operations Shift Manager (SRO)

• Licensed Unit Supervisor (SRO) 1.8 ORGANIZATION CHARTS NOTE The following organization charts are incorporated by reference in the Millstone Station Emergency Plan. Changes to these organization charts require an effectiveness review in accordance with 10 CFR 50.54 (q).

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2.0 QUALIT/ ASSURANCE PROGRAM 2.1 GENERAL REQUIREMENTS Northeast Utilities (NU) has established a Quality Assurance Program (NUQAP) for the Millstone Power Station which complies with the criteria of 10CFR50, Appendix B, and follows the regulatory documents and their endorsed ANSI /IEEE 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 NU policy  !

with regard to quality assurance for all the Millstone Station nuclear power plants. This NUQAP Topical Report is established to accomplish the required level of quality in activities carried out throughout the life of the Station's nuclear power plants.

This NUQAP applies in its entirety to all activities affecting the safety-related functions of structures, systems and components. Safety-Related , i structures, systems and components are functionally identified in Appendix A of this NUQAP and are designated Category I by Northeast Utilities.

n Applicability of Appendix A to cach FSAR is addressed by existing Nuclear V 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. This NUQAP is also applicable in its entirety to materials, equipment, parts, consumables and services designated Category 1.

This NUQAP applies to other quality programs including Anticipated Transient Without Scram (ATWS) Quality Assurance which is applicable to MP-1 and MP-2 only (MP-3 commits to Generic Letter 85-06) and Electrical Equipment Qualification (EEQ) as defined by NU commitments. Portions of this NUQAP are also applicable to Fire Protection Quality Assurance (FPQA), Station Blackout Quality Assurance (SBOQA) and Radwaste Quality Assurance (RWQA) which are delineated in applicable procedures.

The Materials, Equipment, and Parts List (MEPL) Program provides instructionc to identify structures, systems, components, materials, equipment, parts, consumables, quality software and activities that need to be identified as safety-related or augmented quality.

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QAP-2.0 Rev.: 20 Change 10 Date: 7/15/99 Page 1 of 7

O The requirements of this NUQAP are implemented by Northeast Utilities

.. Service Company (NUSCO), the Northeast Nuclear Energy Company

-(NNECO) which operates Millstone Power Station, and their vendors performing activities affecting quality structures, systems, and components of the Station'c nuclear power plants.

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Procedures define the required indoctrination and training of personnel I 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.,

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

Periodic progam review of the statue and adequacy of this NUQAP is accomplished by Nuclear Oversight audits, surveillances and inspections, by Nuclear Safety Assessment Board (NSAB) reviews, and by the independent review team which performs me annual Management Quality Assurance Review described herein and in QAP 1.0, " Organization", l Section 1.5. Organizations outside NU are required to review the status l and adequacy of that part of this NUQAP for which they have been ,

delegated responsibility. )

2.2 IMPLEMENTATION _

2.2.1 GOALS AND OBJECTIVES The goals of this NUQAP 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 structures, systems, and  ;

components. To meet these goals, the following objectives of this l NUQAP have been defined: j l

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

b. Establish, assign, and document the responsibilities for the conduct of those activities affecting quality' structures, systems, and components; O QAP-2.0 Rev.: 20 Change 10 Date: 7/15/99 Page 2 of 7

c. Establish confidence that (a) quality activities for the Station nuclear power plants. are performed consistent with NU policies and.

(b) quality activities are performed by qualified personnel, and are j verified through a system of audits, surveillances, and inspections of those organizations with quality responsibilities; i

d. Apprise the Senior Vice President and Chief Nuclear Officer -

- Millstone (SVP & CNO) of unresolved problems and trends which '

could have a significant effect on nuclear power plant safety.

2.2.2 PROGRAM DOCUMENTATION This NUQAP defines the NU 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 NUQAP 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 NNECO Procedure.

Revisions to this NUQAP, which reduce commitments previously I accepted by the NRC, are submitted to the NRC for review and approva! prior to implementation.

Revisions which do not reduce previously accepted commitments 1 are periodically submitted to the NRC as required by 10 CFR 50,54 (a)(3) and 10 CFR 50.55 (f)(3).'

Quality procedures are developed by the departments performing quality activities. These procedures are reviewed for concurrence i by .the ' departments which are' responsible for implementing i portions of these procedures and are approved by the initiating department. The Nuclear Oversight Department reviews other department quality procedures for compliance with this NUQAP and concurs with such procedures as described in QAP 5.0, i

" Procedures, Instructions and Drawings". Changes to procedures l are subjected to the same degree of control as that utilized in the preparation of the original document.

Each Vice President and Director le responsible for implementation ] l of this NUQAP.within their organization which includes individual departmental procedure requirements applicable only to their O QAP-2.0 Rev.: 20 Change 10 Date: 7/15/99 Page 3 of 7 i

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• respective . activities. :In addition, they are responsible for the O 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 NUQAP 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 and also as specifically identified in each FSAR addressing Section 3.2.1 of NRC Regulatory Guide 1.70.

For structures, systems and components covered by the ASME .

Code, NUSCO/NNECO 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.

y For structures, systems and components, regulatory commitments and NUSCO/NNECO 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 NUQAP' provides' controls over special processes and skills necessary to attain the required quality, and the need for verification of quality by inspection and test. j The Nuclear Oversight Department and applicable NUSCO/NNECO technical organizations jointly determine and l I

identify the extent' quality assurance controls are applied to quality structures, systems, and components. The quality assurance controls are in conformance with this NUQAP, which complies with the 18 criteria set forth in Appendix B to 10 CFR 50.  ;

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' 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 j responsibilities.

The Nuclear Oversight Department is responsible for: a) the development, coordination, and . administrative control of this NUQAP including coordination of Nuclear Oversight Department procedure review and .. approval; b) assuring issuance of this NUQAP Topical Report as a controlled document (as described in j QAP 6.0, '" Document Control", and; c) the review and concurrence with quality procedures and revisions written by other departments. i Procedute reviews shall be performed in accordance with QAP 5.0,

" Procedures, Instructions, and Drawings".

,. Northeast Utilities (NU) requires that its approved vendors performing . quality activities invoke upon their subvendors, via purchase orders / contracts, 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 O guides and their endorsed ANSI /IEEE standards identified in Appendix C. However, NU retains overall responsibility for the Millstone Power Station Quality Aasurance Program. The specific quality activities performed by l these organizations are specified in the procurement documents.

Nuclear Materials and Document Management is responsible for the review and approval of these vendors' quality assurance programs prior to initiation of contracted activities.

The object of the review is to verify that these vendors have an adequate quality assurance program to meet applicable requirements of 10 CFR 50, Appendix B.

In addition to the initial review, Nuclear Materials and Document Management is responsible for the subsequent performance, as appropriate, of audits, surveillances, and inspections of approved vendor's quality assurance programs to assure continued "

implementation . of quality requirements. Nuclear Materials and Document Management assures that the quarity assurance programs of vendors that perform quality activities are penodically O' OAP-2.0 Rev.: 20 Change 10 Date: 7/15/99 Page 5 of 7 T

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(' reviewed to assure that the. vendors are implementing adequate programs. Evaluation, review, and monitoring of vendor quality programs is conducted in accordance with section OAP 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 NUQAP. These vendors may be contracted to perform quality activities under their approved quality assurance program or directly under the requirements of this NUQAP.

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 thece documents is

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mandatory. Each NUSCO/NNECO Department is responsible for j 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. Additional guidance is established in 4 NUSCO/NNECO 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 certification based upon the  ;

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• . I requirements of the activity. Acceptance criteria are developed to determine if individuals are properly trained and qualifed:

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 i performing quality activities are trained in the principles and {

techniques of the activity being performed. l 2.2.6 MANAGEMENT PARTICIPATlON l b

Millstone Power Station Vice Presidents and Directors are j i responsible for implementing this NUQAP within their organization.

The Director - Nuclear OversQht will assist in development, l coordination, and review of the program.

1 The SVP & C'NO assures that a management review of this l NUQAP is conducted on an annual basis by an independent team O to assess the scope, status, implementation, and effectiveness, and to assure compliante with NRC licensing commitments.

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

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a. Review of selected procedures and documents; l l

b. Verification of the implementation of selected procedural requirements;

c. Review of past audit results and other inspectica/ review results j such as those from previous Management Quality Assurance l l Reviews, the NRC or other departments. l The Management Quality Assurance Review's findings of l deficiencies and recommendations for program improvement ara j forwarded to the SVP & CNO who shall assure appropriate l )

corrective action is taken.

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3.0 DESIGN CONTROL v {

1 g 3.1 QEN,JJJ%LELQl)lREMENTS j This' NUOAP provides measures to assure that the applicable design requirements, such as design bases, regulatory requirements; codes, technical p standards and quality standards, are identified in design documents which are r

reviewed, approved and controlled in accordance with procedures. Such measures include review for suitabi:ity 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 i

Engineering Services and Unit 1 Decommissioning are responsible for l controlling design work, administering design control activitics (including design interface) and design modifications for quality structures. systems, and i components.

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r i The responsibility for adminittration of the design control crogram for the {

Millstone Station r'.uclear power plants :ests with Engineering Swvices and j Unit 1 Decommissioning as it relates to Unit 1 decomtnissioning. The p)

( division of responsibilities and jurisdictional boundaries for design control 1

program implementation are set forth in NUSCO/NNECO procedures.

Although other organizations rnay be delegated the task of establishing and executing the design control program or any part thereof, Engineering Servihes and Unit 1 Decommissioning sha?l retain overali responsibliity for <

the pivgram. The applicable requirerr,ents of this NUQAP shall be imposed on I other organ'zations delegated the task of establishing or executing the design control program in accordance with QAP 4.0, " Procurement Document Control"

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and QAP 7.0, " Control of Purchased Material, Equipment and Services".

The interface controls, both intemal and extemal, for organizations performing )

design work for quality structures, systems, and components are identified and ,

implemented in accordance with procedures. This identification includes those j organizations providing criteria, designs, specifications and technical direction. ;

i Measures are applicd to vanfy the adequacy of design. The extent of design veiification is specified and docurnented by the responsible organization. The individuals performing design vetification should not (1)have immediate  !

supervisory responsibility for +he individual performing the design, (2)have l specified a singular. design approach, (3)have ruled out certain design j considerations, or (4)have established the design inputs for the particular -

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design aspect beigg verified. The independent design verification should not L _ 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 advei ,e 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 'procers are documented and appropriate corrective action is taken.

