B12541, Rev 10 to QA Program Topical Rept
| ML20215C688 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 06/30/1987 |
| From: | NORTHEAST UTILITIES SERVICE CO. |
| To: | |
| Shared Package | |
| ML20215C653 | List: |
| References | |
| B12541, NUDOCS 8706180209 | |
| Download: ML20215C688 (100) | |
Text
<> Docket Nos. 50-213 50-245 50-336
'~ 50-423 B12541 Attachment B Proposed Revision 10 of the Northeast Utilities Quality Assurance Program Topical Report June,1987 B706180209 870604 PDR ADOCK 05000213 PDR .
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r ABSTRACT-NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM-(NUQAP)
TOPICAL REPORT e-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. safe and effective manner.
The NU Quality Ass urance' Program. (NUQAP)~ Topical Report' complies with the requirements set .b th;in Appendix B, of 10 CFR Part 50, along with.
uapplicable' sections of the Safety Analysis Report (SAR) for each license
. appl _ication, and is . responsive to the United States NRC Regulatory. Guide 1.70, which describes'the:information required to be presented in the Quality Assurance.Section of the SAR's for nuclear power plants.
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This NUQAP is also established, maintained and executed with regard to Radioactive Material' Transport Packages'as allowed'by 10 CFR 71.101(f).
, Qua?4ty Assurance provisions for Fire Protection activities are detailed 1 iin- the Northeast Utilities Fire: Protection Program. .
This?NUQAP is appl cableiin its entirety to Category I' systems, structures,
,p ' components,. material, equipment, parts, and services. Appendix A, defines Category I. systems,-structures, and' components. The NUQAP is also
'b" applicable to ather quality related programs, including Fire Protection
- Quality Assurance (FPQA), Radwaste Quality Assurance, Radwaste Systems,.-
Anticipated Transient Without Scram (ATWS), Environmental Qualification
/ of Electric Equipment Important for Nuclear Power. Plants (EEQ) and' i
Mechanical Equipment Qualification (MEQ) as defined by NU commitments as
' listed in Appendix G.
The NUQAP is committed to utilize the guidance obtained from the Regula-tory documents'and'their endorsed Standards.as referenced in Appendix D of the Topical Report.
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QAP - Abstract Rev.: 10 Date: I
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TABLE OF CONTENTS NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)
TOPICAL REPORT Rev. Pages Abstract
.. 10 1 Table of Contents 10 1 Policy Statement 10 l' Introduction 10 1-2 Quality Assurance Program QAP 1.0 Organization 10 1-15 Organizational Charts. 10 Figs. 1.1-1.7 QAP 2.0 Quality Assurance Program 10 1-6 QAP 3.0 Design Control 10 1-6 QAP 4.0 Procurement Document Control 10 1-4L-QAP 5.0 Procedures, Instructions and Drawings 10 1 QAP 6.0 Document Control: 10' l-4 QAP 7.0' Control of Purchased Material, Equip- 10 1-4 ment and Services QAP 8.0 ~ Identification and Control of 10 1-2 Materials, Parts and Components QAP 9.0 Control of Special Processes 10 1-3 QAP 10.0 Inspection 10 1-4 QAP 11.0 Test Control 10 1-3 QAP 12.0 Control of Measuring and Test Equip- 10 1-3 ment QAP 13.0 Handling, Storage, and Shipping 10 1-2 QAP 14.0 Inspection, Test and Operating Status 10 1-2 QAP 15.0 Nonconforming Materials, Parts, 10 1 Components, or Services QAP 16.0 Corrective Action 10 1-3 QAP 17.0- Quality Assurance Records 10 1-2 QAP 18.0 Audits 10 1-3 Appendices A. Category I Systems, Structures and Com- 10 1-3 ponents B. Qualification and Experience Requirements 10 1 NUSCO Manager, Quality Assurance C. List of Typical Quality Assurance Related Procedures 10 1-32 D. Regulatory Guide and ANSI Standard 10 1-2 i Commitments E. Glossary of Quality Assurance Terms 10 1-7 F. Program Exceptions 10 1-2 G. Quality Activity Matrix 10 1-3 QAP Table of Contents Rev.: 10 Date:
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i POLICY STATEMENT NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM f
j TOPICAL REPORT i The policies, requirements and tasks 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.
This NUQAP is applicable in its entirety to Category I systems, structures, components, material, equipment, parts, and services. Appendix A defines Category I systems, structures, and components. The NUQAP is also 3 applicable to other quality related programs, including Fire Protection Quality Assurance (FPQA), Radwaste Quality Assurance, Radwaste Systems, Anticipated Transient Without Scram (ATWS), Environmental Qualification of Electric Equipment Important for Nuclear Power Plants (EEQ) and Mechanical Equipment Qualification (MEQ) as defined by NU commitments as listed in Appeudix G.
The development and overall responsibility for this Quality Assurance Program lies with the Senior Vice President - Nuclear Engineering and Operations. Corporate authority is delegated to the NUSCO Manager, Quality Assurance for the preparation and administration of the Quality Assurance 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 NUSCO Manager, Quality Assurance. Any revisions or additions shall be approved by affected Departments prior to the incorporation of such changes into the program. Final approval of revisions or additions to this policy statement rests with the Senior Vice President - Nuclear Engineering and Operations.
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E. J:tifoczka () l Senior Vice President - Nuclear Engineering and Operations Northeast Utilities QAP - Policy Statement Rev.: 10 Date:
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INTRODUCTION NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT P
This Northeast Utilities Quality Assurance Program (NUQAP) Topical Report contains the quality assurance requirements which are relative to the safety of the nuclear power plant. The Topical Report consists of the following three parts:
- 1. Introduction, which delineates the purpose of the Topical Program, and summarizes its scope and applicability.
- 2. This NUQAP is applicable in its entirety to Category I systems, structures, components, material, equipment, parts, and services.
Appendix A defines Category I systems, structures, and components.
The NUQAP is also applicable to other quality related programs, including Fire Protection Quality Assurance (FPQA), Radwaste Quality Assurance, Radwaste Systems, Anticipated Transient Without Scram (ATWS), Environmental Qualification of Electric Equipment Important for Nuclear Power Plants (EEQ) and Mechanical Equipment Qualification (MEQ) as defined by NU commitments as listed in Appendix G.
- 3. Appendices, which provide supporting statements and tabulations.
This NUQAP Topical Report has been prepared to document that a meaningful quality assurance program has been established and implemented to ensure j that adequate quality requirements are being complied with to safeguard i NU employees, contracted personnel and the general public, from the conceptual phase through the operations phase of nuclear power plant life.
The controls which implement the actions identified in the NUQAP Topical j Report are departmental procedures and instructions which delineate l
actions and steps necessary to accomplish quality requirements. Procedures j and instructions are written by company groups, divisions, departments, l branches, or sections, which have the responsibility for implementing j actions assigned to them as delineated by the NUQAP. Quality procedures l ]
and revisions thereto are reviewed by and concurred with by the applicable 4 NUSC0/NUPOC Quality Assurance Organization, in accordance with QAP 2.0 and QAP 5.0.
l The NUQAP is responsive to applicable codes, Nuclear Regulatory Commis- l sion regulatory requirements, accepted industrial standards and revisions thereto. Provisions are established to update the NUQAP Topical Report in accordance with revisions to codes, standards and regulatory require- !
ments, and to inform cognizant personnel to implement appropriate action l i
QAP - Introduction Rev.: 10 l Date: !
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'to assure the highest standard of quality is achieved for systems, structures, components and services for nuclear power plants.
b b f O) A N Donald O. Noraquist NUSCO Manager, Quality Assurance l
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1.0 ORGANIZATION
1.1 INTRODUCTION
P 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 Power Company (CL&P) and Western Massachusetts Electric Company (WMECO) are the sole owners of Millstone Units Number One and Two with 81% 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 of the decisions affecting the design, procurement, construction and operation of that unit. This decision making authority would be similar for any future units.
l The NU Companies jointly own 44% of The Connecticut Yankee Atomic Power Company (CYAPCO). By contract, NU and Northeast Utilities Service Company (NUSCO) have been delegated operational control 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 CYAPCO are the operating companies established to operate their respective facilities. NNECO is delegated the responsibility for operating the Millstone 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 may solicit technical support during plant operations, d NNECO and CYAPCO comprise the Nuclear Plant Operating Companies (NUPOC) as illustrated in Figure 1.1.
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1 NUSCO, parts of which are organized as shown in Figures 1.2, 1.3, i 1.4 and 1.5 provides services such as engineering, quality assurance, {
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accounting, planning 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 1.6, for quality related activities, indicates how conflicts are resolved.
As indicated, the Senior Vice President-Nuclear Engineering and Operations - NUSCO is also the Senior Vice President-Nuclear l Engineering and Operations - NUPOC. He resolves disputes arising from a difference of opinion between Quality Assurance personnel and other department personnel.
1.2 GENERAL (Refer to Figure 1.2) 1.2.1 The Chairman, President and Chief Executive Officer of NU is also the Chairman, President and Chief Executive j Officer of NUSCO and directs specified nuclear-related activities within NU. He has the ultimate responsibility QAP 1.0 Rev.: 10 Date:
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'fortheestablishmentandexecutionoftheINU. Quality _
Assurance. Program (NUQAP). Reporting to the' Chairman, President =and Chief Executive Officer is the Executive Vice President-Engineering and' Operations'and the; Senior
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Vice President-Administrative' Services. ' Authority for the establishment and execution of the NUQAP is. delegated to the Senior Vice President-Nuclear Engineering and Operations (see Para.:1.2.4).
1.2.2 The Senior Vice-President-Administrative Services is responsible for. procurement and Informition Resources activities within NU. The' System Director-Purchasing and Materials Management reports to the Senior.Vice President-Administrative Services;and'is responsible to ensure that procurement requirements of the NUQAP are' carried out within his' division.(see Para. 1.5.1).
The Vice President - Information Resources Group-is responsible for all information storage, handling and delivery systems 1st NU. . The'following Directors / Managers report to the Vice' President-Information Resources Group:
.a. Director-Systems Development (see paragraph 1.5.2.1).
- b. Dircetor-Information Resources Operations (see para-graphL1.5~2.2).
- c. Director-Information Resources. Administration (see paragraph 1.5.2.4).
- d. Manager-Information Resources Planning and Control (see paragraph 1.5.2.3).
- e. Director-Communication System (see paragraph 1.5.2.5).
1.2 3 The NUSCO Executive Vice President-Engineering and Operations is also the Executive Vice President-Engineering and Operations for NUPOC. ~ Specific nuclear relatea responsibilities rest with the following individuals who are responsible for. ensuring that the requirements of the NUQAP are carried'out within their respective groups.
- a. Senior Vice President-Nuclear Engineering and Operations (see Para. 1.2.4).
- b. Vice President-Transmission and Distribution Engineering and Operations (see Para. 1.5.3).
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Operations is also the Senior Vice President-Nuclear Engineering and Operations for NUPOC. He is responsible E
'for nuclear engineering,' construction, operation, mainte . g nance, modification and quality assurance. * '
1.2.4.1 'The responsibilities of.the Senior Vice President . Nuclear Engineering and Operations relating'to the Quality Assurance Program are described in the Nuclear Engineering and i Operations Policies and Procedures Manual., He has contact with quality assurance activities through the receipt of various documents such as: Weekly progress reports, Nuclear Review Board Meeting Notes and other reports, and audits related to NUPOC nuclear plant operations activities.
1.2.4.2 The Senior Vice President-Nuclear' Engineering and Operations is responsible to assess the scope, status,-implementation and effectiveness of the NUQAP. To meet this. responsibility, he appoints a qualified team of individuals to perform an annual Management Quality Assurance Review.
This Management Quality Assurance Review is:
- a. A systematic evaluation;
- b. Preplanned toward the objective of deter-mining the adequacy of the NUQAP and its compliance with Appendix B to 10 CFR Part 50_and other regulatory requirements;
- c. Capable of identifying, communicating and i l
tracking any required corrective action. '
The team is made up of individuals knowledgable in Quality Assurance, Quality Related Activities, ;
Auditing, Management Responsibilities, and the i NUQAP Topical' Report. I 1.2.4.3 The following division Vice Presidents report to the Senior Vice President-Nuclear Engineering j and Operations:
- a. Vice President-Generation Engineering and ;
Construction (see Para. 1.4.1) !
- b. Vice President-Nuclear and Environmental !
Engineering (see Para. 1.4.2)
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- c. 'Vice President-Nuclear Operations (see Para. 1.4.3) 1.3 RESPONSIBILITIES (Refer to Figure 1.6) 1.3.1 Overall responsibility for the'NUQAP is assigned to the NUSCO Manager-Quality Assurance who reports to the Vice President-Nuclear and Environmental Engineering through.
the Director-Nuclear Engineering and Operations Services.
These responsibilities include: direction of the Quality !
' Assurance program; implementation of policies, plans,.
requirements, procedures, and audits; verification to assure compliance with 10 CFR 50 Appendix B and other regulatory requirements;_and verification of the imple-mentation of the NUQAP Topical Report requirements.
1.3.2 Overall. responsibility for the implementation of the NUQAP Topical Report at the NUPOC Nuclear Plant is assigned to a NUPOC Superintendent. Each NUPOC Quality Assurance Super-visor, reporting to the appropriate NUPOC Superintendent, is responsible for verifying implementation of the requirements of the NUQAP Topical Report.
1.3.3 The head of each NU department or organization performing quality activities is responsible for:
- a. Administering those activities within his organiza-tion which are defined by the NUQAP Topical Report;
- b. Ensuring implementation of the Quality Assurance Program;
- c. Establishing and clearly defining'the duties and responsibilities of personnel within his organization who perform quality activities;
- d. Planning, selecting and training personnel to meet the requirements of the NUQAP Topical Report;
- e. Performing and coordinating quality matters within his department and interfacing with NUSCO/NUPOC Quality Assurance on quality activities.
1.3.4 Each individual, performing or verifying activities affecting quality, is responsible to conduct those activities in accordance with the requirements of the NUQAP and implementing procedures.
1.3.5 The responsibility, authority, and organizational relationship for performing quality activities within each QAP 1.0 Rev.: 10 Date:
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organization-is established and delineated in the NU i Organizational ~ Charts, jurisdictional statements, and written job or functional descriptions.
- 1. 4 NU PARTICIPATING GROUPS - NUSCO NUCLEAR ENGINEERING AND OPfRATIONS GROUP l.
The Senior Vice President-Nuclear Engineering and Operations Group is responsible for providing and directing projects and for providing technical and supp~ ort personnel to meet responsibilities during engineering, construction, preoperational and startup testing, modification, and operation of nuclear power plants.
The Nuclear Engineering and Operations Group is divided into three divisions:
I a) Generation Engineering and Construction (Figure 1.3);
b) Nuclear and Environmental Engineering (Figure 1.4); and !
c) Nuclear Operations (Figure 1.5).
The functions of the personnel, who perform quality activities within these divisions, are as follows:
1.4.1 The Vice President-Generation Engineering and Construction is responsible for engineering and design, and modifica-tion, backfit, and Generation Construction projects for existing NU generating facilities. The following department heads report to him: '(See Figure 1.3) 1.4.1.1 The Director-Generation Engineering and Design *
-Department is responsible to provide technical and support personnel to provide Project Engineers and support for Generation Construction projects in generating facilities directed by the Generation Projects Department.
Technical support is also provided for opera-tions and maintenance activities of the generating facilities. The Generation Engineering and Design Department provides expertise for systems, specifications and pro-curement of equipment and material; it provides design expertise for the preparation and main-tenance of design documents for generating facilities. These Generation Engineering and Design Department activities are performed by personnel within the following department branches:
- a. Mechanical Engineering; QAP 1.0 Rev.: 10 Date:
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- b. Electrical Engineering; !
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- c. Civil Engineering; 1 i
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- d. Engineering Design.
- l 4 1.4.1.2 The Director-Generation Construction Department
- i. . is responsible for.the following areas in ]
i generation facility projects: 1) the direction {
^ and coordination of processes and assurance of I necessary resources for construction; and j
- 2) coordination of startup activities with i NUPOC. When assigned projects, the department !
is responsible for providing construction j management and quality control services. The i department consists of:
- a. Generation Construction to oversee the construction and quality activities of 4 construction contractors for construction I work on generation facilities. I l
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- b. NUSCO Construction Quality Control to 1 l
perform quality control functions on items !
affecting quality, such as; inspection, j receipt control coordination among i applicable NU departments and outside I organizations (see Figure 1.6). {
1 1.4.1.3' The Director-Generation Projects Department is responsible to provide project management and l
- coordination of projects involving Generation !
Construction facilities performed by NUSCO for the NU operating companies. This activity includes but is not limited to projects involving Generation Construction and backfit modifications made to generation facilities.
The coordinating function includes cost and schedule control of projects and outage planning and scheduling for the operating companies.
Sections of this Department, which perform )
quality related activities, are:
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- a. Generation Projects-Millstone Unit No. I !
- b. Generation Projects-Millstone Unit No. 2 i i
- c. Generation Projects-Millstone Unit No. 3 !
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- d. Generation Projects-Connecticut Yankee l
- e. Cost and Schedule Control QAP 1.0 Rev.: 10 Date:
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1.4.2 The Vice President-Nuclear and Environmental Engineering is responsible for Nuclear Engineering and Operations Services (including: Quality Assurance, Reliability i
l Engineering, Generation Facilities Records, Nuclgar Materials and Chemistry, and Nuclear Safety Engineering);
Environmental Programs; Nuclear Engineering (including:
Radiological Assessment, Reactor Engineering, Licensing, and Nuclear Fuel); and Nuclear Training. The following department Directors report to the Vice President-Nuclear and Environmental Engineering (see Figure 1.4): l 1.4.2.1 l The Director-Nuclear Engineering and Operations j Services is responsible to direct and coordinate j the support services as required for nuclear and j Generation Construction projects and for NUSC0/
l NUPOC Departments during the design, construction and operation of nuclear power plants. He has reporting to him the following managers /
supervisors:
- a. The NUSCO Manager, Quality Assurance is responsible for the preparation and issuance l of the NUQAP Topical Report, and verification
) of the implementation of its requirements l
I by applicable NUSCO/NUPOC Departments.
Verification is performed by a planned program of audits / surveillance / inspections /
in process verifications by the quality assurance sections of operations, procure-ment, and engineering assurance. He provides management with objective evidence of the performance of activities affecting '
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 affecting activities are performed and is independent of undue influences and respon-sibilities for schedules and costs. Ne has the responsiblity and authority delineated l in writing, to stop unsatisfactory work and control further processing, delivery, or installation of nonconforming materials.
He also has the responsibility and authority to identify quality problems, to provide solutions, and to verify their implemen-tation. He maintains an overview of NUPOC quality assurance activities through a planned and systematic program of audits and surveillances.
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The following supervisors and their staffs report to the NUSCO Manager, Quality Assurance (see Figure 1.6):
- 1.
- Supervisor, Operations Quality Assurance.
- 2. Supervisor, Engineering Assurance.
- 3. Supervisor, Procurement Quality Assurance.
The Supervisor, Operations Quality Assurance assures that Quality Assurance responsibili-ties; as they relate to the operational phases and Generation Construction projects of nuclear power plants; are being imple-mented.
The Supervisor, Engineering Assurance assures that Quality Assurance responsi- i bilities; as they relate to design control of nuclear power plants; are being imple-mented.
