ML20126B546

Rev 10 to Operations QA Plan

ML20126B546
Person / Time
Site:	South Texas
Issue date:	12/16/1992
From:	Denver D, Hall D HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20126B530	List: ML20126B546 ST-HL-AE-4285, Forwards Rev 10 to Operations QA Plan
References
NUDOCS 9212220124
Download: ML20126B546 (30)

Text

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10 OPERATIONS QU/LITY ASSURANCE PLAN PAGE 1

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((kcm 12/18/92

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Approved by:

Date:

DT W al'1, Group Vice President Nuclear Approved by:

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D.

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D4nver, General Manager Nuclear Assurance 1

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I SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION "* Hble E

of Contents 10 1

OPERATIONS QUALITY ASSURANCE PLAN PAGE 1 OF 2 TABLE OF CONTENTS flEcwn12-18-92 i

l Chapters Requiring NRC Approval l

Chapter Title of Effective Effective.

Change Eumber Chanter Revision No.

Date Notices i

Definitions 5

12-21-90 1.0 Organization 6

12-18-92 2.0 Program Description 8

12-18-92 l

3.0 Conduct of Plant Operations 6

12-20-91 4.0 Qualification, Training, and 4

12-21-90 Certification of Personnel 5.0 Maintenance, Installation of 4

12-21-90 Modifications, and Related-Activities.

6.0 Design and Modification Control 6

12-18-92 j-7.0 Procurement 5

12-21-90 8.0 Control and Issuance of 4

12-21 Documents l-9.0 Control of Material 5

12-20-91 10.0 Inspection-6 12-21-90 11.0 Test Control 5

12-21-90 12.0 Instrument and Calibration 5.

12-21-90 l

Control 13.0 Deficiency Control 5

12-20-91 14.0

-Records Control 4

12-21-90 15.0 Quality Assurance Audit 4

12-21-90 and Surveillance i

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OPERATIONS QUALITY ASSURANCE PLAN PAcc 2 -

or 2 TABLE OF CONTENTS

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Chapters Not Requiring NRC Approval j

i Chapter Title of Effective Effectivo.

Change Number Chaeter Revision No.

Date

_ Notices I

16,0 Nuclear Fuel Management 4

12-21-90 i

i 17.0 ASME Code Section XI -

4 12-21-90 j

Repairs and Replacements I

18.0 ASME Code Section XI -

4 12-21-90 j

Inservice Inspection and-l Testing i

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i Chapter 1.0 5

i OPERATIONS QUALITY ASSURANCE PLAN PAGE 1 OF g ORGANIZATION trFECTM:

s DAK 12-18-92 Ii 1.0 PURPOSE 1.1 The purpose of this chapter is to describe the organizational structure as related to quality assurance and to establish the responsibilities of a

organizations for the South Texas Project Electric l

Generating Station (STPEGS).

2.0 SCOPE i

l 2.1 Houston Lighting & Power Company (HL&P), as licensee and Project Manager for itself and the other owners, has the Quality Assurance (QA) responsibility for design, engineering, procurement, fabrication, modification, maintenance, repair, inservice inspection, refueling, testing, and-operation of the l

South Texas Project Electric Generating Station (STPEGS).

3.0 DEFINITIONS 3.1 None i

4

4.0 REFERENCES

4.1 None i'

5.0 RESPONSIBILITIES 5.1. The Nuclear Group is comprised of Nuclear Generation, Nuclear Engineering, Information Resources, j

Planning / Assessment, Human Resources-Nuclear, Nuclear Licensing,.and Nuclear Assurance. ~TheLheads of these groups-report to the Group Vice President, Nuclear, i

5.1.1-The Group Vice President,. Nuclear, has overall i

responsibility ~for the implementation of the i

Operations Quality Assurance Program and approving the Operations Quality Assurance Plan

-(OQAP) and revisions thereto.- He is also

. responsible for-engineering, modification, and

-operations' activities _of STPEGS.

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j ORGANIZATION EFFECD W DAE 12-18 1 l

i 5.1.2 The Vice President, Nuclear Generation, is i

responsible for staffing STPEGS with qualified personnel and acquiring and coordinating the i

assistance of internal and external organizations for-the testing,-startup, i

operation, modification, maintenance, and j

security of STPEGS.