These design errors and deficiencies are documented in accordance with design' change procedures or as defined in QAP 15.0, " Nonconforming Material, Parts, Components, or Services" and/or QAP 16.0, " Corrective Action",

i 3.2 JMPLEMENTATION Engineering Services and Unit 1 Decommissinning are responsible for the l l design, design review, engineering approval of design changes, design evaluation and design control for the units. Although some portion of the design process may be delegated to other organizations, Engineering Services and Unit 1 Decommissioning organization have the responsibility

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for overall structures, design systems, and final engineering decisions and design c and components.

Nuclear Oversight performs audits, surveillances, and inspections, as apprcpriate, to verify that NUSCO/NNECO departments are effectively complying with this NUQAP and procedural requiremerts for design control.

Additionally, audits, surveillance's 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 enteria for inspections and test. Measures established to control design documents are described in QAP 6.0, " Document Control".

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Program procedures and instructions define the method of i implementing design control measures. These measures require that I 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

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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 3 accuracy and completeness of design drawings and specifications l before release for procurement, fabrication or construction. Design l drawings receive a documented check to verify dimensional accuracy. j i

Design drawings and specifications issued for design changes are  !

reviewed for completeness and accuracy before release to operations, ,

in accordance with design control procedures. l Procedures. describe the provisions to assure that design drawings and specifications are prepared, reviewed and approved in accordance with NUSCO/NNECO 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 ,

l Procedures and instructions governing design change control dunng  ;

modifications to the Station nuclear plants, the control of discrepant or 1 deficient design conditions, and the reporting of unsatisfactory )

performance provide for' the identification of the need for design l 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.

i An independent review and approval of design changes is performed 1 g by the organization that conducted the original design reviews, unless j QAP-3.0 Rev.: 20 Change 10 Date: 7/15/99-Page 3 of 6 l

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/"' such review is performed by NNECO or another qualified organization delegated by NNECO to perform this function.

Proposed design change modifications are submitted to the appropriate Engineering Services and/or Unit 1 Decommissioning l 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 l component, the change shall be reviewed by qualified engineering personnel for technical adequacy. Reviews of the safety evaluations associated with proposed design changes are performed by the Nuclear Safety Assessment Board (NSAB). The sequence of the NSAB review depends upon the determination. of whether an unreviewed safety question is involved (i.e., in accordance with ANSI i N18.7,' if a proposed change in the facility involves an unreviewed l

safety question then the NSAB review is conducted prior to submittal l 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 NSAB is performed to assure that:

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a. the adequacy of the proposed change is cubstantiated; i-

b. unreviewed safety questions are properly idantified and handled l per 10 CFR 50.59;

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.

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

3.2.4 INDEPENDENT DESIGN VERIFICATION Original designs and design modifications are reviewed for adequacy l and the sign-off performed by a person other than the originator of the l design. The originator's 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. re'lew, the next level of management shall fulfill the l- superviso' - responsibilities. Design verification is documented in accordar, with procedures or instructions. Simplified calculations or compute $rograms may be utilized as alternate means of design verificatior,. When design verification is performed by testing, the tests are performed using procedures, which specify the authority and O responsibility of design verification personnel. Responsibility for design adequacy and evaluation is retained by Engineering Services or Unit 1 Decommissioning as appropriate.

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 w%n testing is considered as an attemate method of design verification:

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

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i lNp) 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 l l most adverse conditions as determined by analysis. I Particular emphasis is placed on assuring that designs are in  ;

l conformance with applicable codes, and on selecting the proper  !

design . verification or checking method. Procedures and instructions i 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 L 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.-

l Procedures assure that procedural control is established for design l

) documents that refiect the commitments of the nuclear unit FSAR.

l 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.

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NNECO is responsible for assuring that the design documents )

generated by vendors' for the Station nuclear power plants are l technically correct, approved, and maintained.

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dp 7.0 CONTROL OF PURCHASED MATERIAL. EQUIPMENT AND SERVICES 7.1 GENERAL REQUIREMENTS This NUQAP provides measures for the control of purchased material, equipment, parts and services utilized in quality activities for the Millstone Station nuclear power plants to assure conformance to procurement documents. These measures include provisions for source evaluation and selection, submission of objective evidence by the vendor or subvendors, inspection at the vendor facility, and acceptance inspection and testing of the product upon delivery. Control of quality by vendors and their subvendors is assessed for effectiveness at intervals consistent with the importance, complexity and quantity of the product or service.

7.2 IMPLEMENTATION The evaluation and selection of vendors is performed in accordance with procedures, which specify that procurement source evaluation and selection measures are performed to determine vendor capability and delineate responsibilities of qualified personnel involved in the evaluation and selection p process.

l V 7.2.1 VENDOR QUALIFICATIONS i

Nuclear Materials and Document Management utilizes one or more of the following methods in evaluating the qualifications of a potential vendor:

a. Audits performed by Nuclear Oversight or Nuclear Materials and Document Management and/or coordinated review of potential l vendor utilizing one or more departments (i.e., engineering, site services, operations; procurement);

b. Other utility vendor audits and evaluations;

c. Nuclear Procurement issues Committee (tlUPIC) audits;

d. ASME N, NA, NPT, NV, or MM/ MS Certificate of Authorization;

e. Commercial grade surveys and/or coordinated review of a potential vendor utilizing one or more departments, (i.e.,

engineering, site services, operations; procurement); l

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TN f. Source inspection / surveillance.

V Evaluations assure that vendors providing quality material, equipment, parts and services employ a quality assurance program that conforms to applicable portions of this NUQAP.

Nuclear Materials and Document Management is responsible for  !

assuring that documented evidence of the evaluation and acceptance l of the vendor's quality assurance program is maintained. The i determinatica of vendor approval is based on such factors as prior  ;

performance, quality performance data, audits, commercial grade l surveys, survellances and evaluations of the vendor's quality assurance program.

Vendor Certificates of Conformance are periodically evaluated by i audits,' commercial grade surveys, surveillances, independent inspections and tests, to assure they are valid. This verification of Certificates of Conformance is documented.

7.2.2 SOURCE INSPECTION Nuclear Materials and Document Management is responsible for the performance of source inspections at vendor facilities to assure that

( the requirements of a purchase order / contract have been met.

Source inspections are performed in accordance with procedures which provida for the method of inspection, the extent of documentation required and those responsible for implementing those instructions.

Inspection of items occurs either when verifications of procurement requirements cannot be determined upon receipt or the vendor quality assurance program has not been accepted by Nuclear Materials and Documem Management.

7.2.3 RECEIPT INSPECTION Receipt inspection for procured items is performed by Nuclear Materials and Document Management in accordance with quality procedures which delineate _ requirements and responsibilities necessary to perform inspection functions. The exception to this is Reactor Engineering performing receipt inspection for new fuel assemblies in accordance with quality procedures. Contractual g obligation fulfillment and specified requirements are verified during Q receipt inspections.

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V Receipt inspection of vendor-furnished material, equipment, and parts  ;

is performed to assure that these items and acceptance records are  :

examined in accordance with predetermined inspection instructions l prior to acceptance, installation and operation. Receipt inspections

)- include, as appropriate:

! a. Measures for verifying that the shipment is completa, properly l l identified, undamaged and corresponds with the required documentation; 1

b. Measures for inspection of the item's critical characteristics and review of supporting documentation (e.g., mill test reports, NDE reports) as required by the procurement documents- i

c. Measures for inspection and acceptance of items in accordance with predetermined methods; ,

d. Measures for identifying and controlling acceptable items ,

. including identification of inspection status prior to release from the receiving inspection area;

e. Measures for identifying, segregating and handling nonconforming items;

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f. Measures to ascertain that inspection records or Certificates of Conformance are acceptable prior to release for installation;

g. In cases involving purchased services, the responsible engineer or Department Head shall designate the means by which services may be accepted, and is given the authority to accept services in accordance with methods defined in NUSCO/NNECO procedures.

7.2.4 VENDOR FURNISHED RECORDS Records required to be fumished by the vendor are specified in the procurement documents. Certifications or documentation provided by the vendor which attests to conformance, identifies that all the specific procurement requirements have been met (either by reference to the purchase order or by delineation).

The vendor must fumish the following records as a minimum for nuclear grade purchases:

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a. Documentation that identifies the purchased material. equipment, or parts and the specific procurement r0quirements ;e.g., codes, standards and specifications) which have been met by the items;

b. Documentation that identifies any procurement requimme:ts which have not been met, together with a description of ?.v;?

Nonconformances dispositioned " accept as is" or " repair."

The responsible Nuclear Materials and Document Management anJ/or engineering and other appropriate department personnel shall review for acceptability those documents which pertain to the requirements in the procurement document, in accordance with this NUQAP and applicable procedures.

The department that is contracting onsite quality assurance services shall be responsible for the review and acceptability of vendor personnel / equipment certifications prior to the start of work. The Nuclear Oversight department shall provide oversight of these activities via surveillance, or inspection, as appropriate, to verify compliance with this requirement.

7.2.5 COMMERCIAL DEDICATION NNECO procedures address the measures taken to assure that for commercial grade items, where specific quality assurance controls for nuclear applications cannot be imposed in a practicable manner, that special dedication requirements are established and implemented.

These measures follow the guidance in Regulatory Guide 1.144, paragraph _ C. 3. b (1) and Regulatory Guide 1.123 and applicable paragraphs of Section 10 of ANSI N45.2.13.  ;

These measures include appropriate requirements for special categorization and identification within the procurement document, receiving inspection, and additional controls during the installation and testing process to be performed by Nuclear Materials and Document Management, other NUSCO/NNECO Departments, or other appropriate groups.

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v 12.0 CONTROL OF MEASURING AND TESTING EQUIPMENT 12.1 GENERAL REQUIREMENTS This NUQAP provides measures for the control of measuring and testing equipment (M&TE) used as the basis for acceptance during inspection, testing, and measurement of materials, equipment, and parts affecting quality structures, systems, and components. Periodic calibration and adjustment of M&TE is performed and controlled to assure accuracy is maintained within limits necessary to verify that design and operating condition requirements have been met. Documentation is retained such that all items of M&TE are traceable to their calibration records.

12.2 IMPLEMENTATION 12.2.1 CAllBRATION PROGRAM Procedures delineate the methods and responsibilities for the control, maintenance and calibration of M&TE including portable and temporarily installed instruments, tools, gages, fixtures, reference and transfer standards, and nondestructive test equipment.

Documentation associated with the calibration of all M&TE is maintained in appropriate files and retained as quality records in accordance with the NU Nuclear Records Program. When the information for the control, use, and calibration of M&TE is in electronic form, this information is controlled and protected in accordance with applicable procedures.

