ML20010G116
| ML20010G116 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 08/07/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17252A633 | List: |
| References | |
| CE-1-A-01, CE-1-A-1, CE-1-A-R19, NUDOCS 8109150347 | |
| Download: ML20010G116 (12) | |
Text
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CE-1-A I
Topical Report Revision 19 e
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QUALITY ASSURANCE PROGRAM FOR NUCLEAR GENERATING STATIONS i,
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e109150347 J10827 PDR ADOCK 05000010 r
PDR Commonwealth Edison Company
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CE-1-A Topical Report January 1976 Rev. 19 - 8/7/81 C0MMONWEALTH EDIS0N C0MPANY QUALITY ASSURANCE PROGRAM FOR NUCLEAR GENERATING STATIONS i
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COMMONWEALTH EDISON COMPANY Post Office Box 767 l.
Chicago, Illinois 60690 Commonwealth Edloon
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i LISTING COVERING REVISION OF TOPICAL REPORT CE-1 Listed below is Revision 19 dated 8/7/81 to the Commonwealth Edison Company Quality Assuranca Program Topical Report CE-1:
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Approved By:_
Mafag'er of Quality Assurance 8/7/81 l-l l
Commonwealth Edison
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QUALITY ASSURANCE PROGRAM 2.1 General The C( mnonwealth Edison Company has extensive exper-ience with the development, scheduling, design, cons truction and operation of electric generating facilities.
It has pioneered in commercial nuclear power.
Commonwealth Edison Company and its consultants and vendors have established designs and specifications for compliance with applicable regulations, ASME Code and National Standards to assure installations of utmost safety and reliability.
Commonwealth Edison Company has attained qualified equipment vendors and contractors through experience, evalua-tion at vendor plants and site surveillance during plant erec-tion.
These ef forts provide assurance that compliance with applicable design specifications and codes is maintained and a high level of reliability is achieved.
2.2 Policy It is the policy of Commonwealth Edison Company to assure a high degree of functional integrity of the equip-ment, structures and safety-related systems of its nuclear generating facilities, the performance of which are essential to the prevention of nuclear accidents that could cause undue risk to the health and safety of the public, or to the mitiga-tion of the consequences of such accidents in the unlikely event they should occur.
These systems, equipment, and struc-tures will be identified, designed, fabricated, erected, tested and operated to the criteria and requirements of ASME Boiler and Pressure Vessel Code Sections III AND XI, as refer-enced in the SAR applicable to a specific unit at the time of engineering, construction and major modifications, Appendix B to 10CFR50, and the mandatory requirements of ANSI N45.2 and N18.7 Standards.
Also, Commonwealth Edison commits to comply I
with 10CFR Part 21
" Reporting of Def ects and Noncompliance" and with the Regulatory position of the following Regulatory i
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t 2-1 Rev. 19 8/7/81 Commonwealth Edison L
Guides and the requirements of the following ANSI Standards as listed for each station.
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Dresden, Quad Cities and Zion Nuclear Power Stations 1.28 (Safety Guide 28 - 5/72); 1.30 (Safety Guide 30 -
8/72); 1.33 (Safety Guide 33 - 11/72); 1.37 - 3/73; 1.38 - 3/73 ; 1.39 - 3/73 ; 1.54 - 6/73 ; 1.58 - Rev. 1; 1.64 - 10/73; 1.74 - 2/74; 1.8 (Safety Guide 8 - 3/71);
1.146 - Rev. 0 8/80; ANSI N45.2.8-74 (Draft 3, Rev. 3, 4/74); ANSI N45.2.5-73 (Draft 3, Rev. 1, 1/74); ANSI N45.2.9-74 (Draft 15, Rev. O, 4/74); ANSI N45.2.12-74 (Draft 3, Rev. 4 2/74); ANSI N45.2.13-74 (Draft 2, Rev.
