ML20195F412
| ML20195F412 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/13/1998 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20195F410 | List: |
| References | |
| GGNS-TOP-1A, NUDOCS 9811190258 | |
| Download: ML20195F412 (120) | |
Text
. . . . . . . . . _ . . - . . . . ... . _. ~ .. ..- . -. .... - . - ..- .. . . .. - .. . ~.- -. - - ... ..- .. .. .
l i'
s Attachment B OQAM Rev. 16 - Offical Submittal per 10CFR50.54(a) (3)
(
9811190258 ADOCK981113 13 05000416;n l PDR PDR m.
p c.
[-
OQAMNRC. DOC
_ _ ~ . _ . _ _ _ . . . _ _ . _ . . _ . . _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ . . -
OPERATIONAL QUALITY ASSUMNCE MANUAL
- 4
+
i INTRODUCTION r
.This manual describes the Operational Quality Assurance Program established to assure that the Grand Gulf Nuclear Station'(GGNS)'is operated in accordance with applicable regulatory requirements and in a manner which protects the
- public health and safety. The Operational Quality Assurance Program conforms 6
to the criteria established in Appendix B to 10CFR50, " Quality Assurance criteria for Nuclear Power Plants and Fuel Reprocessing Plants," and to the i regulatory positions in applicable .NRC regulatory guides and industry standards as delineated in Appendix A to this manual. Guidance in the preparation of this manual was obtained from the NRC's " Standard Review Plan" (NUREG-0800, former1y NUREG-75/087).
The quality assurance program described herein is applicable to the Grand Gulf Nuclear Station (GGNS), and is referenced in Section 17.2 of the Updated Final Safety Analysis Report. The scope and degree of program applicability may vary:
Scope: The program applies to all operational phase activities that affect the safety-related functions of those structures, systems and components to prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public.
Degree: .In accordance with Appendix B to 10CFR50, the program elements should be applied to activities affecting the quality of safety-related structures, systems and components to an extent consistent with their importance to safety.
l Page 1 of 1 Introduction Rev. , 16
-OQAMR16
o -
OPERATIONAL QUALITY ASSURANCE MAN 1'AL l
TABLE'OF CONTENTS i-i
[ ' POLICY -TITLE REV.
. Policy 1, Organization 16 l ~ Policy" 2L ' Quality Assurance Program 16
' Policy 13 Design Control -
16-l Policy '4 : Procurement Document Control 16 Policy S' Instructions, Procedures and Drawings 16 Policy- 6- Document Control 16 Policy' 7' Control of Purchased Material, Equipment, 16 and Services
! Policy. 8 Identification and control of Material, 16 Parts, and Components 16
' Policy ~9 Control of Special Processes Policy 10 Inspection 16 Policy 11 Test Control 16
-Policy 12 Control of Measuring and Test Equipment 16 Policy 13 Handling, Storage and Shipping 16' Policy.14 -. Inspection, Test and Operating Status 16
~ Policy 15- Nonconforming Materials, Parts or Components 16 Policy 16 Corrective Action 16 Policy 17. Quality' Assurance Records 16 Policy 18 Audits 16 Appendix A Conformance of GGNS Operational Quality Assurance ;16 Program to NRC Regul, ory Guides and ANSI Standards
-Appendix B. Document Control Responsibility for Quality 16 Related Documents l Appendix C. Operational Quality Assurance Program 16 Implementing Procedures i
l.
. Page 1 of 1 Table of Contents Rev. 16 i
l OQAMR16.
t
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: ORGANIZATION l.0 ORGANIZATION 1.1 PURPOSE This policy describes the organizations and key personnel responsible for developing, implementing and verifying the effectiveness of the Operational Quality Assurance Program for the Grand Gulf Nuclear Station.
1.2 SCOPE This policy defines the organizational structure and delineates the authority, responsibility and lines of communication for organizations performing functions covered by the Operational Quality Assurance Program.
Certain of these functions may be delegated to other qualified organizations, but responsibility for the program is retained and exercised by the licensee. These delegated functions shall be controlled by lower tier policies. These policies will be reviewed and approved by the Director, Quality to verify conformance with the Operational Quality Assurance Program, 1.3 ORGANIZATION AND RESPONSIBILITY Clear and definitive lines of authority, responsibility and communication are established for all licensee organizations involved in the Operational Quality Assurance Program. These lines extend from the highest management level'through intermediate levels to and including the onsite operating organization and offsite organizational elements.
The organizational structure and functional responsibility assignments are such that attainment of program objectives is accomplished by those who have been assigned responsibility for performing the work, and verification of conformance to established requirements is accomplished by qualified personnel who do not have responsibility for performing or directly supervising the work.
Organizational structure and lines of authority, responsibility and communication are depicted in the organizational chart included at the end of this policy. The dashed line between the Director, Quality, and the Executive Vice President & Chief Operating Officer indicates guidance on Quality Assurance policy matters and a direct escalation path. The dashed line from the Quality Assurance Function Designee to the Executive Vice President & Chief Operating Officer indicates guidance on matters related to Quality Assurance and a direct escalation path.
1.3.1 President & Chief Executive Officer Ultimate responsibility for providing top level direction of all activities associated with the safe and reliable operation of the Grand Gulf Nuclear Station rests with the President & Chief Executive Officer of the company. The President & Chief Executive Officer provides guidance with regard to company quality assurance policy. He delegates Page 1 of 14 Policy 1 Fev. 16 OQAMR16
_ - _ - _ _ _ - . ._ . _ _ _ .. . _ . - __ .__ .- . _. . _ _ _ _m OPERATIONAL QUALITY ASSUPANCE MANUAL !
TITLE: ORGANIZATION l l
i 1.3.1 (Continued):
authority and responsibility for the development, implementation and verification of the Operational Quality Assurance Program to the appropriate organizations through i
the Executive Vice President & Chief Operating Officer. In addition, the President & Chief Executive Officer provides the direction of nuclear fuel cycle planning.
1.3.2 Vice President, Operations GGNS The Vice President, Operations GGNS reports directly to the Executive Vice President & Chief Operating Officer and is j responsible for the administration of all functions associated with the operation of the Grand Gulf Nuclear 3tation, except those delegated to the Vice President, l
Engineering, and the Vice President, Operations Support. He is also responsible for training through the Director, Nuclear Training. He provides guidance with regard to l quality assurance goals and objectives to the Director,
) Quality. He maintains a continuing awareness of quality matters through applicable reports and management audits of the program. It is the Vice President, Operations GGNS' responsibility to assure that the requirements of the Operational Quality Assurance Program are implemented by the organizations under his direction.
l 1.3.3 Director, Quality l The Director, Quality, reports directly to the Vice President, Operations GGNS and is delegated the overall au-i thority and responsibility for establishing, controlling and verifying the implementation and adequacy of the Operational Quality Assurance Program. The Director, Quality, through his staff, is responsible for the establishment of quality assurance policies, goals and objectives.
The primary duties and responsibilities of the Director, Quality include:
1.3.3.1 Developing and controlling the Operational Quality Assurance Program and the content of this manual, including the approval of changes thereto
[ and providing for interpretations thereof; 1.3.3.2 Verifying the implementation of the Operational Quality Assurance Program.
l 1.3.3.3 Reporting to the Vice President, Operations GGNS l and the Executive Vice President & Chief
- Operating Officer on the effectiveness of the t
Operational Quality Assurance Program; 1
1.3.3.4 Reviewing and approving quality assurance procedures and instructions; Page 2 of 14 Policy 1 Rev. 16 OQAMR16 l
. _ _ _ . _ . . . ~ . . _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ . - _ _ _ . . _ . _ _ , _ . _ . . , _ _ _ _ _ . _ _ _ _ _ _ _
OPERATZONAL QUALITY ASSURANCE MANUAL TZTLE: ORGAN 8ZATION
1.3.3 (Continued)
l 1.3.3.5 Providing for review of and concurrence with documents as specified in Appendix B of this manual; 1.3.3.6 Providing for the planning, scheduling and coordinating of training for the Quality Programs L
j Staff; providing quality assurance input to the ;
training and'. indoctrination programs for personnel performing quality-related activities; I and providing for the approval of all Quality Programs Staff certifications.
I 1.3.3.7 Maintaining adequate communications with. ;
j regulatory agencies, suppliers, contractors and J L other licensee organizations on quality assurance matters; 1.3.3.8 This section deleted in Revision 4.
1.3.3.9 This section deleted in Revision 14. !
1.3.3.10 Developing and carrying out an audit program, as described in Policy 18 of this manual, to verify conformance with Operational Quality Assurance i Program requirements; l
1.3.3.11 Providing for periodic review and analysis of NRC l and licensee quality deficiency documents to !
detect possible adverse quality trends and {'
reporting results to the appropriate levels of management.
1.3.3.12 Providing for quality inspections and nondestructive examinations.
1.3.3.13 Providing for the coordination, development and issuance of quality assurance reports as required by management and appropriate procedures.
l l 1.3.3.14 Providing for the coordination and/or
! implementation of administrative services for Quality Programs.
1.3.3.15 controlling, processing, tracking, disposition concurrence, verification and closure of GGNS quality deficiency documents as described in Policy 15 of this manual.
1.3.3.16 This section deleted in Revision 14.
J Page 3 of 14 Policy 1 Rev. 16 OQAMR16
. . - . . , , . _ . . , - - . . ~ . .
n.. . , - . - . , . .
OPERATIONAL' QUALITY ASSURANCE MANUAL TITLE: ORGANIZATZON 1.3.3(Continued):
1.3.3.17 Planning, scheduling, coordinating, performing, and documenting assessment activities.
The Director, Quality, is independent of undue influences and responsibilities for schedules and costs, and has sufficient authority and organizational freedom to identify quality problems, recommend solutions and verify implementation of L solutions. If acceptable solutions cannot be reached he has the responsibility and authority to escalate these matters to the Executive Vice President & Chief Operating Officer.. The Director, Quality, and his staff have the authority, as delineated in the appropriate quality assurance procedure, to initiate action to stop unsatisfactory work and control further processing, delivery, or installation of nonconforming items or continuation of nonconforming services
.pending correction of the nonconforming condition.
1.3.4 Entire section deleted in Revision 12.
1.3.5 General Manager, Plant Operations The General Manager, Plant Operations reports to the Vice
( President, Operations GGNS and is delegated the responsibility and authority for assuring the safe, reliable and efficient operation of the plant within the constraints of applicable regulatory requirements and the operating license. He supervises the operating plant staff; approves plant administrative procedures; implements design changes and plant modifications; implements repairs; reports appropriate matters to management and the Safety Review Committee; oversees outage-and work performance; verifies and closes non-significant naterial nonconformance documents and generally administers plant operations on a day-to-day basis.
He has overall responsibility for execution of the Operational Quality Assurance-Program at GGNS; except for training activities, licensing activities, materials, purchasing and contract activities, and the collection, storage and maintenance of quality assurance and vendor records; and has the authority to stop work if an activity at the Plant is not in conformance with program requirements. It is the responsibility of the General Manager, Plant Operations, to assure that these functions are performed in accordance with the requirements of the Operational Quality Assurance Program.
The General Manager, Plant Operations, is assisted in carrying out his responsibilities by the Manager, Plant Operations; the Manager, Plant Maintenance and Modifications; L the Manager, Outage Management, Manager, Planning &
Scheduling and, Manager, Performance & System Engineering as
, well as the operating plant staff which includes individuals knowledgeable in plant radiation protection. l J
t Page 4 of 14 Policy 1 Rev. 16 OQAMR16
.. . . , -- . -- - - _ - _ _ _ . . - - - - _ .~ .- . . .
OPERATIONAL QUALITY ASSURANCE FANUAL TITLE: ORGANZZATION
1.3.5 (Continued)
In addition, the General Manager, Plant Operations oversees the activities of the Plant Safety Review Committee and provides for necessary liaison with the Safety Review Committee of which he is a member.
1.3.6 This Section deleted in Revision 4.
1.3.7 Director, Nuclear Safety & Regulatory Affairs The Director, Nuclear Safety & Regulatory Affairs reports to the Vice President, Operations GGNS and is responsible for directing the activities of the Nuclear Safety & Regulatory Affairs Staff. The Nuclear Safety & Regulatory Affairs Staff is responsible for securing the licenses and permits required to operate the plant. The Nuclear Safety & Regulatory Affairs Staff also provides technical assistance in the areas of safety analysis. The Director, Nuclear Safety & l Regulatory Affairs, is responsible for nuclear safety / thermal analyses, reliability reviews and safety evaluations, and for making independent recommendations to improve both plant safety and reliability as delineated in the operational assessment review policy and nuclear regulatory requirements.
The Director, Nuclear Safety & Regulatory Affairs, directs the activities of the Independent Safety Engineering Group (ISEG) as described in the UFSAR, Appendix 16B, Section 7.2.6. This staff provides support to the Vice President, l Operations GGNS in matters related to Safety Review Committee activities. It is the responsibility of the Director, l Nuclear Safety & Regulatory Affairs to assure that these functions are performed in accordance with the requirements
! cf the Operational Quality Assurance Program.
1.3.8 Director, Design Engineering - GGNS The Director, Design Engineering - GGNS reports to the Vice President, Engineering, and is responsible for directing the
, activities of the Design Engineering Staff. Design Engineering - GGNS, consisting of the Manager, Mechanical /
l Civil Engineering; Manager, Electrical /I&C Engineering; Manager, Safety Analysis; Manager, Engineering Programs; and l their respective staffs, is responsible for plant design, design review, modifications, chemical / environmental analysis, special processes, accident and transient analyses, and engineering programs-including fire protection. It is l the responsibility of the Director, Design Engineerind -GGNS to assure that these functions are performed in accordance with the requirements of the Operational Quality Assurance Program. The Director, Design Engineering - GGNS is responsible for reviewing GGNS design documents for compliance with the Operational Quality Assurance Program requirements and concurring with the same.
I Page 5 of 14 Policy 1 Rev. 16 '
OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: ORGANIZATION
~.
1.3 (Continued)
l 1.3.9 Safety Review Committee (SRC)
]
Committee composition, responsibility and authority, subjects to be reviewed, administrative controls, and reporting requirements are addressed in Appendix 16B, Section 7, and Section 13 of the GGNS UFSAR.
1.3.10 Plant Safety Review Comm$ttee (PSRC)
Committee composition, responsibility and authority, subjects to be reviewed, and reporting requirements are addressed in Appendix 16B, Section 7, and Section 13 of the GGNS UFSAR.
1.3.11 This section deleted in Revision 10.
1.3.12 Other Organizations l
Other organizations, contractors, or consultants may be '
delegated certain functions which fall under the Operational Quality Assurance Program. In such cases, the licensee shall retain responsibility for the delegated work.
1.3.13 Minimum Qualifications of Quality Personnel The qualification requirements and experience levels of Quality personnel are such as to assure competence commensurate with the responsibilities of the position and are described in ANSI /ANS 3.1 (Draft 12/79). See Appendix A.
Key Quality personnel include the Director, Quality, and the Vice President, Operations Support.
1.3.14 This section deleted in Revision 5.
1.3.15 This section deleted in Revision 11.
1.3.16 This section deleted in Revision 13.
1.3.17 This section deleted in Revision 5.
1.3.18 Entire section deleted in Revision 12 -
1.3.19 This section deleted in Revision 6.
1.3.20 This section deleted in Revision 6A.
Page 6 of 14 Policy 1 Rev. 16 OQAMR16
l OPERATIONAL QUALITY ASSURANCE MANUAL
- '"ITLE
- ORGANIZATION ~
1.3 (Continued)
1.3.21 Vice President, Engineering The Vice President, Engineering reports directly to the Executive Vice President & Chief Operating Officer and is responsible for the administration of all functions associated with the following:
i 1.3.21.1 Procurement of nuclear fuel (fabrication and related services) and the design authority for nuclear fuel and core designs. Providing nuclear engineering analysis support in the fuel and core design area to Design Engineering - GGNS and Performance & System Engineering.
l 1.3.21.2 Providing engineering support to Design Engineering - GGNS in the technical areas of welding, flaw evaluations, fracture mechanics, metallurgy and finite element analysis.
1.3.21.3 Providing engineering support to the Design Engineering - GGNS in the technical areas of configuration management, probabilistic risk assessment, and procurement engineering.
1.3.21.4 Maintaining overall administrative, programmatic, and operational control (excluding implementation) of the Entergy Operations, Inc.,
Central Welding Program (Welding, Heat Treatment and NDE).
Maintaining an awareness of GGNS programs and generic issues to identify best practices, facilitate peer group activities, and coordinate the development of standards, procedures, and programs between the Entergy Operations nuclear facilities.
It is the responsibility of the Vice President, Engineering, to assure these functions are performed in accordance with approved policies. _
1.3.22 This section deleted in Revision 9.
i Page 7 of 14 Policy 1 Rev. 16 coAM916
. . . _ . . . . . - . ~ . -- . - - . - - - . - - ..- . . - .. - - - . _ ~ . _ - . _ .. . .... .. . .
I OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: ORGANIZATION -..
r
1.3 (Continued)
1.3.23 Manager, Emergency Preparedness 1
1 The Manager, Emergency Preparedness reports to the Director, j Nuclear Training and is responsible for the Emergency l j Preparedness Program and ' associated activities. It is the '
responsibility of the Manager, Emergency Preparedness to assure these functions are performed in accordance with the requirements of the Operational Quality Assurance Program..
1.3.24 This section deleted'in Revision 12.
l 1.3.25 This section deleted in' Revision 16.
1.3.26- Manager, outege Management g
-The' Manager, Outage Management, . reports directly to the General Manager, Plant Operations. He is responsible.for planning and scheduling outage activities. It is the l responsibility of the Manager, outage Management to assure I these functions are performed in accordance with the requirements of the Operational Quality Assurance Program.
1.3.27 This section deleted in Revision 11.
1.3.28 This section deleted in Revision 12.
1.3.29 This section deleted in Revision 12.
l l l 1
I i
i i
Page 8 of 14 Policy 1 Rev. 16 l OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: ORGANIZATION
1.3 (Continued)
1.3.30 This section deleted in Revision 13.
1.3.31 Executive Vice President & Chief Operating Officer The Executive Vice President & Chief Operating Officer reports directly to the President & Chief Executive Officer.
He is responsible for administration of all functions associated with the operating and engineering of GGNS and is assisted by the Vice President, Operations GGNS; the Vice President, Engineering; and the Vice President, Operations Support. He maintains a continuing awareness of quality assurance matters and monitors effcetiveness of the program through applicable reports such as trend reports, audit reports, and assessments prepared by the Director, Quality and the Vice President, Operations Support. It is the responsibility of the Executive Vice President & Chief Operating Officer to assure requirements of the Operational Quality Assurance Program are implemented.
1.3.32 Vice President, Operations Support The Vice President, Operations Support reports directly to the Executive Vice President & Chief Operating Officer, and is responsible for the administration of support functions associated with materials, purchasing, contracts, security, information technology, and as follows:
1.3.32.1 Provides technical support in the areas of health physics, chemistry, environmental services, and radioactive waste management.
1.3.32.2 Controls and maintains company directives, policies, and procedures.
1.3.32.3 Provides technical support in the areas of materials, purchasing, contracts, maintenance services, system engineering, operations, training, and refueling outage management to the Grand Gulf Staff.
1.3.32.4 Provides licensing support in the licensing area to the Grand Gulf Nuclear Safety & Regulatory Affairs Staff.
1.3.32.5 Directs.through the Director, Materials, Purchasing & Contracts the activities of the GGNS Manager, Materials, Purchasing & Contracts.
Page 9 of 14 Policy 1 Rev. 16 OQAMR16
_ . .- . _ . . _ - ~ - - -
l OPERATZONAL QUALITY ASSURANCE MFWUAL T2TLE: ORGANIZATION 1.3.32 (Continued):
1.3.32.6 Responsible for maintaining a continuing i
involvement in quality assurance matters and assessing the scope, status, implementation, and effectiveness of the program through contact with and review of reports issued by the Director, Quality and by assuring the performance of supplier evaluations and source verification l activities to verify the adequacy of quality assurance programs established and implemented by l
' suppliers including suppliers of nuclear fuel and associated components. The Vice President, Operations Support (or designee) is responsible for development, maintenance, control, review, and approval of procedures that govern off-site quality organization activities. He assures i safety-related activities are performed in I accordance with the Operational Quality Assurance Program.
l The primary quality assurance duties and responsibilities of the Vice President, Operations Support (or designee) include:
1.3.32.6.1 Reviewing and approving off-site support organizations' procedures except those denoted otherwise in Appendix B. I 1.3.32.6.2 Maintaining adequate communications with suppliers, contractors and Entergy Operations organizations; 1.3.32.6.3 Planning, scheduling, coordinating, and performing supplier evaluations L and source verifications; 1.3.32.6.4 Developing and carrying out an audit program as described in Policy 18 of this manual, to verify conformance with the Operational Quality Assurance Program requirements; l
1.3.32.6.5 Reporting to the Executive Vice President & Chief Operating Officer on the status and adequacy of the operational Quality Assurance Program as applicable to off-site support organizations' quality assurance activities (except those under Director, Design Engineering - GGNS).
l l
Page 10 of 14 Policy 1 Rev. 16 l OQAMR16
F l; . OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: _ ORGANISATION-i l
1.3.32 (Continued) :
1.3.32.6.6 Reviewing and approving the off-site support policies to verify conformance with the Operational Quality Assurance Program; 1.3.32.6.7 Providing for the performance of pre-award evaluation of suppliers; f
1.3.32.6.8 'Providing for the control, processing, tracking, disposition, concurrence, and verification of deficiency documents in accordance with approved policies. This includes those used to control i discrepant material, as described in 1 Policy 15 of this manual.
l 1.3.32.6.9 Planning and performing receipt inspections, procurement document quality reviews, warehouse i inspections, shipout inspections, and 1 for controlling discrepant. material at GGNS, as described in Policy 15 of this manual.
g The quality assurance function is l independent of undue influences and L responsibilities for schedules and costs, and the designated person assigned responsibility for quality assurance has sufficient authority and organizational freedom to identify quality problems, recommend solutions-and verify implementation of solutions. If acceptable solutions cannot be reached, the designee has the responsibility and
[ authority to escalate these matters to the Executive Vice President &
Chief Operating Officer. The designee has the authority to initiate action to stop _
)
unsatisfactory work and control I further processing, delivery, or !
installation of nonconforming items or continuation of nonconforming services pending correction of the nonconforming condition.
~
L I i.
l
=
, r l
Page 11 of 14 Policy 1 Rev. 16 OQAMR16
.- - . . - . - - . _ - . . . -. - - _ - . . =
OPERATIONAL QUALITY ASSURM!CE MANUAL TITLE: ORGANIZATION
1.3 (Continued)
1.3.33 Director, Plant Projects & Support The Director, Plant Projects & Support reports to the Vice President, Operations GGNS and is responsible for the l collection, storage, and maintenance of quality assurance and vendor records and security program activities. He provides management direction to the Security Superintendent. He has oversight responsibility for the Change Review Board (CRB).
It is the responsibility' of the Director, Plant Projects &
Support to assure that these functions are performed in accordance with the requirements of the Operational Quality Assurance Program.
1.3.34 This section deleted in Revision 12.
1.3.35 This section deleted in Revision 13.
1.3.36 This section deleted in Revision 11.
1.3.37 This section deleted in Revision 13.
1.3.38 This section deleted in Revision 13.
1.3.39 This section deleted in Revision 13 1.3.40 This section deleted in Revision 12.
1.3.41 This section deleted in Revision 13.
1.3.42 Manager, Mechanical / Civil Engineering The Manager, Mechar.ical/ Civil Engineering, reports to the Director, Design Engineering - GGNS and is responsible for mechanical process designs / design modifications, HVAC designs / design modifications, piping, materials science and structural engineering as required for ductwork supports, pipe supports, miscellaneous structures, etc. In addition to classical design activities, the group provides consultation
, advice in all areas of mechanical engineering and engineering capabilities in the area of environmental monitoring, waste water engineering, seismic qualification of electrical equipment, and certain hydraulic engineering activities. He is also responsible for managing the design and implementation of various major design projects. It is the i responsibility of the Manager, Mechanical / Civil Engineering, '
to assure these functions are performed in accordance with j the requirements of the Operational Quality Assurance 1 Program.
l 1
1 l
4 r
l Page 12 of 14 Policy 1 Rev. 16 l OQAMR16 ,
r-
! OPERATIONAL QUALITY ASSURANCE MANUAL l
! TITLE: ORGANIZATION ~~ {
l i
1.3 (Continued)
l l
1.3.43 Manager, Electrical /I&C Engineering The Manager, Electrical /I&C Engineering, reports to the Director, Design Engineering - GGNS, and is responsible for j electrical designs / design modifications, electrical cable and i l equipment layout, electronic engineering, procurement I engineering, configuration management, drafting and i instrumentation and control / control logic engineering. In l
addition to classical design activities, the group provides consultation advice in all areas of electrical and electronic engineering. It is the responsibility of the Manager, Electrical /I&C Engineering, to assure these functions are performed in accordance with the requirements of the Operational Quality Assurance Program.
1.3.44 This section deleted in Revision 14.
1.3.45 This section deleted in Revision 13.
1.3.46 This section deleted in Revision 13.
1.3.47 Manager, safety Analysis The Manager, Safety Analysis, reports to the Director, Design Engineering - GGNS, and is responsible for design control of
- plant safety analysis and appropriate margins, coordination and performance of fuel reload safety analysis and associated activities, and development and applications of probabilistic risk assessments (PRAs). In addition to classical design activities, the group provides design and operational support in all areas of safety analysis. It is the responsibility of the Manager Safety Analysis, to assure those functions are performed in accordance with the requirements of the Operational Quality Assurance Program.
l-l Page 13 of 14 Policy 1 Rev. 16 OOAMR16
OFFS!TE PRESOENT & CHIEF EXECUTIVE OFFICER I
EXECtJTIVE p----- VICE PRESOENT
~~~~~~~~~-~~~~~~~~~~~~~~~l 1 CHIEF OPERATNG OFFICER
! I I l .._.-______L I I VCE PRESOENT. *! VICE PRESOen,
- VICE PRESOENT, l ENGNEERING l OPERATIONS GGNS OPERA M SUPPORT
== 1 q .._.._..J l -
, i
.i i c____L____ I l
m : weCTm. j
$ I o, RECTOR .
oEScN ERWG oRECTOR.
@m
",",'"^"
Y :
REVIEW l
I OuAuTY ASSURANCE
- N= F "I U"ogsg REGULA Y l COMMITTEE l_________
O l '- - -' - -- ~ ~- h -' - ~~ - ~~ - ~~ - '-' 9 .
- l t
M I DRECTOR, GCNERAL ;
A l MANAGER, PLANT MANAGER,
, j SAFETY ANALYSIS DIRECTOR- PROJECTS PLANT I NUCLEAR g SUPPORT !
-l ONSITE TRANWG OPERATIONS OFFSrTE MANAGER,
- ELECTRICAUl&C gg l M ENGNEERNG PERF N O l .
. & SYSTEM ecNeER= l M AGER.
0 ! MA EMERGENCY x : MECN NAGER, CAuCm PREPAREONESS l' N j ENGINEERING OFFS!TE CUTAGE l MANAGEMENT : ,
MANAGER, r ENGINEERING PROGRAMS l, .
a y
I
" LOCATED PHYSICALLY ONSITE BUT CONSIDERED pg [
,4 OFFSITE N THE PROGRAM' M_ANTENANCE S & .
- 1 m .
I
, MANAGER. MANAGER. i
- PLANNING & PLANT .