The calibration program is implemented in accordance with the requirements defined in NUSCO/NNECO procedures which describe the measures utilized to maintain the calibration of the M&TE. Functional groups are responsible for implementing these procedures which comply with the requirements contained in specifications and drawings. Procedures related to the M&TE calibration program are reviewed and approved by the appropriate on-site review committee or the Station Qualified Reviewer Program, as defined in applicable procedures. Nuclear Materials and Document Management or the appropriate M&TE custodian, as delineated by the purchase order, is responsible for verifying that receipt of calibrated equipment is in conformance with the requirements of procurement documents. Nuclear Materials and Document Management and Nuclear Oversight are responsible for control of calibrated M&TE used during their inspections.

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p Department Heads / Job Supervisors are responsible to assure that M&TE is C/ calibrated, issued, and controlled in accordance with the requirements of applicable procedures.

The Nuclear Oversight Department performs audits, surveillances, and inspections, as appropriate, to verify implementation of the calibration program.

Vendors utilized to perform quality activities for the Station nuclear power plants are responsible for implementing measures for the control of M&TE to l assure the M&TE are properly calibrated, adjusted and maintained at f specified intervals in order to maintain accuracy within required limits. Audits, surveillances, and inspections, are performed, as appropriate, to verify these vendors are effectively complying with their quality assurance program requirements for control of M&TE.

12.2.2 CALIBRATION STANDARDS Measuring and test equipment is calibrated at specified intervals based on the required accuracy, purpose, degree of usage, stability characteristics, and other conditions affecting the measurement. Measuring and test equipment shall be permanently marked or tagged with a unique Identification number and the date calibrated and next calibration date indicated on the M&TE.

O V Procedures describe the measures taken to assure that reference and transfer standards are traceable to nationally recognized standards and that, where national standards do not exist, provisions are established to document the basis for calibration.

Calibration of this equipment should be against standards that have an accuracy of at least four times the required accuracy of the equipment being calibrated. When this is not possible, the standards shall have an accuracy ,

that assures the equipment being calibrated shall be within required tolerance  !

and the basis of acceptance is documented and authorized by the appropriate on-site review committee. In addition, the calibrating l standards shall have greater accuracy than secondary standards being calibrated. Calibrating standards with the same accuracy may be used if they can be shown to be adequate for the requirements and the basis of acceptance is documented.

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12.2.3 "OUT OF TOLERANCE" CONTROL M&TE and reference standards when found out of tolerance are so identified and removed from service. A timely review is conducted to determine the i validity of previous inspection or test results gained through use of the instrument, and of the acceptability of items previously measured or tested.

Where it is determined that use of out of tolerance measuring and test equipment may have resulted in a condition adverse to quality, the condition is promptly identified and corrective action is implemented in accordance with QAP 15, " Nonconforming Materials, Parts, Components or Services" and QAP 16, " Corrective Action" respectively as appropriate.

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U 15.0 NONCONFORMING MATERIALS. PARTS. COMPONENTS OR SERVICES 15.1 GENERAL REQUIREMENTS This NUQAP requires the documentation and control of nonconforming materials, parts, components, or services be performed in accordance with procedures to prevent inadvertent use or installation in Millstone Station nuclear power plant quality structures, systems, or components. These procedures include requirements for identification, documentation, segregation and disposition of nonconforming items; and notification to affected organizations.

15.2 IMPLEMENTATION 15.2.1 PROGRAM Procedures define personnel responsibilities and estsblish various measures for identification, documentation, segregation, review and disposition of nonconforming item reports. The means for reporting nonconforming items are available to all NU and vendor personnel assigned at the Millstone Power Station and other personnel involved with Iq Station quality activities.

V 15.2.2 DOCUMENTATION Documentation of nonconforming items requires identification of the items, description of the nonconformance, disposition of the nonconformance, inspection requirements and signature approval of the disposition.

Tagging systems are utilized to physically identify nonconforming items prior to installation. Nuclear Materials and Document Management l utilizes tags for received materials, parts and components.

l 15.2.3 EVALUATION AND DISPOSITION l

i Evaluations are peiformed to determine the disposition of nonconforming items and services. The evaluation determines whether an item or service is to be used as is, returned to vendor, repaired, reworked, ,

scrapped or salvaged. An engineering evaluation is performed, if l necessary, prior to the resolution of nonconforming conditions. In addition, nonconformances are evaluated for impact on quality structure, system and component operability in accordance with applicable procedures. These evaluations assure that the final condition does not adversely affect safety, operation or maintenance of the item or service.

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p Nonconforming item reports involving deviation from design bases such

'V as "use as is" or " repair" are forwarded to the appropriate engineering organization for. review, and disposition. Applicable information is accumulated and records are maintained.

The need to release /use nonconforming materials, parts or components shall be based on such considerations as:

a. impact on plant safety;

b. Safety of personnel;

c. Suitability of items in the "as is" condition, i.e., probability of eventual satisfactory resolution of the nonconforming condition without repair, rework or replaceinent,

d. Accessibility of items after release;

e. Cost of removal and repair or replacement should items eventually have to be removed, repaired, or replaced;

f. Effect on the orderly progress of work.

Items repaired are verified by inspecting the items as originally inspected or by a documented method which is equivalent to the original inspection method. Items reworked may require inspection to verify conformance to requirements as defined in applicable procedures.

Nuclear Oversight performs audits and surveillances, as apprspriate, to verify that dispositions for reports documenting nonconforming conditions are adequate.

15.2.4 RECURRENCE CONTROL A trend analysis of nonconforming conditions documenting i program / procedural problems is performed in accordance with I procedures. The trend analysis results are periodically reported to upper management, including the senior onsite and offsite nuclear officers and the senior manager responsible for measuring the effectiveness of the quality assurance program, for review and assessment as part of the Station Corrective Action Program reporting as described in QAP 16.0, Corrective Action.

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( 16.0 CORRECTIVE ACTION 16.1 - GENERAt. ildQUIREMENTS -

This NUQAP requires that an effective corrective action program be established to assure that conditions adverse to quality at the Millstone Power Station are promptly identified, corrected, and documented in accordance with procedures. These procedures include measures for reporting to appropriate levels of management and determining the root cause and corrective action to preclude recurrence for conditions evaluated as significant conditions adverse to quality.

16.2 IMPLEMENTATION 16.2.1 PROGRAM Procedures define personnel responsibilities and establish various measures for identification, documentation, review, engineering evaluation, disposition

, and correction of conditions Ldverse to quality. The means to identify conditions adverse to quality are available to all NU and vendor personnel assigned to the Millstone Power Station and other personnel involved with Station quality activities.

L 16.2.2 CORRECTIVE ACTION AND FOLLOW-UP Procedures describe the measures taken to evalu9e if conditions adverse to quality exist and to datermine the need for imme 'iate corrective action or disposition. Vice PrtEdents are responsible fo assuring their assigned l personnel and their vendors working onsite comply with the corrective action program and for assuring that corrective action is adequate and properly implemented in a timely manner within their organization. The Nuclear Oversight Department performs audits and surveillances, as appropriate, to

- verify that NUSCO/NEECO departments are effectively complying with this NUQAP and procedural requirements for the corrective action program and that corrective action is adequate and properly implemented in a timely manner. Audits, surveillances, and inspections, are performed, as appropriate to assure that vendors comply with their corrective action program and that corrective action is adequate.

The Senior Vice President and Chief Nuclear Officer - Millstone has the l i final authority in the event that agreement on the action to be taken is not reached at lower levels of the nuclear organization.

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16.2.3 RECURRENCE CONTROL Procedures identify responsibility and provide direction for determining appropriate significance level based on actual or potential consequences for {

conditions adverse to quality.

{

The significance level determines the need for a root cause determination and for establishing the necessary action to prevent recurrence. In cases of significant conditions adverse to quality, the immediate corrective action, the cause, and recurrence control actions must be documented. Procedures establish the responsibilities and measures taken to accomplish these actions.

An analysis of adverse conditions is pedormed and trends which identify program / procedure problems are periodically reported to upper management, including the senior onsite and offsite nuclear officers and the senior manager responsible for measuring the effectiveness of the quality assurance program for review. Adverse trends concerning specific vendor performance shall be reported to the affected vendor for resolution and recurrence control, as appropriate.

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18.0 AUDITS 18.1 GENERAL REQUIREMENTS This NUQAP requires that a comprehensive system of planned and periodic audits shall be carried out to verify that quality activities for Millstone Station nuclear power plants are ~ performed in compliance with this NUQAP and to determine the effectiveness of the program.

Audits are conducted in accordance- with written procedures or checklists by appropriately trained personnel not having direct responsibilities in the areas being audited.

Audit results are documented and reviewed by management having responsibility in the area audited and the responsible management takes the necessary action to address any audit findings revealed by the audit.

., 18.2 IMPLEMENTATION 18.2.1 PROGRAM P The audit program requires audits of Corporate and Station nuclear power plant quality activities under the osersight of the Nuclear Safety Assessment Board. Audits are performed on activities where the requirements of 10 CFR 50, Appendix B and respective nuclear unit Technical Specifications are being implemented in addition to those activities, audits are performed ,

on areas associated with indoctrination and training programs, interface  ;

control among NNECO and vendors, vendor quality programs and the Nuclear Materials and Docume.,t Management procurement function. Audits are regularly scheduled on the oasis of the status and safety importance of the activities being performed. Regularly scheduled audits are supplemented by audits for one or more of the following conditions:

a. ' When significant changes are made in functional areas of the quality assurance program, such as significant reorganization or procedure revisions; i

b. When it is suspected that the quality of the item is in jeopardy due to deficiencies in the quality assurance program;

c. When a systematic, independent assessment of program effectiveness is considered necessary;  ;

L d. When necessary to verify implementation of required corrective action.

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Schedules for the audit of Corporate, and Station, quality activities are Oi~ originated and maintained by the Nuclear Oversight Department. Schedules for vendor quality assurance activities are maintained by the Nuclear Materials and Document Management and Nuclear Oversight Department, as appropriate.

Audits are performed as specified in procedures by qualified personnel, using an audit plan prepared by the auditing organization. Audits may include evaluation of the work areas, activities, processes, items, and review of documents and records to determine the effectiveness of implementation and conformance to this NUQAP.

Approved vendors utilized to perform quality activities for the Station nuclear l

power plants are responsible for developing and implementing a system of planned and periodic audits to verify compliance with and to determine the effectiveness of all aspects of their quality assurance program. Nuclear I Materials and Document Management is responsible for verifying the acceptability of vendor audit programs. Audits, are performed as appropriate, I to verify that these vendors are effectively complying with their quality assurance requirements.