The Supervisor, Procurement Quality Assurance assures that Quality Assurance responsibilities, as they relate to procurement activities for the nuclear power plants, are being implemented.
These supervisors have positions which are free from non-Quality Assurance duties and can give full attention to assure that the Quality Assurance Program is being effec-tively implemented and have appropriate organizational responsibilities and authority to exercise proper control over the Quality Assurance Program. They have the responsibility and authority to identify quality problems, to provide solutions, and to verify their implementation. Stop work orders initiated by NUSCO Quality Assurance personnel are delineated in writing with the concurrence of a NUSCO Supervisor, Quality Assurance and approved by the NUSCO Manager, Quality Assurance.
The responsibilities and duties of all
', NUSCO Quality Assurance personnel are described in NUSCO implementing procedures ;
and job descriptions. !
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- b. Manager, Generation Facilities Records is responsible to provide guidance by the establishment _of a corporate Nuclear Plant ;
Records Program and Manual for the effective operation of all: Northeast Utilitfes Nuclear Plant Records Facilities to meet corporate nuclear records objectives.
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- c. Manager, Reliability Engineering is responsible to establish and implement specific programs that are intended to monitor and to improve the reliability or capacity of the nuclear generating facilities.
- d. Manager, Nuclear Materials and Chemistry is responsible-to provide evaluations of nuclear plant coolant chemistry and materials and to implement controls in accordance with the Nuclear Plant Water i Chemistry Program,
- e. Manager, Nuclear Safety Engineering is responsible to provide nuclear safety ;
engineering evaluations of operational I experience at NU and industry nuclear power plants.
1.4.2.2 The Director-Environmental Programs is respon-sible for the planning, design, coordination and supervision.M all scientific engineering studies of problems related to-environmental impacts of NU activities affecting proposed and operating generation facilities. He has, reporting to him, the following Managers /
Supervisors: i
- a. Manager, Earth Sciences is responsible for the preparation of atmospheric dispersion ;
calculations required to estimate dose to i the public from both routine releases and
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postulated accidents. He provides criteria j and studies to assure that such calculations reflect state-of-the-art techniques and adequately support the corporate program for Nuclear Emergency Preparedness.
- b. Supervisor, Ecological Assessments provides statistical support to the NU Environmental Lab to ensure state-of-the-art statistical methods and techniques in all areas of the ecological monitoring programs.
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- c. Manager, NU Environmental Laboratory i
j directs ecological impact assessment 1 studies for the operating generation I facilities.
e k 1.4.2.3 The Director-Nuclear Engineering is responsible to direct and coordinate the activities of i Radiological Assessment, Generation Facilities l Licensing, Reactor Engineering and Nuclear Fuel.
The following managers report to Director-Nuclear Engineering:
- a. The Manager-Radiological Assessment is responsible to provide technical services in radiological matters relating to nuclear plant design and operation in nuclear and Generation Construction projects. It includes the studies of radiation exposure to plant personnel and the general public, i liaison with regulatory agencies, and {
responsibility for the corporate program j for Nuclear Emergency Preparedness.
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- b. The Manager-Generation Facilities Licensing is responsible for corporate liaison with the Nuclear Regulatory Commission and coordination of responses to regulatory requirements for new nuclear projects and changes to operating facilities. This includes the preparation and coordination of documents for submittal to various !
regulatory agencies,
- c. The System Manager-Reactor Engineering is responsible to provide reactor engineering, NSSS safety analysis, probabilistic risk assessments, fuel design, and reactor core analysis and performance evaluation services for new nuclear projects, Generation Construction projects, and operations of nuclear generation facilities. This includes services during reload of nuclear reactor cores, direction for optimal operations of reactor cores, evaluation of design and analysis of reactors, and NSSS transient evaluations.
- d. The Manager-Nuclear Fuel is responsible for the planning, scheduling and coordination of the nuclear fuel supply requirements for proposed and operating nuclear generation facilities. This includes contract '
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. engineering'for technical-administration of fuel contracts'and technical support for the procurement lof all elements of the nuclear fuel cycle, the handling of fuel- 'l removed from operating facilities,* and determination of nuclear fuel costs. !
. 1.4.2.4 The Director-Nuclear Training is responsible.for all Nuclear Training and Training Evaluation-activities.. The Department consists of the' Connecticut Yankee, Millstone, and the Berlin Nuclear Training Organizations.
1.4.3 The Vice President-Nuclear Operations is responsible for plant modifications, refueling, maintenance and operation of operating nuclear generation facilities. The division consists of a Nuclear Operations Engineering staff and the i NUPOC organizations (see Figure 1.5).
1.4.3.1 The Supervisor - Nuclear Operations is responsible for the coordination of activities between the NUSCO Engineering personnel and the NUPOC-personnel. An engineer is assigned to each NUPOC operating nuclear generating facility to perform the coordination of the activities. I 1.4.3.2 NUPOC Station Superintendents (Millstone and Connecticut Yankee) are responsible ~for the
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operation,. maintenance,' plant modifications,. j refueling and services of operating nuclear-generation facilities. They provide operational
- f. input ~to the Project Engineers for the design at i
nuclear land operating plant Generation Construction projects. -l
- a. NUPOC Station Services Superintendents.
(Millstone and Connecticut Yankee) report to the individual' Station Superintendents and are responsible for the service depart-ments of each station such as Security, Health Physics, Chemistry, Stores, Nuclear Records and Quality Assurance (see <
Figure 1.6).
p' b. At the Millstone Station only, the Quality Services Supervisor reports to the Station Services Superintendent and has respon-sibility for the areas of Stores, Records, and Quality Assurance (see Figure 1.6).
- c. The Millstone Quality Assurance Supervisor reports to the Quality Services Supervisor. j QAP 1.0 Rev.: 10 Date:
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.The Connecticut Yankee Quality-Assurance Supervisor reports to the CY. Station.
Services Superintendent.(see Figure 1.6).
The Quality Assurance Supervisors ,are responsible for the verification of the.
implementation ofithe NUQAP requirements in the operating nuclear generation facilities.
They provide nuclear-generation facility:
management and'the NUSCO Manager,' Quality-Assurance with objective evidence of the implementation of the Quality Assurance Program within the facility. .Their duties.
and organizational positions are described.
in NUPOC Procedures.
They have the. authority, organizational freedom, and are'sufficiently removed from undue cost and schedule-influences to Lperform quality assurance functions effec-tively. including responsibilities to:
(1) Stop. unsatisfactory work and control
.further processing, delivery'or.
installation of nonconforming materials'as delineated in writing; (2) Identify quality problems';;
(3) Initiate, recommend or provide solutions; and; (4) Verify implementation of solutions.
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The Millstone and Connecticut Yankee Quality Assurance organizations routinely attend ~and participate in daily plant work schedules and status meetings to assure they;are kept aware of day-to-day work
' assignments throughout.the plant. This also assures that1there is adequate Quality Assurance' coverage relative to procedural and inspection control, acceptance criteria, and Quality Assurance staffing and qualifi-cation of personnel to carry out Quality Assurance assignments for quality activities.
1.5 OTHER NU PARTICIPATING GROUPS 1.5.1 ADMINISTRATIVE SERVICES The System Director-Purchasing and Materials Management is responsible to the Senior Vice President-Administrative QAP 1.0 Rev.: 10 Date:
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i Services for procurement activities within NU. Reporting to the System Director-Purchasing.and Materials Management, are several Purchasing Directors and Managers responsible for: ,
- a. The procurement _of materials and services from
' qualified suppliers -in accordance with predetermined j commercial, technical, and quality requirements; ,-
- b. Issuing Purchase Orders / Contracts and changes thereto;
- c. Maintaining traceability of~ purchasing records from NUSCO/NUPOC;
- d. Processing of purchase requistions through to preparation for payment for the purchased item.
The System Director-Purchasing and Materials Management controls purchasing procedures.
1.5.2 INFORMATION RESOURCES GROUP (See Figure 1.7)
The Vice President - Information Resources Group is responsible for all information storage, handling and delivery systems at NU.
1.5.2.1 The Director - Systems Development is responsible for:
- a. The design, coding and implementation of !
computer systems in support of engineering and scientific functions at NU.
- b. The initial supply, life-cycle support and replacement of NU process computer systems including the nuclear plant computers and various special purpose systems,
- c. The design, coding, and implementation of ;
all computer systems in support of j business-related functions at NU.
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.I 1.5.2.2 The Director - Information Resources Operations j is responsible for- !
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- a. Mainframe computer system technical !
support.
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- b. The operation of all NU Data Centers.
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1.5.2.3 The Manager - Information Resources Planning and Control is responsible for:
- a. Evaluating new and emerging technglogies to determine their applicability to NU and their impact on strategic directions.
- b. Coordinating all Information Resources Group Software Quality Engineering activities including:
- 1. Development of software engineering standards detailing policies and procedures governing the development of computer software.
- 2. Identifying minimum documentation levels for all software requirements specifications, design descriptions, verification plans and verification reports.
- 3. Development of computer based systems for automated auditability and trace-ability, including source code libraries, object code libraries and executable load modules.
- 4. Application and review of software products which ensure traceability and auditability of computer programs.
- 5. Development of software system test plans.
- 6. Development of training and indoctri-nation programs in software engineering.
- 7. Monitoring compliance with all Infor-mation Resources Group Software Engineering standards.
- 8. Identifying deficiencies with existing Information Resources Group policies and standards relative to this NUQAP topical report.
1.5.2.4 The Director-Information Resources Administration is responsible for:
- a. Ensuring that data retention and ownership requirements are followed. ,
QAP 1.0 Rev.: 10 Date:
Page 14 of 15 1
i b' . Ensuring data-integrity.
- c. Setting' policy for. data' standardization.
'd. Overseeing the design, construction,-. tuning and recoverability process of physical' data-bases as part of application development. )
- e. Administration of the Information Resources Disaster Recovery Programs.
b f. Administration of the Information Re' sources Information Asset Security Programs.
P g. Maintaining awareness and understanding of !
f legislation and regulations pertaining to ;
l data security concerns.
1.5.2.5 The Director-Communication System is responsible for:
- a. Teleprocessing and distributed processing networks.
- b. Telecommunications 1.5.3 SYSTEM TRANSMISSION AND DISTRIBUTION L
The Vice President - Transmission and Distribution Engineering and Operations is responsible for quality related activities performed by groups within his organization. The System Superintendent-Transmission and j Test. reports to the Vice President-Transmission and )
Distribution Engineering and Operations and-is also i responsible for quality activities. The Superintendent--
Production Test reports to the System Superintendent-Transmission and Test and-is responsible for quality related production test activities which include:
- a. Providing electrical testing services to the Nuclear Plant Operating Companies (NUP00),
- b. Planning and coordinating periodic and corrective maintenance of electrical equipment.
- c. Conducting acceptance tests, calibrations, adjustments, functional checkout and commissioning of electrical' systems.
- d. Overseeing electrical preoperational ter. ting for nuclear generation facilities projects and startup l
testing for backfit/ Generation Construction projects, '
as requested.
QAP 1.0 Rev.: 10 Date:
Page 15 of 15
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i y i 2.0 QUALITY ASSURANCE PROGRAM 2.1 GENERAL REQUIREMENTS e
NortheastiUtilities (NU) has established a Quality Assurance Program (NUQAP) 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 herein and the attached Policy Statement, supplemented by the Quality Assurance Procedures, provide the primary basis ~of the Program and the NU Policy with regard to quality assurance. This Program is established 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.
It includes quality activities during the operation, maintenacce and modification of the in-service nuclear power plants.
The requirements of the NVQAP apply, as a minimum, to nuclear safety-related systems, structures and canponents as functionally identified in Appendix A, " Systems, Structures and Components" and
.other items or services which are specifically identified in each FSAR/FDSA addressing Section 3.2.1 of NRC Regulatory Guide 1.70.
The requirements additicinally apply to other quality programs as defined in Appendix G.
The requirements of the Program are implemented by Northeast Utilities Service Company (NUSCO), Nuclear Plant Operating Companies (NUPOC),
the engineer-constructor, contractors, suppliers and engineering service-organizations performing activities affecting quality systems, structures and components 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 maintained.
Training sessions'are documented, the content described, who attended, when they attended and the results of the training sessions.
l A periodic program review of the status and adequacy of the NUQAP is '
accomplished by NUSCO Quality Assurance audits, by Nuclear Review Board (NRB) Reviews, and by the independent audit team described herein and in QAP 1.0, Section 1.2.4.2. Organizations outside NU are required to review the status and adequacy of that part of the Quality Assurance Frogram for which they have designated respon-sibility.
l QAP 2.0 Rev.: 10 j Date: '
Page 1 of 6 r.
d j
,E q' , .
2.2 IMPIEMENTATION 2.2.1 Goals-and Objectives
'6 As stated in the Policy Statement of NU, the goa b of the
,, NUQAP are to maintain quality levels in an effective and t'
efficient? manner and to assure a high degree of functional
~,
' integrity and . reliability of quality systems, structures and components. To meet this goal, the following objectives of.the NUQAP have been defined:
i
- a. Define..through documented procedures, the quality activities tt9t apply to the design, fabrication,
, procurement, construction, testing, operation, !
rsfueling, maintenance, repair and modification of nuclear power plants;
- b. Establish, assign and document the responsibilities for the conduct of those activities affecting quality systems, structures and components; 3 1
.c. Establish confidence that (a) the design, fabrication, construction and operation of nuclear power generation facilities are performed in a manner consistent with NU Policies and (b) quality activities are performed i by responsible personnel, through a system of audits !
of those organizations with quality responsibilities;
- d. Appraise the%nior Vice President, Nuclear Engineering i and Operations of unresolved problems and trends I which cou1& havp a significant effect on nuclear b
power plant sa'ety J and; i b e. Prevent schedule delays and high cost due to poor
} quality.
2.2.2 Program D e mentation
- This NUQAP Topir.tl Report defines the NU nuclear policies,
, goals and o3jectives, and is used as guidance for the development of the various implementing divisional, departmental, branch, or section procedures. Revisions to the NUQAP Topical Report will be made as needed to reflect current requirements and descriptions of activities prior to implementation. These revisions will be made in accordance with a Nuclear Engineering and Operations Group Procedure.
Revisions to the NUQAP Topical Report, which reduce commitments previously 6ccepted by the NRC, are submitted {
to the NRC for review and approval prior to implementation. l
,'- I QAP 2.0 Rev.: 10 Date:
Page 2 of 6 A .
. .. .a
- v. - - -
Revisions which do not reduce previously accepted commitments are periodically submitted to the NRC as. required by 10CFR50.54(a)(3) and 10CFR50.55(f)(3).
Quality procedures are developed by the departments performing quality activities.
These procedures are reviewed by the departments which are responsible for portions of these procedures. These procedures are approved.by.the departments which initiate these procedures and are reviewed and concurred with by the applicable NUSCO/NUPOC Quality Assurance' Organization for compliance with the NUQAP Topical Report. 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 /NUPOC Superintendent is responsible for implementation of the NUQAP, which includes individuel departmental procedure requirements applicable only to his respective activities. In addition, he is responsible for the preparation, approval and distribution of those instructions, operating procedures, testing procedures or other instructions where further guidance is necessary.
2.2.3 Systems, Structures and Components The requirements of the NUQAP Topical Report shall apply, as a minimum, to all activities affecting the safety functions of the systems, structures, and componenta, as addressed in the Safety Analysis Reports (SARs). Safety systems, structures and components are functionally identified in Appendix A of the NUQAP Topical Report and also as specifically identified in each FSAR addressing l Section 3.2.1 of NRC Regulatory Guide 1.70.
For systems, components, and structures; covered by the ASME Code; NUSCO/NUPOC Procedures describe the measures taken to assure that the Quality Assurance requirements, contained in the code, are supplemented by the specific guidance of the applicable regulatory guides listed in Appendix D of this Topical Report.
For systems, components, and structures; covered by NUQAP Appendix G, Regulatory Commitments and NUSC0/NUPOC procedures describe the measures taken to assure that the Quality Assurance requirements are met.
The degree of control over activities affecting quality systems, structures and components is consistent with their importance to safety. Such controls include use of appropriate equipment, establishment of suitable environmental QAP 2.0 Rev.: 10 Date:
Page 3 of 6
conditions and assurance that all prerequisites for a given activity have been satisfied. This NUQAP Topical Report 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.
NUSC0/NUPOC Quality Assurance organizations and applicable
, NUSCO/NUPOC technical organizations jointly determine and identify the extent Quality Assurance controls are to be applied to quality structures, systems, and components.
The Quality Assurance controls are in conformance with this NUQAP Topical Report, which complies with the 18 criteria set forth in Appendix B to 10CFR Part 50.
2.2.4 Participating Organizations The NU organizations with responsibilities for activities affecting quality systems, structures and components are identified in QAP 1.0, which also briefly describes their assigned responsibilities.
NUSCO Quality Assurance is responsible for: a) the development, coordination, and control of the NUQAP including coordination of NUSCO Quality Assurance Branch Procedure review and approval; b) control and issuance of the NUQAP Topical Report as a controlled document (as described in QAP 6.0) and; c) review and concurrence with quality related procedures and revisions written by other departments. Procedure reviews will be performed in accordance with QAP 5.0.
NU shall require that their Engineer-Constructor, Nuclear Steam Supply System (NSSS), Suppliers, Engineering 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 Appendix D of the Topical Report. However, NU retains overall responsibility for the QA Program. The specific quality activities performed by these organizations are specified in the procurement documents. NUSCO Quality Assurance reviews and approves these organization'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, contractors, suppliers and engineering service organizations have an adequate quality assurance QAP 2.0 Rev.. 10 Date:
Page 4 of 6 1
program to meet the applicable requirements of Appendix B to 10 CFR, Part 50.
In addition to the initial review, the engineer-construc-tor, contractors, suppliers and engineering servfce organizations quality assurance programs shall be periodi-cally audited by NUSCO/NUPOC Quality Assurance to assure continued implementation of quality requirements.
Contractors may be delegated the execution of quality assurance functions by contract. These contracts are reviewed and approved in accordance with NU QAP requirements.
2.2.5 Indoctrination and Training l A program is established and maintained for quality 1 assurance indoctrination and training which provides '
confidence that the required level of personnel competence and skill is achieved and maintained in the performance of quality activities. Quality procedures delineate the requirements for an indoctrination program to assure that personnel responsible for performing quality activities are instructed in the purpose, scope and implementation of quality procedures and instructions and that compliance to these documents is mandatory. The NUSCO Manager, Quality Assurance is responsible for the indoctrination of personnel within his department who perform quality activities.
Nuclear training programs shall be developed and implemented to provide training for all individuals attached to or associated with NU nuclear facilities. Additional guidance is established in NUSCO/NUPOC Procedures.
Implementing NUSCO/NUPOC Procedures describe the nuclear training program requirements which assure that:
- a. Documentation of formal training and qualification programs includes the objective, content of the program, attendees, and date of attendance;
- b. Proficiency, of personnel performing and verifying activities affecting quality, is established and maintained. Personnel proficiency is established and maintained by training, examination / testing, and/or certification based upon the requirements of the activity. Acceptance criteria are developed to determine if individuals are properly trained and qualified.
- c. Certificates or other documentation of qualification clearly delineate the specific functions personnel QAP 2.0 Rev.: 10 Date: )
Page 5 of 6
{
are qualified to perform and the criteria used to qualify personnel in each function.