LEGEND N OPERATIONS
- _ _ _ _ CUALITY ASSURANCE POUCY MATTERS AND ESCALATION PATH '
- TECHNICAL & ADMINISTRATIVE AUTHORITY ,
- - - - - - - - OrrSmmNSnE eOUNomY PL SN j _ _
COORDNATION ANDTECHNCAL SUPPORTFOR . COMMITTEE MATERIALS, PURCHASING, AND CONTRACT ACTMTIES
OPERATIONAL QUALITX ASSURANCE MANUAL
! TITLE: QUALITY ASSURANCE PROGRAM i
l 2.0 QUALITY ASSURANCE PROGRAM 2.1 PURPOSE This policy describes the Operational Quality Assur ance Program for the l Grand Gulf Nuclear Station. l 2.2 SCOPE This policy describes the Operational Quality Assurance Program in terms of the objectives to be accomplished,' the requirements to be met, and the implementation and control mechanisms which have been established. The i total program is described throughout this manual. 1 1
2.3 APPLICABILITY The requirements of the Operational Quality pssurance Program apply to %
all individuals or organizations performing functions during the operational phase which affect the quality of safety-related structures, systems, components or services. .
Operational phase functions to which the program applies include: l designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, auditing, operating, l maintaining, repairing, refueling, and modifying. I 2.4 POLICIES, DIRECTIVES, GOALS AND OBJECTIVES Licensee quality assurance policies, directives, goals, and objectives are summarized in the statement that all licensee individuals and organizations who perform quality-related activities have responsibility to assure that the Grand Gulf Nuclear Station is designed, constructed and operated in a manner which protects public health and safety, and promotes reliable and efficient operation.
The Operational Quality Assurance Program is designed to provide the mechanism for assuring that these policies, goals, and objectives are achieved.
2.5 PROGRAM DESCRIPTION The Operational Quality Assurance Program, as described throughout this manual, delineates the measures that assure activities which affect the quality of safety-related structures, systems, components and services are performed in a controlled manner and are sufficiently documented to provide objective evidence of compliance with established requirements.
l The Operational Quality Assurance Program is documented by written
! policies, procedures, and instructions; and shall be carried out throughout the life of the plant in accordance with these policies, directives, procedures, and instructions. These documents convey the l
l Page 1 of 5 Policy 2 Rev. 16 OQAMR16 l
l OPERATICNAL QUALITY ASSURANCE MANUAL TITLE: QUALITY ASSURANCE PROGRAM
~~
2.5 (continued)
l
! licensee quality assurance philosophy and requirements to all levels of management and to all organizations and individuals involved with program implementation. The applicable policies of the Operational Quality l Assurance Manual are mandatory for safety-related activities and functions as described herein.
l The Operational Quality Assurance Program applies to all activities,
! including the use of expendable and consumable materials, affecting the safety-related functions of those structures, systems and components which prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. The program is designed to comply with the requirements of Appendix B to 10CFR50, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" and with the regulatory position in applicable NRC regulatory guides and ANSI standards as listed in Appendix A to this manual. '
A listing of structures / systems / components designated safety-related is included in the GGNS UFSAR. A Q-list which contains as a minimum those i structures / systems / components designated as safety-related in the UFSAR plus those selected non-safety related structures / systems / components to l which the quality assurance program applies is issued and maintained I current.
Design Engineering - GGNS is responsible for the development and maintenance of this Q-List in accordance with written procedures which i
delineate the contents of the Q-List. The procedures will assure that l structures / systems / components listed in the UFSAR are contained in the '
Q-list. The Q-List will be procedurally controlled. The positions !
authorized to approve changes to the Q-List are designated in Appendix B l l
of this manual.
The applicable requirements of the program are also imposed upon contractors, suppliers and consultants.
I Development, control, and use of computer programs for design control activities as described in Policy 3 for safety-related structures, systems and components will be conducted in accordance with the Operational Quality Assurance Program.
2.5.1 Operational Quality Assurance Manual The Operational Quality Assurance Manual consists of quality assurance policies, goals, and objectives and has been developed in accordance with applicable regulations, codes, and standards. It describes the Operational Quality Assurance Program and delineates the responsibilities and requirements imposed by the program for the performance of safety-related activities.
t Page 2 of 5 Policy 2 Rev. 16 OQAMR16 l
OPERATIONAL QUALITY ASSURANCE MANUAL T2TLE: QUALZTY ASSURANCE PROGRAM
~~
i 2.5.1 (Continued):
! The Director, Quality is responsible for maintaining the manual and controlling its distribution, including revisions thereto, in accordance with approved quality assurance procedures. Revisions to the nanual will be processed per i
2.5.2 Implementing Policies, Directives, Procedures and Inst ructions
, TheOperationalQualityhsauranceProgramisimplemented I
through the use of written, approved policies, directives, procedures and instructions generated by organizations, which are responsible for the performance of specific functions, as outlined in Appendix B of this manual.
The Quality Assurance Procedure Manual ~'contains the implementing procedures / instructions for the quality functions performed by Quality Programs. Quality assurance procedures / instructions provide measures to assure that quality-related activities are performed in a controlled manner and are documented to provide objective evidence of l
' compliance with program requirements. The Director, Quality is responsible for approving quality assurance procedures prior to implementation. Quality Programs supervisors are responsible for approving quality assurance instructions prior to implementation.
1 Quality-related functions performed by other organizations are controlled and documented in accordance with procedures prepared, approved and controlled by the organization performing the function. These procedures assure that the I functions are accomplished in a controlled manner, with specified equipment, under suitable environmental conditions, and that prerequisites have been satisfied prior to inspection or testing.
Appendix C to this manual provides a matrix of quality assurance procedures cross-referenced to the criteria of Appendix B to 10CFR50 which they implement.
2.5.3 Indoctrination and Training Indoctrination and training programs are established for both onsite and offsite personnel performing quality-affecting activities by the organizations responsible for the activities. These programs are implemented by appropriate training plans and procedures which assure that:
2.5.3.1 Personnel responsible for performing quality-affecting activities are instructed as to the 1 purpose, scope and implementation of manuals, I l procedures and instructions; l
l Page 3 of 5 Policy 2 Rev. 16 OQAMR16 l
[
OPERATIONAL QUALITY ASSURANCE MANUM T2TLE: QUEITY ASSURANCE PROGpaM
~~
2.5.3 (Continued)
2.5.3.2 Personnel performing quality-affecting activities are trained and qualified in the principles and techniques of the activity being performed; 2.5.3.3 Proficiency of personnel performing quality-affecting activities is maintained by retraining, reexamining or recertifying; 2.5.3.4 The scope, method and objective of the training are documented; 2.5.3.5 Records of training sessions are prepared and maintained, including identification of the content, the attendees and the date the training was conducted.
2.5.4 This section deleted in Revision 5.
2.5.5 Resolution of Disputes Disputes trising between licensee organizations on any quality assurance matter which cannot be resolved by management of the involved organizations will be referred to he appropriate level of executive management.
2.5.6 Quality Responsibilities Quality responsibilities for the implementation of major activities addressed in this manual are designated in the individual policies of this manual.
2.5.7 This section deleted in Revision ll.
2.5.8 Definitions The terms and phrases given in the " Definition" portions of the ANSI standards endorsed by this manual in Appendix A ,
shall apply as well as those given in pertinent sections of 1 the applicable portions of Title 10, Code of Federal ,
Regulations. As used throughout this Operational Quality l Assurance Manual and its implementing procedures, the j following words shall be construed to have the special {
definitions given: i 2.5.8.1 Shall - A requirement considered enforceable by the appropriate regulatory body.
Page 4 of 5 Policy 2 Rev. 16 l OQAMR16 l
l
)
. .. . . =-_ _ -. -
?
OPERATIONAL QUALITif ASSURANCE MANUAL TITLE: QUALITY ASSURANCE PROGRAM l 2.5.8 (Continued):
2.5.8.2 Should - A recommendation, but not an enforceable requirement. Managedent expects each employee using plant directives to carry out any "should" statement unless circumstances prevent or necessitate a deviation.
2.5.8.3 May - An option, neither a recommendation nor a requirement.
2.5.8.4 Must - A req irement normally established by licensee management or may be used to meet regulatory intent.
2.5.8.5 Additional items are defined in Appendix A (see under Regulatory Guide 1.74), individual quality assurance procedures and other quality documents.
2.5.8.6 Any words which have not been defined in 1 through 5 above or item 7 below shall be as defined in a contemporary collegiate dictionary by a well known publisher or authority.
2.5.8.7 Will - Is defined the same as shall.
2.5.9 Quality Assurance Position Statements Quality assurance position statenmnts are issued when consia-ered necessary by the Director, Quality, for use in interpretation of certain commitments in the Operational Quality Assurance Manual. These statements are not a part of the NRC accepted Operational Quality Assurance Manual, and are being included in the nanual binder only for the convenience of the users.
2.5.10 Resolution of Differences Every attempt has been made to include the pertinent require-ments from external documents, included in this program by the commitments in Appendix A, within these policies; no known conflicts exist between those commitments and these policies. Differences arising during future reviews or implementation of the program, must be brought to the attention of the Director, Quality who initiates changes to the commitments or the policies as necessary to resolve the differences. The provisions delineated in these policies shall take precedence over differing requirements given elsewhere until.the Director, Quality has evaluated the issue and determined which requirement (s) mus t be modified.
l l
s Page 5 of 5 Policy 2 Rev. 16 OQAMR16 l l
__ _ __ . . __ . _ _ ~ - _ _ _. - .__
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: DES 2GN CONTROL 3.0 DESIGN CONTROL 3.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to control design activities affecting safety-related structures, systems and components for the Grand Gulf Nuclear Station.
3.2 SCOPE This policy delineates responsibilit'ies and defines requirements for the development and implementation of design control measures to assure that design activities are carried out in a planned, controlled and orderly manner.
3.3 APPLICABILITY The requirements of this policy apply to all organizations performing design functions on safety-related structures, systems or components during the operational phase of nuclear power plant activities.
3.4 RESPONSIBILITY-3.4.1 Responsibility and authority for the control of design activities related to modifications or changes to plant safety-related structures, systems or components (including control of accident and transient analyses, but excluding nuclear fuel and nuclear core design see 3.4.5) during the operational phase are delegated to the Director, Design Engineering - GGNS. The General Manager, Plant Operations authorizes the design modification or change to be implemented by the Manager, Plant Maintenance and Modifications. The Director, Design Engineering - GGNS is responsible for assuring that procedures are developed and implemented to control the design activities of Design Engineering - GGNS in accordance with the requirements of this policy.
3.4.2 The reviewing of proposed 10CFR50.59 changes is completed as required by the UFSAR, Appendix 16B. This is described in appropriate procedures. When a proposed change is requested, the Director, Design Engi: ;g - GGNS initiates the design change (except in cases reio.ed to nuclear fuel and core de-sign) and assures submittal of the safety evaluation per 10CFR50.59, to the Plant Safety Review Committee (PSRC). The Vice President, Engineering, is responsible for initiating design changes related to nuclear fuel and core design and for coordinating with Design Engineering - GGNS in the development of required 10CFR50.59 evaluation (s) and submittal of the evaluation (s) to the PSRC. The Manager, Outage Management, Manager, Planning & Scheduling, and Manager, Plant Maintenance and Modifications, are responsible (except in cases related to nuclear fuel) for Page 1 of 5 Policy 3 Rev. 16 OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL
' TITLE: DESIGN CONTROL
'~
3.4.2 (Continued)
the coordination of scheduling and installation of Plant modifications, betterments and repairs once reviewed by the PSRC as required by the UFSAR, Appendix 16B.
l
[ The General Manager, Plant Operations is responsible for the '
l scheduling and installation of nuclear fuel and core related l design changes once reviewed by the PSRC as required by the UFSAR, Appendix 16B. The Secretary of the Safety Review Committee (SRC) assures the review of the safety evaluations by the SRC. The Director, Nuclear Safety & Regulatory Affairs is responsible for developing a summary of the safety
[. evaluation and submittal of the summary to the NRC, as l required by 10CFR50.59. l l
3.4.3 Organizations supplying material, equipment or services are l responsible for complying with the requirements of this policy to the extent specified in the applicable procurement documents, and for imposing them on their contractors and l suppliers, as applicable. They are also responsible for verifying, through surveillance or audits, that the !
requirements are being adequately implemented. i 1
3.4.4 The Vice President, Operations Support is delegated the responsibility, through the audit program described in Policy !
18 of this manual, to verify nuclear fuel and nuclear core (excluding accident and transient analyses) design documents l' comply with Operational Quality Assurance Program requirements; and for monitoring the implementation of nuclear fuel and nuclear core-related design control measures by offsite organizations, to verify conformance with l Operational Quality Assurance Program requirements. Those I design documents include the type design documents originated, reviewed and approved by the Vice President,
- Engineering. l 3.4.5 ' Responsibility and authority for control of design activities related to modification of or changes to nuclear fuel or nuclear core design (excluding control of accident and transient analysis activities - See 3.4.1) are delegated to the Vice President, Engineering. The Vice President, l
Engineering, is involved in: providing design inputs; providing interface control; reviewing all " accept-as-is" or
" repair" dispositions for nuclear fuel or core configuration nonconformances. In addition the Vice President, Engineering, may perform design verification of fuel related design activities. The Vice President, Engineering, is responsible for assuring that procedures are developed and l implemented for the above design activities in accordance with approved policies.
l l
l Page 2 of 5 Policy 3 Rev. 16
'OQAMR16 L
i OPERATZONAL QUALITY ASSURANCE MANUAL TITLE: DESIGN COMTROL
~~
3.4 (Continued)
3.4.6 Responsibility and authority for control of design activities (including accident and transient analyses, but excluding modification of or changes to nuclear fuel or nuclear core design) are delegated to the Director, Design Engineering -
GGNS. Generally, the Director, Design Engineering - GGNS is involved in: providing design inputs, providing interface controls controlling design output; and performing design verification. The Director, Design Engineering - GGNS is responsible for assuring .that procedures are developed and implemented for the above' design activities in accordance with the requirements of this policy and will provide or concur with all " accept-as-is" or " repair" dispositions (including accident and transient analyses, but excluding modification of or changes to nuclear fuel or nuclear core design) for nonconformances. The Director, Design Engineering - GGNS is responsible for reviewing GGNS design documents for compliance with the Operational Quality Assurance Program requirements and concurring with the same.
3.4.7 The Director, Quality, and the Vice President, Operations Support, have the responsibility for carrying out an audit program as described in Policy 18 of this manual, to verify conformance with the requirements of the Operational Quality Assurance Program, including the requirements of this policy.
3.5 REQUIREMENTS 3.5.1 Organizations having design responsibilities sha,'1 develop procedures, consistent with the scope of their responsibilities, to provide measures for the centrol of their design activities.
3.5.2 Procedures shall be developed to assure that applicable design inputs such as design bases, regulatory requirements, codes and standards are identified and documented, and are correctly translated into design output documents such as specifications, drawings, procedures and instructions.
3.5.3 Procedures shall provide for the identification and documentation of appropriate quality standards to be specified in the design documents. Deviations and changes from these quality standards shall be controlled.
3.5.4 Procedures shall include measures for: the control of design analyses such as reactor physics, s eis mic, stress, thermal, hydraulic, radiation, and accident analyses; compatibility of materials; accessibility for inservice inspection, maintenance, and repair.
Page 3 of 5 Policy 3 Rev. 16 OQAMR16
- - . . . ._. , ~ - _ - . . . - - . . - .
1 OPERATIONAL QUALITY ASSURANCE MANUAL i TITLE: DESIGN CONTROL
~~
3.5 (Continued)
3.5.5 Provisions shall be made in the procedures for the selection of suitable materials, parts, equipment, and processes which include the use of valid industry standards and specifications.
3.5.6 Procedures shall require that designs be reviewed to assure that: design characteristics can be controlled, inspected and tested, as appropriate; and, inspection and test criteria are identified. Such reviews7 shall be documented.
3.5.7 Materials, parts and equipment which are standard, commercial j (o f f-the-shelf) , or which have been previously approved for a )
different application shall be reviewed for suitability prior I to selection. Such reviews shall be documented.
3.5.8 Procedures shall provide for the control of design interfaces ,
for managing the flow of design information between I organizations. Systematic methods shall be established for communicating needed design information across the j interfaces, including changes to the design information as 1 the work progresses.
3.5.9 Procedures shall include requirements to verify that the design is adequate and that it meets the specified design inputs. The extent of the design verification required shall be a function of the importance to safety of the item, the complexity of the design, the degree of standardization, the state-of-the-art and the similarity with previously proven designs. In each case however, standardized or previously proven designs shall be reviewed for applicability prior to use.
3.5.10 Acceptable verification methods shall include, but not be limited to, design reviews, alternate calculations, or qualification testing. If a test program is used to verify the adequacy of a design, qualification testing of a prototype unit under the most adverse design conditions which are appropriate, shall be used.
i 3.5.11 Individuals or groups responsible for design reviews or other i verification activities shall be identified in the procedures and their authority and responsibility shall be defined and
! controlled. Design verification shall be performed by~any competent individuals or groups other than those who performed the original design but who may be from the same organization. This verification may be performed by the originator's supervisor provided the supervisor is the only technically qualified individual available and the appropriate clarification provisions listed in Appendix A to l
this manual are met.
l t
Page 4 of 5 Policy 3 Rev. 16 l OQAMR16
l OPERATIONAL QUALITlf ASSURANCE MANUAL TITLE: DESIGN CONTROL l 3.5 (Continued):
l 3.5.12 Design and specification changes, including those originating onsite, shall be subject to the same degree of control as the original design and approved by the original design l organization unless another qualified, responsible organization is specifically designated.
3.5.13 Errors and deficiencies in the design process, including computer programs, that could adversely affect safety-related structures, systems or components shall be documented, and corrective action taken t'o preclude repetition.
3.5.14 Proposed modifications or changes which involve an unreviewed safety question or a change to the technical specifications shall be handled in accordance with procedures which address the requirements of 10CFR50.59.
3.5.15 Design records shall'be maintained by the Director, Plant Projects & Support, in accordance with Policy 17 of this manual.
3.5.16 This section Deleted in Revision 4.
3.5.17 Plant procedures are provided to assure that responsible plant personnel are made aware of design changes / modifications which may directly affect the performance of their duties.
3.5.18 This section deleted in Revision 14.
l l
l Page 5 of 5 Policy 3 Rev. 16 OQAMR16
OPERAT80NAL QUALITY ASSURANCE MANUAL TITLE: PROCUREMENT DOCUMENT CONTROL
.~.
4.0 PROCUREMENT DOCUMENT CONTROL 4.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to control procurement documents for safety-related material, equipment and services for the Grand Gulf Nuclear Station.
4.2 SCOPE This policy delineates responsibilities and defines requirements for procurement document preparation, review, approve.1 and ciange ecntrol in order to assure that purchased safety-related items and services will conform to established, specified requirements.
4.3 APPLICABILITY The requirements of this policy apply to all procurement documents for safety-related material, equipment and services purchased by or for the licensee during the operational phase of nuclear power plant activities.
Services obtained from other EOI sites (shared services) are not considered procured services and therefore are not covered by this policy. These services are'obtained and controlled in accordance with documented agreements and applicable EOI Policies.
4.4 RESPONSIBILITY 4.4.1 All organizations participating in the preparation of procurement documents for safety-related items and services during the operational phase are responsible for developing their own procedures or using generic procedures. In either l case procurement document control procedures which address I the requirements of this policy, applicable to their scope of activities, shall be' implemented.
I 4.4.2 The Vice President, Operations Support is responsible for i procurement document control and the quality review of procurement documents. He is responsible for assuring procurement activities affecting GGNS are procedurally controlled in accordance with the requirements of this policy. The General Manager, Plant Operations, is responsible for assuring procurement activities performed by the Plant Staff are procedurally controlled in accordance with the requirements of this policy. This includes -
preparation, review, approval and issue of procurement documents.
4.4.3 The Director, Quality, is responsible for assuring implemen-tation of procurement document control measures and perform-ing quality reviews of onsite procedures prior to issuance, )
to verify conformance to the requirements of this policy.
4.4.4 This section is deleted in Revision 14. I 1
Page 1 of 4 Policy 4 Rev. 16 l
OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: PROCUREMENT DOCUMENT CONTROL
~~
4.4 (Continued)
4.4.5 organizations supplying material, equipment or services are responsible for complying with the applicable requirements of this policy, as specified in the appropriate procurement documents and for imposing them on their contractors and suppliers, as applicable. They are also responsible for verifying, through source verification activities, that the requirements are being adequately implemented.
4.4.6 This section deleted in Revision 12.
4.4.7 This section deleted in Revision 10.
4.4.8 The Director, Design Engineering - GGNS is responsible for assuring procurement activities performed by the Design Engineering - GGNS staff are procedurally controlled in accordance with the requirements of this policy. This includes preparation, review, approval, and issue of procurement documents.
4.4.9 This section deleted in Revision 11.
4.4.10 The Manager, Plant Maintenance and Modifications, is l responsible for assuring procurement activities to support the implementation of design changes and plant modifications are procedurally controlled in accordance with the requirements of this policy. This includes preparation, review, approval and issue of procurement documents.
4.4.11 This section deleted in Revision 13.
4.5 REQUIREMENTS 4.5.1 Procedures shall be established by the responsible organizations to clearly delineate the sequence of actions to be accomplished to control the preparation, review, approval and issuance of procurement documents for safety-related items and services.
4.5.2 The procedures shall assure that procurement documents issued at all levels of procurement include provisions for the following, as applicable:
4.5.2.1 A statement of the scope of work to be performed by the contractor or supplier; 4.5.2.2 Identification of the design basis technical requirements by reference to specific drawings, specifications, codes, regulations, industrial standards or other documentation, including revisions thereto, that describe the itens or services to be furnished; Page 2 of 4 Policy 4 Rev. 16 OQAMR16 t .. . . . . . . .
. - - - _ ~ ~ - . ~ _ - . _ - . _ . ~ . . - . . . . . . _ . . . . - - . . - - . . _ _ . - _ - ~ - -
i OPERATZONAL QUALITY ASSURANCE MANUAL TITLE - PROCUREMENT DOCUMENT CONTROL
~~
4.5.2 (Continued) :
4.5.2.3 Identification of test, inspection and acceptance ,
requirements, and any special instructions and i requirements for such activities as design, fabrication, identification, cleaning, erecting, packaging, handling, shipping and extended '
storage; 4.5.2.4 Identification of the quality assurance program requirements;which must be complied with by the ,
contractor or supplier; 4.5.2.5 Stipulation that the provisions of 10CFR21 apply; I 4.5.2.6 Identification of the documentation, such as ,
drawings, specifications, procedures, fabrication and inspections plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test results to be prepared and maintained by the supplier or contractor and requirements for submittal to the licensee for review and approval; -
4.5.2.7 Identification of those records-to be retained, controlled and maintained by the supplier or :
. contractor and those to be delivered to licensee prior to use or installation of the procured ,
item; i
4.5.2.8 The licensee's right of access to the supplier's facilities and records for source quality verification, inspection and audits, as deemed necessary; 4.5.2.9 Extension of applicable requirements to lower tier subcontractors and suppliers, including the licensee's right of access to facilities and ;
records; I 4.5.2.10 Subject to the clarification of ANSI N45.2.13, Section 8.2, given in Appendix A of this program, reporting and approving the " Accept-as-is" or
" Repair" dispositions of nonconformances; 4.5.2.11 The licensee's right to hold shipment if procurement document requirements, including those for doewmentation, have not been fulfilled.
L i
l l
I Page 3 of 4 Policy 4 Rev. 16 OQAMR16 I
r OPERATIONAL GUALITY ASSURANCE MANUAL TITLE: PROCUREMENT DOCUMENT CONTROL i
- i
~~
L
'4.5 (Continued):
4.5.3 The procedures shall assure that procurement documents are subjected to technical and quality review by qualified personnel and are approved by designated individuals prior to
- i. issuance. The review and approval shall be documented and available for verification.
4.5.4 Review and concurrence with the. adequacy of quality requirements shall include verification that the requirements are correctly stated, inspectable and controllable; that there are adequate acceptance and rejection criteria; and '
that the procurement documents have been prepared, reviewed and approved in accordance with the requirements of this ,
policy. '
4.5.5 Changes or' revisions to procurement documents shall be i subjected to an equivalent review and approval as the original documents, and such review and approval shall be documented. Exceptions to this include changes in quantity, ,
estimated price, . cost codes, taxes, format or editorial changes that do not affect the quality of the item or '
service.
4.5.6 Procurement documents for spare or. replacement parts for safety-related structures or systems shall be subject to controls at least equivalent to those required for purchase of original equipment, or those specified by a properly reviewed and approved revision to the original requirements.
i 1
i 1 1
i l
i i
l l
i i
Page.4 of 4 Policy.4 Rev. 16 00AMR16-
OPERATZONAL QUALITY ASSURANCE MAMUAL TITLE: INSTRUCTIONS, PROCEDURES, AND DRAWINGS 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS 5.1 PUPPOSE This policy describes the Operational Quality Assurance Program measures to assure that all activities affecting the quality or safety of the Grand Gulf Nuclear Station are prescribed and accomplished in accordance with documented instructions, procedures, drawings or other documents appropriate to the circumstances.
5.2 SCOPE This policy delineates responsibilities and defines requirements for the development and implementation of measures designed to assure that safety-related activities are prescribed and accomplished in accordance with documented instructions, procedures or drawings.
5.3 APPLICABILITY The requirements of this policy apply to all individuals or organizations performing activities which affect the quality of safety-related items during the operational phase of nuclear power plant activities.
5.4 RESPONSIBILITY 5.4.1 All organizations performing activities during the operational phase which affect the quality of safety-related structures, systems and components are responsible for performing these activities in accordance with directives, documented instructions, procedures or drawings. It is the responsibility of the management of these organizations to assure the development, review, approval and control of directives, instructions, procedures and drawings necessary to control their safety-related activities in accordance with the requirements of this manual.
It is the responsibility of the Vice President, Engineering; the Vice President, Operations GGNS, and the Vice President, Operations Support, to ensure that those instructions, policies, procedures and drawings that cross internal organizational lines integrate and function in accordance with the above.
5.4.2 This section deleted in Revision 3. _
5.4.3 During the operational phase, the General Manager, Plant Operations is responsible for assuring that adequate inspection plans; test calibration, special process, maintenance, test and repair procedures; drawings, specifications and other safety-related documents and revisions there to are used.
l Page 1 of 3 Policy 5 Rev. 16 OQAMR16 r . ... . . . .. .
OPERATIONAL QUALITY ASSURANCE MANUAL T2TLE: INSTRUCTZOMS, PROCEDURES, AND DRAWZNGS
5.4.3 (Continued)
During the implementation of design changes and plant modifications, the Manager, Plant Maintenance and Modifications, is responsible for assuring that inspection plans; modification procedures; drawings, specifications and other safety-related documents and appropriate revisions thereto are used.
The Director, Quality is responsible for performing the quality review of procedures / instructions to verify that the necessary quality assurance requirements are included.
Quality Programs is responsible for determining the need for inspection requirements in work documents. Documents which contain administrative controls which specify quality assurance requirements will also be reviewed by Quality Programs. Lower tier documents (section procedures /
instructions) may be reviewed by individuals (other than the preparer) of the organization preparing the documents if such individuals have been indoctrinated in the Operational Quality Assurance Program. The Director, Quality is responsible for indoctrination and certification of these 1 individuals.
)
l 5.4.4 The Director, Quality, and the Vice President, Operations l Support, are responsible for reviewing and/or approving instructions, procedures or drawings as indicated in Appendix l B of this manual. !
l 5.5 REQUIREMENTS '
l
! 5.5.1 Written instructions, procedures, drawings, or other documents appropriate to the circumstances shall be used to provide measures for complying with the requirements of the j Operational Quality Assurance Program.