In addition to the audits, other methods, such as surveillances and inspections are used to assure that quality activities are in compliance with this NUQAP.

18.2.2 REPORTING OF AUDIT RESULTS Audit results are reviewed, approved, and reported in accordance with Nuclear Cversight Department and Nuclear Materials and Document i Management procedures, as applicable. The audit reports are issued _to the appropriate management of the area audited to assure appropriate and/or timely corrective action is taken to address conditions adverse to quality identified by the audit findings. In addition, audit data and reports are accumulated as part of the review for quality trends and assessed to assure I the effectiveness of this NUQAP. j 18.2.3 REVIEW. ACTION. AND FOLLOW-UP OF AUDIT FINDINGS Audit findings that involve conditions adverse to quality are reviewed and investigated by the management having the responsibility for the area  ;

audited. The responsible management is required to take the necessary action to address any conditions adverse to quality identified by the audit and: report the results of such reviews and investigations, take the O QAP-18.0 Rev.: 20 Change 10 Date: 7/15/99 Page:2 of 3

i (U necessary actions to correct problems reported, and report the completion of corrective action within specified tirne frames.

Follow-up of audit findings involving. conditions adverse to quality is performed by the auditing organization as necessary to verify appropriate actions have been taken to resolve audit findings. Items which cannot be resolved by affected management are submitted for resolution to tbs Senior Vice President and Chief Nuclear Officer - Miiistone.

18.2.4 RECORDS / REPORTS OF AUDITS Audit records, reports, and associated documentation are retained in the Station Nuclear Document Services Facility, as specified in applicable procedures.

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/ APPENDIX B NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

TOPICAL REPORT - MILLSTONE POWER STATION QUALIFICATION AND EXPERIENCE REQUIREMENTS I

This appendix consolidates specific qualification and experience requirements for several key positions within the NNECO organization.

Much of this material was relocated from the Unit 3 Final Safety Analysis Report.

Vice President - Nuclear Oversiaht and Reaulatory Affairs /Recoverv Officer -

Nuclear Oversicht 1

The Vice President of Nuclear Oversight ar.d Regulatory Affairs (NORA) and the l Recovery Officer - Nuclear Oversight (RONO) shall satisfy the following requirements:

Graduate of a four-year accredited engineering or science college or university, O plus fifteen (15) or more years of industrial experience including five years in positions of leadership, such as lead engineer, project engineer, Audit team leader, etc. At least two years of this experience should be associated with nuclear Quality Assurance Activities, and at least one year of this experience is in a Quality Assurance Organization. A masters degree in engineering or business management is considered equivalent to two years of experience.

Note: The education and exprience requirements for VP - NORA/RONO should not be l treated as absolute when similar training or an outstanding record provides reasonable assurance that a person can perform the required tasks.

ANSI N18.1 1971 Reauirements As stated in Appendix C, education and experience requirements for Millstone Station personnel are established by ANSI N18.1 as endorsed by Regulatory Guide 1.8 1977, subject to the exceptions in Appendix E. The table below identifies ANSI N18.1 requirements applicable to specific positions at Millstone Units 2 and 3.

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l O i Table B-1  !

l Position Applicable ANSI N18.1 1971 Roquirements Station Director Plant Manager (4.2.1)*

Manager- Chemistry Radiochemistry (4.4.3)

Manager- Radiation Protection and Waste Radiation Protection (4.4.4)

Services See Note 1 Manager- Operations Operations Manager (4.2.2)

See Note 2 Shift Managers Supervisors Requiring AEC Licenses (4.3.1)

Unit Supervisors, Control Operators, Plant Operators (4.5.1)

Equipment Operators Manager-I&C Maintenance Instrumentation & Control (4.4.2)

Director- Maintenance Maintenance Manager (4.2.3)

Mechanics, Electricians, Technicians Repairmen (4.5.3)

(repairmen)

Manager- Unit System Engineering TechnicalManager (4.2.4)

Manager- Plant Support Engineering Manager- Common System Engineering Supervisor- ReactorEngineering Reactor Engineering and Physics (4.4.1)

• Numbers in 0 refer to section numbers in ANSI N18.1-1971.

' Notes:

1. For the position of Manager- Radiation Protection and Waste Services, the qualifications considered as minimum acceptable substitutes for a bachelor's degree equivalent are: a high school diploma or its equivalent and four years of applied menagerial experience at a nuclear facility in the area of radiation protection.

2. If the Unit 3 Manager- Operations does not hold an SRO license for Unit 3, then the Manager- Operations shall have held an SRO license at a pressurized water reactor (PWR), and the Assistant Manager- Operations shall hold an SRO license for Unit 3.

If the Unit 2 Manager- Operations does not hold an SRO license for Unit 2, then the Manager- Operations shall have held an SRO license at 2 PWR, and an individual serving in the capacity of the Assistant Manager - Operations shall hold an SRO for Unit 2.

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APPENDIX C NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

TOPICAL REPORT- MILLSTONE POWER STATION REGULATORY GUIDE AND ANSI /IEEE STANDARD COMMITMENTS NOTE: This 'NUQAP is committed to utilize the guidance obtained from the following regulatory documents and their endorsed standards. Exceptions to these positions are listed in Appendix E of this Topical Report.

Appendix B to 10 CFR, Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

10 CFR 50, Section 50.54, Condition of Licenses.

10 CFR 50, Part 55 - Operator's Licenses and its Appendix A- Requalification Programs for Licensed Operators of Production and Utilization Facilities.

Regulatory Guide 1.8 R - 5/77 - Personnel Selection and Training - Endorses ANSI N18.1 - 1971.

Regulatory Guide 1.28 - 2/79 - Quality Assurance Program Requirements (Design and Construction) Endorses ANSI N45.2-1977.

Regulatory Guide 1.30 - (Safety Guide 30), 8-11 Quality Assurance Requirements for I the Installation, Inspection, and Testing of instrumentation and Electrical Equipment-Endorses ANSI N45.2.4-1972.

Regulatory Guide 1.33- 2/78- Quality Assurance Program Requirements (Operation)-

Endorses ANSI N18.7-1976/ANS3.2.

Regulatory Guide 1.37- Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants, 3-16 Endorses ANSI N45.2.1 1973.

ftcgulatory Guide 1.38- Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of items for Water-Cooled Nuclear Power Plants, 5/77 -

Endorses ANSI N45.2.2 - 1972.

Regulatory Guide 1.39- Housekeeping Requirements for Water-Cooled Nuclear Power Plants, 9/77 - Endorses ANSI N45.2.3-1973.

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p Regulatory Guide 1.58- Qualification of Nuclear Power Plant inspection, Examination, and Testing Personnel, Rev.1,9/80 - Endorses ANSI N45.2.6-1978. i Regulatory Guide 1.64- Quality Assurance Requirements for the Design of Nuclear  !

Power Plants,6/76 - Endorses ANSI N45.2.11-1974.

Regulatory Guide 1.70 "A Guide for the Organization and Content of Safety Analysis Reports" Revision 0, June 30,1966 was utilized for Millstone Power Station Unit No. 2;

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however, certain revised sections of the Unit 2 Final Safety Analysis Report are written l to the Revision 3 format. . Regulatory Guide 1.70 " Standard Format and Content of l Safety Analysis Reports for Nuclear Power Plants - LWR Edition," Revision 3, has been l used in the update process for Millstone Power Station Unit No.1 for format and to the nearest extent practical for content. No new analyses have been performed which would be required by Revision 3. Revision 3, November 1978 is utilized for Millstone Power Station Unit No. 3.

Regulatory Guide 1.88- Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records - 10/76 Endorses ANSI N45.2.9-1974.

Regulatory Guide 1.94 - Quality Assurance Requirements for Installation, inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of O Nuclear Power Plant - 4/76 - Endorses ANSI N45.2.5 - 1974 and Section 6.11 of ANSI N45.2.5-1978.

Regulatory Guide 1.116- Quality Assurance Requirements for Installation, inspection, and Testing Mechanical Equipment and Systems - 5/77 - Endorses ANSI N45.2.8-1975.

Regulatory Guide 1.123 - Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants - 7/77 - Endorses ANSI N45.2.13-1976. i Regulatory Guide.1.144- Auditing of Quality Assurance Programs for Nuclear Power Plants - Rev.1 - 9/80 Endorses ANSI N45.2.12 - 1977.

Regulatory Guide 1.146 - Qur:ilification of Quality Assurance Program Audit Personnel For Nuclear Power Plants - 8/80 Endorses ANSI N45.2.23-1978.

Regulatory Guide 1.152 " Criteria for Digital Computers in Safety Systems of Nuclear Power Plants", January 1996 - Endorses IEEE ANS 7 - 4.3.2 - 1993.

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APPENDIX D NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP) l TOPICAL REPORT- MILLSTONE POWER STATION GLOSSARY OF QUALITY ASSURANCE TERMS Accept As is- (also known as "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 and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.

Acoroved '4ndors - Vendors approved to provide material, equipment, parts or services under their quality assurance program.

As-Built Documents - Documents which accurately describe the condition actually achieved in a system, structure, or component. These documents include: material certification and test data; reports of inspections, examinations, and test results; drawing, specifications, procedures, and instructions; and records of nonconformance and their resolution.

Audit- A formal, documented' activity performed in accordance with written procedures or checklists to verify by evaluation of objective evidence that a quality assurance program has been rO developed, documented, and impicmented in accordance with applicable requirements.

Auamented Quality - Nonsafety-related items for which a design basis or regulatory commitment has been made. The augmented quality items are included within the scope of Quality Assurance Program. These items fall under nuclear indicators such as FPQA (Fire Protection Quality Assurance), RWQA (Radwaste Quality Assurance), ATWS (Anticipated Transient Without Scram) and SBOQA (Station Blackout Quality Assurance).

Calibration - The process by which measuring and test equipment are checked against standards of known higher accuracy and adjusted as necessary to assure their compliance with designated specifications.

Cateaorv i - Designation given to safety-related structures, systems, and components (SSC) of a Northeast Utilities nuclear power plant and material, equipment, parts, consumables, and services applicable to the safety-related functions of these SSCs.

Cateaorv 1 Structures. Systems and Components - Defined in each unit FSAR and functionally described in Appendix A. '

Cleanina - Those actions performed to' maintain an item in accordance with cleanliness requirements.

