ML19263D021
| ML19263D021 | |
| Person / Time | |
|---|---|
| Site: | Millstone, 05000496, 05000497  |
| Issue date: | 03/05/1979 |
| From: | Diedrick D, Switzer D NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19263D009 | List: |
| References | |
| NU-QA-1, NUDOCS 7903200439 | |
| Download: ML19263D021 (100) | |
Text
af V.
ABSTRACT NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT Northeast Utilities (NU) has developed and is implementing a compre-hensive Quality Assurance program to assure conformance with established regulatory requirements, set forth by the Nuclear Regulatory Commission (NRC), and accepted industry standards. The participants in the NU Quality Assurance Program assure that the design, procurement, construc-tion, testing, operation, maintenance, repair and modification of nuclear power plants are performed in a cafe and effective manner.
The NU Quality Assurance Program (QAP) Topical Report complies with the requirements set forth in Appendix B, of 10 CFR Part 50, along with applicable sections of the Safety Analysis Report (SAR) for each license application, and is responsive to the United States NRC Regulatory Guide 1.70, Rev. 2, dated September, 1975, which describes the information required to be presented in the Quality Assurance Section of the SAR's for nuclear power plants.
The NU QAP is committed to utilize the guidance obtained from the Regulatory documents and their endorsed Standards as referenced in Appendix D of the Topical Report.
QAP - Abstract Rev.
2 79()32.00 % 9 Date: March 5, 1979 Page 1 of I
IF TABLE OF CONTENTS fl NORTHEAST UTILITIES QUALITY ASSURA: ICE PROGRAM TOPICAL REPORT Rev.
Pages Abstract 2
1 Table of Contents 3
1 Policy Statement 3
1 Introduction 1
1 Quality Assurance Program QAP 1.0 Organization 3
1-6 QAP 2.0 Quality Assurance Program 3
1-6 QAP 3.0 Design Control 3
1-5 QAP 4.0 Procurement Document Control 3
1-4 QAP 5.0 Procedures, Instructions and Drawings 3
1-2 QAP 6.0 Document Control 2
1-3 QAP 7.0 Control of Purchased Material, Equip-2 1-3 ment and Services QAP 8.0 Identification and Control of 3
1-2 Materials, Parts and Components QAP 9.0 Control of Special Processes 3
1-2 QAP 10.0 Inspection 2
1-3 QAP 11.0 Test Control 1
1-3 QAP 12.0 Control of Measuring and Test Equip-2 1-2 ment QAP 13.0 Handling, Storage, and Shipping 1
1-2 QAP 14.0 Inspection, Test and Operating Status 1
1-2 QAP 15.0 Nonconforming Materials, Parts, or 2
1-3 Components QAP 16.0 Corrective Action 3
1-2 QAP 17.0 Quality Assurance Records 2
1-2 QAP 18.0 Audits 3
1-4 Appendices A.
Category I Systems, Structures and Com-2 1-3 ponents B.
Qualification and Experience Requirements 1
1 NUSCO Manager, Quality Assurance C.
Quality Assurance Procedures Implementing 1
1-17 the Regulatory Requirements D.
List of Regulatory Guides and Standards 2
1-2 Commitments E,
Glossary of Quality Assurance Terme 2
1-6 F.
Program Exceptions 2
1 QAP Table of Contents Rev. 3 Date : March 5,1979 Page 1 of 1
o POLICE STATEMENT NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT The policies, requirements and taskt contained in this Northeast Utili-ties Quality Assurance Program description have been developed to achieve a recognized need for quality assurance during the design, procurement, construction and operation of our nuclear facilities.
Northeast Utilities procedures which implement this program are described in various manuals which are referenced herein.
The program has been established to comply with the requirements of Title 10, Code of Federal Regulations, Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants."
It is also responsive to selected NRC Regulatory Guides as well as ANSI N45.2.
The development and overall responsibility for this Qualit.y Assurance Program lies with the NUSCO Executive Vice President of Er.gineering and Operations.
Corporate authority is delegated to the Manager, Qaality Assurance for the preparation and administration of the Quality Assur-ance Program, individual group Vice Presidents are responsible for the implementation of their portion of the Northeast Utilities Quality Assurance Program. Revisions, additions to, and audits of this program are the responsibility of the Manager, Quality Assurance. Any revisions or additions shall be approved by affected Departments prior to the incorporation of such changes into the program.
JAs D. C. Switzer O
Vice Chairman Northeast Utilities Service Company QAP - Policy Statement Rev. 3 Date: March 5, 1979 Paco 1 of 1
i 7,
INTRODUCTION This Northeast Utilities (NU), Quality Assurance Program Topical Report s,
contains the quality assurance requirements which are relative to the safety of the nuclear power plaat. The topical report consists of the following three parts:
1.
Intr 6 duction, which delineates the purpose of the topical program, and summarizes its scope and applicability.
2.
QAP which summarizes the quality assurance approach, through eighteen criteria, to activities related to Category I material, parts, components, systems and services.
3.
The appendices, provide supporting statements and tabulations.
This topical report has been prepared to document that a meaningful quality assurance program has been established and implemented to ensure that adequate quality requirements are being complied with to safeguard NU employees, contracted personnel and the general public, from the conceptual phat e through the operations phase of nuclear power plant life.
The NU QAP establishes controls which are applicable to systems, struc-tures, components, material, parts and services identified as safety related and listed for each nuclear power plant and supplemented, if applicable, for plant betterment projects. The controls which implement the actions identified in the QAP topical report are departmental proce-dures and instructions which delineate actions and steps recessary to accomplish safety related quality requirements.
Procedures and instruc-tions are written by the company and/or departments which have the responsibility for implementing actions assigned to them as delineated by the NU QAP. Quality related procedures and revisions thereto are reviewed by and concurred with by the Manager, Quality Assurance / designee, in accordance with QAP 2.0 and QAP 5.0.
The NU QAP is responsive to applicable codes, Nuclear Regulatory Commis-sion regulatory requirements, accepted industrial standards and revisions thereto.
Provisions are established to update the NU QAP topical report in accordance with revisions to codes, standards and regulatory require-ments, and to inform cognizant personnel to implement appropriate action to assure tb? highest standard of quality is achieved for safety related systems, structures, components and services for nuclear power pla ts.
Y e
David G. diedrick
' s Manager, Quality Assurance n
QAP - Introduction Rev. 1 Date: March 5, 1979 Page 1 of 1
9 1.0 ORGANIZATION
1.1 INTRODUCTION
Northeast Utilities (NU) is a holding company which owns all of the common stock in several companies as illustrated by Figure 1.1.
The Connecticut Light and Powar Company (CL&P), The Hartford Electric Light Company (HELCO) and Western Massachusetts Electric Company (WMECO) are the sole owners of Millstone Units Number One and Two with 53%, 28% and 19% ownership respectively. They are the principal owners in Millstone Unit Number Three with 65% ownership and, by contract have the authority to make all cf the decisions af fecting the design, procurement, construction and operation of that unit. This decision making authority will be the same for future units, i.e., Montague Units Number One and Two.
The NU Companies jo'.ntly own 44% of The Connecticut Yankee Atomic Power Company (CYAPCO). By contract, NU and Northeast Utilities Service Company (NUSCO) have been delegated operational cor. trol of CYAPCO. NUSCO provides technical support for the operation of that plant. This is also illustrated in Figure 1.1.
Northeast Nuclear Energy Company (NNECO) and CYAPC0 are the operat-ing companies established to operate their respective facilities.
NNECO is delegated the responsibility for operating the Millstone and Montague Units by the owners. NNECO in turn has contracted for the services of NUSCO for the design and construction management of all of the units at Millstone and Montague and may solicit technical support during plant operations. NNECO and CYAPC0 comprise the Nuclear Plant Operating Companies (NUPOC) as illustrated in Figure 1.1.
NUSCO, part of which is organized as shown in Figure 1.2, provides services such as engineering, quality assurance, accounting, plan-ning and procurement for the NU system operating companies where these services can be more efficiently and economically performed on a system-wide basis.
The NUPOC and NUSCO interrelationship shown in Figure 1.3, for quality related activities, indicates how conflicts are resolved.
As indicated, the Vice Chairman - NUSCO is also the President of NUPOC.
1.2 GENERAL 1.2.1 The Vice Chairman of NU is also the Vice Chairman of NUSCO and directs specified nuclear related activities of NUSCO.
He has the ultimate responsibility for the estab-lishment and execution of the NU Quality Assurance QAP 1.0 Rev.3 Date: March 5, 1979 Page 1 of 6
g i
Program (QAP). Authority for the establishment and execution of the Program is delegated to the NUSCO Execu-tive Vice President - Engineering and Operations.
The NUSCO Executive Vice President (NLPOC Vice Presi-dent) - Engineering and Operations is responsible for engineering, construction, operation, maintenance, modi-fication, and quality assurance within NU.
See Figure 1.3.
The NUSCO Vice President Nuclear Engineering and Operations, reporting to the NUSCO Executive Vice P esident Engineer-ing and Operations, nd the Vice President of Purchasing and Stores reporting
_o the NUSCO Vice Chairman, are responsible for ensuring that the requirements of the NU QAP are carried out within their respective groups.
1.2.2 The NUSCO Vice President Nuclear Engineering and Opera-tions (NUPOC Vice President) reporting to the NUSCO Executive Vice President Engineering and Operations assesses the scope, status, implementation and effective-ness of the NU QAP by conducting, with the assistance of a team of individuals, annual reviews to assure that the Program is adequate and complies with 10 CFR 50, Appendix B and other regulatory requirements.
The team is made up of individuals knowledgeable in management, auditing, quality assurance and the NU QAP.
They are appointed by and report to the NUSCO Vice Presi-dent Nuclear Engineering and Operations.
The management quality assurance review is:
a.
Preplanned toward the objective of determining the adequacy of the NU QAP and its compliance with Appendix B to 10 CFR Part 50; systematic evaluation; b.
a c.
capable of identifying, communicating and tracking any required corrective action.
1.3 PARTICIPATING GROUPS 1.3.1 The major groups participating in the NU QAP are the NUSCO Nuclear Engineering and Operations and NUSCO Purchas-ing.
1.3.2 Overall responsibility for the NU QAP, including direc-tion of the program, implementation of the policies, plans, requirements, procedures, audits and verification to assure compliance with regulatory requirements includ-QAP 1.0 Rev.3 Date: !!srch 5,1979 Page 2 of 6
w ing 10 CFR 50, Appendix B, is assigned to the Director Reliability Engineering and Quality Assurance. The Manager, Quality Assurance reporting to the Director Reliability Engineering and Quality Assurance, is directly responsible for verifying implementation of the require-ments of the NU QAP.
1.3.3 Overall responsibility for the implementation of the NU QAP Topical Report at the NUPOC nuclear plant is assigned to a NUPOC Superintendent. Each NUPOC Quality Assurance Supervisor, reporting to the appropriate Superintendent, is responsible for verifying implementation of the require-ments of the NU QAP.
1.4 RESPONSIBILITIES 1.4.1 The head of each department or organization performing quality related activities is responsible for:
a.
Administering those activities within his organi-zation which are quality related as defined by the NU QAP Topical Report; b.
Establishing and clearly defining the duties and responsibilities of personnel within his organi-zation who execute quality related activities; c.
Planning, selecting and training personnel to meet the requirements of the NU QAP; d.
Performing and coordinating quality matters within his department and interfacing with the Quality Assurance Department on quality related matters.
The responsibility, authority, and organizational rela-tionship for performing quality related activities within each organization is established and delineated in the NU organization charts and written job or functional descrip-tions.
1.4.2 Nuclear Engineering and Operations Group The Vice President Nuclear Engineering and Operations Group is responsible for providing and directing projects, technical and support personnel to meet NUSCO responsibilities during engineering, construction and assigned functions during preoperational and startup testing and modifications of nuclear power plants.
QAP 1.0 Rev. 3 Date : March 5,1979 Page 3 of 6
The Nuclear Engineering and Operations Group is divided into five departments:
a) Nuclear Operations; b) Nuclear and Environmental Engineering; c) Nuclear Projects; d)
Generation Engineering; e) Reliability and Quality Assur-ance (See Figure 1.2).
1.4.2.1 The Director Reliability Engineering and Quality Assurance is responsible to direct and/or coordinate the support for Project Managers and others and the establishment and verification of implementation of the requirements of the NU QAP.
He assures that audit data are analyzed and the reports, which indicate quality trends and effectiveness of the QA Program, are reported to management for review and assessment.
The Manager, Quality Assurance reporting to the Director Reliability Engineering and Quality Assurance, is directly responsible for veri-fying implementation of the requirements of the NU QAP Topical Report.
He provides management with objective evidence concerning quality, independent of the individual or group directly responsible for performing the specific activity.
He has the authority and organizational freedom to assure all necessary quality af fecting activities are performed and is independent of undue influences and responsibilities f'r schedules and costs. He has the responsibility and authority delineated in writing, to stop unsatisfactory work end control further processing, delivery, or installation of nonconforming materials.
He maintains an overview of NUPOC quality assurance activities through a planned and systematic program of audits and surveil-lances.
He maintains a quality assurance staff which covers QAP aspects of construction, procurement, design, preoperational testing and operations.
1.4.2.2 The Director Nuclear Projects is responsible to direct and/or coordinate the processes and assure the necessary resources for the licens-ing, engineering, procurement, construction, quality assurance, startup of new nuclear generating facilities and provide construction management services for generation facility betterment work.
The Nuclear Projects Depart-ment consists of a Nuclear Project Manager and a Nuclear Project Engineer for each nuclear QAP 1.0 Rev. 3 Date March 5,1979 Page 4 of 6
D project planned or under construction, construc-tion site management and cost and schedule control.
1.4.2.3 The Director Generatica Engineering Department is responsible for providing support to projects directed by the Nuclear Projects Department and other NUSCO/NUPOC departments and to provide Project Engineers for backfit/ betterment projects.
His department provides systems design expertise and the expertise for specification and procure-ment of equipment and materials. The Genera-tion Engineering Department consists of the following activities; mechanical engineering, electrical engineering, civil engineering and engineering design.
1.4.2.4 The Director Nuclear and Environmental Engineer-ing Department is responsible for licensing and safeguards, reactor engineering, technical support, nuclear systems' analyses, environmental programs and all engineering associated with nuclear fuel and those components which con-stitute or significantly effect the reactor core, for both new nuclear projects and operat-ing nuclear power plants. The Nuclear and Environmental Engineering Department consists of the following activities; environmental programs, reactor analysis, licensing and safeguards and nuclear fuel ranagement.
1.4.2.5 The NUSCO System Superintendent of Nuclear Operations is responsible for modification, refueling, m=intenance and operation of in-service nuclear power plants and for controlling and directing the preoperational and startup test program of new units.
Assumption of preoperational testing responsibility by the Nuclear Operations Department commences with system turnover by Nuclear Projects.
The Nuclear Operations Department consists of the NUSCO Nuclear Operations Engineering staff and the NUPOC organizations.
The NUPOC Superintendents are responsible for the operation, maintenance, modification and refueling of in-service nuclear power plants, and for controlling and directing the preopera-tional and startup test program of new units in accordance with an approved startup manual per QAP 5.0.
Assumption of preoperational testing QAP 1.0 Rev. 3 Date. March 5,1979 Page 5 of 6
s responsibilities commences with system turnover.
They are also responsible for. providing qualified personnel to perform these activities in accor-dance with approved drawings, specifications and procedures. They provide nuclear plant operations input to the Nuclear Engineering Departments for the design of new facilities and plant betterment projects.
The NUPOC Quality Assuranct Supervisor report-ing to a NUPOC Superintendent,is responsible for verifying implementation of the NU Quality Assurance Program rcquirements at the in-service nuclear power plants and at assigned pre-service plants, for all those quality affected activities commencing with system turnover. He also provides station management and the Manager, Quality Assurance with objective information concerning quality, indeptadent of the individual or group directly respo..sible for performing the specific activity.