This program also requires the head of each department (including NUSCO/NUPOC Quality Assurance) to be gesponsible for a training plan which assures that personnel perform-ing quality activities are trained in the principles and techniques of the activity being performed.
-2.2.6 Management Participation NUSCO Department Heads /NUPOC Superintendents are respon-sible for implementing the NUQAP Topical Report within their Departments / Plants. The NUSCO Manager, Quality Assurance will assist in development, coordination and review of the 'J Program.
A management review of the Program is conducted on an annual basis, by an independent audit group, to assess the l scope, status, implementation, effectiveness and to assure compliance to NRC licensing commitments. The Management Review Committee is appointed by the Senior Vice President -
Nuclear Engineering and Operations. He ensures that deficiencies are tracked and resolved, and advises upper management of the results of the audits.
Actions considered by the Management Review Committee may include, but are not limited to, the following:
- a. Review of selected procedures and documents,
- b. Verification of the implementation of selected procedural requirements
- c. Review of past audit results such as those conducted by previous Management Review Committees, the NRC, or other departments.
The Review Committee's findings of deficiencies and ,
recommendations for program improvement are forwarded to j the Senior Vice President - Nuclear Engineering and Operations, who will ensure appropriate corrective action is taken.
The quality assurance programs of the engineer-constructor, NUSCO contractors, suppliers and engineering service organizations that perform quality activities are reviewed i by NUSCO Quality Assurance to assure that their management ;
regularly reviews the status and adequacy of their part of the NUQAP.
l1 4
QAP 2.0 Rev.: 10 Date: !
Page 6 of 6 l
__ J
3.0 DESIGN CONTROL 3.1 GENERAL REQUIREMENTS e
The NUSCO/NUPOC is responsible for controlling design work, administering design control activities (including design interface) and design modifications for quality systems, structures and com-ponents.
The NUQAP for design is established to assure that the applicable design requirements, such as design bases, regulatory requirements, codes, technical standards and quality standards are identified in design documents which are reviewed, approved and controlled in accordance with established procedures. Such controls include review for suitability of application of materials, equipment, parts and processes that are essential to the functions of the systems, structures and components. Changes to and deviations from specified requirements are identified, documented and controlled.
The responsibility for design control program implementation rests with NUSC0/NUPOC for all NU nuclear generating facilities. The division of responsibilities and jurisdictional boundaries are set forth in Nuclear Engineering and Operations Procedures (NE0s).
Although other organizations may be delegated the task of establishing and executing the design control program or any part thereof, NUSCO/NUPOC will retain the ultimate responsibility for the program.
The applicable requirements of the NUQAP will be imposed on other organizations delegated the task of establishing or executing the program in accordance with QAP 4.0 and QAP 7.0.
The interface controls, both internal and external, for organiza-tions performing design work for quality systems, structures and components are identified and implemented in accordance with documented procedures. This identification includes those organizations providing criteria, designs, specifications and technical direction.
Measures are applied to verify the adequacy of design. The extent of design verification is specified and documented by the respon-sible 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, o- (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 are required for the change, including evaluation of the effects of those changes on the overall design. Design verification may be accomplished by testing. Tests to demonstrate adequacy under i
QAP 3.0 Rev.: 10 Date:
Page 1 of 6 j
i
. adverse design' conditions shall comply with the requirements of QAP l 11.0;.." Test Control". Design errors and deficiencies which ad-versely affect quality. systems, structures and components in the :f
. design. process are documented, and appropriate corrective action is taken..Thesedesignerrorsanddeficienciesaredocumentedin.
accordance 'with design' change precedures 'or as defined in QAP 15.0, 3.2 IMPLEMENTATION NUSCO/NUPOC:is responsible for the design, design review, engineering approval of design changes, design evaluation and design control.of.
. nuclear. power plants. The function may be delegated to other.
organizations-to perform the design activity, or any part thereof, but the' responsibility for overall design remains with NUSC0/NUPOC.
'In all cases, final. engineering decisions and. ultimate design
[. control-of systems, structures and components related to nuclear.
L power plants is the responsibility of NUSCO/NUPOC.
p l-
' NUSCO/NUPOC Quality Assurance performs audits /surveillances/inspec-tions/in-process. verifications to verify that the engineer-constructor, contractors, suppliers, engineering service organizations and NU departments are effectively complying with the NUQAP and procedural requirements for design control.
3.2.1 Design Process Design contro1' measures are applied to design analyses, such as,. reactor physics, stress, thermal, hydraulic, nuclear radiation, accident and r.eismic analyses; compat-
- l. ibility,of materials; accessibility for in-service inspec- 1 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 j 6.0. i l
Prograin procedures and instructions define the' method for !
implementing design control measures. These measures i
require that applicable design requirements, such as, i design bases, regulatory requirements, codes and stand- !
ards, 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" l commercial or previously approved items essential to the !
quality 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.
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i ii NUSCO Procedures assure'that a documented' check'is performed-
~
-to. verify the: accuracy and completeness of design drawings and specifications before release,toLeonstruction. Design
? drawings receive a documented check to verify dimensional..
accuracy.
+
Design drawings and specifications issued for plant design changes during the operations phase of an in-service nuclear plant are reviewed for completeness and ' accuracy-before release to. operations in'accordance with NUSCO/NUPOC Procedures. Drawings are reviewed for accuracy and.
completeness in'accordance with NUSC0/NUPOC Procedures defining Document Control.
NUSC0/NUPOC Procedures describe the provisions to assure
- that design. drawings and. specifications are prepared, reviewed and' approved.in accordance with company procedures, and that the documents contain the necessary Quality
-Assurance requirements, such as inspection and test' requirements, acceptance requirements, and the extent of documenting inspection and test results.
3.2.2- -Design Change Control Procedures and instructions governing design change control during 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.
An independent review and approval of design changes is performed by the organization that. conducted the original.
design reviews, unless NUSCO/NUPOC designates another e qualified organization to perform this function.
Proposed design change / modifications are submitted to the in-service units management'for processing and review.
This review includes the Plant Operations Review Committee (PORC)/ Site Operations Review Committee (SORC). PORC/SORC is advisory to the appropriate NUPOC Superintendents on matters relating to nuclear safety. Its. composition, responsibilities, and authority are defined in Section 6 of each in-service unit Technical Specification. NUPOC QA personnel can be represented at the PORC/SORC Committees if assigned by the appropriate NUPOC Unit Superintendent.
If the change involves a quality system, structure or component, the change will be reviewed by qualified QAP 3.0 Rev.: 10 Date: 1 Page 3 of 6 l.
engineering personnel for technical adequacy.
the design change requests are performed Reviews of by ther Nuclea environmental questions. Review Board / Environmental Review The sequence of the NRB review )
depends safety upon isthe question determination of whether an unreviewed involved.
(i.e. , in accordan(e with ANSI N18.7, . if a proposed change in the facility involves an unreviewed safety question then the NRB review is conducted prior to implementation.)
)
t p
PORC/SORC and NRB/ ERB are performed to! assu a.
the adequacy of the proposed change is determined; >
b.
i perly identified and handled per 10 CFR 50.59;unre c.
nuclear safety / environmental requirements have been considered.
p Errors and deficiencies in design, including the design l
process, that could adversely affect quality structures systems, and components are documented and corrective ,
action is taken to preclude repetition.
During the operations phase, notification of plant design changes are transmitted to responsible plant personnel as part of the design package close out.
describe this notification which-assures that personnelNUSCO/NUPOC Proc affect the performance of their duties.are made aware of design 3.2.3 Design Interface Control During design, construction or modifications of nuclear power plants, the Nuclear Engineering and Operations Group is design of responsible for review, coordination and documentation interfaces.
identification of design interfaces, design interfaceProcedures prov changes, documents. and modifications affecting drawings and design 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 .
i During the operations phase, procedures and instructions identify design interfaces which are controlled by the appropriate NUPOC Superintendent.
interface questions are documented. Resolution of design i
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l 3.2.4 Independent Design Verification Original designs and design modifications are reviewed for 4
adequacy and the sign-off performed by a person other than the originator of the design. Design verificati8n is 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 i personnel. Ultimate responsibility for design adequacy l and evaluation is retained by NUSC0/NUPOC, as appropriate.
l Design verification (if other than by qualification l
! testing) is normally completed prior to release for procurement, manufacturing, and construction, or to l
another organization for use in other design activitit..
For those cases where design verification cannot be completed prior to release for procurement, manufacturing, and construction, procedures ensure that design verification is completed prior to the point when the installation is i
declared operational.
NUSCO/NUPOC Procedures describe the requirements which assure the following when testing is considered as an
- alternate method of design verification
- a. Specifications or procedures provide criteria that ,
specify when verification should be by test.
- b. Prototype, component or feature testing is performed as early as possible prior to installation of plant equipment, or prior to the point when the installation is declared operational.
- c. Verification by test is performed under conditions that simulate the most adverse conditions as determined by analysis.
Particular emphasis is placed on assuring that designs are in conformance with appliceble codes, and on selecting the proper design verification or checking method. Procedures and instructions provide the requirements and necessary controls for design verification. These controls include a review to assure that design characteristics can be l controlled, and verification that there is adequate accessibility for inspection or test, and that inspection and test acceptance criteria are incorporated. During the l operations phase, documentation of reviews is provided.
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NUSCO/NUPOC Procedures include requirements which identify the responsibility of. design verifiers, the areas and features to be verified, and the extent of the documentation.
NUSCD/NUPOC Procedures assure that procedural control is established for design documents that reflect the commit-ments of the SAR. These procedural controls vary for design documents which receive formal design verfication i
by several. disciplines or organizations, and those which can be reviewed by a single individual. The specific design documents and specialized reviews are determined and used as required by the design changes and modifications.
NUSCO/NUPOC Procedures are established to assure that verified computer codes are certified for a specific use.
During the design and construction phases, the NUSCO Project Engineer maintains the ultimate responsibility for the design documents generated by the engineer-construc-tor, NSSS supplier and other NUSCO departments. The evaluation of selected documents by project engineers may be accomplished with assistance from other NUSCO depart-ments concerned with the equipment / subject covered by the doemnent being evaluated.
The NUSCO Project Engineer is responsible for the resolution of NUSCO comments on specifications and drawings issued'by the engineer-constructor, NSSS supplier, and contractors.
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, m 4.0 PROCUREMENT DOCUMENT CONTROL I
4.1 GENERAL REQUIREMENTS-' i P
-The procurement of materials,. equipment, parts and/or services required during the design,: construction, operation and maintenance .i of-quality systems, structures and components in nuclear power plants.is performed in a controlled manner which assures compliance with applicable regulatory requirements, procedures, quality assur-1 ance standards ~and regulations affecting procurement documents.
Changes to procurement documents are subject _to the same' degree of control as utilized'in the preparation of the' original documents.
4.2: IMPLEMENTATION 'l '
'4.2.1 Program j
a A Project Manager and a Project Engineer are selected for each major modification to an in-service nuclear power ]
plant. The project engineer coordinates the preparation, -
review and approval of procurement documents for quality-material, equipment,. parts.or' services, and ensures the c
f
' technical adequacy and inclusion of quality assurance 3 requirements.
During the operations phase of nuclear power plants, 1 NUSCO/NUPOC Purchase Requisitions are reviewed for technical j adequacy and. verification of the quality designation. 'The 4ppropriate NUSCO Project Engineer /NUPOC Superintendent reviews and approves NUSCO/NUPOC Purchase. Requisitions.
NUSCO quality. assurance personnel then review the purchase requisition, for the inclusion and' adequacy of quality assurance requirements, prior to the issuance of the ;
purchase order.
During design, construction, preoperational testing and operation of nuclear power plants, and modifications thereto, the engineer-constructor, contractors, suppliers and engineering service organizations utilized by NUSCO/
NUPOC are responsible to implement measures for control of '
procurement documents associated with quality material, j equipment, parts and services to ensure applicable requirements including quality assurance requirements are specified. NUSCO Quality Assurance performs on and off-site audits /surveillances/ inspections /in-process verifications to ensure organizations utilized by NUSCO/ 1 NUPOC are effectively complying with their requirements for the control of procurement documents.
QAP 4.0 Rev.: 10 J Date: J Page 1 of 4 {
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Changes to procurement documents, whether initiated by NUSCO/NUPOC or their representative, are subjected to the i
same degree of control as that utilized in the preparation of the original document. The procurement of spare or replacement parts for quality systems, structurel or components is subject to the controls of the latest NU QA-Program and NUSCO/NUPOC procedure requirements. The spare or. replacement parts are subject to controls equivalent to original.or subsequent codes and standards.
QA review of procurement documents determine that:
- a. .The quality requirements are correctly stated, inspectable and controllable; ,
- b. There are adequate acceptance and rejection criteria;
- c. The procurement document has been prepared, reviewed, and approved in accordance'with the NU QA program requirements.
4.2.2 Procurement Document Provisions Procurement documents are prepared, reviewed and approved in accordance with approved procedures of the issuing organization or department and are documented prior to release and available for verification. These procedures require that procurement documents consist of the follow-ing, as necessary:
- a. The scope of work to be performed;
- 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;
- c. Quality Assurance Program requirements to be imposed on contractors which include the applicable require-ments of 10 CFR 50, Appendix B, and the NRC regula-tory position 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 appropriate, for access to contractor facilities and records for inspection or audit by NUSCO or its designated I
QAP 4.0 Rev.: 10 Date:
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representative; and provides access for events such as those requiring notification of hold points;
- e. The documentation required to be prepared, Tnain-tained, and/or submitted to NUSC0/NUPOC or its f representative for review, approval or historical j
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, contractor, or supplier is j 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 procurement prior to issuing the purchase order for the 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 charac-teristics 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 organizations with !
unapproved quality assurance programs. These procurement documents to unapproved organizations contain detailed supplementary quality assurance requirements to meet NUSCO requirements. {
Procurement documents are reviesed by NUSCO/NUPOC Quality Assurance to ensure appropriate quality assurance require-ments are specified. These requirements, included in the procurement document as necessary, include audits and l inspections at the suppliers facilities with scheduled 1
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witness / hold points and acceptance criteria during the fabrication and process of the procurement item. 'Accep-tance inspections-and tests determined by NU,shall be performed after receipt at NU but prior to operay on.
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5.0 PROCEDURES, INSTRUCTIONS, AND DRAWINGS
'5.1 ' GENERAL REQUIREMENTS *
- The NUQAP provides measures for the preparation,. review, approval,
. control and distribution of procedures, instructions and drawings of activities affecting quality systems, structures and components
'during design, construction, preoperational testing and operation of l nuclear power plants. These documents include appropriate quantita- 1 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 Procedures provide direction for personnel performing l quality functions. -The applicable NUSCO/NUPOC Quality Assurance Organization reviews and concurs with Quality Procedures. Comments .l concerning compliance with the NUQAP Topical Report and regulatory requirements are resolved prior to issuance of the procedure. NUSCO !
Quality Assurance receives controlled copies of Quality' Procedures '
issued by other departments. During the design, construction and l procurement' phases, the engineer-constructor, centractors, 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 NUPOC' Superintendent, NUSCO Director /
Generation Construction, or Project Engineer, as appropriate. In this case,.NUSCO. Quality Assurance performs on-site and off-site audits /surveillances/ inspections /in process verifications of the i quality assurance programs.to ensure the engineer-constructor, j contractor, suppliers and engineering service organizations are i effectively complying with'their requirements for procedures and instructions. Contractor programs are required to clearly delineate i j
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.
{
5.2.1 Procedures and Instructions )
j Procedures and instructions for activities affecting quality are prepared, reviewed, and approved in accordance with written procedures and instructions.
During the design and construction phase, NUSCO Director /
Generation Construction, or Project Engineer, ensures that' contractors, suppliers and engineering service organi-zations implement quality assurance programs which contain written instructions for preparation, review and approval i QAP 5.0 Rev.: 10 Date:
Page 1 of 2 s
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of procedures and instructions affecting quality. In j addition, Contractor's site construction procedures and '
quality control inspection procedures are reviewed for.
concurrence by NUSCO Quality Assurance to assure compliance with the Program.
The NUPOC organization is responsible for the preparation, !
review and approval of plant Quality Procedures. These l l procedures include preoperational and startup test ' procedures l and overall site administrative procedures which implement the requirements;of the NUQAP Topical Report. Each NUPOC organization is also responsible for the preparation, J review and approval of procedures covering quality activities l in accordance with individual license requirements. The applicable NUSC0/NUPOC Quality Assurance Organization l i
reviews and concurs with inspection plans, tests, calibra-tions and special process procedures, and changes thereto.
5.2.2 Drawings The design control and verification measures described in QAP 3.0, are applicable for the review and approval of d rawings . 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 and review activities, or any part thereof, but retains ultimate responsibility for this work.
The measures taken to assure the preparation of as-built drawings and related documentation in a timely manne.r to accurately reflect the actual plant are described in NUSCO/NUPOC Procedures. Drawings critical to operation are updated prior to system turnover to operation and are available to the operating personnel.
5.2.3 Acceptance Criteria Cognizant Department Heads review and approve dept.rimeutal procedures, instructions and drawings to ensure the inclusion of adequate quantitative and qualitative accep-tance criteria, as appropriate, for determining satisfact-ory work performance and quality compliance. These criteria apply to activities such as design, operations, test control, inspection and plant modifications.
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I 6.0 DOCUMENT CONTROL 6.1 GENERAL REQUIREMENTS The NUQAP 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 quality systems, structures and components in accordance <
with NUSC0/NUPOC quality'related procedures and 10 CFR 50, Appendix B.
Documents such.as procedures, instructions, drawings, specifications and reports are prepared, reviewed for appropriate qualitative and quantitative acceptance criteria, and approved by authorized person-nel in the affected organization. Approved controlled documents are distributed to affected locations in accordance with controlled distribution lists. Changes to controlled documents are reviewed 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 I preclude the possibility of the use of outdated documents.
6.2 IMPLEMENTATION 6.2.1 g sponsibility-F NUSCO/NUPOC 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 quality systems, structures and componentt during design, construc-tion, preoperational testing, operation and major modifi~
cations thereto such as:
- a. Design Specifications;
- b. Design, Manufacturing, Construction and Installation Drawings;
- c. As-Built Documents.
- d. Quality Assurance Program Manuals, Procedures and Instructions;
- e. Manufacturing, Inspection and Testing Instructions;
- f. Test Procedures; QAP 6.0 Rev.: 10 ,
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- g. Preliminary Safety Analysis Report;
- h. Facility Description and Safety Analysis;
- i. Final Safety Analysis Report;
- j. Procurement documents;
- k. Design Change requests;
- 1. Topical Report;
- m. Nonconformance Reports;
- n. Computer Codes.
NUSCO/NUPOC Procedures describe the measures taken by NUSC0/NUPOC Quality Assurance or individuals other than the person who generated the document but qualified in quality assurance, for the control of documents to assure review and concurrence, as necessary, for such documents listed above with regards to Quality Assurance-related aspects.
The requirements for control of procurement documents are contained in QAP 4.0. During all phases of plant life, it is the responsibility of each organization issuing con-trolled documents to employ document control procedures.
The issuing organization is additionally responsible for distribution of the documents to appropriate locations.
There shall be provisions to assure that approved changes are included in instructions, procedures, drawings and other documents prior to implementation of the changes. !