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's f' Commercial Grade item (CGI) - A commercial grade item per 1CCFR21 is a structure, system, or component, or part thereof that affects its safety function that was not designed and manufactured as a basic component. Commercial grade items do not include items where the design and manufacturing process require in-process inspections and verifications to assure that defects or failures M comply are identified and corrected (i.e., one or more critical characteristics of the item cannov verified).

Commercial Grade Survey - Activities conducted by the purchaser to ascertain and verify that a supplier or manufacturer of commercial grade items, controls the technical and quality characteristics determined to be critical for satisfactory performance of specifically designated commercial grade items, as a method to accept those items for safety-related use.

Condition Adverse to Quality - Failures, malfunctions, deficiencies, deviations, defective materials and equipment, abnormal occurrences and nonconformances.

Contractor - Any organization under contract for fumishing items or services.

Corrective Action - Action taken to correct an identified condition adverse to quality.

Deficiencies - Departures from specified requirements.

Department - The use of the word " Department" throughout this NUQAP can refer to any portion of the NUSCO/NNECO organization (i.e., Group, Division, Department, Branch, Section, or Unit, as applicable). I Desian - The technical and management process which leads to and includes the issuance of j design output documents such as drawings, specifications, and other documents defining I technical requirements of structures, systems, and components.

Desian Chanaes - Changes in drawings and specifications that define the design of structures, systems, and components of nuclear power plants.

Desian Documents - The drawing, calculation, specification, or other document (s) that define the technical requirements of structures, systems, or componer .s.

Enaineerina Service Oraanization - Organizations that provide services such as analysis, computer software, testing, and inspection.

Group - The use of the word " group"In Section 1.0 of this NUQAP refers to a portion of the NUSCO/NNECO organization (i.e., Department, Unit, Branch, as applicable).

Handlina - An act of physically moving an item by hand or by mechanical machinery, but not including transport modes.

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.O identification - A means by which material, equipment and parts can be traced to their associated Q documentation through the use of heat numbers, lot numbers, part numbers, serial numbers, or other appropriate means.

4 Item - Any level of unit assembly, including structures, systems, subsystems, subassembly, component, part, or material.

l Insoection - A phase of quality control which, by means of examination, observation, or  !

measurement, determines the conformance of meterial, supplies, components, parts, appurtenances, systems, processes, structures, or services to predetermined quality requirements. ]

Insoection Status - Identification of material, equipment, and parts that have completed inspection, j either acceptable or unacceptable. i Licensino Basis - The set of requirements that includes the applicable NRC regulations, plant -

specific NRC requirements, plant - specific design basis and regulatory commitments that are docketed and in effect.

Life Records - Those quality documents that are maintained for the lifetime of an in-service nuclear power plant (the duration of the operating license) or for the life of the particular component or part. Life records are those which would be of significant value in meeting one or more of the following criteria:

(1) demonstrating capability for safe operation.

(2) maintaining, reworking, repairing, replacing or modifying the item.

.(3) determining the cause of an accident or malfunction of an item.

(4). ~ providing required base line data for in-service inspection.

Material Reauest - A formal electronic request for the purchase of material, equipment, parts and/or services.

Measurina and Test Eauioment - Those instruments, gages, tools, fixtures, reference and transfer standards, nondestructive test equipment, and measuring devices used during inspection and testing to determine that the measuring and test parameters comply with appropriate requirements in specifications and drawings.

Nonconformance - A deficiency in characteristic documentation or procedure which renders the quality of an item unacceptable orindeterminate.

Non-Life Records - Those quality documents that are maintained for a specific period of time other than the lifetime of the in-service nuclear power plant or the particular component or part.

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i Northeast Utilities (NU)- A public utility holding company which owns Northeast Utilities Service Company (NUSCO) and the Northeast Nuclear Energy Company (NNECO).

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' Northeast Nuclear Enerav Comoany (NNECO) - The Northeast Utilities Power Operating ,

Company responsible for the operation of the Millstone Station nuclear power plants. )

i Northeast Utilities Service Company (NUSCO) - A wholly owned subsidiary of Northeast Utilities that provides support engineering, purchasing, and quality assurance services for the Millstone Station nuclear power plants.

Northeast Utilities Quality Assurance Proaram (NUQAP) - Millstone Power Station - Consist of this NUQAP Topical Report, Nuclear Oversight Department procedures and other NUSCO/NNECO Group / Division / Department / Branch /Section/ Unit quality procedures.

Nuclear Document Services - The organization responsible for establishing the Corporate Nuclear ,

Plant Records Program which is implemented at each Nuclear Document Services Facility. I Nuclear Grade - The procurement classification applied to all materials and services intended for items listed as Category I (CAT I) in the MEPL These may require validating documentation such l as Certificate of Material Test Report, Certificate of Conformance, Certificate of Compliance, {

personnel qua'ifications, etc., - as specified by codes or standards, and have been  !

designed / qualified for a nuclear application. Nuclear Grade items are manufactured / qualified {'

under a 10CFR50, Appendix B program with the vendor responsible for 10CFR21. The vendor should be an " Approved Vendor".

Nuclear Document Services Facilities (NDSF) - A facility which has been established for the

- purpose of handling nuclear power plant records in accordance with the Nuclear Records Program.

Obiective Evidence-- Any statement of fact, information, or record, either quantitative or

, - qualitative, certaining to the quality of an item or service based on observation, measurements, or tests which can be verified.

Preservation - Those actions performed to maintain an item in its original and usable condition.

Procedures and Instructions - Documents that specify how an activity is to be performed. They may include methods to be employed; material, equipment, or parts to be used; and a sequence of operations.

l Procurement Documents . Purchase requisitions / material requests, purchase orders, contracts, li . drawings, specific.tlOne or instructions used to define requ.rements for purchase.

Product Acceptance Test- Activities conducted as part of the receiving or source inspection o process to verify acceptability of one or more critical characteristics of the item being inspected.

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t- QAP - Appendix D

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t' S Purchased Material. Eauipment. and Parts fMEP)- Items procured for installation in the Millstone  !

(,) Station nuclear power plants quality structures, systems, and components, and items procured as spare MEP for potential installation in those structures, systems, and components.

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Purchased Services,- Services provided by vendor when requested under a QA Material Request j l and parformed under a quality assurance program other than this NUQAP. (Synonymous with

" Services" and " Quality Services" in this NUQAP)

Quality Activities- All activities affecting the safety functions of structures, systems, and components; these activities include designing, purchasing, fabricatina, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, inaintaining, repairing, l refueling, and modifying. Quality activities also include those activities associated with ,

Augmented Quality (including Radwaste Packaging and Shipping) and other regulated programs  !

to which this NUQAP is applicable.

Quality Assurance Records- Any record pertaining to the quality of mateiial, equipment, parts, processes, or operations relating to structures, systems, and components which are founded on observations, measurements, or tests which can be fully checked or verified. Suen statements may be recorded on a written or preprinted document or tag. The statements are authorized with I a signature or stamp identifiable to the person making the statement of fact. l n

Quality Structures. Systems and Components - Structures, systems, and components (SSC) ,

including Safety-Related SSCs, Augmented Quality items, and items under other regulated '

O programs to which this NUQAP is applicable. '

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Quality Procedures- Those Nuclear Oversight Department and other department procedures which implement the requirements of this NUQAP.

Repair - A disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose which are modified by the use of additional operations and/or processes so that they are suitable for their intended purpose but may not meet all specified requirements.

Reportable item - An event or condition that could affect nuclear plant safety and must be reported to the NRC in accordance with regulatory requirements such as,10CFR50.72, 10CFR50.73, or 10CFR50.9(b).

Pesponsible Enaineer- A NNECO employee assigned the responsibility to coordinate the engineering activities addressed in NUQAP. The responsible engineer may be designated as the project engineer.

Retest- A test conducted prior to operation following installation inspections of work associated with maintenance and refueling to verify that structures, systems, and components will function satisfactorily when in operation. A retest may : iso be performed when original test results are invalidated.

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QAP - Appendix D Rev.: 20, Change 10 Date:7/15/99 Page 5 of 7

Retum to Vendor - A disposition applied to nonconforming material, equipment, and parts that are d(N unsuitab!e for their intended purpose but which are feasible to repair or re .ork at a vendor's facility. l I

Rework- A disposition applied to nonconforming material, equipment, and parts tha' are unsuitable for their intended purpose due to incomplete operations or variations from original engineering requirements but which are modified through the use of additional operations or processes to meet all specified requirements.

Safety-Related Structures. Systems and Components- Those structures, systems and components that are relied on to remain functional during and following design basis (postulated) events 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; l

and '

3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the applicable guideline exposures set l forth in 10CFR50.34(a)(1) or 10CFR100.11 as applicable.

l Sionificant Condition Adverse to Quality - A condition adverse to quality involving actual or potential consequences that have a serious impact on public or personnel health and safety or l  !

plant operations, and requiring a root cause evaluation to determine corrective action to prevent  !

p recurrence.

C Special Processes - Processes for which the desired level of quality can only be assured through the use of additional process controls, and where control through direct inspection alone is inadequate, impossible, or disadvantageous. These processes are performed under controlled conditions in accordance with special requirements utilizing qualified procedures, equipment, and personnel. Special processes may include, but are not limited to welding, brazing, soldering, cleaning, heat tresting, and nondestructive testing.

Station Blackout - The complete loss of altemating current electric power to the essential and non-essential switchgear buses in a nuclear power plant as defined in 10CFR50.2. It involves the loss of offsite power concurrent with turbine trip and failure of the onsite emergency ac power system, but not the loss of available ac power to buses fed by Station batteries through inverters or the loss of power from attemate ac sources.

Storaae - The act of holding an item at the site in an area other than its permanent location in a plant.

Surveillance- A documented record of the observation of work operations performed at the Millstone Power Station or vendor's site to assure compliance with applicable codes, standards, specifications, procedures, drawings, and procurement documents. Surveillance may be performed with a prepared checklist.

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QAP - Appendix D Rev.: 20, Change 10 Date:7/15/99 Page 6 of 7

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A Test and Ooeratino Status -Identification of material, equipment, and parts that are ready for test V or operation, or an existing stage cf a test operation.

Tentina- The determination or verification of the capability of an item to meet specified requirements t.y subjecting the item to a set of physical, chemical, environmental, or operating conditions.

Vendors - Organizations that provide material, equipment, parts, computer software, or services.

This includes contractors, engineering service organizations, and consultants. (Synonymous with

" Supplier" in this NUQAP)

Work Procedures and Work Documents - Procedures, instructions, and documents used to control and document maintenance and modification work performed on Millstone Station nuclear plant structures, systems, and components.

