ML20149G100
| ML20149G100 | |
| Person / Time | |
|---|---|
| Site: | 07100346 |
| Issue date: | 07/15/1997 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20149G092 | List: |
| References | |
| NUDOCS 9707230009 | |
| Download: ML20149G100 (19) | |
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ATTACHMENT TO i
P-97038 JULY 15,1997 t
PUBLIC SERVICE COMPANY OF COLGRADO OPERATIONAL QUALITY PROGRAM List of Attachments Proposed Operational Quality Program (ISFSI SAR Section 11.3) e Organizational Structure (ISFSI SAR Section 9.1)
Qualifications (ISFSI SAR Table 9.1-1)
Organizational Charts (ISFSI SAR Figures 9.1-1 and 9.2-2) b i
9707230009 970715 ADOCK071g3j6 DR
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ISFSI SAR Revision 7 11.3-1 11.3 OPERATIONAL QUALITY PROGRAM 11.3.1 Procram Descrintion and Oraanizati?D 11.3.1.1 hethodolocy
. Quality'Proaram Policy Statement It is the policy of Public Service Company of Colorado
'(PSC) to use its best efforts to ensure that the Fort St.
Vrain- (FSV)
Independent Spent Fuel Storage Installation (ISFSI) is operated, maintained, and decommissioned in a manner that assures the health and safety of plant personnel and the'public-is protected.
This Quality Program is also applicable to the packaging and transportation of radioactive material.
l The Corporate Executive responsible for the ISFSI, acting through the FSV Station management has the authority and
, responsibility within PSC for all activities acsociated with the operation, maintenance, modification, and decommissiorsing of-the ISFSI.
To ensure that all operational activities.are performed in a manner consistent with this policy, the Company
.has established a Quality Program to meet the requirements of
-10 CFR 72 Subpart G for operations, maintenance, and eventual decommissioning of the FSV ISFSI.
This Quality Program also meets the applicable requirements of 10 CFR 71 Subpart H for packaging and transportation of radioactive material.
All personnel performing ISFSI operational duties or packaging and transportation;of radioactive material duties, including PSC employees, contractors, and suppliers, are responsible for compliance with this Quality Program.
Each individual shall be familiar with this program and shall implement those einants for which they are responsible.
Quality Proaram Levels Level I - Structures, systems, components, and associated activities classified as "Important to Safety" as identified
' in Section J4 ~. 5, or.the "Important to Safety" provisions of shipment requiring the use of NRC approved packages in
-accordance with 10 CFK 71 Subpart H.
Level II.
. Structures,
- systems, components, and associated' activities that are classified as
" Enhanced Quality" as. identified in Section 4.5.
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' Revision 7 l
11.3-2 l:
Level. III Structures,. systems, components, and-l activities designated and used as commercial, commodity items, j
-and not-classified as "Important to Safety" or " Enhanced Quality" as identified in section 4.5, and not involving the "Important to Safety" provisions of shipment requiring the use of NRC approved packages in accordance with 10-CFR 71 Subpart
-H... The Quality Program requires that only commercial quality.
j standards are applied.to these items.
l 11.3.1.2 Oraanization, ResDonsibilities, and Authority 1
Section IX addresses PSC's organizational structure, functional responsibilities, levels of authority, and.
interfaces for operations.
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Cornorate Executive i
Responsible and accountable for the implementation of the
- Quality Program Policy Statement and this Quality Program. -
1 This position maintains an awareness of the effectiveness of the' Quality Program implementation through reviews of selected i
assessment results.and'by reports from the ISFSI Manager.
l The Corporate Executive is responsible for ensuring that the Quality Program is properly documented, approved and implemented.
The ' Quality Program shall: be implemented by
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trained personnel with adequate resources so that cost and schedn' ting considerations do not override the Quality Program l functions.
The Corporate Executive will annually assess the adequacy of the Quality Program implementation.
p-ISFSI Manager l
Responsible and accountable for the overall i
L implementation of this Quality Program. This position ensures
. l that' the Corporate Executive is apprised - of the Quality 3
Program implementation effectiveness and of any major concerns 1
or implementation problems.
QA Manager F
Responsible and ' accountable ~ for coordinating with the var 3cus managers to assure the establishment of an acceptable Cuality Program, maintaining this program document current, I-and verifying the implementation, adequacy, and effectiveness of the Quality Program.
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11.3-3 This position:
has the necessary authority, resources, and organizational freedom to implement the Quality Program which includes the ability to identify quality problems, initiate, recommend and provide solutions; and to verify implementation of solutions; han the authority to-stop unsatisfactory work and control further processing, delivery, insta11ationi or use of nonconforming items; ensures that the assessments of the Quality Program and its effectiveness are reported to the appropriate levels of management; and reports l to the Corporate. Executive.on matters related to quality.
