ML17354B000
| ML17354B000 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Turkey Point  |
| Issue date: | 03/18/1998 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17354A999 | List: |
| References | |
| NUDOCS 9806300067 | |
| Download: ML17354B000 (205) | |
Text
Florida Power,& Light Topical Quality Assurance Report June, 199S ENCLOSURE 'III
'N06300067 980622 PDR ADQCK 05000250 PDR
ill II)
TOPICAL QUALITYASSURANCE REPORT FPLTQAR 1-76A Rev: 16 Title Page Date:06/12/90 FPL TQAR 1-76A.
(FPL-NQA-100A)
REVISION 16 JUNE 12,,1990 TOPICAL QUALITY ASSURANCE REPORT Procedure No: FPLTQAR.1-76A Rev: 16 Page 1 of 1
ili ili
TOPICAL QUALITYASSURANCE REPORT Rev: 147 Revision Summary
'ate:03ftN98
SUMMARY
OF MANUALREVISION PQOC I~O QEV
SUMMARY
TQR 1.0 32 Documents that describe the Nuclear Material Control and Accountability Program are changed from the Special Nuclear Material. Control Manual to Nuclear Fuel Standards in Paragraph 1.3.1.3.b.
Appendix A Figure 1-3 St..Lucie organization chart revised as a result of.a reorganization.
Procedure No: Rev: 147 Revision Summary Page 1 of 1
ili il~
TOPICAL QUALITYASSURANCE REPORT Rev: 4 Abstract Date:06/24NB Florida Power 8 Light Company (FPL) has established'and implemented a Quality Assurance Program to provide assurance that the design, procurement, modification and operation, of nuclear power plants conform with applicable'regulatory requirements. The FPL Quality Assurance Program described in this Topical Report is in compliance with the requirements of Appendix B to 10 CFR Part 50.
The FPL Quality Assurance Program meets the requirements provided by the NRC Regulatory Guidance
.and Industry Standards as listed in Appendix C of this Topical Quality Assurance Report.
Procedure No: Rev: 4 Abstract Page 1 of 1
~li lit Oi
h (
~hh hggy fp0 t~ UNITED STATES nO NUCLEAR REGULATORY COMMISSION I
Vl C WASNNQTOH, O.C.'~
O
+ ~O 4y NJ610 ie SCDB:TNI 07100169
~ECPypo
'Florida Power 5. Light Company ATTH: Hr. J. E. Geiger Vice President 4te]~ 6 Huclear Assurance P.O. Box 14000 Juno Beach, .FL 33408-0420
Dear Hr. Geiger:
Enclosed is.,guality Assurance Program Approval for Radioactive Haterial Packages Ho. 0169, Revision Ho. 5.
Please note the conditions in 'the Approval.
This Approval will remain in effect until the expiration date, indicated in Block Ho. 3. Termination of a materials license does not cause this Approval to be .automatically terminated. If you wish to. renew, amend, or terminate this Approval, please request. it in writing.
Sincerely, John P. Jankovich, Section Leader guality Assurance Section Source 'Containment and Devices Branch Division of Industrial and Hedical,HucIear Safety, HHSS
Enclosure:
As stated
ili ill O~
U. S. NUCLEAR REGUIATORY COMMISSION I ~ APPROVAL rsUI4SER NRC FORM SII QUALITYASSURANCE PROGRAM APPROVAL FOll RADIOACTIVEMATERIALPACKAGES pursuant to che Acome Enersy Act ol 'I 954, as amended. the Enerey Reoreanltacion Act of 1574, as amencled. and Thle 10. Code of Federal Recrulatlons, chapter I, Part 71, and In reliance on statemencs and representations heretofore made in Item 5 by che person nemed in leam 7.
the Duality Asnrrence Program Identified In Item 5 is hereby approved. This approval Is Issued to satisfy the reoulrements of Session 71.151 of 10 CFR part 71. This apprmrat ls sublect to acl spot@able rule. resucachcns, end orders ol the Nwlear Reprlacory Commits>>n now or hamarcer In effect end co any condldons speelfwd below.
- 2. NAME S. EXPIRATION DATE Plorida Potrer 5 Light Company STREET ADDRESS August 31. 1999 P 0 Box 14000 4. DOCKET NUIASER ZIP CODE Juno Beach 33408-0420 07100169
- 5. OUAVTYASSURANCE PROGRAM APPV CATION PATE($ )
Jul 21,
'. CONDITIOIIS 1994 Activities conducted with regard to transportation packages under applicable criteria of Appendix B to 10 CFR Part 50 authorized by this approval: procurement, maintenance, repair, and use. All other activities (i.e., design, fabrication, assembly, and modification) shall be satisfied by obtaining certifications from package suppliers that these activities were conducted in, accordance with an NRC-approved gA program.
It shall remain the responsibility of the licensee-user that all transportation activities meet the.'requirements of 10 CFR 571.101.
- 2. Records describing activ'ities affecting quality must be kept for three years after the gA~rogram ends in accordancewith 10 CFR 71.135.
FOR THE UA. IIUCLEAR REGULATORT COMSSISSION 7 >rc ohn P. J ovich DATE DNISION OF INDUSTRIALAND MEDICALNUCLEAR SAFETY OFRCE OF NUCIEAR MATERIALSAFEIY AND SAFEGUARDS
ev
<I~
F ig~
Oi i
TOPICAL QUALITYASSURANCE REPORT Rev: 56 Table of Contents Date:03/18/98 TOPICAL QUALITYASSURANCE REPORT REV RELEASE TITLE QO ~DT Title Page 16 June 12, 1990
.Revision Summary 147 March 18, 1998 I Abstract June 24, 1988 NRC Letter 8 Certificate - Quality August 10, 1994 Assurance Program Approval for t
Radioactive Material Packages Table of Contents 56 March 18, 1998 I Quality Assurance Program Policy 10 June 3, 1996 Introduction 14 June 3, 1996 To ical uali Re u e en s TQR 1.0 Organization 32 March 18, 1998 I TQR 2.0 Quality Assurance Program. 15 October 16, 1996 TQR 3.0 Design Control 13 October 16, 1996 TQR 4'.0 Procurement Document Control October 16, 1996 TQR 5.0 Instruction, Procedures & Drawings 12 February 28, 1997 TQR 6.0 Document Control February 28, 1997 TQR 7.0 Control of Purchased Items'& Services February,28, 1997 TQR 8.0 Identification & Control of Material; Parts February 28,.1997 8: Components TQR 9.0 Control of Special Processes 13 February 28,,1 997 TQR 10.0 Inspection 12 June 3, 1996 Procedure No: Rev: 56 Table of Contents Page 1 of 2
~ ~
il~
TOPICAL QUALITYASSURANCE REPORT REV RELEASE TITLE ~O DATE TQR 11.0 Test Control February 28, 1997 TQR 12.0 Control of Measuring & Test Equipment February 1, 1994 TQR 13.0 Handling, Storage & Shipping 10 February 28, 1997 TQR 14.0 Inspection, Test & Operating Status June 3, 1996 TQR 15.0 Nonconforming Materials, Parts or Components 12 February 28, 1997 TQR 16.0 Corrective Action 10 October 16, 1996 TQR 17.0 Quality Assurance Records October 16, 1996 TQR 18.0 Audits June 3, 1996 Q~edjces A - Organizations 8 Figures Figure 1-1:Organization of Departments 25 April 30, 1997 Affecting Quality Figure 1-2:Turkey Point Nuclear 13 November 18, 1997 Site Organization Figure 1-3:St. Lucie Nuclear March,18,1998 I Site Organization B - Qualification 8 Experience Requirements June 12, 1990 for Quality Assurance Personnel C - Baseline Document Matrix 15 October 16, 1996 D - Cancelled May 7, 1982 E - Cancelled 19 April 26, 1996 F - Topics to be Addressed in Safety May 7, 1982 Analysis Reports GIos~sry Glossary 24 July 18, 1997 Procedure No: Rev: 56 Table of Contents Page 2 of 2
I i/i il~
TOPICAL QUALITYASSURANCE REPORT Rev: 10 Quality Assurance Program Policy Date:06/03/96 EED F POLICY To avoid undue risk to the health and safety of the public and company employees, it is necessary to design, construct, operate and modify nuclear power plants with a high degree of. functional integrity, quality and reliability.
S TE E T OF POLICY It is the policy of Florida Power 8 Light Company'to design, construct, operate and modify nuclear power plants of a quality level. that will meet or exceed government regulations and will merit public confidence by providing electricity in a reliable efficient and'safe manner.
ES 0 S BILT The Chairman of the Board and Chief Executive Officer of Florida Power & Light Company has delegated responsibility for execution of the Quality Assurance Program for Florida Power & Light Company nuclear plants to the President, Nuclear Division. The authority for developing and verifying execution of the program is delegated to the Director Nuclear Assurance.
The head of each organization performing quality-related activities is responsible for: identifying those activities within their organization which are quality-related as defined by the QA Program; establishing and clearly defining the duties and responsibilities of personnel within their organization who execute those quality related activities; and planning, selecting, and training personnel to meet the requirements of the QA program.
T. F.'Plunkett President, Nuclear Division Procedure No: Rev: 10 Quality Assurance Program Policy Page 1 of 1
TOPICAL QUALITYASSURANCE REPORT Rev: 14 Introduction Date:06/03/96 The Topical Quality Assurance Report (FPLTQAR 1-76A) contains the description of the Florida Power &
Light Company (FPL) Quality Assurance Program relative to its nuclear power plants. This report consists of three parts: The Introduction, which delineates the purpose and summarizes the scope and applicability of the Topical Quality Assurance Report. The second part, Topical Quality Requirements (TQRs), which delineate Quality Assurance Program requirements and summarizes the FPL approach to activities related to materials, parts, components, systems and services included in the Quality Assurance Program. The third part, Appendices, which provide supporting statements, tabulations, and technical analyses or deviations which are not, in themselves, the subject of the report.
The corporate Quality Assurance Manual (FPL-NQA-100A) consists of the Topical Quality Assurance Report and a Glossary of commonly used terms. The Topical Quality Assurance Report delineates the generic requirements and responsibilities by which FPL implements the corporate Quality Assurance Program. Revisions and changes to this report are made in accordance with a Quality Instruction outlined in TQR 2.0.
In addition to the Quality Assurance Manual, Quality Instructions (Qls) are developed as required by each of the implementing plants and departments. Quality Instructions describe the measures to be used to implement the quality requirements of the Quality Assurance Manual. The Quality Instructions describe actions and responsibilities to be performed within a department or organization and address the requirements of the appropriate Topical Quality Requirements. I'l The FPL Quality Assurance Program meets the requirements provided by the,NRC Regulatory Guidance and Industry Standards as listed in Appendix C of this Topical Quality Assurance Report.
The requirements of this Topical Quality Assurance Report apply to safety-related materials, parts, components, systems and structures; services employed for design, procurement construction, operation, maintenance, refueling, repair, and modification; and packaging and shipping of radioactive material (but not design and fabrication of packages for which a license, certificate of compliance, or other approval must be issued by the NRC) in accordance with 10 CFR Part 71. The safety-related systems for each plant are specified in the respective plant Safety Analysis Report.
The'FPL Quality Assurance Program fully addresses the requirements of Appendix B to 10 CFR Part 50.
The Topical Quality Assurance Report shall be applicable to all existing nuclear plants, those under construction, and supporting FPL departments, and will be referenced in the Safety Analysis Report (SAR). For future plants, the description of activities, requirements, and organizations structures that are unique to a particular plant shall be addressed in the respective SAR document.
Director Nuclear Assurance Procedure No: Rev: 14 Introduction Page1 of1
i b
iIi ig~
il~
4 J
TOPICAL QUALITYASSURANCE REPORT TQR 1.0 Rev: 32 Organization Date:03/18/98 1.1 GENERAL RE U E E The Florida Power & Light (FPL) organizational structure shall be defined such that the responsibilities for establishment and implementation of the Quality Assurance Program are clearly identified. The authority and duties of individuals and organizations performing quality assurance and quality control functions shall be described, and shall illustrate the organizational independence and authority necessary to identify problems; to initiate, recommend, or provide solutions; and to verify implementation of solutions. In addition, the description shall illustrate that persons or groups responsible for verifying the correct performance of an, activity are independent of the person or groups responsible for performing the activity.
1.2 IMPLE ENTAT ON The FPL Chairman of the Board and Chief Executive Officer is ultimately responsible for the execution of the Quality Assurance Program for FPL nuclear power plants. The authority for developing and verifying execution of the program is delegated to the President Nuclear Division and the Director Nuclear Assurance. The reporting relationship of each department involved with the Quality Assurance. Program is shown in Appendix A.
To provide for a review and evaluation of Quality Assurance Program policies and activities, the President Nuclear Division has established the Company Nuclear Review Board (CNRB). This organization's responsibilities are defined in Section 1.3.1.
In addition, a Quality Assurance Program Review Committee (QAPRC) has been established to review changes to the Quality Assurance Program and to provide an interface for quality matters in each department affecting quality. The QAPRC is an interdepartmental organization with the responsibility to review and resolve recommended changes to the Quality Assurance Program.
This committee is administered by the Quality Assurance Performance Assessment group.
Quality Assurance Program changes reviewed by the QAPRC are reviewed and signed by the affected department heads.
A Quality Assurance Program Review Committee (QAPRC) Member shall be designated by the head of each department or organization. The QAPRC Member is the prime interface for coordination of quality matters within the member's department, with the Quality Assurance Department, and with other departments.
Procedure No: TQR 1.0 Rev: 32 Page 1 of 13
Oi Qi II
The head of each department or organization performing activities affecting quality is responsible for: a) identifying those activities within the organization which affect quality as defined by the Quality Assurance Program; b) establishing and clearly defining the duties and responsibilities of personnel within his organization who execute those activities affecting quality; and c) planning, selecting, and training personnel to meet the requirements of the Quality Assurance Program.
The responsibility, authority, and organizational relationship for performing activities affecting quality within each organization shall be established and delineated in organizational charts and written job or functional descriptions.
Activities affecting quality may be performed by FPL or be contracted. Should any of these functions be contracted, the contractor may perform the activities under his own Quality Assurance Program, which must have prior approval by FPL Quality Assurance, or the contractor may directly adopt the requirements of the FPL Quality Assurance Manual. If the contractor implements the Quality Control function directly to the FPL Quality Assurance Manual requirements, the contractor's Quality Control Supervisor shall have the authority and freedom to administer the Quality Control program.
1.3 E 0 SIB L IE The organization charts in Appendix A illustrate the lines of authority and areas of responsibility for each of the organizations that are involved in activities affecting quality. Below are listed the departments and organizations that have quality assurance responsibilities. Organizational responsibilities for implementation of the Quality Assurance Program are described in the Topical Quality Requirements (TQRs).
1.3.1.1 Plant Vice Presidents 1.3.2.1 Corporate Records 1.3.1.2 Licensing and Special Programs 1.3.2.2 Environmental Services 1.3.1.3 Nuclear Engineering. 1.3.2.3 Protection & Control Systems 1.3.1.4 Nuclear 1.3.2.4 Information Assurance Management 1.3.1.5 Nuclear Business Services 1.3.1 I r Div'hroughout plant life, the Nuclear Division maintains control of and responsibility for nuclear power plant design, preoperational and start-up testing, operation, maintenance, refueling, and modification of the plant in accordance with written and approved procedures.
The President Nuclear Division has overall responsibility for the Nuclear Division's activities including corporate responsibility for overall plant nuclear safety. Reporting to the President Nuclear Division are: the Vice President - Turkey Point Plant, Vice President - St. Lucie Plant, Director Nuclear Assurance, Vice President Nuclear Engineering, Manager of Licensing and Special Programs, and the Director Nuclear Business Services.
Procedure No: TQR1.0 Rev:32 Page 2 of 13
I ill 4i Oi
The Company Nuclear Review Board (CNRB), reporting to the President Nuclear Division, is comprised of executive level members of management with responsibilities for the execution of the Quality Assurance Program. The CNRB reviews, or directs the performance of reviews of, activities concerning the technical aspects of the operating nuclear power plant insofar as they impact plant safety, the health and safety of the public, and laws, regulations and licensing commitments. In addition, audits of these areas are performed under the cognizance of the CNRB.
The CNRB composition is described in Section 6.0 of each facility's Technical Specifications. Subjects within the purview of the CNRB are listed in the appropriate plant Technical Specifications. The CNRB has the authority to carry out its responsibilities by way of written action letters, verbal directions, meeting minutes or appointed subcommittees. Where necessary, the CNRB may use consulting services to perform required reviews.
The CNRB is responsible for reviewing and evaluating Quality Assurance Program policies and activities. Quality Assurance Program status reports shall be periodically given by the Quality Assurance Department.
CNRB meetings shall be held by the Chairman to keep members apprised of conditions including significant problems that require management attention. Periodic audits of the Quality Assurance Department shall be performed by a team independent of the Quality Assurance Department. The results of this audit are presented to the Director Nuclear Assurance and the CNRB.
1.3.1.1 Plant Vice Presidents The Vice President - St. Lucie Plant and Vice President - Turkey Point Plant are accountable for the operation, maintenance, and modification of their respective nuclear plant, as well as the selection, development and direction of the assigned staff. They will act as liaison between the plants and corporate headquarters, and are accountable for ensuring that company policies and procedures are properly implemented and continued at the nuclear site, including procurement and control of material. The Plant Vice President has overall responsibility for implementation of the Environmental Protection Plans'at their respective sites.
Other responsibilities of the site'Vice President include the following:
~ Configuration management.
~ Preparation of policy documents regarding nuclear training;
~ Support to secure the necessary resources to ensure that site personnel are adequately trained. They must have adequate technical and job related skills to provide safe and efficient operation while complying with NRC requirements.
Procedure No: TQR1.0 Rev: 32 Page 3 of 13
i/i Qi
~ Coordinate'with the opposite plant site for overall development and implementation of the FPL Nuclear Security program.
I r in
~ Coordinating contract activities.
~ Reviewing contracts to assure that technical and quality requirements developed by others are incorporated into the procurement documents which it authorizes.
~ Ensuring that site-based information management programs are in compliance with FPL software QA commitments.
~ Business Systems Departments at PSL and PTN are accountable for directing the identification, design, development, implementation, on-going maintenance, and control of all nuclear site specific data processing information management systems (excluding process applications), and identifying applicable site specific software in a Computer Software Index (CSI).
i nin
~ Maintenance of the operating license;
~ Interface with the NRC;
~ Resolution of NRC safety and regulatory issues;
~ Administering the Operating Experience and Feedback System.
N I rM ri n m
~ Negotiation, generation, issuance of procurement documents for required items and services supporting the operation, licensing, maintenance, notification, and inspection of FPL nuclear plants, and for materials and equipment to support Nuclear Division staff;
~ Reviewing procurement documents to assure that technical and quality requirements developed by others are incorporated into the procurement documents which it authorizes.
The organization of Turkey Point Plant and St. Lucie Plant is shown in Appendix A.
The Plant General Manager - PSL and Plant General Manager - PTN, through the respective Plant Vice President, are responsible for the safe operation of the nuclear plant. The Plant General Managers have control of the onsite resources necessary for the safe operation and maintenance regardless of organizational reporting.
The Plant Nuclear Safety Committee (PNSC) at Turkey Point Plant and the Facility Review Group (FRG) at the St. Lucie Plant are comprised of key plant management and staff personnel as described in the plant Technical Specifications. The PNSC/FRG serves the plant manager in a technical advisory capacity for the review of all safety-related procedures and activities that impact plant safety and the facility operating license.
Procedure No: TQR1.0 Rev:32 Page 4 of 13
4+ k ili III
~i
1.3.1.2 Licensing and Special Programs The Manager Licensing and Special Programs is responsible for selected
, licensingsupportactivitiesatthe Juno BeachOffice. This includes:
~ Advising senior Nuclear Division management on a regular basis of important developments in licensing areas which could significantly affect the Nuclear Division;
~ Coordinating with the Law Department for Nuclear Division licensing hearings and legal services;
~ Administering special programs, such as:
~ Environmental issues,
~ Self assessment,
~ INPO coordination,
~ Serving as FPL liaison in matters of high level waste disposal.
1.3.1.3 Nuclear Engineering The Vice President Nuclear Engineering is responsible for nuclear plant design and engineering support.
The Nuclear Engineering organization is shown in Appendix A.
- a. Nuclear Engineering Nuclear Engineering includes personnel located at both nuclear sites and at the corporate office. Nuclear Engineering performs design-related activities and delegates design-related activities to qualified contractors.
For activities performed by Nuclear Engineering, the work is governed by FPL's Quality Assurance Program, and Nuclear Engineering is responsible for approval of the design output.
Delegated activities are performed in accordance with an FPL approved Quality Assurance Program and the contractor is responsible for approval of design output. Nuclear Engineering is responsible for defining the scope of delegated activities and the responsibilities of the contractor. Prior to the release of design outputs by contractor organizations, Nuclear Engineering ensures that the contractor is technically qualified to perform the design-related activity.
The Manager - Turkey Point Engineering and the Manager - St. Lucie Engineering provide on-site engineering support and direct the engineering aspects of all FPL nuclear power plant projects during construction and.operation to assure efficient, economical and reliable power plant design, conformance with engineering schedules and budgets and compliance with regulator requirements.
Procedure No: TQR1.0 Rev:32 Page 5 of 13
Nuclear Engineering is responsible for:
~ power plant design related aspects of the FPL Quality Assurance Program throughout all phases of plant life;
~ development and maintenance of the design control program governing design-related activities performed by Nuclear Engineering and for providing technical support to the. Quality Assurance Department for assessing the adequacy, implementation and effectiveness of'contractor design control programs;
~ the preparation, revision, approval and distribution of plant design records that are identified to be maintained as "as -constructed" drawings during plant operation;
~ the development, control, and performance of certain aspects. of items and services procurement, including establishment of procurement standards, the technical evaluation, equivalency evaluation, and commercial grade dedication of replacement parts/components for nuclear plants;
~ review of the technical and quality requirements in procurement requisitioning documents and changes thereto for safety related and quality related items and services, as well as configuration control activities for controlled design documentation associated with procurement. The review shall be performed by individuals other than the document originator,
~ Plant license renewal.
Aspects of the above activities are performed by the Juno Beach Engineering organization as determined by the Vice President Nuclear Engineering.
b..Nuclear Fuel The Manager Nuclear Fuel is responsible for nuclear fuel engineering and procurement activities including the following:
~ assuring that technical and quality requirements (including inputs from other FPL departments) are incorporated in fuel contracts and letters of authorization;
~ .administering and managing contracts for, nuclear fuel and related services to assure that technical and quality obligations are met, and serving as FPL liaison in all matters of nuclear fuel and fuel-related contracts; Procedure No: TQR1.0 Rev:32 Page 6 of 13
O~
Oi O~
~ administering and managing spent fuel disposal contracts with Department of Energy and serving as FPL liaison in matters of nuclear fuel;
~ all fuel related design, analyses, reviews,,and technical assistance necessary. to ensure the safe, reliable, and economic operation of the nuclear plants;
~ the development and/or review of fuel and nuclear physics design; Revtgeg) ~
, ~ implementing and maintaining the FPL corporate nuclear material accountability program as described in Nuclear Fuel Standards;
~ providing support to the Quality Assurance Department for their auditing of nuclear fuel design and fuel assembly manufacturing;
~ performing audits and coordinating accountability reporting on all nuclear fuel.
- c. Component Support and Inspections
~ The Manager Component Support.and Inspections is responsible for providing support to the plants as follows:
~ providing technical support of activities associated with component reliability, materials evaluations, inspections, corrosion protection, non-destructive examiriation,.and ASME Section XI implementation/problem resolution for. nuclear plant components;
~ providing specific component expertise, metallurgical support, and non-destructive examination and inspections;
~ establishing the FPL Welding Program to meet the requirements of the Quality Assurance Program and applicable codes and standards;
~ developing, maintaining, and controlling the procedures and instructions to implement the FPL Welding Program; and
~ originating and qualifying welding procedure specifications; and
- d. Reliability and Risk Assessment The Supervisor of Reliability and Risk Assessment is responsible. for providing support to the plants as follows:
~ prepare and maintain Probabilistic'Safety Assessment (PSA) for each plant;
~ perform Risk Assessments, in support of Maintenance activities;
~ perform Risk Assessments in support of the NRC'Maintenance Rule.
'Procedure No: TQR1.0 Rev: 32 Page 7 of 13
Wa ig~
ig~
ggi I 4
1.3.1.4 Nuclear Assurance The Director Nuclear Assurance is responsible for the selection, technical direction, administrative control (e.g. performance appraisal, salary review, hire/fire, position assignment) staffing, training and development of personnel required for supervisory and operating continuity of the Quality Assurance Department, Nuclear Safety Speakout, and the CNRB Subcommittee. The Director Nuclear Assurance serves as the CNRB Chairman. The Director Nuclear Assurance also initiates QA Program policy changes when necessary.
In addition, the Director Nuclear Assurance is responsible for selecting a team independent of the Quality Assurance Department to perform periodic audits of the Quality Assurance Department. The results of these audits are presented to the Director Nuclear Assurance and the Company Nuclear Review Board (CNRB).
The Nuclear Assurance organization is shown in Appendix A.
- a. Nuclear Safety Speakout The Nuclear Safety Speakout Program provides a forum for employees and contractors to communicate their concerns to FPL. Concerns are documented, investigated and corrective actions are taken when necessary.
The program offers confidentiality.