During the design and construction phase, the engineer- :
constructor, 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 I complying with the requirements for document control. J' NUSC0/NUPOC Quality Assurance performs periodic on-site and off-site audits /surveillances/ inspections /in process verifications of the engineer-constructor, contractors, ,
suppliers and engineering services organizations to verify l compliance with their approved quality assurance programs.
l 1
6.2.2 Distribution of Controlled Documents
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NUSC0/NUPOC Procedures, specify in what manner controlled documents and revisions thereof, are distributed to appropriate locations, prior to commencing the work.
l QAP 6.0 Rev.: 10 Date:
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l Holders of controlled copies of documents' complete acknow-ledgement of receipt forms and return them to the distri-butor in order to assure that obsolete or superseded L
documents'are removed from the work areas in a timely l
manner. NUSC0/NUPOC Quality Assurance perform periodic on-site and off-site Audits /Surveillances/ Inspections /
In-Process Verifications to verify compliance with the requirements of procedures for document control.
6.2.3 Drawing Control The NU Generation Facilities Records Organization is responsible ta implement a program, as per approved procedures, for the retention and retrieval of drawings I and. records submitted by the cognizant NUSC0/NUPOC project personnel. The NU Generation Facilities Records Organi-zation maintains a drawing status file for in-service units which includes drawings newly issued or revised with latest revision and current status.
The engineer-constructor, contractors, suppliers and-engineering service organizations utilized by NUSCO/NUPOC during the design, construction and ma.jor modification to
- nuclear power plants may be delegated the function of drawing control and must furnish periodic status reports listing the revisions of applicable drawings which they issue.
NUSC0/NUPOC Quality Assurance performs on-site and off-site audits /surveillances/ inspections /in process verifications of suppliers to verify they are effectively complying with their programs for document control of drawings.
If the engineer-constructor, contractor or supplier is not !
delegated the function of drawing control, the Project L Engineer is responsible for the distribution of drawings to appropriate NUSC0/NUPOC personnel in accordance with controlled distribution lists.
6.2.4 Instruction and Procedure Control !
During the design and construction phase, the engineer-constructor, contractors, suppliers and engineering service organizations are responsible for control of quality procedures and instructions issued by them.
NUSC0/NUP0C Quality Assurance performs on-site and off-site audits /surveillances/ inspections /in process verifications !
of the engineer-constructor, contractors, suppliers and engineering service organizations quality assurance programs to ensure they are effectively complying with ,
their program for control of procedures and instructions. !
QAP 6.0 Rev.: 10 Date:
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.The originating department is responsible for establishing adequate control over quality 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. i l
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7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 7.1 GENERAL REQUIREMENTS ,,
l l
Measures for the control of procured material, equipment, parts and I services by or for NU related to the safety of nuclear power plants l are established and imposed by the NLyAP during design, construction, j preoperational testing, operation, mainter.ance and major modification, j to ensure conformance to procurement doeurients. 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 sul-contractors is assessed q
for effectiveness at intervals consistent with the importance, 4 complexity and quantity of the product or service, f 7.2 IMPLEMENTATION I
The word supplier is used in this section to designate what is '
otherwise described as the engineer-constructor, contractor, supplier or engineering service organization.
The evaluation and selectior. of suppliers is performed in accordance with procedures, which specify that procurement source evaluation and selection measures are performed to determine supplier capabil-ity and delineate responsibilities of qualified personnel involved in the evaluation and selection process.
7.2.1 NUSCO Quality Assurance 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 /other utility supplier evalua-tions;
- c. Coordinating Agency for Supplier Evaluation (CASE) evaluations.
- d. ASME N, NA, NPT, NV, or MM/MS Certificate of Authorization.
Evaluations ensure that NU suppliers employ a quality assurance program that conforms to applicable portions of the NUQAP Topical Report. NUSCO Quality Assurance maintains documented evidence of the evaluation and acceptance of 6
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- r' the supplier's . quality assurance program. ' The determination of supplier' approval is based on such. factors as prior performance, historical quality performance data,. audits,. 'l and' evaluations of the supplier's quality assurabee program.
Suppliers Certificates of Conformance are periodically evaluated by. audits, independent' inspections and. tests, to-assure-they are valid. This verification of Certificates- l of Conformance is documented.
.7.2'.2 Source Inspection NUSCO Quality-Assurance is responsible for the performance-of source inspections at suppliers; facilities to ensure i that'the requirements of a Purchase Order / Contract have been met.
Surveillances of suppliers are performed in'accordance with written procedures which provide for:
.I
- a. The method of surveillance and the ' extent of docu- '
mentation required and those responsible for imple-
- y. menting those instructions; j
- 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 NUSCO Construction Quality Control /NUPOC Quality Assurance in accordance with quality procedures which delineate requirements-and responsibilities necessary. )
to perform inspection functions. Contractua1' obligation i fulfillment and quality assurance requirements are veri- 'l fied 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 prede- ;
termined inspection instructions prior to installation or l use. Receipt inspections include, as appropriate: '
a.- Measures for verifying that the shipment is complete,-
properly identified, undamaged and corresponds with the receiving documentation; 1 i
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Measures for inspection of the. item and review of supporting docuaentation (e.g., mill test reports, NDE reports) as required by the purchase.doeuments; p
c.
Measures for inspection and acceptance of items to inspection instructions; rd.
Measures for identifying and controlling acceptable items including identification of inspection' status
. prior- to release from the receiving inspection area; e.
Measures for' identifying, segregating and handling
-nonconforming items; 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.
Docmaentation 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 requirements which have not been met, together with a description of those nonconformances dispositioned
" accept as is" or " repair".
The responsible NUSCO/NUPOC QA/QC personnel shall review for acceptability these documents which pertain to the requirements in the procurement document, in accordance with the NUQAP Topical Report and its. applicable procedures.
7.2.5 NUSCO/NUPOC Procedures address the measures taken to assure that for nonengineered "off-the-shelf" items, where specific quality assurance controls for nuclear applications cannot be imposed in a practicable manner, special verification ,
requirements are established and described. i QAP 7.0 Rev.: 10 Date:
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These measures follow the guidance in Regulatory Guide l.144, paragraph.C.3.b(1) and Regulatory Guide l.123 and applicable paragraphs of Section 10 of ANSI N45.' 2.13.
These measures include appropriate requirements for special-cagpgorization-and identification.within the procurement document,-
receiving. inspection, and additional controls during the installation and testing process to be performed by
' applicable.NUSCO/NUPOC Quality Assurance organizations .
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'l 8.0' IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND' COMPONENTS Sil ~ GENERAL REQUIREMENTS e NUSCO/NUPOC organizations assure that the identification of
', inspections, tests, and operating status of. structures, systems, and components isik nown by affected organizations.
The NUQAP provides measures for the identification and control of !
, material, parts and components,-including partially fabricated l assemblies,'during' design, construction, preoperational testing, f 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, 3 part number,; serial number, or other appropriate methods, and is i physically marked.on the item and/or.'on records traceable to_the {
' item. Documentation associated with material, equipment, and '
.' components verify that these items have been designed, fabricated, manufactured, tested,~ and inspected in accordance with specified requirements. . The object of these controls is to prevent the use of- 1 1
' incorrect or defective material,-parts and components, in accordance-
~
with 10 CFR 50, Appendix B. !
8.2' IMPLEMENTATION j
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:
1
- a. Requirements for traceability to appropriate' documentation such as: j procurement documents, manufacturing documents, drawings, '
specifications, certifications, inspection and test records, and nonconformance reports. )
- b. Controls to assure that the correct identification of an item i
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 specifications, drawings, procurement documents, procedures or instructions. !
During the design, construction, preoperational testing, operation, i maintenance or modifications to nuclear power plants, NUSCO/NUPOC
.'may delegate any portion of the implementation of the identification and' control program to the engineer-constructor, contractors, QAP 8.0 Rev.: 10 Date:
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suppliers and-engineeririg service organizations, as appropriate. If delegated, contracts require that the contractor establish an identification and control program which meets the NUQAP Topical Report requirements. In this case NUSCO/NUPOC Quality Assurance performs on-site and off-site audits /surveillances/inspecti*ons
/in-process verifications of the engineer-constructor, contractors, suppliers,-engineering service organizations quality assurance program to ensure they are effectively complying with their require-ments for identification and control of material, equipment and components.
Receipt inspections are performed to verify that material, equipment and components are properly identified in accordance with procurement requirements. NUPOC Quality Assurance /NUSCO Construction Quality Control is responsible for assigning and applying permanent identi-fication to;the items in accordance with approved procedures. If .i 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 and are identified and controlled in accordance with QAP 15.0.
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' )k['y 9.0 CONTROL OF SPECIAL PROCESSES 9.1 GENERAL' REQUIREMENTS
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The NUQAP provides measures to-sssure control of special processes associated with quality systems, structures and components by the use of qualified, approved procedures, equipment and personnel during design, construction, preoperational testing, operation, maintenance and major modifications to nuclear power plants. ,
q 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.
I 9.2 IMPLEMENTATION During design and construction of nuclear power plants the NUSCO Project Engineer is responsible for ensuring that special process ,
data and' documentation is reviewed, and that 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.
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 opera- g tion phase of nuclear power plants the responsibility for control of j special processes, when applicable, is delegated to the engineer- j constructor, contractors, suppliers and engineering service organi- {
zations utilizing special process procedures which are approved. ;
Personnel and equipment involved in special process procedures are '
qualified prior to the start of work. NUSCO/NUPOC Quality Assurance personnel perform on-site and off-site audits /surveillances/ inspec-tions/in-process verifications to ensure the engineer-constructor, contractors, suppliers, and engineering service organizations are effectively complying with their quality assurance program require-ments for control of special processes.
9.2.1 Procedure Qualification and Control NUSCO/NUPOC Procedures specify that written process control documents are utilized and qualified, as required, in accordance with applicable specifications, codes or standards.
QAP 9.0 ;
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g 9.2.2 . Personnel Qualification and Certification 1 !
Codes, standards and NUSCO/NUPOC procedures specify personnel qualification / certification requirementp.
Personnel responsible for the performance and verification of special processes are trained, tested, and certified as required by applicable specifications, codes and stand-ards. 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 applic- l able codes, standards, specifications, and contract or i procurement document requirements.
l The NUSCO Manager, Quality Assurance is responsible for the training, testing, and certification of all NUSC0/
NUPOC NDE personnel in accordance with the requirements of p Regulatory Guide 1.58 (Rev. 1, 9/80) and ASNT Recommended ;
Practice No. SNT-TC-1A.
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During construction, NUSCO Director / Generation Construction, and Manager-NUSCO Construction Quality Control are respon-y sible for the review of records of qualified personnel, equipment and procedures associated with special processes. I During preoperational testing and operation of nuclear power plants, the NUPOC Quality Assurance Supervisor is responsible for the review of these records. 1 9.2.3 Special Process Records Records provide objective evidence that special processes were performed in accordance with approved procedures, by 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 {
supplied to NUSCO/NUPOC as required by contract or purchase orders. If records are to be retained by the supplier, the contract or purchase order specifies the retention period and instructions for final disposition of records.
During construction, NUSCO Director / Generation Construction, and Manager-NUSCO Construction Quality Control are respon-sible for the review of documents for acceptance, and for assuring that documents for special processes utilized q 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.
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e Special process documentation such as: special process procedures, qualifying data, and personnnel and equipment qualification records associated with the performance of special processes at nuclear power plants, are kqpt current and maintained in appropriate NUSCO/NUPOC files, with final disposition to the appropriate NU Nuclear Plant
, -Records' Facility.
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i 10.0 INSPECTION '
10.1 GENERAL REQUIREMENTS ,
Inspection of activities to verify the quality of systems, structures and components, which are performed by or for Northeast Utilities
' (NU), are executed in accordance with the Quality Assurance Program (NUQAP) 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. Inspection notification and hold points are identified, as required, in the applicable documents.
10.2 IMPLEMENTATION '
10.2.1 Inspection Responsibilities During the construction phase, NUSCO/NUPOC Quality Assur-ance performs audits /surveillances/ inspections /in-process verifications to verify that the engineer-constructor, contractors, suppliers and engineering service organizations are effectively complying with their quality assurance program requirements for inspection. NUSCO/NUPOC Quality Assurance also observes the performance of selected inspections on-site and at 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 /in process verifications activities are performed as specified in written quality assurance procedures.
During the preoperational testing and the operations phase, qualified NUSCO/NUPOC Quality Assurance personnel shall review procedures for maintenance, modification, and inspection in order to determine the need for:
- a. Inspections (c.g., receipt inspections, installation, system turnover, and product acceptance);
- b. Identification of inspection personnel;
- c. Documentation of inspection results.
The review also ensures that the necessary inspection requirements, methods, and acceptance criteria have been identified.
NUSCO/NUPOC Quality Assurance performs audits / surveil-lances / inspections /in process verifications to verify that QAP 10.0 Rev.: 10 Date:
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l contractors, suppliers, and engineering service organiza-tions are. effectively complying with their quality assurance program requirements for inspection and for performing /
witnessing inspections at " hold" or "notificatiod" points identified in NUSCO/NUPOC procurement documents. All audit / surveillance / inspection /in process verification activities are performed under requirements specified.in written quality assurance proceuures.
10.2.2 Inspection Plans and Schedules
. Documented inspection plans may be either a separate
. document or an integral part of work instruction docu-ments. 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.
During NUSCO-directed activities of nuclear plants, NUSCO Procedures provide criteria for the determination of accuracy requirements of inspection equipment and when ,
inspections are required. These procedures describe requirements for the preparation of inspection plans and schedules by NUSCO Construction Quality Control. NUSCO Procedures also describe requirements for audits and surveillances performed by the NUSCO Operations Quality Assurance Section to assure the implementation of the inspection plans and schedules.
During the operations phase of nuclear plants, inspection activities are performed in accordance with NUPOC Procedures.
NUPOC Quality Assurance participates in inspection activities by the review of work procedures and the preparation and approval of inspection plans. ;
The inspection criteria, including the use of inspection equipment and their accuracy requirements, are specified in the Job Packages / Inspection Plans.
10.2.3 Inspection Personnel and Inspection Document Access
- a. Inspections are performed by individuals other than those who performed or directly supervised the activity being inspected. Inspection personnel are qualified and/or certified in accordance with appro- q priate codes, standards, and/or NU training programs; l
- b. Inspections are performed by NUSC0/NUPOC Quality Assurance / Quality Control personnel or by qualified i i
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NUPOC plant personnel / contracted personnel, who are independent from undue pressure such as cost and.
schedule. When NUPOC plant personnel / contracted personnel perform inspections, their inspect 4on plans / procedures and personnel qualification criteria are reviewed and found acceptable by the Quality
' Assurance organization prior to the initiation of the activity.
- c. 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
- a. Required inspections, surveillance, or monitoring activities are performed and documented according to- !
written, approved procedures and/or checklists.
Inspection procedures, plans or checklists contain the following:
(1)- Identification of characteristics to be inspec-ted; (2) Identification of the individual or groups responsible for performing the inspection; (3) Requirements for the necessary measuring and test equipment and the required accuracy of this equipment.
(4) Acceptance criteria; (5) A descrlption of the method of inspection; (6) A record of the results of the inspection; (7) Record of inspector or data recorder.
- 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 QAP 10.0 Rev.: 10 Date:
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Assurance personnel to determine the need for: 1) an independent inspection, 2) the degree and method of the inspection, if such anlinspection is required, 3) the identification of inspection personnel, pnd 4) the documentation of inspection results (for proce-dure review requirements, see QAP 5.0).
10.2.5 Mandatory Hold and Notification Points Mandatory hold points are utilized when an inspection /-
operation must be performed or witnessed and signed-off by the responsible personnel before work can proceed. Noti-fication points are used to identify the operations or completed processes that NUSCO/NUPOC or its representa-tives may elect to witness and/or inspect during the manu-facturing, 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 NUSCO/NUPOC Quality Assurance for adequacy of inspection, notification and/or mandatory hold controls.
10.2.6 Inspection Result Evaluation Inspection results are evaluated for acceptability in accordance with approved NUSC0/NUPOC Procedures which identify the responsible organization.
These evaluations are performed by the responsible NUSCO/
NUPOC personnel who are qualified in accordance with the-appropriate Regulatory Guide / ANSI Standard commitments listed in Appendix D.
NUSCO Quality Assurance performs audits to assure that inspections are performed per the requirements of applicable NUSCO/NUPOC Procedures.
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11.0 TEST CONTROL 11.1 GENERAL REQUIREMENTS P
A. documented test control program is established by the NUQAP for
- 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.
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The test control program is systematic and. includes proof test prior to installation, construction tests, preoperational tests, surveil- ;
lance tests, start-up tests and retest following repairs, replace-ment or modification. I 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 (iAR), technical' specifications, procedures or procurement cocuments, as appropriate, are accomplished by subjecting the item to a set of physical, chemical, environmental or operating conditions. Retest.following repairs, replace-l
' ment or modification is performed in accordance with the original design requirements or acceptable alternatives and is performed when original test results are invali- (
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NUSCO/NUPOC procedures are written and approved to delineate the methods and responsibilities for controlling, accomplishing and documenting testing during the construc- ;
l tion, preoperational testing, maintenance, operation and )
l modification of nuclear power plants.
During design, construction, preoperational testing, l operation, maintenance and modification to nuclear power plants the engineer-constructor, contractors, suppliers and engineering service organizations, as appropriate, are responsible for imple menting measures for the control of tests to ensure that material, equipment and parts will l
perform satisfactorily. NUSCO/NUPOC Quality Assurance j performs on-site and off-site audits /surveillances/
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inspections /in-process verifications of' selected proof tests when " notification" points have been identified in Purchase. Order / Contracts-of the engineer-constructor, contractors, suppliers and engineering service'organi-zations to verify they are~ complying with'their quality.
assurance program requirements for test control.
Documentation associated with these observations are maintained by NUSCO/NUPOC Quality' Assurance.
Proof tests,: product acceptance' tests, retest, and periodic surveillance tests are conducted by' qualified personnel in
.accordance with approved procedures. . Personnel performing tests ensure.that calibrated-equipment and instrumentation utilized are.within the calibration interval specified.
. Documentation including test procedures and approved data.
sheets'are maintained in appropriate files.
11.2.2 Test Procedure Preparation and Test Performance Testing is. accomplished in a'cordance c with approved test procedures which incorporate or reference the requirements 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;
- f. Methods for documenting or recording test data and results;
- g. Provisions for data collection and storage.
11.2.3' Test Equipment During NUSCO-directed activities of nuclear plants, NUSCO/NUPOC Procedures provide the criteria for determining QAP 11.0 Rev.: 10 Date:
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when'a test is required and the accuracy requirements of test equipment. '
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During the operations phase of a nuclear plant, tAe following steps are taken:
- a. To ensure accuracy, test instrumentation is checked-and calibrated in accordance with NUSCO/NUPOC procedures.
- b. Plant instrumentation used in testing is calibrated.
It is' maintained in calibration at regular intervals in accordance with established surveillance and/or-preventative raintenance procedures.
- c. Where special instrumentation is required for testing, the requirements are stated in the procedures.
Instrument characteristics, including accuracy requirements, are equivalent to or better than those specified by the vendor.
11.2.4 Evaluation of Test Results 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, eval-uste the data against predetermined' criteria and document the results of the evaluation and acceptance status _of the test. NUSCO Quality Assurance performs audits / surveil-lances / inspections /in p-ocess verifications to verify that these~ organizations are effectively complying with their quality assurance program requirements for test control.