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QAP - Appendix D Rev.: 20, Change 10 Date.7/15/99 Page 7 of 7

4 A APPENDIX E V i NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

TOPICAL REPORT- MILLSTONE POWER STATION <

I PROGRAM EXCEPTIONS j l

1. ANSI N45.2.9. states in part, " structure, doors, frames, and hardware ei,ould be l Class A fire-related with a recommended four-hour minimum rating." '!ba three record storage vauke at NNECO have a two-hour rating.

{

i NNECO's vaults are used for storage of documentation that is unsuitable for l filming or awaiting filming.

{

l A records organization exists along with written procedures addressing the control l' of quality assurance records.

2. ANSI N18.7-1976. paragraph 4.3.2.3 " Quorum" states in part: "A quorum for formal meetings of the (Independent Review) Committee held under the provisions of 4.3.2.2 shall consist of not less than a majority of the principais, or duly appointed alternates..."

A quorum of the Nuclear Safety Assessment Board shall consist of the Chairman or Vice Chairman and at least enough members to constitute a majority of the assigned members. No more than a minority of the quorum shall have line responsibility for operation of one of Northeast Utilities' nuclear units. No more than two attemates shall be appointed voting status at any meeting in fulfillment of the quorum requirements.

3. ANSI N45.2.9-1974. paragraph 1.4, definition of " Quality Assurance Records" states in part: "For the purposes of this standard, a document is considered a quality assurance record when the document has been completed!

Northeast Utilities has developed the following altemative definition to provide  ;

puidance during the interim period from the time a document is completed until it is transmitted to the Nuclear Document Services Facility:

"A record is considered a wo*,ing document until it is transmitted to the Nuclear Document Services Facility (NDSF) at which time it is designated as a Quality Assurance Record. The following maximum time limits are established for the transmittal of working documents to the NDSF:

O QAP - Appendix E Rev.: 20, Change 10 Date: 7/15/99 Page 1 of 5 b

w ,

O' Operations Documents - Documentation generated during plant operations may be maintained, as needed, by operating plant departments, for up to one year.

New Construction or Betterment Documents- Documents which evolve during new construction or betterment projects shall be transmitted to NDSF within 90 days of completica of a new construction project or turnover of a betterment project or plant operations.

Procurement Documents - Inspection / Surveillance / Audit . Reports generated during vendor oversight activities which are used to maintain vendor status for current and future procurements may be maintained, as needed, by Nuclear Materials and Document Management for up to three years.

All Other Workino Documents- All other working documents shall be transmitted to NDSF within 6 months of their receipt or completion."

The requirements of ANSI N45.2.9-1974 do not apply.- to these " working documents" based on paragraph 1.1 of the ANSI standard which states:

1 "It (ANSI N45.2.9) is not intended to cover the preparation of the records nor to include working documents not yet designated as Quality Assurance O . Records."

4. Reoulatorv Guide 1.64 - 6/76. the Regulatory position states, in part, "It should not be construed that such verification constitutes the required independent design verification." Northeast Utilities has developed the following altemative to allow for adequate independent design verification:

This review may be performed by the originator's Supervisor, only if the Supervisor:

Did not specify a singular design approach; Did not establish the design inputs or did not rule out certain Design considerations;

~

ls 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 Supervisor's responsibilities. j l

O QAP - Appendix E

)

Rev.: 20, Change 10 -

Date: 7/15/99 Page 2 of 5 i

i 5.

']

b ANSI N45.2.13 - 1976, paragraph 10.3.4, states in part, " Post-Installation Test requirements and acceptance documentation (should) shall be mutually established by the purchaser and supplier." Involvement by the supplier in establishing Post-Installation Test requirements and acceptance documentation is requested only when it is deemed necessary and proper by the responsible enginwring organization.

Northeast Utilities no longer has any nuclear plants under construction. As a result, most procurements are made for spare parts from suppliers who are not the original equipment manufacturer. In these cases, the supplier may have little or no understanding or knowledge of either the operation of the system the component is to be installed in, or applicable Post-Installation Test requirements and acceptance documentation. As such, Northeast Utilities assumes responsibility for establishing Post installation Test requirements and acceptance documentation.

6. ANSI N45.2.2-1972, paragraph 1.2, states in part that, 'The requirements of this standard apply to the work of any individual or organization that participates in the packaging, shipping, receiving, storage, and hand.9ng of items to be incorporated into nuclear power plants."

Since a portion of Northeast Utilities procurement activities involve commercial suppliers which do not fully comply with the requirements of ANSI N45.2.2, the O Northeast Nuclear Energy Company Nuclear Materials and Document Management organization verifies through source inspections, receipt inspection, ,

and/or survey activities that the quality of the materiais, items, components or l equipment is preserved by those suppliers to the extent that packaging, shipping, storage and handling methods are employed which are commensurate with the '

nature of the product.

7. ANSI N18.1-1971, paragraph 4.2.2, states in part 'The Operations Manager shall hold a Senior Reactor Operator's license". NU has developed an attemative to this requirement which has been accepted by the NRC via amendment 132 for the 4 Malstone Power Station Unit No. 3 license which allows that::

If the Operations Manager does not hold a Senior Reactor Operator license for Millstone Unit No. 3, then the Operations Manager shall have held a Senior Reactor Operator license at a pressurized water reactor, and the Assistant Operations Manager shall hold a Senior Reactor Operator license for Millstone Unit No. 3.

.8. ANSI N18.1-1971. paragraph 4.2.2, states in part "The Operations Manager shall hold a Senior Reactor Operator's license". NU has developed an attemative to this O CAP - Appendix E Rev.: 20, Change 10 Date: 7/15/99 Page 3 of 5

O requirement which has been accepted by the NRC via amendment 190 for the Midstone Power Station Unit No. 2 license which allows that:

If the Operations Manager does not hold a Senior Reactor Operator license for Millstone Unit No. 2, then the Operations Manager shall have held a Senior i Reactor Operator license at a pressurized water reactor, and an individual serving in the capacity of the Assistant Operations Manager shall hold a Senior Reactor Operator license for Millstone Unit No. 2.

9. Reaulatorv Guide 1.33 - 2/78. regarding audits, states in part:

(a) "The results of actions taken to correct deficiencies...at least once per 6 months."

l (b) " .. technical specifications and applicable license conditions - at least once per 12 months."

l (c) "The performance, training, and qualifications of the facility staff - at least once  !

per 12 months."

NU has developed an attemative which modifies these Audit frequencies to at least once per 24 months. This altemative has previously been accepted by the NRC via license amendments 79,184, and 104 for MP1, MP2, and MP3, O respectively.

10. Deleted l l

11. ANSI N45.2.13-1976. paragraph 10.3.5., states in part, "in certain cases involving procurement of services only, such as third party inspection; engineering and consulting services, and installation, repair, overhaul or maintenance work; the Purchaser may accept the service by any or all of the following methods:

(a) Technical verification of the data produced (b) Surveillance and/or audit of the activity (c) Review of the objective evidence for conformance to the procurement document requirements such as certifications, stress reports, etc."

In order to maintain the independence requirement of the NRC's August 14,1996 Order, NNECO will not perform an acceptance review of the work produced by the vendors contracted to conduct the independent Corrective Action Verification Program. This work will be performed in accordance with the vendor's own approved,10 CFR 50 Appendix B Quality Assurance Program.

O QAP - Appendix E Rev.: 20, Change 10 Date: 7/15/99 Page 4 of 5

,. : , ]

12. Deleted.

13. Reaulatorv Guide 1.70 Revision 3. November 19~/8 Section 17.1.2.4 states in part:

"The PSAR should include a listing of OA program procedures or instructions that will be used to implement the QA program for each major activity such as design, procurement, construction, etc. The procedure list should identify which criteria of Appendix B to 10 CFR 50 are implemented by each procedure".

NU has developed an ahemative to this requirement where procedure indices are maintained which identify the procedures that implement the Quality Assurance Program for Millstone Power Station and which, by title and originating organization, indicate the Appendix B to 10 CFR 50 criterion being implemented.

l O

G QAP- Appendix E Rev.: 20, Change 10 Date: 7/15/99 Page 5 of 5 l

L APPENDIX F NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

TOPICAL REPORT - MILLSTONE POWER STATION ADMINISTRATIVE CONTROLS NOTE:

1. " Specification" numbers refer to the unit specific Technical Specification.

2. Unit specific titles are given in [ ] for generic titles used in Technical Specifications.

INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)- Unit 3 Only Function

)

The ISEG shall include, as part of its function, examination of unit operating characteristics, NRC issuances, industry advisories, Licensee Event .

Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to appropriate station / corporation management.

Composition The ISEG shall be composed of at least four full-time personnel located on site to perform the functions described above for Millstone Unit 3. Each person shall have either:

(1) A bachelor's degree in engineering or related science and at least 2  ;

years of professional level experience in his field, at least 1 year of which experience shall be in the nuclear field, or, (2) At least 10 years of professional level experience in his field, at least 5  ;

years of which experience shall be in the nuclear field.

A minimum of 50% of these personnel shall have the qualifications specified in (1) above.

O QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 1 of 21

L Responsibilities The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

• that these activities are performed .

correctly and that humari errors are reduced as much as practical. I Records Records of activities performed by the ISEG shall be prepared and maintained, and quarterly reports of completed safety evaluations will be made to the Vice President-Nuclear Oversight.

• Not responsible for sign-off function 1

i REVIEW AND AUDIT -

Plant Operation Review Committee (PORC) - Unit 1 Only l Function The PORC shall function to advise the demnated manager [ Director - Unit 1 l )

g Operations) on all matters related to nuclear safety. l

\ l Composition j The PORC shall be composed of nine to eleven members. Members shall l collectively have experience and expertise in the following areas:

Plant Operations Engineering Reactor Engineering Maintenance Instrumentation and Controls Health Physics .

Chemistry Work Planning Quality Assurance l The minimum qualifications of PORC members shall be that all members have an  ;

. academic degree in an engineering or physical science field, or hold a 1 management position, and have a minimum of five years technical experience in  ;

their respective field of expertise. The members of PORC shall be appointed in writing by the. designated manager (Director - Unit 1 Operations]. The l

~

QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 2 of 21

Chairperson and alternate Chairperson of the PORC shall be drawn from the o PORC members and be appointed in writing by the designated manager [ Director Ci - Unit 1 Operations).

l Alternates Alternate members shall be appointed in writing by the PORC Chairperson to ,

serve on a temporary basis; however, no more than two altemates shall participate 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 Chairperson.