5.5.2 Directions commensurate with the nature of the activity shall j be prescribed in instructions, procedures and/or drawings for i i the performance of activities affecting quality. The l activities shall then be performed in accordance with the instructions, procedures and/or drawings.
5.5.3 Instructions, procedures or drawings shall include ;
- quantitative and/or qualitative acceptance criteria for !
! verifying that the activities have been satisfactorily l accomplished.
l 5.5.4 The responsible organizations shall establish procedures which define responsibilities and clearly delineate the sequence of actions to be accomplished in the preparation, ,
review, approval and control of instructions, procedures, or drawings, and changes thereto.
5.5.5 Safety-related administrative procedures must reference documents used in their preparation.
5.5 (Continued)
Page 2 of 3 Policy 5 Rev. 16 OQAMR16
. ..- ~ . ~ _ ~ . . - - .. . - - - . - - - - . - -. ~
l OPERATZONAL QUALITif ASSURAMCE MAMUAL TITLE: INSTRUCTIONS, PROCEDURES, AND DRAWINGS i
l
5.5 (Continued)
5.5.6 When the NRC accepts changes to a policy or an appendix which result in more restrictive requirements, affected implementing procedures must be issued or revised within 120 days. If procedures cannot be revised or issued within 120 days, the manager of the affected organization (s) must approve a schedule detailing when the required changes will be accomplished. If the approved changes are less restrictive, the more restrictive requirements must be complied with until the o'id procedures are revised or new procedures are issued. When changes to procedures (more restrictive) are required by changes to NRC regulations or by bulletins or orders, the required procedures shall be changed within 120 days or as stipulated in the licensee's response to the bulletin or order or as set forth in the regulation.
The more restrictive time frame shall be met.
I i
l i
l l
l l Page 3 of 3 Policy 5 Rev. 16 i
OQAMR16 l
OPERATIONAL QUALTTY ASSURANCE MANUAL TITLE: DOCUMENT CONTROL 6.0 DOCUMENT CONTROL 6.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to control safety-related documents for the Grand Gulf Nuclear Station.
6.2 SCOPE This policy delineates responsibilities and defines requirements for the review, approval, issuance and control of documents and changes or revisions thereto, which prescribe all activities affecting quality or safety.
6.3 APPLICABILITY The requirements of this policy apply to all individuals or organizations performing functions which affect safety-related structures, systems or components during the operational phase of nuclear power plant activities.
6.4 RESPONSIBILITY 6.4.1 Responsibility and authority for the control of safety-related documents during the operational phase are delegated to the individuals / organizations specified in Appendix B of this manual. They are responsible for developing and implementing procedures to control the review, approval and issue of doewments in accordance with the requirements.of this policy.
6.4.2 Organizations supplying material, equipment or services are responsible for complying with the applicable requirements of this policy as specified in the appropriate procurement documents, and for imposing them on their contractors and suppliers, as applicable. They are also responsible for assuring, through surveillance or audits, that the requirements are being adequately implemented.
6.4.3 This section deleted in Revision 4.
6.4.4 The Director, Quality, and the Vice President, Operations Support, are responsible for monitoring document control activities.
6.5 REQUIREMENTS 6.5.1 Procedures shall be established and implemented by the responsible organizations to provide for the control of documents, including changes thereto, which prescribe all activities affecting quality or safety. These procedures are identified in Appendix B to this manual.
i Page 1 of 4 Policy 6 Rev. 16 OQAMR16 l
t
I f
OPERATIONAL GUALITY ASSURANCE MANUAL i l T8TLE: (DOCUMENT CONTROL '
i
- 6.5 (Continued): '
6.5.2- The pro'cedures shall identify the documents to be controlled, As a minimum, they.shall include: f' Design Specifications '
\
Design, Manufacturing, Construction and Installation Drawings. [
',; ' Procurement Documents <
Quality Assurance Manuals, Procedures and Instructions f'
Operating Procedures '
Operating and Special. Orders '
' Maintenance and Modification Procedures !
t Manufacturing, Inspection and Test Procedures I
! Equipment and Material Control Procedures l
Refueling Procedures Updated Final Safety Analysis Report' l
l Design Change Requests / Packages Design Change Notices ;
Quality Deficiency Documents L Q-List '
i 6.5.3- The procedures shall specify the individuals or organizations j responsible for the preparation, review, approval, issuance ;
l 'and control of the' documents, and revisions thereto. i V ;
6.5.4 Review of documents for adequacy shall be performed by .
knowledgeable personnel other than the originator. Reviewers l shall have access to pertinent background information and l shall have adequate understanding of requirements and intent f l- of the document. i 1
6.5.5 Documents shall be approved for issue by authorized personnel l l- prior to release and shall be distributed in accordance with~
- ' current, documented distribution lists.
i r
i
- I i.
l i
- Page 2 of 4 Policy 6 Rev. 16 l t
." OQAMR16
- OPERATIONAL QUALITY ASSURANCE MANUAL
! TITLE: DOCUMENT COMTROL
6.5 (Continued)
i 6.5.6 Master lists or their equivalents shall be established and maintained to identify the current status of instructions, procedures, specifications, drawings and procurement documents. The lists shall be available to responsible l personnel to preclude the use of superseded documents.
6.5.7 Documents required to perform a specific activity shall be available at the location where the activity is to be performed prior to commencement of the activity. Cancelled, deactivated or superseded documents shall be controlled to prevent their inadvertent use.
6.5.8 Unless delegated to other appropriately qualified organizations, changes to documents shall be reviewed and
- approved by the same organizations that performed the original review and approval.
6.5.8.1 Changes shall be included in the documents (i.e.,
procedures or instructions) prior to implementation of the change, except in those cases where adequate procedural controls allow implementation of changes prior to revision of the original document. These changes, if considered permanent, shall be incorporated into the original document in a timely manner as defined by Quality Programs.
6.5.8.2 This section deleted in Revision 11.
! 6.5.8.3 This section deleted in Revision 11.
- 6.5.8.4 This section deleted in Revision 11.
6.5.9 This section deleted in Revision 11.
6.5.10 Sub ,t to the clarification of ANSI N18.7-1976/ANS 3.2, Section 5.2.15 given in Appendix A of this program, plant procedures (as defined in the UFSAR, Appendix 16B, Section 7.6.1) shall be reviewed by an individual knowledgeable in the area affected upon identification of new or revised
- source material potentially affecting the intent of t
procedures or prior to use if the procedure / instruction is i not used routinely to determine if changes are necessary or
[ desirable. A biennial audit by the Quality Prograns t
Department will be performed to verify the effectiveness of controls used to maintain procedures current. A revision of the procedure constitutes a procedure review.
l l
i
[ Page 3 of 4 Policy 6 Rev. 16 l OQAMR16 I
f i
OPERATIONAL QUALITY ASSURANCE MANUAL-TITLE: DOCUMENT CONTROL
6.5 (Continued)
6.5.11 Following any modification to a plant system and prior to initiation of any activity affected by the modification, the applicable procedures shall be reviewed to determine if changes are required.
6.5.12 A documented review of applicable procedures shall be performed following an accident, an unexpected transient, significant operator error, or equipment malfunction which results in a reportable event, to determine if changes are required to prevent recurrence.
6.5.13 Review and approval of documents, and changes thereto, shall be documented to the extent necessary to provide evidence of compliance with the requirements of this policy. I l
l l
Page 4 of 4 Policy 6 Rev. 16 OQAMR16
- . ~ + - . . . . . . .- - - - - . . , . ~ . - ~ - - . - . - . . - . . . - - . ~ . - - _ . - . .
6 l
OPERATIONAL QUALITY ASSURANCE MANUAL
- TITLE: _ CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l.
7.0 . CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 7.l ~ ~ PURPOSE
'This policy describes the Operational Quality Assurance Program measures to control the procurer. ant of safety-related material, equipment and "
services for the Gran'l Gulf Nuclear Station. '
.7.2 SCOPE This policy delineates responsibili$ies and defines requirements for the
, control of activities performed during the procurement of safety-related.
items and services in order to' assure that such items and services -
conform to the procurement documents.
-7.3' APPLICABILITY The requirements of this policy apply to all safety-related material, l
. equipment and services procured for the operational phase of nuclear '
l-power plant activities, and to all individuals or organizations .
participating in the procurement of such items or services. Services '
obtained from other EOI sites (shared services) are not considered procured services and therefore are not covered by this policy. These services are obtained and controlled in accordance with documented i
-agreements and applicable EOI Policies. '
7.4 RESPONSIBILITY l 7.4.1 Responsibility and authority for controlling the procurement !
of safety-related material, equipment and-services during the ,
operational phase are delegated to; the Vice President, Operations Support; the Director, Nuclear Safety & Regulatory Affairs; the Director, Quality; the Director, Design Engineering - GGNS; the General Manager, Plant Operations ;
(for post modification, startup testing and operations); and the Director, Plant Projects & Support. It is the responsibility of these individuals to assure that the. i requirements of this policy, which are applicable to their scope of activities, are implemented in accordance with written approved procedures. These activities include, as appropriate: source evaluation and selection; evaluation of objective evidence of quality furnished by the suppliers source verification; examination of items upon delivery.
7.4.2 organizations supplying safety-related material, equip' ment and services are responsible for complying with the
, applicable requirements of this policy, as stipulated in the l procurement documents, and for imposing them upon their contractors and suppliers as applicable.. They are also responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented.
.7.4.3 This section deleted in Revision 14.
4 1
- 1 i-
-Page 1 of 5 Policy 7 Rev. 16 OQAMR16 l
i
! 1 l' i
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES
7.4 (Continued)
7.4.4 The Director, Quality is responsible for assuring the implementation of Operational Quality Assurance Program requirements relative to procurement activities through an audit program, as described in Policy 18 of this manual, to verify conformance with Operational Quality Assurance Program requirements, including the requirements of this policy.
7.4.5 The Vice President, Operations Support, is responsible for assuring the implementation of the Operational Quality
~
Assurance Program requirements relative to procurement )
activities, including: receipt inspection, as described in l Policy 10 of this manual, and the quality evaluation of suppliers and source verification, as described in Policy 18 of this manual, to verify conformance with the operational )
Quality Assurance Program requirements, including the requirements of this policy.
7.5 REQUIREMENTS l
7.5.1 Measures shall be established, implemented and documented by the appropriate organizations, consistent with their scope of responsibilities, to assure that purchased material, equipment and services, whether procured directly or through contractors, conform to the procurement documents. These measures shall include provisions, as appropriate, for source evaluation and selection, objective evidence of quality furnished by the supplier, inspection, source verification, and/or examination of items upon delivery.
7.5.2 Procedures shall be established to provide for the selection of suppliers based on one or more of the following:
1.5.2.1 An evaluation of the supplier's quality assurance program / manual / procedures, as appropriate.
7.5.2.2 Review and evaluaticn of historical quality performance data; 7.5.2 3 Source qualification programs; 7.5.2.4 Source quality surveys; 7.5.2.5 Through the use of Nuclear Procurement Issues Committee (NUPIC) audits and other utility audits indicating a program meeting appropriate requirements. A copy of the qualifying audit report shall be obtained and reviewed for adequacy and applicability prior to selection.
l l
l l-Page 2 of 5 Policy 7 Rev. 16
- OQAMR16 l
l
,. . . , - - - - - - - .- - ._ - - - ~ .- - . . - . . - . - - ~ _ . - . . -
OPERATIONAL QUALITY ASSUPANCE MANUAL TITLE: CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES
~~
7.5.2 .(Continued):
7.5.2.6 Through the NRC's " Licensee Contractor and Vendor Inspectica Status Report" (white book) for i contractors confirming quality assurance program )
implementation;
)
7.5.2.7 Through documented information received from others (architect-engineer, NSSS supplier, other l utilities, ASME, etc.) indicating a program l meeting appropriate quality assurance program 1 requirements.
The procedures shall specify the organizations responsible for performing technical and quality evaluations, the methods of evaluation and the criteria for supplier acceptance.
7.5.3 Evaluation and selection of the supplier shall be performed in.accordance with written procedures by qualified quality ;
assurance and technical personnel prior to or concurrent with award of the procurement document.
Items which have been manufactured or are to be manufactured i prior to this concurrence with the contractor or supplier ;
quality assurance program will be acceptable, but shall not ;
be relied upon to fulfill any safety-related function until l after the item is shown to meet procurement requirements '
(including quality assurance program).
7.5.4 Results of supplier evaluations shall be documented and retained on file. Any deficiency identified during a supplier evaluation shall be resolved early enough in the procurecent cycle to prevent -the deficiency from adversely affecting the quality of the purchased product or service.
7.5.5 Procedures shall be established to provide for evaluation and verification activities such as source verifications, as necessary, to assure the quality of the item and to verify supplier conformance to procurement document requirements.
7.5.6 Inspection procedures shall specify the characteristics or processes to be witnessed, inspected or verified, and accepted. The method of verification and the extent of documentation required; and those responsible for implementing the inspection. Quality procedures shall .
specify the characteristics or processes witnessed, observed or verified, including the method of verification and the
, extent of documentation required. Audits shall be performed L in accordance with procedures which implement the l requirements of Policy 18 of this manual.
i l
- a.
Page 3 of 5 Policy 7 Rev. 16 OQAMR16
. .. ~ , - . - .. .- -, -- . , - -.- ~__...- - .~.- - - - . _ -- _ - - .. - . _ _ .-
' OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES
~~
l
7.5 (Continued)
l
- 7. 5.7 - The extent and frequency of evaluation and verification activities of approved supplier's performance is continuously evaluated. The effectiveness of a Supplier's Quality l Assurance program is evaluated with consideration given to pertinent factors'such as the importance, quantity, quality, and complexity of the product (s)/ service (s) being procured.
The methods employed by Entergy Operations, inc. for providing continuous evaluation of suppliers include:
evaluation feedback fromLNRC, NUPIC, and/or ASME audit / surveillance results; site feedback regarding a supplier's product (s) / service (s) ; and evaluation of industry operating experiences. The processes for performing these activities are described in implementing procedures."
7.5.8 Receipt inspection of supplier-furnished items shall be
-procedurally controlled to assure: that the items are properly identified and correspond with he identification on the receiving documentation; that the items and acceptance records are inspected and judged acceptable in accordance with predetermined instructions prior to installation or use; that inspection records or certificates of conformance are available at GGNS prior to installation or use of the item; and, that items accepted and released are identified as to their inspection status prior to storage or use.
Procedure controls will cover the conditional release I process, and will assure that the applicable procedural and administrative aspects of this section(7.5.8) and Sections 8.5.8, 14.5.5 and 15.5.5 of the Operational Quality Assurance Manual are fulfilled.
7.5.9 Records required to be furnished by the supplier shall be specified in the procurement documents, as stipulated in Policy 4 of this manual. These records shall be reviewed and accepted by personnel specifically designated to perform this activity. These personnel will be designated in accordance with applicable procedures. Other licensee organizations may be used when their areas of expertise provide an adequate basis for such a review. (e.g., the nuclear fuels organization could review records from nuclear fuel l suppliers.) l 7.5.10 The records shall include, as a minimum, documentation'that identifies the purchased item and the specific procurement requirements (e.g., codes, standards, specifications) met; ,
and documentation which identifies procurement requirements i which have not been met. Subject to the clarification of ANSI N45.2.13, Section 8.2, given in Appendix A of this manual, such documentation shall include a description of those nonconformances dispositioned " accept-as-is" or
" repair".
l
'7.5.11 Where supplier certificates of conformance are used to identify the requirements met by the item, the certificates j of conformance shall be periodically evaluated by audits, ,
3 independent inspections or tests to assure that they are l valid.
l l Page 4 of 5 Policy 7 Rev. 16 OQAMR16 i
e______. . _ _ _ . _ _ . _ _ -_. . _ . . _ _ .
_ . .. _ _.. _- _ _ . _ _ . . . ._.__._,_....____..m._,
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: CONTROL OF PURCHASED MATERTAL, EQUIPMENT AND SERVICES
~
- 7. 5 '; (Continued) ':
.7.5.12 Spare or replacement parts for safety-related systems or components shall be procured, fabricated and controlled in accordance with present quality assurance programmatic controls and technical requirements at least equivalent to those used for the original item, or those specified by a properly reviewed and approved revision to the original requirements.
-7.5.13 When a supplier is removed from the Qualified Suppliers List,.
procedures shall assure.that any outstanding purchase ' orders for that. supplier are reviewed, and appropriate action taken to assure that materials subsequently received from that supplier are handled and dispositioned as nonconformances.
7.5.14 This section deleted-in Revision 6. i l
l l l
l l
1 l
- i i
I i, ,
i
-Page 5 of 5 Policy 7 Rev. 16 OQAMR16 )
t
. OPEPATIONE QUALITY ASSURANCE MANUAL -
. TITLE: . IDENTZFICATION, AND CONTROL OF. Mf(TERIALS, PARTS AND COMPONENTS l 8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS l ,
8.l' , PURPOSE l This policy describes the Oparational Quality Assurance Program measures ;
l to provide for the identification and control of safety-related material, i parts and components for the1 Grand Gulf Nuclear Station.
I.
l 8.2 SCOPE j
This policy delineates responsibilities and defines requirements for the identification and control of safety-related items in order to assure 1 l that only correct and accepted items are used or installed.
I 8.3 . APPLICABILITY The requirements of this policy apply to all individuals or organizations participating in the procurement, fabrication, receipt, storage, installation, operation, modification or repair of safety-related items during the operational phase of nuclear power plant activities.
l l 8.4 RESPONSIBILITY j
' I
.8.4.1 Responsibility and authority for the identification, control and testing of materials, parts and components during the operational phase are delegated to the General Manager, Plant Operations. He is responsible for assuring that procedures l _are established to address the applicable requirements of this policy, and that identification and control of .
safety-related items is maintained in accordance with the l procedures from procurement of the item through fabrication, storage, installation and.use.
8.4.2 Organizations supplying safety-related material, equipment
, and services are-responsible for complying with the
! applicable requirements of this policy, as stipulated in the procurement documents, and for imposing them on their contractors and suppliers as applicable. They are also responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented, i
8.4.3 The Director, Quality is responsible for assuring implementation of identification and control requirements for items at GGNS by quality inspections. He is responsible ~ for ensuring the review of procedures and work documents to the extent necessary to verify conformance to the applicable requirements of this policy.
8 .' 4 . 4 This section deleted in Revision 12.
8.4.5 The Vice President, Operations Support, is responsible for the implementation of identification and control requirements
,- for items at GGNS by receipt and warehouse inspections.
t 4
1 Page 1 of 2 Policy 8 Rev. 16
- OQAMR16-I-
I.
I f
l OPEPATIONAL QUALITY ASSURANCE MANUAL TITLE: IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS
~~
8.5 REQUIREMENTS 8.5.1 Procedures shall be established and implemented to provide for the identification and control of safety-related materials, parts and components, including partially fabricated subassemblies, in order to assure that only correct and accepted items are used and installed.
l 8.5.2 The procedures shall be developed by the appropriate organizations to cover the various stages from procurement of the item through fabrication, receipt, storage, installation, use, modification or repair.
l 9.5.3 The procedures shall provide assurance that a unique l identification of items is maintained, such as by part number, serial number, heat number, drawing identification number or other appropriate means.
'* The procedures shall assure that identification is maintained either on the item or on records traceable to the item.
Physical identification, such as by marking or tagging, shall be used to the maximum extent practical.
8.5.5 When specified by codes, standards, procurement documents, or other requirements; identification shall be such that itens are traceable to appropriate documentation (e.g.,
specifications, drawings, purchase orders, manufacturing and inspection documents, nonconformance reports, physical or l chemical mill test reports).
8.5.6 Where identification marking is employed, the marking shall be clear, unambiguous and indelible, and shall be applied in such a manner as not to affect the fit, function or quality of the itet.
8.5.7 Markings shall be transferred to each part of an item, if i subdivided, and shall not be obliterated or hidden by surface treatment or coatings unless other means of identification I
are substituted.
8.5.8 Procedures shall provide for the verification and documentation of correct identification of itena prior to release for fabrication, assembling, shipping, storage or installation. Items may be conditionally released under adequate procedural controls. These controls shall assure that the system, subsystem, or component that receives such itene is considered inoperable, no reliance shall be placed l on such system, subsystem, or component for fulfilling their l intended safety function. The Vice President, Operations Support, and the Director, Quality are responsible for the review of and concurrence with conditional releases.
Applicable procedural and administrative aspects of this section (8.5.8) and Sections 7.5.8, 14.5.5 and 15.5.5 of the i Operational Quality Assurance Manual shall be fulfilled.
I Page 2 of 2 Policy 8 Rev. 16 OQAMR16
OPERATIONAL QUA1,ITY ASSURANCE MANUAL T2TLE: CONTROL OF SPECIAL PROCESSES 9.0 CONTROL OF SPECIAL PROCESSES 9.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to provide for the control of safety-related special processes for the Grand Gulf Nuclear Station.
9.2 SCOPE This policy delineates responsibilities and defines requirements for the control of special processes including, but not limited to, cleaning, heat treating, welding, nondestructive examination or unique fabricating or testing processes which require interim in-process controls.
9.3 APPLICABILITY The requirements of this policy apply to all individuals or organizations performing special processes during the operational phase of nuclear power plant activities under this Operational Quality Assurance Program.
9.4 RESPONSIBILITY 9.4.1 Responsibility and authority for the control of special processes, except nondestructive examination, at GGNS during the operational phase are delegated to the Director, Design Engineering-GGNS. During the implementation of design changes and plant modifications, the Manager, Plant l Maintenance and Modification is responsible for ensuring that
! special processes are controlled in accordance with procedures developed by the Director, Design Engineering- ,
GGNS. Responsibility and authority for the control of 1 nondestructive examination are delegated to the Director, Quality. They are responsible for assuring that special processes are performed in accordance with procedures and instructions which implement the requirements of this policy.
They are also responsible for assuring that contractors who are delegated responsibilities for the onsite performance of special processes, impose the applicable requirements of this
! policy on their internal operations and on their contractors and suppliers.
! 9.4.2 Offsite organizations responsible for the performance of I special processes shall be subject to the applicable ~
requirements of this policy as specified in the appropriate j procurement documents. Individuals or organizations
! responsible for the preparation of procurement documents i shall assure that the applicable requirements of this policy
- are included, as stipulated in Policy 4 of this manual.
1 i
Page 1 of 3 Policy 9 Rev. 16 OQAMR16
OPERAT80NAL QUALITY ASSURANCE MANUAL TITLE: CONTROL OF SPECTRL PROCESSES )
~~
9.4 (Continued)
9.4.3 The Director, Quality, is responsible for reviewing plant administrative procedures, design engineering procedures, and j work documents controlling special processes. Prior to use, l the Director, Quality is also responsible for reviewing and I approving any nondestructive examination procedure for on-site activities, including the procedures of offsite organizations. The Director, Quality is also responsible for verifying, to the extent necessary, conformance to the requirements of this policy through monitoring, audit, or inspection of special process activities, including nondestructive examinations.
9.4.4 The Director, Quality, and the Vice President, Operations Support, have the responsibility for monitoring the onsite special process control measures of offsite organizations.
9.4.5 The Director, Design Engineering - GGNS has the l responsibility for assuring that special process standards and specifications are established to address the applicable requirements of this policy. With the exception of procedures for on-site performance of nondestructive
' examination, the Director is also responsible for reviewing and approving all contractor special process standards prior to use at GGNS.
9.4.6 The Vice President, Engineering has responsibility for l maintaining overall administrative, programmatic, and operational control (excluding implementation) of the Entergy Operations, Inc., Central Welding Program (Welding, Heat Treatment and NDE).
l 9.5 REQUIREMENTS 9.5.1 Procedures shall be developed and implemented by the responsib.le organizations to assure the control of special processes including, but not limited to, chemical cleaning, heat treating, welding and nondestructive examination.
9.5.2 Special processes shall be accomplished under controlled conditions in accordance with applicable codes, standards, specifications or other special requirements.
9.5.3 Special processes shall be performed by personnel qualified in accordance with applicable codes, standards, specifications, or other special requirements.
9.5.4 Equipment and procedures used in the performance of special processes shall be qualified in accordance with applicable l codes, standards, specifications or other special requirements.
9.5.5 Qualification records of personnel, equipment and procedures associated with special processes shall be established, maintained and kept current.
l t
Page 2 of 3 Policy 9 Rev. 16
( OQAMR16 l
- OPERATIONAL QUALITY ASSURANCE MANUAL.
TITLE: CONTROL OF _SPECIAL PROCESSES
~~ '
- 9.5 (Continued)':
9.5;6 For special processes not covered by existing codes or standards, or where item quality requirements exceed the requirements of existing. codes or standards, the necessary qualifications of personnel, procedures and equipment shall be defined and documented..
J i-I l-i.
l Page'3 of 3 ' Policy 9 Kev. 16
[: OQAMR16 l'
l.
s
n-OPERATIONAL QUALITY ASSURANCE MANUAL i TITLE: INSPECTION
'10.0 ' INSPECTION I .10.1 - PURPOSE - .
l This policy describes the Operational Quality Assurance Program measures to provide for.the inspection of activities affecting the safety of the Grand Gulf-Nuclear Station.
-10.2 SCOPE This policy delineates responsibilities and defines requirements for the
_ development and. implementation of a program for the inspection of
-activities affecting safety in order to verify conformance to the documented instructions, procedures and drawings.for accomplishing the activity.
10.3 APPLICABILITY The-requirements of this policy apply to all inspections performed on safety-related structures, systems or components during the' operational phase of nuclear power plant activities.
10.4 RESPONSIBILITY 10.4.1 Overall responsibility and authority for establishing and
. implementing an inspection program at GGNS during the operational phase are delegated to the Vice President, Operations Support, the Director, Quality and the General-Manager, Plant Operations. During the implementation of design changes and plant modifications, the Manager, Plant Maintenance and Modifications, in conjunction with the Director, Quality is responsible for these activities. The l Vice President, Operations Support and Director, Quality are l responsible for assuring that procedures / instructions l developed for the performance of work operations include appropriate inspection requirements-and for assuring that inspections and examinations are performed and documented ,
where necessary to assure quality. The General Manager, I Plant Operations and the Manager, Plant Maintenance and i Modifications (for implementation of design changes and plant modifications) are responsible for assuring that measurements and tests of materials, products or activities are performed and documented for each work operation where necessary to i assure quality. _
l l
10.4.2 The Director, Quality is responsible for assuring that the j L onsite inspection program (except those inspections for which !
the Vice President, Operations Support is responsible) is carried out in accordance with the requirements of this policy. The Director, Quality is responsible for reviewing plant administrative procedures which control work
- instructions, modification and repair instructions; and other l- documents to assure that they contain the appropriate inspection requirements.
r I:
L i-l i Page 1 of 5 Policy 10 Rev. 16 OQAMR16 o
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: IMSPECTION 10.4.2 (Continued):
The Director, Quality, is responsible for developing and implementing procedures for the performance of all quality inspections. The coordination of activities concerning the training and certification of all quality inspectors shall be accomplished by the Director, Quality. Level III quality inspectors are appointed. The Director, Quality assures all safety-related work authoritations will be reviewed, as defined by the appropriate implementing administrative procedures, for determination of any quality inspection requirements. Procedures or work authorizing documents which control repetitive tasks are reviewed initially and when revised for inclusion of inspection requirements.
10.4.3 The licensee may delegate the responsibility for= implementing l
certain portions of the inspection program to other organizations. However, the licensee retains the ultinate responsibility for assuring that all aspects of the inspection program are carried out. At GGNS, the Director, Quality is responsible for assuring that inspection activities assigned to onsite contractors are accomplished in accordance with the requirements of this policy.