5.1.2.1 The Plant Manager, STPEGS, has prime responsibility for the safe operation of.the STPEGS.

The plant staff, under j

the direction of the Plant Manager, STPEGS, develops detailed procedures and instructions for testing, operation, modification, maintenance, and radiological monitoring of the STPEGS.

I The Plant Manager, STPEGS, reports to j

the Vice President, Nuclear Generation.

5.1.2.2 The Manager, Nuclear Security, is responsible for the development and coordination of the security program, i

including. practices and procedures;-

providing security services; establishment and maintenance of physical security.

l The Manager, Nuclear Security,. reports to the Vice President, Nuclear Generation.

i 5.1.2.3

.The Manager, Nuclear Training, is responsible for developing and implementing formal training programs and curricula no support the training 4

and' certification-of STPEGS personnel.

The Manager, Nuclear Training, reports to the-Vice President, Nuclear Generation.

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OPERATIONS QUALITY ASSURANCE PLAN PAGE 3 0F g ORGANIZATION EFFECTIVE DAR 12-18-92 5.1.3 The Vice President, Nuclear Engineering has overall responsibility for design engineering, plant-engineering, nuclear engineering,-

purchasing. :v.terial control, and design reviews for STPEGS.

In addition, the Vice President, Nuclear EnejAneering is responsible for nuclear fuel design, fuel acquisition, fuel management, and provides for procurement and storage of equipment, material, and services for STPEGS.

5.1.3.1 The General Manager, Nuclear Engineering is responsible for design engineering, plant engineering, and nuclear purchasing and materials management.

The-General Manager, Nuclear Engineering reports to the Vice President, Nuclear Engineering.

5.1.3.2 The Nuclear Fuel Manager is responsible for providing staff assistance to the STPEGS owners in procuring nuclear fuel, other than-fabricated assemblies, for STPEGS, and for off-site disposal of spent fuel assemblies.

The Nuclear Fuel Manager reports to the Vice President, Nuclear Engineering.

5.1.3.3 The Plant Analysis Manager is responsible for providing engineering, licensing, and operations analysis in the areas of risk,-reliability, and-thermal hydraulics.

The Plant Analysis Manager reports to.

the Vice President, Nuclear Engineering.

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PAGE 4 OF g ORGANIZATION EFFECmt 2

DAR 12-18-92 l

d 5.1.3.4 The Manager, Nuclear Purchasing and Materials Management is responsible'for the procurement of equipment, material and services, including the l

coordination of procurement document reviewt receipt, handling,1 storage and issuance of equipment _and materials.

4 The Manager, Nuclear Purchasing and Materials Management reports to the General Manager,. Nuclear Engineering 2

for administrative and project direction and is matrixed to the HL&P Corporate Organization for corporate procurement policy direction.

i 5.1.3.5 The Manager, Design Engineering is responsible for establishment and maintenance of the plant. design basis and plant configuration.

Design l

Engineering issues plant modifications, I

resolves. plant nonconformances, l

approves.special process procedures and supports the ASME-XI Inservice-l Inspection Program.

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The Manager, Design Engineering reports to the General Manager,. Nuclear t

Engineering.

5.1.3.6 The: Manager, Plant Engineering is responsible for providing technical-support-for the-day-to-day' activities l

of plant. operations, for tP-development,_ implementation and administration'of the plant testing program, for the~ administration of the nuclear fuel contract, and for-

.providing the nuclear fuel design-interface between Westinghouse-and-i STPEGS.

The Manager, Plant Engineering reports to the General Manager, Nuclear l-Engineering.

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OPERATIONS QUALITY ASSURANCE PLAN PAGE 5 OF g ORGANIZATION EFFECTiw DATE 12-18-92 5.1.4 The General Manager, Information Resources, is responsible for assuring that activities associated with the distribution of documents, the records management system, plant communications, and the administrative computer systems are in compliance with the OQAP.

5.1.4.1 The General Manager, Information Resources, reports to the Group Vice President, Nuclear.

5.1.5 The General Manager, Nuclear Assurance, is responsible for the development, implementation, and maintenance of the STPEGS QA Program, making periodic reports on its effectiveness, review of selected documents which control activities within its scope, and preparation, control, and approval of the OQAP and revisions thereto.