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12.0 CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 GENERAL REQUIREMENTS e
The NUQAP provides measures for the control of measuring and testing *
- equipment (M&TE) used as the basis for acceptance in activities L
affecting quality during inspection, testing and measurement of f material, equipment and parts. Periodic calibration and adjustment y of measuring and test equipment is performed and controlled to assure accuracy is maintained within limits necessary to verify that l- design and operating condition requirements have been met. Documen-tation is retained such that all items of M&TE are traceable to their calibration records.
l 12.2 IMPLEMENTATION 12.2.1 Approved procedures delineate the methods and respon-sibilities for the control, maintenance and calibration of M&TE, (including portable and installed instruments, tools, gages, fixtures, reference and transfer standards, and nondestructive test equipment).
All documentation associated with M&TE is maintained in appropriate files, with eventual. incorporation into the NU Nuclear Records Organization.
During NUSCO-directed activities of a nuclear plant, the-NUSCO calibration program is implemented in accordance .I with the requirements defined in NUSCO' Procedures. NUSCO Generation Construction Group is responsible for implementing these procedures which comply with the requirements contained in specifications and drawings. NUSCO Construction Quality Control is responsible for verifying that receipt {
of calibrated equipment is in conformance with the require- {
ments of procurement documents, and to control calibrated j M&TE used during their inspections.
During NUPOC-directed activities, the calibration program is implemented in accordance with the requirements defined in NUPOC Procedures. The Site / Plant Operations Review Committee (SORC/PORC) reviews and approves procedures related to the calibration program. Department heads are responsible to ensure that M&TE equipment is calibrated, issued, and controlled in accordance with the requirements of the procedures. Department Heads are responsible for calibrating M&TE within the required frequency and for i reviewing calibration data associated with M&TE calibration !
by outside vendors in accordance with the procedures, j i
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NUSCO/NUPOC Quality Assurance performs audits / surveil-Iances/ inspections /in process verifications to verify implementation of the calibration programs. i The engineer-constructor, contractors, suppliers *and engineering service organizations utilized by NUSCO/NUPOC during the design, construction, operation, maintenance and modification of nuclear power plants, as appropriate, are responsible for implementing measures for the control of H&TE to ensure they are properly calibrated, adjusted and maintained at specified intervals in order to maintain accuracy within required limits. NUSCO/NUPOC Quality Assurance performs on-site and off-site audits /surveillan-ces/ inspections /in-process verifications of the quality assurance programs of the engineer-constructor, 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 l
Measuring and test equipment is calibrated at specified I intervals based on the required accuracy, purpose, degree :
of usage, stability characteristics, and other conditions affecting the measurement. Measuring and test equipment shall be labeled or tagged to indicate the date calibrated and next calibration date.
NUSCO/NUPOC Procedures describe the measures taken to assure that reference and transfer standards are traceable to nationally recognized standards and that, where national standards do not exist, provisions are established to document the basis for calibration.
Calibration of this equipment should be against standards j that have an accuracy of at least four times the required accuracy of the equipment being calibrated. When this is not possible, the standards r. hall have an accuracy that assures the equipment being calibrated will be within required tolerance and the basis of acceptance is documented ;
and authorised by the Director / Generation Construction (for NUSCO-directed activities) or the SORC/PORC (for NUPOC-directed activities). In addition, the calibrating standards shall have greater accuracy than secondary I standards being calibrated. Calibrating standards with the same accuracy may be used if they can be shown to be 1 adequate for the requirements and the basis of acceptance is documented and authorized by the Director / Generation Construction or PORC/SORC.
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.s 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 inspection or test results gained through use of the instrument, and of the acceptability of items previously measured or tested.'
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I 13.0 HANDLING, STORAGE AND SHIPPING 13.1 GENERAL REQUIREMENTS Measures are established by the NUQAP using approved procedures,
' instructions and procurement documents to ensure proper handling, storage, shipping, cleaning and preservation of material, equipment and parts. These measures are imposed during the design, procurement, construction, preoperational testing and operation of nuclear power 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, cleaning and preservation of material, equipment and parts, and required implementation of established design and specification requirements.
During design and construction the responsibilities associated with handling, storage, shipment, cleaning and preservation of material, equipment and parts may be delegated to the engineer-constructor, contractors, suppliers and engineering service organizations. These organizations are monitored through audits / surveil-lances / inspections /in process verifications by NUSCO/NUP0C Quality Assurance to verify compliance with their quality assurance program requirements for handling, shipping, cleaning and preservation.
i Handling, storage, cleaning and preservation requirements of material, equipment and parts is conducted in accor-dance with written procedures and procurement documents during the preoperational testing and the in-service phase j nuclear power plants. The Nuclear Plant Operating Compan- 1 ies may utilize contractors, suppliers, and engineering I service organizations during the operation, maintenance f and modification of the in-service nuclear power plant.
These organizations are responsible for implementing measures for handling, storage,-shipping, cleaning and preserving material, equipment and parts to preclude damage, loss or deterioration. NUSC0/NUP0C Quality Assurance performs audits /surveillances/ inspections / l in process verifications to verify that NUPOC, contractors, '
suppliers and engineering service organizations are effectively implementing and complying with their approved procedures and instructions for handling, storage, shipping, l
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. cleaning and preservation of material, equipment and parts. I
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l 13.2.2 Establishment of Special Handling, Storage, Shipning, l Cleaning and Preservation Requirements j
- Special or additional handling, storage, shipping, clean- )
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'ing and preservation requirements are to'be identified and implemented as specified in procurement documents and approved procedures. These established requirements are L consistent.with the regulatory positions of the NRC ]
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' Regulatory Guides'and their endorsed ANSI Standards, J listed in Appendix D of the NUQAP Topical Report, or i i
specifications.and/or suppliers technical manual, and will i be consistent with accepted industry standards.
L NUPOC Procedures describe the measures taken for.the storage of chemicals, reagents (including. control of shelf life), lubricants, and other consumable materials. ,
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1 14.0 INSPECTION, TEST AND OPERATING STATUS q
i 14.1 GENERAL REQUIREMENTS , j The NUQAP 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 material, equipment and parts throughout design, construction, preoperational testing, operation, maintenance and modification of nuclear power plants, to preclude the inadver-tent 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 estab-lished for indicating the operating status of systems, structures ;
and components to prevent inadvertent operation. '
14.2 IMPLEMENTATION '
14.2.1 General The engineer-constructor, NUSCO/NUPOC contractors, sup-pliers 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 materials, equipment and parts to preclude the bypassing of requirements. NUSCO/
NUPOC Quality Assurance performs on-site and off-site I audits /surveillances/ inspections /in-process verifications i of the engineer-constructor, contractors, suppliers and engineering service organizations to verify that they are effectively complying with their requirements for identi- '
fication 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 provide 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 or other appropriate methods.
Where NUSC0/NUPOC performs receipt inspections at nuclear power plants, the NUPOC Quality Assurance Supervisor /NUSCO Manager-Construction Quality Control ensures that traceability is maintained of acceptable material, equipment and parts, to indicate conformance to Purchase Order / Contract require-ments. Nonconforming material, equipment and parts are identified in accordance with QAP 15.0.
QAP 14.0 Rev.: 10 Date:
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'During tests and inspections of operating nuclear power.
plants a status tagging system is implemented,.s a per approved procedures and instructions, to prevent inadver-tent operations offsystems, structures and compogants.
NUSCO/NUPOC Procedures describe the measures taken to
- control the altering of the sequence.of required tests, !
inspections and_other operations taken during, Generation
' Construction / Operations. The review and approval for these actions is subject to the same control as taken during the original review and approval of tests,.
inspections!and other operations.
14.2.2 Status 1dentification 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 systems, structures and components to prevent inadvertent operation, and to preclude omission of inspections, tests or.other critical operations. These procedures and instructions! delineate the requirements, methods and responsibilities for indicating the status of the affected.
items. The complete status of all items under the calibra-tion system is recorded and maintained.
Records associated with status identification are main-tained in accordance with approved procedures.
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15.0' NONCONFORMING MATERIALS, PARTS, COMPONENTS, OR SERVICES 15.1 Genera 1' Requirements P
The NUQAP requires'that documentation and control of nonconforming
' material, parts, components, or services utilized in systems, structures and components.during design, construction, preoperational
. testing, operation ~ and maintenance of nuclear power ' plants and major modifications thereto, be performed ~in accordance.with. approved procedures in order to prevent inadvertent use or installation.
These-procedures include' appropriate' requirements for identification, documentation, segregation and dispos >' tion of nonconforming items, and notification to affected organizations. In accordance with -3'
-procedures, nonconforming material,. parts, components, or services are reviewed'and accepted, rejected, repaired or reworked.
15.2 Implementation
.15.2.1 Program Approved procedures define the responsibilities and {
establish measures for identification, documentation, i segregation, review and disposition'of nonconforming materials, parts, components, or services, and notification to affected organizations. Each NU de-partment is responsible for the identification, control and disposition of nonconformances within the scope of their departmental responsibilities.
NUSCO/NUPOC Quality Assurance performs-on-site and off-site audits /surveillances/ inspections /in-process
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verifications of the. engineer-constructor, contractors, suppliers and engineering service organizations to verify these organizations are effectively complying with their quality assurance program requirements for documentation and controlsof nonconforming material, parts, components, or services.
15.2.2 Documenting and Controlling Nonconformances Nonconformances of systems, structures and components are documented'and reported as requiring corrective action.
Approved procedures delineate controls required for further processing and installation of nonconforming items. These controls include:
- a. Physical identification of the material, part, component, or services as nonconforming; QAP 15.0 ,
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- b. Segregation of nonconforming items or services 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 requirements and signature approval of the disposition. A trend analysis of nonconformances is performed by NUSC0/QA in accordance with approved procedures. The trend analysis results are periodically reported to the NUSCO Manager Quality Assurance and then to upper management, including the Senior Vice President, Nuclear Engineering and Operations, for review and assessment.
An engineering evaluation is performed, if necessary, prior to the resolution of nonconformances relating to systems, structures and components.
15.2.4 Evaluation and Disposition Evaluations are performed to determine the disposition of nonconforming items and services. The evaluation determines whether an item or service is to be accepted as-is, returned to supplier, repaired, reworked, scrapped or salvaged. These evaluations assure that the final condition does not adversely affect safety, operation or maintenance l of the item or service, or of the component or system in which the item is installed or on which the service is performed. Applicable information is accumulated and records are maintained.
i The engineer-constructor, contractors or NUSCO/NUPOC ;
personnel are required to report to the NUSCO Director / j Generation Construction, or the appropriate NUPOC Superintendent, as applicable, to obtain release of i j
nonconforming item or service prior to its installation or j use. These release items are identified by a Noncon- l formance Tagging System which defines the description of the nonconformance and its nonconformance status. )
i Nonconformance reports dispositioned " accept as is" or
" repair" are forwarded to the KUSCO Director / Generation j
Construction, NUSCO Project Engineer, or the appropriate NUPOC Superintendent, as applicable, and to NUSCO/NUPOC Quality Assurance for review and approval, and then made part of the materials receipt inspection records. In addition, the status of all materials, parts, or components QAP 15.0 l Rev.: 10 l Date: i Page 2 of 3 l j
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i is maintained byt a system of tags,1which.is ~ administrative 1y.
controlled by.the cognizant QA/QC Department.
- During'NUSCO-directed ~ activities of a' nuclear plant, NUSCO
' Generation-Construction and NUSCO Construction Quality
-Control. organizations are responsible for documenting the
- status ~ of nonconforming, inoperative, or malfunctioning structures,- systems, components, 'and services as described -
in NUSCO Procedures. :During NUPOC-directed activities of a nuclear pla'nt, the status of ' nonconforming, inoperative, o Lor malfunctioning' systems,. structures components, and services'is documented as necessary by NUPOC Quality Assurance / Quality' Control and NUPOC Operations personnel:
m as described.in applicable NUPOC Procedures.-
The need to. release nonconforming material, parts or components shall be; based on such. considerations as:
- a. ' Impact on plant safety; ,
b '.' Safety of: personnel;-
- c. Suitability of material or. items in the "as-is" condition, i.e., probability of eventual satisfactory resolution of the nonconformity without repair, rework or. replacement;
- d. . Accessibility of material lor 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, i
1 QAP 15.0 '
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-16.0 CORRECTIVE ACTION
- 16.1l GENERAL-REQUIREMENTS .
The NUQAP provides documented measures 'for corrective action to
, ensure that. nonconforming systems,. structures and components are identified and promptly corrected. .These' measures shall include, asL appropriate, procedures for' identification, documentation, segrega-tion, disposition' notification to affected. organizations and follow-up to prevent recurrence.' Nonconforming items shall be' l
reviewed and accepted, rejected, repaired or reworked-in accordance !
with approved procedures. When conditions, adverse to quality, are identified through trend analysis, measures are taken to ensure
- corrective action and to prevent recurrence of the problem.
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. NUSCO/NUPOC.
Procedures describe the measures taken to evaluate conditions' adverse to quality, to determine the need.for corrective' action, to document the evaluation, and to assure Qua' lity' Assurance concurrence with the adequacy of the correctiveiaction. NUSCO/NUPOC Procedures also describe the measures taken to assure what follow-up action is.taken by NUSC0/NUPOC Quality Assurance to verify proper. implementation and close out of corrective action in a timely manner.
Procedures describe the measures taken by NUSC0/NUPOC Quality Assurance to review and document concurrences with corrective action procedures established by applicable NUSC0/NUPOC' departments.
During design, construction, preoperational testing and operation of nuclear power plants, the engineer-construc-tor, contractors, suppliers, engineering service organi-zations and their subtier contractors, (utilized by !
NUSCO/NUPOC), and NU personnel are responsible for inform-ing the Senior Vice President Nuclear Engineering and Operations, through their respective organizational chains ;
i of command, of significant conditions which are adverse to quality, the cause of the condition and the corrective action taken. NUSC0/NUP0C Quality Assurance or NUSCO Construction Quality Control, as appropriate, identifies QAP 16.0 Rev.: 10 Date:
Page 1 of 3
1 deficiencies by audits /surveillances/ inspections /in process verifications of the engineer-constructor's, contractor's, supplier's and engineering service organization's quality ;
assurance programs for corrective action. A reardit/
inspection / surveillance /in process verification to verify implementation of corrective action and close-out of
, corrective action documentation shall be accomplished by the original auditing organization.
NUSCO Quality Assurance performs audits to identify deficiencies in departmental corrective action programs.
The appropriate NUSCO Department Director / Branch Manager /
Section supervisor or the appropriate NUPOC Superintendent, is responsible to implement timely corrective action.
NUSCO Quality Assurance may reaudit the affected department to verify corrective action 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 Senior Vice President - Nuclear 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, NUSCO/NUP00 defines in procedures and contracts the corrective action interface between NUSC0/NUPOC and the contractor. NUSCO/NUPOC requires the engineer-con- i structor, contractor, suppliers and. engineering service l organizations, as appropriate, to have a documented !
corrective action program for materials and services.
16.2.2 Recurrence Control The organization which is responsible for the condition adverse to quality, shall ensure that the corrective action will not only correct the immediate condition, but also prevent the adverse condition from recurring.
NUSCO/NUPOC procedures establish the responsibilities and measures taken to identify trends of conditions, adverse to quality, and to ensure that corrective action is taken for those conditions to prevent their recurrence. A trend ;
analysis report; which identifies the conditions, adverse '
to quality; is issued to appropriate levels of NU management.
The NUSCO Manager, Quality Assurance is responsible for follow-up of the trend analysis items and their corrective action.
QAP 16.0 Rev.: 10 Date:
Page 2 of 3
Trends concerning specific contractor's performance shall be ' reported to the' affected contractor for resolution and corrective action to prevent recurrence of the problem.
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l 17.0 QUALITY ASSURANCE RECORDS 17.I' GENERAL' REQUIREMENTS
- The NUQAP provides 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,Ltests,Laudits, monitoring of work performance )
b' and material' analyses. The records also. include closely related y data'such as' qualifications of personnel, procedures and equipment.
1 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
'NUSCO/NUPOC Procedures and Instructions establish the responsibilities and requirements for the maintenance,; identification, retention _and retrievability of records pertaining.to material, equipment, parts, .
2 processes or operations relating to systems, structures and components which when founded on' observations,.measurementsJor tests can be fully verified, and' documented by' cognizant' personnel.
During design, construction, preoperational. testing,' operation, maintenance and modification of nuclear power ~ plantsLthe engineer-constructor, ~ contractors, suppliers and engineering service organi- ~ !,
zations, as appropriate, utilized by NUSCO/NUPOC are responsible to implement measures for identification, maintenance, retention, retrieval and turnover,'to the NUSCO Project Engineer / Cognizant NUPOC personnel, of documented and approved records which contain
-objective evidence of quality, as specified in Purchase Order / -
Contracts. NUSCO/NUPOC Quality Assurance performs'on-site and off-site audits /surveillances/ inspections /in process verifications
'of the engineer-constructor, contractors, suppliers and engineering service organizations, as appropriate, to verify.they are effec-tively complying with their program for quality assurance records.
NUSCO/NUPOC records are' identified, controlled and maintained in e appropriate files and are identifiable to specific systems, structures and components within the nuclear power plant. When identification to a specific system,. structure or component is not practical, records are filed by category; (e.g. specification, nonconformance '
reports, audits, etc).
QAP 17.0 Rev.: 10 Date:
Page 1 of 2 !
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-17.3 RETENTION 1
NU Quality, Assurance records are classified as life records or non-life. records as-delineated by Generation Facilities Rec.ords.
Non-life records are'those documents that are maintained for a l
- 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 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 signifi-cant value in meeting one or more of the following criteria:
- a. Demonstrating capability for safe operation;
- b. Maintaining, reworking, repairing, replacing or modifying the item;
- c. Determining the cause of an accident or malfunction of an item;
- d. Providing required base line data for in-service inspec-tion.
Records'are, reviewed and approved by the Project Engineer _or other cognizant qualified personnel of NUSCO/NUPOC, engineer-constructor,
- ' etc., as appropriate, and are transmitted to the appropriate Nuclear Plant Records Facility. The responsibility of the appropriate Nuclear Plant Records Facility upon receipt of: records, is to main-tain and provide controlled retrievability of records affecting nuclear power plants, in such a manner as to prevent destruction of records by fire, flood, theft,-and environmental conditions, such as temperature'or humidity,'as delineated in procedures.
QAP 17.0 Rev.: 10 Date:
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18.0 AUDITS i
18.1 GENERAL REQUIREMENTS . !
The NUQAP 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 j audited to ensure compliance with the NUQAP Topical Report. The results of audit findings are documented and then reviewed with ]
management having responsibility in the area audited.
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18.2 IMPLEMENTATION l
18.2.1 Program The following audits relating to the NUQAP are performed:
i
- a. Engineering Assurance Audits (audits of corporate j quality activities are completed within a period of 1 two (2) years and are administered under the direction {
of the NUSCO Audit Program).