10.4.4 Organizations supplying safety-related material, equipment l and services are responsible for complying with the i
applicable requirements of this policy, as stipulated in the procurement documents, and for imposing them upon their contractors and suppliers as applicable. They are also responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented.
10.4.5 This section deleted in Revision 12.
10.4.6 The Vice President, Operations Support, is responsible for assuring that headquarters source, receipt, warehouse, and l shipout inspections are accomplished in accordance with the requirements of approved policies. He is responsible for developing and implementing procedures and for the qualification, training, and certification of personnel for the performance of these inspections. Level III receipt
! inspectors are appointed.
l 10.5 REQUIREMENTS _
10.5.1 Inspection requirements shall be included in applicable i
specifications, drawings, procedures, instructions or other l documents which prescribe and control safety-related activities.
10.5.2 These inspection requirements shall be translated into a documented inspection program, to be implemented by the responsible organizations in accordance with written procedures, which verifies that the activities are accomplished in accordance with the specifications, drawings, procedures or instructions.
Page 2 of 5 Policy 10 Rev. 16 OQAMR16
. = . - _ _._ ._ _ _ _ _ . _ . .___ _ .- _
1 OPERATIONAL QUAL 2TY ASSURANCE MANUAL T2TLE: INSPECTION 10.5 (Continued):
10.5.3 Inspection procedures, instructions or checklists shall include provisions, as required, for the following:
10.5.3.1 Identification of characteristics and j activities to be inspected; 1
10.5.3.2 Identification of the individuals or I
organizations responsible for performing the inspection activities; i '
1 l
10.5.3.3 Identification of acceptance and rejection '
criteria; i 10.5.3.4 A description of the method of inspection; 10.5.3.5 Recording evidence of the completion and verification of a manufacturing, inspection or test operation; 10.5.3.6 Recording the identity of the inspector or data recorder and the results of the inspection operation; and, 10.5.3.7 Specifying the necessary measuring and test equipment, including the accuracy requirements.
Accuracy may be specified by requiring a specific model or type of instrument.
10.5.4 The applicable drawings and specifications shall be available for use with the inspection procedures, instructions or checklists when an inspection operation is being carried out.
10.5.5 Inspections shall be performed by qualified personnel who are independent of those individuals who performed the activity being inspected. Inspection of operating activities (work functions associated with normal operation of the Plant, routine maintenance, and certain technical services routinely assigned to the onsite operating organization) may be conducted by s"cond-line supervisory personnel or by other qualified personnel not assigned first-line supervisory responsibility for conduct of the work.
When inspections of operating activities are performed _by individuals other than those who performed or directly supervised the work, but are within the same group, the following controls shall be met:
10.5.5.1 The quality of the work can be demonstrated through a functional test when the activity involves breaching of pressure retaining items; Page 3 of 5 Policy 10 Rev. 16 OQAMR16
? l 1
l.
- l. OPERATIONAL QUALITY' ASSURANCE MANUE
' TITLE: INSPECTION 10.5.5 (continued):
10.5.5.2 The qualification criteria for inspection personnel are reviewed and found acceptable by
! Quality Programs prior to initiating the inspection.
I 10.5.6 Personnel performing inspections which require specialized qualifications or skills shall be qualified in accordance with applicable codes,. standards or~ licensing requirements,
- and their qualifications 1and certifications shall be
! documented and kept current.
l 10.5.7 If mandatory inspection hold points are required, the
[ specific hold points shall be specified in the appropriate
[ drawings, specifications, procedures or instructions. The l- inspection program shall provide assurance that work does not l progress beyond the hold point until released by the l designated authority, and that required notification and l acknowledgement has been satisfied prior to work continuing.
! 10.5.8 If. inspection is impossible or disadvantageous, indirect
- control shall be provided by monitoring processing methods, t
equipment, and personnel. Inspection and process monitoring j shall be utilized if control is inadequate without both.
-10.5.9 Instructions addressing maintenance, modifications, repairs or replacements ahall be reviewed by qualified personnel
, (other than the preparer) who have the knowledge required to
[ determine the need for inspection, identification of l inspection personnel, and documenting inspection results.
10.5.10 Modifications, repairs and replacements shall be inspected in accordance with the original design and inspection requirements or documented engineering approved alternatives.
10.5.11 Inspection data and results shall be evaluated by designated Personnel to assure that the inspection objectives have been met and that items requiring action or follow up are identified and documented.
10.5.12 Records shall be kept in sufficient detail to provide adequate confirmation of the inspection program. Records shall be maintained in accordance with Policy 17 of this manual.
l 10.5.13 Inspections need not be performed for each specific work activity. Procedures used for assigning inspections shall l
l require the following to be evaluated in assignment of l inspections:
10.5.13.1 complexity, magnitude or criticality of the work.
i i
i l
, Page 4 of 5 Policy 10 Rev. 16 OQAMR16
OPERATIONAL QUALITY ASSUPANCE MANUAL TITLE: INSPECTION 10.5.13 (Continued):
10.5.13.2 Documented engineering inspection requirements.
10.5.13.3 Design organization inspection requirements.
10.5.13.4 Components safety impact.
10.5.14 Inspections shall be performed on repetitive, routine and rework items as determined by Quality Programs.
l Page 5 of 5 Policy 10 Rev. 16 OQAMR16
b OPERATIONAL QUALITY ASSURANCE MANUAL l
. TITLE: TEST COMTROL i
[.
11.0 TEST CONTROL l
11.1 PURPOSE ,
This policy describes the Operational Quality Assurance Program measures l l to control testing of safety-related structures, systems and components
.for the Grand Gulf Nuclear Station. i 11.2 SCOPE This policy delineates responsibilities and defines requirements for the establishment and implementation of a test program to assure that testing required to demonstrate that safety-related items will perform ;
satisfactorily in service is identified, accomplished and documented, 1 l
11.3 APPLICABILITY The requirements of this policy apply to all testing performed on safety-related structures, systems and components during the operational phase i of nuclear power plant activities and also to required preoperational j . testing.
11.4 RESPONSIBILITY 11.4.1 The responsibility and authority for the development and l implementation of maintenance and surveillance testing !
L programs during the operational phase are delegated to the '
l General Manager, Plant Operations and Director, Design Engineering-GGNS. They are also responsible for the develcpment and implementation of testing programs for design changes and plant modifications. They are responsible for l assuring that the test programs are established and implemented'in accordance with procedures and instructions which address the requirements of this policy. They are also l responsible for assuring that contractors who are delegated i onsite testing responsibilities impose the applicable j l
requirements of this-policy on their internal operations and l on their contractors or suppliers.
l 11.4.2 Organizations responsible for conducting offsite testing are l subject to the applicable requirements of this policy as specified in the appropriate procurement documents.
l l l Individuals or organizations responsible for the preparation
! of procurement documents shall assure that the applicable l
l' requirements of this policy are included, as stipulated in Policy 4 of this manual.
11.4.3 This section deleted in Revision 3.
L i Page 1 of 3 Policy 11 Rev. 16 OQAMR16
OPEPATIONAL QUALITY ASSURAMCE MANUAL l TITLE: TEST CONTROL
~~
11.4 (Cantinued):
11.4.4 The Director, Quality has the responsibility for assuring test control implementation by inspection of test activities at GGNS and review of test programs and plant administrative procedures which control testing to verify conformance to the requirements of this policy.
11.4.5 This section deleted in Revision 12.
11.5 REQUIREMENTS -
11.5.1 A test program shall be established and implemented to assure that testing required to demonstrate that a safety-related structure, system or component will perform satisfactorily in l
service is identified and documented, and that the testing is performed in accordance with written, controlled test procedures.
11.5.2 The test program shall be implemented by the responsible organizations to cover all required testing, including prototype tests, preoperational tests, initial start-up tests, surveillance tests, and tests associated with plant maintenance and modifications during the operational phase.
11.5.3 This section deleted in Revision 3.
11.5.4 This section deleted in Revision 3.
11.5.5 Surveillance testing during the operational phase shall be performed to provide assurance that failures or substandard performance do not remain undetected and that the required reliability of safety-related systems is maintained. A surveillance testing schedule (s) shall be established reflecting the status of all planned in-plant surveillance tests and inspections. Frequency of surveillance tests may be related to the results of reliability analyses, the frequency and type of service, or age of the item, as appropriate.
11.5.6 Tests performed following plant modifications, repairs or replacements shall be conducted in accordance with the original design and testing requirements or engineering approved, documented alternatives. Testing shall be sufficient to confirm that the modifications or changes reasonably produce expected results and that the change does not reduce safety of operations.
11.5.7 Written procedures for performing the tests shall incorporate or reference the following, as applicable:
11.5.7.1 A description of test objectives; I
l l
l Page 2 of 3 Policy 11 Rev. 16 OQAMR16
. . . _ . - . . . . . . - - . - - . ~ . . . , . _ . - ~ . - . . ~ . , . - _ . - _ . . _ . - . . . . . . - - . - . . ~ . .
l:
OPERATIONAL QUALITY ASSURANCE MANUAL,
. T2TLE: .. TEST CONTROL
"~
, 11.5.7 (Continued)i j 11.5.7.2 The requirements and acceptance limits contained in applicable design and procurement documents;
-11.5.7.3
' Instructions for performing the testi 11.5.7.4 Test prerequisites (e.g., calibrated instrumentation; adequate and appropriate equipment; trained, qualified, and licensed or i
certified personnel; assurance of completeness of the item to be tested; suitable and controlled environmental conditions; and provisions for data
- collection and storage);
I
( 11.5.7.5 . Hold points ' or witness points for inspection by designated personnel;
'11.5.7.6 Acceptance and rejection criteria;
'11.5.7.7 Methods of documenting or recording test data and l
. results.
11.5.8 The documented test results shall be evaluated and their 1 acceptability determined by qualified individuals or organizatiens as designated in the pro edures.
i l
l l
l I-t _
t !
l l ,
I 1
L Page 3 of 3 Policy 11 Rev. 16 OQAMR16 l'
o s~ .
f l
OPERATIONAL QUALTTY ASSURANCE MANUAL TITLE: CONTROL OF MEASURIMG AND TEST EQUIPMENT 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 PURPOSE This policy describes the Operational Quality Assurance Prv;iam measures to provide for the control of measuring and test equipment used in the performance of safety-related activities for the Grand Gulf Nuclear Station.
12.2 SCOPE q This policy delineates responsibilities and defines requirements for the calibration, maintenance and control of measuring and test equipment used in safety-related applications in order to assure the required accuracy i of such equipment.
12.3 APPLICABILITY The requirements of this policy apply to all tools, instruments, testing equipment and measuring and contrcl devices used in inspections, measurements, tests or monitoring of safety-related components, systems or structures during the operational phase of nuclear power plant 1 activities.
I The requirements of this policy do not apply to rulers, tape measures, levels and other such devices if normal commercial practices provide ;
-sufficient accuracy.
)
12.4 RESPONSIBILITY 12.4.1 Responsibility and authority for the control of measuring and 1 test equipment at GGNS during the operational phase are delegated to the General Manager, Plant Operations. During implementation of design changes and plant modifications, thu Manager, Plant Maintenance and Modifications is responsible j for ensuring that all METE utilized are controlled in accordance with procedures developed by the General Manager, Plant Operations. They are responsible for assuring that procedures are developed to implement the requirements of this policy.
12.4.2 Organizations supplying materials equipment or services are responsible for complying with the applicable requirements of this policy, as specified in the appropriate procurement documents and for imposing them on their contractors and suppliers, as applicable. They are also responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented.
Page 1 of 3 Policy 12 Rev. 16 OQAMR16
D OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: CONTROL OF MEASURING AND TEST EQUZPMENT 12.4 (Continued):
12.4.3 The Director, Quality has the responsibility for assuring by audit and inspection, the control of measuring and test equipment at GGNS. The Director, Quality is responsible for reviewing plant administrative procedures which govern equipment control instructions to verify canformance to the requirements of this policy.
12.4.4 This section deleted in Revision 12.
, 12.4.5 The Vice President, Engineering, and Vice President, i Operations Support, are responsible for headquarters measuring and test equipment activities. They are also responsible for assuring that procedures are developed to implement the requirements of this poljcy.
12.5 REQUIREMENTS I l
12.5.1 Organizations performing safety-related functions which require the use of measuring and test equipment such as instruments, control devices, gages, tools, fixtures, calibration standards and nondestructive test equipment shall l establish and implement procedures to control the l calibration, maintenance and use of such equipment. i l
12.5.2 Procedures shall assure that measuring and test equipment I used for measurements, tests or calibrations is of the proper range and type and is controlled, calibrated, adjusted and maintained at specific intervals, or prior to use, to assure necessary accuracy.
12.5.3 The method and interval of calibration shall be established for each device or generic grouping thereof, and shall be based on the type of equipment, stability and reliability characteristics, required accuracies and other conditions affecting calibration.
12.5.4 Procedures shall provide methods for the positive identifica-tion of all measuring and test equipment included under the calibration system, documentation of its calibration status; and traceability to documented calibration test data.
12.5.5 Installed operations measuring and test equipment requiring calibration shall be labeled, tagged or otherwise controlled in accordance with written, approved procedures to assure that approved calibration intervals are not exceeded.
Portable measuring and test equipment may be similarly controlled; but shall, as a minimum, be clearly labeled to indicate the date on which the current calibration expires.
Portable measuring and test equipment that has exceeded the approved calibration interval shall not be used for measurements or tests.
l l 12.5.6 Calibration standards shall be t,,ceable to nationally
, recognized standards; or, where national standards do not
, exist, provisions shall be established to document the basis for calibration.
I-l Page 2 of 3 Policy 12 Rev. 16 OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL TZTLE: CONTROL OF MEASURING AND TEST EQUIPMENT i
12.5.6 (Continued):
In order to establish this traceability, calibrating standards should have a greater accuracy than the standard being calibrated and possess sufficient range and stability to assure that the standard being calibrated is within the l required tolerance. Calibrating standards with the same l accuracy as the standard being calibrated shall be allowed if it can be shown to be adequate for.the requirements and the basis of acceptance is documented and evaluated by a technically knowledgeable individual and authorized by responsible management. '
12.5.7 Measuring and Test Equipment (M&TE) should be calibrated against standards (for the purpose of calibration M&TE is defined as that equipment, whether permanently installed or portable, used to calibrate permanent plant devices) that have an accuracy of at least four times the required accuracy of the M&TE being calibrated. A standard of lesser accuracy shall be allowed provided that the basis of acceptance is documented, evaluated for adequacy by a technically knowledgeable individual and authorized by responsible management.
Calibration of permanent plant devices shall be against M&TE l having sufficient accuracy, greater than the device being j
calibrated, to assure that the system containing the device is within the specified system tolerance. The basis for I
determining the greater than accuracy of the M&TE used shall be reproducible, either by engineering demonstration or i
documentation. When an accuracy is specified in the Technical Specifications or bases therecf or in the UFSAR, Appendix 16B, this accuracy may be used in lieu of one determined by engineering demonstration or documentation.
12.5.8 Measures shall be established to assure that, if a piece of measuring and test equipment is found to be out of calibration, an evaluation shall be made and documented, in accordance with Policy 15, to verify the validity of previous tests and the acceptability of devices tested since the time of the last calibration. A permanent plant device which is found out of calibration, but within the tolerance given in the Technical Specifications or in the UFSAR, Appendix 16B, may be adjusted. Such actions shall be documented, but they need not be evaluated or processed as specified in Policy 15.
12.5.9 If any calibration, testing or measuring device is consistently found to be out of calibration, it shall be repaired or replaced.
l I
e l
Page 3 of 3 Policy 12 Rev. 16 OQAMR16 i
i
OPERATIONAL QUALZTY ASSURANCE MANUAL TITLE: HANDLING, STORAGE AND SHZPPIMG 13.0 HANDLING, STORAGE AND SHIPPING 13.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to control the handling, storage and shipping of safety-related materials, components and systems for the Grand Gulf Nuclear Station.
13.2 SCOPE This policy delineates responsibilities and defines requirements for handling, storage and shipping, including cleaning, packaging and preservation of safety-related items in order to assure that the requisite quality of the items is maintained until they are used or incorporated into the nuclear power plant.
13.3 APPLICABILITY The reqtirements of this policy apply to all individuals or organizations participating in the cleaning, handling, packaging, preservation, shipping and storage of safety-related itens during the operational phase of nuclear power plant activities.
13.4 RESPONSIBILITY 13.4.1 During the operational phase at GGNS, the responsibility and authority for control of handling, storage and shipping, including cleaning and preservation, are delegated to the Vice President, Operations Support and the General Manager, Plant Operations. During the implementation of design p changes and plant modifications, the Manager, Plant Maintenance and Modifications is responsible for these activities. They are responsible for assuring that procedures are established to address the applicable requirements of this policy and that work and inspection activities are accomplished in accordance with the established procedures.
13.4.2 Organizations supplying safety-related material, equipment and services are responsible for complying with the applicable requirements of this policy, as stipulated in the procurement documents, and for imposing them on their contractors and suppliers as applicable. They are also responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented.
13.4.3 The Vice President, Operations Support, has the responsibility for warehouse-related inspection (including receipt inspection) of the control of handling, storage and shipping at GGNS. He is also responsible for headquarters handling, shipping, and storage activities. The Director, Quality is responsible for the review of plant administrative procedures to verify conformance to the applicable requirements of this policy.
13.4.4 This section deleted in Revision 12.
Page 1 of 3 Policy 13 Rev. 16 OQAMR16 i
1
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: HANDLING, STORAGE AND SHIPPING 1
13.5 REQUIREMENTS l 13.5.1 Procedures shall be established to control handling, storage and shipping, including cleaning, packaging and preservation of safety-related materials, components and systems. The Procedures may be developed to cover generic classifications of items which require equivalent levels of protection and control during handling, storage and shipping. Classified items shall be restricted to that level or higher for each of the particular handling, storage and shipping operations; and '
a change in the classific'ation of an item shall only be made in accordance with a written, engineering approved procedure.
13.5.2 The procedures shall be developed by the appropriate organizations to cover the various stages from fabrication or j manufacture of the items to incorporation into the plant. ;
1 13.5.3 The procedures shall address the applicable design and regulatory requirements; codes and standards; and manufacturer's recommendations as approved by the licensee engineering personnel for the prevention of damage, ,
deterioration or loss prior to installation or use. I Source quality verification or inspection operations necessary to verify conformance to the established criteria shall be included in procedures, and documentation of the verification l activities soall be required.
13.5.4 Packaging and preservation procedures shall provide assurance of adequate protection against corrosion, contamination, l physical damage or any effect which would lower the quality l of the item or cause it to deteriorate during shipping, handling or storage. Special protective environments, special coverings, inert gas atmosphere, allowable moisture content, and temperature level shall be specified as required and their existence verified and documentud.
13.5.5 Cleaning procedures shi.11 provide assurance that necessary l cleaning operations are carried out prior to packaging, storage or installation. The level of cleanliness required and verification and documentation requirements shall be specified in the procedures.
I 13.5.6 Procedures shall be provided to assure that proper marking and labeling of items and containers is accomplished to i provide identification and necessary instructions during l
packaging, shipment and storage. I 13.5.7 Measures for receipt inspection of items, disposition of ;
received items and control of nonconforming items shall be l addressed in procedures which implement the applicable requirements of Policies 7 and 15 of this manual.
i Page 2 of 3 Policy 13 Rev. 16 OQAMR16
. _. _ . . . . ~ _ .. _ _ _ _ . __
l l
OPERATZONAL QUALITY ASSURANCZ MANUAL TITLE: E'NDLYNG, STORAGE AND SHIPPING j -~
l 13.5 (Continued):
l l 13.5.8 Detailed handling procedures shall be provided for all items I
that require special handling. Special handling tools and equipment shall be provided and controlled to ensure safe and adequate handling. These tools and equipment shall be maintained, inspected and tested in accordance with written
, procedures at established intervals to ensure their I
reliability and availability for use.
13.5.9 Storage procedures shall ' provide for methods of storage and the control of items in storage which will minimize the possibility of damage or deterioration during storage.
Periodic inspections of storage areas shall be performed and documented to verify compliance with storage procedures.
helease of items for installation shall also be procedurally controlled.
13.5.10 This section deleted in Revision 11.
i l
I l
l l
l Page 3 of 3 Policy 13 Rev. 16 OQAMR16
! OPERATIONAL QUALITY ASSURAMCE MANUAL TITLE: INSPECTION, TEST AND OPERATING STATUS l
14.0 INSPECTION, TEST ~AND OPERATING STATUS 14.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to identify and control the inspection, test and operating status of safety-related structures, systems and components for the Grand Gulf Nuclear Station.
14.2 SCOPE This policy delineates responsibilities and defines requirements for identifying and controlling the inspection, test and operating status of safety-related items in order to assure that required inspections and tests are performed and the acceptability of items is known, and to prevent the inadvertent operation of items which are in a controlled status.
14.3 APPLICABILITY The requirements of this policy apply to all individuals or organizations performing functions on safety-related structures, systems and components during the operational phase of nuclear power plant activities.
14.4 RESPONSIBILITY 14.4.1 During the operational phase, responsibility and authority for identifying and controlling the test and operating status of safety-related items, excluding preoperational testing, are delegated to the General Manager, Plant Operations. The Director, Quality has the responsibility and authority for identifying and controlling the inspection (except those inspections for which the Vice President, Operations Support, is responsible), test, and operating status of safety-related items. They are responsible for assuring that procedures are developed and implemented to address the applicable requirements of this policy.
14.4.2 Organizations supplying safety-related material, equipment and services are responsible for complying with the applicable requirements of this policy, as stipulated in the i procurement documents, and for imposing them on their I contractors and suppliers as applicable. They are also l responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented; 14.4.3 The Director, Quality is responsible for reviewing plant administrative procedures to verify conformance to the applicable requirements of this policy.
14.4.4 This Section deleted in Revision 12.
14.4.5 The Vice President, Operations Support, is responsible for assuring that headquarters inspection and test status activities applicable to GGNS and GGNS source, receipt, warehouse, and shipout inspections are accomplished in l accordance with the requirements of this policy. He is also responsible for developing and implementing procedures for the performance of inspection anc test status activities.
Page 1 of 3 Policy 14 Rev. 16 OQAMR16
~ _ _ , . . - ~ _ _ . . . - _ . - ~ .. - - . . . ~ - - . - . _. ,_-. ~ .- . .- ~ . - ~
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: INSPECTZON, TEST AND OPERATING STATUS 14.5 REQUIREMENTS 14.5.1 Procedures shall be established and implemented by the organizations responsible for the fabrication, storage, installation, test, and operation of safety-related l structures, systems and components to assure that the l- inspection, test and operating status of such items is identified, controlled and made known to affected organizations.
l 14.5.2 The procedures shall requ, ire that the status of inspections l and tests be indicated by the use of appropriate status i indicators such as stamps, tags, labels, routing cards,' shop travelers, or other suitable means. Suitable means may include identification numbers which are traceable to inspection and test records.
, 14.5.3 The procedures shall identify the status indicator to be used l
and provide for its control, including responsibility and authority for application and removal.
14.5.4 Bypassing of required inspections, tests or other critical operations shall be procedurally controlled with concurrence by Quality Programs. Where necessary to preclude inadvertent bypassing of required inspections and tests, the procedures shall provide for the identification of itens which have passed such inspections and tests.
14.5.5 In cases where documentary evidence is not available to confirm that an item has passed required inspections and tests, that item shall be considered nonconforming and processed in accordance with Polit " 15. Affected systems shall also be evaluated for operability in accordance with the Technical Specifications or the UFSAR, Appendix 16B, and reliance shall not be placed on any such systems (which are evaluated as inoperable) to fulfill their intended safety functions.
14.5.6 Procedures shall be provided to require identification of the operating status of systems, components, controls, or support equipment in order to prevent inadvertent or unauthorized operation. These procedures shall require control measures, such as locking or tagging to secure and identify equipment in a controlled status. Independent verification shall be required, where appropriate, to ensure that necessary -
measures, such as tagging equipment, have been implemented correctly.
l l
!~
I l
Page 2 of 3 Policy 14 Rev. 16 OQAMR16 l
l
.= .. . . .-, . . _ _
. - . .. ... . . . . . , . - . . . . . - ~ . . . - . - - . - - . . - . . - - . _ . . . - - . . . . ,
OPERATIONAL QUALITY' ASSURANCE MANUAL
.TITLEt INSPECTION, TEST AND OPERATING STATUS
-14.5' (Continued):
~~
14.5.7 Temporary modifications shall be controlled by approved j' procedures which include a requirement for independent l verification. A log shall be maintained of the-current- ,
[ status of such temporary modifications. ;
1 .
! 14.5.8 ~ Nonconforming services and nonconforming, inoperative or i malfunctioning structures, systems,- components or materials
' shall be identified'and controlled in accordance with the requirements of Policy 15,.of this manual.
l-i I
l Page 3 of 3 Policy 14 Rev. 16 OQAMR16
l' l
OPERATIONAL QUALITY ASSURANCE MFWUAL TITLE: NONCONFORMING MATERZALS, PARTS OR COM?ONENTS 15.0 NONCONFORMING MATERIALS, PARTS OR COMPONENTS l (Including Items, Services and Activities) 15.1 PURPOSE l
This policy describes-the Operational Quality Assurance Program measures to identify and control safety-related items, services or activities for the Grand Gulf Nuclear Station which do not conform to established requirements.
The term discrepant material used within this manual refers to nonconforndng materials, parts or components discovered before receipt inspection acceptance.
15.2 SCOPE This policy delineates responsibilities and defines requirements for the identification and control of nonconforming safety-related items, services or activities in order to assure that the nonconforming naterial conditions do not compromise quality or safety.
15.3 APPLICABILITY The requirements of this policy apply to all individuals or organizations performing functions en safety-related structures, systems, materials, parts or components during the operational phase of nuclear power plant activities.
15.4 RESPONSIBILITY 15.4.1 Responsibility and authority for the identification, control and disposition of nonconforming items, services and activities during the operational phase are delegated to the Director, Design Engineering - GGNS; the Vice President, Engineering, (for nuclear fuel or core items); the General Manager, Plant Operations; the Director, Quality; the Vice ,
President, Operations Support (for discrepant material); and I the manager of the organization performing the activity. It ,
is the responsibility of these individuals to assure that the i requirements of this policy which are applicable to their ;
scope of activities are implemented in accordance with
{
documented procedures. All personnel are responsible for i reporting detected nonconformances in accordance with t_he l procedures applicable to their particular organization.
15.4.2 Organizations supplying material, equipment or services are responsible for complying with the applicable requirements of this policy, as specified in the procurement documents, and for imposing them on their contractors and suppliers, as applicable. They are also responsible for verifying, through surveillance or audits, that the requirements are being adequately implemented.
I l
Page 1 of 3 Policy 15 Rev. 16 l OQAMR16
. - . . . . - . _ - - - ~ _ . . - . - ..-.- - -.-. - - - -. . - . . . - . - . . . . - - - . - -
! -OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: NONCONFORMING MATERIALS, PARTS OR COMPONENTS 15.4 (Continued):
15.4.3 This section deleted in Revision 15..
15.4.4 The Director, Quality, and the Vice President, Operations Support,-are responsible for the periodic review and analysis of nonconformance reports, NRC and licensee quality deficiency documents to detect possible adverse quality trends. The results shall be reported to the appropriate levels of management for review and assessment.
15.5 REQUIREMENTS 15.5.1 Procedures shall be established by the responsible organizations to identify and control nonconforming safety-related items, services and activities. The procedures shall include provisions for identification, documentation, segregation, review, disposition and notification to affected organizations, as appropriate.
15.5.2 The procedures shall:
15.5.2.1 Specify the individuals or organizations responsible for the disposition and approval of nonconforming itenm, services or activities (including an independent review and acceptance).