He has the authority and organizational freedom, is sufficiently removed from undue cost and schedule influences, has responsibilities to perform his quality assurance functions effec-tively, including:
Stop unsatisfactory work and control a.
further processing, delivery of noncon-forming materials as delineated in writing; b.
Identifying quality problems; c.
Initiating, recommending or providing solutions, and; d.
Verifying implementation of solutions.
1.4.3 Purchasing The Purchasing Managers are responsible to the Vice President Purchasing and Stores for the procurement of materials and services from qualified suppliers, in accordance with predetermined commercial, technical, and quality requirements; to issue NUSCO Purchase Orders /
Contracts and changes thereto; maintains traceability of purchasing records from NUSCO/NUPOC, initiation of pur-chase requisitions through to payment for the purchased item.
The Vice President Purchasing and Stores controls quality related purchasing procedures.
QAP 1.0 Rev. 3 Da te. March 5,1979 Page 6 of 6
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2 March 5, 79
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2.0 QUALITY ASSURANCE PROGRAM 2.1 GENERAL REQUIREMENTS Northeast Utilities (NU) has established a Quality Assurance Pro-gram (QAP) which complies with the criteria of 10 CFR 50, Appendix B, and follows the guidance referred to in Appendix D of this report. The quality assurance requirements set forth henein and the attached Policy Statement, supplemented by the Qualitt Assur-ance Procedures, provide the primary basis of the Program and the NU Policy with regard to quality assurance. This Program is estab-lished for each plant site in a manner intended to accomplish the required level of quality and is carried out throughout the life of nuclear power plants. This includes quality related activities initiated prior to submittal of the Preliminary Safety Analysis Report (PSAR), such as design and procurement, preparation of the PSAR, and safety related site preparation construction activities.
It also includes quality related activities during the operation, maintenance and modification of the in-service nuclear power plants.
The requirements of the NU QAP apply, as a minimum, to nuclear safety related systems, structures and components as functionally identified in Appendix A, " Category I Systems, Structures and Components", and other items or services which are specifically identified by NU in each license applicat. ion submitted to the NRC.
The requirements of the Program are implemented by Northeast Utili-ties Service Company (NUSCO), Nuclear Plant Operating Companies (NUPOC), the engineer-constructor, (NUSCO) contractors, suppliers and engineering service organizations performing activities affect-ing the quality of safety related systems, structures and compon-ents of nuclear power plants.
Procedures define the required indoctrination and training of personnel performing activities affecting quality, as necessary, to assure that suitable proficiency is achieved and matutained.
Training sessions are documented, the content described, who attended, when they attended and the results of the training sessions.
A periodic program review of the status and adequacy of the NU QAP is accomplished by Quality Assurance Department audits and by the independent audit team described in QAP 1.0, Section 1.2.2.
Organ-izations outside NU are required to review the status and adequacy of their own QA Program, so that it satisfies the applicable re-quirements of NU QAP.
QAP 2.0 Rev. 3 Date : March 5, 1979 Page 1 of 6
2.2 IMPLEMENTATION 2.2.1 Goals and Objectives As stated in the Policy Statement of NU, the goals of the NU QAP are to maintain quality IcVels in an effective and efficient manner and to assure a high degree of functional integrity and reliability of nuclear safety related systems, structures and components. To meet this goal, the following objectives of the NU QAP have been defined:
Define through documented procedures, the quality a.
activities that apply to the design, fabrication, procurement, construction, testing, operation, refueling, maintenance, repair and modification of nuclear power plants; b.
Establish, assign and document the responsibilities for the conduct of those activities affecting quality of the safety related systems, structures and components; c.
Establish confidence that (a) the design, fabrication, construction and operation of nuclear poter generation facilities are performed in a manner consistent with NU Policies and (b) quality related activities are performed by responsible personnel through a system of audits of those organizations with quality related responsibilities; d.
Appraise management of quality related unresolved problems and trends which could have a significant effect on nuclear power plant safety and; e.
Prevent schedule delays and high cost due to poor quality.
2.2.2 Program Documentation This topical report on the NU QAP defines the NU nuclear policies, goals and objectives, and is used as guidance for the development of the various implementing departmental procedures. Revisions to the NU QAP Topical Report will be made as needed to reflect current requirements and descriptions of activities. These revisions will be made in accordance with a Quality Assurance Department Procedure.
If a regulatory commitment reflects a deviation from the NU QAP Topical Report, an amendment shall be submitted to the Nuclear Regulatory Commission (NRC) thirty (30) calendar days prior to implementation.
Quality Procedures are developed by the department with major responsibilities for a quality related activity.
QAP 2.0 Rev. 3 Date March 5,1979 Page 2 of 6
These procedures are reviewed by the departments which are responsible for pertions of these procedures. These procedures are approved by the departments which initiate these procedures and are reviewed and concurred with by the Manager of Quality Assurance for compliance with the NU QAP.
Changes to procedures are subjected to the same degree of control as that utilized in the preparation of the original document.
Each NUSCO Department Head / Nuclear Plant Operating Ccmpany l
(NUPOC) Superintendent is responsible for implementa-tian of the NU QAP, which includes individual departmental procedure requirements applicable only to his respective activities.
In addition, he is responsible for the preparation, approval and distribution of those instruc-tions, operating procedures, testing procedures or other instructions where further guidance is necessary.
2.2.3 Systems, Structures and Components The requirements of the NU QAP shall apply, as a minimum, to nuclear safety related systems, structures and components, as addressed in the Safety Analysis Reports (SAR).
Safety related systems, structures and components are functionally identified in Appendix A of the NU QAP Topical Report and also specifically identified in Sec-tion 3 of each License Application submitted to the NRC.
The degree of control over activities affecting the quality of safety related systems, structures and compon-ents is consistent with their importance to safety.
Such controls include use of appropriate equipment, establish-ment of suitable environmental conditions and assurance that all prerequisites for a given activity have been satisfied.
The Program provides for controls over special processes and skills necessary to attain the required quality, and the need for verification of quality by inspection and test.
2.2.4 Participating Organizations The NU organizations with responsibilities for activities affecting quality of nuclear safety related systems, structures and components are identified in QAP 1.0, which also briefly describes their assigned responsibil-ities.
The Quality Assurance Department is responsible for:
a) the development, coordination, and control of the NU QAP including coordination of Quality Assurance Department Procedure review and approval; b) control and issuance of the NU QAP Topical Report as a controlled document (as QAP 2.0 Rev. 3 Date : March 5,1979 Page 3 of 6
described in QAP 6.0) and; c) review and concurrence with quality related procedures written by other department and revisions thereto.
Procedure reviews will be per-formed in accordance with QAP 5.0.
NU shall require that their engineer constructor, Nuclear Steam Supply System Supplier (NSSS) suppliers, engineer-ing Service Organizations and contractors shall invoke upon their subcontractors, via procurement documents, requirements for a quality assurance program to meet the applicable criteria of Appendix B to 10 CFR, Part 50, including the applicable elements of the Regulatory Guides and their endorsed Standards identified in Appen-dix D of the Topical Report.
However, NU retains overall responsibility for the Program. The speci fic quality related activities performed by these organizations are specified in the procurement documents. The Quality Assurance Department reviews and approves these organiza-tion's quality assurance programs prior to initiation of contracted activities, and audits subsequent activities for compliance to their procedures.
The object of the review is to verify that the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations have an adequate quality assurance program to meet the applicable requirements of Appendix B to 10 CFR, Part 50; or that an acceptable alternative to Appendix B to 10CFR, Part 50 requirements is described and documented.
In addition to the initial review, the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations quality assurance programs shall be periodi-cally audited by the Quality Assurance Department to assure continued implementation of quality requirements.
Af ter system construction by the engineer constructor and system turnover to NUPOC, the program will fall under the requirements of NU QAP.
A formal test program is prepared to provide assurance that all systems and equipment function in accordance with design specifications.
The formal test program is described in a startup test manual which describes the administrative organization and procedure which will be followed, during the phaseout of design and construction, preoperational testing and plant turnover.
It demonstrates control of quality related activities including management and technical interfaces among the engineer constructor, NSSS Supplier and NUPOC.
QAP 2.0 Rev. 3 Date. March 5,1979 Page 4 of 6
During operation, contractors may be delegated the execu-tion of quality assurance functions by contract.
These contracts are reviewed and approved in accordance with NU QAP requirements.
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 related activities. Quality procedures delineate the requirements for an indoctrination program to assure that personnel responsible for performing quality acti'. ities are instructed in the purpose, scope and implementation of quality related procedures and instructions and that compliance to these documents is mandatory. The Manager, Quality Assurance is responsible for the indoctrination of nonsupervitory personnel within his department who perform quali.ty related activities.
This program also requires the head of each department (including the Quality Assurance Department) to be responsible for a training plan which assures that personnel performing quality related activities are trained in the principles and techniques of the activity being performed. The proficiency of personnel is maintained in the skills necessary to perform quality related activities through retraining, requalification or re-examination, as appropriate.
2.2.6 Management Participation NUSCO Department Heads /NUPOC Superintendents are responsible for implementing the N" QAP Topical Rep rt within their Departments / Plants.
The Manager, Quality Assurance will assist in development, coordination and review of the Program.
A management review of the Program is conducted on an annual basis, by an independent audit group, to assess the scope, status, implementation, effectiveness and to assure compliance to NRC licensing commitments. The Management Review Committee is appointed by the NUSCO Vice President of Nuclear Engineering and Operations. He ensures that deficiencies are tracked and resolved, and advises upper management of the results of the audits.
The following actions are instituted by the Review Committee to assure that the NU QAP meets its published responsibilities:
QAP 2.0 Rev. 3 Date March 5,1979 Page 5 of 6
a.
The Review Committee will review documents comprising changes to the NU Quality Assurance Program to assure compliance to the NU QAP Topical Report; b.
The Review Committee utilizes results of audits conducted by the NRC or other departments to determine whether or not any adverse trends exist, and ascertain if further atcention is required by management; c.
The Review Committee's findings of deficiencies and recommendations for program improvement are forwarded to the NUSCO Vice President Nuclear Engineering and Operations, who will ensure appropriate corrective action is taken.
The quality assurance programs of the engineer-constructor, NUSCO con
- -tors, suppliers and engineering service organization. that p rform quality related activities are reviewed by the Quality Assurance Department to assure that contractors management regularly reviews the status and adequacy of their part of the NU QAP.
QAP 2.0 Rev. 3 Date : March 5,1979 Page 6 of 6
3.0 DESIGN CONTROL 3.1 GENERAL REQUIREMENTS The Nuclear Engineering and Operations Group or the appropriate Nuclear Plant Operating Companies (NUPOC) are responsible for controlling design work and administering design control activities (including design interface) and design modifications for nuclear safety related systems, structures and components defined in the
" Category I Systems, Structures and Components List" (A9pendix A).
The Northeast Utilities (NU) Quality Assurance Program (QAP) for design is established to assure that the applicable design require-ments, such as design bases, regulatory requirements, codes, technical standards and quality standards are identified in design documents and their selection reviewed, approved and controlled in accordance with established procedures.
Such controls include review for suitability of application of materials, equipment, parts and processes that are essential to the safety related functions of the systems, structures and components.
Changes to and deviations from specified requirements are identified, documented and controlled.
Northeast Utilities Service Company (NUSCO) has the ultimate responsi-bility for design control program implementation for plants presently under construction and for proposed plants. hdPOC has the responsi-bility for design control program implementation for operating plants unless they elect to appoint NUSCO to perform a modification.
NUSCO AND NUP0C may delegate to other organizations the work of establishing and executing the design control program or any part thereof, but retains the ultimate responsibility, for the program.
The interface controls, both internal and external, for organiza-tions nerforming design work for safety related systems, structures and components are identified and implemented in accordance with documented procedures. This identification includes those organi-zations providing criteria, designs, specifications and technical direction.
Measures are applied to verify the adequacy of design. The extent of design verification is specified and documented by the responsible organization. The individuals performing design verification should not (1) have immediate supervisory responsibility for the individual performing the design, (2) have specified a singular design approach, (3) have ruled out certain design considerations, or (4) have established the design inputs for the particular design aspect being verified. The independent design verification should not dilute or replace the responsiblity of the supervisors for the quality of work performed under their supervision.
Where changes to previously verified designs have been made, design verifications QAP 3.0 Rev.3 Date: March 5, 1979 Page 1 of 5
i are required for the change, including evaluation of tne effects of those changes on the overall design. Design verification may be accomplished by testing.
Tests to demonstrate adequacy under adverse design conditions shall comply with the requirements of QAP 11.0, " Test Control". Design errors and deficiencies which adversely affect scfety related systems, structures and components in the design process are documented, and appropriate corrective action is taken. These design errors and deficiencies are documented in accordance with design change procedures or as defined in QAP 15.0.
3.2 IMPLEMENTATION The Nuclear Engineering and Operations Group or NUPOC is responsi-ble for the design, design review, engineering approval of design changes, design evaluation and design control of nuclear power plants.
The fuiction mev be delegated to other organizations to perform the design ac+.vity, or any part thereof, but the respon-sibility for overal) design remains with the Nuclear Engineering and Operations Greap or NUPCC.
In all cases, final engineering decisions and ultimate design control of systems, structures and components re..ated to nuclear power plants is the responsibility of KUSCO Nuclear Engineering and Operations Group /NUPOC.
The Quality Arsurance Department performs audit s/surveillances/-
inspections co verify that the engineer-constructor, NUSCO contrac-tors, suppliers, engineering service organizations and NU Depart-ment, are effectively complying with their QAP 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; compat-ibility of materials; accessibility for in-service inspec-tion, maintenance, and repair; and delineation of accept-ance criteria for inspections and tests.
Measures estab-lished to control design documents are described in QAP 6.0.
Program proceduces and instructions define the method for implementing design control measures. These measures require that applicable design requirements, such as, design bases, regulatory requirements, codes and standards, are translated into specifications, drawings, procedures or instructions.
Instructions further require that appropriate quality standards are specified and included in design documents. All materials, equipment, parts and processes, including standard "off the shelf" commercial or previously approved items essential to the safety QAP 3.0 Rev. 3 Date: March 5, 1979 Page 2 of 5
related functions, are selected and reviewed for suit-ability of application. The basis for selection may include industry standards, material and prototype hard-ware testing programs, and design reviews.
3.2.2 Design Change Control Procedures and instructions governing design change control during construction, modifications to operating plants, control of discrepant or deficient design condi-tions, and reported unsatisfactory performance, provide for the identification of the need for design changes and a documented method to control these changes. Design and specification changes are subject to design control measures commensurate with those applied during the original design.
Prior to receipt of an operating license, an independent review and approval of design changes is performed by the organization that conducted the original design reviews, unless NUSCO designates another qualified organization to perform this function.
Subsequent to receipt of an operating license, proposed safety related design change / modifications are submitted to the in-service units management for processing and review. This review includes the Plant Operation Review Committee (PORC)/ Site Operations Review Committee (SORC).
PORC/SORC is advisory to the appropriate NUP0C Superin-tendents on matters relating to nuclear safety.
Its composition, responsibilities, and authority are defined in Section 6 of each in-service unit Technical Specifica-tions. NUP0C QA personnel can be represented at the PORC/SORC Committees if assigned by the appropriate NUPOC unit Superintendents.
If the change involves a Category I, system, structure or component, the change will be reviewed by qualified engineering personnel for technical adequacy.
Review of the design change requests is performed by the Nucle,r Review Board / Environmental Review Board on an unreviewed safety / environmental question. These independent reviews are performed to assure that:
the adequacy of the proposed change is determined; a.
b.
unreviewed safety / environmental questions are properly l
identified and handled per 10 CFR 50.59; c.
nuclear safety / environmental requirements have been considered.