- b. Quality. Assurance'Department The Quality Assurance Department is responsible for administering the FPL Quality Assurance Program. This includes developing and verifying implementation of corporate policies, plans, requirements, and procedures affecting quality. The Quality Assurance Department retains responsibility for delegated portions of the Quality Assurance Program by performing initial evaluation and subsequent periodic audits of the contractors'uality Assurance Programs. The Quality Assurance Program responsibility further extends to the performance of audits within the Company to assure management that the established requirements and procedures are being implemented, and that the Program complies with the baseline document requirements.
The organizational freedom of the Quality Assurance function is accomplished through the corporate structure, illustrated in Appendix A, which provides independence from those departments responsible for design, procurement, engineering, construction and operation. With quality assurance as its sole function the. Quality Assurance Department, both on-site and off-site, is completely free from the cost and scheduling pressures of design, procurement, construction and operation. The Quality Assurance Department has the freedom and authority to: a) identify quality problems; b) initiate, recommend or provide corrective action; c) verify implementation of the corrective. action; and d) recommend the stoppage of Procedure No: TQR1.0 Rev:32 Page 8 of 13
il~
III ili
work or operations adverse to quality, when necessary. The QA Supervisor Performance Assessment, QA Supervisor Procurement Quality, Site Quality Manager - St. Lucie, and Site Quality Manager - Turkey Point report administratively and functionally to the Director Nuclear Assurance. These reporting relationships assure that:the Quality Assurance Department has direct access to the levels of management necessary to assure effective implementation of the Quality Assurance Program.
The duties, responsibilities, and authorities of each Quality Assurance group are described in the sections which follow.
- 1) Performance Assessment The QA Supervisor, Performance Assessment directs and administers the. Corporate Quality Assurance Program assuring compliance with the baseline documents listed in Appendix C of this Topical Quality Assurance Report. Quality Performance Assessment activities include the'following:
~ develop and maintain the corporate Quality Assurance Manual, including the administration of the Quality;Assurance Program Review Committee (QAPRC);
~ develop and implement a Quality Assurance indoctrination program
.for FPL personnel;
~ prepare reports on Quality Assurance Program activities for review, by the CNRB;.
~ plan, coordinate and implement a comprehensive system of periodic internal audits with support from the other'Quality Assurance groups, when necessary;
~ .perform periodic activity audits of FPL procurement and associated, documents and changes,to these documents to assure that the necessary quality requirements are imposed;
~ provide NDE Level III services including technical direction and monitoring of NDE activities performed by Quality Control at the
'plant sites (PTN and PSL).
- 2) Procurement Quality The QA Supervisor Procurement Quality directs and administers the Procurement Quality program in support'of both nuclear plants.
'Procurement Quality activities include the following:
Procedure No: TQR1.0 Rev:32 Page'9 of 13
ilt J'gi Oi
~ .perform appropriate. surveillance of hardware during manufacture;
~ develop.and implement a program for auditing of supplier Quality Assurance/Quality Control programs including Architect Engineer/Nuclear Steam Supply System Suppliers;
~ assist other FPL departments in the identification of quality problems associated with procurement and storage; initiate, recommend, or provide solution; and verify implementation of solutions;
~ maintain, the Quality Assurance Department list of approved suppliers; For. purchased items and services, the responsibility of this group extends through receipt of shipment or performance of contract.
- 3) Site Quality Assuiance Turkey Point Nuclear (PTN) and St. Lucie (PSL)
Quality Assurance activities at the plant sites'(PTN and PSL) are accomplished by the respective site Quality Assurance groups, reporting
- to the Site Quality Manager. The Site Quality, Manager has responsibility for on-site development and implementation of the Quality. Assurance Program, including the following:
~ coordinate the development and implementation of quality assurance policies, plans, requirements, and procedures at the plant site;
~ perform audits, assessments and other observations as specified in procedures and instructions to verify compliance with Quality Assurance Program commitments;
~ perform periodic activity audits of site generated FPL procurement and associated documents and changes to these documents to assure that the necessary quality requirements are imposed;
~ recommend stoppage of work or operations adverse to quality at the plant site in accordance with the appropriate instructions;
~ review and comment on Quality Instructions or equivalent quality administrative procedures prior to issue, with respect to the requirements of the FPL Quality Assurance Program, the applicable Final Safety Analysis Report, and the applicable Technical Specifications;
~ perform audits of the architect engineer and Nuclear Steam Supply System suppliers both on-site and off-site, in conjunction with the Procurement Quality group.
Procedure No: TQR1.0 Rev: 32 .
Page 10 of 13
~i ik~
The interface with the Procurement Quality group ends with the receipt of a shipment of nuclear safety-related equipment at the plant site. The Quality Assurance program for the shipment is then within the purview of the Site Quality Assurance group.
The Quality Manager - Turkey Point and Quality Manager - St. Lucie are additionally responsible for the establishment and implementation of quality control aspects of the Quality Assurance Program at the plant site. Reporting directly to the Site Quality Manager are the Quality Control Supervisors who have the authority and freedom to administer the Quality Control program and, when necessary, to stop activities adverse.to quality. The, Quality Control Supervisors and personnel performing Quality Control inspection functions are required to be independent of groups or persons performing, activities that they may be required to verify or inspect.
Quality Control responsibilities include:
~ inspection, monitoring, surveillance, and review of plant activities to verify compliance with the provision of the facility operating license and the Quality Assurance Manual;
~ acceptance of the installed items; 1.3.1.5 Nuclear. Business Services The Director Business Services is responsible for Nuclear Division business and financial planning and analysis and nuclear plant support in the areas of document control and QA records management, division-based and staff computer systems, security, emergency preparedness, and radiological services.
Nuclear Business Services is shown in Appendix A.
- Accountabilities related to division-based and staff computer systems encompass:
~ directing the identification, design, development, implementationon-going maintenance, and control of division-based information management systems;
~ identifying applicable division-based software in a Computer Software Index (CSI);
~ Coordinating and directing computer hardware and telecommunication planning and control;
~ ensuring that the information management programs are in compliance with FPL software QA commitments.
Procedure No: TQR1.0 Rev: 32 Page 11 of 13
III ili 35i
- P hl
132 Su o De m Providing support activities for the Nuclear Division are Corporate Records, Environmental Affairs, Protection 8 Control Systems, and Information Management.
The reporting relationship of each department is described in the following sections and is shown in Appendix A.
1.3.2.1 Corporate Records The Supervisor Corporate Records is responsible for:
~ storage, retrieval and control of Quality Assurance records received from other departments;
~ assisting with the development and implementation of records and micrographics programs;
~ maintaining a QARSET approved storage facility;
~ serving as the Records Official.
1.3.2.1.a The Records Official, reporting to the General Counsel and Secretary is responsible for.
~ ensuring the Quality Assurance records program activities are managed in accordance with applicable recordkeeping requirements;
~ locating acceptable record storage areas when requested;
~ leading the evaluation of specially designated QARSET approved storage facilities, maintaining records of this evaluation, and establishing schedules to assure that re-evaluations are performed every two (2) years.
1.3.2.2 Environmental Services Environmental Services is responsible for obtaining the federal and state environmental permits required for FPL facilities and operations.
Environmental Services is also responsible for providing technical support on environmental regulatory requirements, including regulatory development, enforcement actions, compliance with environmental requirements and environmental assessments and clean-ups at all company facilities, as well as technical support and/or advice on non-radiological environmental monitoring (federal and state) programs at the nuclear power plant sites.
The Site Vice President has overall responsibility for implementation of the Environmental Protection Plans (EPPs) at nuclear, power plant sites.
The Environmental Services Department through its functional areas is responsible for providing technical support and/or advice on non-radiological environmental monitoring programs and oversight, of other requirements related to the Environmental Protection Plans. The Department provides review of proposed changes to the Environmental Protection Plans, review of plant changes, tests or experiments and review of other plant activities which may be subject to environmental regulations to ensure their compliance.
Procedure No: TQR1.0 Rev:32 Page 12 of 13
0~
i/i ili
The Department provides'information as necessary to the CNRB Chairman on environmental matters for which requirements are included in Environmental Protection Plans.
1.3.2.3 Protection & Control Systems The Director of Protection & Control Systems reports to the Vice President of Power Delivery.
Protection & Control Systems is responsible for:
~ test, calibration and maintenance of certain high voltage electrical protective relays for safety-related systems of the nuclear plant;
~ final wiring connection checks;
~ preoperational check-out and test of system protection devices;
~ providing inspection of equipment under their cognizance;
~ providing certain setpoint and checkpoint values for protective devices.
1;3.2.4 Information Management The Corporate Information:Management organization is shown in Appendix A.
Information Management is responsible for ensuring the integrity of the operating. environment and the applications used by the Nuclear Division.
The Director of IT Operations and the Director of Business Systems report to the Vice President of Information Management.
1.3.2A.a The Director of IT Operations is responsible for:
~ the installation and maintenance of operating, system software and the operation of, computer hardware for FPL's corporate computer system;
~ executing software production release and change control activities.
1.3:2.4.b The Director of Business Systems is responsible. for administering physical databases and providing on-going technical support.
Procedure No: TQR1.0 Rev: 32 Page 13 of 13
il~
~gi 3Qi
TOPICAL QUALITYASSURANCE REPORT TQR 2.0 Rev: 15 Quality Assurance Program Date:10/16/96 2.1 GE E L RE U E E S Florida Power 8 Light Company has established a Quality Assurance Program which complies with the, criteria of 10 CFR 50 Appendix B, and meets, the requirements of Regulatory Guides and Industry Standards referenced in Appendix C of this report. The Topical Quality Requirements and attached Policy Statement, together with Quality Instructions document the Program and the FPL policy with regard to Quality Assurance. This Program shall be instituted for each plant site in a schedule consistent with accomplishing the required activity and shall be carried out throughout the life of FPL nuclear plants.
The requirements of the FPL Quality Assurance Program shall only apply to nuclear safety related structures, systems, and components as identified in the Safety Analysis Report for each nuclear unit. Additionally, the requirements of the FPL Quality Assurance Program shall apply to all FPL, contractor, or consultant organizations performing activities affecting the quality of safety related structures, systems, and components of FPL nuclear power plants. Portions of the FPL Quality Assurance Program requirements are also applicable to Quality Related items and services. Those portions applicable to specific Quality Related items or services shall be delineated in appropriate instructions.
Documented procedures shall require and define indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintained.
Periodic program reviews of the status and adequacy of the FPL Quality Assurance Program shall be accomplished by the independent audit team described in Section 2.2.6.d and by Quality Assurance Department audits.
Management of organizations outside Florida Power 8 Light Company, participating in the Program shall be required to regularly review the status and adequacy. of that part of the FPL Quality Assurance Program which they are executing. The FPL Quality Assurance Department shall review and concur in the Quality Assurance Program of contractors.
2.2.1 Goals and Objectives As stated in the Policy Statement of the President of the Nuclear Division, the goal of the FPL Quality Assurance Program is to maintain quality levels in an effective and efficient manner, and to assure the high degree of functional integrity and reliability of nuclear safety related structures, systems, and components. To meet this goal, the following objectives of the FPL Quality Assurance Program have been defined:
Procedure No: TQR2.0 Rev:15 Page1 of 5
il~
~ ~
!I~
- a. Define through documented procedures and instructions the quality activities that apply to the design, fabrication, procurement, modification, testing, operation, refueling, maintenance, and repair of nuclear power plants;
- b. Establish, assign, and document the responsibilities for those activities affecting quality of safety related structures, systems, and components; C. Establish confidence that the design, fabrication, modification, and operation of nuclear power generation facilities are performed in a manner consistent with FPL policies by assuring activities affecting quality are performed by responsible personnel;
- d. Apprise management of unresolved problems and trends which could have a significant effect. on nuclear power plant safety; and
- e. Prevent schedule delays and high cost due to poor quality.
2.2.2 Program Documentation The Topical Quality Assurance Report, which defines the policy, goals, objectives, responsibilities and interfaces regarding the Quality Assurance Program, shall be contained in the FPL Quality. Assurance Manual, and used as guidance for the development of Quality Instructions. Revisions to the Topical Quality Assurance Report will be made, as needed, to reflect current FPL program requirements and descriptions of activities. These revisions shall be made in accordance with a Quality Instruction. If a program reflects a reduction of the commitments from the baseline documents contained in Appendix C, the revision shall be submitted to and approved by the NRC prior to implementation.
In all other cases, amendments to the Topical Quality Assurance Report will be submitted to the NRC to reflect implemented program revisions on an annual or more frequent basis.
Each department head shall have the responsibility for implementation of the Quality Assurance Program, which includes compliance with procedure requirements applicable to the department. In addition, each department head shall be responsible for the preparation, approval, and distribution of Quality Instructions, operating procedures, testing procedures, or other instructions where further guidance is necessary for implementation of the Quality Assurance Program requirements within the department.
Quality Instructions shall be reviewed by the Quality. Assurance Department at each revision.
2.2'.3 Structures, Systems, and Components The requirements of the FPL Quality Assurance Program shall apply to nuclear safety
.related structures, systems, and components, as defined in the SAR. Safety related structures, systems, and components are listed as those necessary to assure the integrity of the reactor coolant boundary, the capability to shutdown the reactor and maintain it in a safe shutdown condition, or the capability.to.prevent or mitigate the consequences of accidents which could result in off-site exposures comparable to the guideline exposures of 10 CFR 100.
Procedure No: TQR2.0 Rev:15 Page2of5
igi ili
/Q~
Control over activities affecting the quality of safety related structures, systems, and components shall be to the extent consistent with their importance to safety. Such control shall include use of appropriate equipment, establishment of suitable environmental conditions, and assurance that all prerequisites for a given activity have been satisfied. The Program shall provide for controls over special processes and skills necessary to attain the required quality, and the need for verification of quality by inspection and test.
2.2.4 Participating Organizations The FPL organizations with responsibilities for activities affecting quality of nuclear safety related structures, systems, and components are identified in TQR 1.0, which also briefly describes their assigned responsibilities.
Florida Power & Light Company may delegate activities to contractor, organizations and equipment vendors. Delegated activities are subject to the external organization's FPL approved Quality Assurance Program or the FPL Quality Assurance Program, or some FPL approved combination thereof.
However, FPL shall retain overall responsibilities for the Quality Assurance Program.
Procurement documents shall define the scope of delegated activities, as well as Quality Assurance Program requirements that shall govern these activities.
The Quality Assurance Department shall review and approve the Quality Assurance Program governing contracted activities prior to award of contract except for activities for which the output is of a conceptual and/or prototype nature. In all cases, final approval shall occur at a point in the process to ensure that the output complies with the requirements of the FPL approved Quality Assurance Program. The object of this review shall be to verify that the program is in compliance with the applicable requirements of Appendix B, 10CFR50,.and ANSI N45.2. Audits shall be conducted periodically to verify the acceptable implementation of the contractor"s FPL approved Quality Assurance Program governing delegated activities. The Quality Assurance Department is responsible for conducting these audits. The initial review and periodic audits shall be performed by qualified Quality Assurance Department personnel, and as appropriate, by technical specialists from other FPL departments and contractor organizations.
2.2.5 Indoctrination and Training A program shall be established and maintained for quality assurance indoctrination, and for training which assures that the required level of personnel competence and skill is achieved and maintained in the performance of activities affecting quality. Instructions shall delineate the requirements for an indoctrination program,to assure that personnel responsible for performing activities affecting quality are instructed in the purpose, scope, and implementation of the manuals, instructions, and procedures and that compliance to these documents is a mandatory requirement.
Procedure No: TQR2.0 Rev:15 Page3of5
ill ill il~
Instructions shall also require the head of each department to be responsible for a training plan which assures that personnel performing activities affecting quality are trained in the principles and techniques of the activity being performed. This training shall maintain the proficiency of personnel in the skills necessary through retraining, requalification or reexamination, as appropriate. This training shall be conducted to reflect significant procedure changes, or plant modifications which significantly affect the operation of the department. When personnel are assigned to perform their functions under the direction of personnel from other. than their home department, the department head of the organization providing direction is responsible for the indoctrination and training of personnel who perform activities under their direction. Instructions shall specify the requirements for documenting indoctrination and training sessions, including a course description, attendance, location, and date. Records shall contain sufficient information to identify persons in attendance with the corresponding lesson plans.
2.2.6 Management Participation In addition to the involvement of department heads in implementing the Quality Assurance Program within their departments and the involvement of the Director Nuclear Assurance and the Supervisor Performance Assessment in the development, coordination, and review of the Program, the Company Nuclear Review Board (CNRB) shall be apprised of the status and adequacy of the Quality Assurance Program on a periodic basis. The following actions shall be instituted to assure that the CNRB remains informed and meets its Program responsibilities:
- a. The CNRB shall review a summary of the results of management level Quality Assurance audits of FPL Departments; The Quality Assurance Department shall periodically, but not less than quarterly, circulate reports of activities to members of the CNRB and affected department heads. The reports may include such items as the status of audits, a summary of audit findings, the status of development projects, and descriptions of policy matters or problems requiring management attention;
- c. The CNRB shall review the status of the Quality Assurance Program on a semiannual basis. The review will include assessment of the Program goals, objectives, and accomplishments; Periodic audits of the Quality Assurance Department and Program shall be conducted by an independent audit group under the direction of the Director Nuclear Assurance. This audit group shall employ FPL audit procedures and shall distribute the audit report to the Director Nuclear Assurance, and to the CNRB for review of findings and corrective action. Auditor certifications of independent audit teams will be retained by the Quality Assurance Department.
The programs of contractor organizations that perform activities affecting quality shall be reviewed by Quality Assurance to assure that their management regularly reviews the status and adequacy of that part of the FPL Quality Assurance Program which they are executing.
Procedure No: TQR2.0 Rev:15 Page4of5
il~
2.3.1 Each direct report of. the President, Nuclear Division and Department Heads of organizations supporting the,Nuclear,Division shall be responsible for:
- 1. Reviewing changes to the FPL QA Manual and determining the need for departmental'instructions, revising existing instructions, and approving instructions; E
- 2. Controlling'distribution and coordinating the use of the instructions with affected organizations and functions;
.3. Submitting Quality Assurance Indoctrination'(QAI) lesson, plans to the Director Nuclear Assurance for approval to conduct their own QAI.'.3.2 The Director Nuclear Assurance'has overall responsibility for:.
- 1. Development, coordination, and periodic reviews of the status and'adequacy of the FPL Quality Assurance Program;
- 2. Reviewing Regulatory Guides, codes, SAR document commitments and standards for impact on the Quality Assurance, program and recommending appropriate program changes;
- 3. Establishing; conducting, reviewing and authorizing the implementation of FPL's requirements for QAI;
- 4. Coordinating revisions to the Topical. Quality, Assurance Report.
Procedure No: TQR2.0 Rev:15 Page 5 of 5
TOPICAL QUALITYASSURANCE REPORT TQR 3.0 Rev:
DesIgn Control 13'ate:10/16196 3.1 GE E L E UIRE EN S A Quality Assurance Program shall be established for design-related activities. The design control program shall ensure that the design is defined, controlled and verified; that applicable design inputs are specified and correctly translated into design output documents; that design interfaces are identified and controlled; that design adequacy is verified by persons other than those who designed the item; and that design changes, including field changes, are governed by control measures commensurate with those applied to the original design.
Design records shall be developed to provide evidence that the design process and design verification were performed in accordance with the requirements of FPL's Quality Assurance Program.
Design records shall include design output documents and the important steps in the design effort. The intent of this documentation is to allow a technically qualified person to understand how the design was developed, and to allow that person to verify the design based on the design documentation and engineering data sources referenced therein.
Documents and databases designating safety related and quality related items and any revisions thereto shall be controlled in accordance with the FPL QA Program requirements.
The controlling document for the identification of safety related items shall be the FSAR. Where the FSAR is not definitive for a specified plant, Nuclear Engineering shall develop and maintain documents/databases identifying those items which are safety related (e.g., plant equipment database, drawings, etc). These documents/databases shall clearly identify the boundaries of safety related systems and may take the form of identifying boundaries on engineering drawings.
For quality related items, Nuclear Engineering shall specify explicitly those aspects of design, manufacture, procurement, installation; and testing that shall be subject to the FPL QA Program requirements, as appropriate, in the design output documents (e.g., Plant Change/Modification package).
The design organization's Quality Assurance Program for design control shall be approved by the FPL Quality Assurance Department prior to the release of approved design output by the design organization. The design organization is the organization responsible for approval of design output. Quality Instructions shall be developed to delineate design control requirements governing design-related activities performed by Nuclear Engineering and for delegating activities to contractor organizations.
Procedure No: TQR3.0 Rev:13 Page1 of 6
il~
ili Qi
~4 II
Design data approved by the design organization shall be transmitted in design output documents such as specifications, drawings, and other documents defining technical requirements or in correspondence which may reference these documents. Transmittals shall identify the status of design information or documents provided, and where necessary, identify incomplete items which require further evaluation, review, or approval.
A standard PC/M and numbering system shall be established and used at each plant to ensure that all PC/Ms are handled in a uniform manner and properly documented. Nuclear Engineering shall forward the approved PC/M to the applicable Plant Vice President. Internal plant coordination and review of design control. documents shall be controlled by approved instructions.
3.2.1 Design Process The design organization shall specify.and document its design activities to the level of detail necessary to permit the design to,be developed in a correct manner and to permit verification that design output documents satisfy design input requirements. Design methods, materials, parts, equipment and processes, including those associated with commercial grade items that are essential to the function of the item shall be selected, reviewed and approved for suitability of application by the design organization.
Design inputs shall be identified, documented, reviewed and approved by the design organization. They shall be specified to the level of detail necessary to permit the design activity to be carried out in a correct manner, and to provide a consistent basis for making design-related decisions, performing design verification and evaluating design changes. Changes to approved design inputs, including the reason for the changes, shall be approved, documented and controlled by the design organization.
The design organization shall identify-aspects of manufacture, construction, inspection and testing critical to achieving the function of the item. Quality standards and quality requirements shall be specified on design output documents. Changes from approved quality- requirements specified in design output, including the reason for the changes, shall be approved, documented and controlled by the design organization.
Design analyses shall be controlled and documented. Approved design output documents and approved changes thereto shall be relatable to the design input by documentation in sufficient detail to permit verification. The design organization shall establish procedures to review industry design experience. As appropriate, this experience shall be made available to cognizant design personnel.
3.2.2 Design Change Control Changes to approved design output documents, including field changes, shall be justified, subjected to control measures commensurate with those applied to the original design, and shall be reviewed and approved by the same design organization that approved the original design. unless other organizations are specifically designated.
Where a significant design change is necessary because of an incorrect design, Nuclear Engineering shall determine the cause of the incorrect design. As necessary, design and verification procedures shall be reviewed and modified to correct the cause of the incorrect design.
Procedure No: TQR3.0 Rev:13 Page2of6
Design changes shall be reviewed to ensure that implementation of the design change is coordinated with any necessary changes to operating procedures and practices, and required Nuclear Assurance activities, such as inspections and surveillances.
3.2.3 Design Interface Control Quality Instructions shall establish interface controls between participating organizations and between the various technical disciplines within the design organization. These Quality Instructions shall include the assignment of responsibility, and be in sufficient detail to cover the preparation, review, approval, release, distribution and revision of design output documents.
For interdisciplinary design, approval documentation of each involved discipline of the design organization shall appear on the design output document or on a separate document directly traceable to the design output. The design organization shall designate a discipline(s) responsible for resolution of the comments of participating organizations. The designated discipline(s) approval of a design output shall also document resolution of the comments of participating organizations.
3.2.4 ,Design Verification Design control measures shall be established to independently verify the design inputs, design process, and that design inputs are correctly incorporated into design output. The design organization shall develop instructions that govern design verification. These instructions shall require that the design organization identify and document the verification method utilized and that the documentation clearly identify those individuals performing the design verification.
Design verification shall be performed by technically qualified individual(s) or group(s) other than those who performed the design. The original designers and verifiers may both be from the design organization. Design verification by the designer's immediate supervisor shall be limited to those instances where the supervisor is the only qualified individual available within the design organization. These instances are further restricted to designs where the supervisor did not specify a singular design approach, or did not restrict design methods or alternatives,,or did not specify design inputs (unless the specified design inputs have already been independently verified). Justification for verification by the designer's immediate supervisor should be documented along with the extent of the supervisor's involvement in the design.
The design organization shall be responsible for determining the extent of design verification and methods to be employed. The methods may include, one or more of the following: the performance of design reviews, the use of alternate calculations, or the performance of qualification tests. This shall apply to original design and to changes to approved design output.
Where reverification is not required for a design change, the bases shall be documented by the design organization. Cursory supervisory reviews and mathematical checks for calculation accuracy do not satisfy the independent design verification requirement.
Design verification shall normally be completed prior to release of design output for procurement, manufacture or release by the design organization for use in design activities by a participating organization. Verification shall be conducted based on the Procedure No: TQR 3.0 Rev: 13 Page 3 of 6
-status of design at the time of release of design documents. Where this timing cannot be met, verification may be deferred provided that the unverified portion of the design output, and all design output documents, structures, systems and components based on the unverified portion of design are identified and controlled. In all cases verification shall be completed prior to relying on any affected items to perform their design functions.
3.2.5 Computer Programs/Software Organizations developing software or utilizing purchased or FPL developed computer programs/software in the performance of activities affecting quality as defined in the TQAR, shall maintain instructions or procedures to effect the following:
That such programs/software within the scope of the quality assurance program are identified and included in a computer software index. The controlled distribution of this index, electronic or hard copy, shall include the Director Information Technology (IT) Operations. The method for determining which programs/software fall within the scope of the QA program shall be described in these procedures or instructions; That such programs/software are verified for their particular use using benchmark problems, alternate calculations, comparison with other code or experimental results, requirements and/or design reviews or similar methods; C. That such programs/software have been qualified for their specific application sufficient to ensure valid results; That such programs/software are provided with user instructions sufficient for a technically competent individual to follow; That configuration controls are provided to assure that such programs/software changes or modifications are documented and controlled; That errors in such programs/software are identified, evaluated, provided with a disposition and corrected.
3.3 RESPONSIB LI IES 3.3.1 The Vice President Nuclear Engineering is responsible for:
Determining and documenting which items are nuclear safety related or quality related;
- b. The review and coordination of design interfaces; C. Assuring that design documents are reviewed for possible design interfaces, that
.interface problems are resolved and that design criteria and design interface changes are reviewed by participating organizations prior to approval of design documents; Preparing design documents, including performing the safety evaluation or screening to determine if the proposed design change involves an Unreviewed Safety Question or a change to the Technical Specifications; Procedure No: TQR3.0 Rev:13 Page 4 of 6'
~gi tl~
ig~
- e. Performing design verification, including evaluation of the effects of proposed design changes on overall design adequacy (design integration);
- f. Providing Nuclear Engineering approval of design documents;
- g. Updating design documents and drawings according to applicable procedures;
- h. Coordinating the NRC interface for 10 CFR 50.59 reports.
3.3.2 The Plant Vice President is responsible for:
- a. Reviewing, tracking the status of,,and maintaining a file on proposed PC/Ms;
- b. Reviewing proposed PC/Ms for inclusion of appropriate quality criteria, standards, and hold points, including human factors considerations for design changes'involving the Control Room or Remote Shutdown Panel; reviewing completed PC/Ms, after implementation for compliance with governing procedures, including a review of all endorsements, sign-offs, completion of required acceptance testingfinspection, and any necessary changes to operating practices and procedures;
- d. maintaining, design documents as. Quality Assurance records;
- e. assuring that all plant design changes and drawing changes are coordinated through Nuclear. Engineering; determining whether or not a proposed design change affects nuclear, safety; approving. or disapproving implementation of the proposed design change after receipt of a recommendation'from the Plant Nuclear Safety Committee (PNSC) or Facility Review Group (FRG);
ensuring Environmental Services is included in the proposed PC/M review if the design change may.have an adverse impact on the environment; reviewing design changes to ensure that the implementation of the design change is coordinated with any necessary changes to:operating practices and procedures.
3;3;3 The Plant Nuclear Safety Committee (PNSC) or. Facility Review Group (FRG) is responsible for:
Reviewing all proposed PC/Ms for plant systems or equipment related to nuclear safety; Rendering a determination in writing (PNSC/FRG meeting minutes) as to whether or not the proposed design change constitutes an Unreviewed Safety Question.
Procedure No: TQR3.0 Rev:13 Page 5 of 6
~li il~
ili
3.3.4 The Director Nuclear Assurance is responsible for.
- a. reviewing PC/Ms and other'FPL originated design specifications for inclusion of appropriate quality criteria, standards, hold points, and Nuclear, Assurance activities.
3.3.5 The Company Nuclear. Review Board (CNRB) is responsible for:
- a. Reviewing Safety Evaluations for, design changes to verify that the design changes did not constitute an Unreviewed'Safety Question. CNRB review of evaluations involving screening rather than Safety Evaluation is not mandatory;
- b. Reviewing proposed design changes which involve an Unreviewed Safety Question or a change in Technical Specifications or L'icense.
3.3.6 Each direct report to the President, Nuclear Division and Department Heads of organizations supporting the Nuclear Division shall be responsible for:
- a. identification of. computer programs/software used to accomplish activities affecting quality;
- b. establishment of departmental instructions which prescribe the methods and.
techniques used to meet the QA program requirements for control of computer programs/software.
3.3.7 Director Information Technology (IT) Operations is responsible for evaluating all hardware or operating system software changes or problems occumng on computer systems under IT Operations control to determine if the answers produced or the integrity of data maintained in databases may be affected. If IT Operations determines applications may be affected, then IT Operations is responsible for notifying user departments.
Procedure No: TQR3.0 Rev:13'age6of6
TOPICAL QUALiTYASSURANCE REPORT TQR 4.0
'ev:9
. Procurement Document Control Date:1011 6/96 4.1 GE ERAL E Ul EMENTS Procurement of items and,selvices shall, be performed in accordance with procedures and instructions which assure that applicable regulatory requirements, design bases, code requirements, and other. requirements necessary to assure quality shall be included or invoked by reference in the procurement document. These procedures and instructions shall delineate the sequence of, actions to be accomplished in the preparation, review, approval, and control of procurement documents. Changes to procurement documents shall be-subjected to the same degree of control as utilized in the preparation of the original documents.
4.2 IMPLEMEN ATIO 4.2.1 Procurement Document Provisions Quality Instructions shall identify the responsibilities and actions required of the organizations originating, reviewing, approving, and controlling procurement documents.
These .instructions shall require the procurement documents to specify:
- a. The scope of work to be performed;
'b. Technical requirements (by specifying or referencing),which shall include the applicable components and materials identification requirements; drawings, specifications, procedures, instructions, codes, and regulations and provide for identification of applicable test, inspection and acceptance requirements, or special process instructions; I
- c. Quality Assurance Program requirements to be imposed on contractors which shall include the applicable portions of 10 CFR 50, Appendix B;
- d. Right of access which provides, as appropriate,.for access to contractor facilities and records, for inspection or audit by:FPL or its designated representative, and to access for events such as witness and hold points;,
The documentation required to be prepared,,maintained, and/or submitted.to FPL or its representative for review, approval, or historical record. The time of submittal of this documentation and the retention and disposition of Quality Assurance Records which will not be delivered to FPL shall be prescribed.
Consideration shall be given to the need for special requirements in the preparation and review of procurement documents. Procedures and instructions shall be prepared and implemented for special on-site handling or storage requirements. The receiving department shall ensure on-site'implementation of the special handling, shipping, and.
storage requirements for items received and controlled by their organization.
Procedure No: TQR4.0 Rev:9 Page 1 of 3
lt iSi
~I~
i51
Special handling, preservation, storage, cleaning, packaging, and shipping requirements shall be specified, as appropriate, in the design documents or purchase orders. The requirements established in the design documents or purchase orders shall be consistent with industry accepted standards, the importance of equipment or material to nuclear safety, and the material or equipment's sensitivity to damage. The preparation of these design documents or purchase orders may be delegated by FPL to other organizations.
4.2.2 Procurement Document Review Procurement documents shall be reviewed for correctness, and inspectability and controllability of quality requirements in accordance with Quality Instructions to assure that the appropriate provisions of Section 4.2.1 are included. This review shall be documented and performed by designated personnel who have been trained and qualified in quality assurance practices and concepts. These reviewers shall have access to pertinent information and have an adequate understanding of the quality and technical requirements and intent of the procurement documents.
Spare or replacement parts for safety related structures, systems, and components are subject to technical or quality requirements equivalent to, or better than, those used for the original equipment.
Changes to procurement documents, whether initiated by FPL or their representative, are subjected to the same degree of control as that utilized in the preparation of the original document.
4.2.3 Selection of Procurement Sources It shall be verified that the procurement document has been reviewed and approved, and that the supplier has been approved prior to issuing the purchase order for safety related materials or services. Verbal purchase orders shall be made in accordance with TQAR Appendix C exceptions to ANSI N45.2.13. Supplier approval is not necessary if the important characteristics of the item can be verified by inspection or test.
The overall procurement requirements, including those related to planning, bid evaluation, and review and concurrence of suppliers Quality Assurance programs,.are described in Quality Instructions.
4.3 RESPONS 8 LITIES 4.3.1 Direct reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division originating a procurement requisition shall be responsible for:
Clearly describing the technical and quality considerations for the procurement of items or services;
- b. Specifying any special requirements; C. Specifying documentation required from the supplier;
- d. Specifying special handling, preservation, storage, cleaning, packaging, and shipping requirements, as appropriate.
Procedure No: TQR4.0 Rev:9 Page 2 of 3
ilt il~
il~
4.3.2 The Vice President Nuclear Engineering is responsible for.
Performing technical evaluations to.verify and/or establish technical and quality requirements for permanent and temporary power plant items and services;
- b. Reviewing technical and quality requirements contained in procurement documents and changes thereto to assure that ordering requirements are technically correct and complete for items and services as specified in 4.2.1; Evaluating the interchangeability of items that are not identical to what is currently installed.
4.3.3 The Director Nuclear Assurance is responsible for:
Assisting in the resolution of quality requirements;
- b. Approving suppliers for safety related procurement and commercial grade item procurement (when applicable); .
Identifying surveillance witness and/or hold points at the supplier's facility for safety related procurement when supplier QA program is relied upon and programmatic deficiencies dictate; Performing supplier surveillance.
4.3.4 The Plant Vice President or, for nuclear fuel procurement only, the Vice President Nuclear Engineering is responsible for.
Incorporating requisition technical and quality requirements into the procurement documents; Notifying Nuclear Assurance of discrepancies and/or changes in supplier activities which may conflict with the work scope of Nuclear Assurance approved suppliers; C. Reviewing each procurement document to ensure that it is correct, in accordance with Nuclear Assurance approved supplier work scope and restrictions (when applicable) and the originating procurement requisition; Referencing and attaching appropriate Quality Assurance Program requirements, as referenced on respective procurement requisitions, requests for bid proposals, purchase orders and contracts; D
Verifying that the procurement document has been reviewed and approved and issuing procurement documents to suppliers, as approved by FPL Nuclear Assurance when supplier QA programs are required; Maintaining traceability of procurement documents until stored in an approved storage'facility as a record.
Procedure No: TQR4.0 Rev:9 Page3of3
<S~
ilt ili
TOPICAL QUALITY,,ASSURANCE REPORT TQR 5.0 Rev: 12 Instruction, Procedure & Drawings Date:02/2N97 5.1 GENE AL RE UIREMENTS Activities affecting quality of. nuclear safety-related structures, systems, and components shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or
.drawings; These documents shall include appropriate quantitative criteria such as dimensions, tolerances, and operating limits, and qualitative criteria such as comparative workmanship samples,,to assure'that the quality assurance activity has been satisfactorily accomplished.
5.2 PLE E 0 5.2;1 Quality Assurance Program Documents
'he FPL Quality Assurance Manual described in TQR 2.0 contains the Topical Quality Assurance Report which complies with the criteria of 10 CFR 50, Appendix B. Quality Instructions provide direction for activities affecting quality. The Quality Assurance Department reviews and comments on Quality Instructions written by other departments.
Comments concerning compliance with corporate Quality Assurance commitments and regulatory requirements are resolved prior. to issuance. The Quality Assurance Department,receives'controlled copies of Quality Instructions issued by other departments.
5:2.2 Procedures and Instructions Instructions and procedures for activities affecting quality shall be prepared, reviewed, and approved in accordance with written Quality Instructions.
For plant operations, on-site plant procedures shall be prepared, reviewed, and approved in accordance with written instructions which includes a review'for concurrence by Quality Assurance or Quality. Control personnel and provisions for temporary changes and temporary procedures. These plant procedures include operating procedures, off-normal and emergency procedures, test procedures, and calibration procedures. Also included are maintenance and repair procedures for subcontracted maintenance and repair activities which are outside the normal scope of plant craft capability. Temporary procedures may be issued during testing, refueling, maintenance, modifications, unusual situations not within the scope of normal procedures, and for short periods when the plant, system or component is performing in a manner not covered by existing detailed procedures or has been modified in such a manner that portions of existing procedures do not apply.
Procedure No: TQR5.O Rev:12 Page1 of 2
ill ili
Contractors shall be required to have Quality Assurance Programs which contain written instructions for preparation, review, and approval of procedures, instructions, and drawings affecting quality. In addition, Contractor's site:procedures and Quality Control inspection procedures shall be approved by the Plant General Manager, or designee, following reviews by Quality Assurance or Quality Control personnel to assure compliance with Corporate commitment and regulatory requirements.
During the design, modification, and procurement phases, the Architect/Engineer or other contractors may be delegated responsibility for maintaining, issuing and verifying the implementation of appropriate program documents. In this case, Quality Assurance or Quality Control audit or surveillance activities shall assure that such measures are established and implemented. Contractor programs shall clearly delineate the actions to be accomplished in the preparation, review and control of instructions, procedures and drawings, and the methods for complying with the appropriate criteria of 10 CFR 50, Appendix B.
5.2.3 Drawings The design organization is responsible for review and approval of drawings. For delegated design activities, the Nuclear Engineering Department may approve changes to drawings. The technical control of drawings, i.e., review and approval of the drawing and all changes thereto shall be governed by procedures. A means shall be developed and updated as required to identify approved drawings and revisions thereto. A Master Drawing List is the normal means used for this.
5.2.4 Acceptance Criteria Quality Instructions shall require that instructions, procedures, and drawings affecting quality include adequate quantitative and qualitative acceptance criteria, as appropriate, for determining satisfactory work performance and quality compliance. These acceptance criteria requirements apply to important activities such as design, operations, test control, inspection, and plant modifications.
5.3 ES 0 SIBILI IES 5.3.1 Each direct report to the President Nuclear Division and Department Heads of organizations supporting the Nuclear Division is responsible for:
a.. Establishment of a documented system for"the preparation, review, approval and revision of procedures. This system shall comply with regulatory requirements, the applicable Plant Technical Specifications and Topical Quality Requirements.
5.3.2 The Director Nuclear Assurance is responsible for:
Review and concurrence of procedures affecting quality in accordance with Paragraph 5.2.
Procedure No: TQR5.0 Rev:12 Page2of2
il~
ili O~
TOPICAL QUALITYASSURANCE REPORT TQR 6.0 Rev: 11 Document Control Date:02/2N97 i6.1 GENERAL RE UIREMENTS The distribution of documents such as instructions, procedures, drawings, and software which provide guidance, specifications, or requirements affecting, the quality of nuclear safety related structures, systems, and components shall be controlled; These documents shall be prepared, reviewed for adequacy,.and approved for release by. authorized personnel in the affected organization. These documents shall be distributed to locations where the activity is performed.
Changes to controlled documents shall be so identified and shall be reviewed and approved by the same"organization,that performed, the original review and approval unless otherwise specified in the implementing procedures;:In addition, procedures shall preclude the possibility of use of outdated documents.
62 I PLE E T IO 6.2.1 Quality Instructions shall delineate the control measures that provide for:
6.2.1;1 Identification of individuals or organizations responsible for. preparing, reviewing, approving, and issuing documents and revisions thereto; 6.2.1.2 Identifying the proper documents to be used in performing the activity; 6.2.1.3 Coordination and control of interface documents; 6:2.1.4 Ascertaining that proper documents are being, used; 6.2.1.5 Establishing current and updated distribution lists.
These control measures shall apply to documents affecting the quality. of nuclear safety related structures, systems, and components such as:
- a. design specifications;
- b. design, manufacturing, construction, and installation drawings; C. qualityprogram manuals, procedures, and instructions;
- d. inspection, manufacturing, and test procedures and instructions;
- e. plant operating and maintenance procedures;
- f. plant Safety Analysis Reports and related design criteria documents.
Procedure No: TQR 6.0 Rev:.11 Page,1 of 3
ili
'i ili 4)
P 1
The requirements for control of procurement documents are contained in TQR 4.0, Procurement Document Control.
6.2.2 Drawing Control FPL assumes control of the drawings and Master Drawing List after initial operation of the facility or delegates this activity to a qualified contractor. Nuclear Engineering shall require that participating design organizations update the drawings and Master Drawing List to reflect the as-built conditions of the facility prior to FPL's acceptance of these documents.
Maintenance, distribution and control of the drawings and the Master Drawing List by FPL during the operation phase shall be assigned to a drawing custodian. Revision to drawings shall be approved prior to release by the drawing custodian. Approval shall be by Nuclear Engineering, or a designated design organization.
During the operation phase, a system shall be established to provide ready access and availability of drawings to engineering and operations personnel; to identify drawings affected by approved plant design changes; and to update drawings and the Master Drawing List to reflect implemented design changes.
6.2.3 Design Documents Other Than Drawings Ascertaining that proper design documents are accessible and are being used shall be accomplished by periodic issuance of master document lists showing the latest applicable revision, or by a document receipting system.
6.3 RESPONSIBILITIES 6.3.1 Direct reports to the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division shall be responsible for.
- a. the development, maintenance and control of those documents identified in Section 6.2 issued by them as controlled documents;
- b. the adequacy of their instructions, including the instructions for control of the documents and changes thereto to preclude the possibility of use of outdated or inappropriate documents.
6.3.2 Each recipient of a controlled document is responsible for ensuring that the appropriate latest revision is being used.
6.3.3 The Vice President, Nuclear Engineering, is responsible for assuring that the Architect-Engineer, Nuclear Steam Supply System vendor, and other contractors, as a minimum:
provide for the development, control and distribution of drawings, specifications and procedures; and the development and periodic distribution of a master drawing list for each'project; Procedure No: TQR6.0 Rev:11 Page2of3
ill ili
provide that all revisions required as a result of FPL comments, nonconformances, or engineering work are incorporated into revised documents.
6.3.4 The Site Vice President is responsible for, establishing a document distribution and control system.to assure that the latest appropriate revisions of documents are used for construction and installation at each project site.
Procedure No: TQR6.0 Rev:11 Page3of3
il~
ig~
ili
TOPICAL QUALITYASSURANCE REPORT TQR 7.0 Rev: 9 Control of Purchased Items & Services Date:02I2N97 7.1 GE E L E Ul E E Measures shall be, established to assure that items or services purchased by, or for FPL conform to the requirements of the procurement document. These measures shall include documented evidence of source selection, verification activities and examination of items or services to assure compliance with the procurement document. The effectiveness of the control of quality by contractors and subcontractors shall be assessed at intervals consistent with the importance, complexity, and quality of the product or service.
7.2 PLE EN 0 7.2.1 Evaluation of Suppliers Procurement source evaluation and selection measures shall be specified in Quality Instructions which shall identify the responsibility of qualified individuals for determining supplier capability. The evaluation may require integrated action involving Quality, Assurance and one or more organizations based upon the item or service being procured. This evaluation is to ensure that the FPL contractors comply with the applicable portions of 10 CFR 50, Appendix B. Documented evidence of the evaluation, and the acceptance of the contractor's quality program and procedures shall be retained in the Quality Assurance Department files. The determination of supplier approval shall be based on such factors as prior performance, historical quality performance data, source surveys or audits, and evaluation of the supplier's Quality Assurance Program.
The basis shall be consistent with the importance, complexity, and quality required for the items or services involved.
7.2.2 Verification Activities Quality Instructions shall define the requirements for verification activities such as surveillance, inspection, or audit to assure conformance of procured items and services to identified requirements. These verification activities shall be performed in accordance.
with written procedures, procurement documents and their references, which specify the documentation required and the characteristic or process to be witnessed, inspected, verified, or accepted. FPL verification activities shall be accomplished by qualified personnel to verify.that the supplier complies with quality requirements, and depending on the importance/complexity, shall be performed on those items where verification of procurement requirements cannot be determined upon receipt.
Procedure No:, TQR 7.0 Rev: 9 Page 1 of 3
~l~
]gal il~
7.2.3 Receiving Inspection C
Quality Instructions shall delineate requirements and responsibilities for the performance of receiving inspection. This inspection shall verify that suppliers have fulfilled their contractual obligation and that the procured items meet the appropriate quality requirements. Receipt inspections shall be planned. The receipt inspection plans shall identify the characteristics to be verified and the documentation to.be reviewed at receipt inspection. Receiving inspection shall include, as appropriate:
Measures for verifying that the shipment is complete, properly identified, undamaged, and corresponds with the purchase order documentation;
- b. Measures for inspection of the item and review of supporting documentation (e.g., mill test reports, NDE reports) as required by the purchase documents;
- c. Measures for disposition of items to inspection instructions;
- d. Measures for identifying and controlling, items including identification of inspection status prior to release from the receiving inspection area; Measures to ascertain that inspection records or Certificates of Conformance are available prior to release; Measures verifying completion of Commercial Grade Item dedication requirements.
7.2.4 Supplier Furnished Records Records required to be furnished by the supplier shall be specified in the procurement document. Certifications or documentation verifying conformance provided by the supplier shall identify the specific procurement requirements met (either by reference to the purchase order. or by referenced requirements therein). Such certification shall identify any procurement requirements which have not been met and provide a description of those nonconformances dispositioned "accept as is" or "repair".
7.3 RESPONSIB L IES 7.3.1 Direct reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division are responsible for:
- a. Determining the methods of acceptance for services requested by them;
- b. The performance of the acceptance methods selected, when assigned to them.
7.3.2 The Vice President Nuclear Engineering is responsible for:
- a. Requesting that Nuclear Assurance perform a supplier evaluation;
- b. Determining the methods of acceptance for items and services.
Procedure No: TQR7.0 Rev:9 Page2of3
il~
4~
ggi
.7.3.3 The. Director Nuclear Assurance is responsible for.
- a. Assuring that evaluations, of suppliers are'performed and the results documented in accordance with approved Quality Instructions;
- b. Determining the;methods of source verification;
- c. Performing receipt inspections in accordance with approved. Quality Instructions; 7.3.4 The Site Vice President is responsible. for:
- a. Requesting that Nuclear Assurance perform a supplier evaluation;
- b. Examining items for shipping damage upon receipt;
- c. Performing receipt'inspection in accordance with approved Quality Instructions.
Procedure No: TQR7.0 Rev: 9 Page3of3
ili TOPICAL QUALITYASSURANCE REPORT TQR 8.0 Rev: 4 Identification of Control of Material, Parts, & Components Date:02I28/97 8.1 GENERAL RE UIREMENTS Materials, parts, and components, including partially fabricated assemblies, shall be identified and controlled as required throughout fabrication, receipt, handling, storage, installation, and use of the item. The identification of the item shall be maintained by heat number, part number, serial number, assigned traceability numberor other suitable means, and shall be physically marked on the item or on records traceable to the item. The object of these controls shall be to prevent the use of non-inspected, incorrect or defective materials, parts, and components.
8.2 IMPLE E 0 Quality Instructions shall establish the, responsibilities and requirements for the identification, and control of materials, parts and components. The procedures and instructions used by all organizations shall assure that identification and control is maintained throughout fabrication, receipt, handling, storage, installation and use of items. This shall include welding material traceability to the point of consumption. Provisions include:
- a. Physical identification shall be used to the maximum extent possible. When physical identification is impractical or insufficient, items shall'be physically segregated and identified by batch, lots, etc.;
- b. When items are subdivided, their identification shall be maintained by transferring the identification to each of the subdivided parts or their container, Post-installation identification of items that cannot feasibly be physically marked shall be traceable by record verification; Items requiring identification, but whose identification was lost during storage, shall be segregated and documented as nonconforming and dispositioned in accordance with established procedures; Requirements for traceability to appropriate documentation, sUch as: procurement documents, manufacturing documents, drawings, specifications, inspection and test records, nonconformance or deficiency reports or other. Quality Assurance Records, in sufficient detail to preclude any possibility of doubt or confusion concerning the traceability'of an item to the documentation, or the documentation to the item; Procedure No: TQR8.0 Rev:4 Page1 of 2
tli ISA
Controls to assure that the correct identification of an item is verified and documented prior to fabrication, receipt, handling, storage, installation and use; Requirements which assure that the method or location of markings are not detrimental to, and do not affect the function'or.quality of an item; are clear, unambiguous and indelible; are in plain unobstructed view; do not provide conflicts with other requirements; are not obliterated by any surface treatment unless other means of identification are substituted; withstand normal shipping, handling and environmental effects and are able to be retained;
- h. Establishment of identification requirements by specifications, drawings, procurement documents, instructions or procedures during initial planning; Requirements to ensure that dedicated Commercial Grade Items are identifiable to the specific component or equipment for which they are dedicated.
FPL may delegate any portion of the implementation of the identification and control program to the Architect/Engineer, Constructor, Nuclear Steam Supply System vendor or other contractors.
If delegated, contracts shall require that the contractor establish an identification and control program which meets the requirements of this TQR.
8.3 RES PO SI8ILITIES 8.3.1 The Site Vice President has overall responsibility for:
- a. Assuring that an identification and control system is developed and implemented for items to be utilized within the plant; Receiving, controlling and ensuring, the security of items; Segregating items until the required receipt inspection is performed;
- d. Assuring the placement of any necessary markings on the items as required by applicable procedures or as requested in accordance with applicable purchase orders, specifications or commercial grade dedication packages; and Incorporating applicable pre-installation and/or post-installation inspections, tests, and QC hold points (including Commercial Grade Item Dedication requirements) into applicable work control documents.
8.3.2 The Vice President Nuclear Engineering has overall responsibility. for:
Determining and specifying end use applications for items.
Procedure No: TQR8.0 Rev:4 Page2of2
l~
Ol 4t Oi
TOPICAL QUALITYASSURANCE REPORT TQR 9.0 Rev:,13 Control of Special processes Date:02/2I97 9.1 GENE L RE U E EN Measures shall be established to assure that special processes such'as welding, heat treating, and nondestructive examination items, are controlled and accomplished by qualified personnel using qualified procedures and equipment in accordance with applicable codes, standards, specifications, criteria, and other special requirements.
9.2 PLE E TO Special process requirements shall be included in design outputs and changes thereto. Special process procedures shall be developed, reviewed, approved and controlled, and special process personnel and equipment shall be qualified.
9;2.1 ifi i f i IPr c Special processes are those processes which must be qualified and controlled where quality is highly dependent on close control of process variables or operator skills, and objective verification (inspection, examination or testing) of end quality is difficult.
Special processes identified by applicable codes and standards shall be controlled, qualified, and implemented in accordance with those codes and standards. Examples of special processes include (but are not limited to) welding, heat treating, and nondestructive examination. Others, (e.g., flushing, protective coating, plating applications and nuclear cleaning) should be reviewed to determine if they are special processes.
9.2.2 Pr d r lifi i n ndC nr I Process control procedures'written by FPL organizations or, their contractors shall be used and qualified as required by applicable specifications, codes, or standards.
Where FPL assigns work to outside contractors, the contractors shall make their procedures and personnel. qualifications available for review to FPL prior to the start of work. The Architect/Engineer, Nuclear Steam Supply, System vendor, or other organization designated by FPL shall be responsible for the evaluation and acceptance of
.on-site contractor special'process procedures, and shall interface with the appropriate FPL department, as necessary, to.resolve. review comments with the contractor. The contractor shall also be responsible for the control and approval of sub-contractor procedures.
Procedure No: TQR9.0 Rev:13 Page 1 of 4
ili Qi s
Special process procedures shall be:
- a. Sufficiently detailed for a qualified person to perform the. technique and achieve the desired results;
- b. Reviewed and approved prior to use to ensure the procedure complies with applicable codes, standards, and specifications, and that specified materials, equipment, and techniques are suitable for the intended application;
- c. Qualified prior to, or during initial use.
Special process procedures and revisions thereto which specify acceptance criteria (other than those identified in the ASME code) shall have the, concurrence of the acceptance criteria by Nuclear Engineering prior to issuance and use.
9.2.3 Procedures or instructions shall specify personnel qualification and certification requirements. Personnel responsible for the performance and verification of special processes shall be trained, tested, and certified as required by applicable specifications, codes and standards. Requirements for the period of certification, retesting, and recertification of personnel shall also be specified. Contractors shall qualify personnel and maintain records of qualified personnel in accordance with applicable codes, standards, specifications, and coritract or procurement document requirements.
9.2.4 rl f i n Equipment that must be of a specific type, range, or accuracy to provide conformance to specified requirements shall be controlled to ensure that it is qualified, maintained, and calibrated in accordance with those requirements.
9.2.5 S i I Pr c rd C
Records shall provide objective evidence that special processes were performed in compliance with approved procedures by qualified personnel and equipment.
Results of nondestructive examinations shall be documented and shall be evaluated for acceptance in accordance with applicable specifications, codes and standards by an individual who is certified in the applicable method.
Records shall also be maintained for verification activities when required by procedure, code or specification. For contracted work, these records shall be retained by the vendor or supplied to FPL as required by contract or- purchase order. If records are to be retained by the vendor, the contract or purchase order shall specify the retention period and instructions for final disposition of such records.
Procedure No: TQR9.0 Rev:13 Page 2 of 4
9.3 E PONSIBIL T E 9.3.1 Direct reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division involved in special process activities are responsible for:
Ensuring that special process procedures used by their department are reviewed, approved, controlled, and are qualified prior to or during initial use;
- b. Ensuring that special process personnel in their department are qualified and certified;
- c. Ensuring that records associated with special processes under their control are reviewed and maintained;
- d. Performing special process inspections, examinations, and activities, when assigned to their department, as required by applicable codes, standards, criteria, or other special requirements identified;
- e. Ensuring that work documents under their control contain adequate requirements for the identification and control of special processes; Ensuring special process procedures and revisions which specify acceptance criteria (other than identified in the ASME code) have Nuclear Engineering concurrence of acceptance criteria prior to use;
- g. Ensuring nondestructive examination documents are reviewed for accuracy and adequacy;
- h. Ensuring that welding activities requiring a qualified program are implemented in accordance with the welding program developed by Nuclear Engineering.
9.3.2 The Vice President Nuclear Engineering is responsible for:
- a. Determining (as'requested) if a specific activity constitutes a special process;
- b. Identifying applicable codes, standards, specifications, criteria, and other requirements related.to special processes;
- c. Preparation, qualification, issuance, and control of Visual Test (VT) and Nondestructive Examination (NDE) procedures, instructions, and technique sheets for all ASME Section XI examination activities; Direction, including technical direction to all personnel, of the welding program to meet the requirements of applicable codes and standards. This shall include the development, maintenance, and control of a welding program; Review and approval of contractor welding programs.
Procedure No: TQR9.0 Rev:13 Page3of4
P,A, Oi
-9.3.3 The Site Vice President'is responsible for:
Welding activities performed at the site including issuance and control of weld documentation packages,:welding material and equipment; b; Maintaining a current report of qualified welders and weld operators and assigning welder symbols; Ensuring that the Authorized Nuclear Inspector/Authorized Nuclear Inservice Inspector (ANI/ANII)is permitted access to all parts of the plant site or supplier facilities while work on an item or system is being performed that concerns the welding fabrication, modification, repair, or replacement of the item, or system; including inspections, examinations, and tests.
Procedure No: TQR9.0 Rev:13 Page 4 of 4
p igi
~ ~
TOPICAL QUALITYASSURANCE REPORT TQR 10.0 Rev: 12 Inspection Date:06N3l96 10.1 GE E L E U E E TS A program for inspection shall be established and executed by or for FPL to verify conformance with the documented instructions, procedures and drawings for accomplishing an activity.
Inspections shall be performed by individuals or groups other than those who performed the activity being inspected. Examinations, measurements and tests of materials or products processed shall be performed for each work operation, where necessary, to assure conformance to established requirements. If direct inspection of processed materials or products is impossible or disadvantageous, indirect control by surveillance or monitoring shall be provided. Mandatory inspection, witness, or hold points beyond which work shall not proceed without the consent of FPL or a designated representative shall be indicated in the appropriate documents.
10.2 LE E TATION 10.2.1 Inspection Program For plant operations, maintenance, or modification activities, a program for on-site inspection of activities affecting quality shall be established. This program shall ensure the performance of inspections, surveillance and monitoring of plant activities including operations, maintenance or modifications as required by established plans, schedules and/or procedurally. required inspection, witness or hold points. In all cases, the personnel performing the inspection shall be independent of the group performing the work.
For preoperational start-up and testing of plant modifications, Nuclear Division personnel may report functionally to the manager responsible for the start-up and testing and establish plans, schedules and procedurally required inspection, witness or hold points.
In all cases, the personnel performing the inspection shall be independent of the group performing the work.
Protection 8 Control Systems personnel may perform inspections of equipment within their purview during operations. Inspections shall be performed in accordance with approved, written procedures by qualified personnel.
Quality Instructions shall be written which delineate the requirements and responsibilities for the performance of inspections.
Procedure No: TQR 10.0 Rev: 12 Page 1 of 4
S y~
Ot ill ig~
10.2.2 Inspection Plans and Schedules Documented inspection plans may be either a separate document or an integral part of work instruction documents. The plans shall be based on design specifications, procurement documents, drawings, other specifications. or previous experience, as appropriate. The frequency and timing of inspections shall be scheduled according to the activities being conducted and to assure that. sufficient time and resources are available, and inspections are not inadvertently omitted or bypassed.
Inspection planning should include a review for the acceptability of sampling. If sampling is permitted, the sampling procedure shall be based on nationally recognized standard practices.
10.2.3 Inspection Personnel Inspections shall be performed by individuals other than those who performed or directly
- supervised the activity being inspected. Inspection personnel shall have current qualifications and certifications in accordance with appropriate codes, standards and/or company training programs. These qualifications and certifications shall be documented.
Prior to performing inspections, inspection personnel shall have access to.the drawings, procedures, specifications or other documented criteria necessary for performance of the inspection.
10.2.4 Inspection Procedures Required inspection, surveillance or monitoring activities shall be performed and documented according to written, approved instructions or procedures.
Inspection procedures, instructions or checklists shall contain the following:
Identification of characteristics to be inspected; Identification of the individual or groups responsible for performing the inspection; Acceptance criteria or reference to the acceptance criteria; A description of the method of inspection; Verification of completion and certification of inspection.
Inspection records shall identify:
Inspector or data recorder; Method or type of observations; Test or inspection results; Statement of acceptability; Date of observation; Deficiencies and nonconformances, and the action taken in connection with these deficient conditions, either by inclusion or by reference to other documents; Procedure No: TQR 10.0 Rev: 12 Page 2 of 4
iIi
~i ili
C. Inspection procedures. shall be reviewed by Nuclear Assurance personnel to determine. the',need for an independent. inspection and the'degree and method if such an'inspection is required, and to assure the identification of inspection personnel'and the method of documentation of inspection results;
- d. Written approved instructions shall specify surveillance or monitoring of processing'methods, or. testing and operation of equipment when inspection is impossible, inaccessible or'not applicable;
- e. Modification, repair, replacement or rework items shall be inspected in accordance with original inspection requirements or acceptable alternatives.
10.2.5 Inspection, Witness, and Hold Point Identification Appropriate inspection, witness or hold points shall appear in process documents,(e.g.,
construction, testing, operating and maintenance procedures)'. These process procedures are subject to the review of the Quality Control organization for adequacy of inspection; witness, and hold points.
Mandatory hold points shall be identified in process documents when witnessing and inspecting must be performed and signed-off by the responsible personnel before work can proceed.
FPL procurement documents shall indicate. FPL witness or hold points applicable prior to during, or after the manufacture of an item or the performance of a service. A distinction shall be made between witness points and mandatory hold points.
10.3 RESPO SIBILIT ES 10.3.1 Direct Reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division that perform inspection activities are responsible for:
- a. Implementation of a program for inspection activities;
- b. Ensuring that this program verifies compliance with applicable portions of Technical Specifications, SAR requirements, procurement documents, other operating license requirements and the QA Manual; Ensuring coordination with QC for incorporation of QC inspection and hold points
.into procedures and work documents; Ensuring that inspections are not inadvertently omitted or, bypassed; Ensuring that, personnel assigned to perform inspections are appropriately qualified and certified; Procedure No: TQR 10.0 Rev:.12 Page3of4
tlat Oi
Ensuring inspection procedures are reviewed by Nuclear Assurance personnel to determine the need for an independent inspection and the degree and method if such an inspection is required, and to ensure the identification of inspection personnel and the method of documentation of inspection results.
10;3.2 The Director Nuclear Assurance is responsible for:
a.,implementation of a program for. inspection and surveillance activities; Ensuring that required QC inspections are incorporated into:inspection/test/
maintenance procedures,,design'change documents, and work process control documents; C. Ensuring that inspections and surveillances are correctly. performed and documented; Reviewing inspection procedures to determine the need for an independent inspection and the degree and method if such an inspection is required, and to ensure the identification of inspection personnel and the method of documentation of inspection results.
Procedure No: TQR10.0 Rev:12 Page 4 of 4
~ 1 il~
TOPICAL QUALITYASSURANCE REPORT TQR 11.0 Rev: 6 Test Control Date:02/28/97 11.1 GE ERAL RE UIRE ENTS A test program shall be established to assure that testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified, accomplished, and documented in accordance with written procedures. The test program shall include, as appropriate, proof tests prior to installation, pre-operational tests,'start-up tests, operational tests, and retest following repairs, replacements or modifications.
11.2 IMPLEMENT TION 11.2.1 Test Program Testing requirements. shall be identified in the engineering/design documents, SAR documents, procedures, or procurement documents, as appropriate. Retest following repairs, replacements, or modifications shall be performed in accordance with the original design and test requirements or acceptable alternatives. Retest shall be performed when the original test results are invalidated. A schedule shall be provided and maintained to provide assurance that all tests are performed and properly evaluated on a timely basis.
Quality, Instructions shall be written which delineate the methods and responsibilities for scheduling, controlling, accomplishing, and documenting testing.
FPL may delegate the implementation of all or any part of the test program to other organizations but shall retain ultimate responsibility for the program. The contractor shall be required to control, perform and evaluate tests in accordance with written procedures and shall be required to prepare a written test program detailing the testing required.
11.2.2 Test Procedure Preparation and Test Performance Testing shall be accomplished in accordance with written approved test procedures which incorporate or reference the requirements and acceptance limits in the applicable design and procurement documents. Test procedures shall be revised as necessary to assure that tests are performed in accordance with the latest approved information. The test procedure or test program documents shall include or reference the following as a minimum:
Instructions for. the testing method used (including precautions, limitations, and restoration of normal conditions upon test completion);
- b. Required test equipment and instrumentation;
- c. Test requirements and acceptance criteria;
- d. Hold, witness, inspection and data collection points; Procedure No: TQR.11.0 Rev: 6 Page 1 of 3
4~
il~
Test prerequisites such as: calibrated instrumentation; trained, qualified, and licensed or certified personnel; preparation, condition and completeness of item to be tested; suitable and controlled environmental conditions; defined system interfaces; initial plant conditions; Methods for documenting or recording test data and results;
- g. Test records shall identify:
- 1) Identification of personnel performing the testing activities;
- 2) Method or type of observations;
- 3) Test or inspection results (to include pertinent test data);
- 4) Specific measuring and test equipment utilized for testing;
- 5) As found and as left condition (as applicable);
- 6) Statement of acceptability;
- 7) Date of observation; and
- 8) Deficiencies and nonconformances, and the action taken in connection with these deficient conditions, either by inclusion or by reference to other documents.
11.2.3 Evaluation of Test Results The documented test results shall be evaluated against the predetermined acceptance criteria by a group or individual having appropriate qualifications. The acceptance status of the test shall be documented. Deficiencies noted during the evaluation shall be documented'and disposition provided in accordance with TQR 15.0 and approved Quality Instructions.
The evaluation of the test results may be delegated to other organizations; however, FPL shall retain the responsibility for the evaluation. The evaluating organization shall be required to use qualified personnel, evaluate the data against predetermined criteria, and document the results of the evaluation and acceptance status of the test.
1.1.3 RE PONSIBILITIES 11.3.1. The Site Vice President is responsible for.
- a. Assuring, that plant tests are identified, scheduled, controlled, performed and documented;,
- b. Assuring that plant test procedures are reviewed andIapproved.
Procedure No: TQR11.0 Rev:6 Page2of3
~i
~
11.3.2 The Director Nuclear Assurance is responsible for:
- a. Assuring that test procedures specify necessary quality requirements such as witness and hold points, and adequate data sheets.
11.'3.3 The'Director Protection &'Control Systems is responsible for:
- a. Assuring the identification, scheduling, control, performance, and documentation of tests performed by Protection & Control Systems;
- b. Submitting test procedures to the Plant General Manager for review;
- c. Coordinating test schedules with the'Plant Gerieral Manager.
11.3.4 The Vice President Nuclear Engineering is responsible for:
- a. Specifying. the need for pre-installation and post-installation testing of items within the purview of, Nuclear Engineering;
- b. Writing test procedures as requested;
- c. Evaluating test results as requested.
Procedure No: TQR11.0 Revt 6 Page 3 of 3
TOPICAL QUALITYASSURANCE REPORT TQR 12.0 Rev: 5 Control of Measuring'& Test Equipment Date:02/01/94 12.'1 GE E AL E UI E E Measures shall be established to assure that tools, gages, instruments, and other measuring and testing devices used in activities affecting quality are properly controlled, calibrated, and adjusted at specified, periods to maintain accuracy within necessary limits. It is the responsibility. of each department, maintaining calibrated instruments to provide for the calibration and control of such instruments.
12.2 IMPLEME TATION 12.2.1 Calibration and Control of Measuring and Test Equipment Procedures shall be written to delineate the. methods and responsibilities for the control, maintenance, and calibration of measuring'and test equipment (M&TE) and installed plant instrumentation and control equipment. MBTE control procedures or calibration program documents shall contain the following:
- a. A complete listing of MBTE and installed plant instrumentation and control equipment to be controlled;
- b. The frequency of calibration of listed MBTE and installed plant instrumentation
,and control equipment. The frequency may be based on calendar time or relate to usage and shall'be based on such factors as licensing commitments, regulatofy requirements, experience, inherent stability,.manufacturer's recommendations, purpose of use, frequency of service, or company standards.
A schedule for calibration shall. be established and shall indicate as a minimum the instrument, calibration frequency, and procedure to be used or the identification of. the approved supplier qualified to provide calibration services;.
- c. A method for controlling issue and recall of portable:MBTE;
- d. A method to uniquely identify controlled.M&TE (e.g., labeling), required calibration frequency and calibration test data applicable to the M&TE and installed plant instrumentation and control equipment;
- e. A method to document and maintain the status of MBTE and installed plant
.instrumentation and control equipment.
MB TE shall be calibrated in. environments which will not adversely affect their accuracy.
When inaccuracy due to environmental effects cannot be avoided, compensating corrections shall be determined.and applied in accordance with the manufacturer technical instructions.
M&TE and reference standards shall be suitably marked so that the calibration status Procedure No: TQR12.0 Rev:5 Page 1 of 3
- j. $
ilt igi
'li
can be determined.
FPL may delegate the control and/or calibration of M&TE to other organizations. FPL, however, retains ultimate responsibility for control and calibration, and the contractor shall meet the requirements of this TQR or an acceptable alternative program as required by the procurement document for the contracted services.
12.2.2 Calibration Procedure M&TE, reference standards, and listed installed plant instrumentation and control equipment shall be calibrated in accordance with written approved procedures.
Calibration procedures shall contain, or reference as a minimum:
- a. Identity of M&TE or equipment to which the procedure applies;
- b. Calibration equipment and reference standards to be used;
- c. Acceptance criteria;
- d. Sequence of operations;
- e. Special instructions (such as, prerequisites, power level requirements, precautions, limitations) as applicable; Documentation and data collection requirements; A requirement that equipment to be calibrated, be checked and results recorded before adjustments or repairs are made;
- h. Calibration frequency required.
12.2.3 Calibration Standards M&TE shall be calibrated using reference standards whose calibration has a known, documented, valid relationship to nationally recognized standards or accepted values of natural physical constants. If no national standard exists, the basis for calibration shall be documented. Standards and reference standards shall have an accuracy level, range and stability which are adequate to verify that the equipment being calibrated is within tolerance and adequate for the programmatic requirements of the equipment being calibrated.
M&TE shall be calibrated against working standards having an accuracy of at least four times the required accuracy of the equipment being calibrated. When this is not practical, working standards shall have an accuracy that assures that the M&TE being calibrated will be within required accuracy tolerances and that the basis of acceptance is
.documented and authorized by designated responsible management.
Procedure No: TQR12.0 Rev: 5 Page 2 of 3
ig~
i4~
il~
The meaning of this paragraph.may be diagrammed as follows:
NATIONALINSTITUTE OF STANDARDS AND TECHNOLOGY (NIST)
"greater'than".tolerance IB! PRIMARY STANDARD (if applicable)
"greater than" tolerance 8 SECONDARY STANDARD (if applicable)
"greater than" tolerance H WORKING STANDARD "1:4 ratio" tolerance (except as noted above)
V~ M&TE (installed instruments and measuring and test equipment used for inspection, maintenance, etc.)
The accuracies of M&TE and reference standards shall be chosen such that the equipment being calibrated can be calibrated and maintained within the required tolerances.
12.2.4 "Out of Tolerance" Control and Corrective Action The reporting, follow-up, and correction of conditions adverse,to quality found during calibration or calibration checks shall be documented. M8TE and reference standards, when found out of tolerance, shall be so identified and removed from service, tagged to indicate its status and segregated from M&TE in service, pending disposition of corrective action. A documented investigation shall be conducted to determine the validity of previous inspection or test results gained through use of the instrument, and of the acceptability of items previously inspected or tested.
12.3 RESPONSIBILITIES 12.3.1 Direct reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division shall be responsibile for:
- a. Assuring that the affected plant departments establish and maintain a calibration control program;
- b. Assuring that written procedures governing calibration activities are reviewed and approved prior to use;
- c. Assuring that documentation of calibration activities are reviewed and approved.
12.3.2 The Director Protection 8 Control Systems is responsible for assuring that calibration control procedures'for installed plant instrumentation and control equipment under his control are submitted to the Plant General Manager for review, and for coordination of calibration activity schedules with plant supervisors.
Procedure No: TQR12.0 Rev:5 Page3of3
ili ili
TOPICAL QUALITYASSURANCE REPORT TQR 13.0 Rev: 10 Handling, Storage & Shipping Date:02/28/97 13.1 GE ERAL RE UIREMENTS Written, instructions or procedures shall be established and implemented for the cleaning, shipping, storage, preservation,.packaging, and handling of specified items. These instructions and procedures shall delineate measures which prevent degrading an item through damage or deterioration. When necessary for particular products, special protective environments such as inert gas atmosphere, specific moisture content levels, and temperature levels shall be specified and provided.
Housekeeping procedures and instructions shall require cleanness to be maintained at a level consistent with the work performed to prevent the entry of foreign material into safety related systems. Control of personnel, tools, equipment and supplies shall be established with approved procedures or instructions when:the safety function of a system, component or item may be jeopardized and also while the reactor system is opened for inspection, maintenance or repair.
Documented cleanness inspections shall be performed prior to system closure.
13.2.1 General Instructions or procedures shall be written to define the requirements and responsibilities for the housekeeping, cleaning; packaging, preservation, handling, storage, and shipping of equipment and material, and shall require implementation of the established design and specification requirements by personnel having appropriate qualifications. FPL may delegate any portion of the responsibility for cleaning, housekeeping, handling, storage and shipping of material and equipment, but shall retain ultimate responsibility. Where any of the functions in the sections which follow is delegated to a contractor, the contractor shall be required to adhere to the FPL requirements stated herein.
13.2.2 Handling, Storage, and Shipping Procedures Materials and equipment which are to be incorporated into a safety related system of a nuclear power plant shall be handled, stored, and shipped in accordance with written procedures, where necessary, to implement the design document and purchase order requirements. These procedures shall assure that cleaning, handling, storing, packaging, shipping, and preserving materials, components and systems will preclude damage, loss, or deterioration by environmental conditions, such as temperature or humidity.
Site specific procedures or specific work instructions shall be developed which provide guidelines in handling heavy loads that are lifted over, or in proximity to, irradiated fuel or safe shutdown equipment/systems.
Procedure No: TQR13.0 Rev:10 Page 1 of 2
ili il>
ili 4
The preparation and/or implementation of these procedures may be delegated to other organizations, but FPL shall retain the ultimate responsibility for proper material handling, storage, and shipping.
13.2.3 Cleanness Procedures Procedures or work instructions for cleaning; cleanness control practices and inspections; examinations or tests to verify cleanness of items; shall be prepared and implemented.
13.2.4 Housekeeping Procedures Methods and techniques for controlling and maintaining'housekeeping and documenting housekeeping surveillances and inspections shall be delineated in procedures or instructions.
13.3 RESPONS BILITIES 13.3.1 The Site Vice President has overall:responsibility for ensuring that handling, storage, shipping, cleanness and housekeeping requirements are identified, and implemented.
13.3.2 The Vice. President Nuclear Engineering is responsible for:
- a. Identifying special handling and storage. requirements for. site-'fabricated items in applicable design output documents/work instructions;
- b. Identifying cleaning and cleanness verification methods in appropriate specifications, drawings or procedures.
13.3;3 The Director Nuclear Assurance is responsible for:
- a. Verifying proper handling, storage, and shipping activities at supplier facilities;
- b. Verification of housekeeping, handling,;storage, shipping and cleanness of items through inspections, surveillances, examinations or. tests at'the plant site.
Procedure No: TQR 13.0,Rev: 10 Page2of2
4'I 15~
~ ~
TOPICAL QUALITYASSURANCE REPORT TQR 14.0 Rev: 11 tnspectlon, Test & Operating Status Date:06J03l96 14 0 GENERAL E U EME S Measures shall be established to indicate by use of markings such as stamps, tags, labels, routing cards or other. suitable means, the status of inspections and tests performed on material, equipments, or systems. These measures shall provide for the identification of items which have satisfactorily passed required inspections and tests. Measures shall also be established for indicating the operating status of structures, systems and components to prevent inadvertent operations.
142 PLE E 0 14.2.1 General A suitable system. for identifying the inspection, test, and operating status of materials, equipment, systems, and components shall be established. Each system shall be implemented and maintained in accordance with.written Quality Instructions. The Architect/Engineer or Contractors shall develop and implement procedures to comply with contractual responsibilities, and applicable codes, standards, specifications, and criteria governing the status identification of procurement items being tested, installed, or fabricated. The Architect/Engineer (where applicable), suppliers and contractors shall be required to maintain a system for identifying the inspection, test and processing status of materials, parts, and components. Elements of this-system require that suppliers and contractors have a controlled manufacturing and test operation in order to preclude the inadvertent bypassing of processing, inspections or test, and to provide a positive:
identification of component status throughout all phases of manufacturing, testing, and inspecting, by means of tagging, routing cards, stamping, manufacturing or test reports, labeling or other appropriate methods. Methods to verify adequacy of the controls shall
'be established and implemented, as appropriate.
14.2;2 Status Identification and Control Quality Instructions shall describe control of the application and removal of markings such as stamps, tags, labels, routing cards, and other suitable means to indicate the status of non-operational, nonconforming, or malfunctioning nuclear safety related structures, systems and components to prevent inadvertent operation, and to prevent omission of inspections, tests, or other critical operations. These procedures and instructions shall delineate the requirements, methods and responsibilities for indicating the status of the affected items. These procedures will clearly, delineate the individuals or groups responsible for application and removal of status indicators. These procedures shall require independent verifications, where appropriate to ensure that necessary measures have been implemented.
Procedure No: TQR14.0 Rev:11 Page1 of2
il~
ig~
4,
!I~
14.3:1 Direct reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division shall be responsible for coordinating activities affecting the inspection, test and operating status of material, equipment, systems, and components with the appropriate plant organization.
14.3;2 The Site Vice President is responsible for the establishment, maintenance, and implementation of a suitable system for identifying, inspecting; testing, and providing operating status of material, equipment, systems and components in accordance with written and approved procedures and instructions and the approval of other programs utilized on site which provide for inspections, test and operating status; 14.3.3 The Director Nuclear Assurance is responsible for assuring that requirements are implemented per written instructions and procedures.
Procedure No: TQR14.0 Rev:11 Page 2 of 2
TOPICAL QUALITYASSURANCE REPORT TQR 15.0 Rev: 12 Nonconformtng Materials, Parts or Components Date:02/28/97 15.1 GENERAL E Ul E ENTS Measures shall be established to control materials, parts, or components which do not conform to requirements in order to prevent their. inadvertent use or installation. These measures shall include, as appropriate, procedures for identification, documentation, segregation, disposition and notification to affected organizations. Nonconforming items shall be reviewed and accepted, rejected, repaired or reworked in accordance with documented procedures.
15.2 PLEMEN 0 15;2.1 Program Quality Instructions shall define the responsibilities and methods for identifying, documenting, segregating and providing disposition for nonconforming items.
Throughout plant life, FPL may delegate any portion of the identification and control of nonconforming items and services to an Architect/Engineer (A/E), constructor, NSSS vendor or other contractor. In any case, FPL retains the responsibility for assuring that requirements are met, and shall assure that the contractor's actions conform to requirements set by FPL.
15.2.2 Documenting and Controlling Nonconformances All nonconformances shall be documented and reported for corrective action. Measures shall be delineated in Quality Instructions which control further processing, installation, or operation of nonconforming items. These measures shall include:
- a. Physical identification of the item as nonconforming;
- b. Segregation of nonconforming items until disposition is properly provided.
Where physical segregation is not practical, suitable tags, marking or documentation shall be used to assure control.
The control of, and the documentation generated by the identification, disposition, correction, and verification of nonconformances may be transferred between processing methods. Adequate controls shall be established to assure traceability between processing methods and the identified nonconforming item and to prevent inadvertent cancellation of the corrective action implementing document.
15.2.3 Documentation Documentation of the nonconforming item shall: identify the item; describe the nonconformance; show disposition of'the nonconformance and inspection requirements; and include the signature of the person approving the disposition.
Procedure No: TQR 15.0'ev: 12 Page 1 of 3
i5
~ ~
Oi
15.2.4 Evaluation and Disposition Nuclear Engineering, or other delegated organizations, as specified by procedure, shall evaluate nonconformances and provide disposition for them based on the results of the evaluations. Nonconforming conditions which cannot be made acceptable utilizing existing design documents shall be evaluated by Nuclear Engineering for disposition.
These evaluations and dispositions shall be reviewed, approved and documented in accordance with procedures.
An evaluation to determine the disposition of nonconforming items shall be performed.
The evaluation shall determine whether an item is to be accepted as-is, repaired, reworked or rejected. A technical evaluation shall be performed when an item is accepted as-is or is repaired to an acceptable condition. Records of the disposition of these items shall be made part of the nonconformance report. This evaluation shall assure that the final condition does not adversely effect safety, operability or maintainability of the item, or of the component or system in which it is installed.
The NE, or other contractors on-site, shall be required to inform FPL as specified in procurement documents prior to use or installation of a nonconforming item. The nature and extent of a nonconformance and the reason for proposing its use or installation shall be justified. Nonconforming items with a disposition of "accept as-is", or repaired to an acceptable condition, shall be so identified. Nonconformance reports for those items shall be made part of the item records and forwarded with the items to FPL.
The determination of the need and the advisability of releasing nonconforming items shall be initiated by the Site Vice President, and approved by Nuclear Engineering. The following factors may be appropriate considerations in making this determination:
- a. Effect on the orderly progress of work if items are released;
- b. Safety of personnel;
- c. Suitability of items in "as-is" condition, i.e., probability of eventual satisfactory resolution of the nonconformance without repair, rework, or replacement;
- d. Accessibility of items after release;
- e. Cost of removal and repair of replacement should items eventually have to be removed, repaired, or replaced;
- f. Impact on plant safety.
Items shall be reworked or repaired in accordance with documented procedures and shall be verified by reinspecting the item as originally inspected or by a documented method which is at least equal to the original inspection method.
Nonconformance reports shall be periodically reviewed to identify quality trends. The results of these analyses shall be reviewed with appropriate members of upper-level management.
Procedure No: TQR15.0 Rev:12 Page 2 of 3
'I g ii) il~
c
15.3 E 0 S B L ES.
15.3.1 Direct reports of the President, Nuclear Division, and'Department Heads of organizations supporting the Nuclear Division are responsible for:
- a. the generation of instructions/procedures to'implement requirements for the identification, control, disposition, and verification of nonconformances within
.their purview; identifying and'documenting nonconforming, items within.the scope of their departmental responsibilities; A
submitting'nonconformances requiring design evaluations to the appropriate engineering organizations; tracking and control of open nonconforming items within the scope of, their departmental responsibilities; providing disposition and verifying the resolution of nonconforming items within the scope of their departmental responsibilities;
- f. periodically assessing quality trends related to nonconformances.
15.3.2 The Site Vice President is responsible for.
- a. supplier notification and follow-up of nonconformances requiring supplier corrective actions;
- b. initiation of release of nonconforming material for use.
15.3.3 The Director Nuclear Assurance is responsible for:
- a. periodically assessing quality trends related to nonconformances and reviewing the results of these assessments with appropriate members of upper-level management.
15.3.4 The Vice President Nuclear Engineering is responsible for:
the review, evaluation, and disposition of nonconformances submitted by other departments;
- b. approval of release of'nonconforming items; c; supplier notification and follow-up of nonconformances requiring supplier corrective actions.
Procedure No: TQR15.0 Rev:,12 Page 3 of 3
TOPICAL,QUALITYASSURANCE REPORT TQR 16.0 Rev: 10 Corrective Action Date:10/16/96 16.1 GE E L RE UIREMENTS Documented measures shall be'used to assure that'conditions adverse to quality such as
,failures, malfunctions, deficienciesdeviations, defective material and equipment, and nonconformances, are promptly'identified and corrected as soon as practicable. In the case of significant conditions adverse to quality, the cause of the condition shall be determined.and action taken to preclude repetition. The identification of significant conditions adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriate levels of management.
16.2 IMPLEMENTATION 16.2.1 Corrective Action'and Follow-Up Quality Instructions shall define responsibilities,and methods for identifying and correcting conditions'adverse to quality. When an adverse condition is detected, a determination shall be made by plant supervision or Nuclear Assurance personnel as to whether immediate. or. routine corrective action is required.
"Immediate'Corrective Action" applies to conditions which pose a threat to plant safety or to the health and safety. of the public, which could result in major equipment and material damage, or could, if not corrected, produce defects of significantly greater consequences than those immediately resulting from the condition. "Immediate Corrective Action" is accomplished through stop-work requests/orders to appropriate levels of management,;requiring that. work be stopped, the plant be shut. down or other appropriate actions be taken.
Specific personnel having stop work authority include the Plant General Manager, Site Quality Manager and Plant Vice President.
"Routine Corrective Action" applies to conditions. which do not require immediate corrective action. Routine corrective action is assured through the. distribution and disposition associated with inspection reports, surveillance reports, nonconformance reports, and audit reports; and the investigation analysis and action associated with reportable events.
Interdepartmental corrective action shall be requested by use of written correspondence.
Audit. reports, nonconformance reports,.interoffice letters, and other documents may be used for this purpose.
Procedure No: TQR16.0 Rev:10 Page 1 of 3
I ill
'i
Follow-up,to verify implementation of corrective action and close-out of corrective action documentation is accomplished by the organization responsible for verifying the corrective action. The'uclear Assurance Department shall track,'follow-up, and closeout open items identified by Nuclear Assurance Department. The'respective department or plant shall track those items charged to its operating license by the NRC.
Each department shall be responsible for follow-up and close-out of corrective action resulting from their departmental inspections, tests, or operations.
If corrective action is inadequate or not timely, the follow-up organization shall request corrective action from management, as delineated in procedures. The President Nuclear Division is the final authority in the event that agreement is not reached at lower levels regarding stop work requests or other corrective action.
Where corrective action is required of contractor personnel, FPL shall define in procedures and contracts the corrective action interface between FPL and the contractor.
FPL shall require the AJE, NSSS vendor, constructor and other suppliers of safety related materials and services to have a documented corrective action system.
16.2.2 Recurrence Control It is the responsibility of the organization which identifies the significant condition adverse to quality to verify that corrective action description not only corrects the immediate condition, but also precludes the condition from recurring. The organization(s) that provide(s) the corrective action disposition and implementation is responsible to assure
..that the corrective action taken not only corrects the immediate condition, but also precludes recurrence.
16.2.3 Incidents and Reportable Events Reporting Operating reportable events and reports of incidents shall be investigated, documented as to cause and corrective action, and reported to the NRC in accordance with the applicable plant Technical Specifications and Federal Regulations. Reportable events and reports of incidents that are safety related or that result in damage shall be forwarded to the Company Nuclear Review Board (CNRB) for review. Conditions adverse to quality are reported to operating plant management through: distribution of QA audit reports, QC inspection reports,.corrective action requests, and the investigation and reporting of reportable events in accordance with plant Technical Specifications.
Procedure No: TQR16.0 Rev: 10 Page2of3
~li IS)
~ ~
16.3.1 The President Nuclear Division is the final authority in the event agreement relating to stop work requests or other proposed corrective action is not reached at lower management levels.
16.3.2 Direct reports of the President Nuclear Division and Department Heads of organizations supporting the Nuclear Division are'responsible for.
- a. Assuring that timely corrective action within their respective organization;
- b. Follow-up and assuring completion of corrective action resulting from, their respective department's audits, inspections, surveillances, tests, or operations;
- c. Reviewing and investigating audit findings to determine and schedule appropriate corrective action and responding as requested in the audit report.
16.3.3 The Director Nuclear Assurance has the responsibility and authority to recommend that work be stopped or appropriate corrective action taken as a result of QA findings during department audits'and reviews or QC activities.
16.3.4 All personnel detecting conditions adverse to quality or significant conditions adverse to quality are responsible for reporting such conditions to the appropriate authority.
16.3.5 The Vice Presidents, PSL, PTN, Nuclear Engineering, and the Director of Nuclear Assurance are responsible for administering a commitment tracking system.
Procedure No: TQR 16.0, Rev: 10 Page3of3
ilt
'g ik~
ha . %I-
TOPICAL QUALITYASSURANCE REPORT TQR 17.0 Rov: 6 Quatity Assurance Records Date:10116/96 17.1 GE ER L E UI E E S Sufficient records shall be maintained to furnish documented evidence of the quality of safety related structures, systems, and components, and of activities affecting their quality. The records shall include, as appropriate, data such as qualifications, of personnel, procedures, and equipment; and other documentation such as inspection or test acceptance criteria, and the action taken in connection with deficiencies noted during inspection.
The records required to furnish documentary evidence of quality, herein called quality assurance records, shall be identifiable and retrievable. These records shall be maintained in facilities that provide a suitable environment to minimize deterioration or damage and to prevent loss.
The requirements and responsibilities for quality assurance record. control, transmittal, retention, and maintenance shall be established and documented. These record requirements shall be consistent with applicable design, manufacturing, and installation codes and standards, and with procurement document requirements.
LE E AT 0 17.2.1 Records Identification and Classification Quality Instructions shall define the quality assurance records necessary to furnish documentary evidence of the quality of safety related structures, systems, and components; and activities affecting quality. These records shall include plant operating logs; results of design reviews, inspections, tests, audits, and material, analyses; qualification of personnel, procedures, and equipment; design records such as drawings and specifications; procurement documents; calibration records; and nonconformance or corrective action reports.
Quality assurance records shall be classified as lifetime or non-permanent as required by the NRC facility operating license, the NRC construction permit, applicable parts of 10CFR, the FSAR, or other NRC commitments. Retention times shall be established for each record series and provided to the Records Official.
17.2.2 Completeness and Control Quality assurance records submitted for retention shall be legible, completely filled out, and adequately identifiable and retrievable for each item.
Quality Instructions shall include methods for handling corrections and supplements to existing QA records.
Procedure No: TQR17.0 Rev:5 Page 1 of 3
<gi if' h
17.2.3 Retrieval Records shall be filed in an approved record storage area or facility using a documented system to provide retrievability.,Documented methods for control and accountability of records removed from the record storage area shall be instituted.
17.2.4 Storage Construction features and location requirements for record storage facilities shall be established to assure that quality assurance records are protected from possible destruction by causes such as fire, flooding, theft, tornadoes, insects, rodents, and from possible deterioration by a combination of extreme variations in temperature and humidity. Specific instructions regarding the record storage area or facility shall be given for special processed records (e.g. radiographs, magnetic media, and microfilm, etc.).
A QA Record Storage Evaluation Team (QARSET) shall be established to determine if the methods utilized to store and protect QA records are adequate. The QARSET shall consist of the following: the QA Supervisor Performance Assessment, a Risk Management Representative, and the Records Official. The QARSET shall maintain records of evaluations and establish schedules to assure that reevaluations are performed every two (2) years.
The QARSET shall evaluate the status of existing record storage facilities and the adequacy of additional record storage facilities prior to the construction of a new facility or the conversion of existing structures.
When temporary storage of records (such as for processing, review, or use) is required by an organization's procedures, the records shall be stored in a QARSET approved container. The maximum allowable time limit for temporary storage is 24 months.
J The requirements of the Topical Quality Assurance Report, Appendix C shall be utilized in the evaluation of potential permanent and temporary record storage facilities.
17.3 RESPONS B LI ES 17.3.1 Direct reports of the President, Nuclear Division, and Department Heads of organizations supporting the Nuclear Division that generate quality assurance records are responsible for:
the technical content and accuracy of the records they generate; transmitting records and indexing information to the appropriate record storage facility or requesting approved storage locations from QARSET; establishing and approving a list of quality assurance records generated by the organization and their retention times and assuring that these quality assurance records are identified in the appropriate quality assurance record index; the storage and retrieval of quality assurance records prior to transmittal to permanent record storage facilities; Procedure No: TQR17.0 Rev:5 Page 2 of 3
ili ill
performing periodic surveys to ensure that their record control system is adequate;,
transmitting a copy of the records retention schedule to the Records Official for all records maintained by their organization.
17.3.2 The Records Official is responsible for:
- a. ensuring the quality assurance records program activities are managed in accordance with applicable recordkeeping requirements; reviewing and retaining copies of record retention schedules received from originating departments; locating acceptable record storage areas when requested; leading the evaluation of specially designated QARSET approved record storage facilities, maintaining records of this evaluation,.and establishing schedules to assure that re-evaluations are performed every two (2) years.
17.3.3 The Plant Vice President is responsible for:
- a. the storage, retrieval, and control of quality assurance records at the site.
17.3.4 The Corporate Records Supervisor is responsible for.
- a. storage, retrieval, and.control of records.and documents stored at the Corporate Records Center and Documentary Files..
17;3.5 The Quality Assurance Record Storage Evaluation Team (QARSET) is responsible for:
- a. evaluating the acceptability of storage locations for quality assurance records; b., ensuring that evaluations, of record storage locations are performed every two years.
Procedure No: TQR,17.0 Rev: 5 Page3of3
il~
ili il~
TOPICAL QUALITYASSURANCE REPORT TQR 18.0 Rev: 9 Audits Date:06N3l96 18.1 GENERAL RE UIREME S A comprehensive system of. planned and periodic audits shall be carried out to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program. The audits shall be performed in accordance with the written procedures or checklists by appropriately trained personnel not having direct responsibilities in the areas being audited.
Audit results shall be documented and reviewed by management having responsibility in the area audited. Follow-up action, including reaudit of deficient areas, shall be taken, where necessary.
18.2, IMPLE ENTA 0 A comprehensive program of audits is carried out by the Quality Assurance Department during the design, procurement, construction, and operations phase of nuclear power plants. These audits are performed to verify that all safety related activities associated with nuclear power plants are carried out in accordance with the requirements of the FPL QA Program, and that the implementation is, effective.
18.2.1 Personnel Quality Instructions shall provide instructions for the training of QA Department personnel who perform audit activities, to assure that they are adequately indoctrinated and trained, and that they are qualified to carry out these activities. Quality Instructions provide for personnel qualified as Lead Auditors to be formally certified by Quality. Assurance Department management. Certification shall be based on education, experience, training and other specified criteria.
18.2.2 Planning and Scheduling Quality Instructions provide requirements for written audit plans and schedules. The audits are planned and scheduled on the basis of the following:
Activities shall be audited as early in their life as practicable. Auditing shall be initiated early enough to assure effective quality assurance during the design, procurement and contracting activities; The system of audits devised to verify compliance with aspects of the nuclear plants is described in each unit's technical specifications. Audits of selected aspects of operational phase activities are performed with a frequency commensurate with safety significance. As a minimun, unless otherwise specified by technical specifications, the Code of Federal Regulations or other licensing commitments, these audits are performed at a biennial (2-year) frequency. The audit system is reviewed periodically and revised as necessary to assure coverage commensurate with current and planned activities; Procedure No: TQR18.0 Revt 9 Page 1 of 4
il~
lit ili
An annual evaluation of suppliers'uality performance history shall be performed to determine reaudit requirements. Reaudit requirements for suppliers shall be based on the supplier's quality performance and the complexity and criticality of the equipment or service being procured. A facility evaluation (audit) will be
.performed at least every three years and shall be conducted in accordance with Quality Instructions for supplier evaluations;
- d. Audits shall be regularly scheduled for on-going activities;
- e. Regularly scheduled audits shall be supplemented, as required to cover unforeseen events or changes in requirements.
The scope of audit activities shall include, as a minimum:
- a. The determination of site features which affect plant safety (e.g., core sampling, site preparation, and meteorology);
The preparation, review, approval, and control of the SAR, designs, specifications, procurement documents, instructions, procedures, and drawings; C. Evaluation of bids;
- d. Indoctrination and training programs;
- e. Receiving and plant inspections;
- f. Operation, maintenance/repair and modification;
- g. The implementation of operating and test procedures; All criteria in Appendix B to 10 CFR Part 50; I. Validity of Certificates of Conformance.
External audits shall be performed by the Quality Assurance Department on Architect/Engineers, NSSS vendors, constructors, and other suppliers of safety related materials and services to evaluate their QA programs, procedures and activities.
Procurement documents shall require that FPL suppliers and contractors in turn perform audits on their sub-tier suppliers and contractors.
18.2.3 Conduct of, Audits Quality Instructions shall delineate requirements for the conduct of audits. These instructions shall require that:
- a. Audits be conducted by trained and qualified personnel;
- b. Personnel conducting audits shall not have direct responsibility in the area audited;
- c. Checklists or instructions shall be used to ensure depth and continuity of audits; Procedure No: TQR18.0 Rev:9 Page2of4
igi Objective evidence shall be examined for compliance with quality assurance program requirements. This shall include examination of instructions and activities to assure that documented objective evidence is meaningful and in compliance with the overall Quality Assurance Program;
- e. Audits shall include evaluation of work areas, activities, processes and items; and the review of documents and records.
18.2.4 Reporting of Audit Findings Audit findings shall be documented in written reports. Audit reports shall be distributed to the responsible management of, the audited FPL organization within thirty calendar days after completion of the audit.
18.2.5 Follow-up Responsible management of the audited organization shall take action to correct the deficiencies identified in the audit report and provide a written. response within thirty calendar days after receipt of the report. This response shall include action taken and/or planned to correct deficiencies and to prevent recurrence of the deficiencies, and commitment dates for actions not yet complete. The mechanism for evaluation and.
follow-up of corrective action is described in TQR 16.0. The status of correction of deficiencies shall be followed until the corrective actions have been accomplished and verified.
18.2.6 Reports to Management The Quality Assurance Department periodically reports on the status of the Quality Program to the members of the Company Nuclear Review Board (CNRB). This status report summarizes the results of QA Department audit activities for. the period, keeps all CNRB members apprised of current conditions and program effectiveness, and when necessary, directs management attention to significant trends and problems.
18.3 RESPONSIBILITIES 18.3.1 Direct reports to the President, Nuclear Division, and Department Heads of organizations supporting the nuclear division shall be responsible for:
- 1. Taking action to correct deficiencies identified in audit reports;
- 2. Providing a written response within thirty (30) calendar days of receipt the audit report.
18.3.2 The Director, Nuclear Assurance is responsible for the following:
- a. t. Scheduling audits on a regular basis;
- b. Selecting the audit team and the Lead Auditor;
- c. Reviewing each audit report for accuracy, completeness, proper format and distribution; Procedure No: TQR18.0 Revr 9 Page3of4
5~,
igl 4
ig~
ili
Designating a qualified replacement Lead'Auditor (in writing) if the audit team leader transfers from the respective QA group or is otherwise unable to continue the assigned audit;
- e. The qualification of Lead Auditors.
18.3.3 The Chairman, Company Nuclear Review Board.(CNRB) is responsible for review and concurrence of Annual Audit Program Plans, review of individual audit scopes and involvement in the audit program for internal audits as defined by CNRB instructions.
Procedure No: TQR18.0 Rev: 9 Page 4 of 4
ili il~
O~
TNK BOARD CNIEF EXECUTIVE PRESIDENT PRESIDENT GENERAL COUNSEL NUCLEAR DIVISION FLORIDA POWER & UGHT AND SECRETARY COMPANY NUCLEAR REVIEW BOARD SEE FIGURE 1.1 ON VICE PREMDENT PAGE 2 OF 2 INFORMATXNI MANAGEMENT VICE PRESIDENT DUIECTOR I@RECTOR VICE PRESIDENT VICE PRESIDENT NUCLEAR NUCLEAR NUCLEAR BUSSIESS ST. LUCIE PLANT TURKEY POSIT PLANT ENGSIEEIUNG ASSURANCE SERVICES SEE FIGURE I 1 ON PAGE 2 OF 2 SPEIXFIC SITE ORGAIRZATION SPECFIC SITE MANAGER ORGAIGZATION TURKEY PONT IN FNL IG OA SUPEIIYISOR VICE PRESeENT IN FIG. IG ENGINKERNG POWER DEIIVERY PERFORMANCE ASSESSMENT MANAGER MANAGER PASSPORT SERVICES NUCLEAR UCENSNG AND SPECIAL MANAGEMENT PROGRAMS COMPONENT SUPPORT
& INSPECTION OUAUlYASSURANCE MANAGER SEE FIGURE I I COMPUTER SERVICES ON PROGRAM REVIEW COMMITTEE PAGE 2 OF 2 SUPERVISOR MANAGER BUQNESS PIANNSIG OA SUPERVISOR Sl'. LUCIE PROCUREMENT
& PERFORMANCE ENGINKERNG OUAulY GUAIJIY MANAGER MANAGER TURKEY PONT NUCLEAR FUEL SUPERVISOR OUAIIIYCONmOL REUABIVTY& RISK SUPERVISORS ASSESSMENT MANAGER PSL SGRP ENGSIKESNG OUAVIYMANAGER ST. LUCIE SPECIAL PROJECTS SUPERVISOR NUCLEAR SAFETY SPEAXOUT TOPICAL QUALITYASSURANCE REPORT REVISION 25 ORGANIZATIONOF DEPARTMENTS AFFECTING QUALITY 04/30/97 FIGURE 1-1 APPENDIX A NUCLEAR DIVISION PAGE1 OF2
~li IL ili
CHAIRIlANOF THE BOARD CHIEF EXECUTIVE OFFICER PRESIDENT FLORIDA POWER a uGHT GENERAL COUNSEL a SECRETARY VICE PRESIDENT INFORIIATION MANAGEMENT DUIECTOR ENVXIONNENTAL SERVICES VICE PRESIDENT POWER DEUVERY IIANAGER IXRECTOR BUSINESS DEFLECTOR SYSTENS CORPORATE RECORDS SUPERVISOR VT OPERATIONS DIRECTOR PROTECTION a CONTROL SYSTENS TOPICAL QUALITYASSURANCE REPORT REVISION 25 ORGANIZATIONOF DEPARTMENTS AFFECTING QUALITY 04/30/97 FIGURE 1-1 APPENDIXA NUCLEAR DIVISION PAGE 20F2
VICE PRESIDENT TURKEY POINT PLANT r
PLANT GENERAL MANAGER'UMAN SERVICES RESOURCES MANAGER MANAGER'USINESS UCENSING SYSTEMS MANAGER PTN ENGINEERNG MANAGER'PERATCNS MANAGER'TECBMCAL SUPPQRTI PlANT CHANGE CONTROL SUPPORT SUPERVISOR ENGSIEERNQ MANAGER'RAIhlNG PROTECTION ENSSEERNS')
~'REACTOR (STAA I SERVICES PlANT ENGINEERING MANAGER WORK CONTROL MANAGER MANAGER'AINTENANCE OPERATIONS MANAGER'YSTEMS ENGINEERING MANAGER ac MAINTENANCE OPERATIONS PHYSCSCHEMISTRY SUPERVISOR'ECHAMCAL SUPERVISOR SUPERVISOR'UCLEAR MAINTENANCE SUPERVISOR'EALTH HEALTH SUPERVISOR CHEMISTRY PHYSICS PLANT SUPERVISOR SUPERVISOR' ELECTRICAL MAINTENANCE SUPERVISOR MAINTENANCE SUPPORT SUPERVISOR PROJECTS SUPERVISOR Indicates position with accountabilities in Technical Specifications.
TOPICAL QUALITYASSURANCE REPORT REVISION 13 Although Operations Support Engineering (OSE) personnel may report to the site Engineering Manager, the Plant General Manager shall have direct and unfettered control over those actMles necessary for safe operation TURKEY POINT PLANT SITE ORGANIZATION 11/1 &/97 and maintenance of the plant.
FIGURE 1-2 The Health Physics Supervisor shall have direct access to the Plant APPENDIXA PAGE 1 OF 1 General Manager for matters relating to the radiological health and safety of employees and the public.
lid Oi O~
VICE PRESIOENT ST. LUCIE PLANT I
MANAGER'ERVICES PtANT GENERAL MANAGER'UMAN RESOURCES MANAGER UCENSING MANAGER'ATERIALS MANAGER BUSINESS SYSTEM MANAGER INFORMATION SERVICES SUPERVISOR MANAGER'NGNEERNQ TRAINING SUPERNSOR'REACTCR EtCINEEPJNG')
(STAs'j PIANT ENGINEERING MANAGER SECURITY SUPERVISOR SYSTEMS ENGINEERING MANAGER WORK CONTROL MANAGER MANAGER'AINTENANCE OPERATIONS MANAGER'PERATIONS MAINTENANCE SUPERVISOR'LECTRICAL SUPERVISOR'EALTH MAINTENANCE PHYSICS SUPERVISOR'HEMISTRY SUPERVISOR'ac SUPERVISOR'ECHANICAL MAINTENANCE SUPERVISOR'OTATING MAINTENANCE MAINTENANCE SUPERVISOR'Indicates position with accountabilities in Technical Specifications.
SERVICES'lthough TOPICAL aUALITYASSURANCE REPORT REVISION11 Operations Support Engineering (OSE) personnel may report to the Site Engineering Manager, the Plant General Manager shall have direct and unfettered control over those OSE resources necessary for sate operation and maintenance ST. LUCIE PLANT, UNIT 1 & 2 SITE ORGANIZATION 03/18/98 of the plant.
FIGURE 14 The HP Supervisor shall have direct access to the PGM for matters relating to the APPENDIX A PAGE1 OF 1 Radiological Health and Safety of employees and the public.
igi igi
~ i
TOPICAL QUALITYASSURANCE REPORT Appendix B Rev: 5 Qualification and Experience Requirements for FPL Quality Assurance Personnel Date:06/12/90 TITLE EDUC 0 ND B C G 0 D Quality Managers(JB/PTN/PSL) Shall satisfy the following set of requirements:
Graduate of a four year accredited engineering or science college or university, plus seven years of industrial experience, including five (5) years in positions of leadership such as lead engineer, project engineer, audit team leader, etc. At least two (2) years of this five (5) years experience shall be nuclear power plant experience in the implementation of the Quality Assurance Program. Six (6) months of the two (2) years experience shall be obtained within a Quality Assurance organization. A masters degree in engineering or business management is considered equivalent to two (2) years of general industry experience.
The education and experience requirements should not be treated as absolute when similar training or an outstanding record will provide reasonable assurance that a person can perform the required tasks.
Procedure No: Appendix B Rev: 5 Page1 of1
i5
<Qi ik~
TOPICAL QUALITYASSURANCE REPORT Appendix C Rov: 15 Baseline Document Matrix Date:10/16/96 This topical report contains the program requirements for Florida Power & Light Company's Quality Assurance Program. The Quality Assurance'Program is described in detail in the Florida Power & Light Company Quality Assurance Manual.
The Regulatory Guides,.codes, and standards specifically listed in the matrix of this appendix'(on page 2) represent the baseline documents used in the preparation of FPL's QA Manual and this topical report.
These documents, therefore, provide the basis for the FPL QA Program, but they are not considered to be part of the QA Program unless specifically addressed in the applicable SAR, technical specifications, etc.
The-FPL Quality Assurance Program meets the requirements of the, documents referenced in this appendix. Any alternatives or clarifications made to the requirements contained in these documents are stated on pages subsequent to the second page of this appendix.
Procedure No: Appendix C Rev: 15 Page 1 of 14
DRAFT REFERENCE REV.
GOVERNMENT INDUSTRY ISSUED QQGUhKHI UBIETY .GEEHDBBR RBIK 10 CFR'PART,50, APPENDIX B 2/1 9/75 ANSI-N45.2 1971 10 CFR PART 50.55a ASME B8 PV Code Section III & XI Regulatory, Guide 1.8 Rev. 1 9n5 ANSI-N18.1 1971 ANSI/ANS 1978 3.'1'NSI-'N45.2 Regulatory Guide 1.28 enn2 1971
.Regulatory Guide 1.30 .8/1 1/72 ANSI-N45;2.4 1972 Regulatory Guide 1;33 Rev. 2 ANSI-N18.7 1976 Regulatory Guide 1.37 3/1 6/73 ANSI-N45.2.1 1973 Regulatory Guide 1.38 Rev. 2 5n7 ANSI-N45.2.2 1972
,Regulatory Guide 1.39 Rev. 2 9n7 1973 ANSI-N45.2.3'NSI-N45;2.6 Regulatory Guide 1.58,Rev. 1 9/80 1978 Regulatory, Guide 1.64'Rev. 2 6/76 ANSI-N45.2.11 1974 Regulatory Guide 1.74 ANSI-N45.2.10 1973 Regulatory Guide 1.88 Rev. 2 10/76 ANSI-N45.2.9t 1974 Regulatory Guide 1.94 Rev. 1 4ne ANSI-N45.2.5 1974 Regulatory Guide 1.116 ene ANSI-N45.2.8', 1975 Regulatory Guide 1.123 Rev; 1 7n7 ANSI-N45.2.13 1976 Regulatory Guide 1.144 Rev. 1 9/80 ANSI-'N45.2.12 1977 Regulatory Guide 1;146 8/80 ANSI-N45.2.23 1978 Specified in the document of'the respective plant.
Procedure No: Appendix C Rev:15 Page 2 of 14
ili ii i
Florida Power & Light Company position regarding conflicting guidance and exceptions:
S-The Regulatory Guides and industry standards listed in:Appendix C to the Topical Quality Assurance Report take precedence over any Regulatory Guide or industry standard which may be referenced in any one of these documents.
e Gui 18 v1AN 18 - 1AN IAN 1P ANSI N18.1 describes the training and education requirements for plant staff positions and is endorsed by. Reg. Guide 1.8 with an exception. That exception is the requirement for the Supervisor - Radiation Protection. ANSI N18.1 is invoked by Technical Specifications (Appendix A of the Facility Operating License) at the Turkey Point plants and PSL-1. ANSI/ANS 3.1-1978 is invoked by Technical Specification at PSL-2. Reg. Guide 1.8 is also invoked by Technical Specifications at our St. Lucie plant and a license amendment has been approved for our Turkey Point plant to specify the Health Physics Supervisor qualifications addressed in Reg. Guide 1.8.
To avoid duplication of requirements, FPL will address Plant Staff Qualifications in only the Technical Specifications.
i 1.30 N I N4 2 -1 ANSI N45.2.4-1972, Paragraph 2.3 addresses installation specifications and'requires the inclusion of inspection and test objectives. FPL maintains that test values and inspection scope are inherently contained in the applicable procedures.
ANSI N45.2.4-1972, Paragraph 6.1.2 requires that the inspection of installed equipment verify that "good and proper workmanship" has prevailed. FPL maintains that acceptable parameter compliance with codes and standards along with company preference is the verification of "good and proper workmanship'.
ANSI N45.2.4-1972, Paragraph 6.2.1 requires that "Items requiring calibration shall'be tagged or labeled on completion indicating date of calibration and identity of person that performed the calibration." In lieu of tagging or labeling equipment, FPL has chosen to control calibration of installed instrumentation and control equipment by maintaining records for each piece of equipment by instrument tag number (or equivalent) to show that established schedules and procedures for calibration have been followed.
G v N I N187-1 7 FPL's method of addressing Paragraphs 4.0, 5.2.2, 5.2.15 and 5.3 of ANSI 18.7-1976 as modified by
'Regulatory Guide 1.33, Rev. 2 is covered in Section 6 of each individual plant's Technical Specifications.
ANSI N18.7-1976, Section 4.3, requires that personnel performing the independent review and audit be specified in number and technical discipline. This standard is invoked by the Technical Specifications (Appendix A of the Facility Operating Licenses) which have been approved for the FPL nuclear plants at St. Lucie and Turkey Point. Specifically this function is performed by the Company Nuclear Review Board (CNRB) identified in Section 6.5.2 of the Technical Specifications.
To avoid duplication of requirements, FPL.will address the personnel and functions of this independent review and audit only in the Technical Specifications.
Procedure No: Appendix C Rev: 15 Page 3 of 14
FPL's method of addressing Section 5.2 of ANSI N18.7-1976, as modified by Regulatory Guide 1.33, Rev. 2, is by administratively controlling licensed operator hours on shift. FPL's Radiological Emergency Plan is a response to NUREG 0654 which provides staffing availability.
FPL's method of addressing Paragraph 5.2.8 of ANSI N18.7-1976, as modified by Regulatory Guide 1.33, Rev. 2, is covered in Section 4 of each plant's Technical Specifications.
FPL's method of addressing Paragraph 5.2.9 of ANSI N18.7-1976, as modified by Regulatory Guide 1.33, Rev. 2, is covered in 10 CFR 73 and each plant's Security Plan, and as such is not included in the Quality Assurance Program.
Chemical cleaning is not presently controlled as a special process per se; however, the requirements of ANSI N45.2.1-1 973 and Regulatory Guide 1.37 dated 3/16/73 are part of the FPL QA Program and are met in our program. FPL proposes these requirements to be an alternative to the requirements of ANSI N18.7-1976, Paragraph 5.2.18. Further, TQR 9.0, Paragraph 9.2 explains the review of potential special processes and determination of their status as special processes.
FPL meets the intent of Section 5.2.19.3 of ANSI N18.7-1976 as modified by Regulatory Guide 1.33, Rev. 2, as applied to significant changes to operating procedures, by the technical review of the procedure change by knowledgeable plant professionals, by the safety review of the procedure change by the on-site facility review group, by the regulatory and QA review of the procedure by the plant Quality Department, by training the licensed operators in the change through the training report system, and by trained, licensed operators using the revised operating procedure and observing the, proper result. In addition, procedure changes will be reviewed to assure 10 CFR 50.59 requirements are met.
Appendix A of Regulatory Guide 1.33 lists "typical safety related activities which should be covered by written procedures". Regulatory Guide 1.33 is invoked by the Technical Specifications at FPL Nuclear Plants.
In order to avoid duplication of requirements invoked in our licensing documents, the FPL Quality Assurance Program does not list those required operating procedures specified in Appendix A.
R I N I N4 ANSI N45.2.1-1973, Paragraph 5 states in part that, "Fitted and tackwelded joints (which will not be immediately sealed by welding) shall be wrapped with polyethylene or other non-halogenated plastic film until the welds can be completed". The FPL QA Manual shall require that the weld be covered to prevent entry. of moisture and contaminants but will not specify the material to be employed. Materials employed to cover openings shall meet the requirements of Regulatory Guide 1.37, Position 4.
ANSI N45.2.1-1973, Paragraph 7.1 states in part, "provisions shall be made to collect leakage and protect insulation from being wetted". FPL Quality Assurance Program includes the above requirements. However, FPL's program allows the wetting of metallic type insulations which are not adversely affected by wetting.
ANSI N45.2.1-1973, Paragraphs 7.2.2, 7.2.3, and 7.3 address specific cleaning methods (Alkaline, Chelate, Acid) and make recommendations associated with several types of cleaning methods. FPL's QA manual does not specifically delineate these paragraphs. However, the procedure developed per Paragraph 2.2 of ANSI N45.2.1- will ensure that any specific cleaning method chosen will be properly considered and controlled.
Procedure No: Appendix C Rev: 15 Page 4 of 14
FPL will meet the requirements of Reg. Guide 1.38, Rev. 2, Position 2C, D and E for safety related applications during preoperational and operational activities. Restrictions imposed for tapes to be color contrasting will only be applied'to the extent that these colors are dissimilar or otherwise distinguishable.
This does not preclude using other tapes when precautions are taken to ensure these tapes do not come in contact with austenitic stainless steel or nickel alloy materials.
Vapor barrier material (other than metal) shall be colored to contrast with or be otherwise distinguishable from safety related systems to prevent undisclosed entry into the system.
These requirements do not apply to components in storage which would require removal of such tapes and barriers to effect installation.
'NSI N45.2.2-1972 Section 2.7 requires that items governed by this standard be classified into one of four levels by the buyer or the contractor. FPL intends to consider what care is appropriate for each item individually rather than generically classifying the material into protection levels and providing care required of that level. The following shall be considered when determining the handling, storage, and
,shipping requirements:
- 1. The vendor's recommended handling, shipping, and storage standards.
- 2. Environmental requirements which may include such requirements as inert gas atmosphere, humidity limits, temperature limits, chemical, requirements, acceleration,(g force) requirements.
- 3. Special tools or equipment which are provided and controlled as necessary to ensure safe and adequate handling. These tools or equipment shall be inspected and tested at specified times to verify that they are adequately maintained.
- 4. Packaging, covering or coatings required to meet environmental requirements such as barrier and wrap material, desiccants,'ipe caps, plugs, contact preservatives, etc.
- 5. Container, crating, skids of sufficient strength to support the item (including stacking).
- 6. Cushioning, blocking, bracing, and anchoring to prevent movement during shipment or handling.
- 7. Special handling or storage procedures for unique situations.
- 8. Marking and identification of the item and its packaging.
- 9. Anticipated shelf life" of the item.
FPL considers this to be a more effective approach since the quantity of spare and'replacement material, parts and components governed by this standard will be afforded protection commensurate with the recommendations of Section 2.7 of this standard.
ANSI N45.2.2-1972 Sections 3.0, 4.0, and the Appendix address all the requirements applicable to the packaging and shipping of material. FPL in general does not package or ship material governed by this standard. Suppliers of material are required by purchase order to provide adequate packaging and shipping protection. Isolated cases of material packaging or shipping are treated on a case-by-case basis and receive protection comparable to that required by the manufacturer of that material. Loading, rigging and handling precautions identified in'Section 4.3 are applied to material unloaded by FPL from a transport vehicle.
Procedure No: Appendix C Rev: 15 Page 5 of 14
<Ii 4t
]I i
ANSI N45.2.2-1972 Section 5.2 requires that specific attributes of material and components received by FPL be inspected. For plants with operating licenses FPL verifies conformance to procurement documents during receipt inspections. Any of these attributes identified in these procurement documents are verified during this inspection.
ANSI N45.2.2-1972 Section 5.2, paragraph 5.2.1, requires certain preliminary inspections to be done "prior to unloading" of material which is received. We believe that the sequence specified in the standard is to facilitate commercial claims, and should these preliminary inspections occur "after unloading" that control of materials quality would not be degraded. Accordingly, required shipping damage inspections may be performed after unloading.
The requirements of ANSI N45.2.2, Paragraph 7.2 for items that require special handling, instructions is clarified by FPL to be limited to those items covered in the scope of NUREG 0612, entitled "Control of Heavy Loads at Nuclear Power Plants". IU ANSI N45.2.2-1972, Paragraph 7.4 requires that an inspection program be established for handling equipment and rigging, including methods for identifying acceptable and nonconforming items. In lieu of having a program of periodic, documented inspections of rigging and handling equipment, FPL's practice is to have the individual user determine the equipment's acceptability prior to each use. This prior-to-use inspection is exactly the same as that required during periodic inspections, and uses criteria identified in ANSI N45.2.2-1972, paragraph 7.4. This practice also precludes the need for a system to indicate the acceptability of rigging and handling equipment. Implementation of this prior-to-use inspection will be assured through periodic surveillances and audits performed by Quality Assurance and Quality Control. Cranes are inspected on a periodic basis and will not be subjected to this prior-to-use inspection.
Certain mechanical components of the PSL-2 nuclear unit have been designed for a service environment of the site area because portions of the plant are exposed to the temperature, humidity, and ocean salt spray during operations. Extreme air temperature variations, snow or slush are not encountered during operations or in the out-of-doors storage environment. As an alternative to the rigid requirements of storage levels B and C in paragraph 6.1 of ANSI N45:2.2-1972, FPL proposes to store these particular mechanical components outdoors, but within controlled areas, with sufficient periodic surveillances and inspections to minimize the possibility of damage or lowering of quality due to corrosion, contamination, deterioration, or physical damage. In cases where special environmental conditions are present (i.e., hurricanes, paint sprays, concrete pours, etc.) precautions or additional steps will be taken to further protect the items.
e 6 v. N IN4 2.-17 For FPL's operating nuclear plants, alternative methods are followed to achieve equivalent objectives for the below listed sections of ANSI N45.2.3-1973:
The zone designations of Section.2.1 of N45.2.3 and the requirements associated with each zone are not consistent with the FPL Housekeeping requirements at our operating nuclear units.
In lieu of the zone designation, cleanliness is. maintained at a level. consistent with the work being performed, so as to prevent the entry of foreign material into safety related systems. Documented cleanliness inspections are performed immediately prior to system closure. Control of personnel, tools, equipment, and supplies is established with approved procedures when the safety function of a system, component, or item may be jeopardized and also while the reactor system is opened for inspection, maintenance, or repair.
Procedure No: Appendix C Rev: 15 Page 6 of 14
vii N I ANSI N45.2.6-1 978, Paragraphs 1.1, 3.1, 3.2.2(a) and 4 (Table-1) identify requirements which apply to personnel who perform inspections, tests or nondestructive examinations or who participate in the approval of procedures, the handling of data or test results, or the control of reports and records.
FPL proposes an alternative to capability requirements for those who participate in: (1) the approval of procedures', (2) the handling of data or test results and (3) the control of reports and records. FPL accomplishes this by having personnel determined to be qualified and competent by management through consideration of education, training, and experience.
The Florida Power & Light Company position on the scope of ANSI N45.2.6-1978 is that personnel participating in testing who take data or make observations, where special training is not required to perform this function, need not be qualified in accordance with ANSI N45.2.6 but need only be trained to the extent necessary to perform the assigned function.
For leak testing conducted as part of the preoperational and operational testing programs, FPL considers that the qualification requirements of Regulatory Guide 1.8 (ANSI N18.1-1971) and ANSI N45.2.6-1978, Paragraph 3.0 to be an acceptable alternative to SNT-TC-1A-1 975 requirements for-leak testing, except for leak testing defined in and performed under the ASME Code, where in such cases, the appropriate section of the Code shall govern.
For preoperational and operational inspection, examination and testing by Quality Control Inspectors, FPL considers that Position C.1 of Regulatory Guide 1.58, Revision 1 and ANSI N45.2.6-1978, Paragraph 3.0 are acceptable requirements for training and qualification, except for inspections, tests and examinations defined in and performed under the ASME Code, where in such cases, the appropriate section of the Code shall govern.
For all other preoperational and operational inspection, examination and testing performed by operating plant and support personnel, FPL considers that training and qualification to the requirement of ANSI N18.1-1971 and Regulatory Guide 1.8 are sufficient for the type and scope of activities performed and that qualifications to ANSI N45.2.6-1978 is unnecessary and redundant. These preoperational and operational inspections, examinations and tests shall be supervised or directed by personnel qualified to Position C.1 of Regulatory Guide 1.58, Revision 1.
FPL shall comply with Position C.10 of Regulatory Guide 1.58, Revision 1, effective with Revision 4 of the Topical Quality Assurance Report, in that all new certifications issued for personnel shall meet the education and experience requirements or shall document objective evidence demonstrating that the individual indeed does have comparable or equivalent competence to that which would be gained from having the required education and experience.
FPL's position on ANSI N45.2.6-1978, Paragraph 2.3 is that an initial and periodic review (not to exceed two years) of personnel shall determine the capabilities in his qualified area. If during this review, or at any other time, it is determined that the individual's capabilities are not in accordance with the specified requirements, that individual shall be removed from that activity until the required capability has been demonstrated. In addition, during this. review a determination shall be made that an individual has been actively involved in the inspection process in his qualified area.
Procedure No: Appendix C Rev: 15 Page 7 of 14
tfp i5~
~i il~
la Guid 1 64 R v AN I'N4 11-1 FPL's exception to Regulatory Guide position C.2 is as follows:
Design verification shall be performed by technically qualified individual(s) or group(s) other than those who performed the design. The original designers and verifiers may both be from the design organization. Design verification by the designer's immediate supervisor shall be limited to those instances when the supervisor is the only qualified individual available within the design organization.
These instances are further restricted to designs where the supervisor did not specify a singular design approach, or did not restrict design methods or alternatives, or did not specify design inputs (unless the specified design inputs have already been independently verified). Justification for verification by the designer's immediate supervisor should be documented along with the extent of the supervisor's involvement in the design.
ANSI N45.2.11-1974, Paragraph 11.4 requires that "audits shall include an evaluation of design quality assurance policies, practices, procedures and instructions...." FPL's design quality assurance (and all other QA elements) policies, procedures and instructions are included in FPL's Quality Assurance Program documentation. The Quality Assurance Department evaluates all of this documentation in reviews performed during its development and revision. Accordingly, FPL does not require subsequent (and redundant) evaluations of these Quality Assurance Program policies, procedures and instructions during audits. FPL audits will include evaluations of the adequacy of the practices which are the implementation of these policies, procedures and instructions.
I i 1 11 Regulatory. Guide 1.68 (11/73) entitled "Preoperational and Initial Start-up Test Programs for Water Cooled Power Reactors" is addressed in Section 14;2.1 of the St. Lucie Unit 2 FSAR which states in part, "The start-up test program is developed using the recommendations of Regulatory Guide 1.68".
To avoid duplication of requirements, FPL will address Regulatory Guide 1.68 in the FSAR.
ANSI N45.2.10 - 1973 identifies terms and their definitions important to the uniform understanding of the intent of required quality assurance practices for the construction of nuclear power plants. Regulatory Guide 1.74 (2-74) endorses these terms and definitions and extends them through the operational phase and includes a clarification of procurement documents.
FPL has developed a glossary of terms and their definitions as part of the Quality Assurance Manual which is being used throughout its nuclear construction and operating plant activities.
The following definitions are currently listed in our glossary and are alternatives or clarifications to those listed in the ANSI Standard and Regulatory Guide:
Assembly A combination of subassemblies or components or both, fitted together to form a workable unit.
Audit A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective evidence, that applicable elements of the quality assurance program have been developed, documented and effectively implemented in accordance with specified requirements. An audit does not include surveillance or inspection for the purpose of process control or product acceptance.
Procedure No: Appendix C Rev:15 Page 8 of 14
~li Qi 0!
A
Guidelines Particular provisions which are considered good practice but which are not mandatory in programs intended to comply with Standards. The term "should" denotes a guideline; the term "shall" denotes a requirement;:and the word "may" denotes permission, neither a requirement nor a recommendation.
Inspector (Owner's or Installer's) A qualified inspector employed by the Owner or Installer, whose duties include the verification of quality related activities on installations.
Inspection Examination, observation, or measurement to determine the conformance of materials, supplies, components, parts, appurtenances, systems, processes, or structures to predetermined requirements.
Procurement Documents Purchase requisitions, purchase orders, drawings, contracts, specifications or instructions used to define requirements for purchase.
Qualification (Personnel) The characteristics or abilities gained through training or experience or both as measured against established requirements such as standards or tests that qualify an individual to perform a required function.
Quality Assurance All those planned and systematic actions necessary to provide adequate confidence that a structure, system or component will perform satisfactorily in service. Quality Assurance includes quality control.
Quality Control Those quality assurance actions related to the physical characteristics or material, structure, component or system, which provide a means to control the quality of the material, structure, component or system to predetermined requirements.
Storage That period following the. release of an item for shipment until turnover for start-up preoperational testing. This would include inplace storage.
System An integral part of a nuclear power plant comprised of electrical, electronic, or mechanical components (or combinations thereof) that may be operated as a separate entity to perform a specific function.
Testing Performance of those steps necessary to determine that systems or components function in accordance with predetermined specifications.
"R i m "Cl rii i A mandatory action, denoted by the word shall. (See "Guidelines" )
Requirements are generally based on statutes or regulations, but may be internally generated within the company. "Shall" is therefore used for both external, legally enforceable actions and internal requirements not enforceable under current NRC practices.
Procedure No: Appendix C Rev: 15 Page9of14
I 1 R v N N4 -1 ANSI N45.2.9-1974, Section 3.2.5 requires Quality Assurance Records be classified as lifetime or non-permanent and further defines lifetime and non-permanent in Section 2.2 of the Standard. FPL provides the following definitions as an alternative to the above.
Lifetime Records: Records which are required by the NRC facility operating license, the NRC construction permit, applicable parts of 10CFR, the FSAR, or other NRC commitments to be retained for the life of the plant.
Non-permanent Records: Records which are required by. the NRC facility operating license, the NRC construction permit, applicable parts of 10CFR, the FSAR, or other NRC commitments to be retained for periods of time less than the life of the plant.
ANSI N45.2.9-1974,, requirements for Section 5.6, "Facility", are clarified by FPL as follows:
QA Records shall be stored in a manner as to protect contents from possible destruction by causes such as fire, flooding, tornados, insects, rodents, and from possible deterioration by a combination of extreme variations in temperature and humidity conditions.
A QA Record Storage Evaluation Team (QARSET) shall be responsible for determining methods utilized to assure that QA Records are adequately stored and protected.
The QARSET shall consist of the following: the QA Supervisor Performance Assessment, a Risk Management Representative and the Records Official, who shall be responsible for maintaining records of evaluations and establishing schedules to assure that reevaluations are performed every two (2) years. If necessary, the QARSET may delegate appropriate designees to serve as team members.
As part of their responsibility, the QARSET shall evaluate the status of existing facilities and the adequacy of additional records facilities prior to the construction of a new facility or the conversion of existing structures. Preferably, such evaluations should be performed during the design phase.
ANSI N45.2.9-1974 will be utilized in the evaluation of potential record storage facilities. Section 5.6 "Facilities" is modified as follows and shall be the basis for QARSET approved QA Record Storage Facilities.
A 2-hour vault, meeting NFPA No. 232 without additional provisions.
2-hour rated fire resistant file room as defined in NFPA No. 232- 1980 if the following additional provisions are provided:
a; Early warning fire detection and automatic fire suppression shall be provided, with electronic supervision at a constantly monitored central station.
- b. Records shall be stored in fully enclosed metal cabinets. Records shall not be permitted on open steel shelving. No storage of records shall be permitted on the floor of the facility. Adequate access and aisle space shall be maintained at all times throughout the facility.
- c. Work not directly associated with records storage or retrieval shall be prohibited within the storage facility.
Procedure No: Appendix C Rev:15 Page 10 of 14
- d. Smoking, eating and drinking shall be prohibited throughout the records storage facility.
- e. Ventilation, temperature, and humidity control equipment shall be provided with approved fire dampers where they penetrate fire barriers.
- 3. Other conditions from the above may be approved by the QARSET if, in their judgement, the condition meets the established level of protection defined above.
There are two acceptable alternatives to the establishment of an approved QA Record storage facility:
- 1. The maintenance of duplicate QA Records stored in separate locations which are not subject to the same destructive force at the same time.
For temporary storage, the use of QARSET approved factory built record protection equipment, such as insulated record containers, fire-resistive safes, and insulated filing devices.
Where a specially constructed storage room is maintained to store the only copy of QA records, at least the following features should be considered in its construction:
(1) Reinforced concrete, concrete block, masonry, or equal construction.
(2) Concrete floor and roof with sufficient slope for drainage; if a floor drain is provided, a check valve (or equal) shall be included.
(3) Structure, doors, frames and hardware should be fire-rated with a recommended two hour minimum rating.
(4) Sealant applied over walls as a moisture or condensation barrier.
(5) Surface sealant on floor providing a hard-wear surface to minimize concrete dusting.
(6) Foundation sealant and provision for drainage.
(7) Forced-air circulation with filter system.
(8) Adequate fire detection and/or suppression system.
(9) .No pipes other than those providing fire protection to the storage facility are to be located within the facility.
I i 1 A ANSI N45.2.8-1975, Paragraph 2.3 requires that Measuring and Test Equipment (M&TE) used for inspection be identified on the Inspection Report. FPL may, as an option, employ a M&TE issue log which provides traceability between MBTE and the applicable inspections.
ANSI N45.2.8-1975, Paragraph 4.6 addresses care of items to the extent that temporary use of equipment or facilities to which the standard applies that are to'become part of the. completed project may be desirable.
Procedure No: Appendix C Rev: 15 Page 11 of 14
The following clarification applies to the above statement. For FPL.plants'in.the construction phase (to the point'of plant operation license) temporary use of equipment and facilities may be required according to need and/or situation. In this case, authorization for usage shall be provided along with all the documents, conditions, safeguards and evaluations to verify permanent plant equipment adequacy.
In the operations phase all equipment, including temporary equipment, is subject to identical controls to preclude adverse effects on safety and suitability for use.
I 8 i 1 N IN4 -1 ANSI N45.2.13-1976 Section 1.1 states that the extent to which the individual requirements of this standard will apply will depend upon the nature and scope of the work to be performed and the required quality of the items or services purchased. For commercial grade items, FPL has determined that certain aspects of the individual requirements of ANSI.N45.2.13 need not apply. The term commercial grade item is defined in the QA Manual Glossary. Commercial items are subject to varying degrees of control as indicated in quality instructions.
As a minimum, an evaluation is performed by qualified personnel to assure that the commercial item satisfies the necessary technical and quality requirements and the item is checked upon receipt to assure that the. item received was the one ordered, damage was not sustained during shipment, and documentation, if required, was received.
ANSI N45.2.13-1976 Section 3.3.(a) requires that procurement documents be reviewed prior to release for bid and contract award. The FPL Quality Assurance Program requires procurement document reviews prior to bid and contract award for all safety related purchases. A "Confirming Purchase Order" is an order which is initially placed verbally with the supplier and then later confirmed with a written Purchase Order. A "Confirming Purchase Order" is only used when time restraints would prohibit the issuance of a written purchase order. The following controls are provided in the FPL Quality Assurance Manual to assure that the intent of ANSI N45.2.13 is satisfied for "Confirming Purchase Orders".
(1) Prior to verbally placing the order, it must be verified that the intended supplier is on the FPL Quality Assurance Approved Supplier List.
(2) The verbally placed order must be promptly followed-up (confirmed) with a written procurement document which is subject to all reviews and approvals required for safety related purchases.
Section 8.2 of ANSI N45.2.13 identifies those nonconformances which shall be submitted to the Purchaser. Florida Power & Light's (FPL) position regarding the nonconformances to be reported is as follows. Suppliers (including NE's and Contractors) shall submit all nonconformances which consist of one or more of the following:
- 1) Technical or material requirements are violated.
- 2) Requirement in supplier documents which have been approved by the Purchaser is violated.
- 3) Nonconformances which would affect the quality of the item in regard to function of safety related features. In cases where the supplier cannot make this determination, they shall be submitted to the Purchaser for evaluation.
This policy assures that all nonconformances affecting safety related functions will be reviewed and approved by, FPL. In all cases, the supplier's documentation on nonconformances is available for FPL's review.
Procedure No: Appendix C Rev: 15 Page 12 of 14
ill ili
id 11 4 v1 N N4 2 Regulatory Guide 1.144,.Positions C.3 a8b, states in part that applicable elements of an organization's Quality Assurance Program should be audited at least annually or at least once within the life of the activity, whichever is shorter.
ANSI N18.7-1976/ANS-3.2, Paragraph 4.5 (endorsed by Regulatory Guide 1.33 Revision 2) states in part'Audits of selected aspects of operational phase activities shall be performed with a frequency commensurate with their safety significance, and in such a manner as to assure that an audit of safety related functions is completed within a period of two years.
FPL has chosen a two year cycle for auditing elements of-the. internal and on-site QA Program during the operation phase of plant life following initial fuel loading. FPL's position is that the two year cycle:
(1) allows more in-depth and meaningful audits in each regularly scheduled area, (2) permits more audits. of ongoing activities, and (3) in conjunction with the planning and scheduling requirement of TQR 18.0 provides for a comprehensive audit program. The audit frequency requirements of Regulatory Guide 1.144 will be followed during other plants'hases.
In the case of suppliers, an annual evaluation of quality performance history shall be performed to determine reaudit requirements. Reaudit requirements for suppliers shall be based on the quality performance, and the complexity and criticality of the equipment or service being procured.
ANSI N45.2.12, Paragraph 4.3.1 states: "A brief pre-audit conference shall be conducted at the audit site with cognizant organization management. The purpose of the conference shall be to confirm the audit scope, present the audit plan, introduce auditors, meet counterparts, discuss audit sequence and plans for the post-audit conference, and establish channels of communication." FPL will not require the pre-audit conference for audits of limited scope and of specific site activities conducted by the Construction and Operations Groups. This conference is omitted because. the day-to- day contact of the auditors and plant management, the awareness on the part of plant management that these audits are conducted without pre-audit conferences, and the limited scope of the audits meet the intent of a pre-audit conference.
ANSI Standard N45.2.12-1977, Paragraph 4.5.1: states'in part "The audited organization shall provide a follow-up report stating the corrective action taken and the date corrective action was completed". The FPL QA Program requires the QA Department to followup on all action taken by the audited department. This is documented on the corrective action followup form by the QA Department and closed by the QA Department instead of the audited department. This assures that all actions taken by the audited department are verified by the QA Department and that the QA Department concurs with the resolution. We feel that it is appropriate for this to be documented by the QA Department instead of the audited department.
Pl nnin I rifi io ANSI N45.2.4-1 972, Paragraph 2.1; ANSI N45.2.6-1973, Paragraph 2.1; ANSI N45.2.13-1976, Paragraph 7.2; ANSI N18.7-1 976/ANS 3-2, Paragraph 5.2.7.1; ANSI N45.2.8-1975, Paragraph 2.1 and Paragraph 2.2 include plans and/or planning as required.
Procedure No: Appendix C Rev:15 Page 13 of 14
~~+eas~~
4~
<g~
The terms plan and/or planning are included in FPL's'activities as indicated in':the following clarification:
,Planning is considered to be a management process or analytical tool used as an aid to help
,develop identification and/or development of program requirements, implementation activities, assignments and staffing, inspections, surveillances and,audits, controls and other activities to assure completeness of the requirements. Planning, as such, is not always documented nor addressed as an end item and is considered to be an integral "process" within the developed item.
Plans which are considered to be end type or output type documents have the term "plan" in the
.title, such as ISI Master Plan, Audit Plan, Start-up Plan, and others, which as such will reflect directly the requirement of these standards in the appropriate documents.
Plans which are not,considered to be end type or output type documents do not have the word plan in the title..However, certain procedures, instructions, flow charts, schedules and checklists may be considered to be plans reflecting planned actions which especially require step-by-step accomplishments. In these cases, the term plan may not appear, in the title but considered to be a plan only in the indirect sense and identified as a procedure or other document. FPL considers.
the above practice to be in compliance with the "plan" requirements of these standards.
Procedure No: Appendix C Rev:15 Page 14 of'14
-~MMMM~~
C ig) ili iki
TOPICAL QUALITYASSURANCE REPORT Appendix F Rev: 1 Topics To Be Addressed In Safety AnalysIs Reports Date:05/07N2 The FPL Topical Quality Assurance Report is the statement of Florida Power 5 Light Company Quality Assurance Program Requirements which do not vary with plant site. These stated requirements form a description of the FPL Quality Assurance Program which does not contain identification of the involvement of principal contractors such as the Architect/Engineer, Nuclear Steam Supply System vendor, or Constructor. The contractor involvement in the Program will be described in the plant Safety Analysis Report. In addition, other detailed aspects of the Quality Assurance Program vary from plant-to-plant or with plant site. These aspects will also be described in the plant SAR. The requirements of the FPL Quality Assurance Program shall apply to the nuclear safety related. structures, systems and components as defined in the applicable plant SAR.
Procedure No: Appendix F Rev: 1 Page 1 of 1
- 4~
iIi
'O~
Attachment to L-98-153 Page 1 of 17 Response to NRC Request for Additional Information to Turbine Building Exemption Request By letter L-97-181 dated July 31, 1997, Florida Power Sc Light (FPL) submitted a request for exemption from the requirements of Appendix R subsection III.G.2.a for electrical raceways in the open turbine building. The Nuclear Regulatory Commission (NRC) has requested additional information (RAI) via letter dated March 23, 1998, in order to complete the review. The specific questions and responses are itemized below.
NRC Question 2.a(1)
Describe the fire threat posed by a challenging fire involving the turbine building related to each major-in-situ combustible and what adverse affects these fires would have operationally on the plant. In addition, describe the post-fire safe shutdown functions that are in the 50-foot zones associated with each of these major-in-situ combustibles and, for cases where redundant post-fire safe shutdown functions are in the zone, describe which function willbe protected by 1-hour fire barrier system. On a drawing, show the general location and routings of each shutdown function in each of these zones of concern.
FPL Response 2.a(1)
The major in-situ combustibles located inside or in close proximity to the Unit 3 and 4 turbine buildings are as follows:
Unit 3 Main Transformer Unit 4 Main Transformer Unit 3 Startup Transformer Unit 4 Startup Transformer Unit 3 Auxiliary Transformer Unit 4 Auxiliary Transformer Unit 3 Turbine Lube Oil Reservoir Unit 4 Turbine Lube Oil Reservoir Unit 3 Turbine Lube Oil Transfer Skid Unit 4 Turbine Lube Oil Transfer Skid Unit 3 Hydrogen Seal Oil Skid Unit 4 Hydrogen Seal Oil Skid The loss of any of these components, with the exception of the Turbine Lube Oil Transfer skid, due to a fire is expected to result in a Turbine Trip/Reactor Trip. The components listed above are protected by existing fixed water spray systems, a containment structure and have control room annunciation. Due to the nature of the events which would lead to a fire in these components, it is expected that the component would sustain sufficient damage to preclude continued operation.
However, safe shutdown of the affected unit would commence immediately upon a unit trip. Based on the response of the installed fire suppression systems and the containment structure provided for each of these components, fire damage to the surrounding areas would be minimal. No other loss of safe shutdown equipment is anticipated considering the proposed upgrades. Thermo-Lag fire barriers upgraded for a 1-hour rating and augmented automatic sprinkler coverage are proposed for all post-fire safe shutdown circuits inside the turbine buildings within 50-feet of these major in-situ combustibles. The Control Room would immediately dispatch the Fire Brigade. As documented in the exemption request (refer to FPL letter L-97-181, dated July 31, 1997), the Fire Brigade response times have historically been 10 minutes or less, with the average being approximately 5 minutes. The combination of a fixed water spray system and containment at the source, the
.9807080062)'
0 Attachment to L-98-153 e Page 2 of 17 protection afforded by 1-hour rated fire barrier and automatic sprinklers as well as Fire Brigade response provides the necessary assurance that applicable post-fire safe shutdown circuits are protected.
As stated previously, a fire at the Turbine Lube Oil Transfer Skid would not be expected to result in an immediate unit trip. However, the equipment is provided with fixed water spray which annunciates in the Control Room and a containment structure. As discussed above, expected Fire Brigade response to the event would be timely. There are no post-fire safe shutdown circuits within 50 feet of the skids inside the turbine buildings. There are post-fire safe shutdown circuits at the 50 foot perimeter of the equipment envelope outside the turbine building. These circuits are protected by a 1-hour Thermo-Lag fire barrier, as discussed in the submittal for outdoor areas other than the turbine buildings, (refer to FPL letter L-96-318, dated December 12, 1996). With regard to the Lube Oil transfer skid, the circuits are as stated above at the perimeter of the envelope and shielded by plant equipment in the intervening area. Therefore, a fire at the Turbine Lube Oil Transfer skid poses little threat to safe shutdown of the units.
Furthermore, the protection scheme. proposed in the turbine building exemption request (refer,to FPL letter L-97-181, dated July 31, 1997) is appropriately augmented as, compared to the protection scheme proposed for major in-situ combustibles in other outdoor areas (refer to L-96-318, dated December 12, 1996). Post-fire safe shutdown circuits in the turbine buildings and within 50-feet of a.major in-situ combustible are protected by a 1-hour rated fire barrier and automatic sprinklers.
Post-fire safe shutdown circuits in other outdoor areas within 50-feet of a major in-situ combustible are protected by a 1-hour rated fire barrier. The enhancement of automatic sprinkler systems in the turbine buildings will add significant positive protection to the circuits and the fire area.
Post-.fire safe shutdown. functions required in each fire zone are listed in Table 1'. The general routing of these circuits include those fire zones shown on Figures 1 and 2, included herein. These figures are based:on those originally provided via FPL letter L-97-181, dated July 31, 1997 and are augmented to.show complete area coverage within the Steam Generator Feedwater Pump Room.
NRC Question 2.a(2)
Describe the fire threat posed by a challenging fire involving a turbine failure and resulting fire event and what adverse affects this fire would have operationally on the plant. In addition, describe the post-fire safe shutdown functions that are located, between column lines A and E,and between column lines E and J,. For the turbine building area between column lines A and E, if.redundant post-fire safe shutdown functions are located in this area describe which function will be protected by 1-hour fire barrier system and on a drawing show their general locations and routings within the area. For the turbine building area between column lines E and J ifredundant safe shutdown factions (sic) or trains are located in this area describe the functions protected'by 25-minute fire rated barriers and on a drawing show their general locations and routings within the area. %'ith respect to the proposed 20-foot separation scheme, for the turbine building area between column lines I: and Jdescribe the functions afforded the proposed spatial separation and on a drawing show their general locations and routings within the area.
Attachment to L-98-153 Page 3 of 17 FPL Response 2.a(2)
Any event resulting in.a loss of bearing integrity would result in a Turbine Trip from the event itself, i.e., overspeed, high vibration, eccentricity, etc., or the loss of bearing oil pressure. The resulting turbine trip would initiate a Reactor Trip. A pool fire, as described in FPL's exemption request, would manifest itself in the area beneath the generator and/or the Condensate Pump Pit.
This area is essentially within the bounds of column lines A to E in the turbine buildings. FPL's proposed protection is to provide upgraded 1-hour rated Thermo-Lag fire barriers for post-fire safe shutdown circuits between column lines A and E and the Condensate Pump Pit and augment the automatic sprinklers in-the areas subjected to the postulated fire. The area of the Condensate Pump Pit where the oil can accumulate is covered by checker plate flooring (refer to'figure 3). There are existing automatic sprinklers beneath the flooring. Automatic sprinklers are also provided at the post-fire safe shutdown circuits. The, result of this arrangement is to provide 1-hour rated fire barriers and full automatic sprinkler coverage-to all protected circuits directly influenced by the fire and automatic sprinklers at the accumulation point in the Condensate Pump Pit. Based on discussions with the NRC Staff, the proposed 1-hour rated fire barriers will be upgraded using Thermo-Lag 770-1. Thermo-Lag 770-1 material provides improved structural performance over Thermo-Lag 330-1 and is therefore a preferable material. This level of protection is essentially as required by Appendix R, subsection III.G.2.c, except for detection.
Detection in. this case would provide little added protection based on the, physical surroundings and the initiating event. With the turbine buildings'pen structure, smoke detection would not be a reliable means of detection. Thermal detection would provide little, ifany, advanced warning to the initiation of the automatic sprinkler. Activation of the automatic sprinklers would be evident via local alarms or fire pump start, which is. annunciated in the Control Room. As stated previously,.the hydrogen seal oil skid and the auxiliary transformer are protected by fixed water spray systems with annunciation in the Control Room. Available turbine annunciation would first alert the Control Room to the initiation of the event, whether from vibration, overspeed or loss of oil. The ControlRoomwouldimmediatelydispatchanOperator(s) to the turbinebuilding. The Operators on the scene would provide an immediate assessment of the conditions within the building and aid in the deployment of the Fire Brigade.
NRC Staff raised an additional concern for post-fire safe shutdown circuits which may be in the path of the lube oil below the operating deck. To address this concern, FPL will provide "drip shields" in order to ensure oil does not directly impinge on the. protected. circuits. The drip shields will consist of sheet steel over the upgraded fire barriers.
The exemption request describes the proposed protection for post-fire. safe shutdown circuits between column lines E and J to be an upgraded 25-minute rated Thermo-Lag fire barrier and automatic sprinklers. During a public meeting between the NRC Staff and FPL personnel on May 26, 1998, the NRC Staff expressed a concern over the sharp transition from 1-hour rated fire barriers to 25-minute rated fire barriers at column line E. To address that concern, FPL proposes to revise the protection scheme via this RAI response. For those post-fire safe shutdown circuits 0 located above the Condensate Pump Pit, up to the underside of the 42'levation operating deck, the fire barriers provided will be rated for 1-hour. The 1-hour rated fire barriers will be upgraded using Thermo-Lag 770-1 material. The. revised protection will:result in 1-hour rated fire barriers until a distance of over 20 feet is obtained from the postulated pool fire at the 18'levation and a distance
Attachment to L-98-153 Page 4 of 17 of approximately 9- /m feet from the edge of the checker plate flooring above the Condensate Pump Pit. 'For those areas where the Condensate Pump Pit extends to the east, the 1- hour rated fire barriers will follow the outline of the pit, augmenting the distances referenced above. The remainder of the post-fire safe shutdown circuits between column lines E and J will be protected by 25-minute rated fire barriers. Refer to Figures 4 and 5 for details of the revised scope of coverage.
The addition of a transition zone with 1-hour rated fire barriers willprovide additional assurance the post-fire safe shutdown circuits remain free of fire damage.
'hat Post-fire safe shutdown circuits.'between column lines J and J, are provided with an upgraded 25-minute rated Thermo-Lag fire barrier. Although only approximately 34-feet from column line D, this area is outside the turbine building structure and open to the atmosphere. Suppression is provided at the source of the fire.and additional'suppression is provided in the intervening space between column lines E and J to provide cooling. With the combination. of suppression and an essentially. infinite heat sink (outdoor area), a 25-minute rated Thermo-Lag fire barrier provides the necessary assurance that the circuits will remain free from fire damage.
With:regard to spatial separation,.FPL will not credit spatial separation within column lines A to E.
Evaluation of those areas east of column line E is still underway. Therefore, no details as to the routing of redundant circuits is'available at this time. FPL willprovide those details at a later date should it determine that separation is a viable alternative for any post-fire safe shutdown circuits between column, lines E and J,.
Based on proposed post-fire safe shutdown circuits protection and expected Control Room and Fire Brigade response, the fire protection features provided for a challenging fire involving a turbine failure provide the necessary assurance that the essential circuits are protected and that essential equipment will be available for post-fire safe shutdown.
Post-fire safe shutdown functions required for the. area from column lines A to E are listed in Table
- 1. Post-fire, safe shutdown functions required for the. area from column lines E to J, are listed in Table 2. The general routing of these circuits included in these fire zones is shown on Figures 1 and 2 included with the Attachment to FPL letter L-97-181, dated July 31, 1997.
NRC Question 2.a(3)
For a turbine fire event, certain areas between column lines A and E.could be significantly challenged by a lube oil fire and within this area. Post-fire safe shutdown functions will be protected by 1-hour rated ERFBS and could be subject to direct flame impingement and engulfment. Within the area of concern identify the raceway protected by a 1-hour rated ERFBS which could potentially be engulfed or impinged by the fire. In addition, it is the staff's-understanding that the current ERFBSs in this area of concern willbe upgraded to,1-hour designs which were subjected to ASTM E-119 standard time-temperature curve conditions for 1-hour. The fire exposure represented by the ASTM E-119 time temperature
~ ~
~
curve does not bound the potential fire exposure conditions resulting from
~
flammable/combustible liquid fires. ASTM E-1529 time temperature curve is, generally used
~ ~ ~
~
to bound these types of fire exposures. In the area of concern, l.e., where the potential exists,
~
for an ERFBS to be subject to fire engulfment or flame impingement, provide an evaluation
~
0 Attachment to L-98-153 Page 5 of 17 which assesses the fire resistive performance of the proposed fire barrier design when exposed to the ASTM E-1529 time-temperature environmental conditions.
FPL Response 2.a(3)
ASTM E-1529, "Standard Test Methods for Determining Effects of Large Hydrocarbon Pool Fires on Structural Members and Assemblies," is intended to provide a test, methodology for fire conditions resulting from large, free-burning, fluid-hydrocarbon-fueled pool fires. This type of fire results in high heat flux and temperature conditions that are rapidly achieved. The proposed fire barrier is rated at 1-hour based on ASTM E-119.
The objective of ASTM E-1529 was reviewed in comparison with the postulated fire described in the exemption request. The presumption in ASTM E-1529 is that objects are exposed to a large heat flux in a relatively short period of time. Hence, the time-temperature curve requires at least 1500 'F aAer the first 3 minutes of the test and between 1850 'F and 2150 'F aAer the first 5 minutes of the test. While this may be representative of the development of a large hydrocarbon pool fire in a refinery or other processing facility, it is not representative of the postulated hazard in the Turkey Point turbine buildings.
As noted in the exemption request (refer to page 50 of the Attachment to L-97-181, dated July 31, 1997), Factory Mutual Research Corporation (FMRC) performed sprinkler discharge testing over lubricating oil fires for the Atomic Energy Commission (AEC), "Fire Tests of Automatic Sprinkler Protection for Oil Spill Fires," (September 9, 1957). The oil used was more volatile than the lube oil used at Turkey Point. Additionally, the oil and floor were preheated to approximately 165 'F and 130 'F, respectively. Lubricating oil is a combustible but not flammable liquid. In all cases the oil was difficultto ignite, slow to spread and required the use of accelerants. ("Slow" is used in the comparative context as opposed to flammable liquids which would be fast, i.e. minutes versus seconds). Conversely, in the absence of accelerants but assuming immediate ignition from the generator hydrogen, it can be presumed that the development of the fire will require a short but finite period of time. This alone is not consistent with the hazard as described in ASTM E-1529, where the test method is to "get hotter faster" than ASTM E-119.
The time required for the fire to propagate should also be coupled with the time required for the lube oil to leak from the bearings and eventually collect and form the pool. As evidenced by the FMRC testing, sprinkler actuation will occur long before the formation of a pool of substantial size.
By combining these elements, it is reasonable to conclude that a fire as postulated in the turbine building is slower to develop and better represented by the time-temperature curves of ASTM E-119.
Another aspect of the testing is the uniformity achieved by adherence to a given standard. Both ASTM E-119 and ASTM E-1529 are laboratory tests which provide a controlled environment with which to measure response to a given input. In actuality, the response of the automatic sprinkler system will result in actual conditions which are far less severe than either test. This is consistent with the philosophy of Appendix R, which was repeated in NRC Generic Letter 86-10, Supplement 1, that the fire barrier protection should be selected considering the other fire protection features available. Therefore, ifthe response to the suppression system is considered, the two tests provide very similar assurances for the acceptability of the materials, construction and craftsmanship
Attachment to L-98-153 Page 6 of 17 required to construct a qualified assembly.
Based on the above;
~ ASTM E-1529 need not be considered for the postulated pool fire as evidenced by the results of the industry testing and the time interval required for the formation of the pool,
~ suppression should be considered acting in conjunction with a 1-hour rated fire barrier, as implied by Appendix R and stated within NRC Generic Letter 86-10, Supplement 1, and
~ both ASTM E-1529 and ASTM E-119 provide assurance that the materials, construction and craftsmanship are adequate to construct a quality fire barrier.
NRC Question 2.b National Fire Protection Association (NFPA) Standard 850, "Fire Protection for Fossil Fueled Steam and Combustion Turbine Electric Generating Plants," 1992, recommends a minimum level of fire protection for turbine-generators and its systems. Specifically this standard recommends the use of water suppression systems, specifies the level of protection needed for the hazards and the building and specifies suppression system performance criteria. Using this standard, perform an evaluation which compares the Turkey Point Units 3 and 4 turbine e fire protection features (provided and proposed) against those recommended by NFPA 850.
This evaluation should identify and describe avhere the Turkey Point Units 3 and 4 turbine fire protection features deviate from the criteria specified by the standard and the appropriate justification for these deviations.
FPL Response 2.b NFPA 850, "Recommended Practice for Fire Protection for Electric Generating Plants," 1992 provides guidance for the protection of the turbine-generator and its auxiliaries, as well as addressing many other types of equipment associated with combustion turbines and resource recovery facilities. This guidance will help mitigate damage to equipment and structures as the result of a fire event. Many of the recommendations of NFPA 850 are in place in the Turkey Point turbine buildings and the proposed modifications serve to enhance those protection features.
However, the proposed turbine building fire protection modifications are designed with the purpose of providing additional protection to post-fire safe shutdown circuits and the turbine building structure, not for the protection of the turbine generator and its auxiliaries. The turbine-generator and its auxiliaries are not required for post-fire safe shutdown and therefore, protection of the turbine-generator and its auxiliaries is a commercial issue. The existing fire protection features in conjunction with the prescribed preventive maintenance and the assessed low risk of such an event satisfies the requirements of FPL's insurance underwriter.
This issue was further discussed during the previously referenced public meeting between the NRC Staff and FPL personnel on May 26, 1998. At that time the NRC Staff indicated that the intent of the question was to prompt consideration of such additional fire protection features as additional suppression under the turbine-generator skirt and location of openings on the turbine operating deck and the use of curbs.
Attachment to L-98-153 Page 7 of 17 FPL has reviewed'these items and concluded that no additional measures are required. Only branch lines enclosed in guard pipe and'instrument sensing lines extend under the turbine-generator skirt. The distribution piping is below the operating deck and is currently protected by automatic sprinklers. All pipe sleeves through the operating deck extend approximately 3"- 4" above the concrete deck. Only the main steam piping penetrations at the turbine front standard are within the deck drains on the operating deck. Oil leakage is not postulated to occur in the area of the front standard. Large openings in the deck underneath, the Moisture Separator Reheaters are outside the turbine deck drains. Although not curbed completely, these openings are in excess of 20 feet from the turbine centerline and not located in the vertical plane of the bearings. Also, should lubricating oil still migrate to this area, it would drain onto the condenser shell and ultimately to the pit. The east side of the condenser shell is within the proposed sprinkler coverage. The west side of the condenser does not pose a threat to the post-fire safe shutdown circuits.
Turkey Point Units 3 and 4 have not committed to the recommendations of NFPA 850, "Recommended Practice for Fire Protection for Electric Generating Plants," 1992. Also, the scope of NFPA 850 specifically excepts nuclear power plants referring to NFPA 803, "Standard for Fire Protection for Light Water Reactors Nuclear Power Plants," which would also indicate that an evaluation of the recommendations of NFPA 850 is'not applicable.
Based on the above, an evaluation-of the Turkey Point Units 3 and 4 turbine fire protection features with regard to the recommendations of NFPA 850 is not provided.
NRC Question 2.c Generally, sprinkler systems are used for fire control and not normally designed for the extinguishment of oil fires., In order to extinguish a fully developed'oil fire with water, a properly designed water spray system with open head nozzles is needed. The system design needs to consider energy output from the burning fuel and its configuration when burning.
The burning characteristics dictate the distance the nozzle can be located from the hazard, the spacing between the nozzles, the required velocity of the water spray and the rate of discharge from each systems nozzle. FPL in their supporting analysis for the exemption references a Factory Mutual Research Corporation Report, "Fire Tests of Automatic Sprinkler Protection for Oil Spill Fires,"'dated September 9, 1957, and summarized the observations made by this report. This summary suggests that sprinklers would be effective at. controlling the hot gas layer of an oil spill fire. The staff would like to review this report in detail in order to understand the insights and its applicability to fire conditions resulting from a turbine, failure event. The NRC staff requests that the referenced report and other referenced reports (e.g., V. Babrauskas, "Temperatures in Flames and Fires," May 1997) be provided to support its for review of the exemption request.
FPL Response 2.c FPL concurs that the use of fixed water spray is appropriate for transformers, storage tanks, etc.
However,.NFPA 803 recommends that areas beneath the turbine operating deck where oil can spread should be, protected by automatic sprinklers or pre-action sprinklers. The testing conducted by FMRC, referenced earlier, demonstrates the effectiveness of this type of protection.
Attachment to L-98-153 Page 8 of 17 With regard to the requested documents, the following reference materials are provided with this response to assist in your review:
Factory Mutual Research Corporation, "Fire Tests of Automatic Sprinkler Protection for Oil Spill, Fires, September 9, 1957
- 2) Babrauskas, V. "Temperatures in Flames and Fires," May 1997
- 3) Alpert, R. L., "Calculation of Response Time of Ceiling Mounted Fire Detectors," Fire Technology, 1972
- 4) Evans, D. D. and Stroup, D. W., "Methods to Calculate the Response Time of Heat and
, Smoke Detectors Installed Below Large Unobstructed Ceilings," Fire Technology, 1986
- 5) Mower, F. W., "Lag Times Associated With Fire Detection and Suppression," Fire Technology, August 1990 NRC Question 2.d(1)
From its review, the NRC staff is concerned that the fire predictions made by FPL may not be conservative and that the general reduction of heat release from a fire by the combination of factors noted in the submittal is not a recognized modeling practice. In order to understand the fire conditions bounded by the FPL fire predictions, provide the supporting assumptions and their technical basis, the fire prediction calculations, a summary of the
~ ~ ~ ~
~ ~
uncertainties associated with these fire predictions, and any experimental data which would
~ ~ ~ ~ ~ ~
~
provide validation for these predictions. In addition, provide your technical basis for the
~ ~ ~ ~ ~ ~ ~
~
,assumption that.a five man fire brigade is capable of applying sufficient water from manual
~ ~ ~
hose lines (i.e., within 5 minutes) to be effective in the control and extinguishment of a significant turbine building fire.
FPL Response 2.d(1)
An abridged version of the fire hazard analyses is included in Section V of the Attachment to FPL letter L-97-181, entitled, "Supplemental Evaluations." A complete copy, of the fire hazard analyses is provided for your review. The assumptions and their bases are documented within the analyses.
As noted earlier, referenced periodicals are also provided per your request. FPL would like to re-emphasize that the exemption request as submitted is capable of standing on its own merit. The fire hazard analyses is not required as justification for the exemption request and serves only as supplemental information.
The 5 minutes for the initiation of manual fire fighting is based on the average response times by the fire brigade members during training and actual fire events. Refer to Section V.I of the Attachment to L-97-181 for a list of fire brigade response/control times for fires during the period of 1989-July 1997. The reference to the 5-minute response'time does not imply that control or extinguishment of the fire would occur in five minutes, but merely that the fire brigade responds in five minutes on average and that manual fire fighting efforts would be underway in that time frame.
e During the NRC Staff/FPL public meeting of May 26, 1998, some additional questions about fire brigade training with regard to oil fires were posed by the NRC Staff. In response, the Fire Brigade annual training previously required training for a liquid pit fire. Changes in environmental
Attachment to L-98-153 Page 9 of 17 regulations no longer allow the use of liquids. Current training techniques are to simulate the hazard using gas.
In addition.to annual offsite training, the Fire Brigade conducts site specific training exercises during the course of the year. The Fire Protection Department is currently developing a Fire Brigade training exercise to address the postulated fire event described in the exemption request.
NRC Question 2.d(2)
Based on the predicted ceiling jet temperatures predicted it appears',that the area of sprinkler actuation may be underestimated and that the actual water demand'may be greater than estimated. Provide the analysis supporting the 0.3 gpm/3000 square foot area design for the general area sprinklers provided in the turbine building. In addition, based on FPL fire predictions, the fire could cause sprinkler actuation on multiple levels of the turbine building (elevation 30'-0", hydrogen seal'oil unit, auxiliary transformer, condenser pit). Provide the water supply analysis >vhich demonstrates that the fire water system has sufficient capability and capacity to supply fire fighting water to the fire systems and to hose lines for manual fire fighting.
FPL Response 2.d(2)
The original design density of the existing automatic sprinkler system was to provide 0.3 gpm/
3,000 square feet. One of the proposed modifications contained in the exemption request is that the area of coverage will be increased to 5,000 square feet. This is sufficient to provide. coverage to essentially the. entire area underneath the generator, which is open from the ground floor elevation to the underside of the operating deck, and the Condensate Pump Pit. Therefore, the design considers actuation of sprinkler heads throughout the entire postulated fire area, including multiple elevations.
Preliminary capacity calculations (the. final design will not be complete before the end of June 1998) assume a sprinkler density of 0.25 gpm over 5;000 square feet for:a total flow,of 1,250 gpm, which meets NFPA 13 requirements. Design flows for the fixed water spray systems are approximately 100 gpm for the hydrogen seal oil skid and 389 gpm for the auxiliary transformer.
Combining these flows with an additional.500 gpm for hose streams totals 2,239'gpm. Based on a degraded pump curve, the output of the smaller of the two fire pumps is 2,390 gpm. Therefore, adequate capability exists. The capacity required should be sufficient to supply the demand for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Therefore, at 2,239 gpm for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> a total of 268,680 gallons is required. A dedicated capacity of 300,000 gallons is available. Therefore, sufficient capacity exists for the proposed system.
NRC Question 2.d(3),.
The temperatures predicted may not be conservative and bounding. The uncertainties associated >vith these fire predictions and their predicted temperatures may have led to under estimations of the resulting conditions. These temperatures may not be conservatively
Attachment to L-98-153 Page 10 of 17 bounding. The current predictions indicate a concern that temperatures may exceed the
~
~
operability threshold of plant equipment in the area of fire concern. For those safe shutdown
~ ~
functions not protected by ERFBS between column lines E and J, and that can be affected by direct and'indirect fire damage (e.g., ceiling jet temperatures, radiant energy, and smoke),
provide the engineering analysis that demonstrates sufficient fire protection defense-in-depth diversity is factored in the;overall fire protection design such that one train of shutdown capability >vill remain functional.
FPL.Response 2.d(3)
Currently, post-fire safe shutdown, circuits between column lines E and J, are to be protected by a 25-minute rated Thermo-Lag fire barrier. FPL has not yet completed the analysis to determine whether any circuits do not require protection. When FPL has completed its evaluation of the areas east of column line E, the requested information will be provided for any, circuits which are currently protected, but which FPL has evaluated as not requiring protection.
iti nal a n R P Pu li e tin f a 2 Compensatory measures When removing any fire protection equipment out of service, a comprehensive review is conducted to determine the appropriate compensatory measures, as required by plant procedure 0-ADM-016.3, "Fire Protection Impairments", and O-ADM-016, "Fire Protection Program." Based on the specific situation, compensatory measures may include additional fire watches, the staging of temporary fire fighting equipment, specific instructions for the fire brigade and/or Control Room briefings for Operations personnel. Also, another objective of pre-job planning is to minimize equipment out of service time. The combination of these features provides adequate assurance that sufficient compensatory measures are provided.
0
~O
Attachment to L-98-153 Page 11 of 17 Table 1 Turkey Point Units 3 and 4 Protected Post-Fire Safe Shutdown Circuits Column Lines A to E Fire Zones Safe Shutdown Function Fire Zone 80 Unit 4 AFW Flow Control Valves Fire Zone 80 Unit 4 SG Level Instrumentation Wide Ran e Fire Zone 80 Unit 4 Train B Cold Le Tem erature Instrumentation Fire Zone 80 Unit 4 Train B Hot Le Tem erature Instrumentation Fire Zone 80 Unit 4 RCS Pressure Instrumentation Fire Zone 80 Unit 4 SG Blowdown Flow Control Valves Fire Zone 80 Unit 4 Instrument Air Containment Isolation Valve Fire Zone 80 Unit 4 AFW Turbine Steam Valve Control Fire Zone 80 Unit 4 AFW to SG Control Valve Power Fire Zone 80 Unit 4 Main Steam Isolation Valves Control Fire Zone 80 NCC Fan 4D ammeter Fire Zone 80 NCC Fan 4D Control Fire Zone 80 NCC Fan 4D Power Fire Zone 80 NCC Fan 4D, 4B Dam er Control Fire Zone 80 Auxilia Transformer Breaker Control 4KV Bus 4B Fire Zone 80 Start U Transformer Breaker Control 4KV Bus 4B Fire Zone 80 Heater Drain Pum 4B Fire Zone 80 Unit 4 125 VDC for Feedwater B ass Valve Fire Zone 80 4160 V Bus 4B Lockout Fire Zone 82 NCC Fan 4D ammeter Fire Zone 82 ote 1 NCC Fans 4D, 4B Control Fire Zone 82 NCC Fan 4D Power Fire Zone 82 NCC Fan 4D, 4B Dam er Control Fire Zone 82 Auxilia Transformer Breaker Control 4KV Bus 4B Fire Zone 85 MCC 3K Power Feeder Fire Zone 91 Unit 4 AFW Flow Control Valves Fire Zone 91 ote 2 Unit 4 SG Level Instrumentation Wide Ran e Fire Zone 91 Unit 4 Train B Cold Le Tem erature Instrumentation Fire Zone 91 Unit 4 Train B Hot Le Tem erature Instrumentation Fire Zone 91 Unit 4 RCS Pressure Instrumentation Fire Zone 91 Unit 4 SG Blowdown Flow Control Valves Fire Zone 91 Unit 4 Instrument Air Containment Isolation Valve Fire Zone 91 Unit 4 AFW Turbine Steam Valve Control Fire Zone 91 Unit 4 AFW to SG Control Valve Power Fire Zone 91 Unit 4 Main Steam Isolation Valves Control
~O Cl
Attachment to L-98-153 Page 12 of 17 Table 1 Turkey Point Units 3 and 4 Protected'Post-Fire Safe Shutdown Circuits Column Lines A to E
'Fire Zones Safe Shutdown Function Fire Zone 91 NCC Fan 4D ammeter Fire Zone 91 NCC Fan 4D Control Fire Zone 91 NCC Fan 4D Power Fire Zone 91 NCC Fans 4D, 4B Dam er Control Fire Zone 91 Auxilia Transformer Breaker Control 4KV Bus 4B Fire Zone 91 Start U Transformer Breaker Control 4KV Bus 4B Fire Zone 91 Heater Drain Pum 4B Fire Zone 91 Unit 4 125 VDC for Feedwater B ass Valve Fire Zone 91 4160 V Bus 4B Lockout Fire Zone 92 120V AC to 3B Load Se uencer Fire Zone 92 MCC 3K Power Feeder Notes:
- 1) Manual actions used for adverse fire affects to certain circuits of NCC Fans 4B and 4D.
- 2) Narrow range instrumentation used for adverse fire affects to certain circuits.
0 Attachment to L-98-153 Page 13 of 17 Table 2 Turkey Point Units 3 and 4 Protected Post-Fire Safe Shutdown Circuits Column Lines E to J, Fire Zones Safe Shutdown Function Fire Zone 79 125 VDC to Condensate and Feedwater Valves Fire Zone 79 ote 1 Unit 4 AFW Flow Control Valves Control Fire Zone 79 Unit 4 AFW to SG Control Valve Power & Control Fire Zone 79 Unit 4 Feedwater B ass Control Valve Fire Zone 79 ote 1 AFW Turbine Driven Pum Steam Su 1 Valve Control Fire Zone 79 AFW Turbine Tri & Throttle Valve Control Fire Zone 79 125 VDC for Feedwater B ass Control Valves Fire Zone 79 ote 2 CCWPum 4C Control Fire Zone 79 NCC Fan 4D Dam er Control Fire Zone 79 ote 2 NCC Fan 4D Control Fire Zone 79 NCC Fan 4D Power Fire Zone 79 NCC Fan 4D Ammeter Fire Zone 79 DC Inverter Room HVAC E16F Fire Zone 79 MCC 4K Power Feeder Fire Zone 79 4160V Bus 4B Lock Out Rela Fire Zone 79 4160V Bus 4B Clearin Circuit Fire Zone 79 Auxilia Transformer Breaker Control 4160 V 4B Fire Zone 79 EDG 3B, 4B Breaker Control Fire Zone 79 Heater Drain Pum 4B Fire Zone 79 SBO Tie Breaker Contxol Fire Zone 79 4160V Bus 4D-4B ali nment si nal to Load Se uencer 4B Fire Zone 79 ote 3 Unit 4 SG Level Instrumentation Wide Ran e Fire Zone 79 Unit 4 RCS Pressure Instrumentation Fire Zone 79 Unit 4 Train B Hot Le Tem erature Fire Zone 79 Unit 4 Train B Cold Le Tem erature Fire Zone 79 125 VDC for 480 V Loadcenter 4B, 4H Fire Zone 79 120VAC to Load Se uencer 4B Fire Zone 79 Alternate 125 VDC to 4160V Bus 4B Fire Zone 79 Unit 4 Main Steam Isolation Valve Control Fire Zone 79 Pressure Relief Isolation Valve MOV-4-535 Power Fire Zone 79 Unit 4 CCW Thermal Barrier Su I Isolation Valve Control Fire Zone 79 Normal 125VDC to 4160V Bus 4B Fire Zone 79 ote 2 125VDC to 480V Loadcenter 4D Fire Zone 79 Unit 4 Start-u Transformer Breaker Control
f, Attachment to L-98-153 Page 14 of 17 Table 2 Turkey Point Units 3 and 4 Protected Post-Fire Safe Shutdown Circuits Column Lines E to J, Fire Zones Safe Shutdown Function Fire Zone 79 125'VDC to Load Se uencer 4B Fire Zone 79 EDG 4B Control Fire Zone 79 Breaker Control - Bus 4B-4D Tie Fire Zone 79 ote 2 Intake Coolin Water Pum 4C'Control Fire Zone 79 CCW-to Unit 4 NCC Return Isolation Valve Power Fire Zone 84 Unit 3 Feedwater B ass Control Valve Fire Zone 84 ote 1 AFW Turbine Tri 8~, Throttle Valve Control Fire Zone 84 NCC Fan 3B, 3D Dam er Control Fire Zone 84 NCC Fan 3B, 3D Control Fire'Zone 84 NCC Fan 3B Power Fire Zone 84 NCC Fan 3B Ammeter Fire Zone 84 MCC 4K Power Feeder Fire Zone 84 4160V Bus 4B Clearin Circuit Fire Zone 84 EDG 3B, 4B Breaker Control Fire Zone 84 SBO Tie Breaker Control Fire Zone 84 4160V Bus 4D -4B ali nment si nal to Load Se uencer 4B
. FireZone84 RCS Pressure Instrumentation Fire Zone 84 Unit 3 Train B. Hot Le Tem erature Fire Zone 84 Unit 3 Train B Cold Le Tem erature Fire Zone 84 125 VDC for 480'V Loadcenter 3D, 3B
. Fire Zone 84 120VAC to Load Se uencer 3B,:4B Fire Zone 84 Alternate 125 VDC to 4160V Bus 4B Fire Zone 84 Unit 3 Main Steam Isolation Valve Control Fire Zone 84 ote 1 AFW to SG Control Valve Fire Zone 84 ote 2 Com onent Coolin Water Pum 4C Breaker Control Fire Zone 84 Unit 3 CCW Thermal Barrier Su 1 Isolation Valve Control Fire Zone 84 Char in .Pum 3B Control Fire Zone 84 Normal 125 VDC to 4160V Bus'3B, 4B Fire Zone 84 125 VDC to 4160 Bus 4D,3D Fire Zone 84 ote 2 Boric Acid Transfer Pum 3B Control Fire, Zone'84 Boric Acid Transfer Pum 3B Power Fire Zone 84 .Unit3 Loo C Hot Le Char in Isolation Valve Control Fire Zone 84 Unit 3 Excess Letdown Isolation Valve Control
Attachment to L-98-153 Page 15 of 17 Table 2 Turkey-Point Units 3 and 4 Protected Post-Fire Safe Shutdown Circuits Column Lines E to J, Fire Zones Safe Shutdown Function Fire Zone 84 Unit 3 RWST to Char in Header Su 1 Valve Control Fire Zone 84 Unit 3 Pressurizer Auxilia S ra Valve Control Fire Zone 84 EDG 3B', 4B Rela in and Meterin Fire Zone 84 EDG 3B, 4B Control Fire Zone 84 EDG 3B, 4B Lock Out Rela Fire Zone 84 125 VDC to EDG.3B Exciter Cabinet Fire Zone 84 EDG 4B Control Room Meterin Fire Zone 84 EDG 4B Volta e Re lator Fire Zone 84 EDG,4B Governor Control Fire Zone 84 MCC 3K Power Feeder Fire Zone 84 4160V Bus 3B Clearin Circuit Fire Zone 84 Breaker Control - Bus 4B-4D Tie, Bus 3B 3D Tie Fire Zone 84 Unit 3 Containment IA Header Isolation Valve Control Fire. Zone 84 Unit 3 Pressurizer Level Instrumentation Fire Zone 84 Unit 3 SG Level Instrumentation arrow Ran e Fire Zone'84 ote 3 Unit 3 SG Level Instrumentation Wide Ran e Fire Zone 84 ote 2 Pressurizer Pressure Instrumentation Fire Zone 84 Unit 3 SG Pressure Instrumentation Fire Zone 84 125 VDC to Load Se uencer 3B Fire Zone 84 120 VAC to ASD Panel 3P93 from Inverter 3C and CS Fire Zone 84 125 VDC to Panel 4D36 Fire Zone 84 ote 2 Pressurizer Heater Control Grou 3B11 Fire Zone 84 Pressurizer Heater Back-u Grou 3B Control Fire Zone 84 Pressurizer Power 0 crated Relief Valve PCV-3-455C Control Fire Zone 84 Intake Coolin Water Pum 4C Control Fire Zone 88 Unit 3 AFW Flow Control Valves Control Fire Zone 88 NCC Fan 3B Dam er Control Fire Zone 88 ote 2 NCC Fan 3B, 3D Control Fire Zone 88 NCC Fan 3B Power
, Fire Zone 88 NCC Fan 3B Ammeter Fire, Zone 88 EDG 3B Breaker Control Fire Zone 88 SBO Tie Breaker Control Fire'Zone 88 4160V Bus 3D 3B ali'mentsi nal to Load Se uencer3B
0 Attachment to L-98-153 Page 16 of 17 Table 2 Turkey Point Units 3 and 4 Protected Post-Fire Safe Shutdown Circuits Column Lines E to S, Fire Zones Safe Shutdown Function Fire Zone 88 125 VDC for 480 V Loadcenter.3B Fire Zone 88 120 VAC to Load Se uencer 3B Fire Zone 88 Com onent Coolin Water Pum 3C Breaker Control Fire Zone 88 Normal 125 VDC to 4160 Bus 3B Fire Zone 88 125 VDC to 4160 Bus 3D Fire Zone 88 EDG 3B Rela in and Meterin Indication Fire Zone 88 EDG 3B Control Fire Zone 88 EDG 3B Lock Out Rela Fire Zone 88 4160V Bus 3B Clearin Circuit Fire Zone 88 Breaker Control - Bus 3B-3D Tie Fire Zone 88 125 VDC to Load Se uencer 3B Fire Zone 88 Intake Coolin Water Pum 3C Control Fire Zone 89 ote 2 Unit 3 AFW Flow Control Valves Control Fire Zone 89 NCC Fan 3B Dam er Control Fire Zone 89 NCC Fan 3B, 3D Control Fire Zone 89 NCC Fan 3B Power Fire Zone 89 NCC Fan 3B Ammeter Fire Zone 89 4160V Bus 4B Clearin Circuit Fire Zone 89 EDG 3B Breaker Control Fire Zone 89 SBO Tie Breaker Control Fire Zone 89 4160V Bus 4D -4B ali nment si nal to Load Se uencer 4B Fire Zone 89 125 VDC for 480 V Loadcenter 3D, 3B Fire Zone 89 Com onent Coolin Water Pum 4C Breaker Control Fire Zone 89 Normal 125 VDC to 4160V Bus 3B Fire Zone 89 125 VDC to 4160V Bus 4D, 3D Fire Zone 89 125 VDC to Load Se uencer'3B
, 'Fire Zone 89 120 VAC to ASD Panel for EDG 3B Indication Fire Zone 89 EDG 3B Rela in and Meterin Fire Zone 89 EDG 3B Control Fire Zone 89 'DG 3B Lock Out Rela Fire Zone 89 125 VDC to EDG 3B Exciter Cabinet
'Fire Zone 89 MCC 3K Power Feeder Fire Zone 89 Breaker Control - Bus 4B-4D Tie
'Fire Zone 89 Intake Coolin WaterPum 4C Control
0 Attachment to L-98-153 Page 17 of 17 Table 2 Turkey Point Units 3 and 4 Protected Post-Fire Safe Shutdown Circuits Column Lines E to J, Notes:
AFW function protected for certain scenario. Stand-by Steam Generator Feedwater Pump may be used ifAFW function is not available ..
- 2) Manual actions used for adverse fire affects to certain circuits for. these components.
- 3) Narrow range instrumentation used for adverse fire affects to certain circuits.
1 C
II 0