15.5.2.2 Provide for documentation to identify the item,
! service or activity; describe the nonconformance; document the disposition and inspection requirements; and provide signature approval of the disposition.
Unless evaluated as having no impact on satisfactory performance, nonconformances are corrected or resolved prior to the initiation of the preoperational test on the item.
15.5.3 Measures shall be established to procedurally control further processing, delivery or installation of a nonconforming item or continuation of a nonconforming service or activity, i pending a decision on its dirposition.
i 15.5.4 In order to prevent its inadvertent use or installation, a nonconforming item shall be identified by marking or tagging and shall be physically segregated, where practical. If physical segregation is not practical, identification of ;
the item as nonconforming by marking or tagging shall be '
acceptable. Where marking or tagging is not feasible, l nonconforming items may be controlled by the use of i appropriate documentation. Markings or tags used to identify i nonconforming items shall be removed af ter resolution of the nonconforming condition.
i 15.5.5 Nonconforming items, services or activities shall be reviewed i
, and dispositioned in accordance with documented procedures.
1 Items may be dispositioned in the following ways:
2 15.5.5.1 Accept-as-iss Page 2 of 3 Policy 15 Rev. 16 OQAMR16 l.
OPERATIONAL QUALITY ASSURANCE MANUAL -
TITLE: NONCONFORMING MATERIALS, PARTS OR COMPONENTS 15.2.2 (Continued):
15.5.5.2 Scrap; 15.5.5.3 Rework to conform to a drawing or specification; 15.5.5.4 Repair in accordance with an engineering approved procedure.
Items received without the necessary documentation shall be controlled. Acceptance of such items will be withheld l pending receipt of required documentation or the items will l be considered nonconforming.
15.5.6 The acceptability of rework shall be verified by reinspecting or retesting the item to the original requirements, or by an equivalent method which has been reviewed and approved. The acceptability of repair shall be verified by reinspection, or retesting the item by an engineering approved method even though the item still may not conform to the original requirements. Inspection, testing, rework and repair shall be documented.
l 15.5.7 For items dispositioned " accept-as-is" or " repair," a description of the change, waiver or deviation shall be documented to record the change and denote the as-built condition. Documentation verifying the acceptability and approval of such items shall also be required.
15.5.8 Nonconformance reports with " accept-as-is" or " repair" dispositions submitted by contractors or suppliers shall be reviewed and concurred with by the designated incividuals and shall become a part of the inspection records to be submitted with the item.
15.5.9 This section deleted in Revision 12.
Page 3 of 3 Policy 15 Rev. 16 l OQAMR16 l
r OPERATZOMAL QUALITY ASSURANCE.MAMUAL TITLE: CORRECT 3VE ACTZON 16.0 CORRECTIVE ACTION 16.1' PURPOSE
! This policy describes the operational Quality Assurance Program measures l l 'to provide for the correction of conditions adverse to the quality or !
I safety of the Grand Gulf Nuclear Station. l l
16.2 SCOPE ,
- This policy delineates responsibilities and defines requirements for the l identification, documentation, reporting, and correction of conditions l adverse-to quality or safety, including requirements for the l determination of cause and corrective action to preclude the recurrence of significant conditions adverse to quality or safety.
16.3 APPLICABILITY The requirements of this policy apply to all individuals or organizations
-performing functions which affect safety-related structures, systens or components during the; operational phase of nuclear power plant activities.
16.4 RESPONSIBILITY 16.4.1 Responsibility and authority for the development and control of measures to assure corrective action during the operational phase are delegated to the General Manager, Plant Operations; Director, Design Engineering - GGNS; Vice President, Engineering; Director, Nuclear Safety & Regulatory Affairs; Vice President, Operations Support; and the Director, Quality. They are responsible for assuring that procedures are established in accordance with the requirements of this policy to provide for the identification, documentation, and correction of conditions adverse to quality or safety. They are also responsible for assuring-that corrective action implemented is' designed to prevent recurrence of significant adverse conditions.
'16.4.2 All organizations performing quality or safety affecting activities are responsible for incorporating into the appropriate procedures, measures for identifying and reporting conditions which may warrant corrective action. ~
Responsibility for determining and implementing necessary corrective action is delegated to the organization performing or controlling the activity. During the operational phase, ,
the responsibility for the determination and implementation of corrective action onsite, is delegated to the General Manager, Plant Operations.
- l. During implementation of design changes and plant modi-
- l. fications, the Manager, Plant Maintenance and Modifications l l is responsible for this activity.
i L Page 1 of-3 Policy 16 Rev. 16
! OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL TZTLE: CORRECTIVE ACTION
. . ~ .
16.4 (Continued):
16.4.3 This section deleted in Revision 4.
16.4.4 Organizations supplying material, equipment or services are responsible for complying with the requirements of this policy as specified in the appropriate procurement documents, and for imposing them on their contractors and suppliers as I applicable. They are also responsible for verifying, through l surveillance or audits, that the requirements are being '
adequately implemented.
16.4.5 The Director, Quality and the Vice President, Operations Support, have the responsibility for the periodic review and analysis of NRC and licensee quality deficiency documents to detect possible adverse quality trends; for reporting such items, if any, to the appropriate levels of executive management for further action.
16.5 REQUIREMENTS )
16.5.1 Procedures shall be established and implemented by the l responsible organizations, consistent with the scope of their activities, to provide measures for the identification, documentation, reporting and correction of conditions adverse to quality or safety.
16.5.2 The procedures shall provide for the evaluation of conditions such as nonconformances, failures, malfunctions, deficiencies, violations, deviations, reportable occurrences, 10CFR21 items, and defective material and equipment to determine the need for corrective action and to identify possible adverse quality trends.
16.5.3 The procedures shall require that action be promptly initiated and adequately documented by the responsible organization to correct the condition and to determine if action is necessary to preclude its recurrence.
16.5.4 The documentation to be used to report conditions adverse to quality or safety and request corrective action, and the appropriate distribution and control thereof, shall be specified in the procedures. _
16.5.5 The procedures shall provide for follow-up reviews by the appropriate organizations to verify proper implementation of the corrective action and to close out the documentation.
l Page 2 of 3 Policy 16 Rev. 16 OQAMR16
. _ _ ...,-__m._ .~.- - _ _ - _ _ _ _ ... _.~.- _ .m .. . _. - --..._. _.. _m.m-._ - ._ _ .. ._
- OPERATIONAL QUALITY ASSURANCE MANUAL
. TITLE: CORRECT 2VE ACTION
'16.5 (Continued):
. 16.5.6 For significant conditions adverse-to quality or safety, the cause of the conditions, and the corrective action taken which is designed to prevent recurrence of the event shall be documented and reported to. appropriate levels of management for review.
l ~
16.5.7 Nonconforming materials, parts and component? (including l
items, services and activities) shall-be identified, controlled and dispositioned in accordance with procedures which implement the requirements of Policy 15 of this manual.
I ,
i i
t i
e l
l l
l 1
l i
i l
Page 3 of 3 Policy 16 Rev. 16
.OQAMR16 l
_ _ . _ . . _ _ . = . . . .._ . _ _ _ _ _ _ _
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: QUALITY ASSURANCE RECORDS 17.0 QUALITY ASSURANCE RECORDS 17.1 PURPOSE l This policy describes the Operational Quality Assurance Program measures for the collection, storage, and maintenance of quality assurance records for the Grand Gulf Nuclear Station.
17.2 SCOPE This policy delineates responsibilit1es and defines requirements for the
~
l development of a records management system to provide for the collection, storage, and maintenance of quality assurance records. Quality assurance records include those records which furnish documentary evidence of the quality of items and of activities affecting quality.-
17.3 APPLICABILITY The requirements of this policy-apply to all individuals or organizations participating in the collection, storage or maintenance of quality assurance records during the operational phase of nuclear power plant activities.
17.4 RESPONSIBILITY 17.4.1 Responsibility and authority fer the development of a records management system are delegated to the Vice President, Operations GGNS. This includes responsibility for the collection, storage and maintenance of quality assurance records generated during design and construction, as well as during the operational phase. He shall assure that records are collected, stored and maintained in accordance with procedures which address the requirements of this policy.
Responsibility for the development of the required procedural ccr.trols for the collection, storage and maintenance of quality assurance records is delegated to the Director, Plant Projects & Support.
17.4.2 The Director, Plant Projects & Support is responsible for the collection, storage and maintenance of records generated onsite and required to be maintained at GGNS. Such records include those necessary to operate and maintain the facility and meet regulatory requirements. Such records shall be identified in appropriate procedures developed to meet-the requirements of this policy.
17.4.3 .The Director, Quality has the responsibility for assuring im-plementation of the collection, storage, and maintenance of those quality assurance records onsite which are under the control of the Director, Plant Projects & Support.
1 Page 1 of 3 Policy 17 Rev. 16 OQAMR16
m.__ m , __ .- ~ . _ . . _- -
. OPERATIONAL-QUALfTY ASSURPNCE MANUAL TITLE: -QUALITY ASSURANCE RECORDS 17.4 (Continued)
L 17.4.4 The Director, Plant Projects & Support, is responsible for.
l the collection, storage and maintenance of records related to-f GGNS. Records to be maintained by the Director, Plant l
Projects & Support shall be identified in the appropriate administrative procedures developed to meet the requirements of this policy.
.17.4.5 The Director, Quality is responsible for the collection and storage of quality assurance records generated by Quality Programs until such time as they are transmitted to the Director, Plant Projects &' Support. Such records shall be identified in appropriate quality. assurance procedures developed-to meet the requirements of this policy.
17.4.6 Other organizations whose. scope of activities require the generation, collection, storage or maintenance of quality assurance records shall establish procedures to assure compliance with the applicable requirements of this policy.
~
Contractors and suppliers are responsible for complying with the requirements of'this policy to the extent specified in the appropriate procurement documents, and for imposing them on their contractors and suppliers, as applicable. They are also res'ponsible for verifying, through surveillance or audits, that the requirements are being adequately implemented.
17.4.7 This section deleted in Revision 12.
17.4.8 The Vice President, Engineering, and the Vice President, Operations Support, are responsible for the collection, storage and maintenance of headquarters quality assurance records applicable to GGNS. They are responsible for developing and implementing procedures to assure that these activities are performed in accordance with the requirements of this policy.
17.5 REQUIREMENTS 17.5.1 A system for the collection, storage and maintenance of quality assurance records including provisions for identification, classification, indexing, retention, preservation, safekeeping, retrievability and disposition shall be established. ~
17.5.2 The records system shall define requirements and responsibilities for records transmittals, retention, and maintenance, subsequent to the completion of a work activity, consistent with applicable codes, standards and procurement documents. Measures to assure that the required records have been received and are acceptable shall be established.
l-Page 2 of 3 Policy 17 Rev. 16 OQAMR16
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: QUALITY ASSURANCE RECORDS I "'
l 17.5 (Continued) 1 17.5.3 The records system shall provide measures to assure that records are identifiable and retrievable. Retention periods of sufficient duration to assure the ability to reconstruct ;
significant events and satisfy regulatory or statutory l requirements shall be specified. Inspection and test records I shall contain the following where applicable. l 17.5.3.1 A description of the type of observation; 17.5.3.2 Evidence of completing and verifying a manufacturing, inspection, or test operation; 17.5.3.3 The date and results of the inspection or test; 17.5.3.4 Information related to conditions adverse to quality; 17.5.3.5 Inspector or data recorder identification; 17.5.3.'6
. Evidence as to the acceptability of the results.
17.5.4 Storage facilities for quality assurance records shall be designed to prevent records' damage or loss, to the maximum extent practical; or as a satisfactory alternative, duplicate l record shall be stored in a separate remote location.
17.5.5 Records and documentation requirements are specified in the other Policies of this manual. Quality assurance records include, but are not limited to: design records, such as specifications and drawings; procurement documents; operating logs and procedures; principal maintenance and modification documents; results of reviews, inspections, tests, audits, material analyses; monitoring of work performance; personnel, procedures, and equipment qualification records; quality deficiency documents; corrective action documents; and 10CFR evaluations (i.e., 10CFR50.59, 10CFR21).
l i.
I Page 3 of 3 Policy 17 Rev. 16 OQAMR16
OPEPATIONAL QUALITY ASSURANCE MAPUAL l TITLE: AUDITS l
l l
18.0 AUDITS 1
l 4 18.1 PURPOSE This policy describes the Operational Quality Assurance Program measures to provide a comprehensive audit program for the Grand Gulf Nuclear Station.
18.2 SCOPE i
This policy delineates responsibilities and defines requirements for the I development and implementation of a comprehensive program of planned and l documented audits designed to verify compliance with, and assess the )
effectiveness of, the Operational Quality Assurance Program. l l
18.3 APPLICABILITY l The requirements of this policy apply to all internal and external audits performed by or for the licensee during the operational phase of nuclear power plant activities.
18.4 RESPONSIBILITY 18.4.1 Responsibility and authority for the licensee's audit program are delegated to the Director, Quality and the Vice President, Operations Support. They are responsible for the development and implementation of a program of planned and documented audits to verify compliance with all aspects of the Operational Quality Assurance Program and to assess its effectiveness. They are responsible for assuring that procedures are developed, in accordance with the requirements of this policy, to provide for both internal and external audits. The Director, Quality is responsible for performance .
of audits to verify plant conformance to the Technical Specifications and the UFSAR, Appendix 16B; audits of operational phase activities (including those under the Director, Design Engineering - GGNS and the GGNS Manager, Materials, Purchasing & Contracts); and audits of contractors and suppliers performing onsite activities under their own quality assurance programs. The Vice President, Operations l Support, is responsible for the performance of audits of activities performed by off-site support organizations (except those under Director, Design Engineering - GGNS and the GGNS Manager, Materials, Purchasing & Contracts), and contractors and suppliers performing offsite activities.
They shall also assure that audit results are documented and reported to appropriate management, and that prompt corrective action is taken to eliminate conditions adverse to quality detected during the course of audits.
18.4.2 This section deleted in Revision 3.
I Page 1 of 3 Policy 18 Rev. 16 OQAMR16 e
OPERATIONAL QUALITY ASSURANCE MANUAL TITLE: AUDITS
~~
18.4 -(continued):
18.4.3 organizations supplying material, equipment or services are responsible for auditing their internal operations and their
-contractors and suppliers, as stipulated in the appropriate L procurement documents, in order'to verify compliance with the t
quality assurance program requirements specified in the
! procurement documents.
18.4.4 The section deleted in Revision 5.
18.5 REQUIREMENTS 18.5.1 A comprehensive program of planned and documented audits shall be established and implemented by Quality Programs, and the off-site quality organization to verify compliance with L all aspects of the operational Quality Assurance Program. The
!- audit program shall be carried out in accordance with written approved procedures which address the requirements of this policy.
18.5.2 The audit program shall provide for both internal and external audits. Internal audits shall include audits of the procedures and performance of all licensee organizations whose activities affect the quality of safety-related structures, systems and components. External audits shall include audits of the practices, procedures and instructions of contractors and suppliet: '<ho provide safety-related material, equipment or services.
18.513 Audits shall provide an objective evaluation of quality related practices, procedures, instructions, activities, and items; and review of documents and records.
18.5.4 This section deleted in Revision 14.
18.5.5 Audits shall be performed by trained, qualified personnel not having direct responsibilities in the areas being audited. 1 Qualification and training requirements for auditors shall be j established and documented and records of auditor j qualifications shall be maintained and kept current. !
Personnel selected for quality assurance audit assignments shall have experience or training commensurate with the scope, complexity, or special nature of the activities to be audited.
18.5.6 An audit schedule shall be developed, maintained, reviewed and updated, as necessary.
l l
l l
J l \
1 Page 2 of 3 Policy 18 Rev. 16 00AMR16
^ 1
. . . - . .. . - , _. . ~ . - .-~ -
l l
l' OPERATZONAL QUALITY ASSURANCE MANUAL
( T2TLE: AUDITS l
"~
18.5.6 (Continued):
18,5.6.1 Auditing shall be initiated as early in the life of an activity as practical to assure timely implementation of QA program requirements.
I 18.5.6.2 Audits shall be scheduled on the basis of the status and importance of the activities to be audited.
l 18.5.6.3 This section. deleted in Revision 14.
l 18.5.7 Individual audits shall be performed in accordance with 1 I
documented procedures, plans, or checklists which describe j the audit and provide for an objective evaluation of the '
status and adequacy of the areas being audited.
The " objective evaluation" referenced is not to be confused with the evaluation statement in ANSI N45.2.12 to which the licensee has provided a clarification. See Appendix A.
18.5.8 Audit results, including conditions adverse to quality detected during the audit, shall be documented and reviewed with the supervisor or manager having responsibility in the areas audited. Distribution of audit reports shall include management of the audited organization and appropriate licensee management.
18.5.9 Management of the audited organizations shall be responsible for correcting conditions adverse to quality identified during an audit. They shall assure that corrective action is scheduled, accomplished as scheduled, and documented. The corrective action shall be designed to prevent the recurrence of significant conditions adverse to quality. (See also i Appendix A, Regulatory Guide 1.144, Item 11.)
18.5.10 Deficient areas shall be reviewed or reaudited on a timely basis to verify implementation of corrective action.
18.5.11 Audit results shall be analyzed to detect adverse quality trends and to evaluate the effectiveness of the Operational Quality Assurance Program. Results of such analyses which indicate adverse quality trends shall be r_eported to appropriate management for review and #ssessmenu.
18.5.12 Records shall be generated and retained for all audits including individual audit plans, audit reports, written replies, and records of corrective action. (See also Appendix A, Regulatory Guide 1.144, Item 13.)
18.5.13 The licensee interprets the requirements of the UFSAR, Appendix 16B, Section 7.4.2.8, which requires that audits shall be performed under the cognizance of the SRC, to be met by the following: The SRC shall review the results of audits j of nuclear activities conducted in accordance with the GGNS Operational Quality Assurance Program and maintain cognizance of the audit schedule.
I Page 3 of 3 Policy 18 Rev. 16 OQAMR16
-. _ __- . =~ .. .
~~
APPENDIX A Conformance of GGNS Operational Quality Assurance Program to NRC Regulatory Guides and ANSI Standards -
In each of the ANSI standards, other documents (i.e., other standards, codes, regulations, tables, or appendices) required to be included as a part of the standard are either identified at the point of reference or are described in a special section of the standard. The specific applicability or acceptability of these listed standards, codes, regulations or appendices is either covered in other specific areas in the operational. Quality Assurance Manual, including appendices, or such documents are not considered as quality assurance program requirements, although they may be used as guidance.
NRC Regulatory Guide 1.8 " Personnel Qualification and Training" (2nd Proposed l Revision 2) - Endorses ANSI /ANS 3.1 (Draft 12/79)
The operational Quality Assurance Program complies with those requirements of Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.2.1, 3.2.2, 3. 2. 3, 3. 3, 4.0, 4.1, and 4.4.5 of ANSI /ANS 3.1 (Draft 12/79) that are applicable to Quality Programs (both j onsite and offsite) with the following clarifications: '
- 1) With regard to the term " Bachelor's Degree" as used in the draft Standard, the following qualifications may be considered equivalent to a bachelor's degree:
- a. 4 years of formal schooling in science or engineering,
- b. 4 years of applied experience at a nuclear facility in_the area for which qualification is sought, j
- c. 4 years of operational or technical experience / training in '
nuclear power, or
- d. any combination of the above totaling 4 years. '
- 2) With regard 2 Section 4.4.5 of ANSI /ANS 3.1 (Draft 12/79) titled Quality Ass ance: The licensee will comply with Paragraph 4.4.5 as originally stated in ANSI /ANS-3.1 - 1978 which reads as follows:
At the time of initial core loading or assignment to the active position, the responsible person shall have six years experience in the field of quality assurance, preferably at an operating nuclear plant, or operations supervisory experience. At least one year of this six years experience shall be nuclear power plant experience in the overall.
implementation of the quality assurance program. (This l experience shall be obtained within the quality assurance organization.) A minimum of one year of this six years experience shall be related technical or academic training. A maximum of four years of this six years experience may be fulfilled by related technical or academic training.
The applicability of this guide / standard to other personnel in the licensee's organization is addressed in other Sections of the UFSAR and the Technical Specifications.
I l Page 1 of 36 Appendix A Rev. 16 OQAMR16 i
l l
1 1
NRC Regulatory Guide 1.26 " Quality Group Classification, and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants (Rev. 3, 2/7 6).
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarification:
The licensee may choose not to use the specific A, B, C and D level classification system set forth in this guide. The licensee generally followed the requirements of this guide in developin'g the list of structures, systems and components ("Q" List) to which the program will apply. The licensee "Q" List will describe the items to which the Operational Quality Assurance Program will apply in lieu of the guidance contained in this regulatory guide.
1 NRC Regulatory Guide 1.28 " Quality, Assurance Program Requirements (Design and l Construction)" (6/72) - Endorses ANSI N45.2 - 1971. l This guide and the standard it endorses have been superseded for operations I activities by Regulatory Guide 1.33 and ANSI N18.7 - 1976 which it endorses. l The Operational Quality Assurance Program complies with Regulatory Guide 1.33 and ANSI N18.7 - 1976 as stipulated in Appendix A to the OQAM; therefore, Regulatory Guide 1.28 (Safety Guide 28) and ANSI N45.2 - 1971 which it endorses are not considered necessary and are not included as part of the program.
NRC Regulatory Guide 1.29 " Seismic Design Classification" (Rev. 3, 9/78)
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarification:
For operations phase maintenance and modification activities, the licensee shall control these activities under this Operational Quality Assurance l Program. The licensee shall comply with the Regulatory Position established in this regulatory guide in that quality assurance programmatic / administrative ,
requirements included therein shall apply to these maintenance and modification I activities even though such requirements may not have been in effect originally. Technical requirements associated with the maintenance or modification shall be the original requirements or better (e.g., code requirements, material properties, design margins,' manufacturing processes, and inspection requirements).
l NRC Regulatory Guide 1.30 " Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment" (C/72) - Endorses ANSI N45.2.4 - 1972.
l l l
I l
Page 2 of 36 Appendix A Rev. 16 OQAMR16 l
_ . _ , _____ m____. ._ .m_ _ _ _ . . . _ _ _ _ _., _ . _ . . . _ . . _ _ _ . . _ _ . . . _ . _ _ _ _ . . _ _ . _ . _ _ _ _ _ _
NRC Regulatory Guide ~1~.30 (Continued):
.The operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) For operations phase maintenance and modification activities, the j licensee shall control these activities under this operational l- . Quality Assurance Program. The licensee shall comply with the l Regulatory Position established in this regulatory guide in ' chat quality assurance programmatic / administrative requirements
[ included therein (subject to the clarifications in item 2 below) shall apply to these maintenance and modification activities even though such requirements may not have been in effect originally. j Technical requirements associated with maintenance and modifications shall be the original requirements or better (e.g.,
code requirements, material properties, design margins, ;
manufacturing processes, and inspection requirements).
- 2) Additional clarifications for ANSI N45.2.4 - 1972 are indicated for i specific sections below. l Section 1.4 - Definitions in this Standard which are not included i in ANSI N45.2.10 will be used; all definitions which are included )
in ANSI N45.2.10 will be used as clarified in the licensee ;
commitment to Regulatory Guide 1.74. j i
Section 2.1 - Planning requirements, when necessary, will be incorporated into maintenance and modification procedures.
Section 2.3 - Procedures and Instructions will be implemented as set forth in Policies 2, 3, 5, 10, and 11 of the operational Quality Assurance Manual and by compliance with the Technical Specifications or the UFSAR, Appendix 16B, and ANSI N18.7 as set i forth in Appendix A to the OQAM in lieu of the requirements set forth here.
Section 2.4 - Results will be implemented as set forth in Policies 10, 11 and 17 of the operational Quality Assurance Manual and by j compliance with ANSI N18.7 as set forth in Appendix A of the OQAM in lieu of the requirements set forth here.
Section 2.5.2 - Calibration and control. The third sentence of this section states in part, " .. equipment shall be suitably marked to indicate date of next required calibration." The licensee will utilize a computerized system to indicate the calibration status of installed operations measuring and test equipment in lieu l of marking or tagging the individual item.
t b
Page 3 of 36 Appendix A Rev. 16 OQAMR16 c, . .- , . ._ __ ~ . _ - _ _ _. , ,
.- .- ._ . - ~_ . . . . . - - .
i i
f NRC Regulatory Guide'l'.30 (Continued):
l l Section 3 - Preconstruction Verification will be implemented as j follows: (1) is required only for modifications; (2) will be '
implemented with the clarification that " approved instruction ;
manuala" shall be interpreted to mean the manuals provided by the l supplier as required by the procurement order--these manuals will I
! not be reviewed and approved, per se, by the licensee; (3) no !
special checks will be made by the person withdrawing a replacement !
part from the warehouse--equivalent controls are assured by compliance with ANSI N45.2.2 as set forth in Appendix A to the )
Operational Quality Assurance Manual; and, (4) will be complied
! with as stated, by individual technicians as part of the i maintenance / modification process. !
Section 4 - Installation will be implemented by inclusion, as necessary,.in the appropriate maintenance or modification procedure, where such procedures are used. Standard licensee maintenance practices require that care be exercised in the six areas listed whether a procedure is required or not.
Section 5.1 - Inspections, including subsectiens S.1.1, 5.1.2, and the first sentence in 5.1.3, will be implemented as set forth in Policy 10 of the Operational Quality Assurance Manual. The inspection program will incorporate, as applicable, those items listed in these subsections. The remaining sentence in 5.1.3 is covered in equivalent detail in the licensee's ceramitment to ANSI N18.7, Section 5.2.6; the requirements as set forth in that commitment will be implemented in lieu of the requirements stated here.
Section 5.2 - Tests, including subsections 5.2.1 through 5.2.3, will be implemented as set forth in Policies 3 and 11 of the Operational Quality Assurance Manual. The test program will consider the elenents outlined in this Section, where applicable, when developing test requirements for inclusion in maintenance and modification procedures. In some cases, testing requirements may be met by post-installation surveillance testing in lieu of a special post installation test.
Section 6 - Post-Construction Verification is not generally considered applicable at operating facilities because of the scope of the work and the relatively short interval between installation and operation. Where considered applicable, as in modifications, the elements described in this section will be considered in the development and implementation of inspection and testing programs as described in Policies 3, 10 and 11 of the Operational Quality Assurance Manual.
With regard to Section 6.2.1 of ANSI N45.2.4 - 1972 titled Equipment Tests: The last paragraph of this section deals with tagging and labeling. The licensee will comply with an alternate last paragraph which reads: "Each safety-related item of process instrumentation is identified with a unique number. This number is j utilized in instrument maintenance records so that current l calibration status, including data such as the date of the l.
I Page 4 of 36 Appendix A Rev. 16 OQAMR16
l
~
NRC Regulatory Guide l'.30 - Section 6 (Continued):
calibration and identity of person that performed the calibration, can be readily determined. Such information may also be contained on tags or labels which may be attached to installed instrumentation."
l Section 7 - Data Analysis and Evaluation will be implemented as stated herein after adding the clarifying phrase "where used" at the beginning of that paragraph.
Section 8 - Records will be implemented by conformance with Policy
[
17 of the Operational Quality Assurance Manual and ANSI N45.2.9 as set forth in Appendix A to the OQAM.
NRC Regulatory Guide 1.33 " Quality Assurance Program Requirements (Operation)" (Rev. 2, 2/78) - Endorses ANSI N18.7 - 1976.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) Paragraph C.3 of Regulatory Guide 1.33 (and Section 4.3.4 of ANSI N18.7 which it references) will be implemented as required by the UFSAR, Appendix 16B, which defines " Subjects Requiring Independent Review."
- 2) Paragraph C.4 (" Audit Program") of Regulatory Guide 1.33 (and Section 4.5 of ANSI N18.7 - 1976 which it references).