The General Manager, Nuclear Assurance, has the authority to identify, initiate, recommend, or provide solutions to quality-related problems and verify the implementation and effectiveness of the solutions.

This position has the independence to conduct QA/ Quality Control (QC) activities without undue pressure of cost or schedule.

The General Manager, Nuclear Assurance, has the authority to stop work for cause in engineering, design, procurement, fabrication, modification, testing, and operations phases of the nuclear plant.

This authority in QA matters has been granted by the Group Vice President, Nuclear.

The QA organization's responsibilities during operation are shown in Attachment II.

The QA organization, including the inspection staff, is based upon the anticipated QA/QC involvement in operation, modification, and maintenance activities and by a survey of site QA staffs of other utilities with nuclear power plants in operation.

The position of General Manager, Nuclear Assurance, is on the same or higher organizational level as the highest line manager responsible for performing activities affecting quality as shown in Attachment I.

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OPERATIONS QUALITY ASSURANCE PLAN PAGE 6

@ 8 ORGANIZATION ErrECDW j

DAE 12-18-92 l

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l 5.1.6 The General Manager of Nuclear Licensing, is j

responsible for development of plans and

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procedures which implement the Emergency Plan, the conduct of drills and exercises which test the effectiveness of the Emergency Plan, -

operation of the Plant Access Authorizationz i

Program, and'for providing-technical direction i

to ensure that STP Licensing activities are j

consistent.with HL&P Licensing-policy.

5.1.6.1 The Executive _ Director NSRB is i

responsible-for the management of the Nuclear SafetycReview Board which conducts independent reviews and audits i

of significant activities as delineated l

by technical specifications.

l The Executive Director NSRB reports to the General Manager of_ Nuclear Licensing.

6.0 REOUIREMENTS 6.1 South Texas Project Electric Generating Station Organization i

6.1.1 Attachment I depicts the organizational l

structure of the STPEGS as it relates to-the implementation of the Operations Quality Assurance Plan.

The structure reflects the reporting alignment-for key positions.

7.0 DOCUMENTATION 7.1 None j

8.0-ATTACHMENTS i-8.1 Attachment I - Nuclear Group - QA Functions l

8.2 Attachment II - Nuclear Assurance Responsibilities I

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OPERATIONS QUALITY ASSURANCE PLAN Pact or y

33 PROGRAM DESCRIPTION EFFECTIVE DAE yg.lg_gg 1.0 PURPOSE 1.1 The purpose of this chapter is to define criteria and establish administrative controls for implementation of the Operations Quality Assurance Program for the South Texas Project Electric Generating Station (STPEGS).

2.0 SCOPE 2.1 The Operations Quality Assurance Program is applicable to safety-related material, equipment, services and activities described in 10CFR50, Appendix B; 10CFR71, Subpart H (except design and fabrication of NRC certified radioactive waste shipping casks); ASME Boiler and Pressure Vessel Code, Sections III and XI; and quality related areas as defined by STPEGS management in this Operations Quality Assurance Plan (OQAP) or other program documents or procedures.

Quality-related areas include the Fire Protection Program, Emergency Plan, Radiological Environmental Monitoring Program, Radwaste Management Program, Computer Program Verification and Control, Physical Security Program, Seismic and Environmental Equipment Qualification Programs, Radiation Protection Program, and Station Blackout (SBO) systems and equipment.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 10CFR50, Appendix B 4.2 10CFR71, Subpart H 4.3 ASME B&PV Code 4.4 OQAP Chapter 14.0, Records Control 4.5 10CFR50.63, Loss of All Alternating Current Power

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OPERATIONS QUALITY ASSURANCE PLAN

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PAGE 2 OF 13 PROGRAM DESCRIPTION ErFECTIVE DAE 18-92 5.0 REOUIREMENTE 5.1 The Operations Quality Assurance Program consists of l

various documents which identify and provide the mechanism for verifying implementation of commitments, a

requirements, and actions necessary to attain quality assurance objectives, t

5.2 The OQAP is prepared to implement the STPEGS Operations Quality Assurance Program.

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5.2.1 The OQAP provides policies to be implemented for the STPEGS..The.OQAP also-assigns-responsibilities necessary for the attainment of quality assurance objectives and-the verification of conformance to established requirements.