- b. NUSCO/NUPOC Engineer-Constructor, Contractor, Supplier, and Engineering Service Organization Audits; (as per procurement documents)
- c. Plant Audits; (audits of the 18 criteria of Appendix B 10CFR Part 50 are completed within a period of two (2) years and are administered under the direction of the NUSCO Audit Program)
In addition, provisions are established to require that audits be performed of those activities where the require-ments 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 foundation preparation);
- b. The preparation, review, approval and control of early procurements;
- c. Indoctrination and training programs; QAP 18.0 Rev: 10 Date:
Page 1 of 3
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- d. i Interface control among the licensee and the principal '
contractors.
Measures are provided to perform audits of the f611owing operations activities:
, a. Operation, maintenance, and modifications;
- b. The preparation, review, approval and control of design documents, specifications, procurement docu- a ments and instructions, procedures and drawings; f
- c. Receiving and plant inspections; I 1
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- d. !
Indoctrination and training programs;
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- 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 j importance of the activities being performed. Schedules 1 are originated and maintained by NUSCO Quality Assurance.
Audits are performed as specified in procedures 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 NUQAP.
The engineer-constructor, 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 j and the effectiveness of all aspects of their quality ?
assurance programs including reporting and resolution of deficiencies. NUSCO/NUPOC Quality Assurance personnel perform on-site and off-site audits /surveillances/inspec- )
J tions/in process verifications to ensure these organizations are effectively complying with their quality assurance requirements for audits.
Departments within the NUSCO/NUPOC organizations are l responsible for implementing their functions in accordance j with approved procedures and instructions. Internal '
audits are performed to verify implementation of the requirements prescribed in the NUQAP topical Report and implementing departmental procedures.
QAP 18.0 Rev: 10 Date:
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18.2.2- Review of Audit Findings '
-i Audit results~are documented, reviewed, and analyzed with management having responsibility in the area audited. The .
responsible management.is required to takeLthe necessary 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 / Designee. He is responsible, based on the audit documentation, for issuing the audit reports to the appropriate management of the area audited and -for j ensuring that timely corrective action is taken to rectify- I deficiencies. In addition, audit data and reports'are accumulated for the review and assessment of quality trends and the effectiveness of the Quality Assurance
~
1-Program. This report is then submitted to the Senior Vice
. President, Nuclear Engineering 'and Operations.
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18.2.4 Resolution of Audit Deficiencies Appropriate action to resolve' deficiencies identified during audits is to be taken by the cognizant engineer- s constructor, contractor, supplier, engineering service, organization'or internal management before the scheduled resolution date. . Follow-up audits lare performed as necessary, to' verify appropriate l actions have been taken to' resolve deficiencies. Items'which exceed the scheduled resolution date and cannot be resolved by affected management are submitted for resolution to the Senior Vice President ;
Nuclear Engineering and Operations.
18.2.5 Records / Reports of Audits Audit records, reports and associated documentation pertinent to audits are maintained in the appropriate ,
NUSCO files with disposition to the appropriate Nuclear Plant Records Facility, as specified 'in procedures.
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APPENDIX A CATEGORY I SYSTEMS, STRUCTURES, AND COMPONENTS j
i The following systems, structures and components of a nuclear power i plant, including their foundations and supports, are designated as i Category 1. The pertinent quality assurance requirements of Appendix B
' to 10 CFR Part 50, should be applied, as a minimum, to all quality activities affecting the safety related function of these systems, j structures and components as listed below and to other items and services specifically identified by NU in each FSAR addressing Section 3.2.1 of l j NRC Regulatory Guide 1.70. !
(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 jl core cooling; (2) post-accident containment heat removal or; (3) post-accident containment atmosphere cleanup (e.g., hydrogen removal system).
l (d) Systems or portions of systems that are required for (1) reactor ,
shutdown; (2) residual heat removal or; (3) cooling the sp mt 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 cystems including the intake structures, that are
- required for (1) emergency core cooling; (2) post-accident con-i tainment heat removal; (3) post-accident containment atmosphere cleanup; (4) residual heat removal from the reactor or; (5) cooling the spent fuel storage pool.
QAP - Appendix A Rev.: 10 Date:
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(h) ' Cooling water and' seal. water systems or portions' of these ~ systems -
f that"are. required for functioning of reactor coolant system com--
ponents important to safety, such.as reactor coolant pumps.
l(i) Systemsor portions-'of systems that are required to supply fuel for emergency. equipment.
('j) fall 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 tystems.
(k) ' Systems or portions.of systems that are required for (l')' monitoring of, systems'important'to safety and;'(2) actuation of systems impor-.
tant to safety.
g" _
i l (1) The spent fuel storage pool structure, including the fuel racks.
UI(m) .The reactivity, control system-(e.g., control rods, control rod 5'
. drives, and boron injection system). '
(n) ' The coiittol' room, inclu' dthg its assSciated equipment and ~all equip-ment. nu dgd to maintain.the control room within safe habitability.
limith for personnel and safe environmental limits for vital equip-ment. ,
(o) Primary and' secondary reactor containment.
?(p)' SystemsJother'than radioactive waste management systems not covered by items (a) through (o') above which contain or may contain radio-active materials c.nd'whose postulated failure would result in conservativelp calculated potential offsite doses (using meteorology 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. ;
is (q) ' The class'lE electric systems, including the auxiliary systems for s
the onsite electrii power supplies, that provide the emergency electric power needed for functioning < ofc plant features included in items (a) through,(p)'above. I
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.n( .(r) . Those portions of systems,. structures or componenta) hose continued function is not. required but whose failure could reduce the fune-tioning of any plant feature included in items (a) throbgh (q) above to an unacceptable safety level or could result injincapacitating
,y
' 'iejury to occupants.of the control room should be deMgned and
- constructediso' that the SSE would not cause such ~ failures.
(s)'. Items and services ossociated with Radioactive Material Transport
' Packages'as described in 20CFR71.
l QAP - Appendir A I Rev.: 10 Date:
Page 2 of 3
CONSUMABLIS The following specific consumables when utilized in safety related systems shall be included in those portions of the NUQAP, as applicable.
- 1. Emergency generator diesel fuels "2. Hydraulic snubber fluids
- 3. Reagents-
- 4. Resins
- 5. Boric Acid
- 6. Lubricants 1
QAP - Appendix A
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Date:
Page 3 of 3
APPENDIX B
. NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT QUALIFICATION AND EXPERIENCE REQUIREMENTS NUSCO MANAGER, QUALITY ASSURANCE The NUSCO Manager, Quality Assurance shall satisfy the following require-ments:
Graduate of a four year accredited. engineering or science college or university, plus twelve (12) or more years of industrial experience 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 Quality Assurance Activities. And at least one year:of this experience is in a Quality Assurance Organization. A masters degree in engineering i or business management is considered equivalent to two years of experience.
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.: 10 j Date: ?
Page I of I
h APPENDIX C NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT LIST OF TYPICAL QUALITY ASSURANCE RELATED PROCEDURES INDEX PAGES NUSCO QUALITY ASSURANCE BRANCH PROCEDURES 2-5 NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL 6-9 NUSCO GENERATION' ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL 10-12 NUCLEAR PLANT RECORDS MANUAL 13-15 INFORMATION RESOURCES GROUP PROCEDURES 16 l NUSCO NUCLEAR OPERATIONS DEPARTMENT PROCEDURES 17 MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES 18-22 CONNECTICUT YANKEE QA PROCEDURES 23-26 NUSCO STANDARD QUALITY CONTROL PROCEDURES 27 l NORTHEAST UTILITIES WELDING MANUAL 28 NU PURCHASING BUSINESS PROCEDURES 29 NUSCO RELIABILITY ENGINEERING PROCEDURES MANUAL 30 REACTOR ENGINEERING BRANCH PROCEDURES 31 GENERATION FACILITIES LICENSING BRANCH PROCEDURES 32 i
QAP - Appendix C Date: .
Topical Rev.: 10 l
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NUSCO QUALITY ASSURANCE
. BRANCH PROCEDURES 10CFR50: APP. B CRITERIA NQA - PROCEDURES' I. .OrganizationL NQA-1.01 Quality Assurance Branch Organiza-tion.
II. Quality Assurance . .
Program NQA-1.02 ' Preparation, Issuance, and Con-trol of the Northeast Utilities Quality Assurance Program Topical Report.
NQA-1.04 Objective of Engineering Assurance Section NQA-1.07 Preparation and Issuance of NUSCO.
Quality Assurance Branch Quarter-ly and Annual Activity Reports.
NQA-1.10 Quality Assurance Work Assignment i System.
NQA-2.01 Engineering Assurance Functions.
NQA-3.01 NUSCO Quality Assurance Branch Indoctrination and Training Program.
NQA-3.02 Training and Qualification of NQA Lead Auditors & Surveyors.
NQA-3.03 Selection, Training, Qualifica-tion and Certification of NUSCO Non-NDE Inspection and Testing Personnel.
III. Design Control IV. Procurement Document Control NQA-2.03 Procurement Document Review.
NQA-2.18 Assignment of suppliers to periodic surveillance status.
V. Instruction, Pro- NQA-1.03 Preparation Issuance and Control cedures, & Drawings of NUSCO Quality Assurance Branch Procedures.
QAP - Appendix C Date:
Topical Rev.: 10 Page 2 of 32
NUSCO QUALITY ASSURANCE BRANCH PROCEDURES 10CFR50 APP. B CRITERIA NQA - PROCEDURES VI. Document Control NQA-1.08 Issuance of NUSCO Quality Assur-ance Correspondence / Communications.
NQA-1.11 Control of Safeguards Information.
NQA-1.12 Retrievability of Quality Records From the Nuclear Plant Records Facility (NPRF)
NQA-2.02 Routing, Followup, Review and Ap-proval of Engineer - Constructor, NUSCO Contractor, and Engineering Service Organization Quality Documents.
VII. Control of Purchased Material, Equipment, and Services NQA-2.04 Supplier Evaluations.
NQA-2.05 Instructions for Use of the NUSCO Quality Assurance Supplier Infor-mation Computer Program.
NQA-2.07 Review and Approval of the QA Program /QA Surveys of NUSCO Sup-pliers.
NQA-2.12 Preparation, Issuance and Control of the NUSCO Quality Assurance Category I Contractor, Supplier, and Engineering Service Organiza-tion List. .
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NQA-2.14 Preparation, Issuance, and Control !
of the NUSCO Commercial Commodity l List.
VIII. Identification & !
Control of Materials, Parts, and Components IX. Control of Special Processes NQA-3.04 Selection, Training, Qualifica-tion, and Certification of NUSCO and NUPOC Nondestructive Examina-tion Personnel.
QAP - Appendix C Date:
Topical Rev.: 10 l Page 3 of 32 l
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NUSCO QUALITY ASSURANCE BRANCH PROCEDURES 10CFR50 APP. B CRITERIA NQA - PROCEDURES X. Inspection NQA-2.08 Preparation, Condet, and Reporting of NUSCO Quality Assurance Inspections.
NQA-2,10 Performance, Reporting, and fol-low-up of Surveillance Activities.
XI. Test Control
-XII. Control.of Measuring and Test Equipment XIII. . Handling, Storage, and Shipping XIV. Inspection, Test, and Operating Status XV. Nonconforming Materials,
. Parts, or Components NQA-1.06 Procedure to Stop Work.
XVI. Corrective' Action NQA-2.11 Corrective Action Request (C.A.R.)
Program.
NQA-2.17 Verification of Corrective Action Contained in Significant Defici-ency Reports Submitted to the NRC.
XVII. Quality Assurance NQA-1.09 Transmittal of Quality Assurance Records Record for Permanent Storage.
NQA-2.19 Review, Approval, and Transmittal of NUSCO Betterment Project Records.
TVIII. Audits NQA-1.05 Audit, Survey, and Inspection Computer Program.
QAP - Appendix C Date:
Topical Rev.: 10 Page 4 of 32
, NUSCO QUALITY ASSURANCE F
BRANCH PROCEDURES 10CFR50 APP. B CRITERIA NQA - PROCEDURES NQA-2.06 Conduct, Reporting, and Followup of Audits.
NQA-2.09 Joint Audits.
NQA-2.15 In-Process Verification Report l
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QAP - Appendix C Date:
Topical Rev.: 10 Page 5 of 32
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NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL 10CFR50 APP. B CRITERIA NEO - PROCEDURES I. Organization NE0-1.01 Organization of the Nuclear
, Engineering and Operations Group.
NEO-2.02 Charter for Nuclear Review Boards.
II. Quality Assurance Program NE0-1.02 Scope and Function of Nuclear Engineering and Operations Poli-cies and Procedures Manual.
NEO-2.03 Nuclear Training NEO-2.08 Management Review of The Northeast Utilities Quality Assurance Program.
NE0-2.14 Nuclear Plant Fire Protection Program.
NEO-3.08 Processing Proposed Revisions to the Northeast Utilities Quality Assurance' Program Topical Report.
NE0-7.01 Construction Implementation of Operating Plant Modifications.
NEO-7.02 Turnover of Systems, Components, and Structures.
III. Design Control NEO-3.03 Preparation, Review and Disposi-tion of Plant Design Change-Records (PDCR's).
l NE0-3.04 Preparation, Issuance, and Control of Project Assignments.
NE0-3.12 Safety evaluations.
NE0-5.04 Preparation, Review, Approval, Revision, and Control of Specifications.
NEO-5.05 Design Inputs and Design Verification.
QAP - Appendix C Date:
Topical Rev.: 10 Page 6 of 32
NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL 10CFR50 APP. B CRITERIA NEO - PROCEDURES NE0-5.06 Preparation, Review, Approval of Design Analyses and Calculations.
NE0-5.11 Design Change Notices for Design Documents.
NE0-5.12 Performance of Fire Protection Reviews.
NE0-6.01 Material, Equipment, and Parts Lists for In-Service Nuclear Generation Facilities.
IV. Procurement Document 4 Control NE0-6.02 Preparation and Review of Quality ;
Related Purchase Requsitions. '
NE0-6.04 Review of Proposals.
V. Instructions, Pro-l cedures & Drawings NEO-1.04 Preparation, Issuance and Control of Nuclear Engineering and Opera-tions Procedures.
NE0-3.10 Preparation and Processing of Proposed Revisions to In-Service Inspection Manuals.
VI. Document Control NE0-4.01 Correspondence with the Nuclear Regulatory Commission.
NE0-4.02 Proposed Technical Specification Change Requests.
NE0-4.03 Changes and Updates to Final Safety Analysis Reports for Operating Nuclear Power Plants.
NE0-4.04 Review and Approval of Proposed Changes to Selected License Requirements.
NEO-5.03 Controlled Distribution of Design Documents for Interface Review and Transmittal.
i QAP - Appendix C Date:
Topical Rev.: 10 Page 7 of 32
I NUCLEAR ENGINEERING AND OPERATIONS i
i E
POLICIES AND PROCEDURES MANUAL 10CFR50 APP. B CRITERIA' NEO - PROCEDURES
, -I VII. Control of Purchased Material, Equipment, j and Services NEO-2.11 Trend analysis from Quality . {
Related Documents. i NEO-6.03 Transfer of Material, Equipment and Parts.
o VIII. Identification &
Control of Materials, Parts and Components !
IX. Control of Special l Processes NE0-3.11 Preparation, Qualification, Approval and Revision of Northeast Utilities Nondestructive Examina-tion Procedures.
X. Inspection NEO-2.07 Management of In-Service Inspec-tion Programs.
XI. ' Test Control NEO-7.03 Preoperational Testing of Plant Modifications.
XII. Control of Measuring and Test Equipment XIII. Handling, Storage, and Shipping XIV. Inspection, Ter.., and JEO-8.01 Jumper, Lifted Lead, and Bypass i
Operating Status Control.
XV. Nonconforming Materials, NEO-2.01 Implementation of the Parts, or Components Requirements of Part 21'of Title 10, Code of Federal Regulations: Reporting of Defects and Noncompliance.
XVI. Corrective Action NEO-2.18 Corrective Action.
NEO-3.07 Response to Audit Findings.
XVII. Quality Assurance Records NE0-2.10 Safeguarding Supplier Proprietary Material.
QAP - Appendix C Date:
Topical Rev.: 10 j Page 8 of 32
NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL
.10CFR50 APP. B CRITERIA 'NEO - PROCEDURES NEO-2.12 Control of Nuclear Facilities Safeguards Information.
NEO-2.13 Managment of Nuclear Power Plant Records.
XVIII. Audits. NE0-3.01 Conduct and Format of Nuclear l
Review Board Audits.
)
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1 QAP - Appendix C l Date:
Topical Rev.: 10 Page 9 of 32 1
NUSCO GENERATION ENGINEERING AND' CONSTRUCTION 1
DIVISION PROCEDURES MANUAL !
i 10CFR50 APP. B CRITERIA GE&C - PROCEDURES I. Organization GE&C-1.01 Generation Engineering and Construction Division.
II. Quality Assurance Program GE&C-1.02 Applicability and Use of Genera-tion Engineering and Construction Procedures Manual.
GE&C-1.03 Procedure'for Review of Genera-tion Engineering and Construction ;
Division Procedures as Required !
by Revisions to NU QA Topical Report.
GE&C-1.05 Generation Engineering and Construction Procedures Training Program.
III. Design Control GE&C-2.01 Preparation, Review, Approval, Revision, and Control of NUSCO Generation Engineering and Construction Division- l Specifications.
GE&C-4.02 Review of Engineering Service Or-ganization, Supplier, and Engineer Constructor Design Documents.
GE&C-4.06 Materials List.
IV. Procurement Document Control GE&C-2.06 Purchase of Materials List Equip-ment.
V. Instructions, Pro- GE&C-1.04 Preparation, Issuance and Control-cedures, & Drawings of Generation Engineering and 4 Construction Division Procedures.
GE&C-3.01 Design Information.
GE&C-3.05 Preparation and Control of Design Drawings.
GE&C-5.01 Processing, Documenting, and Filing of Results of the Review of Contractor Procedures. ]
j QAP - Appendix C Date:
Topical Rev.: 10 Page 10 of 32 1
NUSCO GENERATION ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL 10CFR50 APP. B I CRITERIA GE&C - PROCEDURES I
GE&C-5.08 Preparation, Issuance, and l Control of NUSCO Betterment l Construction Work /Special and '
Administrative Work Procedures GE&C-5.09 Preparation, Issuance, and Control of NUSCO Betterment Construction Special Instruc-tions/ Requirement Sheets.
VI. Document Control GE&C-3.04 Design Document Summary. Log.
GE&C-5.10 Preparation, Issuance and Control j
' of NUSCO Betterment Construction Project Documents List.
VII. Control of Purchased Material, Equipment, l and Services GE&C-2.02 Review of Proposals Submitted by Engineering Service Organizations, Suppliers, Vendors, and Contractors.
VIII. Identification and Control of Materials-l Parts & Components IX. Control of Special GE&C-5.03 Control of Special Processes.
j- Processes 1
X. Inspection XI. Test Control XII. Control of Measuring GE&C-5.04 Measuring and Test Equipment
& Test Equipment Control Program.
XIII. Handling, Storage, and Shipping XIV. Inspection, Test, and Operating Status QAP - Appendix C Date:
Topical Rev.: 10 Page 11 of 32
NUSCO GENERATION ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL ~-
10CFR50 APP. B CRITERIA' GE&C - PROCEDURES XV. Nonconforming .GE&C-5;05-Issuance of.a Stop Work Order.
Materials, Parts,
+- or' Components GE&C-5.06 InstaIIation of Nonconforming Material,. Equipment, and Parts.
GE&C-5.07 Processing Nonconformance Reports.