Audit frequencies will be implemented as required by the applicable code of Federal Regulations, Updated Final Safety Analysis Report, and commitments by various correspondence to the NRC. All other audit frequencies will be determined in accordance with a performance-based audit scheduling program. The scheduling program, through an expert panel, uses assessment indicators to identify and schedule audits based on performance results and importance of the activity relative to safety. Potential audit subject areas are periodically assessed against appropriate performance criteria. From these reviews a determination is made in regard to the depth, scope, and scheduling of specific audits.
Functional areas important to safety are assessed annually (+/-
25%) to identify strengths and weaknesses (if applicable) to determine the level and focus of independent oversight activities for the upcoming year. The basis for the assessment shall include the results of QA audits and surveillance, NRC inspections, LERs, self-assessments, and applicable conditions reports (for example, nonconformance and corrective action reports). Personnel changes, change / increase in functional area responsibilities, industry operating experience, and INFO evaluations,will also be considered.
Each area will be assigned a rating with a comparison to previous years. This assessment will be documented, reviewed, and approved by QA management.
I I
Page 5 of 36 Appendix A Rev. 16 OQAMR16
_. . ~ ~ _ > _ . .m.._m .._____m - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _
i l
l
~
NRC Regulatory Guide 1~.33 - Section 2 (Continued):
This document is considered a QA record and will be available for NRC review. . Audit subject areas contained in TS Section 6.5.2.8
- l. prior to the implementation of the ISTS in March 1995, shall l continue to-be audited on the frequencies previously designated in j the TSs unless expert panel judgment, based on performance results,
! . determines such as an audit to be unnecessary. In such cases the j expert panel basis shall be documented.
l
- 3) Paragraph C.S.a of Regulatory Guide 1.33 (and Section 4.4 of ANSI {
N18.7 which it references) will be-implemented with the 1
- clarification that the Plant Safety Review Committee shall perform l L this activity. i i
- 4) Paragraph C.5.d of Regulatory Guide 1.33 (and Section 5,2.7.1 of l ANSI N18.7 which it references) will be implemented by adding the clarifying phrase "Where practical" in front of the fourth sentence i of the fifth paragraph. The regulatory guide's changing of the two
- uses of the word ,'should" in this sentence to "shall"
. unnecessarily restricts the licensee's options on repair or i replacement parts. It is not.always practical to test parts prior l to use. For modifications where these requirements are not ;
considered practica), a review in accordance with the provisions of 10CFR50.59 will be conducted and documented.
Paragraph C.5.e of Regulatory Guide 1.33 (and Section 5.2.13.4 of
- 5) '
ANSI N18.7 which it references) will be implemented subject to the same clarifications made for ANSI N45.2.2 elsewhere in Appendix A to the operational Quality Assurance Manual.
- 6) Paragraph C.S.f of Regulatory Guide 1.33 (and Section 5.2.19(2) of ANSI N18.7 which it references) will be implemented with the j substitution of the word " practical" for the word "possible" in the last sentence.
- 7) Paragraph C.5.g of Regulatory Guide 1.33 (and Section 5.2.19.1 of ANSI N18.7 which it references) will be implemented with the addition of the modifier normally" after each of the verbs (should) which the regulatory guide converts to "shall." It is the licensee's intent to fully comply with the requirements of this paragraph, and any conditions which do not fully comply will be documented and approved by management personnel. In these cases, the reason for the exception shall also be documented. The documentation shall be retained for the same period of time as the affected preoperational test.
- 8) With regard to Section 3.4.2 of ANSI N18.7 - 1976 titled Requirements for the Onsite operating Organization: Training standards referenced in this section will be implemented if such standards are included in Appendix A to the operational Quality Assurance Manual or in Technical Specifications or the UFSAR, Appendix 16B, or are otherwise part of the license of the individual nuclear facility. The licensee's method of documenting and otherwise meeting the remainder of the requirements of this section are set forth in Policies 1 and 2 of the Operational Quality Assurance Manual and in the Technical Specifications or the UFSAR, Appendix 16B.
I Page 6 of 36 Appendix A Rev. 16
,OQAMR16
,.w.__ - _ 1_. . _ . - , . . _ .
I NRC Regulatory Guide ~~1.33 (Continued): I
- 9) With regard to Section 4.1 of ANSI N18.7 - 1976 titled General: The l licensee audit program will be implemented in accordance with and
! to meet the requirements of: ANSI N45.2.12 as endorsed in Appendix A; Policies 2, 16 and 18 of the operational Quality Assurance ,
Manual; and the requirements of the UFSAR, Appendix 16B. !
l
- 10) With regard to Section 4.2 of ANSI N18.7 - 1976 titled Program l Description Two aspects are addressed in this sections audits and l
independent reviews. The independent review program is implemented as required by the UFSAR, Appendix 16B, and by Policies 1 and 2 of the operational Quality Assurance Manual. The licensee audit I
program will be described in accordance with and to meet the requirements of ANSI N45.2.12 as endorzad in Appendix A of the Operational Quality Assurance Manual, the requirements of Appendix 16B of the UFSAR, and Policies 16 and 18 of the Operational Quality Assurance Manual.
- 11) With regard to Section 4.3 of ANSI N18.7 - 1976 titled Independent Review Process: The requirements of this section, including all of its subparts, shall be met by compliance with the requirements of Appendix 16B of the UFSAR.
- 12) With regard to Section 4.5 of ANSI N18.7 - 1976 titled Audit i Program The licensee audit program will be implemented in I accordance with and to meet the requirements of: ANSI N45.2.12 as endorsed in Appendix A; Policies 2, 16, 17 and 18 of the Operational Quality Assurance Manual. Audit frequencies will be in accordance with Clarification 2 above.
- 13) With regard to Section 5.1 of ANSI N18.7 - 1976 titled Program De-scription: The fourth sentence in this section required a " summary document"; the licensee has submitted Appendix C to the Operational Quality Assurance Manual and interprets this Appendix to fulfill the requirements for a summary document.
- 14) With regard to Section 5.2.2 of ANSI N18.7 - 1976 titled Procedure Adherence: The temporary change requirements of this section are delineated in the Technical Specifications and the UFSAR, Appendix 16B, for activities occurring after the operating License (OL) is issued; the requir; ment; of the Technical Specifications and the UFSAR, Appendix 16B, shall be used in lieu of the general re-quirements in this section to control temporary changes. For, temporary changes which occur under this program during preoperational and startup testing p'rior to issuance of an OL, the licensee will comply with this section with the clarification that another test supervisor or shift supervisor or other member of the Plant Staff (limited to shift superintendent, responsible Section supervisor, Manager, Plant Operations; or General Manager, Plant operations) knowledgeable in the areas affected by the change, may approve changes which require the signer to hold an SRO license.
- When there is a requirement to " implement" or " address" a j procedure, actions prescribed by procedures shall be accomplished. .
j This does not necessarily imply that in all cases the operator, i engineer, or technician has a copy of the procedure in-hand and l signs-off a checklist as each step or function is performed. l l l l
Page 7 of 36 Appendix A Rev. 16 OQAMR16 l
I
l l
NRC Regulatory Guide'l'33 (Continued):
- 15) With regard to Section 5.2.6 of ANSI N18.7 - 1976 titled Equipment control: The licensee will comply with the " independent verification" requirements based on the definition of this phrase i as given under our commitment to Regulatory Guide 1.74.
]
The third sentence of the fourth paragraph requires independent l verification "when appropriate.".Where significant exposure to l radiation, which is determined by cognizant health physics personnel, would result from such verification, they shall advise I operations of current radiological conditions. Operations will !
then decide whether or not the confidence gained from the independent verification is worth the additional radiation exposure. In all cases, radiation doses will be As Low As Reasonably Achievable (NUNRA) . Since the licensee sometimes uses descriptive names to designate equipment, the sixth paragraph, second sentence is replaced with: " Suitable means include identification numbers or other descriptions which are traceable to records of the status of inspections and tests."
l The first sentence in the seventh paragraph will be complied with after clarifying " operating personnel" to mean trained employees assigned to, or under the control of, licensee management at an operating nuclear facility.
- 16) With regard to Section 5.2.7 of ANSI N18.7 - 1976 titled Maintenance and Modification: Since some emergency situations could arise which might preclude preplanning of all activities, the licensee will comply with an alternate to the first sentence in the second paragraph which reads:
"Except in emergency or abnormal operating conditions where immediate actions are required to protect the health and safety of the public, to protect equipment or personnel, or to prevent the deterioration of plant conditions to a possibly unsafe or unstable level, maintenance or modification of equipment shall be preplanned and performed in accordance with written procedures. Where written procedures would be required and are not used, the activities that were accomplished shall be documented after-the-fact and receive the same degree of review as if they had been preplanned."
operations or maintenance personnel may restore the system to design drawing requirements, provided the work and actions are properly documented and that quality and engineering evaluations are obtained. These evaluations may be obtained after-the-fact.
- 17) With regard to Section 5.2.7.1 of ANSI N18.7 - 1976 titled Maintenance Programs: The licensee will comply with the requirements of the first sentence of the fifth paragraph, where practical. This clarification is needed since it is not always possible to promptly determine the cause of the malfunction. In all cases, the licensee will initiate proceedings to determine the cause, and will make such determinations promptly, where practical.
Page 8 of 36 Appendix A Rev. 16 OQAMR16
l l
~
l NRC Regulatory Guide 1~.33 - Section 17 (Continued):
The fifth sentence of the fifth paragraph, will be implemented by
- the licensee not allowing the maintenance organization to evaltate and/or use replacement parts that are anything other than direct I
replacement parts. Replacement parts that are NOT "like-for-like" will be evaluated under a Design Engineering - GGNS design change program.
- 18) With regard to Section 5.2.8 of ANSI N18.7 - 1976 titled Surveillance Testing and Inspection Schedule: In lieu of a " master surveillance schedule," the following requirement shall be complied with: "A surveillance testing schedule (s) shall be established reflecting the status of all in-plant surveillance tests.and inspections."
- 19) With regard to Section 5.2.9 of ANSI N18.7 - 1976 titled Plant Security and Visitor Control: The requirements of the Physical Security Plan shall be implemented in lieu of these general requirements.
- 20) With regard to Section 5.2.10 of ANSI N18.7 - 1976 titled l Housekeeping and Cleanliness Control: The requirements of this I section, beginning with the last sentence of the first paragraph l and continuing through the end of the section, will be implemented l as described in the licensee's commitments to ANSI N45.2.3 and '
N45.2.1 as set forth in Appendix A to the Operational Quality Assurance Manual.
- 21) With regard to section 5.2.13.1 of ANSI N18.7 - 1976 titled Procurement Document Control: The words "the same" in the last sentence are replaced with the words "an equivalent".
- 22) With regard to Section 5.2.15 of ANSI N18.7 - 1976 titled Review, Approval and Control of Procedures: The third sentence in Paragraph Three is interpreted to mean: Applicable procedures shall be reviewed following an accident, an unexpected transient, l significant operator error, or equipment malfunction which results in a reportable occurrence. The first sentence in Paragraph Four i is interpreted to mean: This requirement for routine followup l review can be accomplished in several ways, including (but not necessarily limited to): documented step-by-step use of the i procedure (such as occurs when the procedure has a step-by-step checkoff associated with it), or detailed scrutiny of the pro _cedure as part of a documented training program, drill, simulator exercise, or other such activity. Grand Gulf Nuclear Station has taken exception to the biennial review process because of programmatic controls that are equivalent to or better than the biennial review process for compliance with ANSI N18.7-1976. These programmatic controls are effected in an effort to ensure that procedures are reviewed for possible revision upon identification of new or revised source material potentially affecting the intent !
of procedures, thereby maintaining the procedures current. Entergy Operations believes that this approach better addresses the intent of ANSI N18.7-1976 and is more acceptable from both a technical and a practical perspective than a static two-year review process.
Procedures which are only used infrequently, i.e., every three to five years, will be reviewed prior to use. A revision of a
- procedure constitutes a procedure review.
1 Page 9 of 36 Appendix A Rev. 16 OQAMR16 l
^" - _ _ _ _ - - _ - ,
L
~~
NRC Regulatory Guide l.33 (Continued):
- 23) With regard to Section 5.2.17 of ANSI N18.7 - 1976 titled Inspections: Not all inspections will require generation of a separate inspection report. Inspection requirements may be integrated into appropriate procedures o other documents with the procedure or document serving as the record. However, records of inspections will be identifiable and retrievable.
l
- 24) With regard to Section 5.3.9 of ANSI N18.7 - 1976 titled Emergency '
Procedures As directed by thetNRC, the licensee will follow a format for emergency procedures which is " symptom" based as opposed ;
to " event" based as stipulated in Section 5.3.9.1. Since the l licensee will have these " symptom" based procedures, " event" based I procedures will not normally be provided.
- 25) With regard to Section 5.3.9.2 of ANSI N18.7 - 1976 titled Events of Potential Emergency: NRC review of the FSAR has identified all l natural occurrences which affect the nuclear facility. Therefore, j the licensee will interpret Item (11) to mean the natural l occurrences which have been evaluated in the FSAR. l
- 26) With regard to Section 5.3.9.3 of ANSI N18.7 - 1976 titled Procedures for Implementing Emergency Plan: The licenree's NRC accepted Emergency Plan will be implemented in lieu of the l requirements in this section. I
- 27) With Regard to Section 5.2.18 of ANSI N18.7 - 1976 titled Control of Special Processes: The last four words of the first sentence are clarified by inserting the word " approved" before the word
" procedure": We shall use qualified personnel and approved procedures.
- 28) with regard to Section'5.2.7 of ANSI N18.7 - 1976 titled Maintenance and Modification: The first sentence of the first paragraph could be interpreted to require the same degree of inspection for all maintenance activities as was provided during construction. When viewed in conjunction with Section 5.2.17, the third paragraph, we believe the actual intent is clear. We shall provide inspections comparable in nature and extent to that provided during construction if the maintenance / modification work is comparable in nature and extent.
- 29) with regard to Section 5-3.5(4) of ANSI N18.7 - 1976 titled Supporting Maintenance Documents: The licensee may choose to' include material from vendor manuals in any of three ways. (1) The applicable section of the manual may be duplicated, referenced in, and attached to the procedure. (2) The procedure may simply state that the manual or a specific section is to be followed for performing a particular function; the manual must then be used in conjunction with the procedure for performing the activity. (3) The pertinent material from the manual, either as originally written or as modified by the author / reviewers of the procedure, may be written into and become a part of the procedure.
i-l Page 10 of 36 Appendix A Rev. 16 OQAMR16
NRC Regulatory Guide'l!33 - Section 19 (Continued):
In options, (1) and (3) above, the material meets the requirement to receive "the same level of review and approval as operating procedures" since the naterial is reviewed as part of the procedure review process. In option (2), the requirements shall be deemed to have been fulfilled by requiring a copy of the pertinent manual (manual sections) to be available to and considered by persons conducting the review of the procedure.
- 30) With regard to Section 5.2.16 of ANSI N18.7 - 1976 titled Measuring and Test, Equipment: The second sentence of the third paragraph states " Records shall be made and equipment suitably marked to indicate calibration status." The licensee will utilize a computerized system to indicate the calibration status of installed operations measuring and test equipment in lieu of marking or tagging the individual item.
- 31) With regard to Section 1 of ANSI N18.7 titled Scope: The fourth and
, fifth sentenens state, "However, applicable sections of this standard should be used as they apply to related activities.
Activities included are: Design Changes, Purchasing, Fabricating.."
The licensee does not intend to fabricate, design, assemble, or modify any NRC licensed container to be used to transport radioactive material.
NRC Regulatory Guide 1.37 " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants" (3/73) Endorses ANSI N45.2.1 - 1973.
The operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) With regard to Paragraph C.3 of Regulatory Guide 1.37: The water quality for final flushing of fluid systems and associated components shall be at least equivalent to the quality of the operating system water except for the oxygen and nitrogen content, but this does not infer that chromat,a or other additives, normally in the system water, will be added to the flush water.
- 2) With regard to Paragraph C.4 of Regulatory Guide 1.37: Expendable materials, such as inks and related products, temperature -
indicating sticks, tapes, gummed labels, wrapping materials (other than Polyethylene), water soluble dam materials, lubricants, NDT penetrant naterials and couplants, which contact stainless steel or nickel alloy surfaces shall not con *nin lead, zinc, copper, mercury, cadmium and other low melting point metals, their alloys or compounds, as basic and essential chemical constituents.
Prescribed maximum levels of water leachable chlorides, total halogens, and sulphur and its compounds shall be imposed on expendable products.
- 3) With regard to Section 5 of ANSI N45.2.1 - 1973 titled Installation Cleaning: The recommendation that local rusting on corrosion resistant alloys be removed by mechanical methods is interpreted to mean that local rusting may be removed mechanically, but the use of other removal means is not precluded.
Page 11 of 36 Appendix A Pev. 16 OQAMR16 l
NRC Regulatory Guide ~1137 (Continued):
- 4) For operations phase maintenance and modification activities, the licensee shall control these activities under this Operational Quality Assurance Program. The licensee shall comply with the Regulatory Position established in this regulatory guide in that quality assurance programmatic 7 administrative requirements included therein (subject to the stated clarifications) shall apply to these maintenance and modification activities even though such requirements may not have been in effect originally. Technical requirements associated with the maintenance or modification shall
, be the original requirements or better (e.g., code requirements, {
material properties, design margins, manufacturing processes, and I inspection requirements).
- 5) With regard to Section 1.4 of ANSI N45.2.1 - 1973 titled Definitions: Definitions in this standard which are not included in
, ANSI N45.2.10 shall be used; all definitions which are included in ANSI N45.2.10 shall be used as clarified in the licensee's commitment to Regulatory Guide 1 74.
- 6) with regard to Section 9 of ANSI N45.2.1 - 1973 titled Records: The licensee shall maintain records in accordance with and to meet the requrrements of Policy 7 of the OQAM and ANSI N45.2.9 as specified in Appendix A of the OQAM.
- 7) Throughout this Standard, references are made to cleanness associated with initial installation. When this standard is used for operations, qualified supervisory raintenance personnel determine what itens within a particular cleanness level are appropriate. As an example, the reactor internals are initially classified as Level B. Section 3.1.2 requires this cleanness level tv have " metal clean" surfaces and either a visual inspection or dry white-cloth wipe. After use in the reactor coolant system, the l licensee does not intend to clean a component until it has a bright
" metal clean" surface, nor do we (from an ALARA and accessibility considerations) intend to perform a dry white-cloth wipe.
Coaponents which have been removed from plant systems of established cleanliness levels may be considered to be of the same cleanliness as the system from which they were removed. Such components need not be reeleaned prior to reinstallation provided that measures are taken to prevent degradation of the previously existing state of cleanliness.
NRC Regulatory Guide 1.38 " Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants" (Rev. 2, 5/77) - Endorses ANSI N45.2.2 - 1972.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
Page 12 of 36 Appendix A Rev. 16 OQAMR16
. . _ _. _ _ _ _ . _ _ _ ~ _ _.
NRC Regulatory Guide"l'.38 (Continued):
- 1) With regard to Section 1.4 of ANSI N45.2.2 - 1972 titled Definitions: Definitions in this standard which are not included in ANSI N45.2,10 will be used; all definitions which are included in ANSI N45.2.10 will be used as clarified in the licensee's commitment to Regulatory Guide 1.74.
l
' 2) With regard to Section 2.1 of ANSI N45.2.2 - 1972 titled Planning:
(first sentence) The specific items to be governed by the standard shall be identi fied on the Q List. However, the standard (as modified by the clarifications in Appendix A of the OQAM) is part of the Operational Quality Assurance Program and will, therefore, be applied to those structures, systems, and components which are included in that program.
- 3) With regard to Secti,on 2.3 of ANSI N45.2.2 - 1972 titled Results:
,The specific methods for performing and documenting tests and inspections are given in Policies 10 end 11 of the Operational Quality Assurance Manual. The requirements in these policies will be implemented in lieu of the general requirements he:e.
- 4) With regard to Section 2.4 of ANSI N45.2.2 - 1972 titled Personnel Qualifications: Specific requirements for personnel qualifications and training are set forth in Policy 2 and in the commitments to training standards in Appendix A of the Operational Quality Assurance Manual. These requirements will be implemented in lieu of the general requirements stated in this section.
- 5) With regard to Section 2.7 of ANSI N45.2.2 - 1972 titled Classification of Itenm: The licensee may choose not to explicitly use the four level classification system. However, the specific requirements of the standard that are appropriate to each class will generally be applied to the items suggested in each classification and to similar items.
- 6) With regard to Section 3.2 of ANSI N45.2.2 - 1972 titled Level of Packaging, the following alternates are provided for the indicated subparts:
(1) With regard to Section 3.2.1 - 1972 titled Level A Items: As an alternate to the requirements for packaging and con-tainerizing items in storage to control contaminants (Items (4) and (5)), the licensee may choose a storage atmosphere which is free of harmful contaminants in concentrations that could produce damage to stored items. Similarly 'for Item (7)) the licensee may obviate the need for caps and plugs with an appropriate storage atmosphere, and may choose to protect weld end preparations and threads by controlling the manner in which the items are stored. These clarifications apply whenever itene (4), (5) or (7) are subsequently referenced and to Section 3.5.1 titled Caps and Plugs and Section 3.4 titled Methods of Preservation.
j Page 13 of 36 Appendix A Rev. 16 l
OQAMR16
, - . ~. ..- ,-. . _ - - . . _ . - . . - . - - _ . - - - -
NRC Regulatory Guide "1138 - Section 6 (Continued):
(2) With regard to Sections 3.2.2, 3.2.3, and 3.2.4 titled Level B Items, Level C Items, and Level D Items, respectfully: As an alternate to the requirements for protecting items in storage by capping, plugging, or sealing cpenings into them and protecting weld end preparations from corrosion and ;
physical damage (3.2.2, Item (1) in 3.2.3 and Item (7) in '
3.2.1, and Item (2) in 3.2.4), the licensee may obviate the need for caps,-plugs, tape, and adhesives with an appropriate storage atnesphere and may choose to protect weld end preparations and threads'by controlling the manner in which the items are stored. These clarifications apply whenever Section 3.2.2, Item (1) in Section 3.2.3 and Item (7) in ;
Section 3.2.1, or Item (2) in Section 3.2.4 are subsequently 1 referenced and to Section 3.5.1 titled Caps and Plugs and I Section ?.4 titled Methods of Preservation.
7). With regard to.Section 3.3 of ANSI N45.2.2 - 1972 titled cleaning: 1 (Third sentence) The licensee interprets " documented cleaning methods to allow generic cleaning procedures to be written which !
are implemented, as necessary, by trained personnel. Each particular cleaning operation may not have an individual cleaning procedure, but the generic procedures will specify which methods of cleaning or which type (s) of solvent may be used in a particular application.
- 8) -With regard to Section 3.4 of ANSI N45.2.2 - 1972 titled Methods of Preservation: .(First sentence) The licensee will comply with these
! requirements subject to the clarifications of Section 3.2.1 (4) and ;
(5) above,.and the definition of the phrase " deleterious corrosion" to mean that corrosion which cannot be subsequently removed and which adversely affects form, fit, or function.
- 9) With regard to Section 3.6 of ANSI M45.2.2 - 1972 titled Barrier and Wrap Material and Desiccants: This section requires the use of j nonhalogenated materials in contact with austenitic stainless steel. Refer to Regulatory Guide 1.37 above for the licensee's position.
- 10) With regard to Section 3.7.1 of ANSI N45.2.2 - 1972 titled Containers: Cleated, sheathed boxes may Le used up to 1000 lbs.
rather than 500 lbs. as specified in 3.7.l(1) . This type of box is
- i. safe for, and has been tested for, loads up to 1000 lbs. Other national standards allow this (see Federal Specification PPP-B-601). Special qualification testing may be required for loads'above 1000 lbs.
- 11) With regard to Section 3.7.2 of ANSI N45.2.2 - 1972 titled Crates and Skids: Crates or skids will be used on equipment with a gross weight of 500 lbs. or more. Skids or runners will normally be fabricated from 2 X 4 inch nominal lumber size, minimum, and laid flat except where this is impractical because of the small dimensions of the container. If forklift handling is required,
- minimum floor clearance for forklift tines will be provided.
J i
Page 14 of 36 Appendix A Rev. 16 (L OQAMR16
, . _ ~ .,-
NRC Regulatory Guide ~i".38 (Continued):
- 12) With regard to Section 4.2.2 of ANSI N45.2.2 - 1972 titled Closed Carriers: The use of fully enclosed furniture vans, as recommended in (2), of this section is not considered a requirement. The licensee will assure adequate protection from weather or other i environmental conditions by a combination of vehicle enclosure and I item packaging.
- 13) With regard to Sections 4.3, 4.4 and 4.5 of ANSI N45.2.2 - 1972 titled, respectively, Precautions During Leading and Transit, l Identification and Marking, and Shipment from Countries outside the i United States: The licensee will comply with the requirements of these sections subject to the clarifications taken to other sections which are referenced therein. I l
- 14) With regard to Section 5.2.1 of ANSI N45.2.2 - 1972 titled Shippinq !
Damage Inspection: Warehouse personnel will normally visually scru-tinize incoming shipments for damage of the types listed in this l section, this activity is not necessarily performed prior to '
unloading. Since all required items receive the item inspection of Section 5.2.2, separate documentation of the shipping damage inspection is not necessary. Release of the transport agent after unloading and the signing for receipt of the shipment may be all of the action taken to document completion rf the shipping damage inspection. Any nonconformances noted will be documented and dispositioned as required by Policy 15 of the Operational Quality Assurance Manual. The person performing the visual scrutiny during unloading is not considered to be performing an inspection function as defined under Regulatory Guide 1.74; therefore, while he will be trained to perform this function, he may not be certified (N45.2.6) as an inspector.
- 15) With regard to Section 5.2.2 of ANSI N45.2.2 - 1972 titled Item Inspection: The secor.d division of this subsection requires six additional inspectioa activities if an item was not inspected or examined at the source. The licensee will consider that a source inspection has been conducted if the supplier of the item is required to comply with ANSI N45.2.2 for the purchased item and if the supplier's program has been audited and found acceptable in the area (i.e., the supplier performs a source inspection of his supplier or conducts a receipt inspection that includes, as applicable, the six additional items listed).
- 16) With regard to Section 6.1.2 of ANSI N45.2.2 - 1972 titled Levels of Storage: Subpart (2) is replaced with the following:
Page 15 of 36 Appendix A Rev. 16 OQAMR16
~ . ~ , ~ . . ~ . .. - .-. - - . . - - - - - - - - - . . - - . - . - -
~
NRC Regulatory Guide l~.'38 - Section 16 (Continued):
(2) Level B items shall be stored within a fire resistant, weathe; tight, .and well ventilated building or equivalent enclosure. This building shall be situated and constructed so that it will not normally be subject to flooding;-the
. floor shall be paved or equal, and well drained. If any outside~ waters should come in contact'with stored equipment, such equipment will be labeled or. tagged nonconforming, and then the nonconformance document will be processed and evaluated in accordance with Policy 15. Items shall be placed on pallets or shoring or shelves to permit air circulation. The building shall be provided with heating and temperature control or their equivalent to reduce condensation and corrosion. Minimum temperature shall be 40'F and maximum-temperature shall be 140'F or. less if so stipulated by a manufacturer.
- 17) With regard to Section 6.2.1 of ANSI N45.2.2 - 1972 titled Access to Storage Areas: Items which fall within the Level D classification of the standard will ce stored in an area which may be posted to limit access, but other positive controls such as fencing or guards will not normally be'provided.
