Text

Submittal of Operations Quality Assurance Plan Change QA-057
	ML050660379
Person / Time
Site:	South Texas
Issue date:	02/28/2005
From:	Sheppard J; South Texas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	G09.19, NOV-AE-05001855, STI: 31846055
	Download: ML050660379 (82)
	v • d • e

Nuclear Operating Company South T=s/'cdEdkct& a-enemllngft=MS 0 POxr289 IfldmrTs 7748)

February 28, 2005 NOC-AE-05001855 File No.: G09.19 10CFR50.54(a)

STI: 31846055 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units I and 2 Docket Nos. STN 50498 and STN 50-499 Submittal of Operations Quality Assurance Plan Change OA-057

Reference:

Letter, J. J. Sheppard to NRC Document Control Desk, "Submittal of Operations Quality Assurance Plan Change QA-054," dated May 8, 2003 (NOC-AE-03001525)

The South Texas Project Nuclear Operating Company (STPNOC) submits the attached change to revision 16 of the Operations Quality Assurance Plan. This change provides the necessary revisions to the applicable chapters of the Operations Quality Assurance Plan (OQAP) in order to implement the organizational realignment made effective on February 7, 2005.

In addition, this change also relocates requirements that were moved into Chapter 19.0 of the OQAP from the Technical Specification section 6.8 (change QA-054, Revision 15). When QA-054 was made, the Nuclear Regulatory Commission was informed that subsequent changes would eliminate duplication. For example, there were requirements moved into Chapter 19.0 from the Technical Specification section 6.8 regarding Records are more appropriately located in Chapter 14.0, Records Control. The requirements have not been eliminated, they are only relocated.

4n S

NOC-AE-05001855 Page 2 This change does not reduce any element of or responsibilities for implementation of the QA program. This change therefore does not represent a reduction in commitment and does not require NRC approval prior to implementation in accordance with the provisions of IOCFR50.54(a)(3).

There are no commitments in this letter.

If there are any questions regarding this matter, please contact Mr. M. A. McBurnett at (361) 972-7206 or me at (361) 972-8434.

VI

. J. Sheppard President and Chief Executive Officer

Attachment:

QA-057

NOC-AE-05001855 Page 3 cc:

(paper copy) (electronic copy)

Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 David H. Jaffe Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission R. L. Balcom Attention: Document Control Desk Texas Genco, LP One White Flint North 11555 Rockville Pike C. A. Johnson Rockville, MD 20852 AEP Texas Central Company Richard A. Ratliff C. Kirksey Bureau of Radiation Control City of Austin Texas Department of State Health Services 1100 West 49th Street Jon C. Wood Austin, TX 78756-3189 Cox Smith Matthews Jeffrey Cruz J. J. Nesrsta U. S. Nuclear Regulatory Commission R. K. Temple P.1O. Box 289, Mail Code: MNI 16 E. Alarcon Wadsworth, TX 77483 City Public Service C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704

CHANGE QA-057

SUMMARY

OF CHANGES Page 1 of 9 ALL CHANGES ARE IN BOLD TYPE CHAPTER LOCATION ACTION TEXT TOC CH 1.0 INSERT QA-057 TOC CH 2.0 INSERT QA-057 TOC CH 7.0 INSERT QA-057 TOC CH 10.0 INSERT QA-057 TOC CH 13.0 INSERT QA-057 TOC CH 14.0 INSERT QA-057 TOC CH 15.0 INSERT QA-057 TOC CH 16.0 INSERT QA-057 TOC CH 17.0 INSERT QA-057 TOC CH 18.0 INSERT QA-057 TOC CH 19.0 INSERT QA-057 CH 1.0 5.1 DELETE Financial Support, &

Technical Services, Station, Safety and Quality Concerns Program 5.1 INSERT Finance, Oversight 5.1.2 DELETE plant general management, operating experience, production support, projects 5.1.2 INSERT operations, maintenance, chemistry, health physics

CHANGE QA-057

SUMMARY

OF CHANGES Page 2 of 9 ALL CHANGES ARE IN BOLD TYPE CH 1.0 5.1.3 DELETE Engineering & Technical Services (E&TS), quality &

licensing, probablistic risk assessment, and training functions, E&TS 5.1.3 (Is5 para) INSERT Oversight (2 places),

nuclear safety assurance, performance improvement, training, plant protection, and employee concerns 5.1.3 (2 nd 3r 4h para) DELETE This text will be incorporated and re-aligned to the Manager, Nuclear Safety Assurance in the new 5.1.3.1 New 5.1.3.1 REWRITE The Manager, Nuclear Safety Assurance has the independence to conduct Quality activities without undue pressure of cost or schedule and is responsible for the following:

Development, maintenance, and independent verification of implementation of the STP Quality Program; making periodic reports on its effectiveness; review of selected documents which control activities within its scope; and preparation,

CHANGE QA-057

SUMMARY

OF CHANGES Page 3 of 9 ALL CHANGES ARE IN BOLD TYPE CH 1.0 New 5.1.3.1 REWRITE control, and approval of the OQAP and revisions thereto;ldentify, initiate, recommend, or provide solutions to quality-related problems and verify the implementation and effectiveness of the solutions; and Independent oversight activities, including audits, independent assessments, evaluations, surveillances, performance monitoring,"

inspections, independent -

oversight of NDE examinations, and administration of organizational unit independent review activities.

5.1.3.2 DELETE senior management of the Quality & Licensing function; reports directly; relating to Licensing, the management of the Programmatic Oversight function

CHANGE QA-057

SUMMARY

OF CHANGES Page 4 of 9 ALL CHANGES ARE IN BOLD TYPE CH 1.0 5.1.3.2 INSERT Manager, Nuclear Safety Assurance has unfettered access; and the Board of Directors; where a conflict of interest could exist for the Manager, Nuclear Safety Assurance, the Quality Manager,; or the Board of Directors 5.1.3.3 DELETE senior management of the Quality & Licensing function has 5.1.3.3 INSERT Manager, Nuclear Safety Assurance and the Quality Manager have 5.1.3.4 DELETE senior management of the Probabilistic;Assessment function 5.1.3.4 INSERT Manager, Management New 5.1.4 INSERT The Vice President, Engineering is responsible for implementing quality program requirements applicable to the following functions: nuclear fuels & safety analysis, plant engineering, design engineering, and administrative support. The senior management of these functions report to the Vice President, Engineering New 5.1.5 (old 5.1.4) DELETE Station (2 places); human resources, plant protection

CHANGE QA-057

SUMMARY

OF CHANGES Page 5 of 9 ALL CHANGES ARE IN BOLD TYPE CH 1.0 New 5.1.6 (old 5.1.5) DELETE Financial Support (2 places); supply chain management; nuclear accounting; and financial service New 5.1.6 INSERT Finance (2 places); nuclear purchasing and material management Old 5.1.6 DELETE The Manager, Safety Quality Concerns Program is responsible for implementing quality program requirements applicable to this function.

CH2.0 5.1.2 DELETE Engineering & Technical Services (E&TS) 5.1.2 INSERT Oversight 5.8.2 DELETE Engineering & Technical Services; senior management of the Quality & Licensing function 5.8.2 INSERT Oversight; Manager, Nuclear Safety Assurance CH 7.0 5.4.1.1 DELETE & Technical Services 5.4.1.1 INSERT , Nuclear Safety Assurance 5.4.1.6 DELETE senior management of the Quality & Licensing function

CHANGE QA-057

SUMMARY

OF CHANGES Page 6 of 9 ALL CHANGES ARE IN BOLD TYPE CH 7.0 5.4.1.6 INSERT Manager, Nuclear Safety Assurance or the Quality Manager 5.4.2.1 DELETE senior management of the Quality & Licensing function 5.4.2.1 INSERT Manager, Nuclear Safety Assurance or the Quality Manager 5.4.3.2 DELETE senior management of the.

Quality & Licensing function 5.4.3.2 INSERT Manager, Nuclear Safety Assurance or the Quality Manager 5.5.5 DELETE & Technical Services 5.5.5 INSERT , Support 5.5.7 DELETE & Technical Services 5.5.7 INSERT or Nuclear Safety Assurance CH 10.0 5.1.7.1 DELETE & Technical Services (3 places) 5.1.7.1 INSERT , Nuclear Safety Assurance; or Nuclear Safety Assurance personnel; and/or Nuclear Safety Assurance personnel

CHANGE QA-057

SUMMARY

OF CHANGES Page 7 of 9 ALL CHANGES ARE IN BOLD TYPE CH 10.0 5.1.7.2 DELETE & Technical Services (2 places) 5.1.7.2 INSERT and/or Nuclear Safety Assurance personnel (2 places)

CH 13.0 5.2.9 DELETE & Technical Services 5.2.9 INSERT , Nuclear Safety Assurance, 5.6 DELETE senior management of the Quality & Licensing function 5.6 . INSERT Manager, Nuclear Safety Assurance or Quality Manager CH'14.0 5.11 INSERT This entire section was moved from Chapter 19.0, section 5.4 to consolidate requirements concerning records into one chapter.

CH 15.0 5.2.1 DELETE The following areas are included in the audit program:

5.2.1 INSERT These audits shall encompass: (Moved from Chapter 19.0, section 5.4)

CHANGE QA-057

SUMMARY

OF CHANGES Page 8 of 9 ALL CHANGES ARE IN BOLD TYPE CH 15.0 5.2.1.1 thru 5.2.1.9 DELETE This text is being removed to consolidate the audit activities into the appropriate chapter. It is being replaced as noted below with the information from chapter 19.0 that resulted from moving the applicable portions of the Technical Specifications section 6.8 to the OQAP.

5.2.1.1 thru 5.2.1.11 INSERT The text was moved from Chapter 19.0, sections 5.2.4.1 through 5.2.4.11 5.2.3.1 (2 nd para) DELETE senior management of the Quality & Licensing function; Engineering &

Technical Services 5 .2 . 3 . 1 (2nd para) INSERT the Manager, Nuclear Safety Assurance; Oversight CH 16.0 5.1 DELETE Engineering & Technical Services 5.1 INSERT Oversight 5.2 DELETE senior management of the Quality & Licensing function 5.2 INSERT Manager, Nuclear Safety Assurance

CHANGE QA-057

SUMMARY

OF CHANGES Page 9 of 9 ALL CHANGES ARE IN BOLD TYPE CH 17.0 5.2 DELETE & Technical Services (E&TS); E&TS 5.2 INSERT Engineering CH 18.0 5.1 DELETE & Technical Services (E&TS); E&TS 5.1 INSERT Engineering CH 19.0 5.2.4 DELETE These audits shall encompass: (This has been moved to Chapter 15.0, section 5.2.1) 5.2.4.1 thru 5.2.4.11 DELETE These sections have been relocated to Chapter 15.0, sections 5.2.1.1 thru 5.2.1.11) 5.3.1.1 INSERT and Technical Requirements Manual 6.8 5.4 DELETE This entire section through 5.4.3.16 has been relocated to Chapter 14.0, Sections 5.11 through 5.11.3.16

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OPERATIONS QUALITY ASSURANCE PLAN TABLE OF 16 CONTENT TABLE OF CONTENTS PAGE 1OF2 EFFECTIVE DATE 02-01-04 Chapter Title Effective Effective Change Number Chapter Revision Date Notice No.

Definitions 9 2-1-02 1.0 Organization 12 2-1-04 QA-057 2.0 Program Description 14 2-1-04 QA-056,QA-057 3.0 Conduct of Plant Operations 7 2-1-98 4.0 Qualification, Training, and 6 2-1-98 Certification of Personnel 5.0 Maintenance, Installation of 5 2-1-98 Modifications, and Related Activities 6.0 Design and Modification Control 8 2-1-02 7.0 Procurement 9 2-1-02 QA-057 8.0 Control and Issuance of 6 2-1-98 Documents 9.0 Control of Material 6 2-1-98 10.0 Inspection 9 2-1-02 QA-057 11.0 Test Control 7 2-1-00 12.0 Instrument and Calibration 6 2-1-98 Control 13.0 Control Of Conditions Adverse 10 2-1-02 QA-057 to Quality 14.0 Records Control 7 2-1-02 QA-057 15.0 Quality Oversight 9 2-1-04 QA-057 Activities

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OPERATIONS QUALITY ASSURANCE PLAN TABLE OF 16 CONTENT TABLE OF CONTENTS PAGE 2 OF2 EFFECTIVE DATE 02-01-04 Chapter Title Effective Effective Change Number Chapter Revision Date Notice No.

16.0 Independent Technical 8 2-01-04 QA-057 Review 17.0 ASME Code Section XI - 6 2-01-00 QA-057 Repairs and Replacements 18.0 ASME Code Section XI - 7 2-01-00 QA-057 Inservice Inspection and Testing 19.0 Administrative Controls I

2-01-04 QA-056, QA-057

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OPERATIONS QUALITY ASSURANCE PLAN 1.0 12 ORGANIZATION PAGE I OF 4 EFFECTIVE DATE 02-01-04 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 organizations for the South Texas Project Electric Generating Station (STP).

2.0 SCOPE 2.1 STP Nuclear Operating Company (STPNOC), as licensee, has the Quality responsibility for design, engineering, procurement, fabrication, modification, maintenance, repair, in-service inspection, refueling, testing, and operation of the STP.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 None 5.0 RESPONSIBILITIES 5.1 The STPNOC is comprised of Generation, Oversight, Engineering, Finance, and >

Support. The senior management of these groups report to the President and Chief Executive Officer.

5.1.1 The President and Chief Executive Officer has overall responsibility for the implementation of the Operations Quality Assurance Program and approving the Operations Quality Assurance Plan (OQAP) and revisions thereto. The President and Chief Executive Officer shall designate those members of senior management to function as the Senior Management Team.

5.1.2 The Vice President, Generation is responsible for implementing quality program requirements applicable to staffing STP with qualified personnel and acquiring and coordinating the assistance of internal and external organizations for the following functions including: generation support, c operations, maintenance, chemistry, health physics, and work 6 management. The senior management of these functions report to the Vice President, Generation.

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OPERATIONS QUALITY ASSURANCE PLAN 1.0 12 ORGANIZATION PAGE 2 OF 4 EFFECTIVE DATE 02-01-04 5.1.2.1 The Plant General Manager has prime responsibility for the safe operations of the units. The plant staff, under the direction of the Plant General Manager, develop detailed procedures and instructions for testing, operation, modification, and maintenance of the STP.

5.1.3 The Vice President, Oversight is responsible for implementing quality program requirements applicable to the following functions: nuclear safety assurance, performance improvement, training, plant protection, and employee concerns. The senior management of these functions report to the Vice President, Oversight.

5.1.3.1 The Manager, Nuclear Safety Assurance has the independence to conduct Quality activities without undue pressure of cost or schedule and is responsible for the following:

Development, maintenance, and independent verification of implementation of the STP Quality 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; Identify, initiate, recommend, or provide solutions to quality-related problems and verify the implementation and effectiveness of the solutions; and Independent oversight activities, including audits, independent assessments, evaluations, surveillances, performance monitoring, inspections, independent oversight of NDE examinations, and administration of organizational unit independent review activities.

5.1.3.2 The Manager, Nuclear Safety Assurance, at his discretion, has unfettered access to the President and Chief Executive Officer and the Board of Directors. During performance of independent oversight of activities where a conflict of interest could exist for the Manager, Nuclear Safety Assurance, the Quality Manager, at his discretion, may report to the President and Chief Executive Officer or the Board of Directors.

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OPERATIONS QUALITY ASSURANCE PLAN 1.0 12 ORGANIZATION PAGE 30F4 EFFECTIVE DATE 02-01.04 5.1.3.3 The Manager, Nuclear Safety Assurance and the Quality >

Manager have the authority to stop work for cause. This authority has been granted by the President and Chief Executive Officer. The Quality organization, including the inspection staff, is based upon the anticipated Quality involvement in operations, modification, and maintenance activities.

5.1.3.4 The Manager, Risk Management is responsible for activities 6O related to the Comprehensive Risk Management Program, including oversight of Probabilistic Safety Assessment activities. The Comprehensive Risk Management Expert Panel guides the implementation of the Comprehensive Risk Management Program and is composed of a Chairman and additional senior level management designated by the President and Chief Executive Officer.

5.1.4 The Vice President, Engineering is responsible for implementing quality program requirements applicable to the following functions: nuclear fuels >

& safety analysis, plant engineering, design engineering, and administrative support. The senior management of these functions report to the Vice President, Engineering 5.1.5 The General Manager, Support is responsible for implementing quality c program requirements applicable to the following functions: information >

technology and records management services and administration for STP. <

The senior management of these functions report to the General Manager, Support.

5.1.6 The General Manager, Finance is responsible for implementing quality program requirements applicable to the following function: nuclear purchasing and material management activities. The senior management 6 of this function reports to the General Manager, Finance.

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OPERATIONS QUALITY ASSURANCE PLAN 1.0 12 ORGANIZATION PAGE 4 OF 4 EFFECTIVE DATE 02-01-04 6.0 REQUIREMENTS 6.1 The fundamental responsibility for implementing quality program requirements is assigned to all personnel performing activities affecting the safe and reliable operation of the STP. These personnel and their management are responsible for implementing through approved procedures and other work documents, the quality assurance program controls described in the OQAP. Line organizational details and responsibilities are further described in STP UFSAR Chapter 13. 1.

7.0 DOCUMENTATION 7.1 None 8.0 ATTACHMENTS 8.1 None

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE IOF16 EFFECTIVE I DATE 02-01-04 1.0 PURPOSE 1.1 The purpose of this chapter is to define criteria and establish administrative controls for implementation of the Quality Assurance (QA) Program for the South Texas Project Electric Generating Station (STP).

2.0 SCOPE 2.1 The QA Program is implemented and controlled in accordance with the Operations Quality Assurance Plan (OQAP) and is applicable to structures, systems, and components to an extent consistent with their importance to safety, and complies with the requirements of I OCFR50, Appendix B and other program commitments as appropriate.

2.2 The QA Program will also extend, as applicable and/or determined by STP management, to programs including IOCFR7I, Subpart H (except design and fabrication of NRC certified radioactive waste shipping casks), ASME Boiler and Pressure Vessel Code, Sections III and XI; and to quality-related areas as defined herein including the Fire Protection Program, Emergency Plan, Radiological Environmental Monitoring Program, Radwaste Management Program, Computer Program Verification and Control, Seismic and Environmental Equipment Qualification Programs, Radiation Protection Program, and Station Blackout (SBO) systems and equipment.

3.0 DEFINITIONS 3.1 Comprehensive Risk Management - A process by which the change in risk to station personnel, the public's health and safety are evaluated as a result of changes in commitments, processes, activities, and human and equipment performance.

3.2 Graded Qualitv Assurance - The process by which risk-based methodology [i.e.,

Probabilistic Safety Assessment (PSA)] and deterministic and performance-based information analyses are combined to establish appropriate levels of programmatic controls for SSCs and appropriate levels of first line and independent oversight needed to provide the necessary assurance that SSCs will operate safely.

3.3 Full program controls - The highest levels of controls and oversight applied to safety-related SSCs categorized as High Safety Significant (HSS), as prescribed in Table I to this chapter and throughout individual OQAP chapters.

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 2 F 16 EFFECTIVE DATE 02-01-04 3.4 Basic program controls - Levels of control and oversight, lower than in the Full Program, applied to safety-related SSCs categorized as Medium Safety Significant (MSS), as prescribed in Table I to this chapter and throughout individual OQAP chapters.

3.5 Targeted program controls - Selected program controls applied to certain non-safety-related SSCs categorized as either HSS or MSS.

3.6 Limited program controls - Limited controls applied to safety-related SSCs categorized as either Low Safety Significant (LSS) or Non-Risk Significant (NRS).

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 4.6 10CFR50.54(a) 4.7 Updated Final Safety Analysis Report 4.8 Safety Evaluation on Exemption Requests from Special Treatment Requirements of 10 CFR Parts 21, 50, and 100 (TAC NOS. MA6057 AND MA6058) 5.0 REQUIREMENTS 5.1 General Program Requirements 5.1.1 The OQAP shall be prepared and maintained to prescribe the STP QA Program. The OQAP reflects the quality program policies to be implemented. The OQAP describes the organization and responsibilities for attainment of quality objectives and verification of conformance to established requirements. The QA Program shall be in effect throughout the operating life of the STP.

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 3 F 16 EFFECTIVE DATE 02-01-04 5.1.2 The President and Chief Executive Officer has overall responsibility for c quality assurance. The Vice President, Oversight is responsible for the development and maintenance of the OQAP. -

5.1.3 The operations phase of the STP includes design, procurement, fabrication, repair, testing, operation, maintenance, refueling, inspection, independent oversight, modification, and other activities as discussed Table I to this chapter and throughout the OQAP. STP and its vendors are required, as appropriate, to comply with the criteria established by 10CFR50, Section 50.55a; 10CFR50, Appendix A, General Design Criterion (GDC) 1; 10CFR50, Appendix B, and 10CFR71, Sub-Part H (except design and fabrication of NRC certified radioactive waste shipping casks). These regulations are not applicable to LSS and NRS safety-related components, to the extent that the Nuclear Regulatory Commission has granted STP an exemption from the regulations as described in Reference 4.8.

STP will implement, as specified, the Regulatory Guides (RG) and implementing American National Standards Institute (ANSI) standards contained in Table I of this chapter.

5.1.4 STP shall maintain the OQAP as an effective and meaningful document to provide programmatic direction for the station. Changes to the OQAP shall be accomplished as prescribed by 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.

5.2 Organizational Independence 5.2.1 The reporting arrangement utilized by the Quality organization ensures that those personnel performing independent oversight have the organizational freedom to:

5.2.1.1 Identify quality problems.

5.2.1.2 Initiate, recommend, or provide solutions.

5.2.1.3 Verify implementation of solutions.

5.2.2 Personnel verifying compliance with quality requirements do not have direct responsibility for the performance of or directly supervise the activity being verified.

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 4 OF 16 EFFECTIVE DATE 02-01-04 5.3 Graded Quality Assurance 5.3.1 Graded Quality Assurance (GQA) is fundamental to the STP QA Program.

It is described in more detail in the implementing procedure for the STP Comprehensive Risk Management (CRM) Program.

5.3.2 GQA is a process by which risk-based methodology [i.e., Probabilistic Safety Assessment (PSA)], deterministic insights, and performance-based information are combined and analyzed to determine what levels of programmatic controls are needed for structures, systems, and components (SSCs) and what levels of first line and independent oversight are needed to provide assurance that items will operate safely and activities are accomplished as prescribed.

5.3.3 Selected systems are evaluated, at the component level, by a cross-discipline Expert Panel comprised of high level station management.

Initial evaluations are performed by the Working Group.

5.3.4 These recommendations are developed in consideration of the risk significance of system functions, components' contribution to core damage frequency and large early release frequency, components' critical attributes (needed to support risk significant system functions),

performance, regulatory/QA requirements, and other deterministic considerations as prescribed in the Comprehensive Risk Management procedures.

5.3.5 Program control recommendations are developed by the Working Group and ultimately approved by the Expert Panel and forwarded to the site for implementation. Controls are implemented in four graded applications (i.e., "Full", "Basic", "Targeted", and "Limited").

5.3.6 "Full" program controls are applied to safety-related SSCs categorized as HSS. These "Full" levels of controls and oversight are designed to provide a high degree of confidence that SSCs perform safely and activities are performed as expected. Table I to the OQAP chapter prescribes the program commitments applicable to "Full" program activities.

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 5 F 16 EFFECTIVE DATE 02-01-04 5.3.7 "Basic" program controls are applied to safety- related SSCs categorized as MSS. These are lower levels of control and oversight, designed to maintain/preserve those identified critical attributes of SSCs needed to support risk significant system functions. These controls are intended to reflect economical and efficient business practices. Table I to the OQAP chapter prescribes the program commitments applicable to "Basic" program activities.

5.3.8 "Limited" program controls are applied to safety-related SSCs categorized as either LSS or NRS. Only specific program controls related to the activities listed in the following subparagraphs are applicable to these SSCs. The other chapters of the OQAP are not applicable to safety-related LSS and NRS SSCs. Instead, the treatment processes applicable to these SSCs are described in the Updated Final Safety Analysis Report Section 13.7.3.3 and implementing procedures:

5.3.8.1 Those elements in Chapter 1.0 that are needed to implement and control activities described above; 5.3.8.2 Applicable requirements in this Chapter; 5.3.8.3 Modification/design activities as described in Chapter 6.0; and 5.3.8.4 Corrective action as described in Chapter 13.0.

5.3.9 "Targeted" program controls are applied to non-safety related SSCs, for which IOCFR50, Appendix B is not applicable, categorized as HSS or MSS . Specific program controls consistent with applicable portions of the "full" and "basic" program controls are applied to those items in a selected manner, "targeted" at those characteristics or critical attributes that render the SSC risk significant.

5.3.10 Safety-related components that are highly reliable, yet whose failure would result in a significant increase in risk, will receive Full program coverage, or will be evaluated based on their risk significance to ensure that Full program controls are applied to their critical attributes.

5.3.11 SSCs governed by the OQAP shall retain their current program coverage until such time as prescribed risk-informed, performance-based analyses are completed and approved, and they are placed into the graded program categories (i.e., "Full", "Basic", "Targeted", or "Limited") as appropriate.

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 6 OF 16 EFFECTIVE DATE 02-01-04 5.3.12 A vital element of the GQA program is the "feedback" loop. On a periodic basis, and as prescribed in the Comprehensive Risk Management procedure, the GQA Working Group and Expert Panel shall review any changes to the PSA information and performance/operating experience that could result in recategorization of an SSC. These reviews are also used to assess the effectiveness and appropriateness of in-place quality program controls. Adjustments shall be made as determined necessary.

5.4 Delegation of QA Functions 5.4.1 The OQAP may be executed in whole or part by subcontract personnel.

However, STP will retain responsibility for the total quality assurance program, and Quality organization personnel will perform appropriate oversight activities of subcontracted activities.

5.5 Identification of Safety Significant Structures, Systems, and Components 5.5.1 The program described herein is applied to activities affecting the safety functions of those structures, systems, and components which prevent, or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. The structures, systems, and components controlled are listed in UFSAR Section 3.2, along with their associated fire protection systems. UFSAR Section 3.2 also identifies those structures, systems, and components which may not represent a safety significant/risk important concern but to which the STP OQAP is applied.

5.5.2 The fire protection QA Program is part of the overall STP Operations QA Program. Fire protection QA Program criteria are implemented as part of the Operations QA Program.

5.5.3 Expendable or consumable items necessary for the functional performance of 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.

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OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 7 OF 16 EFFECTIVE DATE 02-01-04 5.6 QA Program Documents 5.6.1 The QA Program shall be implemented with documented instructions, procedures, and drawings which include appropriate quantitative and qualitative acceptance criteria for determining that prescribed activities have been satisfactorily accomplished. Procedures shall include the control of the sequence of required inspections, tests, and other operations when important to quality. To change these controls, the individual procedure must be changed and shall require the same level of 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 significance by individuals qualified to do so.

5.7 Personnel Indoctrination and Training 5.7.1 General indoctrination and training programs shall be provided for site personnel to assure that they are knowledgeable regarding quality programs and requirements. The training requirements for ST? personnel are described in UFSAR Section 13.2. Personnel performing complex, unusual, or potentially hazardous work shall be instructed in special indoctrination or briefing sessions. Emphasis shall be on 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.

5.8 Policies and Goals 5.8.1 STP policy is to assure that the design, procurement, construction, testing, and operation of the STP are in conformance with specifications, procedures, codes, commitments and Nuclear Regulatory Commission (NRC) regulations to the extent not exempted. The responsibility of each organization supporting the STP is to ensure that the requirements stated in this QA Program are incorporated into procedures. Adherence to those procedures is mandatory for all STP organizations and contractors or vendors providing items or services covered by the QA Program.

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Chapter N.

OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 8 OF 16 EFFECTIVE DATE 02-01-04 5.8.2 The OQAP identifies activities and establishes requirements for procedures which identify, report, and verify the resolution of 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, the Vice President, Oversight or Manager, °6 Nuclear Safety Assurance shall present the problem to the President and Chief Executive Officer for resolution.

5.9 Control of Activities 5.9.1 The OQAP requires Quality department review and/or approval of procedures which control selected activities. These procedures shall require the use of the proper equipment, completion of prerequisites for starting an activity, and suitable environment for performing the activity.

Procedures will comply with the appropriate standards.

5.9.2 STP personnel attend planning, scheduling, and status meetings as necessary to assure adequate quality coverage and program application exists.

5.10 Management Review 5.10.1 The implementation of both line and OQAP requirements shall be verified through independent oversight activities. The Quality organization shall conduct independent oversight activities of the operating plant and of the interfacing organizations' activities; 5.10.2 Independent oversight of the implementation of the OQAP is conducted under the cognizance of the Senior Management Team and results are transmitted to appropriate line and senior management, including the President and Chief Executive Officer for review and/or action.

5.10.3 STP may use the services of architect-engineer firms, Nuclear Steam Supply System (NSSS) suppliers, fuel fabricators, constructors, and others which provide or augment STP efforts during operations. As applicable, the QA programs of such contractors or consultants shall be subject to review, evaluation, and acceptance by the Quality organization before initiation of activities affected by the program.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 2.0 14 PROGRAM DESCRIPTION PAGE 9 OF 16 EFFECTIVE DATE 02-01-04 5.11 Computer Code Programs 5.1 1.1 The development, maintenance, and use of computer code programs will be controlled. Prior to use of a computer code program, 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.

7.0 ATTACHMENTS 7.1 Table I - Program Commitments

TABLE I PROGRAM COMMITMENTS R.GJANSI STANDARD FULL PROGRAM BASIC PROGRAM R.G. 1.8, rev. 1 (9/75) No exceptions taken. No exceptions taken.

ANSI NI 8.1, 1971 4.2.2-The Operations Manager requirements regarding holding a Senior Reactor Same as fuill.

Operator license are met by the Unit Operations Managers.

R.G. 1.28, rev. 0 (6/72) This R.G. is not applicable to operations phase activities. Same as full.

ANSI 45.2, 1971 This standard is not applicable to operations phase activities. Same as fuill.

R.G. 1.33, rev. 2 (2/78) C.2 - the specific revisions of the listed standards to which STP is committed are Same as full.

in this table and are not necessarily the "latest" revision.

C.4 - Chapter 15.0 of the STP OQAP describes the audit program at STP that Same as full.

meets the intent of R.G. 1.33, rev. 2, position C.4 regarding frequency of audits C.4.a.b.c - STP performs these audits in accordance with a nominal biennial Same as full.

frequency.

ANSI N18.7 - I976/ANS 3.2 3.4.2 - refer to R.G. 1.8 regarding Operations Manager holding a Senior Reactor Same as fuill.

Operator license.

3.4.2 refer to R.G. refer to R.G. 1.5.8 regarding use of personnel not qualified in accordance with ANSI N45.2.6.

4.5 - refer to R.G. 1.33 coverage regarding audit frequency. Same as full.

5.2.6 (5th paragraph) - independent verification may be concurrent with (same Same as full.

time as) work perfonnance.

Operations Qualily Assurancc Plan, Chapter 2.0, Revision 14 Page 1I0 of 16

TABLE I PROGRAM COMMITMENTS RG./ANSI STANDARD FULL PROGRAM BASIC PROGRAM ANSI N18.7/ANS 3.2 (cont'd) 5.2.7 (I st paragraph) - STP will use current approved design bases as opposed to Same as full.

original design bases.

5.2.7 - STP will perform inspection as deemed necessary, based on the relative complexity of the work.

5.2.7.1 (5th paragraph) - STP takes exception to use of the word "promptly" with Same as f1l1l.

regard to determining, evaluating and recording the causes of malfinctions. The STP Corrective Action Program includes the elements with regard to timeliness of action associated with causal analyses.

5.2.7.2 - refer to table coverage of ANSI N45.2. 11, 1974.

5.2.13 (Ist paragraph) - refer to table coverage of ANSI N45.2.13, 1976.

5.2.13.1 (Ist paragraph)-referto table coverage of ANSI N45.2, 1971.

5.2.13.4 (5'h paragraph) - refer to table coverage of ANSI N45.2.2, 1972.

5.2.15 (4th paragraph) - Chapter 8.0 of the OQAP describes the requirements for Same as full.

control and issuance of documents, which meets the intent of R.G. 1.33, rev. 2.

The intent of the biennial review is accomplished by other controls that assure that procedures are appropriately reviewed and revised to incorporate infornation based on plant operations, design changes, regulatory requirements, industry experience and other conditions that may impact plant procedures.

Operations Quality Assurance Plan, Chapter 2.0, Revision 14 Page I of 16

TABLE I PROGRAM COMMITMENTS RG.IANSI STANDARD FULL PROGRAM BASIC PROGRAM 5.2.17 (3rd paragraph) - STP may not implement the requirement for conduct of inspections in a manner similar to that associated with construction phase activities (i.e.,

regarding use of personnel not qualified to ANSI N45.2.6)

R.G. 1.38, rev. 2 (5/77) No exceptions taken. No exceptions taken.

ANSI N45.2.2, 1972 2.4 - Audit personnel are qualified in accordance with STP's commitment to R.G. Same as full.

1.146/ANSI 45.2.23.

2.4 - Offsite oversight of vendors of items in the Basic category will only be performed as deemed necessary.

5.2.1 - These activities do not constitute an "inspection" as defined in Same as Full ANSI/ASME NQA-1, 1983, Supplement S-I, Terms and Definitions. Therefore, the requirements for qualification to ANSI N45.2.6 as stated in Section 2.4 do not apply to personnel performing these activities.

R.G. 1.58, rev. 1(9/80) C.2 - STP is committed to ASNT-TC-l A, 1980. STP treats the recommendation Same as full.

("should") of the 1980 edition as requirements ("shall").

ANSI N45.2.6, 1978 1.2 (1st paragraph) - with the exception of receipt inspection, personnel may perform inspections, examinations and tests provided they are experienced, task qualified journeymen, or supervisors, who did not perform or directly supervised the activity being inspected, examined or Operations Quality Assurance Plan, Chapter 2.0, Revision 14 Page 12 of 16

TABLE I PROGRAM COMMITMENTS R.GJANSI STANDARD FULL PROGRAM BASIC PROGRAM ANSI N45.2.6, 1978 tested. These individuals shall also receive training to the applicable inspection procedure,processes, methods in accordance with a Quality approved training program; and Quality will provide periodic oversight of the inspection activities.

1.2 (3rd paragraph) - refer to table coverage of R.G. 1.28. Same as fuill.

1.4.4 - refer to table coverage of R.G. 1.74/ANSI N45.2. 10. Same as fuill.

Personnel performing the activities stated in ANSI N45.2.2, Section 5.2.1 do not Same as Full require qualification to this Standard. (see exception to ANSI N45.2.2)

R.G. 1.64, rev. 2 (6/76) No exceptions taken. C.2 - STP may implement the requirement regarding design verification as prescribed in ANSI N45.2.11, 1974, 6.1, second paragraph/second sentence, as opposed to R.G. wording.

ASNI N45.2.11, 1974 No exceptions taken. 3.2 (1" paragraph) - STP will require personnel to consider items I through 28, but a documented checklist may not be required.

6.3 - Verification and checking of design may be accomplished through supervisory or management review/approval as provided for in 6.1 Personnel will be required to consider Operations Quality Assurance Plan, Chapter 2.0, Revision 14 Page 13of 16

TABLE I PROGRAM COMMITMENTS RG.IANSI STANDARD FULL PROGRAM BASIC PROGRAM ANSI N45.2.1 1, 1974 items I through 19, but a documented checklist may not be required.

R.G. 1.74 (2/74) Not applicable to STP. STP uses ANSI/ASME NQA-1-1983 for Quality Same as full.

Assurance Terms and Definitions.

ANSI N45.2.10, 1973 Same as R.G. 1.74 above. Same as full.

R.G. 1.88, rev. 2 (10/76) No exceptions taken. Same as full.

ANSI N45.2.9, 1974 Section 5.6 - supplement the provisions of this section by providing for alternate Same as full.

temporary storage of records. Allow the use of 1-hotir fire rated cabinets to store records that are awaiting processing (e.g., processing into Optical Disk Storage).

Storage of these records in I-hour fire rated cabinets will be controlled by procedure which specify a maximum allowable time limit. Cabinets housing these records shall be controlled for access and shall be located in an area protected by sprinklers.

R.G. 1.123, rev. 1 (7/77) C.6.b.and e. -The referenced section of ANSI N45.2.13 will be implemented as written.

ANSI N45.2.13, 1976 Various sections refer to ANSI N45.2. Refer to table coverage of R.G. 1.28 and Same as full.

ANSI N45.2.

5.3 and 5.4 - Provision are established for, in special cases and with management Same as fuill.

approval, completion of these activities after award of contract.

9.0 - This section will be implemented based on the scope, complexity and safety Same as full.

significance of the items being procured.

10.3.1 - This section will only be implemented as deemed necessary.

Operations Quality Assurance Plan, Chapter 2.0, Revision 14 Page 14of 16

TABLE I PROGRAM COMMITMENTS R.GJANSI STANDARD FULL PROGRAM BASIC PROGRAM ANSI N45.2.13, 1976 12-TThis section will only be implemented as deemed necessary for audits of suppliers.

R.G. 1.144, rev. 1 (9/80) C.1 -refer to table coverage of R.G. 1.28 and ANSI N45.2. Same as flIl.

C.3a(l) - refer to table coverage of R.G. 1.33 regarding audit frequency. Same as fuill.

c.3.b STP will audit vendors only as deemed necessary. STP will perform biennial evaluations.

ANSI N45.2.12, 1977 No exceptions taken. STP will audit vendors only as deemed necessary. These audits will be conducted as unplanned/unschiedtiled

.__ .audits.

R.G. 1.146, rev. 0 (8/80) C. I - refer to table coverage of R.G. 1.28 and ANSI N45.2.

Refer to table coverage of R.G. 1.74 and ANSI N45.2.10 Same as full.

ANSI N45.2.23, 1978 1.2 - refer to table coverage of R.G. 1.28. Same as fill.

1.4 - refer to table coverage of R.G. 1.74. Same as full.

2.21 - refer to table coverage of R.G. 1.28. Same as filll.

2.3.3.1 - refer to table coverage of R.G 1.28. Same as full.

Opcrations Quality Assurance Plan, Chapter 2.0, Rcvision 14 Page 15 of 16

TABLEI PROGRAM COMMITMENTS R.GJANSI STANDARD FULL PROGRAM BASIC PROGRAM ANSI N45.2.23, 1978 (continued) 2.3.4 - In lieu of the requirements of section 2.3.4 of ANSI N45.2.23-1978 Same as full the following alternative is acceptable:

Prospective lead auditors shall demonstrate their ability to properly C0 implement the audit process and effectively lead an audit team. This 0 LA demonstration process will be described in implementing procedures and CN~

will include the evaluation and documentation of the results of the demonstration. Regardless of the methods used for the demonstration, the prospective lead auditor is required to participate in at least one nuclear quality assurance audit within the year preceding the individual's effective date of qualification. Upon successful demonstration of the ability to effectively implement the audit process and effectively lead audits, and having met the other provisions of Section 2.3 of ANSI N45.2.23-1978, the individual may be certified as being qualified to lead audits.

1- t For Regulatory Guides addressed by the table, and unless specific clarification or exception is indicated, STP will implement the Regulatory Guide positions, including recommendations.

For ANSI Standards addressed by this table, and unless specific clarification or exception is indicated, STP will treat ANSI requirements (i.e., "shall")

as such - except in instances where the standard itself provides options or requires a graded approach - this notwithstanding the general applicability statements found in many standards (i.e., section 1.0)

Operations Quality Assurance Plan, Chapter 2.0, Rcvision 14 Page 16of 16

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE I F II EFFECTIVE DATE 02-01-02 1.0 PURPOSE 1.1 The purpose of this chapter is to establish the requirements for procurement of items and services for the South Texas Project Electric Generating Station (STP).

2.0 SCOPE 2.1 This chapter applies to the procurement of items and services for use at STP which are subject to the controls of this Quality program. These activities include procurement document control, bid evaluation, vendor evaluation, verification of vendor activities and receiving inspection.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 10CFR50, Appendix B 4.2 10CFR21, Reporting of Defects and Noncompliance 4.3 OQAP Chapter 2.0, Table I 4.4 EPRI NP-5652 (NCIG-07), Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Application 4.5 OQAP Chapter 4.0, Qualification, Training and Certification of Personnel 4.6 OQAP Chapter 13.0, Control of Conditions Adverse to Quality 4.7 OQAP Chapter 14.0, Records Control 4.8 Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulent Marketed Products

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 2 OF 11 EFFECTIVE DATE 02-01-02 5.0 REQUIREMENTS 5.1 Procurement Document Preparation, Review and Control 5.1.1 Responsibility for procurement is a joint effort of all the departments within the STP Nuclear Operating Company (STPNOC). The department requesting the material or service provides technical content and quality requirements. Design Engineering/Nuclear Purchasing & Material Management is responsible to provide input to the requesting department on technical content and quality requirements, as requested. Quality will concur with all changes to quality requirements.

5.1.2 The sequence of preparation, review, approval, and issuance of procurement documents is generally as follows:

5.1.2.1 Purchase Requisitions

Purchase requisition forms shall be used to initiate the procurement of materials, parts, components, and services.

Procurement may be initiated by any STPNOC personnel.

Purchase requisitions shall include material and component identification requirements, drawings, specifications, standards, inspection and test requirements, and special process instructions as appropriate.

Purchase requisitions for materials, parts, components, or services shall be reviewed by the cognizant technical organization to verify that adequate technical and quality requirements have been specified.

The reviews for technical and quality requirements shall be performed by someone other than the originator of the requisition. Quality will concur with all changes to quality requirements.

5.1.2.2 Purchase Orders and Contracts

Purchase orders and contracts are prepared and issued by Nuclear Purchasing and Material Management and establish for the suppliers the technical and quality requirements which must be met.

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 3 OF 11 EFFECTIVE DATE 02-01-02

Purchase orders and contracts shall accurately reflect the technical and quality requirements established by the purchase requisition. If, during the bid negotiations with the supplier, it becomes necessary or commercially desirable to change the technical or quality requirements, such changes shall be presented for approval to the cognizant technical organization which approved the original requirements.

5.1.2.3 Change Controls Changes to procurement document quality and technical requirements shall require a review and approval equivalent to that of the original document. Commercial consideration changes not affecting the technical or quality requirements do not require review and concurrence by the originator.

5.1.3 For the procurement of spare or replacement parts, equipment, materials, and services, the quality and technical requirements shall be equal to or greater than the design basis requirements for the original part, equipment, materials or services; except where less stringent quality or technical requirements may be established based on specific evaluations and justification. The cognizant technical organization shall document such justification.

5.1.3.1 Items may be procured as Commercial Grade Items (CGIs) if a documented engineering evaluation indicates the CGI will provide equivalent performance. CGI dedication will comply with established procedures designed to satisfy the requirements of References 4.2 and 4.8.

5.1.3.2 The cognizant technical organization shall verify that quality requirements are correctly stated, verifiable, and controllable; that acceptance/rejection criteria are included; and that the documents have been prepared, reviewed, and approved in accordance with STP Quality Program requirements.

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 4 OF 11 EFFECTIVE DATE 02-01-02 5.2 Procurement Document Content 5.2.1 Procurement document control measures shall assure that appropriate regulatory requirements, design bases, and other requirements are included in the procurement process. The following shall be included or invoked by reference in procurement documents as appropriate:

5.2.1.1 Applicable regulatory, code, and design requirements, including material and component identification requirements, drawings, specifications, standards, inspection and test requirements, special process instructions and handling, preservation, cleaning, storage, packaging and shipping requirements. These requirements shall equal or exceed the original requirements (unless changed by established design control processes).

5.2.1.2 Extent that supplier QA program shall comply with 10CFR50, Appendix B or the QA program requirements of other nationally recognized codes and standards, as applicable; or for CGIs to be dedicated for safety related use by STPNOC based on the results of a survey of the vendor's controls, the vendor's STPNOC approved and/or surveyed program.

5.2.1.3 Requirements for supplier documents, such as instructions, procedures, drawings, specifications, inspection and test records, and suppliers' QA records to be prepared, submitted, or be made available for review and/or approval by STP personnel.

5.2.1.4 Requirements for suppliers to maintain the status of required inspections or tests throughout the manufacturing process to preclude inadvertent bypassing of inspections and tests.

5.2.1.5 Requirements for STPNOC's right of access to suppliers' facilities and work documents for inspection and audit.

5.2.1.6 Requirements for extending applicable STP procurement requirements to lower-tier suppliers and subcontractors, including STPNOC's access to facilities and records.

5.2.1.7 Requirements for supplier reporting to STP nonconformances to procurement document requirements and conditions for their disposition.

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 5 OF 11 EFFECTIVE DATE 02-01-02 5.2.1.8 Requirements for the retention, control, and maintenance of supplier QA records that are not maintained by STPNOC.

Supplier-furnished records shall include:

Documentation (e.g., certification) that identifies the purchased item and the specific procurement requirements (e.g., codes, standards, and specifications) met by the item.

Documentation identifying any procurement requirements that have not been met.

A description of those nonconformances from procurement requirements dispositioned "accept-as-is" or "repair".

5.2.1.9 Requirement for the supplier to submit a copy of its QA program description (does not apply for CGIs).

5.2.1.10 Requirements for the performance of maintenance and receipt inspection checks where applicable.

5.2.1.11 Applicability of 10CFR21 reporting requirements.

The reporting requirements of 10CFR21 do not apply to vendors of CGIs to be dedicated for use by STPNOC.

5.3 Bid Evaluation 5.3.1 Bid Evaluations shall be performed to evaluate adherence to technical and quality assurance requirements.

5.4 Supplier Selection 5.4.1 Suppliers of items (for CGIs, when basis for dedication includes commercial grade survey) or services shall be required to submit copies of their QA program description for evaluation prior to the issuance of a purchase order or execution of a contract, and acceptability shall be documented. The process by which suppliers are judged as being a capable procurement source is described as follows:

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 6 OF 11 EFFECTIVE DATE 02-01-02 5.4.1.1 Procurement source evaluation and selection involves o Engineering, Nuclear Safety Assurance, NPMM, and STP plant personnel, as appropriate. These organizations participate in the qualification evaluation of suppliers in accordance with written procedures.

5.4.1.2 Measures for the evaluation and selection of procurement sources shall be specified in procedures and may vary depending upon the complexity and risk significance of the item or service. When procurement source evaluations are performned, the information to be considered shall include one or more of the following:

Experience of users of identical or similar products of the prospective supplier, other utility or approved contractor audits/evaluations, audits/evaluations by cooperative utility groups, American Society of Mechanical Engineers (ASME) Certificates of Authorization, STP records accumulated in previous procurement actions, and STP product operating experience may be used in this evaluation. When other utility, contractor or cooperative utility audits/evaluations are used, the documentation will be obtained and reviewed. Supplier history shall reflect recent capability. Previous favorable experience with suppliers may be an adequate basis for judgments attesting to suppliers' capability.

An evaluation of the suppliers' current quality records supported by documented qualitative and quantitative information which can be objectively evaluated. This may include review and evaluation of the suppliers' QA Program Manual, procedures, and responses to questionnaires, as appropriate.

A source evaluation of the suppliers' technical and quality capability as determined by a direct evaluation of facilities and personnel (audit, survey, or surveillance) and quality program implementation.

Resolution or a commitment to resolve unacceptable technical or quality requirements identified by the bid evaluation or vendor evaluation shall be obtained prior to the award of a purchase order or contract.

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 7 OF 11 EFTECTIVE DATE D 02-01-02 5.4.1.3 Procurement source evaluations involve a review of technical and quality considerations to an extent considered appropriate by each participant. Technical considerations include the design or manufacturing capability and technical ability of suppliers to produce or provide the design, service, item or component. Quality considerations include one of the previously stated methods of supplier evaluation and a consideration of a suppliers' current quality program or capabilities.

5.4.1.4 A documented quality assurance evaluation of a vendor's quality program shall be performed to assure it meets the appropriate requirements of 10CFR50 Appendix B, or where applicable, other nationally recognized codes and standards, or, for CGIs, to assure the program provides adequate control over established critical characteristics.

5.4.1.5 Vendors may be placed on the Approved Vendors List after passing this evaluation.

5.4.1.6 A vendor shall not be issued a purchase order or contract unless they have been accepted for placement on the Approved Vendors List or an exception has been approved by the C Manager, Nuclear Safety Assurance or Quality Manager. lo 5.4.1.7 Service organizations which will supply only manpower and no other service are not required to be on the Approved Vendors List or have an STP approved quality assurance program as long as the supplied personnel are trained and work under the auspices of the STP Operations Quality Assurance Plan.

5.4.2 Each vendor on the Approved Vendors List shall be periodically evaluated by Quality as provided by Reference 4.3 (i.e., annually for "Full" program, biennially for "Basic" program).

5.4.2.1 A vendor may be removed from the Approved Vendors List if evaluation determines the vendor is unacceptable, the vendor requests removal or by direction of the Manager, Nuclear Safety Assurance or Quality Manager. I>

4

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 8 OF 11 EFFECTIVE DATE 02-01-02 5.4.3 Planning of verification activities to be employed for item or service acceptance shall begin during the purchase requisition or contract preparation and review stage. The extent of the verification activities will vary and be a function of the relative safety significance, complexity of the purchased item or service, and the supplier's past performance. The verification activities may include vendor surveillance, receipt inspection, or post-installation testing. Verification activities are planned to assure conformance to procurement document requirements. Procedures shall establish the organizational responsibilities for identifying required verifications and methods, performing and documenting the verification activities.

5.4.3.1 Verification activities shall be performed using plans developed in accordance with procedures with appropriate input from the cognizant technical organization. The plan shall specify the characteristics or processes to be witnessed, inspected or verified.

5.4.3.2 Specified source inspections may be waived by Manager, Nuclear Safety Assurance or Quality Manager.

5.4.3.3 Vendor related reports shall be evaluated to determine the effectiveness of the vendor's quality assurance program.

5.5 Receiving Activities 5.5.1 Received purchased items shall be observed for shipping damage and the requirements of ANSI N45.2.2 Section 5.2.1. (This activity does not constitute an inspection and does not require qualification in accordance with Reference 4.5).

5.5.2 Receiving inspection shall be coordinated with verification activities. If source inspection is not performed or did not address all applicable attributes, receipt inspection shall be performed and shall include the applicable additional attributes listed in ANSI N45.2.2 Section 5.2.2, except for commercial grade items dedicated by survey which shall be receipt inspected as required by the procurement document.

5.5.3 Receiving inspection checklists shall be developed using the requirements specified in the procurement documents and applicable attributes of ANSI N45.2.2.

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 9 F 11 EFFECTIVE DATE 02-01-02 5.5.4 Statistical sampling methods may be used for groups of similar items.

Sampling shall comply with nationally recognized methods or approved engineering alternates.

5.5.5 Receiving inspections shall be performed by personnel trained and qualified in accordance with Reference 4.5. Technical assistance shall be provided by Generation, Support, or Engineering as applicable. >

5.5.6 Receiving inspection activities shall include:

5.5.6.1 Identifying materials, parts, and components and their status upon receipt by tagging or other acceptable means of identification, or segregating and controlling items in receiving hold areas separate from the storage facilities for acceptable items. Identification of items shall correspond to the identification required by procurement documents and be noted on receiving documentation.

5.5.6.2 Verification of items for acceptance includes correctness of identification and specified quality documentation.

5.5.6.3 Inspecting or testing using approved procedures and calibrated tools, gauges, and measuring equipment for verification acceptance of items, including off-the-shelf items.

5.5.6.4 Items determined to be acceptable for use shall be identified with an "accept" tag or other acceptable means of identification prior to release for storage or use.

5.5.6.5 Received items which do not conform to procurement documents are controlled and segregated (if practical) and processed in accordance with Reference 4.6.

5.5.7 Acceptance by post-installation test may be utilized following one of the preceding verification methods. Post-installation testing may be used for acceptance verification when it is difficult to verify item quality characteristics, the item requires an integrated system checkout or test, or the item cannot demonstrate its ability to perform when not in use.

Engineering specifications shall be used for developing post-installation test instruction requirements and acceptance documentation. Post-installation testing is the responsibility of the Plant Manager and is witnessed by Engineering or Nuclear Safety Assurance personnel at specified hold points. "3

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE l OFlI EFFECTIVE DATE 02-01-02 5.5.8 Acceptance of Procured Items and Services 5.5.8.1 Acceptance of items and services shall be based on one or more of the following:

Written certifications (Note: This shall not be the sole method of acceptance for items in the "Basic" program)

Surveillance/Audit of procured service Source verification Receiving inspection/testing Commercial Grade Item dedication Vendor surveillance Post-installation test 5.5.9 Documented evidence from the supplier that procured items meet procurement quality requirements, when required, such as codes, standards, or specifications will be maintained at the plant site. Such evidence shall be provided by the supplier, at the time of source or receipt inspection, for review and verification before acceptance. The documented evidence will be retrievable and available at the plant site prior to installation or use of the procured item, unless otherwise controlled in accordance with Reference 4.6.

5.6 Vendor Surveys, Surveillance and Audit 5.6.1 For items in the Full Program, Suppliers Certificates of Conformance.

shall be periodically evaluated by audits, independent inspections, surveys, or tests to assure that they are valid and results are documented.

When acceptance is based upon source inspection, documented evidence shall be furnished to the plant receiving organization.

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OPERATIONS QUALITY ASSURANCE PLAN 7.0 9 PROCUREMENT PAGE 11 OF 11 EFFECTIVE DATE 02-01-02 5.6.1.1 Acceptance by source inspection may be considered when the item or service is vital to plant safety; or the quality characteristics are difficult to verify after receipt; or the item or service is complex in design, manufacture, inspection, or test.

Vendor surveillance/source inspection involves a physical presence to monitor, by observation, designated activities for the purpose of evaluating supplier performance and product acceptance (source inspection only).

5.6.2 The STP survey and audit program provide for periodic scheduled audits or surveys of suppliers, the site procurement program, contractors, subcontractors, and others performing work. The audit and survey schedule is prepared and updated by Quality. Frequency of these surveys and audits is based upon the safety, complexity, and quality requirements, and as a minimum shall be in compliance with Reference 4.3.

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 4.7.

7.0 ATTACHMENTS 7.1 None

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 10.0 9 INSPECTION PAGE I OF 5 EFFECTIVE DATE 02-01-02 1.0 PURPOSE 1.1 The purpose of this chapter is to prescribe the requirements and the responsibilities for inspection.

2.0 SCOPE 2.1 This chapter is applicable to inspection activities associated with systems, structures and components at the South Texas Project Electric Generating Station (STP).

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 OQAP Chapter 4.0, Qualification, Training and Certification of Personnel 4.2 OQAP Chapter 12.0, Instrument and Calibration Control 4.3 OQAP Chapter 14.0, Records Control 4.4 OQAP Chapter 2.0, Table I 5.0 REQUIREMENTS 5.1 Inspection 5.1.1 Inspections shall be performed in accordance with written and approved procedures. The inspection criteria established for performing inspections and the detail of the inspection process shall be determined based on the complexity of the activity and possible safety impact to the plant.

Qualification of individuals performing inspections shall be in accordance with Reference 4.1 and 4.4. These individuals shall be other than those who performed or directly supervised the activity being inspected.

Inspection requirements may be included as a part of the document controlling the activity, or a separate inspection procedure prepared to specify, as appropriate, the inspection performance requirements as noted below.

5.1.1.1 Identification of characteristics and activities to be inspected

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 10.0 9 INSPECTION PAGE 2 OF 5 EFFECTIVE DATE 02-01-02 5.1.1.2 Acceptance and rejection criteria 5.1.1.3 Inspection process utilized 5.1.1.4 Identification of procedures, drawings, specifications, and revisions utilized 5.1.1.5 Specification of the necessary measuring and test equipment including accuracy and calibration due dates as applicable 5.1.2 For "Full" program implementation, when inspections associated with normal operations of the plant are performed by individuals other than those who performed or directly supervised the work, but are within the same group, the following additional controls apply:

5.1.2.1 The quality of work can be demonstrated through a functional test when the activity involves breaching a pressure-retaining item; and 5.1.2.2 The qualification criteria for inspection personnel are reviewed and found acceptable by the Quality organization prior to initiating the inspection.

5.1.3 For "Basic" program implementation, with the exception of receipt inspection, personnel may perform inspections, examinations and tests provided:

5.1.3.1 They are experienced, task qualified journeymen, or supervisors, who did not perform or directly supervise the activity being inspected, examined or tested, and 5.1.3.2 These individuals shall also receive training to the applicable inspection procedure, processes, methods in accordance with a Quality approved training program; and 5.1.3.3 Quality will provide periodic oversight of the inspection activities.

5.1.4 Examples of the activities subject to inspection include:

5.1.4.1 Special processes 5.1.4.2 Modifications

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 10.0 9 INSPECTION PAGE 30F5 I EFFECTIVE DATE 02-01-02 5.1.4.3 Receipt of materials, parts and components 5.1.4.4 Maintenance 5.1.4.5 Packaging, shipping and handling of radioactive waste material 5.1.5 Process Monitoring 5.1.5.1 Process monitoring of work activities, equipment, and personnel shall be utilized as a control method when direct inspection of processed items is impossible or impracticable.

Monitoring shall be performed to verify that activities are performed in accordance with documented instructions, procedures, drawings, and specifications.

5.1.6 Supporting Inspections 5.1.6.1 Both inspections and process monitoring shall be.used when control of the activity is inadequate without both. The need for such monitoring shall be determined prior to initiation of the activity, if possible, or may be stipulated later if circumstances warrant.

5.1.7 Mandatory Inspections 5.1.7.1 Mandatory inspection holdpoints are established by the organization performing the work, Nuclear Safety Assurance or Engineering personnel. Witnessing or inspection of hold points by Engineering or Nuclear Safety Assurance personnel shall be accomplished before work can proceed. Plant procedures and work instructions shall be reviewed by Engineering and/or Nuclear Safety Assurance personnel for concurrence with the established mandatory hold points.

5.1.7.2 Engineering and/or Nuclear Safety Assurance personnel also establish notification points for the purpose of being informed of upcoming activities (e.g., prior to the start of a test) where a mandatory holdpoint may not be appropriate, but Engineering and/or Nuclear Safety Assurance personnel involvement may be desired.

5.1.8 Inspection results shall be reviewed and approved by qualified personnel to verify that the inspection requirements were satisfied.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 10.0 9 INSPECTION PAGE 4 OF 5 EFFECTIVE DATE 02-01-02 5.1.9 Inspection activities shall be documented and as a minimum, shall identify the following:

5.1.9.1 Item inspected 5.1.9.2 Date of inspection 5.1.9.3 Inspector 5.1.9.4 Type of observation/inspection 5.1.9.5 Results and acceptability 5.1.9.6 Reference to information on action taken in connection with nonconformances 5.1.9.7 Test equipment used 5.1.10 Inspection requirements for modifications, repairs, and replacements shall be equivalent to the inspection requirements of the original design or approved alternatives.

5.1.11 Procedures shall be reviewed by personnel sufficiently knowledgeable in the requirements of the activity to ensure that the necessary hold points are designated.

5.1.12 Measuring and test equipment utilized as part of the inspection process shall be controlled by the requirements of Reference 4.2.

5.1.13 Acceptance 5.1.13.1 Procedures shall be established for processing, evaluation, and final acceptance of inspection data. The qualified inspector performing the inspection is responsible for the immediate evaluation and acceptability of inspection results. Designated individuals or groups are responsible for reviewing and evaluating inspection results including recording of data, computations, drawings, or specification interpretations.

5.2 Nondestructive Examination (NDE) 5.2.1 NDE shall be performed in accordance with procedures which address the applicable requirements of ASME, ASTM, or other appropriate codes and standards.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 10.0 9 INSPECTION PAGE OF 5 EFFECTIVE DATE 02-01-02 5.2.2 The applicable requirements of Section 5.1 shall apply to the performance, evaluation, and documentation of NDE results.

5.3 Inspection Status 5.3.1 The status of individual item inspections shall be identifiable through the use of stamps, tags, labels, routing cards or documentation traceable to the item.

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 4.3.

7.0 ATTACHMENTS 7.1 None

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION NUMER REV.

Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 13.0 10 Control of Conditions Adverse to Quality PAGE I OF 4 EFFECTIVE DATE 02-01-02 1.0 PURPOSE 1.1 The purpose of this chapter is to establish requirements and responsibilities for the identification, documentation, evaluation, resolution, control and reporting of conditions adverse to quality.

2.0 SCOPE 2.1 This chapter applies to conditions adverse to quality discovered in items, services and activities under the scope of the Operations Quality Assurance Plan and the reporting of items to the Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 10CFR50, Appendix B 4.2 10CFR21, Reporting of Defects and Noncompliance 4.3 10CFR50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors 4.4 10CFR50.73, Licensee Event Report System 4.5 South Texas Project Electric Generating Station (STP) Technical Specifications 4.6 OQAP Chapter 14.0, Records Control 4.7 OQAP Chapter 2.0, Table I 5.0 REQUIREMENTS 5.1 All personnel working under the jurisdiction of the Operations Quality Assurance Plan are responsible for reporting conditions adverse to quality to appropriate management for resolution in accordance with approved procedures.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 13.0 10 Control of Conditions Adverse to Quality PAGE 2 OF 4 EFFECTIVE DATE 02-01-02 5.2 Procedures shall be developed for the control of items, services or activities which do not conform to established requirements. These procedures shall provide for the following:

5.2.1 Identification and documentation of conditions adverse to quality.

5.2.2 Identification of the requirements, source, or reference information being violated.

5.2.3 Notification of responsible management.

5.2.4 Control of conditions adverse to quality by tagging, segregation, administrative controls, or other appropriate means to prevent inadvertent installation, use, or continuation of the activity and removal of such controls when returned to service or availability.

5.2.5 Resolution and/or disposition approved by authorized personnel prior to closing out the documentation and restoring to normal service.

5.2.5.1 Material conditions adverse to quality disposition categories are:

o "Use-as-is" o "Reject" o "Rework" in accordance with documented procedures o "Repair" in accordance with documented procedures 5.2.5.2 "Use-as-is" and "repair" dispositions shall be approved and justified in writing by Engineering & Technical Services.

5.2.5.3 Evaluations shall be performed to ascertain recurrence control measures.

5.2.6 Documentation of the corrective action taken.

5.2.7 Review and/or verification of the corrective action by the Quality organization, as appropriate.

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OPERATIONS QUALITY ASSURANCE PLAN 13.0 10 Control of Conditions Adverse to Quality PAGE 3 OF4 EFFECE DATE 02-01-02 5.2.8 Repaired and reworked items shall be reinspected in accordance with applicable procedures. Reinspection results are documented on inspection reports or other work process control documents.

5.2.9 Installation of nonconforming material, parts, and components may be performed after the effect of their installation has been evaluated and the c installation approved by Plant Management, Nuclear Safety Assurance, and Engineering. Nonconforming items which may not be installed are those which, because of their makeup and intended use, cannot be repaire or reworked after being installed and those which, if installed and later removed, would degrade that system, structure, or component. Once installed, nonconforming items are not energized, used, or placed in service until the action required by the disposition, including reinspection, has been completed or an engineering evaluation has been prepared to justify the intended use of the nonconforming item.

5.2.10 Conditions adverse to quality identified on installed items will be evaluated for operability.

5.2.11 Disputes over corrective action are normally resolved by Plant Management. Should this resolution not be satisfactory, the parties may elevate the matter to higher management for resolution.

5.3 Procedures shall provide the following administrative controls:

5.3.1 Unique identification and numbering of conditions adverse to quality.

5.3.2 Preparing and maintaining status reporting of conditions adverse to quality.

5.3.3 Actions to be taken to assure timely corrective action on conditions adverse to quality.

5.4 Procedures which identify and track conditions adverse to quality shall require management review of each report to determine if the condition is significant.

For significant conditions adverse to quality, the cause of the condition and the corrective action taken to preclude repetition shall be documented and reported to appropriate levels of management.

5.5 Measures shall be established for review and evaluation of conditions adverse to quality for reportability to the NRC as required by References 4.2 (to the extent not exempted), 4.3, and 4.4, as appropriate.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 13.0 10 Control of Conditions Adverse to Quality PAGE 4 OF 4 EFFECTIVE DATE 02-01-02 10 5.6 The authority to stop work has been assigned to Manager, Nuclear Safety Assuance or Quality Manager for any activity being performed by company I -J personnel or contractors which do not conform to established requirements.

5.7 Measures shall be established for the evaluation and trending of conditions adverse to quality. The results of these reviews and analyses are reported to the affected organization and executive management, and are audited by the Quality organization. Adverse trends shall be evaluated and processed in accordance with controlling procedures.

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 4.6.

7.0 ATTACHMENTS 7.1 None

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 14.0 7 RECORDS CONTROL PAGE 1OF5 EFFECTIVE DATE 02-01-02 1.0 PURPOSE 1.1 The purpose of this chapter is to describe the requirements and the responsibilities for the collection, storage, retrieval, and maintenance of records.

2.0 SCOPE 2.1 This chapter is applicable to those records acquired and developed as a result of, or in support of, the South Texas Project Electric Generating Station (STP).

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 OQAP Chapter 2.0, Table I 5.0 REQUIREMENTS 5.1 Records shall be collected, filed, stored, maintained, and dispositioned.

5.1.1 Records include, but are not limited to: plant history; operating logs; records of principal maintenance and modification activities; reportable occurrences and other records required by the Technical Specifications; results of reviews, inspections, tests, audits, and material analyses; monitoring of workl performance; qualification of personnel, procedures, and equipment; drawings, specifications, procurement documents, warehousing documents, calibration procedures and calibration reports; and nonconformance and corrective action reports.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 14.0 7 RECORDS CONTROL PAGE 2 OF 5 EFFECTIVE DATE 02-01-02 5.1.1.1 The records control program provides evidence that activities affecting quality are defined and implemented, and that inspection and test documents contain a description of the type of observation; the identification of inspector or data recorder; the date and inspection or test results; acceptability of the results; and reference any action taken in documenting or resolving any nonconformances.

5.2 Record storage facilities shall meet the requirements of Reference 4.1.

5.3 A list of record types and the classification of these record types as to retention period shall be maintained.

5.4 An index of stored records shall be maintained. The index shall include retention period and location of the records within the storage area. The STP DTL (an electronic database) is used as a record index/checklist. If a conflict of retention times exists between regulatory, standard, technical specification requirements, or the technical requirements manual, the longer retention period shall be specified.

5.5 Records indexing systems shall provide sufficient cross-reference between the record and items or activities to which the record applies.

5.6 The receipt, processing, and handling of records shall be controlled by procedures.

5.7 To ensure that records are identifiable and retrievable, a computerized records management system has been developed. This system provides for a method to identify the document(s)/record(s) or document/ record package(s) for retrieval purposes. The system also provides the ability to cross-reference the identification with other possible identifiers of the document (i.e., specification number, purchase order number, equipment number). Records may be stored on photographic, optical, or electronic media; the file locations of documents are available from the computer.

5.8 Controlled access to the record storage facility shall be established.

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OPERATIONS QUALITY ASSURANCE PLAN 14.0 7 RECORDS CONTROL PAGE 3 OF 5 EFFECTIVE DATE 02-01-02 5.9 Records may be corrected/supplemented in accordance with procedures, which provide for appropriate review or approval by the originating or other authorized organization. Corrections/supplements shall include the date and identification of the person making the correction/supplement, and 5.9.1 For hard copy (i.e. paper) originals, shall be in ink and be entered in a manner such that the original information is not obliterated, or 5.9.2 For originals in an electronic format, shall be annotated in a manner such that the correction/supplement is easily identified as a correction or supplement and the original information is not obliterated.

5.10 Organizations generating records are responsible for ensuring activities are documented accurately, legibly, and with sufficient traceability; and submitting designated documents for independent review prior to entering into the records system in accordance with appropriate procedures.

5.11 Record Retention 5.11.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

5.11.2 The following records shall be retained for at least 5 years: .0 5.11.2.1 Records and logs of unit operation covering time interval at each power level; 5.11.2.2 Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; 5.11.2.3 All REPORTABLE EVENTS; 5.11.2.4 Records of surveillance activities, inspections, and calibrations required by the Technical Specifications;

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OPERATIONS QUALITY ASSURANCE PLAN 14.0 7 RECORDS CONTROL PAGE 4 OF 5 EFFECTIVE DATE 02-01-02 5.11.2.5 Records of changes made to the procedures required by Technical Specification 6.8 and Technical Requirements Manual 6.8; 5.11.2.6 Records of sealed source and fission detector leak tests and results; and 5.11.2.7 Records of annual physical inventory of all sealed source material of record.

5.11.3 The following records shall be retained for the duration of the unit Operating License:

5.11.3.1 Records and drawing changes reflecting unit design modifications made to systems and equipment described in the c Final Safety Analysis Report; 5.11.3.2 Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; 5.11.3.3 Records of doses received by all individuals for whom monitoring was required; 5.11.3.4 Records of gaseous and liquid radioactive material released to the environs; 5.11.3.5 Records of transient or operational cycles for those unit components identified in the Updated Final Safety Analysis Report; 5.11.3.6 Records of reactor tests and experiments; 5.11.3.7 Records of training and qualification for current members of the unit staff; 5.11.3.8 Records of inservice inspections performed pursuant to the Technical Specifications;

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 14.0 7 RECORDS CONTROL PAGE 5 OF 5 EFFECTIVE DATE 02-01-02 5.11.3.9 Records of quality assurance activities required by the Operations Quality Assurance Plan; 5.11.3.10 Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59; 5.11.3.11 Records of meetings of the PORC; 5.11.3.12 Records of organizational unit independent reviews; 5.1 1.3.13 Records of secondary water sampling and water quality; 5.11.3.14 Records of analyses required by the Radiological Environmental Monitoring Program that would permit 0 evaluation of the accuracy of the analysis at a later date. This

'1.

should include procedures effective at specified times and QA -3 records showing that these procedures were followed; 5.11.3.15 Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM; and 5.11.3.16 Records of radioactive shipments.

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 this chapter.

7.0 ATTACHMENTS 7.1 None

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 15.0 9 QUALITY OVERSIGHT ACTIVITIES PAGE 1 OF 7 EFFECTIVE DATE 02-01-04 1.0 PURPOSE 1.1 The purpose of this chapter is to establish requirements for a system of independent oversight activities of quality assurance programs for the South Texas Project Electric Generating Station (STP).

2.0 SCOPE 2.1 This chapter provides for implementing a program of independent oversight activities which includes audits, assessments, evaluations, performance monitoring, and surveillances to ensure the requirements of the Operations Quality Assurance Program are being properly implemented.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 OQAP Chapter 2.0, Table I 4.2 OQAP Chapter 4.0, Qualification, Training and Certification of Personnel 4.3 OQAP Chapter 7.0, Procurement 4.4 OQAP Chapter 13.0, Control of Conditions Adverse to Quality 4.5 OQAP Chapter 14.0, Records Control 5.0 REQUIREMENTS 5.1 Independent Oversight Activities 5.1.1 Procedures shall be developed to control independent oversight activities.

These activities include, but are not limited to, audits, assessments, evaluations, performance monitoring, and surveillances. These activities shall be used to observe and verify that activities are accomplished in accordance with prescribed requirements.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 15.0 9 QUALITY OVERSIGHT ACTIVITIES PAGE OF 7 EFFECTIVE DATE 02-01-04 5.2 Audits 5.2.1 A comprehensive audit program in compliance with Reference 4.1 shall be established and implemented by STP Nuclear Operating Company (STPNOC) to verify internal and external quality activity compliance with the Quality Program. The audit program shall assure that applicable elements of the program have been developed, documented, and are effectively implemented and shall provide for reporting and reviewing audit results by appropriate levels of management. These audits shall encompass:

5.2.1.1 The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions; 5.2.1.2 The training and qualification of the unit staff; 5.2.1.3 Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; 5.2.1.4 The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10CFR50; 5.2.1.5 The fire protection programmatic controls including the implementing procedures; 0 5.2.1.6 The fire protection equipment and program implementation utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant; 5.2.1.7 The Radiological Environmental Monitoring Program and the results thereof; 5.2.1.8 The OFFSITE DOSE CALCULATION MANUAL and implementing procedures; 5.2.1.9 The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes;

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 15.0 9 QUALITY OVERSIGHT ACTIVITIES PAGE 30F7 EFFECTIVE DATE 02-01-04 5.2.1.10 The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring; to and 5.2.1.11 Other activities and documents as requested by the SMT or the President and Chief Executive Officer.

5.2.2 Qualified personnel assigned auditing responsibilities shall be independent of any direct responsibility for the performance of the activities which they audit; shall be experienced or trained commensurate with the scope, complexity, or special nature of the activities to be audited; and shall be qualified in accordance with the requirements of Reference 4.2.

5.2.2.1 An audit team consists of one (or more) qualified person(s). A qualified lead auditor shall be appointed as the audit team leader. The audit team leader shall be responsible for the written plans, checklists, team orientation, audit notification, pre-audit conference, audit performance, post-audit conference, reporting, and follow-up activity to assure corrective action.

The audit team leader shall promptly report conditions requiring immediate corrective action to the appropriate management of the audited organization. Other audit findings will be identified to the audited organization at the post-audit conference.

5.2.2.2 Other qualified personnel may assist in the conduct of audits, such as technical specialists or management representatives.

5.2.3 Internal Audits 5.2.3.1 Internal audits shall be conducted by the Quality Department and performed with a frequency commensurate with their safety significance, past performance and regulatory requirements. Audits are scheduled on a nominal biennial frequency, except those audits whose frequency is specifically governed by regulation.

If a decision is made to extend an audit beyond that nominal frequency, the basis for that decision shall be documented. c Decisions shall be approved by the Manager, Nuclear Safety 6 Assurance and notifications made to the Vice President, l -

Oversight and the Senior Management Team.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 15.0 9 QUALITY OVERSIGHT ACTIVITIES PAGE 4 OF7 EFFECTIVE DATE 02-01-04 5.2.3.2 Review of the audit program shall be performed at least semiannually by the Senior Management Team or by a management representative to verify that audits are being accomplished in accordance with the requirements of the Quality Program.

5.2.3.3 Audit results shall be reviewed periodically by the Quality organization for quality trends and overall audit program effectiveness. The results of these reviews shall be reported to appropriate management in periodic summary reports.

5.2.3.4 Audited organizations are responsible for providing timely corrective action including action to prevent recurrence for programmatic problems identified by an audit.

5.2.4 Supplemental audits shall be conducted when:

5.2.4.1 Significant changes are made to the quality assurance program.

5.2.4.2 It is necessary to determine the root cause of problem areas which may impact the effectiveness of the quality assurance program.

5.2.4.3 A systematic, independent assessment of program effectiveness is necessary.

5.2.4.4 Requested by appropriate management.

5.2.5 Audit implementation shall include the following:

5.2.5.1 Written notification to the audited organization of the audit, if an announced audit.

5.2.5.2 Development of an individual audit plan/scope. The audit plan and any necessary reference documents shall be available to the audit team members.

5.2.5.3 A pre-audit and post-audit conference with responsible organizational management.

5.2.5.4 Use of a checklist or procedure as a guide during the performance of the audit.

5.2.5.5 Identifying and documenting conditions adverse to quality.

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OPERATIONS QUALITY ASSURANCE PLAN 150 9 QUALITY OVERSIGHT ACTIVITIES PAGE 50F7 EFFECTIVE DATE 02-01-04 5.2.5.6 Audit reports shall be prepared and submitted to the audited organization, senior management, and the President and Chief Executive Officer within thirty days after the post-audit conference. The audit report shall address those items required by Reference 4.1.

5.2.5.7 Audited organizations provide timely and thorough corrective action and recurrence control to discrepancies identified during the audit. In the event that corrective action cannot be completed within thirty days, the audited organization's response shall include a scheduled date for the corrective action. Earlier dates for corrective action may be established if circumstances dictate.

5.2.5.8 Evaluation of corrective action for conditions adverse to quality and follow-up verification as appropriate.

5.3 Surveillance/Quality Performance Monitoring 5.3.1 Procedures and/or instructions shall be developed to control surveillance/quality performance monitoring activities.

Surveillance/quality performance monitoring activities shall be used to observe and verify that activities are accomplished in accordance with prescribed procedures.

5.3.2 Surveillance/quality performance monitoring activities will be performed during refueling outages, startup activities, and normal and off-normal operational activities. Areas to be monitored will be determined based on safety significance, past performance, regulatory requirements, and customer request.

5.3.3 The frequency of surveillance/quality performance monitoring activities is based upon the complexity of the activity, importance of the activity, and severity level of conditions noted during previous oversight activities.

5.3.4 Surveillance/quality performance monitoring results shall be documented and a summary shall be prepared and transmitted to responsible management.

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OPERATIONS QUALITY ASSURANCE PLAN 15.0 9 QUALITY OVERSIGHT ACTIVITIES PAGE 60F7 EFFECTIVE DATE 02-01-04 5.4 Assessments/Evaluations 5.4.1 Assessments are conducted annually in accordance with written procedures to assess the Quality organization's implementation of the Operations Quality Assurance Plan.

5.4.1.1 These assessments will be conducted by organizations independent of the activities performed to assure the STPNOC OQAP is being properly implemented.

5.4.1.2 The Senior Management Team shall review the scope and schedule of the assessment.

5.4.1.3 The results of these assessments will be transmitted to the President and Chief Executive Officer and the Senior Management Team.

5.4.2 Other assessments/evaluations may be performed to verify activities are accomplished in accordance with applicable requirements and prescribed procedures.

5.4.2.1 These assessments/evaluations will be performed on areas based on their safety significance, past performance, regulatory requirements, and customer request.

5.4.2.2 Assessmentlevaluation results shall be documented and transmitted to appropriate management.

5.5 An approved oversight plan shall be issued annually to include:

5.5.1 Activities/organizations to receive independent oversight.

5.5.2 Time frame in which the oversight activity will be conducted.

5.6 Conditions adverse to quality identified during an independent oversight activity shall be documented in accordance with Reference 4.4.

5.7 Personnel performing independent oversight activities shall be trained and qualified in accordance with Reference 4.2.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 15.0 9 QUALITY OVERSIGHT ACTIVITIES PAGE 7 OF 7 EFFECTIVE DATE 02-01-04 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 4.5.

7.0 ATTACHMENTS 7.1 None

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 16.0 8 Independent Technical Review PAGE I OF 3 EFFECTIVE DATE 02-01-04 1.0 PURPOSE 1.1 The purpose of this chapter is to describe the requirements and responsibilities for independent technical review for the South Texas Project Electric Generating Station (STPEGS).

2.0 SCOPE 2.1 This chapter describes the independent technical review activities within the scope of the Operations Quality Assurance Plan (OQAP).

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 OQAP Chapter 1.0, Organization 4.2 OQAP Chapter 2.0, Program Description 4.3 OQAP Chapter 4.0, Qualification, Training, and Certification of Personnel 4.4 OQAP Chapter 13.0, Deficiency Control 4.5 OQAP Chapter 14.0, Records Control 4.6 OQAP Chapter 15.0, Quality Oversight Activities 5.0 RESPONSIBILITIES 5.1 The Vice President, Oversight is responsible for implementing quality program requirements including independent technical review.

I .>

5.2 The Manager, Nuclear Safety Assurance is responsible for independent oversight activities performed to accomplish the independent technical reviews.

6.0 REQUIREMENTS 6.1 Independent oversight activities, as described in Reference 4.6, shall be performed in accordance with implementing procedures to ensure the completion of independent technical reviews.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 16.0 8 Independent Technical Review PAGE 2 OF 3 EFFECTIVE DATE 02-01-04 6.2 Independent technical reviews shall be used to observe and verify that activities are performed correctly and that human errors are reduced as much as practical.

6.3 Independent technical reviews shall include, but not be limited to, the following activities:

6.3.1 Unit-operating characteristics 6.3.2 Nuclear Regulatory Commission issuances 6.3.3 Industry advisories 6.3.4 Licensee Event Reports 6.3.5 Other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety.

6.3.6 Plant operations 6.3.7 Maintenance activities 6.3.8 Equipment modifications 6.4 As determined by Quality management, several personnel performing independent technical reviews will be required to have a degree in engineering or related science and at least 3 years of professional level experience in the nuclear field.

6.5 Personnel performing independent technical reviews should be independent of performance function, signoff function, and the plant management chain while performing this oversight activity.

6.6 The results of independent technical reviews will be periodically transmitted to appropriate line and senior management, the Senior Management Team, and the President and Chief Executive Officer for review and/or action and advise management on the overall quality and safety of operations.

6.7 Conditions adverse to quality and recommendations identified during the performance of independent technical reviews shall meet the requirements of Reference 4.4

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 16.0 8 Independent Technical Review PAGE 3 OF 3 EFFECTIVE DATE 02-01-04 7.0 DOCUMENTATION 7.1 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 4.5.

8.0 ATTACHMENTS 8.1 None

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 17.0 6 ASME CODE SECTION XI - REPAIRS AND REPLACEMENTS PAGE I OF 2 EFFECTIVE DATE 02-01-00 1.0 PURPOSE 1.1 The purpose of this chapter is to prescribe requirements and responsibilities for repair and replacement activities governed by ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.

2.0 SCOPE 2.1 This chapter is applicable to examination, repair and replacement activities performed on ASME Class 1, 2, 3, CC, and MC components.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 ASME Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components 4.2 OQAP Chapter 14.0, Records Control 4.3 Generic Letter 89-009, ASME Section III Component Replacements 5.0 RESPONSIBILITIES 5.1 The Vice President, Generation is responsible for the planning, management, and control of the performance of repairs, replacements and tests.

5.2 The Vice President, Engineering is responsible for developing the repair and 110 replacement program including specifications for design, fabrication, testing, and 16 examination. The Vice President, Engineering is responsible for providing -j qualified personnel to perform examinations of component repairs and replacements and verifying the requirements of this chapter are implemented.

6.0 REQUIREMENTS 6.1 Repair and replacement activities required by Reference 4.1 shall be conducted in accordance with written and approved procedures or instructions.

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OPERATIONS QUALITY ASSURANCE PLAN 17.0 6 ASME CODE SECTION XI - REPAIRS AND REPLACEMENTS PAGE 2 OF 2 EFFECTIVE DATE 02-01-00 Areas to be addressed include:

6.1.1 Accessibility for component examination, repair or replacement.

6.1.2 Identification of system boundaries and code class for each component.

6.1.3 The method for interfacing with the authorized nuclear inspection agency.

6.1.4 Qualification of nondestructive examination methods.

6.1.5 Qualification requirements for nondestructive examination personnel.

6.1.6 Qualification requirements for welders and welding operators.

6.1.7 Qualification of welding procedures.

6.1.8 Conduct of examinations and inspections.

6.1.9 A component repair or replacement package including installation and test procedures and quality assurance requirements.

6.1.10 Conduct of system pressure and functional tests.

6.1.11 A component replacement package including specifications for design, fabrication and examination as applicable for the replacements.

6.1.12 Preparation, submittal and retention of required records and reports.

6.1.13 Procurement, in accordance with Reference 4.3, of component replacements not available in full compliance with ASME code stamping and documentation requirements.

7.0 DOCUMENTATION 7.1 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 4.2.

8.0 ATTACHMENTS 8.1 None

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION NUMBER REV.

Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 18.0 7 ASME CODE SECTION XI - INSERVICE INSPECTION AND TESTING PAGE I OF 3 EFFECTIVE DATE 02-01-00 1.0 PURPOSE 1.1 The purpose of this chapter is to prescribe requirements and responsibilities for the inservice examination and testing programs at the South Texas Project Electric Generating Station (STPEGS).

2.0 SCOPE 2.1 This chapter applies to the inservice examination and testing of Class 1, 2, 3, CC, and MC pressure retaining components and component supports as specified in Section XI of the ASME Boiler and Pressure Vessel Code and additional ISI commitments as specified in the UFSAR.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 ASME Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components 4.2 10CFR50.55a, Codes and Standards 4.3 OQAP Chapter 4.0, Qualification, Training and Certification of Personnel 4.4 OQAP Chapter 14.0, Records Control 5.0 RESPONSIBILITIES 5.1 The Vice President, Engineering is responsible for developing and implementing l0 the inservice examination and testing programs as required by ASME Code>

Section XI. The Vice President, Engineering is responsible for verifying the implementation of the inservice examination and testing programs through appropriate quality oversight activities, interfacing with the Authorized Inspection Agency, and performance of nondestructive examinations as requested.

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OPERATIONS QUALITY ASSURANCE PLAN 18.0 7 ASME CODE SECTION XI - INSERVICE INSPECTION AND TESTING PAGE 2 OF 3 EFFECTIVE DATE 02-01-00 6.0 REOUIREMENTS 6.1 The inservice examination and testing programs consist of plans and implementing procedures for the examination and testing of Class 1, 2, 3, CC, and MC pressure retaining components and their supports and the inservice testing of Class 1, 2, and 3 pumps and valves.

6.1.1 Examination and Testing of Pressure Retaining Components and Component Supports 6.1.1.1 Engineering & Technical Services shall develop plans for examination and testing of Class 1, 2, 3, CC, and MC components and their supports. These plans shall prescribe the requirements for nondestructive examinations and tests and the schedule for their performance.

6.1.1.2 Inspection plans (e.g., specifications, vendor documents, etc.)

shall be developed which identify the nature and extent of examination and testing activities including the acceptance criteria which must be met.

6.1.1.3 Procedures shall be developed which provide measures for the performance of activities identified in the plans.

6.1.2 Inservice Testing of Pumps and Valves and System Pressure Testing 6.1.2.1 Engineering & Technical Services shall develop the Inservice Testing Program for pumps and valves and the System Pressure Testing Program. These programs shall include the requirements and the schedule for their performance.

6.1.3 Examination and test results shall be evaluated by specified personnel and verified by the Authorized Nuclear Inservice Inspector.

6.1.4 Coordination of involved STP Nuclear Operating Company (STPNOC) departments, including the use of contractors for the performance, documentation and evaluation of inservice inspection activities, shall be controlled by approved procedures.

6.1.5 When contractors are used to perform activities within the scope of this section, their quality assurance program shall be approved by STPNOC.

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Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 18.0 7 ASME CODE SECTION XI - INSERVICE INSPECTION AND TESTING PAGE 3 OF3 EFFECTIVE DATE 02-01-00 6.1.6 Exceptions to code examination and testing requirements shall be documented in accordance with Reference 4.2.

6.1.7 Personnel performing examinations and tests shall be qualified as required by Reference 4.1 and Reference 4.3.

6.1.8 Plans and reports for inservice examinations and tests shall be submitted to the appropriate regulatory and enforcement authorities as required by Section XI.

7.0 DOCUMENTATION 7.1 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.

8.0 ATTACHMENTS 8.1 None

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION NUMBER REV.

Chapter NO.

OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE I OF 8 EFFECTIVE DATE 02-01-04 1.0 PURPOSE 1.1 The purpose of this chapter is to describe the administrative controls (as previously documented in the Technical Specifications) as related to quality assurance for the South Texas Project Electric Generating Station (STPEGS).

2.0 SCOPE 2.1 STP Nuclear Operating Company (STPNOC), as licensee, has the Quality responsibility for administrative controls of the STP.

3.0 DEFINITIONS 3.1 None

4.0 REFERENCES

4.1 OQAP Chapter 2.0, Table I 4.2 STP Technical Specifications 4.3 Updated Final Safety Analysis Report 4.4 OQAP Chapter 8, Control and Issuance of Documents 4.5 OQAP Chapter 14, Records Control 4.6 OQAP Chapter 15, Quality Oversight Activities 5.0 REQUIREMENTS 5.1 The Plant Operations Review Committee (PORC) shall function to advise the Plant Manager on all matters related to nuclear safety.

5.1.1 The PORC shall be composed of six members, who shall be appointed in writing by the Plant Manager from senior experienced onsite individuals, at the manager level or equivalent, representing each of the following disciplines: engineering, operations, chemistry, health physics, quality assurance/quality control and maintenance. The quality assurance/quality control representatives shall not be appointed as PORC Chairman.

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OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 2 OF 8 EFLECTIVE DATE 02-01-04 5.1.2 The PORC Chairman shall be appointed in writing from among those members by the Plant Manager. One of the members shall meet the requirements of Regulatory Guide 1.8 (Personnel Selection and Training -

Revision 1-R), Radiation Protection Manager.

5.1.3 All alternate members shall be appointed in writing by the Plant Manager to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.

5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.

5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions shall consist of the Chairman or his designated alternate and three other members including alternates.

5.1.6 The PORC shall be responsible for:

5.1.6.1 Review of all safety-related station administrative procedures and changes thereto.

5.1.6.2 Review of safety evaluations for (1) procedures, (2) changes to procedures, structures, components, or systems, and (3) tests or experiments completed under the provisions of 10CFR50.59 to verify that such actions did not require prior Nuclear Regulatory Commission (NRC) approval.

5.1.6.3 Review of proposed (1) procedures, (2) changes to procedures, structures, components, or systems, and (3) tests or experiments completed under the provisions of 10CFR50.59 which may require prior NRC approval.

5.1.6.4 Review of all required programs by Technical Specification 6.8 l and the Technical Requirements Manual 6.8 and changes thereto.

5.1.6.5 Review of all proposed changes to the Technical Specifications or the Operating License.

5.1.6.6 Review of all REPORTABLE EVENTS.

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OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 3 OF 8 EFECTIVE DATE 02-01-04 5.1.6.7 Review of reports of significant operating abnormalities or deviations from normal and expected performance of plant equipment or systems that affect nuclear safety.

5.1.6.8 Review of reports of unanticipated deficiencies in the design or operation of structures, systems, or components that affect nuclear safety.

5.1.6.9 Review of the Security Plan and implementing procedures and changes thereto.

5.1.6.10 Review of the Emergency Plan and implementing procedures and changes thereto.

5.1.6.11 Review of the PROCESS CONTROL PROGRAM and implementing procedures and changes thereto.

5.1.6.12 Review of the OFFSITE DOSE CALCULATION MANUAL and implementing procedures and changes thereto.

5.1.6.13 Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Senior Management Team (SMT).

5.1.6.14 Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Plant Manager and to the SMT.

5.1.6.15 Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.

5.1.6.16 Review of the Fire Protection Program, quality-related implementing procedures and changes thereto.

5.1.7 The PORC shall recommend in writing to the Plant Manager approval or disapproval of items considered under section 5.1.6.1 through 5.1.6.5 prior to their implementation, and items considered under sections 5.1.6.9 through 5.1.6.12.

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OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 4 OF 8 EFFECTIVE DATE 02-01-04 5.1.8 The PORC shall render determinations in writing with regard to whether or not each item considered under sections 5.1.6.1 through 5.1.6.5 and 5.1.6.15 may require prior NRC approval under the provisions of 10CFR50.59.

5.1.9 The PORC shall provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the President and Chief Executive Officer and the SMT of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have the responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.

5.1.10 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility provisions of this chapter. Copies shall be provided to the President and Chief Executive Officer and the appropriate organizational unit.

5.2 Appropriate organizational units shall function to provide independent review of designated activities as required by ANSI N18.7-1976/ANS-3.2, Sections 4.3, 4.3.1, 4.3.3, and 4.3.4.

5.2.1 Staff personnel required to perform these independent reviews shall collectively have the experience and competence to review operational activities in the following areas:

5.2.1.1 Nuclear power plant operations; 5.2.1.2 Nuclear engineering; 5.2.1.3 Chemistry and radiochemistry; 5.2.1.4 Metallurgy; 5.2.1.5 Instrumentation and control; 5.2.1.6 Radiological safety; 5.2.1.7 Mechanical and electrical engineering; 5.2.1.8 Civil engineering; 5.2.1.9 Training;

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OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 5 OF 8 EFFECTWVE DATE 02-01-04 5.2.1.10 Nuclear assurance; 5.2.1.11 Nuclear licensing; 5.2.1.12 Plant security, and; 5.2.1.13 Environmental impact Note: If sufficient expertise is not available from within the STPNOC for the areas noted above, appropriate expertise shall be brought to bear in the independent reviews through the use of outside consultants.

5.2.2 The SMT shall functionally report to and advise the President and Chief Executive Officer on those areas of responsibility specified in sections 5.2.3 and 5.2.4.

5.2.3 Appropriate organizational units shall be responsible for the review of:

5.2.3.1 The safety evaluations for: (1) changes to procedures, equipment, or systems; and (2) tests or experiments completed under the provision of 10CFR50.59, to verify that such actions did not require prior NRC approval; 5.2.3.2 Proposed changes to procedures, equipment, or systems which require prior NRC approval under the provisions of 10CFR50.59; 5.2.3.3 Proposed tests or experiments which require prior NRC approval under the provisions of I OCFR50.59; 5.2.3.4 Proposed changes to Technical Specifications or the Operating License; 5.2.3.5 Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; 5.2.3.6 Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; 5.2.3.7 All REPORTABLE EVENTS;

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OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 60F8 EFFECTIVE DATE 02-01-04 5.2.3.8 All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and 5.2.3.9 Reports and meeting minutes of the PORC.

5.2.4 Reports of audits of unit activities shall be reviewed by the SMT. I 5.2.5 Records of organizational unit independent review activities shall be prepared, approved, and distributed as indicated below:

5.2.5.1 Reports of organizational unit independent reviews encompassed by sections 5.2.3 and 5.2.4 shall be prepared, approved, and forwarded to the President and Chief Executive Officer and the SMT.

5.3 Technical Review and Control 5.3.1 Activities that affect nuclear safety shall be conducted as follows:

5.3.1.1 Procedures required by Technical Specification 6.8 and l Technical Requirements Manual 6.8, and other procedures that 6 affect nuclear safety, and changes thereto, shall be prepared, reviewed, and approved. Each such procedure, or change thereto, shall be reviewed by an individual/group other than the individual/group who prepared the procedure, or change thereto, but who may be from the same organization as the individual/group who prepared the procedure, or change thereto. Procedures other than station administrative procedures shall be approved by the Plant Manager, Plant Superintendent, or the head of the responsible department prior to implementation. The Plant Manager shall approve station administrative procedures, security plan implementing procedures, and emergency plan implementing procedures.

Temporary changes to procedures, which clearly do not change the intent of the approved procedures, shall be approved prior to implementation by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License.

Changes to procedures that may involve a change to the intent of the original procedure shall be approved by the individual authorized to approve the procedure prior to implementation of the change.

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OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 7 OF 8 EFFECTWVE DATE 02-01-04 5.3.1.2 Proposed changes or modifications to safety-related structures, systems, and components shall be reviewed as designated by the Plant Manager. Each such modification shall be reviewed by an individual/group other than the individual/group who designed the modification, but who may be from the same organization as the individual/group who designed the modification. Proposed modifications to safety-related structures, systems, and components shall be approved by the Plant Manager prior to implementation.

5.3.1.3 Proposed tests and experiments that affect nuclear safety and that are not addressed in the Final Safety Analysis Report shall be prepared, reviewed, and approved prior to implementation.

Each such test or experiment shall be reviewed by an individual/group other than the individual/group who prepared the test or experiment but who may be from the same organization as the individual/group who prepared the test or experiment. Proposed tests and experiments shall be approved by the Plant Manager.

5.3.1.4 Individuals responsible for reviews performed in accordance with sections 5.3.1.1, 5.3.1.2, and 5.3.1.3 shall be members of the plant management staff previously designated by the Plant Manager. Each review shall include a determination of whether or not additional, cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by qualified personnel of the appropriate discipline.

5.3.1.5 Each review will include a determination of whether or not prior NRC approval is involved pursuant to 10CFR50.59.

NRC approval of items will be obtained prior to Plant Manager approval for implementation.

5.3.2 Records of the above activities shall be provided to the Plant Manager, PORC, and/or the appropriate organizational unit as necessary for required reviews.

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Chapter OPERATIONS QUALITY ASSURANCE PLAN 19.0 01 ADMINISTRATIVE CONTROLS PAGE 8 OF 8 EFFECTIVE DATE 02-01-04 I

6.0 DOCUMENTATION

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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 the requirements of this chapter and Reference 4.4. /

7.0 ATTACHMENTS 7.1 None

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