XVI. Corrective Action XVII. Quality Assurance .
Records .GE&C-2.05 Retention, Control and Final Disposition of Project Document Files for- Betterment Projects.
XVIII. Audits-
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QAP - Appendix C Date:
Topical Rev.: 10 Page 12 of 32
NUCLEAR PLANT RECORDS MANUAL 10CFR50 APP. B CRITERIA' NPRM - PROCEDURES
. (
I. Organization NPRM-1.07 Nuclear Records Section and Responsibilities.
II. Quality Assurance Program NPRM-6.01 Training Requirements. 5 V. -Instructions Proce- NPRM-1.02 Issuing of the Nuclear Plant cedures, and Drawings Records Manual.
NPRM-1.04 Preparation of Nuclear Plant Records Manual. ;
VI. Document Control NPRM-1.03 Document Review and Acknowledge- l 4
ment.
NPRM-2.02 Maintaining Nuclear Plant Records Vendor and Manufacturer File.
-NPRM-2.03 Maintenance of Nuclear Plant Records Backup Index.
NPRM-2.04 Quality Checking of Record Indexing.
NPRM-3.01 NUPOC/NUSCO Drawing Control System.
NPRM-3,06 Request for Nuclear Plant Drawing or Aperture Card Copies.
NPRM-3.09 Maintenance of Backup to the Drawing Status Files.
XVII. Quality Assurance Records NPRM-1.05 Establishing Submittal Schedules for Transfer of Nuclear Records Into Nuclear Records Facilities.
NPRM-1.06 Nuclear Power Plant Quality Assurance Records Generated Collected and/or Transmitted by External Organizations.
QAP - Appendix C Date:
Topical Rev.: 10 Page 13 of 32
r NUCLEAR PLANT RECORDS MANUAL
,10CFR50 APP. B CRITERIA NPRM - PROCEDURES i
NPRM-1.08 Retention and Control of Quality '
Assurance Records Generated in Support of the Nuclear Plant Records System.
NPRM-2.01 16MM Roll Film Microfilming Procedure.
NPRM-2.05 Inspection of Permanent Storage Vaults for Temperature, Humidity, and General Condition.
NPRM-2.06 Inspection of the Physical Condi-tion of-Nuclear Plant Documents of Record Stored Within Nuclear.
Records Vaults.
NPRM-2.07 Storage of Radiographs and Photo-graphic Materials Other Than-Mi-crofilm.
NPRM-2.08 Use of Updateable Microfiche Sys-tems.
NPRM-3.08 35MM Aperature Card Microfilming Procedure Using the 3M 2000E Camera.
NPRM-4.01 Housecleaning Guidelines for Records.
NPRM-4.02 Transmittal / Receipt of Nuclear Records.
NPRM-4.03 Access to Nuclear Plant Records '
Facilities and Records. !
NPRM-4.04 Disposition of Nuclear Plant Records.
NPRM-4.05 Checklist of Required Nuclear Power Plant Records Including Quality Assurance Records.
NPRM-4.06 Descriptions of Nuclear Plant Records Storage Vaults.
QAP - Appendix C Date:
Topical Rev.: 10 Page 14 of 32
NUCLEAR PLANT RECORDS MANUAL 10CFR50 APP. B CRITERIA NPRM - PROCEDURES S
NPRM-4.07 Guide for Writing Implements and Paper Stock to be used for Docu-ments Intended for. Microfilming. !
1 NPRM-4.08 Proprietary / Confidential Record l Control.
NPRM-4.09 Assignment.of 5ource Record Storage Locations to Nuclear.
. Records NPR Computer File Entries.
NPRM-5.01 Nuclear Records System Descrip- l tion.
NRPM-5.02 NPR/DWG' Computer Program Diction-ary Maintenance. !
NPRM-5.03 NPR/DWG Computer File' Integrity Vertification.
NPRM-5.04 Nuclear Records Indexing Guide-lines & Minimum Index Entry Re-quirement.
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f QAP - Appendix C h l
Date: i Topical Rev.: 10 Page 15 of 32
E6 , .
at 1 INFORMATION RESOURCES.
' PROCEDURES 10CFR50 APP. B.
CRITERIA IR - PROCEDURES
'I. 'OrganizationL IR-1.01 Organization of_the'IR Group.
- I4 .' Quality Assurance
' Program. .'IR-2.01 QA Indoctrination and Training.
III.1 Design Control IR-3.07 QA Requirements for Quality
, Related Computer Software. 1 IV. Procurement Document Control. IR-1.04 Request for Computer Services and/or Equipment Acquisition.
-V. . Instructions, Procedures IR-1.02
~
Format and Content of .IR Procedures..
'IR-1.03 Preparation, Issuance, and Controls of Resources Group Procedures.
VI. ~ Document Control- IR-1.05 Maintenance, Control, and-Distribution of.the Quality Related Software List.
IR-3.02 Allocation, Removal, Access, and Control of Quality Related Software Stored on Magnetic Mediazin the IR Offsite Magnetic Media Vault.
IR-3.04 IR Offsite Magnetic Media Vault.
XVIII. Audits IR-3.01 Resolution of Audit Findings.
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l QAP - Appendix C l Date:
Topical Rev.: 10 Page 16 of 32
l1 NUSCO NUCLEAR OPERATIONS DEPARTMENT PROCEDURES
- 10CFR50 APP. B
' CRITERIA N0D - PROCEDURES 1 I. _ Organization NOD-1.01 Organization. I V. Instructions,~ Pro-cedures:and Drawings N0D-1.02 Preparation, Issuance, and' Control of Department Procedures.
i NOD-1.03 Distribution and Accountability of Department Procedures.
VI. Document Control- NOD-1.04 Distribution of Design Documents. I N0D-3.02 Production Maintenance Management. j System.(PMMS) Automated Work
. Order System.
XVII. Quality Assurance.
Records N0D-1.05 Quality Assurance Records. :
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QAP - Appendix C Date:
Topical Rev.: 10 Page 17 of 32 2
MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
I. Organization ACP-QA 1.01 Millstone Administration.
ACP-QA 1.02 Organization & Responsibi-lities.
ACP-QA 1.04 Plant Operations Review Com-mittee.
ACP-QA 1.05 Site Operations Review Com-mittee.
'II. Quality Assurance ACP-QA 1.06 Quality Assurance / Quality Program Control Program.
ACP-QA 1.10 Fire Protection Quality As-surance' Program. l ACP-QA 2.01 QA Program Boundary.
ACP-QA- 2.02C Work Orders, ACP-QA 2.05 Fire Protection Program.
1 ACP-QA 2.14 Turnover of Systems, Components, and Structures (NEO 7.02).
ACP-QA 8.01 Millstone Station Training.
ACP-QA 8.07 QA Training Program.
ACP-QA 8.08 Millstone Reactor Operator Training Program.
ACP-QA 8.16 Training, Certification &
Identification of Qualified Inspection and Testing Personnel.
ACP-QA 8.21 Qualification of Audit Per-sonnel.
III. Design Control ACP-QA 2.13A Computer Software Implemen-tation.
QAP - Appendix C Date:
Topical Rev.: 10 Page 18 of 32
~ MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES- (ACPS)
APPENDIX B TO 10CFR PART 50' MILLSTONE QA (ACPS)
ACP-QA 2.13B Maintenance and Control of Site Computer Systems.
ACP-QA 3.08' Safety Evaluations-(NE0 3.12). ,
i
~ACP-QA 3.09 Preparation Issuance and
' Control of Project' Assignments.
ACP-QA 3.10 Preparation, Review, and ,
Disposition of Plant Design '
Change Request (PDCRs)
(NEO 3.03). )
ACP-QA 3.11 Preparation, Review, Approval, Revision, and Control of' Specifications (NEO 5.04).
ACP-QA 3.12 Design Inputs and Design Verification (NEO 5.04).
ACP-QA 3.13 Preparation, Review, and Approval of Design Analyses and Calculations (NEO 5.06).
ACP-QA 3.14 Design Change Notices for Design Documents (NEO 5.11).
ACP-QA 3.15 Performance of Fire Protection Reviews (NEO 5.12).
IV. Procurement Document ACP-QA 4.02A Preparation and Review of Control Quality Related Purchase Requisitions (NEO 6.02).
ACP-QA 4.02B Receipt, Control, and Identification of QA Material.
ACP-QA 4.06 Procurement and Evaluation j of Shelf Life Material.
V. Instructions, Pro-cedures, & Drawings ACP-QA 3.05 Review & Approval of Vendor !
Procedures.
ACP-QA 3.06 Preservice Unit Instructions. )
QAP - Appendix C Date:
Topical Rev.: 10 Page 19 of 32
MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
ACP-QA 3.07 Maintenance of Station implementing Procedures in accordance with NUSCO Governing Documents.
VI. Document Control ACP-QA 3.01 ACP's & Station Forms. i ACP-QA 3.02 Station Procedures & Forms.
ACP-QA 3.03 Document Control.
ACP-QA 3.19 Controlled Distribution of Design Documents (NEO 5.03).
VII. Control of Purchased Material, Equipment &
Services ACP-QA 4.05 Product Acceptance Inspec-tion & Testing.
ACP-QA 4.09 Transfer of Material Equipment and Parts (NEO 6.03).
ACP-QA 5.02 Trend Analysis from Quality-Related Documents.
VIII. Identification &
Control of Materials, Parts & Components ACP-QA 4.03A Classifying and Upgrading Spare Parts for Use in QA Application.
ACP-QA 4.03B Material, Equipment, and Parts Lists for In-Service Nuclear Generation Facilities (NEO 6.01).
ACP-QA 4.07 Control of Weld Material. t IX. Control of Special Processes ACP-QA 2.07 Control of Special Processes.
X. Inspections ACP-QA 2.02A Installation Inspections.
ACP-QA 9.CL In-service Inspection Program.
QAP - Appendix C Date:
Topical Rev.: 10 Page 20 of 32
p4, .3 ,
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MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
ACP-QA- 9.07 Quality Assurance Surveillance Program. l XI. Test Control- ACP-QA 2.02B Retests.
n' 2.15 Preoperational Testing'of' ACP-QA i
Plant Modifications (NEO.7,03).
'l ACP-QA 9.02 Station Surveillance Program.
4 ACP-QA 9.02A Unit 1 Surveillance Master Control List, j
- i ACP-QA 9.02B Unit 2 Surveillance Master Test Control List.
'ACP-QA 9.03 Inservice Plant Testing.
XII.-Control of Measuring &
Test Equipment ACP-QA 9.04 Control & Calibration of Measuring and Test Equipment.
XIII. Handling,' Storage
-Shipping. j ACP-QA 4.01 Plant Housekeeping. l
- ACP-QA 4.04 Instructions for Packaging, ;
Shipping, Receiving, Storage !
& Handling.
f q
ACP-QA 6.04 Radioactive Material Ship--
{
ping Requirements. I XIV. Inspection, Test &
Operating Status ACP-QA 2.06A Station Tagging.
ACP-QA 2.06B Station Bypass / Jumper i Control (NEO 8.01).
ACP-QA 2.06C Station Bypass / Jumper Control for Trouble Shooting, Red Lining, and Calibration.
ACP-QA 2.12 System Valve Alignment Con-trol.
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QAP - Appendix C Date:
Topical Rev.: 10 Page 21 of 32
MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
XV. . Nonconforming
, Materials, Parts
. or~ Components- ACP-QA 5.01 Nonconforming Materials &
Parts. !
XVI. Corrective' Action ACP-QA 10.01 Plant Incident Report.
ACP-QA 10.06 NRC Commitment Follow Pro-gram.
-ACP-QA 10.09 Licensee Event Report.
ACP-QA 10.10 Corrective Action.
XVII, Quality Assurance .
i
' Records ACP-QA 10.04 Nuclear Power Plant Records. -'
XVIII~.~ Audits ~ ACP-QA 9.01 Quality Assurance Audits.
i QAP - Appendix C.
Date:
Topical Rev.: 10 Page 22 of 32
-CONNECTICUT YANKEE QA PROCEDURES CONNECTICUT YANKEE APPENDIX B TO 10CFR PART 50- QA PROCEDURES I. Organization ACP 1.0-3 The Connecticut Yankee
- Organization Responsibility and Authority.
ACP 1.2-1.1 Plant Operations Review Committee.
.II. Quality Assurance Program ACP 1.2-2.1 Request-for.a Category Evaluation.
ACP 1.2-2.2 Quality Assurance Program Boundary.
ACP 1.2-2.3 , Certification, and Identifica-tion of Qualified Inspection j and Testing Personnel. 1 I
ACP 1.2-2.4 Housekeeping Requirements. i ACP 1.2-2.5 Classifying and Upgrading Spare Parts.
l ACP 1.2-2.6 Radioactive Waste Packaging k and Shipping Quality Assurance I Program.
ACP 1.2-2.7 NEO 3.08, Rev. 2, Processing i Proposed Revisions to the !
Northeast Utilities Quality Assurance Program (NUQAP)
Topical Report.
ACP 1.2-2.8 NEO 6.10, Use of the PMMS Data Base to Indicate Quality Assurance Program Applicability.
ACP 1.2-2.9 Quality Assurance and Quality Control in Station Radioactive Material Processing, Classification, Packaging, and Transportation.
III. Design Control ACP 1.2-3.1 NEO 3.03 - Preparation, Review and Disposition of Plant Design Change Requests (PDCRs).
QAP - Appendix C l Date:
Topical Rev.: 10 Page 23 of 32 a
1 1
I CONNECTICUT YANKEE QA PROCEDURES i
CONNECTICUT YANKEE
. APPENDIX B TO 10CFR PART 50 QA PROCEDURES ACP 1.2-3.3 Setpoint Change Request (SCR).
ACP 1.2-3.4 NEO 5.04 - Preparation, Review Approval, Revision and Control of Specifications.
ACP 1.2-6.9 NEO 3.12 Safety Evaluations.
IV. Procurement Document Control ACP 1.2-4.1 Procurement Document Review. I V. Instructions, Pro-cedures & Drawings ACP 1.2-5.1 PMMS Trouble Reporting System and Automated Work l Order.
VI. Document Control ACP 1.2-6.1 Document Distribution &
Accountability.
ACP 1.2-6.2 Master Document Index.
ACP 1.2-6.4 Temporary Procedure Change. I i
ACP 1.2-6.5 Station Procedures.
i ACP 1.2-6.10 Maintenance of Station Implementing Procedures with NUSCO Governing Documents.
ACP 1.2-6.11 Drawing Change / Submittal Requests.
ACP 1.2-6.12 NE0 8.04, Safety Evaluation of Proposed Changes to Station Procedures.
ACP 1.2-11.6 Proposed Technical Specifi-cation Change Requests, i VII. Control of Purchased Material, Equipment &
Services ACP 1.2-7.1 Receipt Inspection and Identification of Materials, Parts, and Components.
ACP 1.2-7.2 Fuel Assembly Receipt Inspection.
QAP - Appendix C Date:
Topical Rev.: 10 Page 24 of 32 a
CONNECTICUT YANKEE QA PROCEDURES CONNECTICUT YANKEE APPENDIX B TO 10CFR PART 50 QA PROCEDURES VIII. Idtntification &
Control of Materials,
. Parts & Components ACP 1.2-8.2 Material Issue.
ACP 1.2-8.3 Weld Material Control.
IX. Control of Special Pro' cesses ACP 1.2-9.1 Control of Special Processes.
i ACP 1.2-9.2 Requirements for Cleaning of Fluid Systems & Associated Components.
ACP 1.2-9.3 NEO 3.11 - Preparation,
[
Qualification, Approval, and ,
Revision of Northeast '
Utilities Nondestructive Examination Procedures.
ACP 1.2-9.4 Inservice Inspection Indication Reporting.
X. Inspections ACP 1.2-10.1 Installation Inspections.
1 ACP 1.2-10.3 Authorized Nuclear Inspector 1 (ANI)/ Authorized Nuclear Inservice Inspector (ANII). {
t ACP 1.2-10.4 Monitoring of QA Activities.
i XI. Test Control ACP 1.2-11.1 Technical Specification f Surveillance Tracking. j ACP 1.2-11.2 Review of Test Data.
ACP 1.2-11.3 Retests. \
I 1
ACP 1.2-11.4 Product Acceptance Tests. j ACP 1.2-11.5 QA Activity Surveillance. !
l ACP 1.2-11.6 NEO 4.02 - Proposed Technical ;
Specification Change Requests.
XII. Control of Measuring & !
Test Equipment ACP 1.2-12.1 Control of Measuring and l i
Test Equipment.
QAP - Appendix C Date:
Topical Rev.: 10 Page 25 of 32
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- ?- ,
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.a : ' CONNECTICUT-YANKEFl QA PROCEDURES-
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<: .- 4' CONNECTICUT YANKEE'~
APPENDIX B TO 10CTR-PART 50 _ ,,_ _ QA PROCEDURESJ _ _ ;_.
(- <
XIII. Handlin,;,. Storage.& .
- Shippictfj ACP 1.2-13.1 . Handling of Material L.
Equipment.
- g \
ACP' l'.2-13.2 StorageofMatehial& Equip- j
, ment:. i ACP 1.2-13.5 Entry and;Exf't from Station e of Treasportes for Nuclear ;
By-Product Material (Radwaste). '
N+9 .
ACP 1.2 13.6 Packaging and Shipping Requirements for Material Parts,end Components.
i ACf 1.2-13.7 Shipping'Q'uality Control of Radioactive Material Shipments.
.XIV.'Ynspection, Test &
z' Operating Status ACP 1.2-14.1 NEO 8.01 - Jumper,-Lifted !
Lead and Bypass Control.
ACP 1.2-14.2 Equipment Control (Locking &
Tagging). j i
'.q'-
XV. honconforming 11aterials, Parts,
.g- or Components ACP 1.2-15.1 Nonconformance Control.
a ACP 1.0-14 Determination'and Follow of
/ Substantial Safety Hazards j (SSH).
XVI. Corrective Action ACP 1.2-16.1 Plant Information Reports.
XVII, Quality Assurance Records ACP 1.2-17.2 Nuclear Power Plant Records.
ACP 1.2-17.3 Identification of Radiographs.
I XVIII. Audits ACP 1.2-18.2 NEO 3.07, Rev. 1, Response '
to Audit Findings.
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QAP - Appendix C Date:
Topical Rev.: 10 Page 26 of 32
NUSCO STANDARD
. QUALITY CONTROL PROCEDURES 10CFR50 APP. B-CRITERIA SQC - PROCEDURES II . - Quality' Assurance Program- SQC-1.04 Qualification, Training, and Certification of Quality Control-Inspection and Testing Personnel.
IV. Procurement' Document Control SQC-2.01 Performance of Procurement Document Review.
V. Instructions, Proce-dures, and Drawings SQC-1.01 Preparation and Control of Standard Quality Control Procedures.
VI. Document Control SQC-3.01 Qualit'y Review of Work Orders.
VII. Control of Purchased Material, Equipment, and Services SQC-2.02 Performance of Receipt Inspection Activities.
X. Inspections SQC-3.02 Performance of Inspection Activities.
XIV. Inspection, Test, and
-Operating Status- SQC-1.02 Inspection Status (Tagging).
XV. Nonconforming Materials, Parts, and Components SQC-1.03 Control of Nonconformances.
QAP - Appendix C Date:
Topical Rev.: 10 Page 27 of 32
NU NELDING 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 Processes AP 701 Preparation, Qualification, Approval & Revision of NUSCO Welding Procedures.