5. 2.' 2 Attachment I provides a matrix of 10CFR50, i

Appendix B criteria to the OQAP chapters.

l 5.3 Establishing Policies and Goals 5.3.1 QA policies and goals for STPEGS are defined in the OQAP.

The Group Vice President, Nuclear has overall responsibility for quality assurance.

t 5.3.2 The General Manager,-Nuclear Assurance, is responsible for the-development of_the Quality l

Assurance (QA)' Program.

The minimum j

requirements-established for this position are:

l 5.3.2.1 A. bachelors degree in science or engineering, or an equivalent combination of education and experience.

.E 5.3.2.2 Five years ^ experience in the management of quality assurance.

Fifteen years experience in industry quality assurance standards, and l

federal and state regulatory I

requirements.

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PAGE-3 OF 13 PROGRAM DESCRIPTION ErrECTIVE DAR 12-18-92 5.3.2.3 Familiarity with nuclear power generation facilities and the related operations.

5.3.2.4 Knowledge of the industry's quality assurance standards and regulatory requirements.

5.3.2.5 Management experience and familiarity with HL&P corporate organizations.

4 5.3.3 Procedures and revisions which control. quality-related work programs and activities, performed i.

by STPEGS organizations described in Chapter i

1.0 are reviewed by QA as defined in this chapter.

5.4 Organizational-Independence 5.4.1 The reporting arrangement utilized by the NA Department ensures that those personnel charged with responsibility for verifying compliance with QA Program requirements have the organizational freedom to:

l 5.4.1.1 Identify quality problems.

5.4.1.2 Initiate, recommend, or-provide solutions.

5.4.1.3 Verify implementation of solutions.

5.4.2 The reporting arrangement, as illustrated on Attachment I, of Chapter 1.0, is such that personnel responsible for verifying compliance with quality requirements do not have direct responsibility for the performance of that work.

4 5.4.3

.The General Manager, NA, provides technical and.

administrative direction to.the QA Managers in thecareas of audits, surveillances,-QA Reviews, 4

inspection, and material testing.

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l PROGRAM DESCRIPTION EFRCDW DAE 12-18-92 l

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5.5 QA Program 5.5.1 HL&P has established the Operations QA Program for the operations phase of the CTPEGS, which includes testing,-operation, maintenance, 1

refueling, inservice inspection, and i

modification.

The HL&P Nuclear QA Program for i

the operations phase requires that HL&P, its contractors, subcontractors, and vendors comply with the criteria established by 10CFR Part'50, Section 50.55a; 10CFR Part 50, Appendix A, General Design Criterion (GDC) 1; 10CFR Part 50, Appendix B, and 10CFR Part 71 Sub-Part H.

It is the intent of HL&P to comply, as defined.

herein, with the applicable American National Standards Institute (ANSI) N45.2 daughter standards, ANSI N18.7, and implementing 3

Regulatory Guides (RGs) as defined herein and i

in Updated Final Safety Analysis Report-(UFSAR)

Table 3.12-1.

d 5.6 Delegation of QA Functions l

5.6.1 During normal' operations the QA Program will be l

executed by STPEGS personnel, who may be assisted by subcontract personnel.

During refueling, maintenance, and inservice inspection, first-level quality control inspection and nondestructive examination (NDE) activities may be subcontracted.

However, STPEGS will retain responsibility for the total j_

yQA Program, and STPEGS.NA personnel will perform audits and surveillance (s) of j

subcontracted QA activities.

5.6.2 When first-level _ quality. control inspection and-NDE are performed by STPEGS personnel, they are i

qualified and certified in accordance_with applicable codes, standards, procedures, and i

other-regulations.

Monitoring and surveillance of the quality control and NDE activities shall-l be performed by Operations QA personnel.