- 18) With regard to Section 6.2.4 of ANSI N45.2.2 - 1972 titled Storage of Food and Associated Items: The sentence is replaced with the following: "The use or storage of food, drinks, and salt tablet dispensers in any storage area shall be controlled and shall be limited to designated areas where such use or storage is not deleterious to stored items."
- 19) With regard to Section 6.2.5 of ANSI N45.2.2 - 1972 Litled Measures j to Prevent Entrance of Animals: The sentence is replaced with the i
following: " Warehouse personnel shall be alert to detect evidence of rodents or small animals in indoor storage areas. If any such evidence is detected, a survey or inspection will be utilized to determine the extent of the damage; exterminators or other appropriate measures shall be used to control these animals to minimize possible contamination and mechanical damage to stored material."
- 20) With regard to Section 6.3.3 of ANSI N45.2.2 - 1972 titled Storage of Hazardous Material: The sentence is replaced with the following:
" Hazardous chemicals, paints, solvents, and other materials of a like nature shall be stored in approved cabinets or containers which are not in close proximity to installed systems required for L safe shutdown."
l l: 21) With regard to Section 6.4.2 of ANSI N45.2.2 - 1972 titled Care of l Items: The following alternates are provided for .ndicated subpart:
- (1) " Items in storage shall have all required covers, caps, plugs or other closures intact, or shall be elevated as required to
, allow.for proper drainage. Methods used to seal openings shall be in accordance with Section 3 of this standard.
Covers removed for internal access at any time .or any reason
! shall be immediately replaced and resealed after completion of the purpose for removal."
i 4
Page 16 of 36 Appendix A Rev. 16 e
- . - , - _, - - w .
NRC Regulatory Guide 3538 (Continued):
(5) " Space heaters in electrical equipment shall be energized unless a documented engineering evaluation determines that such space heaters are not required."
(6) "Large (greater than or equal to 50 HP) rotating electrical equipment shall be given insulation resistance tests on a scheduled basis unless a documented engineering evaluation determines that such tasts are not required."
(7) " Prior to being placed in storage, rotating equipnent weighing over approximately 50 pounds shall be evaluated by engineering personnel to determine if shaft rotation in storage is required; the results of the evaluation shall be documented. If rotation is required, it shall be performed at specified intervals, be documented, and be conducted so !
that parts receive a coating of lubrication where applicable l and so that the shaft does not come to rest in the same position occupied prior to rotation. For long shafts or heavy equipment subject to undesirable bowing, shaft ,
orientation after rotation shall be specified and obtained." l
- 22) With regard to Section 6.5 of ANSI N45.2.2 - 1972 titled Removal of Items from Storage: The licensee does not consider the last sentence of this section to be applicable to the operations phase ]
due to the relatively short period of time between installation and ;
use. The first sentence of the Section is replaced with: " The j licensee will develop, issue, and implement a procedure (s) which I cover (s) the removal of items from storage. The procedure (s) will '
assure that the status of all material issued is known, controlled, j and appropriately dispositioned." l
- 23) With regard to Section 6.6 of ANSI N45.2.2 - 1972 titled Storage Records: The licensee will comply with the requirements of this section with the clarification that, for record purposes, only the access of personnel without key cards into indoor storage areas shall be recorded. Unloading or pick-up of material shall not be considered " access," nor shall inspection by NRC or other i regulatory agents, nor shall tours by non-licensee employees who are accompanied by licensee employees.
l
[ 24) With regard to Section 7.3 of ANSI N45.2.2 - 1972 titled Hoisting l
Equipment: Re-rating of hoisting equipment will be considered only when absolutely necessary. Prior to performing any lift above the load rating, the equipment manufacturer must be contacted for his l approval and direction. The manufacturer must be requested to l
supply a document granting approval for a lindted number of lif ts at the new rating and any restrictions involved, such as modifications to be made to the equipment, the number of lifts to be made at the new rating, and the test lift load. At all times
- v. the codes governing re-rating of hoisting equipment must be observed.
Page 17 of 36 Appendix A Rev. 16 I I
OQAMR16 l
NRC Regulatory Guide 1.39 " Housekeeping Requirements for Water-Cooled Nuclear Power Plants" (Rev. 2, 9/77) - Endorses ANSI N45.2.3 - 1973.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) For operations phase maintenance and modification activities, the licensee shall control these activities under this Operational Quality Assurance Program.
The licensee shall comply with the Regulatory Position established in this regulatory guide in that quality assurance programmatic / administrative requirements included therein (subject to the clarifications in Item 2 below) shall apply to these maintenance and modification activities even though such requirements may not have been in effect originally. Technical requirements associated with the maintenance or modification shall be the original requirements or better (e.g., code requirements, material properties, design margins, manufacturing processes, and inspection requirements).
- 2) Specific clarifications for ANSI N45.2.3 - 1973 are indicated for specific sections below.
Section 1.4 - Definitions: Definitions in this standard which are not included in ANSI N45.2.10 will be used; all definitions which are included in ANSI M45.2.10 will be used as clarified in the licensee's commitment to Regulatory Guide 1.74.
Section 2.1 - Planning: The licensee may choose not to utilize the five level zone designation system, but will utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with company policy in the areas of housekeeping, plant and personnel safety, and fire protection.
Cleanliness will be maintained, consistent with the work being per-formed, so as to prevent the entry of foreign material into safety-related systems. This will include, as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary, (e.g., the opening is larger than the tools being used) control of personnel, tools, equipment, and supplies will be established when major portions of the reactor system are opened for inspection, maintenance or repair.
l Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
Section 2.2 - Procedures and Instructions: Appropriate procedures will be written and implemented.
Section 3.1 - Control of GGNS Area: Not applicable to the operations phase.
Section 3.2 - Control of Facilities: The licensee may choose not to 4
utilize the five-level zone designation system, but will utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with company policy in the areas of
. housekeeping, plant and personnel safety, and fire protection.
Page 18 of 36 Appendix A Rev. 16 OQAMR16
~
NRC Regulatory Guide 1".39 (Continued):
Cleanliness will be maintained, consistent with the work being per-formed, so as to prevent the entry of foreign material into safety-related systems. This will include, as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary, (e.g., the opening is larger than the tools ,
being used) control of personnel, tools, equipment, and supplies l will be established when major portions of the reactor system are :
opened for inspection, maintenance or repair. I i
Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
Section 3.3 - Materials and Equipment: The first paragraph in this section is not applicable to the operations phase.
Section 3.4 - Construction Tools, Supplies, and Equipment: Not ap- I plicable to the operations phase. '
section 3.5 - Surveillance, Inspection, and Examination:
Subparagraph (1) is not applicable to the operations phases (2),
(3) and (4) will be implemented.
Section 4 - Records: The requirements of Policy 17 and ANSI N45.2.9 as set forth in Appendix A of the Operational Quality Assurance Manual shall be implemented in lieu of the requirements of this section.
Section 3.2.3 - Fire Protection and Prevention: The accepted Fire Protection Plan shall be used in lieu of the general requirements in this section.
NRC Regulatory Guide 1.58 " Qualifications of Nuclear Power Plant Inspection, l Examination, and Testing Personnel". (Rev. 1, 9/80) - Endorses ANSI N45.2.6 1978.
The operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) The licensee may choose not to apply the requirements of this guide i to those personnel who are involved in day-today operations, surveillance, maintenance and certain technical and support -
services whose qualifications are controlled by Technical Specifications, Appendix 16B of the UFSAR or other Operational Quality Assurance Program commitment requirements, i
i
- 2) With regard to Section 1.2 of ANSI N45.2.6 - 1978 titled l Applicability : The third paragraph requires that the standard be used in conjunction with ANSI N45.2; the licensee no longer specifically commits to ANSI N45.2 in the Operational Quality Assurance Program. The fourth paragraph requires that the standard be imposed on personnel other than licensee employees; the applicability of the standard to suppliers will be documented and applied, as appropriate, in the procurement documents for such suppliers.
Page 19 of 36 Appendix A Rev. 16 OQAMR16 9 - -
~~
NRC Regulatory Guide l.58 (Continued):
3 )' With regard to Section 1.4 of ANSI N45.2.6 - 1978 titled Definitions: Definitions in this standard which are not included in ANSI N45 3 2.10 will be used; all definitions which are included in ANSI N45.2.10 will be used as clarified in the licensee's commitment to Regulatory Guide 1.74.
- 4) With regard to Section 2.5 of ANSI N45.2.6 - 1978 titled Physical:
The licensee will implement the requirements of this section with the stipulation that, where no.special physical characteristics are ,
required, none will be specified. .The converse is also true: If no l
special physical requirements are stipulated by the licensee, none are considered necessary.
)
- 5) With regard to Section 3.5 of ANSI N45.2.6 ,1978 titled Education and Experience - Recommendations: The licensee reserves the right to use personnel who do not meet the experience requirements of this section but have shown capability through training and testing or capability demonstration.
- 6) With regard to Section 1.2 of ANSI N45.2.6 - 1978, titled Applicability, Paragraph 2: The licensee reserves the right to use later editions of ASNT contained with 10CFR50.55a approved ASME editions or addenda.
NRC Regulatory Guide 1.64 " Quality Assurance Requirements for the Design of Nuclear Power Plants" (Rev. 2, 6/76) - Endorses ANSI N45.2.ll - 1974.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) For operations phase maintenance and modification activities, the licensee shall control these activities under this operational Quality assurance Program. The licensee shall comply with the Regulatory Position established in this regulatory guide in that quality assurance programmatic / administrative requirements included therein (subject to the clarifications listed below) shall apply to these maintenance and modification activities even though such requirements may not have been in effect originally.
Technical requirements associated with maintenance and modifications shall be the original requirements or better (e.g.,
code requirements, material properties, design margins, manufacturing processes and inspection requirements).
I
- 2) With regard to Paragraph C.2 (1) of Regulatory Guide 1.64: If in an exceptional circumstance the designer's immediate supervisor is the only technically qualified individual available, this review can be conducted by the supervisor, providing that: (a) the other provisions of the regulatory guide are satisfied, and (b) the justification is individually documented and approved in advance by the supervisor's management, and (c) quality assurance audits cover frequency and effectiveness of use of supervisors as design
. verifiers to guard against abuse.
Page 20 of 36 Appendix A Rev. 16 OQAMR16
i NRC Regulatory Guide 'i'.64 - (Continued) :
- 3) With regard to Section 1.4 of ANSI N45.2.11 - 1974 titled Definitions: Definitions in this standard which are not included in ANSI N45.2.10.will be used; all definitions which are included in ANSI N45.2.10 will be used as clarified in the licensee's commitment to Regulatory Guide 1.74.
t
- 4) With regard to Sections 2.1 (last paragraph), 2.2 (Items 12 and 13), Sectior 9, and Section 11 (including Subsections 11.1 through 11.7) of ANSI N45.2.11 - 1974: The licensee's audit program will be implemented in accordance with and to meet the requirements of:
ANS1 N45.2.12 as endorsed in Appendix A; Policies 2, 3, 16 and 18 '
of the Operational Quality Assurance Manual, and the requirements of the UFSAR, Appendix 16B, in lieu of the audit requirements stated in the referenced sections.
- 5) With regard to Section 5.2.4 of ANSI N45.2.11 - 1974 titled Documentation: For the documentation of interdisciplinary design reviews, there must be documented evidence of the acceptability of design documents or portions thereof, prior to release (material, stress, physics, mechanical, electrical, concrete, etc. ) . The signature or initials of those who determine the acceptability of the design relative to their respective disciplinary area of concern should be on the document or on a separate form traceable to the document. A document that indicates the reviewer's comments need not be retained. .
~6) The licensee does not require the SAR te ba a design document.
However, if the SAR contains any design or design input that has not been previously documented, reviewed and approved in accordance
[ with the requirements contained in the OQAM or another approved design control quality assurance program and if the SAR is used as 4 a design document during the design process, that specific I information must be controlled and verified in accordance with the !
commitments here and Policy 3 of the OQAM.
- 7) With regard to Section 6.1 of ANSI N45.2.11 - 1974 titled General:
-The third paragraph in this section stipulates certain requirements relative "the results of design verification". The licensee may comply with these requirements by having the reviewer (s) sign and date an appropriate document providing the following conditions are also met:
t a) Documented engineering / design procedures are established which cover the extent of design review.
b) The procedures identify the duties of the reviewer and the
- extent of this responsibility for which he attests with his
! signature.
c) The procedures specify the extent of documentation necessary for the type of design verification applicable to the i complexity of the design.
I I L
Page 21 of 36 Appendix A Rev. 16 t
. - .- . . . . - . - - - - . - . . - - - - ~ . - - _ . ~ -~.-.~ ..~.
! 4 ,
l 1
i i l l
1 l
NRC Regulatory Guide'I.64 - Section'7 (Continued):
1 d)' The signature and date is affixed in accordance with the l procedures.
The licensee shall also perndt initials to be used in lieu of the signature required above if a file is maintained to correlate characteristic initials versus individuals such that each set of !
characteristic initials can be traced to an individual. This
~
I correlation must be readily available to NRC inspector whenever the document is being used.
! 8) The timing of design verification is not mentioned in the standard.
The. licensee shall perform verification in a timely manner. If other than by qualifications testing of a prototype or lead production unit, verification should be completed prior to release for procurement, manufacturing or construction or release to another organization for use-in other design activities. In those cases where this timing cannot be met, the design verification may be deferred providing that the justification for this action is documented and the unverified portion of the design output document and all design output documents, based on the unverified data, are l appropriately identified and controlled. Cite GGNS activities i
associated with a design or design change shall not proceed without '
verification past the point where the installation would become i irreversible without extensive demolition and rework. In all I cases, the design verification shall be completed prior to relying upon the component, system, or structure to perform its safety-related function.
- 9) With regard to Section 10 of ANSI N45.2.ll - 1974 titled Records:
The' licensee shall maintain records in accordance with and to meet the requirements of Policy 17.0 of the OQAM and ANSI N45.2.9 as l specified in Appendix A. The additional requirements of the first sentence of the second paragraph in this section shall also be met.
l l -- NRC Regulatory Guide 1.74 " Quality Assurance Terms and Definitions" (2/74)
Endorses ANSI N45.2.10 - 1973.
The operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) The licensee reserves the right to define additional words or phrases which are not included in this Standard. Such additional I
definitions will be documented in appropriate procedures and/or in attachments / appendices to the Quality Assurance Procedure Manual, or in Policies of the Operational Quality Assurance Manual. See Policy 2, Paragraph 2.5.8.
4 4
l-Page 22 of 36 Appendix A Rev. 16 00AMR16
~
NRC Regulatory Guide 1I74 (Continued):
i
- 2) The licensee reserves the right to add additional words/ phrases to those definitions listed in this standard and other ANSI standards as necessary for clarification provided such clarification does not change the intent of the definition. Additionally, the licensee considers the point of application to be the procedure in which the word / phase is defined and used. Also, the licensee considers words/
phrases defined in procedures, which are not otherwise defined, to be applicable only to the activity controlled under the procedure.
In addition to the standard's definition of " Inspection", the licensee will use the following: " Inspection (When used to refer to activities that are NOT performed by Quality Programs' personnel) -
Examining, viewing closely, scrutinizing, looking over or otherwise checking activities. Personnel performing these functions are not necessarily certified to ANSI N45.2.6."
When the licensee intends for inspections to be performed in accordance with the Operational Quality Assurance Program by personnel certified as required by that program and for activities defined by " Inspection" in ANSI N45.2.10, appropriate references to Quality Programs which will perform the activity or to quality assurance procedures / instructions to be used for performing the activity will be made. If such references are not made, inspec-tions are to be considered under the additional definition given above.
Inspections to meet the intent of IOCFR50 Appendix B are described in Policy 10 of the OQAM.
- 3) In addition to the standard's definition of " procurement documents",
the licensee will utilize the definitions given in ANSI N45.2.13 and in Regulatory Guide 1.74. The compound definition is given as follows: " Procurement documents - Contractually binding documents i that identify and define the requirements which items or services must meet in order to be considered acceptable by the purchaser.
They include documents which authorize the seller to perform services or supply equipment, material or facilities on behalf of the purchaser (e.g., contracts, letters of intent, work orders, purchase orders, or proposals and their acceptance, drawings, specifications, or instructions which define requirements for
)
purchase)." l l
- 4) " Program Deficiencies" (Not defined in ANSI N45.2.10, but used and defined in ANSI N45.2.12) - Failure to develop, document or implement effectively any applicable element of the Operational Quality Assurance Program.
- 5) " Quality Assurance Program Requirements" (Not defined in ANSI N45.2.10 but used and defined differently in ANSI N45.2.13) Those ,
individual requirements of the Operational Quality Assurance Program l which, when invoked in total or in part, establish the requirements !
l of the quality assurance program for the activity being controlled.
Although not specifically used in the Operational Quality Assurance Program, ANSI N45.2 may be imposed upon the licensee's suppliers.
1 i
Page 23 of 36 Appendit A Rev. 16
I I
i l
l
~
NRC Regulatory Guide 1!74 (Continued):
- 6) This section deleted in Revision 4.
- 7) " Independent Verification" - Verification by an individual other than the person who performed the operation or activity being verified that required actions have been completed. Such verification will not require confirmation of the identical action when other indications provide assurance'or indication that the prescribed activity is in fact complete. Examples include, but are not limited to verification of a breaker opening by observing remote breaker indication lights; verification of a set point (made with a voltmeter or ammeter for example) by observing the actuation of status or indicating lights at the required panel-meter indicated value, verification that a valve has been positioned by observing the starting or stopping of flow on meter indications or by remote value positions indicating lights.
- 8) The section deleted in Revision 14.
- 9) "Special Processes" - Processes which are controlled and monitored ;
in accordance with approved procedures where required quality levels cannot be assured by inspection of the processed articles alone, or where it is more effective to control the process than inspect the completed article.
- 10) " Permanent Plant Device" (when used with respect to instrumentation)
A device, permanently installed, which functions as a part of a system and is used for monitoring a process variable in the plant.
- 11) " Concurrence" (when used with respect to and in association with a review activity) is defined to mean: (1) a review of a document or portion thereof under consideration; (2) a conclusion that all pertinent and necessary requirements (within the purview of the one performing the review) have been included; and, (3) essential agreement and belief that the manner in which the requirements have been addressed will produce the intended results.
- 12) " Audits" (defined in ANSI N45.2.10 but used and defined differently in ANSI N45.2.12) Audit - A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation e' objective evidence, that applicable elements of the quality assurance program have been developed, documented and effectively implemented in accordance with specific l
requirements. An audit should not be confused with surveillance or inspection for the sole purpose of process control or product acceptance.
l NRC Regulatory Guide 1.88 " Collection, Storage and Maintenance of Nuclear l Power Plant Quality Assurance Records" (Rev. 2, 10/76) - Endorses ANSI N45.2.9 -
l 1974.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
4 Page 24 of 36 Appendix A Rev. 16 OQAMR16
~
NRC Regulatory Guide E 88 (Continued):
- 1) With regard to Section 3.2.1 of ANSI N45.2.9 - 1974 titled Generation of Quality Assurance Records: The phrase " completely filled out" is clarified to mean that sufficient information is recorded to fulfill the intended purpose of the record, and it is considered complete. Only complete records are considered QA !
records.
1
- 2) with regard to Section 3.2.2 of ANSI N45.2.9 - 1974 titled Index The phrase "an index" is clarified to mean a collection of documents '
or indices which, when taken together, supply the information l attributed to "an index" in the standard. '
The specific location of a record within a storage area may not be delineated (e.g., The specific location within a computer record file may not be constant. Further, the licensee may utilize a computer assisted random access, filing system where such location j could not be readily " documented, nor would such a location be
" relevant.") The storage location will be delineated, but where file j locations change with time, the specific location of a record within that file may not always be documented.
- 3) With regard to Section 4.2 of ANSI N45.2.9 - 1974 titled Timeliness:
The licensee's contractual agreement with its contractors and suppliers will constitute fulfillment of the requirements of this section.
- 4) With regard to Section 5.4 of ANSI N45.2.9 - 1974 titled Preservation: The following clarification is substituted for the current subsection 5.4.2: " Records shall not be stored loosely. They shall be secured for storage in file cabinets or on shelving in containers."
The following clarification is substituted for the current subsection 5.4.3: " Provisions shall be made for special processed records (such as radiographs, photographs, negatives, microfilm and magnetic media) to prevent damage from excessive light, stacking, electromagnetic fields, temperature and humidity as appropriate to the record type.
- 5) With regard to Section 5.5 of ANSI N45.2.9 - 1974 titled Safekeeping: Routine general office and nuclear site security systems and access controls are provided; no special security
~
systene shall be established for record storage areas.
- 6) With regard to Section 5.6 of ANSI N45.2.9 - 1974 titled Facility:
This section provides no distinction between temporary and permanent facilities. To cover temporary storage, the following clarification L
is added: " Quality Assurance records will be stored in one-hour fire l rated file cabinets. In general, records shall not be maintained in l temporary storage for more than three months after completion. Any exceptions to this requirement must be evaluated and approved by the Director, Quality; a list of all such excepted records shall be maintained and available for NRC review. Exceptions may include records needed on a continuing basis for an extended period of time (e.g., personnel qualification and training records, equipment history records) and records which are cumulative in nature (e.g. , nonconforming item logs) . "
i l
- Page 25 of 36 Appendix A Rev. 16 l OQAMR16 l
l
NRC Regulatory Guide'1!88 (Continued):
Paragraph 4, subsection 3 is clarified to require a two-hour minimum fire rating to be consistent with the 1979 version of the standard and NRC Criteria for Record Storage Facilities (Guidance-ANSI N45.2. 9, Section 5. 6) issued 7/1/80.
Paragraph 4, Subsection 9 is clarified to read: "No pipes or pene-trations except those providing fire protection, lighting, tempera-ture/ humidity control, or communications are to be located within the facility. All such penetrations shall be sealed or dampered to comply with a minimum two-hour fire protection rating."
- 7) With regard to Section 5.3 of ANSI N45.2.9 - 1974 titled Storage: l The first sentence is clarified by stating that an individual shall ;
be designated and assigned the responsibility for enforcement of i written record storage procedures for each record storage location. '
The term " custodian" may or may not be used as part of that j designation. I l
l NRC 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" (Rev. 1, 4/76) - Endorses ANSI N45.2.5 1974.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) For operations phase maintenance and modification activities, the licensee shall control these activities under this Operational Quality Assurance Program. The licensee shall comply with the Regulatory Position established in this regulatory guide in that grality assurance programmatic / administrative requirements included therein shall apply to these maintenance and modification activities even though such requirements may not have been in effect originally. Technical requirements associated with maintenance and modifications shall be the original requirements er better (e.g.,
code requirements, material properties, design margins, manufacturing processes and inspection requirements).
- 2) With regard to Section 1.2 of ANSI N45.2.5 - 1974 titled Applicability: The first sentence in this section is not applicable l to the operations phase. The licensee shall comply with the' third sentence in this section with the clarifications that "importance of the item or service involved" is interpreted to mean those to which the Operational Quality Assurance Manual applies, and the extent of coverage shall be defined by supervisory maintenance personnel by the way in which they implement the other r,equirements of this standard.
In the second paragraph of this section, the licensee shall substitute the words " maintenance and modification" for the word
" construction" as the modifier of " procedures".
Page 26 of 36 Appendix A Rev. 16 OQAMhl6 i
I
. - - . . -. ~ ~. -. - ~- -- . . - - - - _ _ , - - - - - . - - _ .
NRC Regulatory Guide "i!94 ' (Continued) :
(
- 3) With regard to section 1.3 of ANSI N45.2.5 - 1974 titled Responsibility: This section's requirements are met by the definitions for positions and the organizational responsibilities outlined in the Technical Specifications, Policy 1 of the OQAM and the position descriptions for plant personnel.
- 4) With regard to Section 1.4 of ANSI N45.2.5 - 1973 titled Definitions: Definitions in this standard which are not included in ANSI N45.2.10 shall be used: All definitions which are included in ANSI N45.2.10 shall be used as' clarified in the licensee's commitment to Regulatory Guide 1.74.
- 5) With regard to Section 2:1 of ANSI N45.2.5 - 1974 titled Planning:
1 Planning requirements, when necessary, shall be incorporated into maintenance and modification procedures.
< 6) With regard to Section 2.5.2 of ANSI N45.2.5 - 1974 titled I
Calibration and control: The last sentence of this sectica requires that all items inspected with M&TE which is found to be out of cali-bration shall.be considered unacceptable. The licensee will comply L with an alternate which will require evaluation to determine the va-lidity of previous measurements. This alternative is consistent with ANSI N45.2.4, Section 2.5.2; ANSI N45.2.1, Section 2.5.2; ANSI N45.2.8, Section 2.8.21 ANSI N45.2.13, Section 7.4.2, and ANSI N18.7, Section 5.2.16.
- 7) With. regard to Section 5.5 of ANSI N45.2.5 - 1974 titled Welding:
The licensee will comply with inspection requirements of the applicable welding codes identified in the UFSAR and any exceptions thereto.
l 8) With regard to table 8 of ANSI N45.2.5-1974 titled Required In-l Process Tests: The licensee complies with the requirement of testing grout for compressive strength with the following exception: for prepackaged shelf item, non-shrink grout products compressive strength tests are performed once on each batch of non-shrink grout received, rather than each day grout is placed.
NRC Regulatory Guide 1.116 " Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems" (Rev. O-R, 6/76)
Endorses ANSI N45.2.8 - 1975.
The Operational Quality Assurance Program complies with the requirements- of j this guide with the following clarifications:
!- 1) For operations phase maintenance and modification activities, the i licensee shall control these activities under this Operational Quality Assurance Program. The licensee shall comply with the Regulatory Position established in this regulatory guide in that quality assurance programmatic / administrative requirements included therein shall apply to these maintenance and modification activities e
even though such. requirements may not have been in effect originally. Technical requirements associated with maintenance and j modifications shall be the original requirements or better (e.g.,
code requirements, material properties, design margins, manufacturing processes, and inspection requirements).
?
I l.
Page 27 of 36 Appendix A Rev. 16 OQAMR16
- 2 i -, .
NRC Regulatory Guide 17116 (Continued):
~
- 2) With regard to Section 1.1 of ANSI N45.2.8 - 1975 titled scope: The last paragraph of this section is not applicable to the operations phase. The applicable portions of the requirements of this standard shall also be applied af ter fuel load; therefore, the last twenty-two words in the last sentence of the second paragraph under this section are also not appropriate to the operations phase.
- 3) With regard to Section 1.2 of ANSI N45.2.8 - 1975 titled Applicability: The first sentence in this section is not applicable !
to the operations phase. The licensee shall comply with the third j sentence in this section with the clarifications that "important me- l chanical systems to be, covered" is interpreted to mean those to {
which the OQAM applies, and the extent of coverage" shall be defined by supervisory maintenance personnel by the way in which they implement the other requirements of this standard.
- 4) With regard to Section 1:3 of ANSI N45.2.8 - 1975 titled Responsibility : This section's requirements are met by the I definitions for positions and the organizational responsibilities outlined.in the Technical Specifications, Policy 1 of the OQAM and the position descriptions for plant personnel.
- 5) With regard to Section 1.4 of ANSI N45.2.8 - 1975 titled Definitions: Definitions in this standard which are not included in ANSI N45.2.10 shall be used: All definitions which are included in ANSI N45.2.10 shall be used as clarified in the licensee's commitment to Regulatory Guide 1.74.
- 6) With regard to Section 2.1 of ANSI N45.2.8 - 1975 titled Planning:
Planning requirements, when necessary, shall be incorporated into maintenance and modification procedures.