4, 4/74)
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LaSalle County Nuclear Power Station 1.28 - Rev. O, 6/72; 1.30 - Rev. 0, 8/72; 1.33 - Rev. 2; 1.37 - Rev. O, 3/73; 1.38 - Rev. 2; 1.39 - Rev. 2; 1.54 - 6/73; 1.58 - Rev. 1; 1.64 - Rev. 2; 1.74 - Rev.
O, 2/74; 1.8 - Rev. 1-R; 1.88 - Rev. 2; 1.94 - Rev. 1; 1.116 - Rev. 0-R, 6/76; 1.123 - Rev. 1; 1.146 - Rev. O, 8/80; 1.144 - Rev. 1 III.
Byron and Braidwood Nuclear Power Stations 1.28 - Rev.1; 1.30 - Rev. O, 8/72; 1.33 - Rev. 2; 1.37 -
Rev. O, 3/73; 1.38 - Rev. 2; 1.39 - Rev. 2; 1.54 - 6/73; 1.58 - Rev. 1; 1.64 - Rev. 2; 1.74 - Rev. O, 2/74; 1.8 -
Rev. 1 R; 1.88 - Rev. 2; 1.94 - Rev. 1; 1.116 R, 6/76; 1.123 - Rev. 1; 1.146 Rev. O, 8/80; 1.144 - Rev. 1 Exceptions or alternatives to this Topical Report for specific plants identified in the Safety Analysis Report or Technical Specification will take precedence over commitments in this l
l Topical Report.
l It is also the policy of Commonwealth Edison Company to assure a high degree of functional integrity for its gene-rating facilities so as to achieve high availability of these f acilities for the production of electrical power and to main-tain overall quality levels which will achieve the foregoing in a safe, effective and economic manner.
The Quality Requirements and Quality Procedures of t
the Company Quality Assurance Program Manual (see Appendix A for Program Manual Index) as described herein, document the 2-2 l
Rev. 19 8/7/81 Commonwealth Edison
f written policies and procedures of the Program and are augmented by other written Department pnd Station procedures and instructions.
The quality assurance programs of Commonwealth Edison Company, Architect Engineers and Nuclear Steam Supply System vendors include the requirements of ASME Section III Article NCA-4000, the quality assurance criteria for nuclear power plants of Appendix B to 10CFR50 " Quality Assurance Criteria for Nuclear Power Plants," and the mandatory requirements of ANSI N45.2, " Quality Assurance Program Requirements for Nuclear Power Plants: and ANSI N18.7, " Standards for Administrative Control for Nuclear Power Plants."
The requirements are imple-mented by means of detailed quality procedures delineating the specific methodology to be used.
In addition, individual contractor's fabricator's and vendor's Quality Assurance programs will include the applicable portions of the Code, Standards and Appendix B as they affect the total program.
The overall Commonwealth Edison Company quality assurance program, as a minimum, provides for engineering design control, audit and surveillance of on-site contractors and off-site vendors, surveillance and audit of the performance and quality assurance procedures of the Architect Engineer and CECO Engineering, Purchasing and Construction Groups and for plant operations quality assurance programs covering plant maintenance, repairs, operations, in-service inspections and modifications.
For operating stations, the Corporate Quality Assurance Program activities also are covered by written policies, programs, procedures and instructions included in the Station Procedures Fhnual and other documents.
The Manager of Quality Assurance responsibilities include the establishment and control of the Station Program and prepar-ation and authorization of the Quality Assurance Procedures for operations, audit of station activities and review of the adequacy of the Station Program.
The Station Superintendent provides written procedures and instructions for the Station i
Procedures Manual and administers the policies, procedures and instructions from the item the Operating License is issued throughout the operating life of the station.
The Quality Assurance Program takes into account the need for special controls, maintain the required quality and the need for verification of quality by inspection and test.
The Station activities affecting quality are accomplished in accordance with the Corporate Quality Assurance Program using appropriste equipment and suitable conditions, and completing prerequi-sites.
Disputes of a major nature between the Quality Assur-ance Department and organizations which cannot be resolved l
will be referred to higher management for resolution.