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5.7 Identification of Safety-Related Items and Services 5.7.1 The STPEGS QA Program described herein is applied.to all activities _affecting the safety-related functions of those structures, systems, 3

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 safety-related structures, i

systems, and components controlled by the QA Program are listed in UFSAR Section 3.2, along with their associated fire protection systems.

l UFSAR Section 3.2 also identifies those quality-related structures, systems, and components (in addition to fire protection systems) which are not safety-related but to which the STPEGS Operations QA Program is applied.

5.7.2 The fire protection QA Program is part of the overall-STPEGS Operations QA Program and is therefore under the management control of-QA.

i Fire protection QA Program criteria are being i

implemented as part of the HL&P Operations QA Program, as defined in this OQAP.

5.7.3 Expendable or consumable items necessary for the. functional _ performance of safety-related structures, systems, and components are subjected to quality assurance requirements as specified in written procedures.

These procedures include provisions for review and control in accordance with industry standards and specifications and the safety-related function of the expendable or consumable-item.

5.8 Development of the QA Program 5.8 1 The Operations QA Program was fully implemented.

90 days prior'to initial.-fuel loading.

The QA Program shall be in effect throughout the operating life of the STPEGS.-

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5.9 QA Program Documents 5.9.1 The QA Program shall be implemented with 4

documented. instructions, procedures, and drawings which include appropriate quantitative and-qualitative acceptance criteria for-determining that prescribed activities have been satisfactorily accomplished.

Procedures I

shall include-the control of the sequence of required inspections, tests, and other i

operations when important to quality.

To change these controls, the individual procedure 4

must be changed and shall require the same review and approval'given to the original procedure.

Such instructions, procedures, and drawings are reviewed and approved for compliance with requirements appropriate to their safety classification by individuals qualified-to do so.

5.9.2 Procedures 5.9.2.1 Procedures shall be established to j

implement and control activities covered by the OQAP other operating, licensing and code requirements.

When more than one department or.

organization-is involved,-these procedures provide for the-integration of responsibilities and activities-to. ensure continuity of activity between departments or organizations.

5.9.2.2 Specific departments or organizations i

shall be designated for the preparation and approval of each..

j-procedure. -Procedures which contain requirements for more than one department or organization require a designated procedure coordinator who is responsible for>1nitiating review l~

with affected departments or organizations and resolution of comments.

Procedures shall be approved by the management of the issuing department.

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5.9.2.3 Selected procedures and revisions are 4

reviewed by Nuclear Assurance before their issuance. The review attests that these procedures have been reviewed for compliance with the Operations Quality Assurance Program.

The review is documented and the comments on the current procedure revision will be maintained for verification.

5.10 Personnel Indoctrination and Training 5.10.1 General indoctrination and training programs shall be provided for sito personnel to assure that they are knowledgeable regarding quality programs and requirements.

The training requirements for STPEGS personnel are described in UFSAR Section 13.2.

Records shall demonstrate compliance with applicable requirements.

Personnel performing complex, unusual, or potentially hazardous work shall be instructed in special indoctrination or briefing sessions.

Emphasis shall be on i

special requirements for safety of personnel, radiation control and protection, unique features of equipment and systems, operating constraints, and control requirements in effect during performance of work.

Where required by codes and standards, personnel are trained, qualified, and certified according to written procedures in the principles and techniques of performing specific activities.

5.10.2 Personnel performing surveillance testing activities shall be similarly trained in accordance with written procedures.

5.10.3 Training will be conducted in a time frame adequate to allow personnel to prepare for i

their job responsibilities and before commencing quality-related work.

Proficiency of personnel shall be maintained by retraining, reexamining,-and/or recertifying in accordance with initial requirements and procedures.

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& 13 PROGRAM DESCRIPTION EnTcmt DAR 12-18-92 5.10.4 In addition to general employee training and indoctrination described above, departmental and interdepartmental procedures provide for training of personnel who perform quality-related work.

These procedures provide for training'in the principles and techniques of the activity involved and for maintenance of proficiency of personnel by retraining, re-examining, and/or recertifying to an. extent commensurate with the safety significance of the activity.. The procedures address documentation of:

5.10.4.1 Scope, objective, and method of 1

implementing the training program.

l 5.10.4.2 Documentation of the training j

sessions including attendees, dates, and results, where appropriate.