QAP 3.0 Rev. 3 Date March 5, 1979 Page 3 of 5
Errors and deficiencies in design, including the design process, that cvuld adversely affect safety-related structures, systems, and components are documented and corrective action is taken to preclude repetition.
3.2.3 Design Interface Control During design, construction or modifications by NUPOC of nuclear power plants, the Nuclear Engineering and Opera-tions Group is responsible for review, coordination and documentation of design interfaces.
Engineering pro-cedures provide the method for identification of design interfaces, design interface changes, and modifications affecting drawings and design documents.
l During plant design and construction phases, control of interfaces may be delegated to the engineer-constructor and/or the Nuclear Steam Supply System (NSSS) supplier.
During the operations phase, procedures and instructions identify design interfaces which are controlled by the appropriate NUPOC Superintendent.
Resolution of design interface questions are documented.
3.2.4 Design Verification Original dasigns and design modifications are reviewed for adequacy and the sign-off performed by a person other than the originator of the design.
Design reviews are documented in accordance with procedures or instructions.
Simplified calculations or computer models/ codes may be utilized as alternate means of design verification.
When design verification is performed by testing, the tests are performed using approved procedures, which specify the authority and responsibility of design verification personnel. Ultimate responsibility for design adequacy and evaluation is retained by NUSC0/NUPOC, as appro-priate.
Particular emphasis is placed on assuring that designs are in conformance with applicable codes, and on select-ing the proper design verification or checking method.
Procedures and instructions provide the requirements and necessary controls for design verification. These controls include a review to assure that design characteristics can be controlled, and verification that there is adequate accessibility for inspection or test, and that inspection ind test acceptance criteria are incorporated.
During the operations phase, documentation of reviews is provided.
QAP 3.0 Rev. 3 Date : March 5, 1979 Page 4 of 5
During the design and construction phases, the NUSCO project engineer maintains the ultimate responsibility for the design documents generated by the engineer-con-structor, NSSS supplier and other NUSCO departments. The evaluation of selected documents by project engineers may be accomplished with assistance from other NUSCO departments concerned w th the equipment / subject covered by the i
document being evaluated.
The project engineer is responsible for the resolution of NUSCO comments on specifications and drawings issued by the engineer-constructor, NSSS supplier, and NUSCO tontrac-tors.
QAP 3.0 Rev. 3 Date. March 5,1979 Page 5 of 5
4.0 PROCUREMENT DOCUMENT CONTROL 4.1 GENERAL REQUIREMENTS The procurement of materials, equipment, patts end/or services required during the design, construction, operation and maintenance of Category I systems, structures and components in nuclear power plants is performed in a controlled manner which assures compliance with applicable regulatory requirements, procedures, quality assur-ance standards and regulations affecting procurement documents.
Changes to procurement documents are subject to the same degrce of control as utilized in the preparation of the original documents.
4.2 IMPLEMENTATION 4.2.1 Program A Nuclear Project Manager and a Nuclear Project Engineer is selected and a Project Team is formed under the Director, Nuclear Projects for each new nuclear power plant project.
The Northeast Utilities Service Company (NUSCO) Nuclear Project Engineer by procedure coordinates the prepara-tion, review and approval and control of NUSCO procure-l ment documents for Category I material, equipment, parts or services. The review and approval cycle of procure-ment documents initiated by NUSCO includes:
the appro-priate section of Generation Engineering for technical adequacy; the Manager, Quality Assurance for inclusion of quality assurance requirements, and the appropriate Project Manager.
A project engineer is selected for each modification to a nuclear power plant.
The project engineer coordinates the preparation, review and approval of procurement documents for Category I material, equipment, parts or services, and ensures the technical adequacy and inclu-sion of quality assurance requirements.
During the operations phase of nuclear power plants, Nuclear Plant Operating Companies (NUPOC) Purchase Requisi-tions are reviewed for technical adequacy and verifica-tion of the Category I designation. The appropriate NUPOC Superintendent reviews and approves Category I NUPOC Purchase Requisitions. Quality assurance personnel then review the purchase requisition for the inclusion and adequacy of quality assurance requirements.
During design, construction, preoperational testing and operation of nuclear power plants, and modifications QAP 4.0 Rev. 3 Date March 5, 1979 Page 1 of 4
thereto, the engineer-constructer, NUSCO contractors, suppliers and engineering service organizations utilized by NUSC0/NUPOC are responsible to implement measures for control of procurement documents associated with Cate-gory I material, equipment, parts and services to ensure applicable requirements including quality assurance requirements are specified. The NUSCO Quality Assurance Department performs on and off-site audits /surveillances/
inspections to ensure organizations utilized by NUSCO are effectively complying with their requirements for the control of procurement documents.
Changes to procurement documents, whether initiated by NUSC0/NUFOC or their representative, are subjected to the same degrce of control as that utilized in the prepara-tion of the original document. Procurement documents for the purchase of spare or replacement parts for safety related systems, structures and components are subject to controls equivalent to original code and standard require-ments or to subsequent code and standard revisions.
QA review of procurement documents determine that:
The quality requirements are correctly stated, a.
inspsetable and controllable; b.
There are adequate acceptance and rejection criteria; The procurement document has been prepared, reviewed, c.
and approved in accordance with the NU QA program tequirements.
4.2.2 Procurement Document Provisions Procurement documents cre preparod, reviewed and approved in accordance with approved procedures of the issuing crganization er department and are documented prior to release and available for verification. These procedures require that procurement documents consist of the follow-ing, as necessary:
The scope of work to be performed; a.
b.
Technical requirements (specified or referenced) including the applicable components and materials identification requirements, drawings, specifi-cations, procedures, instructions, codes and regula-tions, and provide for identification of applicable test, inspection and acceptance requirements, or special process instructions; QAP 4.0 Rev. 3 Date Page 2 of 4
Quality Assurance Program requirements to be imposed c.
on contractors which include the applicable require-ments of 10 CFR 50, Appendix B, and the NRC regula-tory pcsition contained in the Regulatory Guides and their endorsed ANSI Standards listed in Appendix D of this Topical Report; d.
Right of access which provides, as appropra ite, for access to contractor facilities and records for inspection or audit by NUSCO or its designated representative, and to access for events such as notification and hold points; e.
The documentation required to be prepared, main-tained, and/or submitted to NUSC0/NUPOC or its representative for review, approval or historical record. The time of submittal of this documentation and the retention and disposition of Quality Assur-ance records which are not submitted to NUSC0/NUPOC is prescribed.
4.2.3 Selection of Procurement Sources If the engineer-constructor, NUSCO contractor or supplier is not delegated the function of procurement source selection, the NUSCO Purchasing Department verifies that the procurement document has been reviewed and approved, and that the supplier has been approved for Category I procurement prior to issuing the purchase order for Category I material, equipment, parts and services.
Supplier approval is not required for the procurement of nonengineered items which are:
a.
Relatively simple and standard in design, manufac-ture, and test (i.e., off the shelf item, the catalog number is in effect, a specification which controls the manufacture of the item) and; b.
Adaptable to standard or automated inspections and/or tests of the end product to verify quality characteristics after delivery and; c.
Of such a nature that product acceptance inspec-tions/ test performed upon receipt of items do not require operations which could adversely affect the integrity, function,. or cleanness of the item.
Procurement documents may be issued to organization,4 with quality assurance programs that are unepproved, when approved by the NUPOC Superintendents, or the cognizant QAP 4.0 Rev.3 Date : March 5,1979 Page 3 of 4
Director or Superintendent within the Nuclear Engineering and Operations Group, and by the NUSC0/NUPOC Quality Assurance Departments who ensures procurement documents to unapproved organizations contain detailed supple-mentary quality assurance requirements to meet NUSCO requirements. Procurement' documents are reviewed by NUSC0/NUPOC Quality Assurance Departme.; to ensure appropriate quality assurance requirements are specified.
These requirements included in the procurement document as necessary, include audits and inspections at the suppliers facilities with scheduled witness / hold points and acceptance criteria during fabrication and process of the procurement item.
Acceptance inspections and tests determined by NU shall be performed af ter receipt at NU but prior to operation.
d QAP 4.0 Rev. 3 Date : March 5, 1979 Page 4 of 4
5.0 PROCEDURES, INSTRUCTIONS, AND DRAWINGS 5.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) provides measures for the preparation, review, approval, control and distribu-tion of procedures, instructions and drawings of activities affect-ing quality of Category I systems, structures and components during design, construction, preoperational testing and operation of nuclear power plants. These documents include appropriate quantita-tive and qualitative acceptance criteria which specify the activity to be performed, the methods of construction and testing to be employed, material, equipment or parts to be used, a sequence of operation and the required documentation.
5.2 IMPLEMENTATION Quality related procedures provide direction for personnel perform-ing safety related functions.
The Northeast Utilities Service Company (NUSCO) Manager, Quality Assurance / designee, reviews and concurs with quality related procedures originated by other depart-ments.
Con;ents concerning compliance with the NU QAP Topical Report and regulatory requirements are resolved. The Quality Assurance Department receives controlled copies of quality related procedures issued by other departments. During the design, construc-tion and procurament phases, the engineer-constructor, NUSCO contrac-tors, suppliers, and engineering service organizations may be delegated responsibility for preparing maintaining, issuing and verifying the implementation of appropriate program documents which are selectively reviewed / approved by the appropriate Nuclear Plant Operating Companies (NU?OC) Superintendent or NbSCO Site Manager /NUSCO Nuclear Project Engineer, as appropriate.
In this case, the Quality Assurance Department performs on-site and off-site audits / surveil-lances / inspections of the quality assurance programs to ensure the engineer-constructor, NUSCO contractor, suppliers and engineering service organizations are ef fectively complying with their require-ments for procedures and instructions.
Contractor programs are required to clearly delineate the actions to be accomplished in the preparation, review and control of procedures, instructions and drawings and the methods for complying with 10 CFR 50, Appendix B.
5.2.2 Procedures and Instructions Procedures and instructions for activities affecting quality are prepared, reviewed, and approved in accord-ance with written procedures and instructions.
During the design and construction phase, the NUSCO Site Manager /NUSCO Nuclear Project Engineer ensures that NUSCO contractors, suppliers and engineering service organi-QAP 5.0 Rev. 3 Date : March 5,1979 Page 1 of 2
zations implement quality assurance programs which contain written instructions for preparation, review and approval of procedures and instructions affecting quality.
In addition, Contractor's site quality related, construction procedures and quality control inspection procedures are reviewed for concurrence by the Quality Assurance Depart-ment to assure compliance with the Program.
The NUPOC organization is responsible, during the pre-operational test ano in-service phase, for the prepara-tion, review and approval of plant quality related pro-cedures. These procedures include preoperationa.! and startup test procedures which are prepared, reviewed and approved in accordance with an approved Startup Manual, and overall site administrative procedures which implement the requirements of the NU QAP. Each NUPOC organization is also responsible for the preparation, review and approval of procedures covering safety related activities in accordance with individual license requirements. The applicable NUSCO/KUPOC Quality Assurance Organizations reviews and concurs with inspection plans, test, calibra-tions and special process procedures, drawings and specifi-cations, and changes thereto.
5.2.3 Drawings The design control and verification measures described in QAP 3.0, are applicable for th-review and approval of drawings. The Nuclear Engineering and Operations Group, during design and construction phase, or the appropriate NUPOC Superintendent, during the preoperational test and in-service phase of the nuclear power plants, has the ultimate responsibility for review and approval of new drawings or modifications to existing drawings. The originating organization may delegate to other organi-zations or departments the work of design anu eview activities, or any part thereof, but retains uitimate responsibility for this work.
5.2.4 Acceptance Criteria Cognizant Department Heads review and approve depart-mental procedures, instructions and drawings to ensure the inclusion of adequate quantitative and qualitative acceptance criteria, as appropriate, for determining l
satisfactory work performance and quality compliance.
These criteria apply to activities such as design, operations, test control, inspection and plant modifications.
QAP 5.0 Rev. 3 Date March 5,1979 Page 2 of 2
6.0 DOCUMENT CG rROL 6.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) provides measures to assure controlled distribution of documents pertinent to Quality Assurance for the design, construction, preoperational testing, operation and major modification of nuclear power plant safety related systems, structures and components in accordance with NUSCUfNUPOC Quality Assurance Procedures and 10 CFR 50, Appendix B.
Documents such as procedures, instructions, drawings, specifica-tions and reports are prepared, reviewed for appropriate qualita-tive and quantitative acceptance criteria, and approved by authorized l
personnel in the affected organization. Approved controlled documents are distributed to affected locations in accordance with controlled distribution lists. Changes to controlled documents are reviewed l
and approved by the same organization which performed the original review and approval, unless otherwise specified in the implementing procedures. Measures are provided for controlling documents to preclude the possibility of the use of outdated documents.
6.2 IMPLEMENTATION 6.2.1 Responsibility NU Department Procedures and Instructions delineate the measures for controlling documents including direction for the review for adequacy, approval by authorized personnel, distribution of controlled documents and verification that changes are promptly incorporated and implemented. These control measures apply to documents affecting the quality of nuclear safety related systems, structures and components during design, construction, preoperational testing, operaticn and major modifications thereto such as:
a.
Design Specifications; b.
Design, Manufacturing, Construction and Installation Drawings; c.
Quality Assurance Program Manuals, Procedures and Instructions; d.
Manufacturing, Inspection and Testing Instructions; QAP 6.0 Rev. 2 Date : March 5, 1979 Page 1 of 3
e.
Test Procedures; f.
Preliminary Safety Analysis Report; g.
Facility Description and Safety Analysis; h.
Final Safety Analysis Report; i.
Design Chauge requests; k.
Topical Report; 1.
Nonconformance Reports; The requirements for control of procurement docu=ents are contained in QAP 4.0.
During all phases of plant life, it is the responsibility of each organization issuing controlled documents to employ document control proce-dures. The issuing organization is additionally responsi-ble for distribution of the documents to appropriate locations. There shall be provisions to assure that approved changes are included in instructions, proce-dures, drawings and other documents prior to implementa-tion of the changes.
During the design and construction phase, the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations are responsible for implementing measures for review, approval, control and distribution of controlled documents, to ensure they are effectively complying with the requirements for docu=en control.
The Quality Assurance Department performs periodic on-site and off-site audits /surveillances/ inspections of the engineer-constructor, NUSCO contractors, suppliers and engineering services organizations to verify compliance with their approved quality assurance programs.
6.2.2 Distribution of Controlled Documents NU Department Procedures, specify in what manner controlled documents and revisions thereof, are distributed to appre riate locations, prior to co==encing the work.
f 6.2.3 Drawing Control During the preoperational test and the in-service phases of nuclear power plants, the NU Nuclear Records Organization QAP 6.0 Rev.2 Date: March 5, 1979 Page 2 of 3
is responsible to implement a program, as per approved procedures, fer the retention and retrieval of drawings and records submitted by the cognizant NUSCO nuclear project Naclear Plant Operating Companies (NUP0C) personnel.
The NU N clear Records Organization maintains a drawing status ile for in-service units which includes drawings newly issueo or revised with latest revision and current status.
The engineer-constructor, NUSCO contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC during the design, construction and major modification to nuclear power plants may be delegated the function of drawing control and must furnish periedic status reports listing the revisions of applicable drawings which they issue.
The Quality Assurance Department performs on-site and off-site audits /surveillances/ inspections of suppliers to verify they are effectively complying with their programs for document control of drawings.
If the engineer-constructor, NUSCO contractor or supplier is not delegated the function of drawing control, the NUSCO Nuclear Project Engineer is responsible for the distribution of drawings to appropriate NUSCO/NUPOC personne: in accordance with controlled distribution lists.
6.2.4 Instructicn and Procedure Control During the design and construction phase, the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations are responsible for control of quality related procedures and instructions issued by them.