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v Achievements of the applicable requirements of the Codes, standards and specifications for materials, structures, equipment and systems will be verified through independent quality control activities.
The control activities will encompass design, procurement specifications, materials, processes, procedures, id er. t i f ic a t ion s, testing, nonconform-ance, corrective action, documentation, handling, storage, operating, maintenance, modifications, in-service inspections and repair.
Commonwealth Edison Company personnel involved in Company Quality Assurance activities will be primarily involved in audit and surveillance of quality control and assurance activities performed by various contractors and other Edison personnel.
Inspection, testing and examination activities generally will be performed by outside independent testing service contractors.
To achieve the necessary background and experience for Commonwealth Edison personnel in quality control and assurance activities, indoctrination and training programs will be established by the Manager of Quality Assurance or his delegated representative to assure such personnel will have adequate knowledge or skill to perform these activities.
These indoctrination and training programs will be an extension of their formal education or work experience.
The training program will consist of, but not be limited to, the following methods as required:
1.
Company Quality Assurance Program Orientation 2.
Formal Training Programs - classroom and hands-on 3.
On-the-job Training - inspections, auditing, testing, etc.
4.
Industry Seminars - concrete, coatings, QA/QC, etc.
5.
Inter-and Intra-Departmental Sessions The orientation sessions covering the Quality Assur-ance Program will include Engineering, Construction, Produc-tion, Quality Assurance, Licensing and Operational Analysis Department personnel.
Various personnel engaged at all levels of site and station activities and general office functions will be included.
These orientation sessions are intended to acquaint personnel with quality assurance / quality control functions and inter-and intra-departmental responsibilities, plus serve as a feedback mechanism to assess and evaluate the Commonwealth Edison Quality Assurance Program.
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Individuals engaged in the quality assurance program 2
(Engineering, Construction, Production, Quality Assurance, Purchasing and Operational Analysis) activities will be involved in formal training programs utilizing outside agencies and consultants and, as required, will include ine following subjects:
1.
Quality Assurance / Quality Control principles 2.
Codes and Standards 3.
Nondestructive Examination (principles and practices) t 4.
Special Processes 5.
Audits The "On-The-Job" Training program will involve new personnel working under the tutelage and direction of experi-enced sad qualified quality assurance personnel.
In addition, these programs will include the following as required:
1.
Site and ff-Site Seminars for selected subjects 2.
Group diueussions and problem reviews 3.
Individual training and tutoring 4.
Appropriate company and other educational courses The utilization of Industry Seminars will be made as appropriate for responsibilities and disciplines involved.
Edison personnel engaged in resting activities will be assigned according to their formal education and on-the-job experience.
Additionally, training programs will be developed to indoctrinate and qualify personnel in specific inspection, testing or examination activities in which they will be engaged.
The Operational Analysis Manager will be responsible for the development and execution of these programs.
Training will be conducted in a time framo adequate to prepare personnel for their job responsibilities.
When a project or station organization is developed, the Directors of Quality Assurance are responsible for reviewing the adequacy of trained and certified personnel and recommending necessary training programs.
Retraining sessions will be scheduled to assure that adequate skills are maintained for qualified and/or certified personnel.
Certification records will be maintained by the Quality Assurance Department as well as the department where in the employe performs his activities.
Qualification and certifications will be maintained in a current status and will be established to meet the applicable requirements of ASME Code and ANSI Standard N45.2.6.
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d The training and certification of personnel associated with nondestructive examination will be carried out in accord-ance with the requirements of SNT-TC-1A and the Code.
A Level III certified person will administer nis activity and the program will be under the surveillance of the Directors of Quality Assurance or their delegated representatives.
Like-wise, a Level III certified person will administer the concrete containment inspection as applicable under Division 2 of the ASME Code.
Training and certification of personnel associated with concrete containment inspection will be carried out in accordance with Appendix VII of ASME Section III, Division 2.
The period of qualification shall be a minimum of two and a maximum of three years.
Near the end of such a period, employes will be notified that they will require either retraining and requalification and/or recertification to renew their qualification status.