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5.11 Policies and Goals 4

5.11.1 It is the policy of HL&P, acting as licensee and Project Manager for itself and the other owners of the STPEGS, to assure that.the design,. procurement, construction, testing, and operation of the STPEGS are in conformance with l

specifications, procedures, codes,-and Nuclear Regulatory Commission (NRC) regulations. The responsibility of each organization supporting the STPEGS is to ensure that the requirements stated in-this QA Program are incorporatedLinto-procedures. Adherence to those procedures is mandatory for all STPEGS organizations and l

contractors or vendors providing items or services covered by the QA Program.

5.11.2 The OQAP identifies activities and establishes requirements for procedures which identify, report, and verify the resolution of safety-related quality problems.

The implementing procedures call for-the resolution of quality problems at the lowest'possible authorized level.

However, if a dispute is encountered in the_ resolution of a quality problem which cannot be resolved at lower levels, Nuclear-Assurance presents the problem to the Group I

Vice President,-Nuclear, for resolution.

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PROGRAM DESCRIPTION ErrECTIVE l

DAR 12-18-92' i

i 5.12 Control of Activities 5.12.1 The OQAP requires NA review and/or approval of procedures which control selected activities.

These procedures shall require the use of the proper equipment, completion of prerequisites I

for starting an activity, and suitable-environment for. performing the activity.

d Procedures will comply with the appropriate j

standards..

1 j.

5.12.2 STPEGS personnel-attend planning, scheduling, i

and status meetings affecting quality-related 2

activities as necessary to assure adequate CA coverage and program application exists.

i 5.13 Management Review i

5.13.1 The implementation of the QA Program requirements shall be verified through independent and integral control activities.

The QA Organization, under-the General Manager, NA, shall conduct audits, surveillances, and inspections of the operating plant and of the interfacing organizations' quality-related activities.

5.13.2 The results of the audits, surveillances, and j

inspection activities are presented in a periodic report to the Group Vice President,

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Nuclear.

i 5.13.3 Assessments of HL&P's implementation of the 1

Operations-QA Program are conducted.under_the cogr.izance of the Nuclear Safety Review Board and:results are. transmitted to the Group Vice i

President, Nuclear.for his review and/or action.

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OPERATIONS QUALITY ASSURANCE PLAN PAGE 10 Of 13 PROGRAM DESCRIPTION EFFECTIVE DAR 12-18-92 5.13.4 STPEGS may use the services of architect-engineer firms, Nuclear Steam Supply System (NSSS) suppliers, fuel fabricators, constructors, and others which provide or augment STPEGS efforts during operations.

These organizations are required to work under a QA program to provide control of quality activities consistent with the scope of their assigned work.

The QA programs of such contractors or consultants shall be subject to review, evaluation, and acceptance by QA before initiation of activities affected by the program.

5.14 Operations Quality Assurance Plan Changes 5.14.1 HL&P is committed to maintaining the OQAP as an effective and meaningful document to provide programmatic direction on STPEGS.

Changes to the QA Program, as described in the OQAP, will be processed under 10CFR50.54(a).

When changes are made in the OQAP to the organizational elements only, appropriate notification will be made to the NRC within 30 days of implementation.

5.15 Computer Code Programs 5.15.1 The development, control, and use of computer code programs which affect quality-related items will be controlled by OQAP.

Prior to use of a computer code program in a quality-related activity, the appropriateness of the program shall be verified.

In addition, all such programs shall be appropriately certified for use.

6.0 DOCUMENTATION 6.1 Procedures which are generated as required by this chapter shall identify the records which are required to implement and document those activities.

The records shall be controlled in accordance with Reference 4.4.