NRC Regulatory Guide 1.123 " Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants" (Rev. 1, 7/77)
Endorses ANSI N45.2.13 - 1976.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) With regard to Section 1.3 of ANSI N45.2.13 - 1976 titled Definitions: With two exceptions (procurement document and quality assurance program requirements) definitions in this standard which are not included in ANSI N45.2.10 will be used; all definitions which are included in ANSI N45.2.10 will be used as clarified in the licensee's commitment to Regulatory Guide 1.74. The two exceptions are defined in Appendix A of the OQAM under Regulatory Guide 1.74.
- 2) With regard to Section 1.2.2 of ANSI N45.2.13 - 1976 titled Purchaser's Responsibilities: Item c is one of the options which may be used by the licensee to assure quality; however, any of the options given in 10CFR50, Appendix B, Criterion VII as implemented
, by Policies 4 and 7 of the Operational Quality Assurance Manual may also be used.
J l
I l
Page 28 of 36 Appendix A Rev. 16 OQAMR16
. ~ , . .-. .
NRC Regulatory Guide"1!123 (Continued):
- 3) With regard to Section 3.1 of ANSI N45.2.13 - 1976 titled Procurement Document Preparation, Review and Change Control: The phrase "the same degree of control" is stipulated to mean
" equivalent level of review and approval. " The changed document may not always be rereviewed by the originator; however, at least an equivalent level of management / supervision shall review and approve any changes.
- 4) With regard to Section 3.4 of ANSI N45.2.13 - 1976 titled Procurement Document Control: The licensee vill meet the requirements of Policies 4 and 7 of the operational Quality Assurance Manual in lieu of the requirements specified in this section.
- 5) With regard to Section 5.3 of ANSI N45.2.13 - 1976 titled Preaward Evaluation: The licensee will comply with an alternate paragraph which reads: "Except in unusual circumstances (e.g., replacement parts are needed to preclude the development of some unsafe condition at a nuclear facility), a preaward evaluation of the Supplier.shall be performed as required by the operational Quality Assurance Program."
- 6) With regard to Section 6.4 of ANSI N45.2.13 - 1976 titled Control of Changes in Items or Services: The phrase "the Operational Quality Assurance Program" will be inserted in lieu of " ANSI N45,2, Section 7."
- 7) With regard to Section 8.2 of ANSI N45.2.13 - 1976, titled Disposition: The third sentence of item b is revised to read:
"Nonconformances to the contractual procurement requirements or purchaser approved documents which consist of one or more of the following shall be submitted to the purchaser for approval of the recommended disposition prior to shipment when the nonconformance could adversely affect the end use of a module or shippable component relative to safety, interchangeability, operability, reliability, integrity, or maintainability:
- 1) Technical or material requirement is violated; I
- 2) Requirement in supplier documents, which have been '
approved by the purchaser, is violated; I 3) Nonconformance cannot be corrected by continuation of l the original manufacturing process or by rework; and/or
)
l I l 4) The item does not conform to the original requirement l even though the item can be restored to a condition such
! that the capability of the item to function is unimpaired."
l l
l l
Page 29 of 36 Appendix A Rev. 16 OQAMR16 i
NRC Regulatory Guide"i!123 (Continued):
- 1. module is an assembled device, instrument, or piece of equipment identified by serial number or other identification code, having been evaluated by inspection and/or test for conformance te procurement requirements regarding end use. A shippable component is a part or subassembly of a device, instrument, or piece of equipment which is shipped as an individual item and which has been evaluated by inspection and/or test for conformance to procurement requirements regarding end use.
- 8) With regard to Section 12 of ANSI N45.2.13 - 1976 titled Audit of Procurement Program: The licensee audit program will be implemented in accordance with and to meet the requirements of: ANSI N45.2.12 as endorsed in Appendix A of the OQAM; Policies 2, 4 and 18 of the Operational Quality Assurance Manual. Audit frequencies will be in accordance with Clarification 2 to Regulatory Guide 1.33.
- 9) Paragraph C.6.e of Regulatory Guide 1.123 (and Section 10.3.4 of ANSI N45.2.13 which it references), shall be implemented as originally written (i.e., with the verb 'should" instead of the verb "shall"). This flexibility is necessary because the licensee may not always be able to obtain agreement with a supplier. The licensee retains the ultimate responsibility for performance of purchased equipment. The appropriate engineering discipline will exercise this management / engineering prerogative with respect to the final decision on post installation test requirements.
- 10) With regard to Section II of ANSI N45.2.13 - 1976 titled Quality Assurance Records: The licensee shall maintain reccrds in accordance with and to meet the requirements of Policy 17 of the OQAM and ANSI N45.2.9 as specified in Appendix A of the OQAM.
NRC Regulatory Guide 1.144 " Auditing of Quality Assurance Programs for Nuclear Power Plants" (Rev. 1, 9/80) - Endorses ANSI N45.2.12 - 1977.
The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
- 1) With regard to Section 1.4 of ANSI N45.2.12 - 1977 titled Definitions: With two exceptions (program deficiencies and audits) the definitions in this standard which are not included in ANSI N45.2.10 will be used: All definitions which are included in ANSI N45.2.10 will be used as clarified in the licensee's commitment to Regulatory Guide 1.74. The excepted definitions are defined i"n Appendix A of the OQAM under Regulatory Guide 1.74.
- 2) With regard to Section 2.2 of ANSI N45.2.12 - 1977 titled Personnel Quali fication: The qualification of licensee audit personnel will be accomplished as described to meet the requirements of ANSI N45.2.23 l 1978 as endorsed in Appendix A and Policies 2 and 18 of the l operational Quality Assurance Manual.
- 3) With regard to Section 2.3 (and subsections 2.3.1 through 2.3.3) of ANSI N45.2.12 - 1977 titled Training: The training of licensee audit personnel will be accomplished as described to meet the requirements of ANSI N45.2.23 - 1978 as endorsed in Appendix A and Policies 2 and 18 of the operational Quality Assurance Manual.
l Page 30 of 36 Appendix A Rev. 16 l OQAMR16
. --- . -. _. _ . - ~ -- . _.
~
NRC Regulatory Guide i!144 (Continued):
- 4) With regard to Section 2.4 of ANSI N45.2.12 - 1977 titled Maintenance of Proficiency: The maintenance of proficiency of licensee audit personnel will be accomplished as described to meet the requirements of ANSI N45.2.23 1978 as endorsed in Appendix A and Policies 2 and 18 of the operational Quality Assurance Manual.
- 5) With regard to Section 3.3 of ANSI N45.2.12 - 1977 titled Essential Elements of the Audit System: The licensee will comply with Subsection 3.3.5 as it was originally written (Subsection 3.2.5) in ANSI N45.2.12, Draft 3, Revision 4: " Provisions for reporting on the effectiveness of the quality assurance program to the responsible management." For the auditing organization (licensee), effectiveness is reported as required by the UFSAR, Appendix 16B, and paragraphs (currently numbered 1.3.1, 1.3.2 and 1.3.15) in Policy 1 of the operational Quality Assurance Manual. Other than audit reports, the licensee may not directly report on the effectiveness of the quality assurance programs to the audited organization when such organizations are outside of the licensee.
Subsection 3.3.6 requirements are considered to be fulfilled by com-pliance with the organization and reporting measures outlined in the Operational Quality Assurance Program.
Subsection 3.3.7 requires verification of effective corrective action on a " timely basis." Timely basis is interpreted to mean within the framework or period of time for completion of corrective action that is accepted by the organization. Each finding requires a response and a corrective action completion date; these dates are subject to revision (with the approval of Quality Pr' grams or Material Requirements) and must be escalated to higher authority when there is a disagreement between the auo.ted and the auditing organization on what constitutes " timely corrective action."
[
- 6) With regard to Section 3.5 of ANSI N45.2.12 - 1977 titled Scheduling: Subsection 3.5.3.1 is interpreted to mean that the licensee may procedurally control qualification of a contractor's or supplier's quality assurance program prior to awarding a contract or purchase order by means other than audit.
( 7) With regard to Section 4.3.1 of ANSI N45.2.12 - 1977 titled Pre-Audit Conference: The licensee will comply with the requirements of this section by inserting the word "Normally" at the beginning of the first sentence. This clarification is required because,'in the case of certain unannounced audits or audits of a particular l operation or work activity, (monitoring audit) a preaudit conference l
might interfere with the spontaneity of the operation or activity being audited. In other cases, persons who should be present at a preaudit conference may not always be available: such lack of availability should not be an impediment to beginning an audit. Even in the above examples, which are not intended to be all inclusive,
- the material set forth in Section 4.3.1 will be covered (if considered necessary or desirable as determined by the Audit Team Leader by signature on the audit report) during the course of the audit.
- Page 31 of 36 Appendix A Rev. 16 OQAMR16
E tRC j Regulatory Guide'1!144 (Continued):
- 8) With regard to Section 4.3.2 of ANSI N45.2.12-1977 titled Audit Process:
~
(a) Subsection 4.3.2.2 could be interpreted to limit auditors to the review of only objective evidence; sometimes and for some program elements, no objective evidence may be available. The licensee will comply with an alternate sentence which reads:
"When available, objective evidence shall be examined for compliance with quality assurance program requirements. If subjective evidence is used (e.g., personnel interviews) then the audit report must indicate how the evidence was obtained."
(b) Subsection 4.3.2.4 is medified as follows to take into account the fact that some conditions adverse to quality are virtually
" obvious" with respect to the needed corrective action: "When l a condition adverse to quality is identified as a result of an J audit, unless the apparent cause, extent, and corrective action are readily evident, further investigation shall be conducted by the audited organization in an effort to identify the cause and effect and to determine the extent of the corrective action required."
(c) Subsection 4 3.2.5 contains a recommendation which is clarified with the definition of " acknowledged by a member of the audited organization" to mean that "a member" of the audited organization has been informed of the findings; it does not mean that person agrees with the findings. Agreement or disagreement with a finding may be expressed in the response from the audited organization. l (d) Subsection 4.3.2.7 is not considered applicable as written.
The licensee will comply with an alternate sentence which reads: " Corrective action taken as a result of the last previous audit of the same area shall be reviewed or reaudited, if necessary, to evaluate the effectiveness of the action to resolve the identified condition adverse to quality."
- 9) With regard to Section 4.3.3 of ANSI N45.2.12 - 1977 titled Post-Audit Conference: The licensee will substitute and comply with the following paragraph: "For all external audits, a post-audit con-ference shall be held with management of the audited organization to present audit findings and clarify misunderstandings; where no adverse findings exist, this conference may be waived by management of the audited organization: such waiver shall be documented in the audit report. Unless unusital operating or maintenance conditions preclude attendance by appruiriate managers / supervisors, a post-audit conference shall be .' eld with managers / supervisors for all internal audits for the same reasons as above. Again, if there are no adverse findings, management of the internal audited organization may waive the postaudit conference: such waiver shall
! be documented in the audit report."
i Page 32 of 36 Appendix A Rev. 16 l
OQAMR16 4
~~
NRC Regulatory Guide 1 144,_(Continued):
- 10) With regard to Section 4.4 of ANSI N45.2.12 - 1977 titled Reporting:
(a) This section requires that the audit report shall'be signed by the audit team leader; this is not always the most expeditious route to take to assure that the audit report is issued as soon as practical. The licensee will comply with Section 4.4 as clarified in the following opening: "An audit report, which shall be signed by the audit team leader, or his supervisor in his absence, shall provide:" In cases where the audit report is not signed by the lead auditor due to his absence, one record copy of the report must be signed by the lead auditor upon his return. The report shall not require the lead auditor's review / concurrence / signature if the lead auditor is no longer employed by the licensee at the time the audit report is issued.
(b) The licensee will comply with subsection 4.4.3 clarified to read: " Supervisory level personnel with whom significant discuscions were held during the course of preaudit (where conducted), audit, and post-audit (where conducted) activities."
(c) Audit reports may not necessarily contain an evaluation statement regarding the effectiveness of the quality assurance program elements which were audited, as required by subsection 4.4.4, but they will provide a summary of the audited areas and the results.
(d) Subsection 4.4.6 requires audit reports to include recommenda-tions for corrective actions; the licensee may choose not to comply with this requirement. Instead, licensee auditors / lead auditors are required to document all adverse audit findings.
The procedure for processing quality deficiency documents allows the auditor / lead auditor to document actions which are considered necessary to correct the finding, the auditor / lead auditor may also document actions which are considered unacceptable for correcting the finding: the quality deficiency document with these " Auditor Recommendations" is then transmitted to the audited organization. In addition, appropriate Quality Programs, Headquarters Quality Assurance, or Material Requirements personnel are required to review corrective action taken for the condition adverse to quality document and determine if it is acceptable. Any disagr~eements must be escalated to higher management for resolution.
(e) The last paragraph in Section 4.4 deals with distribution of audit reports. The licensee will comply with these requirements after substituting the following for the last sentence: "The audit report shall be issued within thirty working days after the last day of the audit. The last day of an audit shall be considered to be the day of the post-audit
[ conference. If the post-audit conference has been formally waived, the last day of the audit shall be considered to be the date of the waiver as documented in the audit report."
Page 33 of 36 Appendix A Rev. 16 OQAMR16
I NRC Regulatory Guide ~!144 1 (Continued):
- 11) With regard to Section 4.5.1 of ANSI N45.2.12 - 1977 titled By Audited Organization: The licensee will comply with the following clarification of this Section: " Management of the audited organization or activity shall review and investigate all "significant conditions adverse to quality" (as defined in ASME NQA-1 89, Supplement S-1, Terum and Definitions, Section 2(c)], as necessary, to determine and schedule appropriate corrective action including action to prevent recurrence. They shall respond, in writing, within thirty working days after the date of issuance of quality deficiency documents generated as a result of the audit ,
clearly stating the corrective action taken or planned to prevent recurrence and the results of the investigation if conducted.
However, written response is not necessary if corrective action is taken and verified prior to issuance of the audit report. The audited organization shall take appropriate action to assure that corrective action is accomplished as scheduled." The Director, Quality or the Vice President, Operations Support, as applicable, .
may, at their discretion, waive the requirement for a supplementary response.
- 12) With regard to Sections 3.4 and 4.2.1 of ANSI N45.2.12 - 1977 titled Audit Planning and Written Plan respectively: In the case of a monitoring audit provisions for " Written Plan" is met by the overall audit planning documents, which may include the audit plan. The audit plan is encompassed by the individual audit report (although ,
may not be identified uniquely as audit plan). In the case of l monitoring audits the written plan may appear in a different form, i
- 13) Paragraph C.3.a of Regulatory Guide 1.144 (and Section 3.5.2 of ANSI I N45.2.12 which it references) shall be implemented by meeting the l audit requirements of the Regulatory Guide 1.33 clarification 2 for i audits under C.3.a (1) . Audits under C.3.a (2) are not covered by this OQAM.
- 14) Paragraph C.3.b(2) first sentence is replaced with the following:
Each Supplier is evaluated initially to determine the acceptability of his quality assurance program. If acceptable, the supplier is placed on the Qualified Supplier List. Audits, when used as the selected method of source verification, should be conducted as follows:
l Paragraph C.3.b(2), second paragraph is replaced with the following:
l A documented ongoing evaluation of the supplier should be performed.
, Where applicable, this evaluation should take into account (1) l review of supplier-furnished documents such as certificates of conformance, nonconformance notices, and corrective actions, (2) results of previous source verifications, audits, and receiving inspections, (3) operating experience of identical or similar l products furnished by the same supplier, and (4) results of audits
- from other sources (e.g. customer, ASME, or NRC audits). The results of the evaluation should le reviewed and appropriate corrective action should be taken Adverse findings resulting from these evaluations should be periodically reviewed in order to determine if, as a whole, they result in a significant condition
- adverse to quality and to provide input to support supplier audit activities conducted by the licensee or a third party auditing entity."
Page 34 of 36 Appendix A Rev. 16 OQAMR16
l 1
~
NRC Regulatory Guide 1!144 (Continued):
Paragraph additions to C.3.b(2) are as follows: Previously evaluated and approved active suppliers, for which audit is not the selected l
method of source verification, should be evaluated concurrent with j the award of a contract. Regardless of the results of the ;
evaluation, active suppliers (except those excluded under C.3.b (1) above) shall have been source verified (audit, surveillance or inspection) within two years prior to award of a contract or have source verification performed.
Inactive suppliers shall be evaluated prior to supplying safety-related. items or services. An audit shall,be conducted if required to deterndne the acceptability of procured itene or services (i.e.
acceptability cannot be determined by receipt inspection or one of the other methods allowable under 10CFR50, Appendix B, Criterion VII).
Paragraph addition to C.5 as follows: When another purchaser's audit is used without being designated "on behalf" of more than one purchaser, a copy of the results of the audit is obtained and reviewed for acceptability.
- 15) Paragraph C.4.a of Regulatory Guide 1.144 (and Section 3.5.3.3 of ANSI N45.2.12 which it references) shall be implemented with the clarification that the Director, Quality, the Vice President, Operations Support, or their designee shall determine which reorganizations or procedure revisions are "significant."
- 16) With regard to Section 5.1 of ANSI N45.2.12 - 1977 titled General:
The licensee shall maintain records in accordance with and to meet the requirements of Policy 17.0 of the OQAM and ANSI N45.2.9 as specified in Appendix A of the OQAM.
- 17) With regard to Section 4.3.2 of ANSI N45.2.12 - 1977 titled Audit Process: Subsection 4.3.2.6 is modified as follows to account for the fact that immediate notification is not always possible:
" Conditions requiring immediate corrective action (i.e., those which are so severe that any delay would be undesirable) shall be reported to management of the audited organization. Where responsible management personnel are available (such as at an operating nuclear power plant), these conditions shall be reported immediately. If responsible management personnel are not available (such as at a supplier's shop on a back shift or for items discovered during a review of vendor supplied materials), these conditions shall'be reported as soon as practical."
i NRC Regulatory Guide 1.146 " Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants" (Rev. O, 8/80) - Endorses ANSI N45.2.23
-1978.
l
! The Operational Quality Assurance Program complies with the requirements of this guide with the following clarifications:
Page 35 of 36 Appendix A Rev. 16
- OQAMR16 l
i NRC Regulatory Guide"l$146 (Continued):
- l l
- 1) With respect to Section 2.2 of ANSI N45.2.23 - 1978 titled '
Qualification of Auditors: Subsection 2.2.1 references an ANSI B45.2 (presumed to be N45.2); the Operational Quality Assurance Program does not include a commitment to this standard; therefore, the licensee will comply with an alternate subsection 2.2.1 which reads: )
Orientation to provide a working knowledge and understanding of the Operational Quality Assurance Program, including the !
ANSI standards and regulatory guides included in Appendix A of '
the OQAM, and the licensee's procedures for implementing audits and reporting results.
- 2) With respect to Section 4.1 of ANSI N45.2.23 - 1978 titled Organizational Responsibility: The licensee will comply with this section with the substitution of the following sentence in place of l the last sentence in the section. I The Director, Quality; the Vice President, Operations Support, or lead auditor shall, prior to commencing the audit, assign I
personnel who collectively have experience or training commensurate with the scope, complexity, or special nature of the activities to be audited. Self-initiated audits will be performed by qualified auditors, but no assignment is made
" prior to commencing the audit" since it is self-initiated.
- 3) With respect to Section 3.2 of ANSI N45.2.23 - 1978 titled Maintenance of Proficiency: The licensee will comply with the re-quirements of this section by defining " annual assessment" as one which takes place at least every twelve (12) months (to a maximum of fifteen (15]) and which uses either the initial date of certification or the last annual assessment date (not the calendar year) as the starting date for determining when such annual assessment is due.
- 4) With respect to Section 5.3 of ANSI N45.2.23 - 1978 titled Updating of Lead Auditors' Records: The licensee will substitute the following sentence for this section:
Records for each lead auditor shall be maintained and updated during the period of the annual management assessment as defined in Section 3.2 (as clarified).
- 5) With respect to Section 5.4 of ANSI N45.2.23 - 1978 titled Record Retention: The licensee will substitute the following sentence for this section.
Qualification records shall be retained as required by the Operational Quality Assurance Program.
l
- 6) With regard to Section 2.3.1.3 of ANSI N45.2.23 - 1978 titled Other Credentials of Professional Competence: Add "This includes RO l (maximum of I credit) and SRO (maximum of 2 credits) licenses" to last sentence of this subsection.
Page 36 of 36 Appendix A Rev. 16 OQAMR16-
., ., _ m... _ . -- __ _ _ - - - _ - _ - - , _ - - - - - - - - - - - - - . - - - - - - - - . - - -
4
~
. APPENDIX B
~
~
DOCUMENT CONTROL RESPONSIBIUTY FOR OUAUTY-RELATED DOCUMENTS DOCUMENT PREPARED BY. REVIEWED BY APPROVED BY.' ISSUED BY
-A. - Operational Quality Assurance - Quality Programs Director, Quality (5) Vice President,Engineerireg Director, Quality .
. Manual (Topical)
. Director, ' Vice President, Design Engineering Operations GGNS :
GGNS --
r General Manager, Vice President, -
Plant Operations Operations Support 'j -l 4 Director, Plant >
Projects & Support Director, Nuclear Safety and Regulatory i
Affairs s :
i Vice President, Operations I
Support
~
B.I. Quality Assurance Procedures. Quality Programs Quality Programs Director, Quality Director, Quality I
2 Quality Assurance Instructions Quality Programs Quality hey-- Quality Programs Supervisor Quality hop-. -
Supervisor - ;
- 3. Headquarters Quality Assurance Off-Site Quality Vice President, Operations Executive Vice President &. COO 'Vice President, Operations i Manual .. Organization Support Support .
~
l Director, Quality (5) !
- 4. - Procedures for Activities Responsible Responsible Director / Responsible Director / Manager Responsible Delegated to Off-Site Support l
Staff Manager ,
. Director / Manager Organizations [
C. GGNS Operations Manual Directives v Rev.16 PageIof4 OQAMAB16. DOC ;
i
a.
APPENDIX B DOCUMENT CONTROL RESPONSIBILITY FOR OUAUTY-RELATED DOCUMENTS DOCUMENT PREPARED BY - . REVIEWED BY APPROVED BY ISSUED BY _
L 1. This Section deleted in Revision 4.
' 2. Administrative Procedures ' Plant Staff General Manager, General Manager, Director, Plant Projects &
- (Safety-Related) Plant Operations Plant Operations Support Other Responsible Staff . PSRC (5), (8), (15) Responsible Director / Manager (10) l
- 3. His section deleted in Revision 3. j
- 4. .Section Procedures Plant Staff See Notes (5) and (15) - See Note (15)
Assigned Reviewer See Note (3)
- 5. Section instructions Plant Staff See Notes (5) and (15) See Note (15)
Assigned Reviewer (See Note 3)
D. His section deleted in Revision 4.
E.1. Entergy Operations Management Responsible Staff Director, Quality (14) Responsible Vice President Vice President, Operations Policies and Directives .
Support Responsible Director / Manager
- 2. His section deleted in Revision 12.
- 3. His section deleted in Revision 12.
f Rev.16 Page 2 of 4 OQAMAB16. DOC
__m._...__.__ __.____s._ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
APPENDIX B DOCUMENT CONTROL RESPONSIBillTY FOR OUAUTY-RELATED DOCUMENTS DOCUMENT PREPARED BY REVIEWED BY APPROVED BY ISSUED BY
- 4. His section deleted in Revision 12.
F. Nuclear Plant Engineering Design Engii[eering - Design Engineerir.g - Director, Design Engineering - GGNS Director, Design Engineering Administrative Procedures GGNS Staff GGNS -GGNS Discipline Managers Director, Quality (5) i G. This section deleted in Revision 5.
H. Q-Ust Design Engineering - Director, Design Director, Design Engineering - GGNS Director, Design Engineenng GGNS Staff Engineering - GGNS -GGNS Vice President, Engineering (7)
Director, Quality (5)
I. His section deleted in Revision 12.
J.
~
His section deleted in Revision 11.
K. His section deleted in Revision 12.
. L. His section deleted in Revision 12.
M. His section deleted in Revision 12.
t Rev.16 Page 3 of 4
d' 4
- APPENDIX B ~
DOCUMENT CONTROL RESPONSIBillTY FOR OUAllTY-RELATED DOCUMENTS I
~
~ NOTES:
^
, '1) ' Responsible individuals listed above may have designated alternates who are authorized to perform the function.
2)
Designated support organization (other licensee organizations, contracte s, consultants, etc.) also be authorized to perform certain of the functions. -
3)'
See Paragraph 5.4.3 of this Manual.
.1 l
- 4) ' . Sections 6.5.3,6.5.4,6.5.5,6.5.6,6.5.8, and 6.5.13 apply to this Appendix. . i' 1-
- 5) _ He Director, Quality reviews these documents to assure quality requirements are addressed and provides concurrence. Concurrence indicated by the actual !
. signature may be provided by the Director, Quality, or designee. -
-i
- 6) his Section deleted in Revision 14. F
.}
p
- 7) On matters relating to nuclear fuel and nuclear core design.
- 8) As required by the UFSAR, Appendix 16B.'
1 .
' i
- 9) This Section deleted in Revision 14. ~*
i
- 10) Hose administrative procedures addres dng responsibilities and authorities of Nuclear Training; Materials, Purchasing & Contracts; Plant Projects & Support; Nuclear -[ -
Safety & Regulatory Affairs; and Emergency Preparedness are approved by both the General Menager, Plant Operations, and the management of those organizations, as i applicable. t
- 11) His Section deleted in Revision 12. !
I
- 12) his Section deleted in Revision 14. i i
- 13) His Section deleted in Revision 14.
L l 14) Safety Related Only. i i
- 15) Section procedures / instructions are reviewed and approved in accordance with the guidelines as stated in the UFSAR, Appendix 16B, Sectim 7.4.3.1.
- 16) His Section deleted in Revision 15. '
3 Rev.16 l Page 4 of 4 !
OQAMAB16. DOC r 6
L
APPENDIX C +- i OPERA'110NALOUAUTY ASSURANCE
, PROGRAM IMPLEMENTING PROCEDURES Implementing Document t by Organization - Summary 10CFR50, Appendix B, Criteria 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 A. Quality Programs f
Manual Program Policies for all 10CIM, ,
Appendix B Criteria, and provide i f appropriate implementation
- procedures / instructions. (QA Procedures are numbered by Appendix B Criteria.)
- 2. QA Procedure Manual X X X X X X X X X X X X X X '
X X X ,
- 3. QA Instruction Manual X X X X X X X X X X X X X X X X X X ,
B. . His section deleted in Revision 12 '
C. Design Engineering-GGNS NPE Administrative X X X X X X X X X X X X X Emphasis of Design Engineering-GGNS is l Procedures on design, independent review, evaluation and technical support. ,
D. Plant Staff. Nuclear Safety l
& Regulatory Affairs.
Plant Proiects & Support. '
NuclearTraining and '
, Material. Purchasing &
Contracts ,
Operations Manual ne Operations Manual contains Safety Related X X X 'X X X X X X X X X X X X X X implementing procedures for all 10CFR50, :
Administrative Procedures Appendix B Criteria.
3 Rev. 16 Page1of2 OQAMAC16. DOC
APPENDIX C OPERA *I1ONALOUAUTY ASSURANCE PROGRAM IMPLEMEN71NG PROCEDURES Implementing Document by Organization Summary 10CFR50, Appendix B, Criteria E. his section deleted in 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 Revision 12.
F. his section deleted in Revision 12.
G. His section deleted in i Revision 12.
H. Headquarters Ouality Assurance Manual Off-Site Support Policies X X X X X X X X X X X X X X X X X X His manual describes the off-site suppoit Quality Assurance Policies.
I. His section deleted in Revision 12.
J. His section deleted in Revision 12.
K. His section deleted in Revision 12.
Rev. 16 Page 2 of 2 OQAMAC16. DOC ,
- - - - r--- ' - - _ _____-___._____._______.___..__m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ . _ _ _ _ .