ML20073E720

Rev 0 to QA Plan

ML20073E720
Person / Time
Site:	University of Texas at Austin
Issue date:	04/15/1991
From:	TEXAS, UNIV. OF, AUSTIN, TX
To:
Shared Package
ML20073E694	List: ML20073E689 ML20073E720
References
NUDOCS 9104300381
Download: ML20073E720 (36)

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QUALITY ASSURANCE PIAN Docket 50 602 Revision 0 Copy with correction Marks!

November 1990 4t/ /Til Nuclear Engineering Teaching Laboratory Balcones Research Center The University of Texas at Austin 9104300381 910415 PDR ADOCK 05000602 l F PDR

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j Revision 0 QUALITY ASSURANCE PROGRAM Objectives of quality assurance (QA) may be divided into two major goals.

First is the goal of safe operation of equipment and activities to prevent or mitigate an impact on public health and safety. Second is the reliable operation of equipment and activities associated with education and research functions of the University. The risk or potential release of radioactive materials is the primary impact on public health and safety, and may be divided into direct risks and indirect risks. Direct risks are activities such as waste disposal, fuel transport and decommissioning that introduce radioactive materials into the public domain. Indirect risks are accident conditions created by normal or abnormal operating conditiono that generate the potential or actual release of radioactive materials from the controlled areas of a facility.

1. Introduction Characteristics of uranium loaded zirconium hydride fuel used in the TRIGA reactor provide substantial benefits to safe reactor operation. Many accident situations are simulated by normal operation of the fuel in either pulse mode or steady state mode. Other features such as fission product retention, stainless steel cladding design, facility engineered features, and periodic schedule of operation combine with routine operation procedures to decrease the consequences of failure of any reactor components. The limited scope of application of formal quality assurance criteria is due to the fact that most parts and procedures associated with operation of the TRIGA type reactor are not relevant to public health and safety.

Safety-related identifications for quality assurance are determined from safety analyses. Although several systems such as the reactor safety and protection system, engineered safety features and radiation monitoring systems are important to safety, only one reactor component is identified as safety-related. The quality assurance program is not applied to routine reactor operations and surveillance activities but shall be implemented for non routine activities determined to be safety-related in nature or affecting safety-related components. Activities shall include design, construction, testing, modification and maintenance of safety related items. Other components related to safety limits, limiting conditions for operation and design features, as identified in technical specifications, will apply only those elements of quality assurance necessary to establish reliable performance of the intended structure, system or component function. The following table lists the components subject to quality assurance program or selected sections of the program.

Two additional conditions remain, however, that are important to the application of at least portions of the quality assurance program. One is the safety to operation personnel and experimenters and the other is continuity of the operations programs. Each of these conditions must be examined objectively relative to operation procedures and program expectations. In general, the application of good industry quality assurance practices is sufficient to meet operational program goals.

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. 1 Revision 0-Table 1 Q List for IMW UT TRICA QC/QA Structures, systems or components Safety

• Specs Fuel' Element Cladding structure 1 manuf.

Shipping package 1 manuf.

Reactor Core Structural components 2 manuf.

Tank structure 2 design '

Shield structure 2 constr.

Experiment Equipment-(core reflector)

Beam enhe ' components 2 design Rotary rack system 2 design

' Experiment Equipment (core grid)

Pneumatic tube components 2 design Installed core system 2 design Protective Systems Instrumentation system 2 manuf.

Control system 2 manuf.

Safety system '2 manuf.

Auxiliary Systems Pool coolant system 2 design Water purification system 2 design Room confinement components 2 const.

EArea ventilation components 2 const.

Area radiation monitor system 2 manuf.

Air radiation monitor system 2 manuf.

Notes:

11- All sections of quality-assurance program shall be considered applicable.

2- Specific sections of quality assurance program should be applied as-required-to assure reliable performance.

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Revision 0 The quality assurance program shall be commensurate with the TRIGA type reactor, The University of Texas administrative programs and the goals of quality assurance. This document provides requirements for establishing, managing, conducting and evaluating the QA Program. The QA Program applied to items or activities determined to be safety related follows the guidelines of Nuclear Regulatory Guide 2.5 (77/05) [1. 79 10). l 1.1 Purpose. Quality assurance of certain activities associated with the University of Texas TRIGA reactor facility is important for the safe and efficient completion of tasks that are identified as safety related. This document outlines the general elements of quality assurance applied to safety-related structures, systems or components, and activities. Requirements are documented for establishing, managing, conducting, and evaluating the QA Program. Although aspects of the QA Program may be routinely applied to many facility activities, the formal implementation of the program is limited to specific items or activities related to public health and safety. Table 1 lists the quality level and description of key systems and components.

1.2 Responsibility. The University of Texas at Austin as owner and operator of the TRICA reactor facility shall be responsible for a quality assurance program. The owner-operator shall establish and implement a program consistent _with the goals of quality assurance for safety related activities, structures,- systems and components. Identification of safety related items shall be the responsibility of the owner-operator and will include a description of the item and the applicable elemonts of the quality assurance program. Special quality provisions, delegated functions of the program, and unresolved quality assurance problems shall also be identified by the owner-operator. The f acility supervisor shall have the ultimate responsibility for both the specifications of quality related requirements and the functions of quality related activities. Table 2 lists the responsibilities and key personnel participating in the University TRIGA QA Program.

Table 2 RESPONSIBILITIES AND KEY PERSONNEL Responsibilities Key University Personnel

1. Establish program Director or Supervisor Implement program of TRIGA facility Identify Safety related items

2. Unresolved issues President or Executive Vice President and Provost

3. Delegated functions Faculty and staff

4. Specialized functions Specified personnel l

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Revision 0 1.3 . Organization. The~ organization applied to quality assurance activities shall be part of the - normal university administrative structure.

The facility Supervisor shall develop and implement the quality assurance program and identify safety related items. Unresolved issues of quality assurance shall be reported to the Director of the facility and the appropriate administrative vice president of the university. Execution of specific elements of the - program may be dele 6ated to persons in the University organization or other organizations as appropriate. University persons shall include committees, faculty, researchers or staff as required for specific program applications. Non university organizations or persons may supplement University personnel when specialized qualifications are necessary for specific quality assurance tasks.

a d q ality as urance Theacaden'c the University organization a i strat o applied rese to by,reactor 31 uresafety D. l .!

e y eyer iow n reyows M. '

E Wi cher pcrkd 1.4= Documentation. All activities affecting safety related items subject to the quality assurance program shall be identified and documented formally.

The format of Table 3 shall be used to identify applicable elements of the Quality Assurance Program and identify documents, procedures, reviews, inspections, tests, or other quality assurance features that are to be-applied to a safety related activity. The checklist or approval shall be incorporated in the table format for the acceptance of each specified quality assurance element by the facility supervisor.

2. Quality Assurance Controls 2.1 Desien controls. Design controls shall consist of design specifications, references to applicable codes, standards and regulations, design verifications and document approval. Applicable codes, standards, regulations or other quality requirements will be identified and requirements incorporated into the design documents. Design document approvals shall be part of the design document. Design approval vill be by a person, other than the design originator, that is knowledgerble of the design criteria and is informed of the quality requirements.

Modifications of safety-related documents shall be subj ect to the same provisions as the original- docu:nent. Approval of the design modification will be included with the design document and the modification identified.

'- Verification of design adequacy _ shall be provided by either _ design reviewe, alternate calculation, test program or other method, determined to be appropriate. Verifications of the design shall check characteristics such as compatibility of materials; suitability -of application of inspection, maintenance and repair; proper interfacing of sub systems, and proper acceptance criteria. Method _of verification will be identified and documented by approval of the design document.

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i Rsvision 0

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1.3 Ornanization. The organization applied to quality assurance activities shall be part of the normal university administrative structure.

The facility Supervisor shall develop and implement the quality assurance program and identify safety related items. Unresolved issues of quality assurance shall be reported to the Director of the facility and the appropriate administrative vice president of the university. Execution of specific elements of the program may be delegated to persons in the University organization or other organizations as appropriate. University persons shall include comaittees, faculty, researchers or staff as required for specific program applications. Non university organizations or persons may supplement University personnel when specialized qualifications are necessary for specific quality assurance tasks. The University organization applied to reactor safety and quality assurance is the aesdemic administration represented by Figure [.

Reactor operation is the responsibility of oualified individuals with operator permits.

1.4 Documentation. All activities affecting safety related items subject to the quality assurance program shall be identified and documented f ormally.

The format of Table 3 shall be used to identify applicable elements of the Quality Assurance Program and identify documents, procedures, reviews, inspections, tests, or other quality assurance features that are to be applied to a safety related activity. The checklist or approval shall be incorporated in the table format for the acceptance of each specified quality assurance element by the facility supervisor.

2. Quality Assurance Controls 2.1 Design Controls. Design controls shall consist of design specifications, references to applicable codes, standards and regulations, design verifications and document approval. Applicable codes, standards, regulations or other quality requirements will be identified and requirements incorporated into the design documents. Design document approvals shall be part of the design document. Design approval will be by a person, other than the design originator, that is knowledgeable of the design criteria and is informed of the quality requirements.

Modifications of safety related documents shall be subject to the same provisions as the original document. Approval of the design modification will be included with the design document and the modification identified.

Verification of design adequacy shall be provided by either design reviews, alternate calculation, test program or other method, determined to be appropriate. Verifications of the design shall check characteristics such as compatibility of materials; suitability of application of inspection, maintenance and repair; proper interfacing of sub systems, and proper acceptance criteria. Method of verification will be identified and documented by approval of the design document.

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i Revision O  !

l President of

'The University of Texas at Austin I

Executive Vice President and Provost

.................. level 1 Radiation ~ Safety Dean College of Engineering Nuclear Reactor Committee Committee I

Radiation Safety Officer i

I Chairman Department of Mechanical 1 Engineering.

l- l I Director Nuclear Engineering Teaching Laboratory

.................. level 2 Reactor Supervisor

'''''''*****'1***1 Health Physicist-Reactor Operators, Technicians, others

..................lovel 4 Responsibility ---

Communication --

Administrative Organization Office of the= President, UT-1 l

Executive t

Vice President and Provost l

Director i

of NETL.

I Assistant Director, Reactor Supervisor QUALITY ASSURANCE Line Organization Figure 1 6

Revision 0 Table 3 FORMAT FOR SAFETY RELATED QA CHECKS Each safety related activity structure, system, or component will be given a letter symbol, such as A, B, C, and be appended with the following designations (for example, A1.0):

1.0 Title Identification and description of safety related item 1.1 Participation - supplemental organization and functions 1.2 Documents - applicable procedures or special measures 2.1 Design Control 2.1.1 Codes, standards and regulations 2.1.2 Method of verification 2.1.3 Modifications proposed 2.2 Procurement Control 2.2.1 Codes, standards and regulations 2.2.2 Quality assurance specifications 2.2.3 Proposed changes enacted 2.2.4 Procurement conformance method 2.3 Document Control 2.4 Material Control 2.4.1 Special procedures required 2.4.2 Equipment required 2.4.3 Personnel qualifications 2.5 Process Control 2.5.1 Special procedures 2.5.2 Special equipment 2.5.3 Personnel qualifications 3.1 Inspection Program Description 3.2 Test Program Description 3.3 Measurement Equipment 3.4 Nonconformance Item and Disposition 3.5 Corrective Actions Instituted 4.0 Records List 7

Revision 0 2.2 Procurement Controls. Procurement controls shall consist of procurement specifications, references to applicable codes, standards and regulations, procurement acceptance and document approval. Applicable codes, i standards, regulations or other quality requirements will be identified and references incorporated into the procurement documents. Procurement document approvals shall be part of the procurement document. Procurement approval will be by a person, other than procurement originator, that is knowledgeable of the procurement specifications and is informed of the quality requirements.

Changes to safety related procurement documents shall be subject to the same provisions as the original document. Approval of procurement changes will be included with the procurement document and the change identified.

Acceptance of procured items or services shall consist of evidence provided by the contractor, evaluation of the procurement source, inspection at the source or inspection upon receipt. Acceptance of the procurement should require measures such as quality assurance by contractor, inspection and test functions, or controls on materials processes and nonconformances. The methods of acceptance will be identified and documented by approval of the procurement document.

2.3 Document Control. Document control consists of monitoring the development, revision, release and use of documents, drawings or specifications affecting safety-related activities. Document control shall include assurance that safety related documents are identified as such, and are completed and maintained properly.

related documents thatThe arelaboratory specified accordingSupervisor toshall the format provide of control of safety l Table ),2.

2.4 Material Control. Procedures shall be written to establish material control when special measures are necessary to assure material quality of safety-related items. Controls shall be applied to activities such as identification, handling, storage, shipping, cleaning and preservation.

Procedures shall specify equipment and personnel required to accomplish the specified material control. Applicable codes, standards, specifications and personnel qualifications shall be documented.

2.5 Process Control. Procedures shall be written to establish process control when special measures are necessary to assure process quality of safety related items. Controls shall be applied to activities such as crimping, soldering, welding, painting, cleaning and heat treating. Procedures shall specify qualifications of equipment and personnel required to perform the appropriate process control. Applicable codes, standards, specifications and personnel qualifications shall be documented.

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Revision 0

3. Insoeetion and Corrective Actions 3,1 Insocetion Program, An inspection program shall be established for safety related items or activities. The inspection program shall apply to construction, procurements, experiment equipment fabrication, and modifications that effect safety related structures, systems, or components. Persons delegated to perform inspections shall not be the same person involved in the safety related activity but may be from the same organization.

The inspection program will consist of written procedures that will include, as appropriate, procedures specifying characteristics to be inspected, acceptance criteria and inspection hold points.

Procedures should provide for identification of inspected and tested items. Provisions shall be made to clearly identify non conforming items from conforming items. In situations that inspections are not advantageous a description shall be provided for monitoring actions.

Procedures shall be written for in service inspections of safety related structures, systems or components.

3,2 Test Procram, A test program shall be established for safety related items or activities, The test program shall apply to prototype qualifications, installation proofs and functional tests. Testing shall be performed in accordance with acceptance criteria derived from design or procurement documents.

The test program will consist of written procedures that will include, as appropriate, procedures that specify acceptance criteria, monitoring requirements, equipment required, personnel qualifications, environmental conditions, data acquisition, and documentation of results.

3.3 Measurine and Test Eaulement. Measurement tools, gages, instruments, and other measuring or test devices that measure critical parameters of safety-related items shall be identified, Provisions for identified measuring and test devices shall include availability, adj ustment , calibration and accuracy as required for each application. Test equipment will be identified, 3.4 Non-Conforming Material and Parts, Non-conforming materials and parts associated with safety related structures, systems or components shall be identified. The disposition such as acceptance, repair, rework or rejection of parts from safety related functions will be determined by the person responsible for document control. Repair or' reworked parts will be removed or labeled until accepted. Rejected parts will be removed and labeled. The disposition of non conforming materials will be documented.

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Revision 0 1

- 3. 5 fdtrrective ActiSD. Documentation of specified quality control or assurance documents shall provide evidence of quality of safety related: items.

Significant deviations from acceptable quality, repeated quality problems or unresolved- quality issues shall be noted and reported in writing to .

administrative management personnel. It should be recognized that a determination of a quality problem may be subjective and should include evaluation of the documented quality requirements relative to the impact on the safety related nature of the item, 3.6 Exocrimental Eautoment. Design, construction, modification, inspection, testing and maintenance of experimental equipment shall be subject to this quality assurance program to the extent that these activities are I

safety related.

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3.7 Reolacements. Modifications. or Changes. Insofar as possible, the i replacement, modification, or change to structures, systems or components with a safety-related funt. tion shall be documented as meeting the requirements of the original s truc ts.re , system or component. Evaluation should establish a performance and reliability equivalent or exceeding the original.

4. Records and Audits 4.1 Ouality Assurance Recorda. Records that document quality of safety-related items or activities are identified according to Table 3. The records identified consist of inspection and test results, quality assurance reviews, quality assurance procedures and engineeritg ani. '.ys i s in support of design modifications or changes. The records s.iall be retained with as built drawings, manuals and other records of 2r,,ortant facility and system information. The retention-period is to be tv.i life of the facility or system for most, if not all, safety related items.

The retention period is- indcative of the expectation that items which af fect safe ty related to as - TRIGA reactor are integrally related to the reactor, l instrumentation and facility design and should persist for the -system or facility life.

4.2 Audits. An audit shall be conducted to examine the records and function of the quality assurance program. Audits will occur within two years of the QA Program activities. by designated persons that were not directly -

responsible for the audited functions. Written procedures, Table 4,_ for the audit will be considered part of - the Quality Assurance Program. A report of

the audit results, actions to resolve deficiencies and evaluation of the

-program will be made to a facility operations committee and university administrative management, and maintained with other Quality Assurance Program documents.

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Revision 0 Table '4 QUALITY ASSURANCE PROGRAM AUDIT PROCEDURES

1. Designate a person or persons responsible to perform the program audit.

2. Determine the date of the previous audit.

3. Review the Quality Assurance Program document.

4. Examine the list of safety related items.

5. Note additions to the safety-related items.

6. Identify records applicable to additional items.

7. Determine the location of all indicated records.

8. Review records for abnormalities and completeness.

9. Prepare statement that evaluates functions ot' Quality Assurance Program.

10. Report findings of audit and program functions to operations committee and management.

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Revision 0 Table 4 QUALITY ASSURANCE PROGRAM AUDIT PROCEDURES

1. Designate a person or persons responsible to perform the program audit.

2. Determine the date of the previous audit.

3. Review the Quality Assurance Program document.

4. Examine the list of safety related items.

5. Note additions to the safety related items.

6. Identify records applicable to additional items.

7. Determine the location of all indicated records,

8. Review records for abnormalities and completeness.

9. Prepare statement that evaluates functions of Quality Assurance Program,

10. Report findings of audit and program functions to operations committee and management.

References

• l

1. "Ouality Assurance Requirements for Research Reactors" Nucient Reculatory Guide 2.5 (77/05).

2. "Oual'tv Assurance Program Reautrements for Research Reactors" ANSI /ANS - .5.8 - 1976 (N402).

Revision 0 Example Quality-Control Record L 1.0

Title:

1 Item identification: ,

. (designate A, B, C, ...) (quality level 1, or 2) l Item description

l l'

l.1 Participation:

(personnel and task assignments)

I i

1.2 Documents

(procedures applicable) l (special provisions) l t

l Applicable Sections (f #):

Section f.f:

Conditions;.

L Comments:

l-l Dates:

Activity Initiated Initial

. Activity Accepted Initial.

i I,

L- Audit of Activities:

1 Review by Date:

! 12 l

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QUALITY ASSURANCE PLAN Docket 50 602 Revision 0 November 1990 Nuclear Engineering Teaching Laboratory l

Balcones Research Center The University of Texas at Austin i

l l

l

Revision 0 QUALITY ASSURANCE PROGRAM Objectives of quality assurance (QA) may be divided into two to major r,oals.

prevent or First is ths goal of safe operation of equipment ed activitiesSecond is the reliable mitigate an impact on public health and safety.

associated with education and research operation of equipment and activities The risk or potential release of radioactive functionn of the University.

materials is the primary impact on public health and safety, and may be divided into direct risks and indirect risks. Direct risks are activities such as waste dispoeal, fuel transport and decommissioning that introduce radioactive materials into the public domain. Indirect risks are accidentthe conditions potential created by normal or abnormal operating conditions that generate or actual release of radioactive materials from the controlled areas of a facility.

1. Introduction Characteristics of uranium loaded zirconium hydride fuel used in Many the TRIGA reactor provide substantial benefits to safe reactor op9 ration.

accident situations are simulated byOther normal operation of the fuel in either features such as fission product pulse mode or steady state mode. and retention, stainless steel cladding design, facility engineered features, periodic schedule of operation combine with routine operation procedures The limited to decrease the consequences of failure of any reactor components. is due to the fact scope of application of formal quality assurance criteria that most parts and procedures associated with operation of the TRICA type reactor are not relevant co public health and safety.

Safety-related identifications for quality assurance are determined from safety analyses. Although several systems such as the reactor safety and protection system, engineered safety features and radiation monitoring systems are important to safety, only one reactor component is identified as safety-related. The quality assurance program is not applied to routine reactor operations and surveillance activities but shall be implemented for non routine activities determined to be safety related in nature or affecting safety-related cotoponents.

Activities shall include design,Otherconstruction, testing, components related modification and maintenance of safety related items.

to safety limits, limiting conditions for operation will applyand onlyderign those features, elementsas of identified in technical specifications, establish reliable performance of the intended quality assurance necessary to The following table lists the structure, system or component function. or selected sections of the components subject to quality assurance program program.

Two additional conditions remain, however, that are important one to is the the least portions of the quality assurance program, application of atsafety to operation personnel and experimenters and the other is continuity of Each of these conditions must be examined objectively the operations programs. In general, the relative to operation procedures and program expectations. is sufficient to meet application of good industry quality assurance practices operational program goals. 2

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Revision 0:

Table 1 Q. List for '1MW UT TRIGA-QC/QA l Structures, systems or components Safety

• Specs

' Fuel Element  :

Cladding structure 1 manuf, Shipping package 1 manuf, Reactor. Core Structural' components 2 manuf.

Tank structure 2 design Shield" structure 2 constr.

- Experiment Equipment (core reflector)

Beam tube components 2 design Rotary rack system 2 design Experiment Equipment (core grid)

Pneumatic tube components 2 design .'

Installed core system. 2 design ,

Protective Systems-Instrumentation system 2 manuf.

Control system' 2 manuf.

Safety system 2 manuf.

Auxiliary Systems -

-Pool coolant. system 2 design Water: purification system 2 design Room confinement components 2 const.

' Area ventilation components 2 const.

. Area radiation monitor system. 2 'manuf, Air radiation monitor' system 2 'manuf.

Notes:

1-- All sections of quality assurance program shall be considered applicable.

2.- ' Specific . sections of ~ quality assurance program should be applied as required to assure reliable _ performance.

i 3

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9 Revision 0 The quality assurance program shall be commensurate with the TRICA type reactor, The University of Texas administrative programs and the goals of quality assurance. This documentnt provides requirements for establishing, managing, conducting and evaluating the QA Program. The QA Program applied to items or activities determined to be safety related follows the guidelines of Nuclear Regulatory Guide 2.5 (77/05) (1, 2).

1.1 Purpose. Quality assurance of certain activities associated with the University of Texas TRIGA reactor facility is important for the safe and efficient completion of tasks that are identified as safety-related. This document outlines the general elements of quality assurance applied to safety-related structures, systems or components, and activities. Requirements are documented for establishing, managing, conducting, and evaluating the QA Program. Although aspects of the QA Program may be routinely applied to many facility activities, the formal implementation of the program is limited to specific items or activities related to public -health and safety. Table 1 lists the quality level and description of key systems and components.

1.2 Resoonsibility. The University of Texas at Austin as owner and operator of the TRICA reactor facility shall be responsible for a quality assurance program. The owner operator shall establish and implement a program consistent with the goals of quality assurance for safety-related activities, structures, systems and components. Identification of safety related items shall be the responsibility of the owner operator and will include a description of the item. and the applicable elements of the quality assurance program. Specia) quality provisions, delegated functions of the program, and unresolved quality assurance problems shall also be identified by the owner-operator. The facility supervisor shall have the ultirate responsibility for both the specifications of quality related requiremet.ts and the functions of quality related activities. Table .2 lists the re6ponsibilities and key personnel participating in the University TRICA QA Program.

Table 2 RESPONSIBILITIES AND KEY PERSONNEL Responsibilitieg Kev University Personnel

1. Establish program Director or Supervisor Implement program of TRICA facility Identify Safety related items t

2. Unresolved issues President or Executive Vice President and Provost

3. Delegated functions Faculty and staff

4. Specialized functions Specified personnel 4

i Revision 0 1.3 QIganization. The organization applied to quality assurance 1 activities shall be part of the normal university administrative structure. l The facility Supervisor shall develop and implement the quality assurance 1 program and identify safety related items. Unresolved issues of quality assurance shall be reported to the Director of the facility and the appropriate l administrative vice prevident of the university. Execution of specific elements o! the program may be delegated to persons in the University organization or other organizations as appropriate. University persons shall include committees, faculty, researchers or staff as required for specific program applications. Non university organizations or persons may supplement University personnel when specialized qualifications are necess6ry for specific quality assurance tasks. The University organization applied to reactor safety and quality assurance is the academic adrainistration represented by Figure 1.

Reactor operation is the responsibility of qualified individuals with operator permits.

1.4 Doewentation. All activities affecting safety.rolated items subject to the quality assurance program shall be identified and documented formally.

The format of Table 3 shall be used to identify applicable elements of the Quality Assurt.nce program and identify documents, procedures, reviews, inspections, tests, or other quality assurance features that are to be applied to a safety.related activity. The checklist or approval shall be incorporated in the table format for the acceptance of each specified quality assurance element by the facility supervisor.

2. Quality Assurance Centrols 2.1 Design Conttglg. Design controls shall consist of design specifications, references to applicable codes, standards and regulations, design ... N ations and document approval.

Applicable codes, standards, regulations or other quality requirements will be identified nd requirements incorporated into Se design documents. Desi6 n document approvals shall be part of- the design docunent. Demign approval will be by a person, other than the design originator,

• hat is knowledgeable of the design criteria and is informed of the quality ,equirements.

Modifications of wfety related documents shall be subject to the same provisions as the original document. Approval of the design modification will be included with the design document and the modification identified.

Verification of design adequacy shall be provided by either design reviews, alternate calculation, test program or other method, determined to be appropriate. Verifications of the design shall check characteristics such as compatibility of materials; suitability of application of inspection, maintenance and repair; proper interfacing of sub systems, and proper acceptance criteria. Method of verification will be identified r.nd documented by approval of the design document.

5 1-

Revision 0 Presidert of ,

The University of lexas at Austin I

Executive Vice tiesident and Provost

. . ............... 1evel 1 Radiation Safety Dean College of Engineering Nuclear Reactor Committee Committee l

Radiation Safety Officer I

I i Chairman Department of Hechanical i Engineering

' I Director Nuclear Engineerin6 Teaching Laboratory

. . ................ level 2 Reactor Supervisor llealth Physicist Reactor Operators, Technicians, Others

. . ............... 1evel 4 Responsibility ---

Communication -

Administrative Organization Off,1ce of the President, UT i  !

Exe,cutive Vice President and Provost Director of NETL i

Assistant Director, Reactor Supervisor QUALITY ASSURANCP. Line Organization Figure 1 6

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Revision 0 i l

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Table 3 FORMAT FOR SAFETY RELATED QA CHECKS j l

l l

Each safety related activity Structure, system, or component I will be given a letter symbol, such as A, B, C, and be appended with the following designations (for example, A1.0):

1.0 Title Identification and description of safety related item 1.1 Participation supplemental organization and functions 1.2 Documents . applicable procedures or special measures 2.1 Design Control ,

2.1.1 Codes, standards and regulations 2.1.2 Method of verification 2.1.3 Modifications proposed 2.2 Procurement Control 2.2.1 Codes, standards and regulations 2.2.2 Quality assurence specifications 2.2.3 Proposed changes enacted 2.2.4 Procurement conformance method 2.3 Document Control 2.4 Material Control 2.4.1 Special procedures required 2.4.2 Equipment required 2.4.3 Personnel qualifications 2.5 Process Control 2.3.1 Special procedures 2.5.2 Special. equipment 2.5.3 Personnel qualifications 3.1 Inspection Program Description 3.2 Test Program Description 3.3 Measurement Equipment 3.4 Nonconformance Item and Disposition 3.5 Corrective Actions Instituted 4.0 Records List 7

_ - _ _ _ . _ _ _ _ _ _ _ _ - _ . . _ .m - .. _ _ _ . _ _ _ . _ _

l Revision 0 2.2 Procurement controls. Procurement controls shall consist of procurement specifications, re fe rences to applicable codes, standards and )

regulations, procurement acceptance and document approval. Applicable codes, )

standards, regulations or other quality requirements will be identified and 1 references incorporated into the procurement documents. Procurement document l approvals shall be part of the procurement document. procurement approval will be by a person, other than procurement originator, that is knowledgeable of the procurement specifications and is informed of the quality requirements.

Changes to safety related procurement dauments shall be subject to the same provisions as the ori inal 6 document. Approvd of procurement changes will be included with the procurement document and the chaage identified.

Acceptance of procured items or services shall consist of evidence provided by the contractor, evaluation of the procurement source, inspection at the source or inspection upon receipt. Acceptance of the procurement should require measures such as quality assurance by contractor, inspection and test functions, or controls on materials processes and nonconformances. The methods of acceptance will be identified and documented by approval of the procurement document.

2.3 Document CpK I21 Document control consists of monitoring the development, revision, release and use of documents, drawings or specifications affecting safety.related activities. Document control shall include assurance that safety related documents are identified as such, and are completed and maintained properly. The laboratory Supervisor shall provide control of safety rela,ted documents that are specified secording to the format of Table 3.

2.4 Material control. Procedures shall be written to establish material control when special measures are necessary to assure material quality of safety related items. Controls shall be appliod to activities such as identification, handling, storage, shipping, cleaning and preservation.

Procedures shall specify equipment and personnel required to accomplish the specified material control. Applicable codes, standards, specifications and personnel qualifications shall be documented.

2.5 Process Control. procedures shall be written to establish process control when special measures are necessary to assure process quality of safety related items. Controls shall be applied to activities such as crimping, soldering, welding, painting, cleaning and heat treating, procedures shall specify qualifications of equipment and personnel required to perform the appropriate process control. Applicable codes, standards, specifications and personnel qualifications shall be documented.

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3. Inspection and Corrective Actions 3.1 Innocetion Progr.am. An inspection program shall be established for I safety related items or activities. The inspection program shall apply to ,

construction, procurements, experiment equipment fabrication, and modifications l that effect safety related structures, systems, or components. Persons 1 delegated to perform inspections shall not be the same person involved in the safety related activity but may be from the same or6anization.

The inspection program will consist of written procedures that will include, as appropria';e, procedures specifying characteristics to be inspected, acceptance criteria and inspection hold points.

Procedures should provide for identification of inspected and tested items. Provisions shall be made to clearly identify non conforming items from conforming iteus. In situations that inspections are not advantageous a description shall be provided for monitoring actions.

Procedures shall be written for in service inspections of safety related structures, systems or components.

3.2 Test Program. A test program shall be established for safety related items or activities. The test program shall apply to prototype qualifications, installation proofs and functional tests. Testing shall be performed in accordance with acceptance criteria derived from design or procurement documents.

The test program will consist of written procedures that will include, as appropriate, procedures that specify acceptance criteria, monitoring requirements, equipment required, personnel qualifications, environmental conditions, data acquisition, and documentation of results.

3.3 Measuring and Test Eatioment. Measurement tools, gages, instruments, and other measuring or test devices that measure critical parameters of safety-related items shall be identified. Provisions for identified measuring and test devices shall include availability, adjustment, calibration and accuracy as required for each application. Test equipment will be identified.

3.4 Non Conformine Material and Parts. Non conforming materials and parts associated with safety related structures, systems or components shall be identified. The disposition such as acceptance, repair, rework or rejection of parts from safety related functions will be determined by the person responsible for document control. Repair or reworked parts will be removed or labeled until accepted. Rej ected parts will be removed and labeled. The disposition of non conforming materials will be documented.

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3.5C.gdrective Action. Documentation of specified quality control or assurance documents shall provide evidence of quality of safety related items.

Significant deviations from acceptable quality, repeated quality problems or unresolved quality issues shall be noted and reported in writing to administrative management personnel. It should be recognized that a de te rtaination of a quality problem may be subjective and should include evaluation of the documented quality requirements relative to the impact on the safety.related nature of the item.

3.6 Exocrimental Eauidment. Design, construction, modification, inspection, testing and maintenance of experimental equipment shall be subject to this quality assurance program to the extent that these activities are safety related.

3.7 Reolacement s . Modifications. o r Change s . Insofar as possible, the replacement, modification, or change to structures, systems or components with a safety related function shall be documented as meeting the requirements of the original structure, system or component. Evaluation should establish a performance and reliability equivalent or exceeding the original.

4. Records and Audits 4.1 Ouality Assurance Recorda. Records that document quality of safety.

related items or activities are identified according to Table 3. The records identified consist of inspection and test results, quality assurcnce reviews, quality assurance procedures and engineering analysis in support of design modifications or changes. The records shall be retained with as built drawings, manuals and other records of important facility and system information. The retention period is to be the life of the facility or system for roost, if not all, safety related items.

The retention period is indicative of the expectation that items which affect safety related to a TRIGA reactor are integrally related to the reactor, instrumentation and facility design and should persist for the system or facility life.

4. 7 Audit e . An audit shall be conducted to examine the records and function of the quality assurance pro 6 ram. Audits will occur within two years of the QA Program activities by designated persons that were not directly responsible for the audited functions. Written procedures, Table 4 for the audit will be considered part of the Quality Assurance Program. A report of the audit results, actions to resolve deficiencies and evaluation of the i program will be made to a facility operations committee and university administrative management, and maintained with other Quality Assurance Program documents.

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Revision 0 Table 4 QUALITY ASSURANCE PROGRAM AUDIT PROCEDURES

1. Designate a person or persons responsible to perform the program audit.

2. Determine the date of the previous audit.

3. Review the Quality Assurance Program document.

4. Examine the list of safety related items.

5. Note additions to the safety related items.

6. Identify records applicable to additional items.

7. Determine the location of all indicated records.

8. Review records for abnormalities and completeness.

9. Prepare statement that evaluates functions of Quality Assurance ProSram.

IV. Report findings of audit and program functions to operations committee and management.

References:

1. " Quality Assurance Requirements for Rosearch .Jactors". Nuclear Regulatory Guide 2.5 (77/05).

2. " Quality Assurance program Requirements for Research Reactors",

ANSI /ANS - 15.8 1976 (N402).

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_ _ - - - = _ _ - _ _ _ _ - _ _ _ . - .

Revisiot. O Example Quality Control Record l

1.0 Title

Item identification:

(designate A, B. C, ...) (quality level 1, or 2) 1 Item description, i I

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1.1 Participation

)

(personnel and task assignments)

1.2 Documents

(procedures applicable)

(special provisions)

Applicable Sections ($.f):

Section d.f:

Conditions:

Comments:

Dates:

Activity Initiated Initial Activity Accepted Initial Audit of Activities:

Review by Date: ,

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