6.2 Operations Quality Assurance Plan (OQAP)

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OPERATIONS QUALITY ASSURANCE PLAN PAGE 11 13 PROGRAM DESCRIPTION EFFECTM DATE 12-18-92 7.0 ATTACHMENTS 7.1 Attachment I OQAP - 10CFR50, App. B Matrix

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OPERATIONS QUALITY ASSURANCE PLAN l

PAGE 12 Or 13 PROGRAM DESCRIPTION ErrECTWE j

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j ATTACHMENT I 1

OPERATIONS OUALITY ASSURANCE PLAN CHAPTERS 10 CFR 50 APPENDIX B CRITERIA 1

1.0 Organization I

i 2.0 Program Description-II i

l-3.0

. Conduct of Plant Operations V, XIV 4.0 Qualification, Training and II, IX Certification of Personnel j

5.0 Maintenance, Installation of III, V, VIII, IX Modifications, and Related Activities f

6. 0 -

Design and Modification Control III 4

7.0 Procurement IV, VIII, X, XIII, XIV, VII 8.0 Control and Issuance of Documents V,-VI 9.0 Control-of Material VIII, XIII, XIV, VII 10.0 Inspection-X 11.0 Test Control XI 12.0 Instrument and Calibration XII Control 13.0 Deficiency Control

~ XV, XVI 14.0 Records-Control XVII 15.0 QA Audit and Surveillance XVIII' L

16.0 Nuclear Fuel Management.

III, IV, VII, VIII, :X,-

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i OPERATIONS QUALITY ASSURANCE PLAN j

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PROGRAM DESCRIPTION trFECTIVE DATE 12-18-92 i

l ATTACHMENT I i

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OPERATIONS OUALITY ASSURANCE PLAN CHAPTERS 10 CFR 50 APPENDIX B CRITERIA 17,0 ASME Section XI Repairs and Replacements i

19.0 ASME Section XI Examination i

and Testing a'

o These sections do not address 10 CFR 50 Appendix B criteria, but

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are included in the-OQAP to identify STPEGS Code and ASME Section XI commitments.

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sw 724 (02/90) s SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION pfop wweta Chapter 6.0 5

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DESIGN AND MODIFICATION CONTROL trrtemt DAR 12-18-92 i

1.0 PURPOSE 1.1 The purpose-of this chapter is to establish the requirements and responsibilities for design control of new structures, systems or components, and modification control of existing structures, systems, or components at the South Texas Project E3ectric Generating Station (STPEGS).

2.0 SCOPE 2.1 This chapter applies to the design and modification activities associated with the preparation and review of design documents including the translation of applicable Code of Federal Regulation requirements and design bases into design documents.

3.0 DEFINITIONS 3.1 None

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4.0 REFERENCES

4.1 STPEGS Technical Specifications 4.2 L

Chapter 5.0, Maintenance, Installation of M

fications, and Related Activities 4.3 OQAr Chapter J+

,,' Records control 4.4 10CFR50.59, Chars"s, Tests and Experiments 5.0 REQUIREMERIE 5.1 Measures shall be established to document selection of design inputs.

Changes to-specified-design inputs, including identification of their source, shall be identified and documented.

As the design evolves, any

-unreviewed-safety question evaluations shall be perforred as required by 10CFR50.59.

5.2 Measures shall be established to concrol design activities to assure design inputs are translated into

. design documents such as specifications,-drawings, procedures, or instructions.

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OPERATIONS QUALITY ASSURANCE PLAN PACE 2 or 6

DESIGN AND MODIFICATION CONTROL ErrEcTwt DAE 12-18-92 5.2.1 Design activities involving reactor physics; stress, thermal, hydraulic, and accident annlysis; materials compatibility; and accessibility for maintenance, inservice inspection, and repair will be performed according to approved procedures by appropriately qualified individuals.

Results of analyses will be appropriately verified and documented.

5.2.2

-Design documents shall include appropriate quality standardc.- If an alternate quality requirement is used (e.g., other than the originally specified quality standard) the change shall be documented and approved.

5.2.3 Design analyoes.shall be sufficiently detailed as to purpose, method, assumptions, design-input, references, units, and status (preliminary or final) such that a technically qualified person can review and understand the analyses and verify the adequacy of the i

results without recourse to the originator.

5.2.4 A review for tpplication suitability of materials, parts, equipment, and processes essential to the functions of quality-related structures, systems, and components is done as part of the design document preparation and review process.

The procedures which govern i

the preparation and review of design documents require that valid industry standards and specifications be used for this review.

l Review of standard off-the-shelf commercial materials, parts, and equipment for suitability of application with quality-related structurso, systems, and components will be conducted before selection.