The Quality Assurance Department performs on-site and off-site audits /surveillances/ inspections of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations quality assurance programs to ensure they are effectively complying with their program for control of procedures and instructions.
During all phases of plant life, the originating NU department is responsible for establishing adequate control over quality related procedures and instructions issued by them. The responsible organization also issues status reports or revised indices listing the latest revision of applicable controlled documents issued by them.
QAP 6.0 Rev. 2 Date. March 5,1979 Page 3 of 3
7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 7.1 PURPOSE Measures for the control of procured material, equipment, parts and services by or for Northeast Utilities (NU) related to the safety of nuclear power plants are established and imposed by the Quality Assurance Program
..sP) during design, construction, preoperational testing, operation, maintenance and major modification, to ensure conformance to procurement documents. These measures include provisions for source evaluation and selection, submission of objective evidence by the contractor or sub-contractor, inspection at the supplier source and examination of items upon delivery.
Control of quality by contractors and sub-contractors is assessed for effectiveness at intervals consistent with the importance, complexity and quantity of the product or service.
7.2 IMPLEMENTATION The word supplier is used in this section to designate what is otherwise described as the engineer-constructor, NUSCO contractor, supplier and engineering service organization.
The evaluation and selection of suppliers is performed in accordance with procedures, which specify that procurement source evaluation and selection measures are performed to determine supplier capability and delineate responsibilities of qualified personnel involved in the evaluation and selection process.
7.2.1 NU Quality Assurance Department utilizes one or more of the following methods in evaluating the qualifications of a potential supplier:
a.
Coordinated review of a potential supplier utilizing one or more departments (i.e., Engineering, Construc-tion, Operations and/or Purchasing);
b.
Engineer constructor supplier evaluations; l
Coordinating Agency for Supplier Evaluation (CASE) c.
evaluations.
Evaluations ensure that NU suppliers employ a quality assurance program that conforms to applicable portions of the NU QAP Topical Report. Documented evidence of the evaluation and acceptance of the supplier's quality assurance program is retained in the Quality Assurance Department Record Center. The determination of supplier l
approval is based on such factors as prior performance, historical quality performance data, source surveys or audits and evaluations of the supplier's quality assurance program.
QAP 7.0 Rev. 2 Date: March 5, 1979 Page 1 of 3
Suppliers Certificates of Conformance are periodically evaluated by audits independent inspections and tests, to assure they are valid.
7.2.2 Source Inspection The NUSCO Quality Assurance Department is responsible for the performance of source inspections at suppliers facilities to ensure that the requirements of NUSCO Purchase Order /
Contract have been met.
Surveillances of suppliers are performed in accordance with written procedures which provide for:
a.
The method of surveillance and the extent of docu-mentation required and those responsible for implement-ing those instructions; b.
Surveillances of those items where verifications of procurement requirements cannot be determined upon receipt.
7.2.3 Receipt Inspection If the supplier is not delegated the function of receipt inspection for procured items, it is performed under the direction of the NUSCO Nuclear Project Engineer /NUPOC Quality Assurance Supervisor in accordance with quality procedures which delineate requirements and responsibili-ties necessary to perform inspection functions.
Contrac-tual obligation fulfillment and quality assurance require-ments are verified during receipt inspections.
Receiving inspection of supplier-furnished material, equipment, and services is performed to assure that material, components, equipment and acceptance records are inspected and judged acceptable in accordance with predetermined inspection instructions prior to installa-tion or use.
Receipt inspections include, as appro-priate:
a.
Measures for verifying that the shipment is complete, properly identified, undamaged and corresponds with the receiving documentation; b.
Measures for inspection of the item and review of supporting documentation (e.g., mill test reports, NDE reports) as required by the purchase documents; QAP 7.0 Rev. 2 Date : March 5, 1979 Page 2 of 3
c.
Measures for inspection and acceptance of items to inspection instructions; d.
Measures for identifying and controlling acceptable items including identification of inspection status prior to release from the receiving inspection area; Measures for identifying, segregating and handling e.
nonconforming items; f.
Measures to ascertain that inspection records or certificates of conformance are available prior to release to construction / plant for installation.
7.2.4 Supplier Furnished Records Records required to be furnished by the supplier are specified in the procurement document.
Certifications or documentation verifying conformance, provided by the supplier, identify that all the specific procurement requirements have been met (either by reference to the purchase order or by delineation).
The supplier must furnish the following records as a minimum:
a.
Documentation that identifies the purchased material or equipment and the specific procurement require-ments, (e.g., codes, standards and specifications) met by the items; b.
Documentation that identifies any procurement require-ments which have not been met, together with a description of those nonconformances dispositioned
" accept as is" or " repair" The responsible NU QA personnel shall review for accept-ability these documents which pertain to the requirements in the procurement document, in accordance with NU QAP and its applicable procedures.
QAP 7.0 Rev.2 Date : March 5, 1979 Page 3 of 3
8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS 8.1 GENERAL REQUIREMENTS During the operations phase, NUSC0/NUPOC organizations assure that the identification of inspections, tests, and operating status of structures, systems, and components is known by affected organ-izations.
The Northeast Utilities (NU) Quality Assurance Program (QAP) provides measures for the identification and control of Category I material, parts and components, including partially fabricated assemblies, during design, construction, preoperational testing, operation, maintenance and major modifications thereto.
To ensure that each item can be traced to associated documentation, the identification of the item is maintained by heat number, lot number, part number, serial number, or other appropriate methods, and is physically marked on the item and/or on records traceable to the item. Docu-mentation associated with material, equipment, and compovents verify that these items have been designed, fabricated, manufac-tured, tested, and inspected in accordance with specified require-ments. The object of these controls is to prevent the use of incorrect or defective material, parts and components, in accord-ance with 10 CFR 50, Appendix B.
8.2 IMPLEMENTATION NUSC0/NUPOC Procedures establish the responsibilities and require-ments for the identification and control of materials, parts and components. The procedures assure that identification and control is maintained throughout fabrication, receipt, handling, storage and installation of items. Provisions include:
a.
Requirements for traceability to appropriate documentation such as: procurement documents, manufacturing documents, dry ings, specifications, certifications, inspection and test re:ords, and nonconformance reports, b.
Controls to assure that the correct identification of an item is verified and documented prior to release for fabrication, assembly, shipping or installation.
c.
Requirements which assure that the method or location of markings do not affect the function or quality of an item.
d.
Establishment of identification requirements in specifica-tions, drawings, procurement documents, procedures or instruc-tions.
QAP 8.0 Rev. 3 Date : March 5, 1979 Page 1 of 2
During the design, construction, preoperational testing, operation, maintenance or modifications to auclear power plants / Northeast Utilities Service Company (NUSCO)/ Nuclear Plant Operating Companies (NUPOC) may delegate any portion of the implementation of the identification and control program to the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations, as appropriate.
If delegated, contracts require that the contrac-tor establish an identification and control pragram which meets the NU QAP requirements.
In this case the Quality Assurance Department /
NUP0C Quality Assurance perform on-site and off-site audits /surveillances/
inspections of the engineer-constructor, NUSCO contractors, sup-pliers, engineering service organizations and quality assurance program to ensure they are effectively complying with their require-ments for identification and control of material, equipment and components.
During the preoperational testing and the in-service phase of nuclear power plants, receipt inspections are performed to verify that material, equipment and components are properly identified in accordance with procurement requirements. Tbc NUP0C Quality Assur-ance Supervisor is responsible for assigning and applying permanent identification to the items in accordance with approved procedures.
If the application of a serial number is not practical, other means of identification are implemented to assure proper identification and traceability.
In the event that the equipment, material or components are noncon-forming or the identification becomes lost or illegible, the items are considered nonconforming are identified and controlled in accordance with QAP 15.0.
QAP 8.0 Rev. 3 Date : March 5, 1979 Page 2 of 2
9.0 CONTROL OF SPECIAL PROCESSES 9.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) provides measures to assure control of special processes associated with Category I systems, structures and co=ponents by the use of qualified, approved procedures, equipment and personnel during design, construc-tion, preoperational testing, operation, maintenance and cajor modifications to nuclear power plants.
Special processes are performed under controlled conditions in accordance with special requirements and may include, but are not limited to: welding, cleaning, heat treating, and nondestructive examination and/or testing.
9.2 IMPLEMENTATION During design and construction of nuclear power plants the Northeast Utilities Service Co=pany (NUSCO) Nuclear Project Engineer is re-sponsible for ensuring that special process data and docu=entation is reviewed, and that NUSCO contractors and/or engineering service organization's special process procedures utilized at nuclear power plants are qualified and approved, and that personnel and equipment utilizing special processes are properly qualified. The Nuclear Pl. ant Operating Companies (NUPOC) special process procedures utilized during preoperational testing, operation, maintenance, modification and refueling of the in-service nuclear power plant are prepared, reviewed and approved in accordance with procedures as specified in QAP 5.0.
During the design, construction, preoperational testing and operation phase of nuclear power plants the responsibility for control of special processes, when applicable, is delegated to the engineer-constructor, NUSCO contractors, suppliers and engineering service organizatioas utilizing special process procedures which are approved.
Personnel and equipment involved in special process procedures are qualified prior to the start of work. NUSCO Quality Assurance Department /NUPOC Quality Assurance personnel perform on-site and off-site audits /surveillances/ innspections to ensure the engineer-constructor, NUSCO contractors, suppliers, and engineering service organizations are effectively co= plying with their quality assurance program requirements for control of special processes.
9.2.1 Procedure Qualification and Control NU Departmental Procedures specify that written process control documents are utilized and qualified, as required, in accordance with applicable specifications, codes or standards.
QAP 9.0 Rev.3 Date : March 5,1979 Page 1 of 2
9.2.2 Personnel Qualification and Certification Codes, standards and NUSC0/NUP0C procedures specify personnel qualification / certification requirements.
Personnel responsible for the performance and verification of special processes are trained, tested, and certified as required by applicable specifications, codes and standards. Requirements for the period of certification, retesting, and recertification of personnel are also specified. Contractors qualify personnel and maintain records of qualified personnel in accordance with applicable codes, standards, specifications, and contract or procurement document requirements.
During construction, the NUSCO Nuclear Project Engineer is responsible for the review of records of qualified personnel, equipment and procedures associated with special processes. During preoperational testing and operation of nuclear power plants, the NUPOC Quality Assurance Supervisor is responsible for the review of these records.
9.2.3 Special Process Records Records provide objective evsience that special processes were performed in accordance with approved procedures, by l
qualified personnel, and that when required by procedures, specifications, and codes, such performance was verified.
Results of nondestructive examinations are recorded in accordance with applicable specifications, codes and standards. These records are retained by the supplier or l
supplied to NUSC0/NUPOC as required by contract or purchase orders.
If records are to be retained by the supplier, the contract or purchase order specifies the l
retention period and instructions for final disposition of records.
During construction, the NUSCO Nuclear Project Engineer is responsible for the review of documents for acceptance, and for assuring that documents for special processes utilized during construction are reviewed and accepted.
During preoperational testing and operation, the NUPOC Quality Assurance Supervisor is responsible for the review for completeness of data and documentation associated with the performance of special processes.
Special process documentation such as:
special process procedures, qualifying data, and personnnel and equipment qualification records associated wi'h the performance of special processes at nuclear power plants, are kept current and maintained in appropriate KUSC0/NUPOC files, with final disposition to the NU Nuclear Records Organiza-tion.
QAP 9.0 Rev.3 Date-. March 5, 1979 Page 2 of 2
10.0 INSPECTION 10.1 GENERAL REQUIREMENTS Inspection _ of activities to verify the, quality of Category I systems, structures and components, which are performed by or for Northeast Utilities (NU), are executed in accordance with the Quality Assu.-
ance Program (QAP) and appropriate procedures, instructions and drawings by qualified personnel independent from the individual or group performing the activity being inspected.
If inspection is impossible or disadvantageous, indirect controls by monitoring processing methods, equipment and personnel are provided.
Inspec-tion notification and hold points are identified, as required, in the applicable documents.
10.2 IMPLEMENTATION 10.2.1 Inspection Responsibilities During the construction phase, the Quality Assurance Department performs audits /surveillances/ inspections to verify that the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations are effectively complying with their quality assurance program requirements for inspection. The Quality Assurance Department also observes the performance of selected inspections on-site and at NUSCO contractors, suppliers and engineering service organizations facilities, associated with or specified as " hold" or " notification" points in procurement documents.
In all cases audit / surveillance /
inspection activities are performed as specified in written quality assurance procedures.
During the preoperational testing and the operations phase, qualified personnel representing NUSCO/NUPOC Quality Assurance shall review pr edures for maintenance and modifications in order to det..aine the need for.
a.
Inspections (e.g., receipt inspections, installation, system turnover, and product acceptance);
b.
Identification of inspection personnel; c.
Documentation of inspection results.
The NUSCO Quality Assurance Department / Nuclear Plant Operating Companies (NUPOC) Quality Assurance Supervisor performs audits /surveillances/ inspections to verify that NUSCO contractors, suppliers and engineering service organizations are effectively complying with their quality assurance program requirements for inspection and for QAP 10.0 Rev. 2 Date : March 5, 1979 Page 1 of 3
performing / witnessing inspections at " hold" or "notifi-cation" points identified in NUSCO procurement documents.
All audit / surveillance / inspection activities are performed under requirements specified in written quality assurance procedures.
10.2.2 Inspection Plans and Schedules Documented inspection plans may be either a separate document or an integral part of work instruction documents.
The plans are based on design specifications, procurement documents, drawings, other specifications, or previous experience, as appropriate.
Inspections are scheduled to assure that sufficient time and resources are available, and to assure inspections are not inadvertently omitted or bypassed.
10.2.3 Inspection Personnel and Inspection Document Access Inspections are performed by individuals other than a.
those who performed or directly supervised the activity being inspected.
Inspection personnel are qualified and/or certified in accordance with appro-priate codes, standards, and/or NU training programs; b.
Access to drawings, procedures, specifications or other documented criteria necessary for the perform-ance of inspections is provided prior to performing the inspection activity.
10.2.4 Inspection Procedures Required inspections, surveillance, or monitoring a.
activities are performed and documented according to written, approved procedures and/or checklists.
Inspection procedures or checklists contain the following:
(1)
Identificatien of characteristics to be inspected; (2)
Identification of the individual or groups responsible for performing the inspection; (3) Acceptance criteria; (4) A description of the method of inspection; (5) A record of the results of the inspection; (6) Record of inspector or data recorder.
QAP 10.0 Rev. 2 Date March 5,1979 Page 2 of 3
b.
Written approved procedures specify surveillance or monitoring of processing methods, or testing and operation of equipment when inspection is impossible, inaccessible or not applicable.
c.
Modification, repair, replacement or rework items are inspected in accordance with original inspection requirements or approved alternatives.
d.
During the preoperational testing and the operations phase, inspection procedures are reviewed by Quality Assurance personnel to determine the need for an independent inspection and the degree and method, if such an inspection is required, and to assure the identification if inspection personnel and the documentation of inspection results, for procedure review requiremeats, see QAP 5.0.
10.2.5 Mandatory Hold end Notification Points Mandatory hold pr.ints are utilized when an inspection /
operation must be performed or witnessed and signed-off by the responsible personnel before work can proceed. Notification points are used to identify the operations or completed processes that NUSC0/NUPOC or its representatives may elect to witness and/or inspect during the manufacturing, construction, installation process. Mandatory hold and notification points, as required, are identified in procurement documents and procedures. These documents are subject to the review and concurrence of the NUSCO Quality Assurance Department / NUPOC Quality Assurance for adequacy of inspection, notification and/or mandatory hold controls.
QAP 10.0 Rev. 2 Date: March 5, 1979 Page 3 of 3
11.0 TEST CONTROL 11.1 GENERAL REQUIREMENTS A documented test control program is established by the Quality Assurance Program (QAP) for Category I systems, structures and components to ensure that they will perform satisfactorily in service and that test results are documented in accordance with 10 CFR 50, Appendix B and other pertinent regulatory and/or technical requirements.
The test control program identifies the systems, structures and components to be tested, method of conducting tests, evaluation of tests and documentation of tests by qualified personnel to assure requirements have been satisfied.
The test control program is systematic and includes proof test prior to installation, construction tests, preoperational tests, surveillance tests, start-up tests and retest following repairs, replacement or modification.
11.2 IMPLEMENTATION 11.2.1 Test Program Test requirements to determine or to verify the capability of an item to meet specified requirements in accordance with engineering / design documents, Safety Analysis Reports (SAR), technical specifications, procedures or procurement documents, as appropriate, are accomplished by subjecting the item 13 a set of physical, chemical, environmental or operating conditions. Retest following repairs, replace-ment or modification is performed in accordance with the original design requirements or acceptable alternatives and is performed when original test results are invalidated.
Northeast Utilities (NU) Departmental Procedures are written and approved to delineate the methods and respon-sibilities for controlling, accomplishing and documenting testing during the construction, preoperational testing, maintenance, operation and modification of nuclear power plants.
During design, construction, preoperational testing, operation, maintenance and modification to nuclear power plants the engineer-constructor, Northeast Utilities Service Company (NUSCO)/ Nuclear Plant Operating Companies (NUPOC) contractors, suppliers and engineering service organizations, as appropriate, are responsible for imple-QAP 11.0 Rev.1 Date : March 5,1979 Page 1 of 3
menting measures for the control of tests to ensure that Category I material, equipment and parts will perform satisfactorily. The Quality Assurance Department performs on-site and off-site audits /surveillances/ inspections of selected proof tests when " notification" points have been identified in Purchase Order / Contracts of the engineer-constructor, NUSC0/NUPOC contractors, suppliers and engineering service organizations to verify they are complying with their quality assurance program requirements for test control. Documentation associ.ated with these observations are maintained by the Quality Assurance Department.
During the preoperational testing phase of nuclear power plants, preoperational and startup testing is conducted by qualified personnel in accordance with procedures prepared, reviewed and approved in conformance to a NUP0C startup manual.
During the in-service phase of nuclear power plants proof tests, product acceptance tests, retest, and periodic surveillance tests are conducted by qualified personnel in accordance with approved procedures.
Personnel perform-ing tests ensure that calibrated equipme1t and instrument-ation utilized are within the calibration interval speci-fied. Documentation including test proceiures and approved data sheets are maintained in appropriate files.
11.2.2 Test Procedure Preparation and Test Performance Testing is accomplished in accordance with approved test procedures which incorporate or reference the require-ments and acceptance criteria in the applicable design and procurement documents. The test procedure or test program documents include the following as a minimum:
a.
Instructions for the testing method used; b.
Required test equipment and instrumentation; c.
Test requirements, such as acceptance and rejection criteria; d.
Hold, notification, inspection and data collection points; e.
Test prerequisites such as:
calibrated instrumenta-tion; trained, qualified, and licensed or certified personnel; preparation, condition and completeness of item to be tested; suitable and controlled environ-mental conditions; QAP 11.0 Rev.1 Date : March 5, 1979 Page 2 of 3
f.
Methods for documenting or recording test data and results; g.
Provisions for data collection and storau-11.2.3 Evaluation of Test Resul_tg The documented test results are evaluated against the predetermined acceptance criteria by an individual or group having appropriate qualifications.
The acceptance status of the test is documented. Deficiencies noted during the evaluation are documented and dispositioned in accordance with approved procedures.
The evaluation of test results may also be delegated to other organizations.
The evaluating organization is required to assure the use of qualified personnel, evaluate the data against predetermined criteria and document the results of the evaluation and acceptance status of the test.
The Quality Assurance Department performs audits / surveil-lances / inspections to verify that these organizations are ef fectively complying with their quality assurance program requirements for test control.
QAP 11.0 Rev.1 Date : March 5, 1979 Page 3 of 3
12.0 CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) provides measures for the control of measuring and testing equipment (M&TE) used as the basis for acceptance in activities affecting quality during inspection, testing and measurement of Category I material, equipment and parts. Periodic calibration and adjustment of measur-ing and test equipment 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 '*-me af M&TE are traceable to their calibration records.
12.2 IMPLEMENTATION 12.2.1 During the preoperational testing and the in-service phase of nuclear power plants, approved procedures delineate the methods and responsibilities for the control, maint-enance and calibration of M&TE.
All documentation associated with M&TE is maintained in appropriate files, with eventual incorporation into the NU Nuclear Records Organization.
The engineer-constructor, NuSCO contractors, suppliers and engineering service organizations utilized by NUSC0/NUP0C during the design, construction, operation, mai.-tenance and modification of nuclear power plants, as appropriate, are responsible for implementing measures for the control of M&TE to ensure they are properly calibrated, adjusted and maintained at specified intervals in order to maintain accuracy within required limits. The NUSCO Quality Assurance Department / NUPOC Quality Assurance Supervisor performs on-site and off-site audits /surveillances/inspec-tions of the quality assurance programs of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations to verify they are effectively complying with their requirements for control of M&TE.
12.2.2 Calibration Standards Measuring and test instruments are calibrated at speci-fied intervals based on the required accuracy, purpose, degree of usage, stability characteristics, and other conditions affecting the measurement. Measuring and test instruments shall be labeled or tagged to indicate the date calibrated and next calibration date.
Measuring and QAP 12.0 Rev. 2 Date : March 5, 1979 Page 1 of 2
test equipment is calibrated at specified intervals based on the required accuracy, purpose, degree of usage, stability characteristics, and other conditicns affecting the measurement.
Calibration of this equipment should b2 against standards that have an accuracy of at least four times the required accuracy of the equipment being calibrated or, when this is not possible, have an accuracy that assures the equipment being calibrated will be within required tolerance and that the basis of acceptance is documented and authorized by responsible management.
In addition, the calibrating s tandards 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 and authorized by responsible management.
Implementing procedures describe the measures utilized in order to maintain the proficiency of the measuring and test equipment.
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 review is conducted to determine the validity of previous inspec-tien or test results gained through use of the instrument, and of the acceptability of items previously measured or tested.
QAP 12.0 Rev. 2 Date March 5, 1979 Page 2 of 2
13.0 HANDLING, STORAGE AND SHIPPING 13.1 GENERAL REQUIREMENTS Measures are established by the Northeast Utilities Quality Assurance Program using approved procedures, instructions and procurement documents to ensure proper handling, storage, shipping, cleaning and preservation of Category I material, equipment and parts.
These measures are imposed during the design, procurement, construc-tion, preoperational testing and operation of nuclear pcwer plants and major modifications thereto, in order to preclude damage, loss or deterioration of material, equipment and parts.
13.2 IMPLEMENTATION 13.2.1 General Procedures, instructions and procurement documents define the requirements and responsibilities for the handling, storage, shipment, cleanino and preservation of Category I material, equipment and parts, and required implementa-tion of established design and specification require-ments.
During design and construction the responsibilities associated with handling, storage, shipment, cleaning and preservation of Category I material, equipment and parts may be delegated to the engineer-constructor, NUSCO contracters, suppliers and engineering service organizations.
These organizations are monitored through audits / surveil-lances / inspections by the Quality Assurance Department to verify compliance with their quality assurance program requirements for handling, shipping, cleaning and preserva-tion.
Handling, storage, cleaning and preservation requirements of material, equipment and parts is conducted in accordance with written procedures and procurement documents during the preoperational testing and the in-service phase nuclear power plants. The Nuclear Plant Operating Companies may utilize NUSCO contractors, suppliers, and engineering service organizations during the operation, maintenance and modification of the in-service nuclear power plant.
These organizations are responsible for implementing measures for handling, storage, shipping, cleaning and preserving Category I material, equipment and parts to preclude damage, loss or deterioration. The Quality Assurance Department performs audits /surveillances/
inspections to verify that NUPOC, and NUSCO contractors, suppliers and engineering service organizations are QAP 13.0 Rev.1 Date March 5,1979 Page 1 of 2
effectively implementing and complying with their approved procedures and instructions for handling, storage, shi; ping, cleaning and preservation of Category I material, equipment and parts.
13.2.2 Establishment of Special Handling, Storage, Thipping, Cleaning and Preservation Requirements Special or additional handling, storage, shipping, clean-ing and preservation requirements are to be identified and implemented as specified in procurement documents and approved procedures. These established requirements are consistent with the regulatory positions of the NRC Regulatory Guides and their endorsed ANSI Standards, listed in Appendix D of the Topical Report, or specifi-cations and/or suppliers technical manual, and will be consistent with accepted industry standards.
QAP 13.0 Rev. 1 Date. March 5,1979 Page 2 of 2
14.0 INSPECTION, TEST AND OPERATING STATUS 14.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) provides measures for indication, by the use of marking such as stamps, tags, labels or other suitable means, the status of tests and inspections of Category I material, equipment and parts throughout design, construction, preoperational testing, operation, maintenance and modification of nuclear power plants, to preclude the inadvertent bypassing of inspection and test requirements. These measures provide for the identification of items which have satisfactorily passed required inspections and tests.
Measures are also established for indicating the operating status of systems, structures and components to prevent inadvertent operation.
14.2 IMPLEMENTATION 14.2.1 General The engineer-constructor, NUSC0/NUPOC contractors, suppliers and engineering service organizations utilized by NUSC0/NUPOC during design, construction, preoperational testing, operation, maintenance and modification of nuclear power plants, as appropriate, are responsible for implementing approved measures for the identification of inspection and test status of Category I materials, equipment and parts to preclude the bypassing of require-ments. The NUSCO Quality Assurance Department /KUPOC Quality Assurance Supervisor performs on-site and off-tite audits /surveillances/ inspections of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations to verify that they are effectively omplying with their requirements for identification of inspection and test status, in compliance with approved procedures and instructions.
Elements of this system require that suppliers and contractors have a controlled manufacturing and test operation, in order to preclude the inadvertent bypassing of process inspections or tests, and to prov_de a positive identification of component status throughout all phases of manufacturing, testing, and inspecting by means of tagging, routing cards, stamping, manufacturing or test reports, labeling cr other appro-priate methods.
Where NUSCO/NUPOC performs receipt inspections at nuclear power plants, the NUSCO Nuclear Project Engineer (during plant construction) or the NUPOC Quality Assurance Supervisor (during preoperational testing phase and at in-service plants), ensures that traceability is maintained of QAP 14.0 Rev.1 Date : March 5, 1979 Page 1 of 2
acceptable material, equipment and parts, to indicate conformance to NUSCO Purchase Order / Contract requirements.
Nonconforming material, equipment and parts are identified in accordance with QAP 15.0.
During tests and inspections of operating nuclear power plants a status tagging system is implemented, as per approved procedures and instructions, to prevent inadver-tent operations of Category I systems, structures and components.
14.2.2 Status Identification and Control Procedures and instructions describe control of the application and removal of markings such as stamps, tags, labels and other suitable means to indicate the status of safety related systems, strcctcres and components to prevent inadvertent operation, and t' preclude omission of inspections, tests or other critical operations.
These procedures and instructions delineate the require-ments, methods and responsibilities for indicating the status of the affected items. The complete status of all items under the calibration system is recorded and maintained.
Records associated with status identification are main-tained in accordance with approved procedures.
QAP 14.0 Rev.1 Date March 5,1979 Page 2 of 2
15.0 NONC0hTORMING MATERIALS, PARTS OR COMPONENTS 15.1 General Requirements The NU Quality Assurance Program requires that documentation and control of nonconforming material, parts or components utilized in Category I systems, structures and components during design, con-struction, preoperational testing, operation and maintenance of nuclear power plants and major modifications thereto, be performed in accordance with approved procedures in order to prevent inad-vertent use or installation. These procedures include appropriate requirements for identification, documentation, segregation and disposition of nonconforming items, and notification to affected organizations.
In accordance with procedures, nonconforming material, parts or components are reviewed and a ;cepted, rejected, repaired or reworked.
15.2 Implementation 15.2.1
,P_ro g ram Approved procedures define the responsibilities and establish measures for identification, documentation, segregation, review and disposition of nonconforming materials, parts or components, and notification to affected organizations. Each Northeast Utilities de-partment is responsible for the identification, control and disposition of nonconformances within the scope of their departmental responsibilities.
The NUSCO Quality Assurance Department /NUPOC Quality Assurance Supervisor performs on-site and off-site audits /surveillances/ inspections of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations to verify these organizations are effectively complying with their quality assurance program requirements for documentation and control of nonconforming material, parts or components.
15.2.2 Documenting and Controlling Nonconformances Nonconformances of Category I systems, structures and components are documented and reported as requiring corrective action. Approved procedures delineate controls required for further processing, installation and opera-tion of nonconforming items. These controls include:
a.
Physical identification of the material, part or component as nonconforming; QAP 15.0 Rev. 2 Date : March 5,1979 Page 1 of 3
b.
Segregation of nonconforming items until properly dispositioned. Where physical separation is not practical, suitable tags, markings and documentation are used to assure control.
15.2.3 Documentation Documentation of nonconforming items requires identifi-cation of the items, description of the nonconformance, disposition of the nonconformance, inspection require-ments and signature approval of the disposition. A trend analysis of nonconformances is performed, as necessary and results are reported to appropriate level of manage-ment.
An engineering evaluation is performed, if necessary, prior to the resolution of nonconformances relating to Category I systems, structures and components.
15.2.4 Evaluation and Disposition Evaluations are performed to determine the disposition of nonconforming items. The evaluation determines whether an item is to be accepted as-is, returned to supplier, repaired, reworked, scrapped or salvaged' These evalua-tions assure that the final condition does not adversely affect safety, operation or maintenance of the item, or of the component or system in which it is installed.
Applicable information is accumulated and records are maintained.
The engineer-constructor, NUSCO contractors or NUPOC personnel are required to report to the NUSCO Site Manager /
NUSCO Nuclear Project Engineer or the appropriate NUPOC Superintendent, as applicable, to obtain release of nonconformance item prior to its installation. These release items are identified by a Nonconformance Tagging System which defines the description of the nonconform-ance and its nonconformance status. Nonconformance reports dispositioned " accept as is" or " repair" are forwarded to the NUSCO Nuclear Project Engineer, NUSCO Site Manager or the appropriate NUP0C Superintendent, and NUSCO/NUP0C QA Organizations, as applicable, for review and approval, and then made part of the materials receipt inspection records.
The need to release nonconforming material, parts or components shall be based on such considerations as:
a.
Impact on plant safety; QAP 15.0 Rev. 2 Date March 5,1979 Page 2 of 3
b.
Safety of personnel; c.
Suitability of material or items in the "as-is" condition, i.e., probability of eventual satis-factory resolution of the nonconformity without repair, rework or replacement; d.
Accessibility of material or items after release; e.
Cost of removal and repair or replacement should material or items eventually have to be removed, repaired, or replaced; f.
Effect.on the orderly progress of work.
Items reworked or repaired in accordance with procedures are verified by reinspecting the item as originally inspected or by a documented method which is equivalent to the original inspection method.
QAP 15.0 Rev. 2 Date : March 5, 1979 Page 3 of 3
16.0 CORRECTIVE ACTION 16.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) provides dccumented measures for corrective action to ensure that nonconform-ing Category I systems, structures and components are identified and promptly corrected. These measures shall include, as appro-priate, procedures for identification, documentation, segregation, disposition, notification to affected organizations and follow-up to prevent recurrence. Nonconforming items shall be reviewed and accepted, rejected, repaired or reworked in accordance with approved procedures.
16.2 IMPLEMENTATION 16.2.1 Corrective Action and Follow-Up Evaluation of conditions adverse to quality such as, nonconformances, failures, malfunctions, deficiencies, deviations, and defective material and equipment is conducted to determine the need for corrective action in accordance with established procedures.
During design, construction, preoperational testing and eperation of nuclear power plants, the engineer-tanstructor, NUSCO contractors, suppliers, engineering service organizations and their subtier contractors, utilized by NUSCO/NUPOC), and NU personnel are responsible for informing the NUSCO Vice President Nuclear Engineering and Operations, through their respective chains of command, of significant conditions which are adverse to quality, the cause of the condition and the corrective action taken. A reaudit to verify in.plementation of corrective action and close-out of corrective action documentation shall be accomplished by the original auditing organization.
The Quality Assurance Department or NUPOC QA, as appro-priate, identifies deficiencies by audits /surveillances/inspec-tions of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations quality assurance programs for corrective action, and Quality Assurance Department /NUPOC Quality Assurance Supervisor, as necessary, reaudits to verify that corrective action has been properly implemented.
The NUSCO Quality Assurance Department /NUP0C Quality Assurance Supervisor performs internal audits to identify def 4 -ncies in departmental corrective action programs.
The,propriate NUSCO Department Director / Manager or the QAP 16.0 Rev. 3 Date : March 5, 1979 Page 1 of 2
appropriate NUPOC Superintendent, is responsible to implement timely corrective action. The NUSCO Quality Assurance Department /NUPOC Quality Assurance Supervisor may reaudit the affected department to verify corrective actica has been implemented and documented.
If corrective action is inadequate or not timely, the follow-up organization requests corrective action from management as delineated in procedures. The NUSCO Exec-utive Vice President of Engineering and Operations has the final authority in the event that agreement is not reached at lower levels.
Where corrective action is required of contractor per-sonnel, NUSC0/NUP0C defines in procedures and contracts the corrective action interface between NUSC0/NUPOC and the contractor.
NUSC0/NUPOC requires the engineer-constructor, NUSCO contractor, suppliers and engineering service organizations, as appropriate, to have a documented corrective action program for safety related materials and services.
16.2.2 Recurrence Control The organization which is responsible for che condition adverse to quality, should ensure that the corrective action shall not only correct the immediate condition, but also prevent the adverse condition from recurring.
QAP 16.0 Rev. 3 Date : March 5,1979 Page 2 of 2
17.0 QUALITY ASSURANCE RECORDS 17.1 GENERAL REQUIREMENTS The Northeast Utilities (NU) Quality Assurance Program (QAP) pro-vides for the maintenance, identification, retention and retrieval of records to furnish evidence of activities affecting quality during design, construction, preoperational testing, operation, maintenance and modification of nuclear power plants. The records include but are not limited to:
operating logs and the results of reviews, inspections, tests, audits, monitoring of work performance and material analyses. The records also include closely related data such as qualifications of personnel, procedures and equipment.
inspection and test records contain as a minimum but are not limited to:
identification of inspector or data recorder and the accepta-bility and the action taken in connection with any deficiencies, and Reportable Occurrences noted. Approved procedures establish requirements concerning record retention such as duration, location and assigned responsibility.
17.2 IMPLEMENTATION NU Departmental Procedures and Instructions establish the respon-sibilities and requirements for the maintenance, identification, retention and retrievability of records pertaining to the quality of material, equipment, parts, processes or operations relating to Category I systems, structures and components which when founded on observations, measurements or tests can be fully verified, and documented by cognizant personnel.
During design, construction, preoperational testing, operation, maintenance and modification of nuclear power plants the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations, as appropriate, utilized by NUSCO/NUPOC are respon-sible to implement measures for identification, maintenance, reten-tion, retrieval and turnover, to the NUSCO Nuclear Project Engineer /
Cognizant NUPOC personnel, of documented and approved records which contain objective evidence of quality, as specified in NUSCO Purchase Order / Contracts. The NUSCO Quality Assurance Department /NUP0C Quality Assurance Supervisor performs on-site and off-site audits /
surveillances/ inspections of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations, as appropriate, to verify they are effectively complying with their program for quality assurance records.
During the preoperational testing and in-service phase of nuclear power plants NUSC0/NUPOC quality records are identified, controlled and maintained in appropriate files and are identifiable to specific systems, structures and components within the nuclear power plant.
QAP 17.0 Rev.2 Date March 5,1979 Page 1 of 2
When identification to a specific system, structure or component is not practical, records are filed by category; (e.g. specification, nonconformance reports, audits, etc).
17.3 RETENTION NU Quality Assurance records are, classified as life records or non-life records as delineated by the NU Nuclear Records Organiza-tion. Non-life records are those quality documents that are main-tained for a specific period of time other than the life time of the in-service nuclear power plant or the particular component or part.
Life records are those quality documents that are maintained for the lifetime of the in-service nuclear power plant or for the life of the particular component or part.
Life records are those which would be of significant valu in meeting one or more of the following criteria:
Demonstrating capability for safe operation; a.
b.
Maintaining, reworking, repairing, replacing or modifying the item; Determining the cause of an accident or malfunction of an c.
item; d.
Providing required base line data for in-service inspection.
Records are reviewed and approved by the NUSCO Nuclear Project Engineer or other cognizant qualified personnel of NUSCO/NUPOC, engineer-constructor, etc., as appropriate, and are transmitted to the NU Nuclear Records Organization. The responsibility of the NU Nuclear Records Organization, upon receipt of records, is to maintain and provide controlled retreivability of records affecting the, quality of nuclear power plants, in such a manner as to preve.t destruction of records by fire, flood, theft, and environment al conditions, such as temperature or humidity, as delineated in procedures.
QAP 17.0 Rev.2 Date : March 5, 1979 Page 2 of 2
18.0 AUDITS 18.1 GENERAL REQUIREMENTS The NU Quality Assurance Program requires that measures be provided to implement an effective audit program. These measures are applied during the design, construction, preoperational testing and operation of nuclear power plants and major modifications thereto, through the performance of audits. Audits are conducted in accordance with preestablished procedures and written checklists by qualified personnel not having direct responsibilities in the areas being audited to ensure compliance with the NU QAP Topical Report. The results of audit findings are documented and then reviewed with management having responsibility in the area audited.
18.2 IMPLEMENTATION 18.2.1 Program Eight (8) types of audits relating to the QAP are performed:
a.
Ncrtheast Utilitieu Service Company (NUSCO) Internal Aadits; (annual audits of the 18 criteria of Appendix B to 10CFR, Part 50.
b.
NUSCO Off-site Engineer-Constructor, Contractor, Supplier, and Engineering Service Organization Audits; (as per procurement documeats) c.
NUSCO Construction Site Audits; (at ually or as applicable by the procurement docut nts) d.
NUSCO Preoperational Testing Audits; (as per test schedule) e.
NUSCO Plant Audits; (annual audits of the 18 criteria of Appendix B 10CFR Part 50) f.
Nuclear Plant Operating Companies (NUPOC) In-Plant Preoperational Test Audits; (as per test schedule) g.
NUP0C Internal In-Plant Audits; (annuai audits of the 18 criteria of Appendix B, 10CFR, Part 50 and selected criteria semi-annually) h.
NUPOC Contractor, Supplier and Engineering Service Organization Audits. (as per the procurement document)
QAP 18.0 Rev.3 Date March 5,1979 Page 1 of 4
In addition, provisions are established to require that audits be performed of those activities where the re-quirements of Appendix B to 10 CFR, Part 50, are being implemented, and associated with:
a.
The determination of site features which affect plant safety (e.g., core sampling, site and founda-tion preparation, and meteorology);
b.
The preparation, review, approval and control of early procurements; c.
Indoctrination and training programs; d.
Interface control among the licensee and the prin-cipal contractors.
Measures are provided to perform audit of those safety-related activities performed during the operational phase. Those areas are listed below:
a.
Operation, maintenance, and modifications; b.
The prepiration, review, approval and control of design documenta, specifications, procurement documents and instructions, procedures and drawings; c.
Receiving and plant inspections; d.
Indoctrination and training programs; e.
The implementation of operating and test procedures; f.
Calibration of measuring and test equipment.
Audits are scheduled on the basis of the status and safety importance of the activities being performed.
Schedules are originated and maintained by the NUSCO Quality Assurance Department or the NUPOC Quality Assur-ance Supervisor.
NUSCO/NUP0C audits are performed as specified in pro-cedures by qualified personnel using a preestablished written audit plan prepared by the auditing organization.
Auditors evaluate work areas, activities, processes, items; review documents and records to determine the effectiveness of implementation and conformance to the NU QAP.
QAP 18.0 Rev. 3 Date : March 5, 1979 Page 2 of 4
NUSCO QA audits are performed of the NUPOC QA organiza-tion audit functions. This includes a review and assess-ment of the audit plan, audit report, corrective action, follow-up activities and NUP0C QA Records made available to NUSCO QA.
The results of NUPOC QA Audits are also submitted for inclusion in the NUSCO QA Quarterly Report, and presented to NU management.
The engineer-constructor, NUSCO contractors, suppliers and engineering service organizations utilized during the design, construction, preoperational testing and operation of nuclear power plants and major modifications thereto, are responsible for developing and implementing a system of planned and periodic audits to verify compliance with and the effectiveness of all aspects of their quality assurance programs including reporting and resolution of deficiencies. The hUSCO Quality Assurance Department /
NUPOC Quality Assurance personnel performs on-site and off-site audits /surveillances/ inspections to ensure these organizations are complying with their quality assurance requirements for audits, effectively.
Departments within the NUSCO and NUPOG arganizations are responsible for implementing quality related functions in accordance with approved procedures and instructions.
The Quality Assurance Department a..d the NUPOC Quality Assurance Supervisor, as applicable, perform internal audits to verify implementation of the requirements prescribed in the NU QAP Topical Report and implementing departmental procedures.
18.2.2 Review of Audit Findings Audit results are documented, reviewed, and analyzed with managemer.t having responsibility in the area audited.
The responsible management is required to take the neces-sary action to correct the deficiencies revealed by the audit.
18.2.3 Reporting of Audit Results Audit results are reviewed and approved by the Manager, Quality Assurance or the appropriate NUFOC Superiaten-dent, as applicable.
These individuals are responsible, based on the audit documentation, for issuing the audit reports to the appropriate management of the area audited and for ensuring that timely corrective action is taken to rectify deficiencies.
In addition, audit data and reports are eccumulated quarterly and reported to manage-ment for the review and assessment of quality trends and the effectiveness of the quality assurance program.
QAP 18.0 Rev. 3 Date March 5,1979 Page 3 of 4
18.2.4 Resolution of Audit Deficiencies Appropriate action to resolve deficiencies identified during NUSCO/NUPOC audits is to be taken by the cognizant engineer-constructor, NUSCO contractor, supplier, engineer-ing service organization or internal NUSCO/NUPOC management before the scheduled resolution date. Follow-up audits are performed as necessary, to verify appropriate actions have been taken to resolve deficiencies. Unresolved items which exceed the scheduled cesolution date and cannot be resolved by affected management are submitted for resolution to the NUSCO Vice President Nuclear En-gineering and Operations.
18.2.5 Records / Reports of Audits Audit records, reports and associated documentation pertinent to audits are maintained in the appropriate NUSC0/NUPOC files with disposition to the NU Nuclear Records Organization, as specified in procedures.
QAP 18.C Rev. 3 Date : March 5, 1979 Page 4 of 4
APPENDIX A CATEGORY I SYSTEMS, STRUCTURES, AND COMPONENTS The following systems, structures and components of a nuclear power plant, including their foundations and supports, are designated as Category 1.
The pertinent quality assurance requirements of Appendix B to 10 CFR Part 50, should be applied, as a minimum, to all quality related activities affecting the safety related function of these systems, structures and components as listed below and to other items and services specifically identified by NU in Section 3 of each license application submitted to the NRC.
(a) The reactor coolant pressure boundary.
(b) The reactor core and reactor vessel internals.
(c) Systems or portions of systems that are required for (1) emergency core cooling; (2) post-accident containment heat removal or; (3) post-accident containment atmosphere cleanup (e.g., hydrogen removal system).
(d) Systems or portions of systems that are required for (1) reactor shutdown; (2) residual heat removal or; (3) cooling the spent fuel storage pool.
(e) Those portions of the steam systems of boiling water reactors extending from the outermost containment isolation valve up to but not including the turbine stop valve, and connected piping of 2-1/2 inches or larger nominal pipe size up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
(f) Those portions of the steam and feedwater systems of pressurized water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves, and connected piping of 2-1/2 inches or larger nominal pipe size up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
(g) Cooling water, component cooling and auxiliary feedwater systems or portions of these systems including the intake structures, that are required for (1) emergency core cooling; (2) pcst-accident con-tainment heat removal; (3) post-arcident containment atmosphere cleanup; (4) residual heat removal from the reactor or; (5) cooling the spent fuel storage pool.
QAP - Appendix A Rev.
2 Date March 5, 1979 Page 1 of 3
(h) Cooling water and seal water systems or portions of these systems that are required for functioning of reactor coolant system com-ponents important to safety, such as reactor coolant pumps.
(i) Systems or portions of systems that are required to supply fuel for energency equipment.
(j) All electric and mechanical devices and circuitry between the process and the input terminals of the actuator systems involved in generating signals that initiate protective actuation of safeguard systems.
(k) Systems or portions of systems that are required for (1) monitoring of systems important to safety and; (2) actuation of systems impor-tant to safety.
(1) The spent fuel storage pool structure, including the fuel racks.
(m) The reactivity control system (e.g., control rods, control rod drives, and boron injection system).
(n) The control room, including its associated equipment and all equip-ment needed to maintain the control room within safe habitability limits for personnel and safe environmental limits for vital equip-ment.
(o) Primary and secondary reactor containment.
(p) Systems other than radioactive waste management systems not covered by items (a) through (o) above which contain or may contain radio-active materials and whose postulated failure would result in conservatively calculated potential offsite doses (using meteor-ology as prescribed by Regulatory Guides 1.3 and 1.4) which are more than 0.5 rem to the whole body or its equivalent to any part of the body.
(q) The Class IE electric systems, including the auxiliary systems for the onsite electric power supplies, that provide the emergency electric power needed for functioning of plant features included in items (a) through (p) above.
(r) Those portions of systems, structures <r components whose continued function is not required but whose fai.are could reduce the fun -
tioning of any plant feature included in items (a) through (q) above to an unacceptable safety level or could result in incapa-citating injury to occupants of the control room should be designed and constructed so that the SSE would not cause such failures.
QAP - A pendix A Rev.
Date March 5,1979 Page 2 of 3
CONSUMABLES The following specific consumables when utilized in safety related systems shall be included in those portions of the NU QAP, as applicable.
1.
Emergency generator diesel fuels 2.
Hydraulic snubber fluids 3.
Reagents 4.
Resins QAP - Appendix A Rev. 2 Date March 5,1979 Page 3 of 3
APPENDIX B NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT QUALIFICATION AND EXPERIENCE REQUIREMENTS NUSCO MANAGER QUALITY ASSURANCE
Title:
Manager, Quality Assurance Shall satisfy one of the following sets of requirements:
A)
Graduate of a four year accredited engineering or science college or university, plus four years of industrial exper-ience including three 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 facilities. A masters degree in engineering or business management is considered equivalent to two years of experience.
B)
Completion of college level work leading to an associates degree in a related discipline plus eight years of industrial experience including three years in positions of leadership, such as project engineer, audit team leader, supervisor, etc.
At least five years of this experience should be associated with nuclear facilities.
C)
High school graduate, plus twelve years of industrial experience, including three years in positions of leadership, such as project engineer, audit team leader, supervisor, etc.
At least five years of this experience should be associated with nuclear facilities.
Note:
The education and experience requirements should not be treated as absolute when similar training or an outstanding record will provide reasonable assurance that a person can perform the required tasks.