AP 703 Preparation, Review & Approval of Detailed Welding Procedures.
AP 702 Control of Welder & Brazer Quali-fications.
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l QAP - Appendix C Date:
Topical Rev.: 10 3
Page 28 of 32
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NU PURCHASING BUSINESS PROCEDURES l J
PURCHASING
' APPENDIX B TO 10CFR PART 50 QA PROCEDURES IV. Procurement Document-
' Control BP - 3.1 Requisition:
- Standard and Repeating.
BP - 3.3- Purchase Orders.
BP - 3.4 Changes to Purchase Orders.
BP - 3.19 Blanket Purchase Orders.
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l QAP - Appendix C Date:
Topical Rev.: 10 Page 29 of 32
I NUSCO RELIABILITY ENGINEERING PROCEDURES MANUAL 10CFR50 APP. B CRITERIA 1U0 - PROCEDURES-I. Organization. QRE-1'.01 Organization.
.II. ' Quality' Assurance Program QRE-1.02 Applicability and Use of Re-
-liability Engineering Sec-tion Procedures Manual.
QRE-1.06 Training Program.
QRE-1.09 Training of Inservice Inspection and.Nondestuctive Examination Personnel.
QRE-1.10 NUSCO ISI Coordinator Responsibilities and Conduct. ,
of'ISI Planning and On-Site
-Activities for Refueling-Outages.
V. Instructions Procedures and Drawings QRE-1.04 Preparation, Issuance and- 1 4
Control of Engineering De--
partment Procedures.
I IX. -Control ~of Special Processes QRE-1.16 Nondestructive Examination Procedures.
XVII. Quality Assurance Records QRE-1.12 Control of Documents.
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QAP - Appendix C Date:
Topical Rev.: 10 l Page 30 of 32 l I
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REACTOR ENGINEERING BRANCH PROCEDURES 10CFR50 APP. B-CRITERIA REB - PROCEDURES III. Design Control REB-3.01 Generation of INCORE Analytical Input From B&W Data.
REB-2.01 Project Follow, Review and Documentation for Initial Core and Reload Fuel Campaigns.
REB-3.02 Generation of Millstone Unit 1 Bundle Exposure and Isotopic Data for the Nuclear Fuel Branch.
REB-3.03Q Generation and Evaluation of Incore Code Results to Verify Technical Specification Compliance.
REB-3.06 Computer Program Development and Control.
V. Instructions, Procedures REB-1.01 Preparation, Issuance and-and Drawings Control of REB Procedures and Subtier Instructions.
XVII. Quality Assurance Records REB-1.02 Reactor Engineering Branch Record Retention - Management of Nuclear Power Plant Records.
I QAP - Appendix C Date:
Topical Rev.: 10 Page 31 of 32
!- i- ..
GENERATION FACILITIES LICENSING BRANCH.
PROCEDURES 10CFR50 APP. B CRITERIA GFL - PROCEDURES II. ~ Quality Assurance Program GFL-2.01Q Training in NEO Group Nuclear Policies, Procedures, and Programs.
V. Instructions, Procedures GFL-1.01Q Preparation, Issuance and-and Drawings Control of Generation-Facilities Licensing Branch Procedures and Instructions.
VI. Document Control GFL-3.01Q Regulatory Agency Correspondence.
GFL-3.03Q U.S. Nuclear Regulatory Commission-NUREG's.
GFL-3.04Q U.S. Nuclear Regulatory Commision Federal Register Notices.
GFL-3.05Q U.S. Nuclear Regulatory Commission Regulatory Guides.
GFL-3.06Q Documentation of Telephone Conversations.
GFL-3.07Q Forward Commitments.
GFL-3.08Q Preparation and Submittal of Special Nuclear Material, Source Material, and Byproduct Material License Applications.
XVII. Quality Assurance Records GFL-3.02Q Management of Nuclear Power Plant Records.
QAP - Appendix C Date:
Topical Rev.: 10 Page 32 of 32
APPENDIX D
{
t NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT j REGULATORY GUIDE AND ANSI STANDARD COMMITMENTS .
i N,0TE: The NUQAP is committed to utilize the guidance obtained from the following regulatory documents and their endorsed standards. 1 Exceptions to these positions are listed in Appendix F of this ;
topical report.
1 Appendix B to 10 CFR, Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. I 10 CFR 50, Section 50.54, Condition of Licenses.
l 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. j Regulatory Guide 1.28 - 2/79 - Quality Assurance Program Requirements (Design and Construction) Endorses ANSI N45.2 - 1977. j 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.
l Regulatory Guide 1.38 - Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled j Nuclear Power Plants, 5/77 - Endorses ANSI N45.2.2 - 1972.
Regulatory Guiae 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, Rev. 1, 9/80 - Endorses ANSI N45.2.6 -
1978.
Regulatory Guide 1.64 - Quality Assurance Requirements for the Design of Nuclear Power Plants, 6/76- Endorses ANSI N45.2.11 - 1974.
QAP - Appendix D Rev.: 10 Date:
Page 1 of 2
Regulatory Guide 1.70, " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants - LWR Edition", Revision 2, September 1975 is utilized for Connecticut Yankee, Millstone 1, and Millstone 2.
Revision 3 has been used in the update process for Connecticut %ankee and Millstone 1 for format and to the nearest extent practical for content.
No new analyses have been performed which would be required by Revision 3.
Revision 3, November 1978 is utilized for Hillstone 3.
Regulatory Guide 1.74 - Quality Assurance Terms and Definitions Feb.
74 -Endorses ANSI N45.2.10 .1973.
Regulatory Guide 1.88 - Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records - 10/76 - Endorses ANSI N45.2.9 -
1974.
Regulatory Guide 1.94 - Quality Assurance Requirements for Installation, inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of 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.
Regulatory Guide 1.144 - Auditing of Quality Assurance Programs For Nuclear Power Plants - Rev. 1 - 9/80 -Endorses ANSI N45.2.12 - 1977.
Regulatory Guide 1.146 - Qualification of Quality Assurance Program Audit t Personnel For Nuclear Power Plants - 8/80 -Endorses ANSI N45.2.23 - 1978.
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l QAP - Appendix D Rev.: 10 Date:
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APPENDIX E j NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT GLOSSARY OF QUALITY ASSURANCE TERMS Accept As Is'- (also known as "Use-As-Is") a disposition which may be imposed for a nonconformance when it can'be established that the discrepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.
l As-Built Documents - Documents which accurately describe the condition i actually achieved in a system, structure, or component. These documents include: material certification and test data; reports of inspectionsc examinations, and test results; drawings, specifications, procedures, sud instructions; and records of nonconformance and their resolution.
Audit - a formal, documented activity performed in accordance with written checklists or procedures to verify by evaluation of objective i evidence that a quality assurance program has been developed, documented, l and implemented in accordance 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 con' sequences 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 engi-neering, procurement, construction, and installation of material, equip- i ment, and parts. The Nuclear Steam Supply System Supplier (NSSS Suppli- !
er) 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.
I Department - The use of the word department, throughout the NUQAP Topical Report, can refer to any portion of the NUSC0/NUPOC organization (i.e.,
Group Division, Department, Branch, Section, or Unit, as applicable).
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Departmental Measuring and Test Equipment List - a list of all departmen-tal 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 5 other documents defining technical requirements of systems, structures, and components.
Design Changes - changes in drawings and specifications which define the design of systems, structures, and components of nuclear power plants.
Design Documents - design documents referred to herein are the drawings and specifications that define the design of systems, structures, and components; the Final Safety Analysis Report (FSAR); the License Document; Technical Specifications; and Environmental Technical Specifications. l {
t 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 systems, structures, and components of a nuclear power plant.
Engineer-Constructor / Contractor Installation Inspection - an inspection of systems, structures and components performed by the Engineer-Constructor /
Contractor prior to system release / transfer to NUPOC for preoperational testing.
Engineering Assurance Audits - Audits performed of corporate quality activities by NUSCO Quality Assurance.
Engineering Service Organization - organizations that provide services such as analysis, testing, and inspection.
Generation Facilties Records - the organization responsible for establir.hing the Corporate Nuclear Plant Records Program which is imple-mented at each Nuclear Plant Records Facility.
Handling - the transfer of an item from one location to another within a \
i contractor's, supplier's or engineering service organization's facility }
or at the nuclear power plant. l l
Identification - a means by which material, equipment and parts can be l traced to their associated documentation through the use of heat numbers, {
lot numbers, part numbers, serial numbers, or other appropriate means. j l
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In-Process Verifications - An in-depth review of an activity to which NUSCO Quality Assurance coverage has been assigned. This review is done with an approved written checklist to verify that the activity is being completed in accordance with the approved documents, utilizing auditing techniques.
- Inspection - a phase of quality control which, by means of examination, observation, or measurement determines the conformance of material, j equipment, parts, and processes to predetermined quality requirements.
l Inspection Status - identification of material, equipment, and parts that i 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.
(4) providing required base line data for in-service inspection.
Manager, QA/ Designee - the designee is a NUSCO Quality Assurance emp-loyee, as well as the respective NUPOC QA/QC Supervisor or NUP0C QA/QC employee as depicted by Figure 1.6 of QAP 1.0.
Measuring and Test Equipment - those instruments, gages, tools, fixtures, reference and transfer standards, nondestructive test equipment, and measuring devices used during inspection and testing to determine that measuring and test parameters comply with appropriate requirements in specifications and drawings.
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 after deli-very.
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(3) Of such a nature that product acceptance inspections / tests performed upon receipt of the items do not require operations l l
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 Company (NUSCO) - a wholly owned subsidiary of Northeast Utilities that provides engineering, procurement, construc-tion, and quality assurance services for Northeast Utilities relating to design, construction, and preoperational testing of nuclear power plants and major modifications thereto.
Northeast Utilities Quality Assurance Program (NUQAP) - consists of the NUQAP Topical Report, Quality Assurance Branch Procedures and other Northeast Utilities Group / Divisional / Departmental / Branch /Section quality related procedures.
Nuclear Plant Operating Companies (NUPOC) - which as a subsidiary of Northeast Utilities performs preoperational testing of 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 nuclear power plants. The companies which comprise NUPOC are The Connecticut Yankee Atomic Power Company and The Northeast Nuclear Energy Company.
Nuclear Plant Records Facilities - three separate facilities; located at Millstone Station, Connecticut Yankee, and Berlin; responsible for indexing, retention, retrieval, and protection of Nuclear Plant Records.
NUSCO/NUPOC Engineer-Constructor Contractor, Supplier, and Engineering Service Organization Audits - audits performed by NUSC0/NUPOC Quality Assurance of the Engineer Constructor, contractors, suppliers, and engineering service organizations quality activities.
NUSCO Quality Assurance Contractor, Supplier, ag Engineering Service Organization List - a list identifying the approval status of the quality assurance programs of contractors, suppliers, and engineering service organizations.
NUSCO Quality Records Center - the location at NUSCO of the NUSCO Quality Assurance records files under the cognizance of the NUSCO Quality Assu-rance Branch.
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l QAP - Appendix E Rev.: 10 Date:
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" Objective Evidence" - any statement of fact, information, or record, either quantitative or qualitative, pertaining to the quality of an item j or service based on observation, measurements, or tests which can be j verified.
(
k Plant Audits - Audits performed at the nuclear power plant by NUSC0/NUPOC Quality Assurance of NUPOC quality activities.
Preoperational Testing - tests performed by NUPOC to ensure systems, structures, and components will perform satisfactorily during operation of the nuclear power plant. 3 j
Preservation - those actions performed to maintain an item in its origi-nal 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, Specifications, Contracts, Purchase Requisitions, and Purchase Orders which provide contractual basis for services such as engineering and procurement; supply of material, ;
l equipment, and parts; construction; installation; inspection; and testing. i They define the requirements which items and services must meet, in order to be considered acceptable by the purchaser.
Product Acceptance Inspection / Test - Inspection /tect 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 systems, structures and components to verify specification requirements have been met.
Project Engineer - a NUSC0/NUPOC employee assigned the responsibility to coordinate the engineering activities addressed in NVQAP.
Project Manager - A NUSCO employee assigned Une responsibility to coordinate all activities addressed in NUQAP relating to their assigned Projects.
Purchased Material, Equipment, and Parts - items procured for use in l systems, structures, and components. I l
Purchased Service - services procured to assist in operation, main- ;
l tenance, modification, and refueling of nuclear power plants. '
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Quality Assurance Records - any record pertaining to the quality of material, equipment, parts, processes, or operations relating to systems, structures and components which are founded on observations, measurements,.
or tests which can be fully checked or verified. Such statements may be recorded on a written or preprinted document or tag. The statesents are authorized with a signature or stamp identifiable to the person making.
the statement of. fact.
Quality Activities - Activities involving parts, components and structures l
for Category I, Radwaste QA, Radwaste Packaging and Shipping, ATWS, FPQA, '
EEQ, MEQ and other regulated programs in accordance with.the requirements mandated by those regulations. Appendix A defines Category I program controls.
Appendix G classifies those attributes applicable to presently committed regulations for other-listed programs above.
Quality Procedures - Those procedures prepared to implement administrative activities associated with the QA Topical Report. Appendix C lists l typical Quality Related Procedures that are reviewed and approved by- '
NUSCO/NUPOC Quality Assurance Organizations.
Note: Department procedures, written to perform specific work activities on components, systems, and structures, are not reviewed by QA organizations as an in-line function. These procedures are reviewed for QA attributes as part of the work order review program at the time of use.
Repair - a disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose which are modified by the use of additional operations and/or processes so that they are suitable for their intended purpose but may not meet all specified requirements.
Retest - a test conducted prior to operation following installation in-spections of work associated with maintenance, modification, and refuel-ing to verify that systems, structures, and components will function satisfactorily when in operation. A retest may also be performed when original test results are invalidated.
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.
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i 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 NUSCO/NUPOC or vendor's site to assure compliance with applicable codes, standards, specifications, procedures, drawings, and procurement documents. Surveillances are not performed to a preplanned ecklist.
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 physi-cal, chemical, environmental, or operating conditions.
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s APPENDIX F !
NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT Program Exceptions
- 1. 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. 1 A records organization exists along with written procedures addressing i the control of quality assurance records.
- 2. ANSI N18.7-1976, paragraph 4.3.2.3 " Quorum" states in part: "A quorum for formal meetings of the (Independent Review) Committee held under the provisions of 4.3.2.2 shall consist of not less than a majority of the principals, or duly appointed alternates...".
.The use of. Alternates was eliminated from the Northeast Utilities Nuclear Review Board (NRB) Charter due to the difficulties of keeping the Alternates up to date. The elimination of Alternates forced the creation of a larger NRB membership (seven to eleven '
members) for greater diversity, resources, and availability.
A quorum of the Nuclear Review Board shall consist of the Chairman or Vice Chairman and at least four NRB members. No more than a minority of.the quorum shall be from the Nuclear Operations Depart-ment. ,
t
- 3. ANSI N45.2.9-1974, paragraph 1.4, definition of " Quality. Assurance Records" states in part: "For the purposes of this standard, a document is considered a quality assurance record when the document has been completed".
Northeast Utilities has developed the following alternative definition to provide guidance during the interim period from the time a document is completed until it is transmitted to the Nuclear Plant i Records Facility:
"A record is considered a working document until it is transmitted to the appropriate Nuclear Plant Records Facility -(NPRF) at which time it is designated as a Quality Assurance Records. The following maximum time limits are established for the transmittal of working documents to the NPRF:
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Operations Documents - Documentation generated during Plant Operations may be maintained, as needed, by operating plant.
departments, for up to one year.
New Construction or Betterment Documents - Documents Which evolve during.new construction or betterment projects shall be transmitted to NPRF within 90 days of completion of a new
' construction project or turnover of a betterment project to plant operations.
All Other Working Documents - All other working documents shall
- 1 i
be transmitted to NPRF within 6 months of their receipt or completion."
i The requirements of_ ANSI N45.2.9-1974 do not apply to these " working documents" based on paragraph 1.1 of the ANSI standard which states:
"It (ANSI N45.2.9) is not intended to cover the preparation of the records nor to include working documents not yet designated as Quality Assurance Records."
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QAP - Appendix F Rev.: 10 1 Date: I Page 2 of 2 l
L APPENDIX G
-QUALITY ACTIVITY MATRIX In addition to QA Category 1, this Topical applies.to other quality activities which are delineated in Appendix G. Quality program requirements are_ derived from the regulatory requirements and NU folicies/ Procedures, some of which are tabulated in Appendix G for Equipment Environmental Qualification (EEQ), Fire Protection (FP),
Anticipated Transient Without Scram (ATWS) and Radwaste (RW). Appendix )
G is intended to be used as a guide. The regulatory requirements and NU Policies / Procedures delineated in Appendix G are not'all inclusive and the user should not solely rely on this section.
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APPENDIX G Quality Activity Matrix
)
Activity Regulatory Requirements NU Policy / Procedure ;
I. EEQ 10CFR50.49 " Environmental 1.NEO Policy Statement i Qualification Rule" Regulatory No. 27 Equipment Guide 1.89 " Qualification of Environmental Qualifi- !
Class IE Equipment for Nuclear cation.
Power Plants" IEEE Standard
- 2. NEO 2.21 Nuclear !
323-1974 " Standard for Qualifying Plant Environmental Class IE Equipment for Nuclear Qualification Program Power Generating Stations" II. Fire Branch Technical Postions: CMEB 1. NEO Policy Statement Protection 9.5-1 Rev. 3, (NUREG 0800) 9.5-1 No. 11 Nuclear Plant Rev. 2, 9.5-1 Appendix A Fire Protection Program 10 CFR 50 Appendix R - Fire 2. NEO 2.14 Nuclear Plant Protection Program for Nuclear Fire Protection Power Plants Operating Prior to Program
' January 1, 1979 III. ATWS 10CFR50.62 " Requirements for 1. NEO Policy Statement - 1 Reduction of Risk from antici- N/A' pated trans'ent without scram 2. NE0 Procedure -N/A (ATWS) event for light water 3. Other
Reference:
cooled nur r power plants" Position of Maintenance of Quality Related Equipment GEE-85-1632' :
8/21/85 I IV. Radwaste QA Regulatory Guide 1.143 and 1. NEO Policy Statement.-
10CFR71, Subpart H - Quality N/A Assurance 2. NEO Procedure - N/A V. Radwaste 10CRF61.55, 10CFR61.56, 10CFR71, 1. NEO Policy Statement -
J Packaging & Subpart N/A Shipping H-Quality Assurance, NRC Low Level 2. NEO 6.07 - Quality Waste Licensing Branch Final Waste Assurance and Quality Classification and Waste Form Control in Station Technical Positions, Rev. O, May 1983, Radioactive Material and NRC Letter L. B. Higginbotham Processing, Classifi- ,
to Licensees, February 10, 1984, cation, Packaging, and !
Additional Guidance on Implementation Transportation of 10CFR61 QAP - Appendix G Rev. 10 Date:
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' VI . MEQ Mechanical Equipment Qualification 1. NEO Policy StatementL-There is currently'no regulatory .
N/A' requirements established for MEQ. 2. NEO Procedures - N/A 1 However, an MEQ program has been 3. Other
Reference:
I established for MP3 and is, therefore, Mechanical Equipment. ;
applicable to MP3 only. Report dated December 4, 1985 1
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