Quorum A quorum of the PORC shall consist of the Chairperson, or Vice Chairperson, and four members including attemates.

Responsibilities The PORC shall be responsible for:

O a. Review of 1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, 2) all programs, except common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto as determined by the designated manager [ Director - Unit 1 l Operations) to affect nuclear safety. Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.

b. Review of all proposed tests and experiments that affect nuclear safety, s

c. Review of all proposed changes to Sections 1.0 - 5.0 of the Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

O V QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 3 of 21

o

e. Investigation of all violations of the Technical Specifications and q preparation and forwarding of a report covering evaluation and V recommendations to prevent recurrence to the designated officer

[ Senior Vice President and CNO - Millstone) and to the Chairperson of the Nuclear Safety Assessment Board.

f. Review of all REPORTABLE EVENTS.

g. Review of facility operations to detect potential safety hazards.

h. Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.

i. Render determinations in writing if any item considered under (a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.

j. Review of the unit-specific Fire Protection Program and implementing procedure.

Authority O The PORC shall:

a. Recommend to the designated manager [ Director - Unit 1 Operations] l written approval or disapproval of items considered under Responsibilities (a) through (d) above.

1

b. Provide immediate written notification to the designated officer [ Senior Vice President and CNO - Millstone) and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the designated manager [ Director - Unit 1 Operations];

however, the designated manager [ Director - Unit 1 Operations] shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

O QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 4 of 21

• 1

. j Records i

The PORC shall maintain written minutes of each meeting and copies shall be provided to the designated officer [ Senior Vice President and CNO - Millstone]

and the Chairperson of the Nuclear Safety Assessment Board.

Plant Operations Review Committee (PORC)- Unit 2 Only Function 4 The PORC shall function to advise the designated manager (Station Director] on all matters related to nuclear safety.

Composition The PORC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas: i Plant Operations Engineering Reactor Engineering 1 Maintenance Instrumentation and Controls 4 Health Physics Chemistry Work Planning Quality Assurance The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The members of PORC shall be appointed in writing by the designated manager [ Station Director]. The Chairperson and l attemate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the designated manager [ Station Director]. l Attemates Altemate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.

O QAP - Appendix F REV.: 20, Change 10 DATE: 7/1C/99 PAGE: 5 of 21

Meeting Frequency The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.

Quorum 1

i A qur., rum of the PORC shall consist of the Chairperson, or Vice j

' Chairperson, and four members including attemates.

j 1

Responsibilities The PORC shall be responsible for;

a. Review of 1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, 2) all programs, except common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto as determined by the designated manager [ Station Director] l to affect nuclear safety. Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.

b. Review of a!! proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Sections 1.0 - 5.0 of the Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications and ,

preparation and forwarr'Ag of a report covering evaluation and  !

recommendations to prevent recurrence to the designated officer l

[ Senior Vice Preside.it and CNO - Millstone) and to the Chairperson of the Nuclear Safety Assessment Board.

f. Review of all REPORTABLE EVENTS. ,

g. Review of facility operations to detect potential safety hazards.

O QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 6 of 21

f 1 ,

h. Performance of special reviews and investigations and reports thereon  ;

c s as requested by the Chairperson of the Nuclear Safety Assessment l lC Board.

i. Render determinations in writing if any item considered under (a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR60.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.  !

j. Review of the fire protection program and implementing procedure.

Authority l

The PORC shall:

a. Recommend to the designated manager [ Station Director] written l approval or disapproval of items considered under Responsibilities (a) through (d) above.

b. Provide immediate written notification to the designated officer [ Senior Vice President and CNO - Millstona] and the Chairperson of the l Nuclear Safety Assessment Board of disagreement between the s PORC and the designated manager (Station Director): however, the t designated manager [ Station Director) shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

Records The PORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CNO- Millstone and Chairperson of the Nuclear Safety Assessr:. ant Board.

Plant Operations Review Committee (PORC) - Unit 3 Only Function The PORC shall function to advise the designated manager ,' Station Director] on all matters related to nuclear safety.

C'

\h QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 7 of 21

Ei ,

i l

Composition The PORC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas:

Plant Operations Engineering Reactor Engineering Maintenance Instrumentation and Controls l Health Physics Chemistry Work Planning Quality Assurance  !

l The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of exrertise. The members of PORC shall bt appointed in writing by the designated manager (Station Director). l The Chairperson and attemate Chairperson of the PORC shall be dcawn from the PORC members and be appointed in writing by the designated manager (Station Director}. l O' Altemates All alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two attemates shall participate as voting members in PORC activities at any one time.

Meeting Frequency The PORC shcil meet at least once per calenua: month and as convened by the PORC Chairperson.

Quorum The quorum of the PORC shall consist of the Chairperson or Vice Chairperson and four members including alternates.

I I

QAP - Appendix F REV.: 20, Change 10 l DATE: 7/15/99 l PAGE: 8 of 21 l

r i4 1* .

Responsibilities O)

(J The PORC shall be responsible for:

a. Review of: (1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, 2) all programs, except common site programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures, programs or changes thereto as determined by the designated manager (Station Director] to l affect nuclear safety. Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.

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

c. Review of all proposed changes to Sections 1.0-5.0 of the Technical Specifications;

d. Review of all proposed changes or modrfications to plant systems or equipment that affect nuclear safety;

e. Investigation of all violations of the Technical q

'v Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the designated officer (Senior Vice President and CNO - Millstone] and to the Chairperson of the Nuclear Safety Assessment Board;

f. Review of all REPORTABLE EVENTS;

g. Review of facility operations to detect potential safety hazards;

h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.

i. Render determinations in writing if any item considered under (a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an ,

unreviewed safety question, or requires a significant j hazards consideration determination.

J. Review of Unit Turbine Overspeed Protection Maintenance and Testing Program and revision thereto.

/7  ;

QAP. Appendix F 1 REV.: 20, Change 10  ;

DATE: 7/15/99 PAGE; 9 of 21 I

I,

k. Review of the Fire Protection Program and implementing procedures.

Authority The PORC shall:

a. Recommeno to the designated manager (Station Director) l written approval or disapproval of items considered under Responsibilities a. through d, above; and

b. Provide written notification to the designated officer [ Senior Vice President and CNO - Millstone) and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the designated manager [ Station Director]; however, the designated manager [ Station Directorj shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

Records The PORC shall maintain written minutes of each meeting and copies shall 3

be provided to the designated officer (Senior Vice President and CNO -

Millstone) and the Chairperson of the Nuclear Safety Assessment Board.

Site Operations Review Committee (SORC)

Function The SORC shall function to advise the desigrated officer [ Senior Vice President and CNO - Millstone) on all matters related to nuclear safety of the entire Millstone Station Site.

Composition The SORC shall be composed of the:

Chairperson: Designated Officer [ Senior Vice President and CNO Millstone)

., Member: Unit 1 Designated Manager [ Director - Unit 1 Operations]

.. Member: Unit 2 Designated Manager [See note below)

Member: Unit 3 Designated Manager [See note below)

Member. Designated Manager, Nuclear Services [Afanager-Radiation Protection and Weste Services)

Member: Designated Manager, General Services [ Director - Site Services)

. Member: Designated Member of Unit 1 PORC [ Designated Member of Unit i PORC)

O QAP- Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 10 of 21

Member: Designated Member of Unit 2 PORC [ Designated Member of Unit 2 PORC]

Member: Designated Member of Unit 3 PORC [ Designated Member of Unit 3 PORC]

Member: Designated Member of Nuclear Oversight [ Designated Member of Nuclear Oversight]

NOTE: The positions of " Unit 2 Designated Manager" and " Unit 3 Designated Manager" shall be filled by any two of the following: Station Director, Assistant Station Director- Safety, Manager. Operations (Millstone 2), Manager - Operations (Unit 3).

The senior designated Unit manager [ senior individual among the Unit 1 Designated Manager, Unit 2 Designated Manager, and Unit 3 Designated Manager]in attendance shall be the Vice-Chairperson.

Alternates:

Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in SORC activities at one time.

Meeting Frequency k The SORC shall meet at least once per six months and as convened by the SORC Chairperson.

Quorum A quorum of the SORC shall consist of the Chairperson or Vice Chairperson and five members including alternates.

Responsibilities The SORC shall be responsible for:

a. Review of 1) all common site procedures required by Specification 6.8 and changes thereto, 2) all common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto as determined by the designated officer [ Senior Vice President and CNO - Millstone] to affect site nuclear safety. Common site programs and procedures required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require SORC review. l O QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 11 of 21 1

i  !

• . l

b. Review of all proposed changes to Section 6.0 " Administrative O Controls" of the Technical Specifications.

V) i

c. Performance of special reviews and investigations and reports as f requested by the Chairperson of the Nuclear Safety Assessment '

Board,

d. Not used.

e. Not used.

4

f. Review of all common site proposed tests and experiments that affect nuclear safety.

g. Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety. l

h. Render determinations in writing or meeting minutes if any item considered under (a) through (g) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety qt.astion or requires a significant hazards consideration determination.

i. Review of the common site fire protection program and implementing procedures.

q Q Authority The SORC shall:

a. Recommend to the designated officer [ Senior Vi:.. President and CNO

- Millstone) written approval or disapproval in meeting minutes of items considered under Responsibilities (a) through (g) above.

b. Provide immediate written notification or meeting minutes to the designated senior officer [ President and Chief Executive Officer (CEO)] and the Chairperson of the Nuclear Safety Assessment Board of disagreement between iLe SORC and the designated officer [ Senior Vice President and CNO - Millstone]; however, the designated senior officer [ Senior Vice President and CNO- Millstone] sb 11 have respo'sibility n for resolution of such disagreements pursuant to Specification 6.1.1.

Records The SORC shall maintain written minutes of each meeting and copies shall be provided to the designated officer [ Senior Vice President arid CNO -

Millstone) and Chairperson of the Nuclear Safey Assansment Board.

O ~~~

QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 12 of 21

r*

, . . l!

Nuclear Safety Assessment Board (NSAB) i i

( Function The minimum qualifications of NSAB members are as follows:

a. The Chairperson and NSAB members shall have:

1. An academic degree in an engineering or physical science field, or hold a senior management position, and

2. A minimum of five years technical experience in their respective field of expertise.

b. The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:

1. Nuclear power olant operations;

2. Nuclear engineering;

{

3. Chemistry and radiochemistry;

4. Metallurgy; l

5. Instrumentation and control;

0. Radiological safety;

7. Mechanical and electrical engineering; and i

8. Quality assurance practices.

The NSAB serves to advise the designated senior officer [ Senior Vice President and CNO - Millstone] on matters related to nuclear safety and notify the designated senior officer (Senior Vice President and CNO - Millstone) within l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement between the NSAB and the l organization or function being reviewed.

i Composition The designated senior officer [ Senior Vice President and CNO - Millstone) shall l appoint, in writing, a minimum of seven members, to the NSAB and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in Function (b) above.

k QAP- Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 13 of 21

• s Alternates O All alternate members shall be appointed, in writing, by the designated senior officer (Senior Vice President and CNO - Millstone); however, no more than two l alternates shall participate as members in NSAB activities at any one time. I Meeting Frequency The NSAB shall meet at least once per calendar quarter. ,

Quorum The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast Utilities' nuclear unit. No more than two alternates shall be appointed as members at any meeting l in fulfillment of the quorum requirements.

Review Responsibilities The NSAB shall be responsible for the review of:

a. The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an C.A unreviewed safety question as defined in 10 CFR 50.59;

b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59;

c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;

d. Proposed changes to Technical Specifications and the Operating License;

e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significance;

f. All Licensee Event Reports required by 10 CFR 50.73;

g. Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety; (3

L.) QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 14 of 21

6 ,

h. Significant accidental, unplanned, or uncontrolled radioactive releases,

,, including corrective actions to prevent recurrence;

i. Significant operating abnormalities or deviations from normal and expected performance of equipment that could affect nuclear safety; J. The performance of the corrective action program; and

k. Audits and audit plans.

Reports or records of these reviews shaji be forwarded to the designated senior officer (Senior Vice President and CNO - Millstone} within 30 days following l completion of the review.

Audit Program Responsibilities The NSAB audit program shall be the responsibility of the Nuclear Oversight Department. NSAB audits shall be performed at least once per 24 months in accordance with administrative procedures [ Nuclear Group Procedures}

and shall encompass:

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions;

b. The training and qualifications of the unit staff;

c. The implementation of all programs required by Specification 6.8;

d. The Fire Protection Program and implementing procedures.

e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.

f. Actions taken to correct deficiencies occurring in equipmer,t, structures, systems, components, or method of operation that affect nuclear safety; and

g. Other activities and documents as requested by the designated senior officer (Senior Vice President and CNO - Millstone}. l Records Written records of reviews and audits shall be maintained. As a minimum these records shallinclude:

a. Results of the activities conducted under the provisions of this NSAB Section; r

U OAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 15 of 21 t-

l

.. 1

b. Recommended approval or disapproval of items. considered under PORC, Responsibilities (a) through (d) and Specification 6.8; and

c. Determination as to whether each item considered under PORC, Responsibilities (a), (b), and (d), and Specification 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.59. '

l Station Qualified Reviewer Program Function The designated manager (Unit 1 only - Director - Unit 1 Operations; Unit 2 and  ;

Unit 3 only - Station Director}, designated officer (Unit 1 only - Vice President - l Site Services; Unit 2 and Unit 3 only - Vice President - Nuclear Operations),

or designated senior officer (Senior Vice. President and CNO - Millstone] may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by PORC, Responsibilities item (a), and SORC, Responsibilities item (a) are performed by Station Qualified Reviewers and approved by designated managers [ Responsible Individual (s) for the procedure (s)). These reviews are in lieu of reviews by the PORC or SORC. However, procedures which require a 10CFR50.59 evaluation must be reviewed by the PORC or SORC.

Responsibilities The Station Qualified Reviewer Program shall:

a. Provide for the review of designated procedures, programs, and changes thereto by a Qualified Reviewer (s) other than the individual who prepared the procedure, program, or change.

b. Provide for cross-disciplinary review of procedures, programs, and changes thereto when organizations other than the preparing organization are affected by the procedure, program, or change.

c. Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated by cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program, or change. Cross-disciplinary reviewers may function as a comniittee.

d. Provide for a screening of designated procedures, programs and changes thereto to determine if an evaluation should be performed in accordance with the'. provisions of 10CFR50.59 to verify that an unreviewed safety question does not exist. This screening will be performed by personnel trained and qualified in performing 10CFR50.59 evaluations.

O QAP Appendix F

REV.

20, Change 10 DATE: 7/15/99 PAGE: 16 of 21

4 l

l**

e.

Provide for written recommendation by the Qualified Reviewer (s) to the  !

responsible Manager for approval or disapproval of procedures and O programs considered under PORC, Responsibilities item (a) and SORC, Respcosibilities item (a), and that the procedure or program was screened by a qualified individual and found not to require a 10 CFR 50.59 evaluation.

If the responsible manager determines that a new program, procedure, or change thereto requires a 10 CFR 50.59 evaluation, that Manager will ensure the required evaluation is performed to determine if the new procedure, program, or change l involves an unreviewed safety question. The new procedure, program, or change l will then be forwarded with the 10 CFR 50.59 evaluation to PORC or SORC for review.

Personnel recommended to be Station Qualified Reviewers shall be designated in writing by the designated manager [ Unit 1 only - Director- Unit 1 Operations; Unit  ;

2 and Unit 3 only - Station Director) or designated officer [ Senior Vice President  ;

and CNO - Millstone or: Unit 1 only - Vice President - Site Services, Unit 2 i and Unit 3 only - Vice President - Nucker Operations} for each procedure, program, or class of procedure or program within the scope of the Station  !

Qualified Reviewer Program.

l Temporary procedure changes shall be made in accordance with Specification 6.8.3 with the exception that changes to procedures for which reviews are l assigned to Qualified Reviewers will be reviewed and approved as described in Responsibilities (a) through (e) above.

Records The review of procedures and programs performed under the Station Qualified I Reviewer Prograr shall be documented in accordance with administrative '

procedures.

Tmining and Qualification The training and qualification requirements of personnel designated as a Qualified Reviewer in accordance with the Station Qualified Reviewer Program shall be in i accordance with admirbtrative procedures. Qualified reviewers shall have;

a. A Bachelors degree in engineering, related science, or technica:

discipline, and two years of nuclear power plant experience; i

OR I

b. Six years of nuclear power plant experience; OR i

QAP - Appendix F I REV; 20, Change 10 DATE: 7/15/99

,_ PAGE: 17 of 21 L

L i..

L

c. An equivalent combination of education and experience as approved c by a Department Manager.

SAFETY LIMITVIOLATION - Units 2 and 3 Only The Senior Vice President and CNO - Millstone and the Chairperson of the NSAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event a Safety Limit is violated.

The Safety Limit Violation Report shall be submitted to the Commission, the Chairperson of the NSAB, and the Senior Vice President and CNO -

Millstone, within 14 days of the violations.

RECORD RETENTION - Units 1 and 2 (1) The following records shall be retained for at least five years:

I

a. Records and logs of facility operation covering time interval at each power level.

I

b. , Records and logs of principal maintenance activities,  !

inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS.

O d. Records of surveillance activities, inspections, and calibrations d required by these technical specifications.

e. Records of reactor tests and experiments.

f. Records of changes made to operating procedures,

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

I. Records of annual physicalinventory of all sealed source material of record.

(2) The following records shall be retained for the duration of the facility operating license:

a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis i Report.  !

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

(G

_)

QAP - Appendix F REV.: 20, Change 10 DATE: 7/15/99 PAGE: 18 of 21

a l

c. Records of facility radiation and contamination surveys, j

d. Records of radiation exposure for all individuals entering radiation control areas,

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

f. Records of transients or operational cycles for those facility corn 7nents designed for a limited number of transients or cycles.

g. Fw ,+ds of training and qualification for current members of the plant staff.

h. Records of inservice inspections performed pursuant to the Technical Specifications.

i. Records of quality assurance activities required by the QA Manual. ,

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

k. Records of meetings of the PORC, the NSAB, and the SORC. I p 1. Records of Environmental Qualification which are covered under V the provisions of Specification 6.13 (Unit 2 Only).

m. Records of Environmental Qualification (Unit 1 Only).

n. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) and the Process Control Program.

RECORD RETENTION - Unit 3 Only (1) In addition to the applicable record retention requirements of Title 10, Code of Federa! Regulations, the following records shall be retained for at least the minimum period indicated.

(2) The following records shall be retained for at least five years:

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

b. Records and logs of principal maintenance activities, ;nspections, repair and replacement of principal items of equipment related to nuclear safety;

{}.

QAP - Appendix F REV.: 20. Change 10 DATE: 7/15/99 PAGE: 19 of 21

Io ,

c. All REPORTABLE EVENTS;

d. Records of surveillance activities, inspections, and calibrations required by Technicai Specificat!ons;

e. Records of changes made to the procedures required by Specificationc 6.8.1 l 1

f. Records of radioactive shipments; 1

g. Records of sealed source and fission detector leak tests and results; i and ,

i

h. Records of annual physicalinventory of all sealed source s material of record. l (3)- The following records shall be retained for the duration of the unit Operating License: 1

a. Rocords and drawing changes reflecting unit design modificationc made to systems and equipment i

described in the Final Safety Analysis Report;

b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; O

V c. Records of radiation exposure for all individuals entering radiation control areas;

d. Records of gaseous and liquid radioactive material released to the ,

environs; j

e. Records of transient m operational cycles for those unit components identified in Technical specifications Table 5.7-1. i

f. Records of reactor tests and experiments;

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

t

h. Records of inservice inspections performed pursuant to the Technical {

Specifications; j

i. Records of quality assurance activities required by the Quality Assurance Topical Report not listed in (2) a. through (2) h. above;

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to I 10 CFR Part 50.59; i QAP - Appendix F REV.: 20, Change 10 l DATE: 7/15/39 PAGE: 20 of 21 m 1

f.

r,

. k. Records of meetings of the PORC, the NSAB, and the SORC;

'=

1. Records of.the service lives of all hydraulic and mechanical snubbers required by Technical Specifications 3.7.10 including the date at which the ' service life commences and associated installation and maintenance records;

m. Records of sec,hdary water sampling and water quality; and n Records of analyses required by the Radiological l Envirorimental Monitoring Program that would permit l evaluation of the accurn:y of the analysis at a later

! date. This should include procedures effective at specified times and QA records showing that these

! procedures were followed.

l~ o. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose l

Calculation Manual (REMODCM) and the Process Control Program.

l

' Relocation of Technical Specification Administrative Controls Related to Quality

- Assurance in Response to AL 95-06.

O i

TY QAP - Appendix F REV.: 20. Change 10 DATE: 7/15/99 PAGE: 21 of 21

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