Radiation Safety Officer Responsible and accountable for assuring that those programs, processes, and activities assigned are developed'and implemented in accordance with this Quality Program.
ISFSI ODerations Manager Responsible and accountable for assuring that. those
- programs, processes, and' activities which govern ISFSI operations, maintenance, and packaging and transportation of radioactive aaterials, are developed and implemented in accordance with this Quality Program.
Enaineerina.. Manager Responsible and accountable for assuring that the technical programs, processes, and activities for the ISFSI are developed and implemented in accordance with this Quality Program.
11.3.1.3 Personnel Trainina and-Qualification Quality Assurance / Quality control personnel are certified in accordance with the provisions of NQA-1, 1986.
Training and qualification requirements are addressed in Table 9.1-1
.and Section 9.3.
11.3.1.4 Corrective Action A corrective action system is established and implemented which promotes a "no-fmult" attitude toward the identification of conditions that are adverse - to quality.
The corrective action system elements consist of prompt identification, documentation, classification, cause analysis, correction of the condition, eli ination of the root cause - factors for significant conditions, follow-up, and provisions that
.9 ISFSI SAR Revision 7 11.3-4 corrective actions are not inadvertently nullified by subsequent actions.
. Nonconforming items are properly controlled to prevent inadvertent test, installation, or use.
The disposition of the nonconformanc3 will identify the item to be used-as-is,. rejected,
- repaired, or reworked.
All corrective action documents are analyzed to identify trends in quality performance.
The results of these analyses are l reported to the Corporate Executive.
. 1 1. 3'. 1. 5 Reaulatory Commitments PSC Complies with the following. regulatory requirements for the operation, maintenance, modification, and decommissioning of the
- ISFSI, and for packaging _ and transportation of radioactive materials.
10 CFR 71 Subpart H is applied to "Important-to-Safety" items associated with radioactive materia 1 transportation packages requiring NRC approval.
10 CFR 72 Subpart G is applied to "Important-to-Safety" items. identified in Section 4.5.
10 CFR 21 is applied' to "Important-to-Safety" items identified in'Section 4.5, with the exception of those items which are defined under the " Enhanced Quality" Program.
Changes to this Quality Program description shall be submitted for NRC approval in accordance - with 10 CFR parts 71.101 and 72.140.
The regulatory commitments are addressed in Soction 1.5.
This program description addresses the requirements of NUREG 0800 Section 17.3.
The specific description of the clarifications and exceptions taken with respect to the Regulatory Guidance documents addressed in Section 17.3 are delineated in' Appendix A11-2.
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Revision 7 11.3-5 11.3.2 Eerformance/ Verification 11.3.2.1 'Methodolooy l
Performance l
Performancc of all activities associated with the operation and maintenance and packaging and transportation of radioactive materials and the implementation of this Quality Program, is predicated on the availability. and use of properly approved procedures.
Verification Verification of Quality Program implementation and l
effectiveness consists of surveillances (monitorings),
i reviews, and audits.
These verification processes evaluate the completeness,
- adequacy, and effectiveness of program requirements.
Verifications are conducted in accordance with j
l written procedures or checklists, documented, and reported to i
appropriate management.
Verification activities will be performed by personnel who are independent of the activity as l.
defined by NQA-1.
SURVEILLANCES:
a flexible means for evaluating and l
verifying the PSO organization's attainment of quality in l
"real time" primarily by direct observation of the activity.
l REVIEWS:
a method of evaluai ing work specifications, l
procedures, and work packages to verify that these documents l
contain the quality and technical provisions required by the ISFSI SAR.
AUDITS:L an activity to determine, through investigation, the adequacy of. adherence to established procedures, instructions, specifications, codes, and standards or other applicable contractual and licensing requirements and the effectiveness of implemantation.
L INSPECTIONS:
examinations or measurements to verify whether an item or activity conforms to specified requirements.
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11.3-6 11.3.2.2 Desian Control When structures, systems and components classified as "Important to Safety" require design modifications, controls are applied commensurate with the controls established for the original design, applicable regulatory requirements, and the health'and safety of operating personnel and the public.
Appropriate provisions of design control shall include:
specifying of design inputs, the correct translation of inputs in design documents, sufficient documentation which details the verification that design outputs relate to design inputs, the verification of design by persons other than the originator, and the assurance that changes to the design are
-properly reviewed, controlled, and~ documented.
Modifications that affect the licensing parameters are r,ent to the NRC for approval prior _to implementation.
Revisions of controlled documents, including design documents, will be reviewed for adequacy and approved for release by the same organization that originally reviewed and approved the documents or by so:ne l
other designated organization that is qualified
.and i
knowledgeable.
11.3.2.3 Desian Verification I
Design verification methods include, but are not limited j
to, design
- reviews, alternative calculations, and qualification. teating.