Contractor personnel engaged in inspection, examina-tion and testing activities will be required to be trained, qualified and certified to perform their specific activity in accordance with the above requirements.
Such training will be documented and the record of those receiving training shall include as a minimum the date, subject and the name of the person who performed the training.
The objectives of the Commonwealth Edison Company Cuality Assurance Program are to:
(1) establish with confi-dence that the design, fabrication, erection and operation phases of its nuclear power generation facilities are performed in a manner consistent with the policies stated above; (2) provide for documenting, retaining documentation and updating design, fabrication, erection and product quality information necessary for Commonwealth Edison Company operation, mainten-ance, repair, modification, refueling and in-service inspection of the nuclear power facilities; (3) avoid schedule delays and high cost due to poor quality; and (4) achieve high plant reliability and availability.
The Quality Assurance Program applies t) safety-related and ASME Section III activities and iteme and related consumables plus fire protection, security, emergency plan, meterorology, radwaste shipment and review of environmental qualification of Class lE Equipment.
The classification of structures, systems and components designated as " safety-related" are listed in the respective St.fety Analysis Reports (SAR) of the Stations.
A copy of the SAR or the listing will 2-6 Rev. 19 8/7/81 Cosnmonwealth Edison
be ava.'lable in the Operations, Construction, Quality Assur-ance and Engineering areas, as necessary, for reference.
Distribution of and revisions to this listing is controlled and approved by the Station Nuclear Engineering Department.
The requirements in ASME Section III, Article NCA-4000 shall be applied to Section III systems and components including concrete containments.
The 18 Criteria of Appendix B of 10CFR50 will be applied to safety-related systems and components for design, construction, maintenance, refueling, in-service inspection, repair and station modifications.
Criteria 1, 2, 5, 6, 10, 11, 12 and 14 to 18 and Regulatory Guide 1.33 will be applied to operation of safety-related systems and components.
The Manager of Quality Assurance will be responsible for assuring a regular review of adequacf of the Quality Assur-ance Program.
Periodic written reports will be provided to upper management covering activities and problems involving the requirements of the Quality Assurance Program.
Also, an overall report will be made annually to upper management for their assessment as to scope, status implementation and ef fectiveness of the Quality Assurance Program to assure that it is adequate and complies with 10CFR50, Appendix B Criteria.
An independent management audit for upper management shall be conducted on a two year cycle to evaluate the status and adequacy of the Quality Assurance Program.
This annual assessment is preplanned and documented.
Requ'. red corrective action is identified and tracked.
The Quality Assurance Programs in the Commonwealth Edison Company Quality Assurance Program Manual and revision thereto are approved and controlled by the Lanager of Quality Assurance.and may only be revised with his approval.
The Quality Requirements and Quality Procedures shall be revised in concert with addenda to reflect revisions in the ASME Section III Code for Class 1, 2, 3, CS, MC and CC components.
Such revisions to the Quality Requirements involving ASME Section III shall require acceptance by the Authorized Nuclear Inspection Agency and notification plus evidence of such acceptance to the Authorized Nuclear Inspector prior to issuance.
Concurrently, a copy of the updated Corporate Quality Assurance Manual shall be made available to the Authorized Nuclear Inspector at stations where Code work is being done.
Programmatic changes to the Program are submitted to NRC for acceptance prior to implementation.
Organizational changes are submitted within thirty days of the ef fective date.
Quality Assurance Procedures involving engineering, construc-2-7 Rev. 19 8/7/81 Commonwealtn Edison
tion, operating and maintenance modification, in-service inspection and Stores activities, and revisions thereto, are signed by the Head of the principally involved department and the responsible Director of Quality Assurance or Quality Assurance Supervisor (Maintenance) and approved by the Mariger of Quality Assurance.
Approval of the Quality Assurance Program Manual Indexes indicates approval of respective changes to the individual pages of the Corporate Quality Assurance Manual.
Sections 2 and 5 of the Quality Procedures provide the procedures for implementing this section of the Quality Requirements.
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Commonwealth Edison