QAP - Appendix B Rev. 1 Date : March 5, 1979 Page 1 of 1
APPENDIX C NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT LIST OF QUALITY ASSURANCE PROCEDURES INDEX Pages NUSCO Quality Assurance Procedures 2-4 NUSCO Nuclear Production Procedures 5
NUSCO Nuclear Projects Procedures 6-9 Millstone Administrative Control Procedures 10-11 Connecticut Yankee QA Procedures 12-14 NUSCO Nuclear Plant Records Manual (NPRM) 15 NU Welding Manual 16 NU Purchasing Business Procedures 17 QAP - Appendix C Rev.
1 Date: March 5, 1979 Page 1 of 17
Sheet 1 of 3 NUSCO QUALITY ASSURANCE PROCEDURES NUSCO APPENDIX B TO 10CFR PART 50 QA PROCEDURES I.
Organization 1.01 QAD Organization & Qualification of Personnel II.
Quality Assurance Program 2.01 Preparation, Issuance & Control of NUSCO Quality Assurance Dept. Proc.
2.02 Northeast Utilities Quality Assurance Orientation and Training Program 2.03 Preparation, Issuance & Control of the Northeast Utilities Quality Assurance Manual 2.04 Review of h0SCO/NUPOC Quality Documents 2.07 Preparation of Prcject Ouality Plans 2.08 Training & Qualifications of NUSCO Quality Assurance Auditors &
Surveyors 2.09 Selection, Training, Qualification
& Certification of NUSCO & NUPOC Inspection Testing & Examination Personnel 2.10 Quality Assurance Department Orientation & Training Program III. Design Control 3.03 Inclusion of Quality Assurance Requirements in Plant Design Change Requests IV.
Procurement Document 4.01 Procurement Document Review Control 4.03 Evaluation / Periodic Re-evaluation of Engineering Constructors, NUSCO Contractors, Suppliers &
Engineering Service Organizations.
4.05 Preparation, Issuance & Control of the NUSCO Quality Assurance Category I Contractor, Supplier & Engineering Service Organization List QAP - Appendix C Rev. 1 Date: M ch 5, 1979 Page 2 17
Sheet 2 of 3 NUSCO QUALITY ASSURANCE PROCEDURES NUSCO APPENDIX B TO 10CFR PART 50 QA PROCEDURES 4.06 Review of " Objective Evidence" submitted by the Engineer-Contractor
& NUSCO Contractors, suppliers &
Engineering Service Organizations 4.07 Instructions for use of the NUSCO Quality Assurance Supplier Information Computer Program 4.08 Purchase Requisitions / Purchase Order Computer Program V.
Instruction, Procedures &
Drawings VI.
Document Control 6.01 Preparation, Issuance, & Control of PSAR, FSAR/FDSA & MSAR Quality Assurance Program Descriptions 6.02 Routing, Follow-up, review &
approval of Engineer-Constructor, NUSCO Contractor & Engineering Service Organization Quality Documents VII. Control of Purchase Material, Equipment &
Service VIII. Identification & Control of Materials, Parts and Components IX.
Control of Special Processes X.
Inspection 10.01 Preparation of Inspection Packages 10.02 Conduct / Reporting of NUSCO Quality Assurance Inspections 10.04 Performance, Reporting & Follow-up of Surveillance Activities XI.
Test Control XII. Control of Measuring &
Test Equipment QAP - Appendix C Rev. 1 Date. March 5,1979 Page 3 of 17
Sheet 3 of 3 NUSCO QUALITY ASSURANCE PROCEDURES NUSCO
~
APPENDIX B TO 10CFR PART 50 Qt. PROCEDURES XIII. Handling, Storage &
Shipping XIV. Inspection, Test & Operating Status XV.
Nonconforming Materials, 15.02 Instructions for Use of the NUSCO Parts, or Components Quality Assurance Deficiency Surveillance Computer Program XVI. Corrective Action 16.01 Verification of Corrective Action Contained in Significant Deficiency Reports submitted to the NRC.
XVII. Qualicy Assurance Records 17.02 Retention & Control of Quality Records at the NUSCO Quality Records Center at Berlin & at the Nuclear Construction Site.
17.04 Review and Approval of Qaality Documentation Plans XVIII. Audits 18.01 Conduct, Reporting & Follow-up of Audits 18.02 Audit, Survey & Inspec' ion Computer Program 18.03 Procedure to Stop Work 18.06 NUSCO Quality Assurance Review &
Approval of NUPOC In-Plant Pre-operational Testing Program Audit Schedules 18.07 Joint Audits QAP - Appendix C Rev.
1 Date: March 5, 1979 Page 4 of 17
Sheet 1 of 1 NUSCO NUCI. EAR PRODUCTION PROCEDURES NUSCO APPENDIX B TO 10CFR PART 50 NUCLEAR PRODUCTION 1.
Organization QA 1.01 Organization II.
Quality Assurance Program QA 2.01 Quality Assurance Program III. Design Control QA 3.01 Plant Design Change Request Control IV.
Procurement Document Control V.
Instructions, Procedures, &
QA 5.01 Preparation, Issuance & Control Drawings of Department Orders QA 5.02 Distribution and Accountability of Department Orders VI.
Document Control QA 6.01 Design Document Control QA 6.02 Distribution of Design Documents VII. Control of Purchased Material, Equipment &
Services VIII. Identification & Control of Materials, Parts & Components IX.
Control of Special Processes X.
Inspection XI.
Test Control XII. Control of Measuring & Test Equipment XIII. Handling, Storage & Shipping XIV. Inspection, Test & Operating Status XV.
Nonconforming Materials, QA 15.01 Control of Nonconformance Reports Parts, or Components Requiring KUSCO Engineering Approval XVI. Corrective Action XVII. Quality Assurance Records QA 17.01 Quality Assurance Records XVIII. Audits QA 18.06 Quality Assurance Audit Follow-up Program QAP - Appendix C Rev. 1 Date: '! arch 5, 1979 Page 5 of 17
Sheet 1 of 4 NUSCO NUCLEAR PROJECTS PROCEDURES NUSCO APPENDIX B TO 10CFR PART 50 NUCLEAR PROJECT PROCEDURES I.
Organization 1.01 Generation Engineering & Construction Division 1.02 Nuclear Projects Department 1.03 Generation Engineering Department 1.04 Nuclear & Environmental Engineering Department 1.05 Generation Reliability Engineering
& Quality Assurance Department II.
Quality Assurance Program 2.01 Preparation, Approval, Distribution
& Control of a Category I Material Equipment & Parts List for New Generation Facilities and In-Service Units 2.02 Procedure for Review of Nuclear Projects Procedures as required by Revisions to NUQAM 2.03 Preparation & Processing of Proposed Revisions to the Northeast Utilities Quality Assurance Manual 2.04 Preparation, Issuaace & Control of NUSCO Nuclear Projects Procedures 2.05 Management Review of Northeast Utilities Quality Assurance Program 2.06 Nuclear Projects Procedure Training Program III. Design Control 3.01 Selection of Design Documents for Review 3.02 Identification of Discipline Engineers for the review of Design Documents 3.03 Review of Design Dcouments
. n QAP - Appendix C Rev. 1 Date March 5, 1979 Page 6 of 17
Sheet 2 of 4 NUSCO NUCLEAR PROJECTS PROCEDLTES NUSCO APPENDIX B TO 10CFR PART 50 NUCLEAR PROJECT PROCEDLTES 3.04 Processing, Documenting & Filing the Results of Design Reviews 3.04a Processing, Documenting & Filing of Results of Construction Procedure Review 3.06 Resolution of Design Deficiencies 3.07 Preparation, Review & Disposition of Plant Design Change Requests 3.08 Preparation, Issuance & Control of Assignments 3.11 Preparation, Review, Approval and control of Design Documents Prepared by NUSCO e
3.12 Review & Disposition cf Deviations from Specifications 3.13 Review and Disposition of NUPOC Design Modification Form IV.
Procurement Document Control 4.01 Preparation, Review & Approval of NUSCO Bid Specification 4.02 Review of Proposals Submitted by the Engineer-Constructor, Contractors &
Engineering Service Organizations 4.03 Review of Proposals Submitted by Suppliers (Vendors) 4.04 Preparation of NUSCO Purchase Re-quisitions and Review o'f NUSCO Purchase Orders 4.05 Approval of Engineer-Contractor Purchase Orders V.
Instructions, Procedures, 5.01 Review of Selected Work Instructions
& Drawings
& Proceduras of the Enginear-Con-cugineering Service tracto,'
o Organizations QAP - Appendix C Rev. 1 Date : March 5,1979 Page 7 of 17
Sheet 3 of 4 NUSCO NUCLEAR PROJECTS PROCEDURES NUSCO APPENDIX B TO 10CFR PART 50 NUCLEAR PROJECT PROCEDURES VI.
Document Control 6.01 Control & Distribution of Drawings &
Specifications (Design Documents) during Design, Construction & Pre-operational testing of Nuclear Power Plants 6.02 Review & Approval of Drawing Change requests 6.02a Review & Approval of Drawing Change Requests for Millstone Unit No. 2 6.03 Review & Approval of FDSA/FSAR Changes 6.04 Safety Evaluation of Technical Specification Changes VII. Control of Purchase Mater-7.01 Control of Purchased Material, Equip-ial, Equipment & Services ment, Parts & Services VIII. Identification & Control of Materials, P.,rts &
Components IX.
Control of Special Processes 9.01 Control of Special Processes X-Inspection 10.01 Inspection XI.
Test Control XII. Control of Measuring & Test Equipment XIII. Handling, Storage &
13.01 Handling, Storage, Shipping, Cleaning Shipping
& Preservation XIV. Inspection, Test, & Oper-14.01 Inspection, Test & Operating Status ating Status XV.
Nonconforming Materials, 15.01 Review and Approval of Nonconformances Parts, or Components Dispositioned "Use as Is" and " Repair" 15.02 Identification & Disposition of Deficiencies identified during Construction & Insti.llation QAP - Appendix C Rev.
1 Date: March 5, 1979 Page Bof 17
Sheet 4 og 4 NUSCO NUCLEAR PROJECTS PROCEDURES NUSCO AP'ENDIX B TO 10CFR PART 50 NUCLEAR PROJECT PROCEDURES 15.03 Documenting & Reporting Significant Deficiencies 15.04 Installation of Nonconformance Material Equipment & Parts XVI. Correction Action 16.01 Corrective Action Program for Significant Deficiencies XVII. Quality Assurance Records 17.01 Retention & Control of Quality Records in the NUSCO Nuclear Project File -
Berlin & Plant Site 17.01A Control and Retention of Design Documents Files For NUSCO Nuclear Plant Betterment Projects XVIII. Audits 18.01 Resolution of Audit Deficiencies QAP - Appendix C Rev.
1 Date March 5, 1979 Page 9 of 17
Sheet 1 of 2 MILLSTONE QA ADMINISTRATIVE C0hTROL PROCEDURES (ACPS)
APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
I.
Organization ACP-QA 1.01 Administrative Control Procedure Program ACP-QA 1.02 Organization & Responsibilities ACP-QA 1.04 Plant Operations Review Committee ACP-QA 1.05 Site Operations Review Committee II.
Quality Assurance Program ACP-0A 1.06 Quality Assurance / Quality Control Program ACP-QA 4.01 Plant Housekeeping ACP-QA 8.07 QA Training Program ACP-QA 8.16 Training, Certification &
Identification of Qualified Inspection, Examination &
Test Personnel ACP-QA 8.21 Indoctrination & Training of Audit Personnel III. Design Control ACP-QA 3.04 Design Change Control IV.
Procurement Document Control ACP-QA 4.02 Procurement, Control & Identi-fication of Material V.
Instruction, Procedure, &
ACP-QA 2.02 Performing Category I Work Drawings ACP-QA
',.01 ACP's & Station Forms AC P - 1".
3.02 Station Procedures & Forms ACP-QA 3.05 Review & Approval of Vendor Procedures ACP-QA 3.06 Preservic-Unit Instructions VI.
Document Control ACP-QA 3.03 Document Control VII. Control of Purchased Mater-ACP-QA 4.05 Product Acceptance Inspection ial, :quipment & Services
& Testing VIII. Identification & Control of (SF-QA 4.03 Classifying & upgrading Spare Materials, Parts & Componet..
Parts ACP-QA 4.07 Control of Weld Material QAP - Appendix C Rev. 1 Date
': arch 5,1979 Page 10 of 17
Sheet 2 of 2 MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
IX.
Control of Special Processes ACP-QA 2.07 Control of Special Processes X.
Inspections ACP-QA 2.02A Installation Inspections ACP-QA 2.04 Control of Work By Outside Construction of In-Service Systems ACP-QA 9.06 In-service Inspection Program XI.
Test Control ACP-QA 2.02B Retests ACP-QA 9.02 Plant Surveillance Program ACP-QA 9.02A Unit 1 Sury. Master Test Cont.
List ACP-QA 9.02B Unit 2 Surv. Master Test Cont.
List ACP-QA 9.03 Inservice Plant Testing XII. Control of Measuring & Test ACP-QA 9.04 Control & Calibration of Test Equipmcat Instruments XIII. Handling, Storage & Shipping ACP-QA 4.04 Instructions for Packaging, Shipping, Receiving, Storage
& Handling ACP-QA 6.04 Radioactive Material Shipping Requirements XIV. Inspection, Test & Oper-ACP-QA 2.06 Station Tagging & Bypass /
ating Status Jumper Control XV.
Nonconforming Materials, ACP-QA 5.01 Nonconforming Materials & Parts Parts, or Components XVI. Corrective Action ACP-QA 10.01 Plant Incident Report ACP-QA 10.03 Reportable Occurrences and Non-routing Environmental Operating Reports ACP-QA 10.06 NRC Commitment Follow Program XVII. Quality Assurance Records ACP-QA 10.04 QA Records XVIII. Audits ACP-QA 9.01 Internal In-Plant Audit Program ACP-QA 9.05 Monitoring of QA Activities QAP - Appendix C Rev.
1 Date March 5,1979 Page 11 of 17
Sheet 1 of 3 CONNECTICUT YANKEE QA PROCEDURES CONNECTICUT YANKEE APPENDIX B TO 10CFR PART 50 QA PROCEDURES I.
Organization ADM 1.1-1 Connecticut Yankee Organization Responsibility & Authority II.
Quality Assurance Program QA 1.2-2.1 Request for Category I Evaluation QA 1.2-2.2 QA Category I Boundary QA 1.2-2.3 Qualification of Inspection, Examination & Test Personnel QA 1.2-2.4 Housekeeping Requirements III. Design Control QA 1.2-3.1 Design Change Control QA 1.2-3.2 QA Requirements for the Design of Nuclear Power Plants IV.
Procurement Document Control QA 1.2-4.1 Procurement Document Control V.
Instructions, Procedures &
QA 1.2-5.1 Maintenance Requests & Job Drawings Orders QA 1.2-5.2 Procedure Format VI.
Document Control QA 1.2-6.1 Document Distribution &
Accountability QA 1.2-6.2 Master Document Index QA 1.2-6.3 Drawing Changes OA 1.2-6.4 Temporary Procedures Changes QA 1.2-6.5 Procedure Review & Approval QA 1.2-6.6 FDSA Change Request QA 1.2-6.7 Technical Specification Change Request QA 1.2-6.8 Centrol of Forms VII. Control of Purchased QA 1.2-7.1 Material Receipt Inspection Material, Equipment &
Services QA 1.2-7.2 Fuel Assembly Receipt Inspection,
QAP - Appendix C Rev-1 Date: March 5, 1979 Pa e 12 of 17
Sheet 2 of 3 CONNECTICUT YANKEE QA PROCEDLTES CONNECTICUT YANKEE APPENDIX B TO 10CFR PART 50 QA PROCEDURES VIII. Identification & Control of QA 1.2-8.1 Identification of Materials, Materials, Parts & Components Parts & Components QA 1.2-8.2 Materials Issue QA 1.2-8.3 Weld Material Control IX.
Control of Special Processes QA 1.2-9.1 Control of Special Processes QA 1.2-9.2 Requirements for Cleaning of Fluid Systems & Associated Components QA 1.2-9.3 QA Requirements for Protective Coating Applied to Nuclear Facilities X.
Inspections QA 1.2-10.1 Installation Inspections QA 1.2-10.2 Supplementary QA Requirements for Installation, Inspection
& Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plant XI.
Test Control QA 1.2-11.1 Operational Surveillance Tests QA 1.2-11.2 Review of Test Data QA 1.2-11.3 Retest Requirements QA 1.2-11.4 Product Acceptance Tests XII. Control of Measuring &
QA 1.2-12.1 Control of Measuring as Test Test Equipment Equipment XIII. Handling, Storage & Shipping QA 1.2-13.1 Handling of Material &
Equipment QA 1.2-13.2 Storage of Material & Equipment QA 1.2-13.3 Shipping of Material & Equipment QA 1.2-13.4 Packaging of Material & Equipment QAP - Appendix C Rev.
1 Date: March 5,197!
Page 13 of 17
Shett 3 of 3 CONNECTICUT YANKEE QA PROCEDURES CONNECTICUT YANKEE APPENDIX B TO 10CFR PART 50 QA PROCEDURES XIV. Inspection, Test & Oper-QA 1.2-14.1 Bypass & Jumper Control ating Status QA 1.2-14.2 Equipment Control (Locking &
Tagging)
XV.
Nonconforming Materials, QA 1.2-15.1 Nonconformance Report Parts, or Components QA 1.2-15.2 Document Deficiency Notice XVI. Corrective Action QA 1.2-16.1 Plant Information Reports QA 1.2-16.2 Failure & Malfunction Reports XVII. Quality Assurance Records QA 1.2-17.1 Quality Assurance Records XVIII. Audits QA 1.2-18.1 Internal Audits QAP - Appendix C Rev. 1 Date : March 5, 197E Page 14 of 17
Sheet 1 of 1 NUSCO NUCLEAR PLANT RECORDS MANUAL (NPRM)
NPRM APPENDIX B TO 10CFR PART 50 QA PROCEDURES XVII. Quality Assurance Records 1.
Administration 2.
Various Operating & Maintenance Procedures 3.
Drawing Control 4.
Source Document Control 5.
Computer Programs & Associates Instructions for NPR 6.
Training Requirements QAP - Appendix C Rev.
1 Date : March 5, 19~ 9 Page 15 of 17
Sheet I of i NU WELDING MANUAL WELDING MANUAL APPENDIX B TO 10CFR PART 50 QA PROCEDURES I.
Organization AP 700 Organization & Control of NUSCO Welding Manual IX.
Control of Special AP 701 Preparation, Qualification, Approval Processes
& Revision of NUSCO Welding Manual AP 703 Preparation, Review & Approval of Detailed Welding Procedures XVII. Quality Assurance Records AP 702 Control of Welder & Brazer Qualifications QAP - Appendix C Rev.
1 Date March 5,197 )
Page 16 of 17
e Sheet 1 of 3 NU PURCHASING BUSINESS PROCEDURES PURCHASING APPENDIX B TO 10CFR PART 50 QA PROCEDURES IV.
Procurement Document Control Applicable BP3.0 Purchasing Procedures QAP - Appendix C Rev.
1 Date: March 5, 197' Page 17 of 17
e APPENDL NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT REGULATORY GUIDE AND ANSI STANDARD COMMITMENTS Appendix B to 10 CFR, Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
10 CFR, Part 55 - Operator's Licenses and its Appendix A - Requalifi-cation 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 - 3/78 - 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 the Installations, Inspection, and Testing of Instru-mentation 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, 3-16-73 -Endorses ANSI N45.2.1 - 1973.
Regulatory 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.
Regulatory Guide 1.58 - Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel, August 1973 - Endorses ANSI N45.2.6 -
1973Property "ANSI code" (as page type) with input value "ANSI N45.2.6 -</br></br>1973" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
Regulatory Guide 1.64 - Quality Assurance Requirements for the Design of Nuclear Power Plants, 6/76-Endorses ANSI N45.2.ll - 1974.
Regulatory Guide 1.70, Revision 2, " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants - LWR Edition" - September, 1975.
QAP - Appendix D Rev. 2 Date March 5,1979 Page 1 of 2
Regulatory Guide 1.74 - Quality Assurance Terms and Definitions, Feb.
74 -Endorses ANSI N45.2.10 - 1973.
Draft Regulatory Guide - Preoperational and Initial Startup Test Programs for Water-Cooled Power Peactors.
(Draft 4, 10-2-73)
Regularoty Guide 1.88 - Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records - 10/76 - Endorses ANSI N45.2.9 -
1974Property "ANSI code" (as page type) with input value "ANSI N45.2.9 -</br></br>1974" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
Regulatory Guide 1.94 - Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants - 4/76 -Endorses ANSI N45.2.5 - 1974.
Regulatory Guide - 1.116 - Quality Assurance Requirements for Installa-tion, 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.
ANSI N45.2.12.- Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants (Draft 3, Rev. 4, February 22, 1974).
QAP - Appendix D Rev.
2 Date : March 5, 1979 Page 2 of 2
APPENDIX E NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAS TOPICAL REPORT GLOSSARY OF QUALITY ASSURANCE TERMS Audit - a formal, documented activity performed in accordance with written checklists or procedures to verify by evaluation of objective evidence that a quality assurance program has been developed, documented, and implemented in ac ordance with applicable requirements.
Calibration - the process by which measuring and test equipment are checked against standards of known higher accuracy and adjusted as necessary to ensure their compliance with designated specifications.
Category I - designation given to systems, structures, and components of a Northeast Utilities nuclear power plant that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public.
Category I Systems, Structures, and Components - defined in Appendix A.
Cleaning - those actions performed to maintain an item in accordance with cleanliness requirements.
Contractor - organizations that provide services that may include engineer-ing, procurement, construction, and installation of material, equipment, and parts. The Nuclear Steam Supply System Supplier (NSSS Supplier) is included in this category.
Corrective Action - action taken to correct conditions adverse to quality in order to preclude recurrence of the conditions.
Deficiencies - departures from specified requirements.
Lypartmental Measuring and Test Equipment List - a list of all departmental measuring and test equipment included in the NUPOC calibration program.
Design - technical and management processes which lead to and include the issuance of design output documents such as drawings, specifications, and other documents defining technical requirements of systems, structures, and components.
Design Changes - chaages in drawings and specifications which define the design of Category I systems, structures, and components of nuclear power plants.
QAP - Appendix E Rev. 2 Date : '&ch 5,1979 Page 1 of 6
Design Documents - design documents referred to herein ate the drawings and specifications that define the design of Categ;.y I systems, structures, and components; the Facility Description and Safety Analysis (FDSA)/ Final Safety Analysis Report (FSAR); the License Document; Technical Specifica-tions; and Environmental Technical Specifications.
Drawing Change Request - a document used to request approval of revisions to existing NUSCO drawings.
Engineer-Constructor - the principal organization contracted by NUSCO that performs the overall engineering, procurement, construction, and installation of Category I systems, structures, and components of a nuclear power plant.
Eagineer-Constructor /NUSCO Contractor Installation Inspection - an in-spection of Category I systems, structures and components performed by the Engineer-Constructor /NUSCO Contractor prior to system release /
transfer to NUPOC for preoperational testing, as defined in the NUP0C Startup Manual.
Engineering Service Organization - organizations that provide services such as analysis, testing, and inspection.
Handling - the transfer of an item from one location to another within a contractor's, supplier's or engineering service organization's facility or at the nuclear power plant.
Identification - a means by which material, equipment and parts can be traced to their associated documentation through the use of heat numbers, lot numbers, part numbers, serial numbers, or other appropriate means.
Inspection - a phase of quality control which, by means of examination, observation, or measurement determines the conformance of material, equipment, parts, and processes to predetermined quality requirements.
Inspection Status - identification of material, equipment, and parts that have completed inspection, either acceptable or unacceptable.
Life Records - those quality documents that are maintained for the lifetime of the in-service nuclear power plant 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.
QAP - Appendix E Rev. 2 Date : March 5,1979 Page 2 of 6
(4) providing required base line data for in-service inspection.
Manager of QA/ Designee - the designee is a NUSCO Quality Assurance Depart-ment employee, as well as the respective NUPOC QA/QC Supervisor or NUPOC QA/QC employee as depicted by Figure 1.3 of QAP 1.0.
Measuring and Test Equipment - those instruments, gauges, tools, and mcaruring devices used during inspection and testing to determine that measuring and test arameters comply with appropriate requirements in specifications and frawings.
Nonconforming Material, Equipment, and Parts - any material, equipment, or parts which do not conform to specified requirements.
Nonengineered Items - Material, equipment and parts which are:
(1) Relatively simple and standard in design, manufacture and test.
(2) Adaptable to standard or automated inspections and/or tests of the end product to verify quality characteristics af ter delivery.
(3) Of such a nature that product acceptance inspections / tests performed upon receipt of the items do noc require operations which could adversely affect the integrity, function, or cleanness of the item.
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.
Northeast Utilities (NU) - a public utility holding company which owns Northeast Utilities Service Company and The Northeast Nuclear Energy Company and thru its operating subsidiaries has a controlling interest in The Connecticut Yankee Atomic Power Company.
Northeast Utilities Service gyrpany (NUSCO) - a wholly cened subsidiary of Northeast Utilities that provides engineering, procurement, construc-tion, and quality assurance services for Northeast Utilities relating to design, construction, and preoperational *esting of nuclear power plants and major modifications thereto.
Nuclear Plant Operating Companies (NUPOC) - which as a subsidiary of Northeast Utilities performs preoperational testing of Category I systems, structures and components of nuclear power plants and major modifications thereto subsequent to completion of their design and construction and is also responsible for the operation of in-service nuclear power plants.
The companies which comprise NUPOC are The Connecticut Yankee Atomic Power Company and The Northeast Nuclear Energy Company.
QAP-pppendixE Rev.
Date March 5, 1979 Page 3 of 6
s NUPOC In-Plant Preoperational Testing Audits - audits performed by the NUPOC, Quality Assurance Supervisor to verify implementation by NUPOC of the requirements of the Northeast Utilities Quality Assurance Program during preoperational testing.
NUPOC Internal In-Plant Audits - audits performed by the NUPOC Quality Assurance Supervisor of NUPOC quality related activities.
NUSCO Contractor, Supplier,.nd Engineering Service Organization Audits -
audits performed by NUSCO Q < slity Assurance of NUSCO contractor, supplier, and engineering service o;.nization quality related activities at their facilities.
NUSCO Contractor, Supplier, and Engineering Service Organization List -
a list identifying the approval status of the quality assurance programs of contractors, suppliers, and engineering service organizations.
KUSCO Internal Audits - audits performed by NUSCO Quality Assurance of NUSCO quality related activities.
NUSCO Nuclear Project Engineer - the engineer designated to act as pro.iect engineer during design, construction and preoperational testing of a nuclear power plant or major modifications thereto. He may or may not be titled engineer.
NUSCO Off-Site Engineer-Constructor Contractor, Supplier, and Engineering Service Organization Audits - audits performed by NUSCO Quality Assurance of the quality assurance programs of the Engineer Constructor and NUSCO contractors, suppliers, and engineering service organizations at their facilities.
NUSCO Plant Audits - audits performed at the in-service nuclear power plant by NUSCO Operations Quality Assurance of NUPOC quality related activities.
NUSCO Preoperational Testing Audits - audits performed by NUSCO Operations Quality Assurance during preoperational testing to verify implementation by NUPOC of the requirements of the hortheast Utilities Quality Program.
NUSCO Quality Records Center - the location at NUSCO of the NUSCO Quality Assurance records files under the cognizance of the NUSCO Quality Assurance Department.
" Objective Evidence" - any st.itement of fact, information, or record, either quantitative or qualitative, pertaining to the item or service based on observation, measurenents, or tests which can be verified.
Preoperational Testing - tests performed by NUPOC to ensure Category I systems, structures, and compocents will perform satisfactorily during operation of the in-service nuclear power plant.
QAP - Appendix E Rev.
2 Dater March 5, 1979 Page 4 of 6
Preservation - those actions performed to maintain an item in this 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.
Procurement Documents - letters of Intent, Contracts, Purchase Requisitions, and Purchase Orders which provide contractual basis for services such as engineering and procurement; supply of material, equipment, and parts; construction; installation; inspection; and testing.
Product Acceptance Inspection / Test - Inspection / test performed as part of receipt inspection at the nuclear power plant to verify the quality characteristics of nonengineered items.
Operations utilized during product acceptance inspections / tests are such that they do not adversely affect the integrity, function or cleanness of the item.
Proof Test - a test conducted prior to installation of Category I systems, structures and components to verify specification requirements have been met.
Project Engineer - a NUSCO/NUPOC employee assigned the responsibility to coordinate the activities addressed in NU QAP.
Purchased Material, Equipment, and Parts - items procured for use in Category I systems, structures, and components.
Purchased Service - services procured to assist in operation, main-tenance, modification, and refueling of in-service nuclear power plants.
Quality Assurance Program (QAP) - consists of the QAP Topical Report, Quality Assurance Department Procedures and other Northeast Utilities Departmental / Divisional quality related procedures.
Quality Assurance Records - any record pertaining to the quality of material, equipment, parts, processes, or operations relating to Cate-gory I systems, structures and components which are founded on observa-tions, measurements, or tests which can be fully checked or verified.
Such statements may be recorded on a written or preprinted document or
- ig.
The statements are authori ed with a signature or stamp identifi-a' ale to the person making the statement of fact.
Quality Related Procedures - an aaministrative document issued by that f
Station Superintendent to implement the requirements of NU QAP.
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 do not meet all specified require-ments.
QAP - Appendix E Rev. 2 Date
'4 arch 5, ly,?
Page 5 of 6
Retest - a test conducted prior to operation following instal!ation in-spections of work associated with maintenance, modification, and refuel-ing to verify that Category I systems, structures, and components will function satisfactorily when in operation.
/
Return to Supplier - a disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose but which are feasible to repair or rework at a supplier's facility.
Rework - a disposition applied to nonconforming material, equipment, and parts that 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.
Salvage - a disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose and not feasible for rework or repair but which contain material, equipment, or parts which are reclaimable for future use.
Special Processes - an operation performed under controlled conditions in accordance with special requirements utilizing qualified procedures, equipment, and personnel.
These special processes may include, but are not limited to: welding, brazing, soldering, cleaning, heat treating, and nondestructive testing.
Storage - Maintenance of an item in the environment specified in appro-priate documents.
Supplier - organizations that provide material, equipment, and parts.
Surveillance - A documented record of the observation of work operations performed at the construction site.
Surveillances are not performed to a preplanned checklist. However, the results are formally documented and reviewed and follow-up action, if necessary, is provided.
Test and Operating Status - identification of material, equipment, and parts that are ready for test or operation, or an existing stage of a test operation.
Testing - the determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, environmental, or operating conditions.
Use As Is - a disposition applied to nonconforming material, equipment and parts which are suitable for their intended purpose but do not meet all specified requirements.
QAP - Appendix E Rev. 2 Date March 5, 1979 Page 6 of 6
APPENDIX F NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT Program Exception ANSI N45.2.9, states in part, " Structure, doors, frames, and hardware should be Class A fire-related with a recommended four-hour minimum rating." The records storage vault door and hardware at NNECO has a two-hour rating and the record storage vault door and hardware at CYAPCo has a three-hour rating.
Both NNECO and CYAPCO's vaults are used for storage of documentation that is unsuitable for filming or awaiting filming.
A records organization exists along with written procedures addressing the control of quality assurance records.
QAP - Appendix F Rev.
2 Date: March 5, 1979 Page 1 of 1