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DESIGN AND MODIFICATION CONTROL trrtenw L

DAR 12-18-92 I

5.3 Measures shall be established to identify and control design interface among participating organizations (internal and external).

5.4 Measures shall be established to verify adequacy of design and design changes.

5.4.1-The design process shall include design verification by qualified persons to assure that the design is adequate and meets specified design input.

Design control procedures shall specify-requirements for the selection and performance of design i

verification.. Design verification shall be either by design review, alternate-calculation, qualification testing, or by a combination of these.

The depth of design verification shall1be commensurate with the.

importance of the system or component to plant safety, complexity of tha design, and similarity.of design to previous designs.

5.4.1.1 If the verification method performed is only through qualification testing, the following are required.

o Procedures shall provide criteria that specify when verification should be by. test, o

Prototype, component, or feature testing shall be performed as early as possible before installation of plant equipment, or before the point when the installation would become irreversible.

- o verification by test shall be=

performed under conditions that simulate the most adverse. design conditions as determined by analysis.

5.4.2-Design verification-shall be performed by.

competent individuals or groups other than j

those'who performed the original design.

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DESIGN AND HODIFICATION CONTROL trrte m t DATE 12-18-92 5.4.3 Design verification should not be performed by S il'aiduals that have immediate supervisory

+;ponsi.bility for the individual performing e designs have specified a singular design dpproach; have ruled out certain design considerations; or have established the design inputs for that particular design aspect.

However, the supervisor may perform the verification if the supervisor is the only technically qualified individual and the need for the supervisor to perform the review is approved and documented in advance by the supervisor's management.

5.4.4 Design verification will normally be performed prior to release for procurczent, manufacture, installation, or use by another organization in other design activities.- Exceptions shall be justified and documented.

Procedures shull control the justification of exceptions and the completion of the verification of.all affected design output documents prior to relying on the component, system, or structure to perform its function.

5.5 Heasures shall be established to control the approval, issuance, and changes of design documents to prevent the inadvertent use of superseded design information.

Design documents include design drawings and specifications, vendor documents, setpoints with tolerances and design limits.

5.6 Changes made to design documents are reviewed and l

approved by the same groups or organization which reviewed and approved original design documents.

If the organization which originally approved a particular design document is no longer responsible, another organization may be designated if competent in the specific design area, has access to pertinent backgroundtinformation and has an-adequate understanding of the requirements and intent of the original design.

5.7 Errors and deficiencies found-in approved design documents, including design methods, that could adversely affect quality-related structures, systems, or components shall be documented and action taken to i

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DESIGli AllD MODIFICATI0!i ColCROL trrtenyt DAR 12-18-92 correct and prevent the recurrence of deficiencies.

5.8 Measures shall be established for the identification and control of deviations from specified quality standards.

5.9 Measures shall be established which assure that maintenance and modifications associated with design changes which may affect the functioning of quality-related structures, systems, or components are performed in a manner to ensure quality at least equivalent to that specified in the UFSAR or other original design bases and requirements.

5.10 Measures shall be established to maintain the list of quality-related structures, systems, and components current after modifications are made.

5.11 Measures shall be established to assure that only verified, qualified and controlled computer codes are authorized for use.

5.12 Modifications 5.12.1 Modifications to quality-related structures, systems, and components shall be controlled, revjewed, and approved.

5.12.2 Installation and testing of modifications shall be performed in accordance with Reference 4.2 and approved procedures.

These procedures shall contain provisions as appropriate to eraure quality of installation and appropriate post modification testing.

5.12.3 Quality-related shructures, systems, and components shall not be declared operable after a modification until the following provisions are satisfied:

5.12.3.1 Affected procedures are revised and distributed to appropriate users.

5.12.3.2 Appropriate personnel are trained.

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DESIGN AND MODIFICATION CONTROL trrtcTivt j

DATE 12-18-92 i

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l 5.13 Plant Modifications will be checked against the design j

change documentation for proper implementation prior to closing out the design change process.

6.0 DOCUMENTATION i

I 6.1 Procedures which are generated as required by this J

chapter shall identify the records which are required to implement and document those activities.

The J

records shall be controlled in accordance with 5

Reference 4.3.

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