Independent design verification is completed before the design outputs are used by other organizations for design work and before they are used to support other activities.
' Appropriate design verification procedures are established and implemented commensurate with the importance of the quality level of the structure, system, or component.
11.3.2.4 Procurement Control Procedures are established to assure that applicable regulatory requirements, design-bases, Quality Program requirements, and other requirements necessary to assure adequate quality are included or referenced in documents for procurement' of material, equipment, and services.
These measures include provisions for:
evaluating the qualifications of. prospective suppliers; ensuring qualified suppliers remain -qualified; accepting purchased items or services; and invoking applicable technical, regulatory, administrative, and reporting requirements.
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ISFSI SAR Revision 7 11.3-7 These procedures include provisions for ensuring that documentation for items classified as "Important to Safety" provides objective evidence that the item conforms to the procurement requirements and that inspection and test requirements have been satisfied before the item is placed in service.
The controls include the selection
- criteria, determination of. suitability for intended use, evaluation, receipt inspection, and dedication of commercial grade items for use in structures, systems and components classified as "Important to Safety" in accordance with the applicable quality-level.
11.3.2.5 Procurement Verification Procedures are established and implemented to verify that the quality of purchased items and services are evaluated at appropriate intervals and to a depth consistent with the items' or services'- quality level, complexity, quantity and the frequency of procurement.
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3.2.6 Identification and Control of Items consistent with the quality
- level, procedures are established and implemented to identify and control items to prevent the use of incorrect or defective items.
11.3.2.7 Handlina. Storaae, and Shinoi tig Consistent with the quality
- level, procedures are established and implemented to control the handling, storage,
-shipping, cleaning, and preserving of items to prevent their damage, loss, or deterioration.
11.3.2.8 Test Control-Procedures are established and implemented to demonst. ate that items will perform satisfactorily in service. Procedures includa:
instructions and prerequisites to perform the test; use of proper test equipment; acceptance criteria; and mandatory inspection witness or hold points.
11.3.2,9 Measurina and Test Eauinment Control Procedures are established and implemented to assure that appropriate tools, gauges, instruments, and other measuring and testing devices used in activities which have quality Trequirements or health ar.d safety considerations are properly
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D' 9-ISFSI SAR Revision 7 11.3-8 controlled, calibrated, and' adjusted at specified intervals.
This will maintain equipment accuracy within necessary limits and maintain traceability to National Institute-of Standards and Technology (NIST).or other known star.dards.
Measuring and test equipment found out of calibration is to be tagged or segregated and not used until recalibration occurs.
The acceptability of the activities conducted by the out-of-calibration equipment is determined.-
f 11.3.2.10 Inanection. Test, and Oneratina' Status Procedures are' established.and implemented to indicate the' status of. inspection, test, and operating condition of 1
items.
The Quality Program has provisions to assure that the inspection, test, and operating status is verified before the f
release, fabrication,' installation, test, and use of items to a
preclude inadvertent bypassing of inspections and tests and to i~
prevent inadvertent operation. The application and removal of I
status indicators and other labels is controlled.
11.3.2.11' Snecial Process (hql Procedures are established and implemented to control special processes, such as welding, heat ' treating, concrete placement, and nondestruct1.ve examination.
Special processes are accomplished by qualified personnel us'ing qualified procedures and equipment in accordance'with the applicable quality level codes, standards, specifications, or other special requirements.-
11.3.2.12 Insnection Procedures are established and implemented to describe the inspection program.
These procedures address inspection planning, acceptance ' criteria, inspection-techniques to be
- applied, establishment of-hold points, documentation of inspection results, and actions to be taken when acceptance criteria'are not met.
These inspection procedures address source, in-process, final, receipt, maintenance, modification, operations, and decommissioning activities.
Inspections are conducted by certified personnel who are independent of the activity conducted. Inspection results are documented by the inspector.
and reviewed by QA.
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1 11.3.2.13 Corrective-Action Procedures are established and implemented to address the identification, documentation, suggested resolution,.and j
verification of resolution of conditions adverse to quality.
These procedures ensure -that items ~that :are -reworked, repaired, and/cr replaced. are inspected and tested to the original requirements or specified alternates.
In the event of significant conditions adverse to quality, measures assure that the root ' cause of the conditions is determined and corrardive action is taken to preclude repetition.
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I 11.3.2.14 Document Control Procedures are established and implemented to control the
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development, review, approval ~,' issuance, use, and revision of i'
documents.
Documents include : such : items as - procedures, j
instructions,
' design ' specifications, design and as-built
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-dra'. tings, engineering calculations, computer codes, purchase j
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orders and related documents, vendor supplied documents, audit and surveillance procedures, normal and emergency operating
' procedures, technical specifications, nonconformance reports,
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corrective action reports, w'ork instructions and procedures, calibration procedures,. quality verification procedures, and inspection and test reports.
The distribution of new and revised controlled documents is-in accordance " with established timeliness guidelines.
Controlled copies of
. instructions and procedures are distributed to and used by the person performing the activity.
11.3.2.15 Records Procedures are established and implemented.to ensure that sufficient records of' items and activities are generated and-maintained to ~ reflect. completed work..
These procedures provide lfor the administration,
- receipt, retrieval, and disposition of these records in accordance with Section 9.4.2.
These.' procedures control records such as:.
- design, engineering, procurement, manufacturing',
construction, inspection. and test, installation, pre-operation, startup, operations, maintenance, modification, decommissioning, n.
audits, packaging and transportation of radioactive material, marmf acturer's records such as proof,-
- receipt, pre-operational, post-installation, training and qualification,
-and records identified in Section 9.4.2.
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j 11.3-10 11.3.3 Self Assessment j
11.3.3.1 Methodoloav
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Personnel responsible for performing the self assessment functions',
including reviews, surveillances, monitorings, l
audits, and other independent assessments, are cognizant of day-to-day activities so that they can act in a management 1
advisory function.
Personnel performing self assessment activities are performance oriented, with their primary focus on the quality of the end product and a secondary focus on procedures and processes. Personnel performing audits are not 4
to have direct responsibilities in the area (s) they are i
auditing.
4 Self assessments are accomplished using instructions, 4
procedures, or other appropriate means that are of a detail I
commensurate'with the activity's' complexity and the quality level.
11.3.3.2 Assessment Procedures for planned and periodic assessments are established and implemented to ' confirm that-activities affecting quality comply with the Quality Program and that the j.
Quality Program has been effectively implemented.
These procedures provide for comprehensive independent evaluation of activities and procedures.
Planning activities 1
identify the characteristics and activities to be assessed and the predetermined acceptance criteria to be met.
Scheduling and resource allocations are based on the status and quality i:
level of the activity.or process being assessed.
Scheduling is dynamic and resources are supplemented when Quality Program effectiveness is in doubt.
' Assessment results are documented and reviewed by ISFSI management having responsibility in the area assessed.
Follow-up action,- including a re-assessment of ' deficient areas, is initiated as necessary. When work carried out under i
the requirements 'of the - Quality Program is delegated' to i
others, implementation of that part of.the work is assessed by i
.PSC.
I Assessments will also be per*ormed as necessary of
' entities other than PSC.
These assessments will use methodology such as surveillances and audits as defined in PSC commitments to NQA-1.
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1 ISFSI SAR-Revision 7 9.1-1 SECTION IX - CONDUCT OF OPERATIOES 9.1 '.QB9 6 9.1.1 ~
Desian. Construction and Initial Fuel Loadina 9.1.'1.1 Cornorate Oraanization The FSV ISFSI was designed, constructed, tested and initially loaded under the same corporate management as the organization responsible for the defueling of the FSV reactor facility.
This organization was described in Section 12.1 and represented in Figure 12.1-1 of the FSV Updated FSAR_(Ref.1).
It was also discussed in the FSV Conduct of Business document (Ref. 2.).
l 9.1.1.2 Coroorate Functions.
Resnonsibilities and Authorities The corporate organization had overall responsibility for the conduct of operations, described in Section 9.1.1.1, relative to 'the ISFSI facility.
The functions represented by this organization had the authority to control various aspects of the ISFSI facility including engineering and design, construction, quality assurance, testing, and initial operation.
9.1.1.3 In-House Oraanization The FSV Nuclear Engineering Division had the specific responsibility.for overseeing the design of structures
'and systems, preparation of specifications, procurement' of materials and equipment, characterization and preparation of the site, and construction of the MVDS on the FSV ISFSI site. Spent' fuel accountability during the initial loading phase was the responsibility of the FSV Nuclear Production-Division.
The FSV Quality Assurance Division was responsible for quality. assurance aspects of the FSV ISFSI design, construction, testing and. initial 3 operation.
The FSV Nuclear ' Licensing and Resource Management Division was responsible for Licensing interface with the Nuclear Regulatory Commission.
9.1.1.4 Relationshins With contractors and Sunolierg, The development' of the
- ISFSI, including
- design, construction, testing, and operations was managed by
.Public Service Company of Colorado.
The contractor for the design, safety analysis, and construction of the FSV I'
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Revision 7 9.1-2 ISFSI, based primarily on:the design presented in the L
Foster Wheeler Energy Applications MVDS Topical SAR (Ref.3), was Foster-Wheeler. Energy Corporation, Energy l
Applications; Division.
General Atomics was utilized for technical analyses support.
9.1~.1. 5 Technical Staff The Corporate technical'. staff supporting the ISFSI was described in.Section 12.1 of Reference 1.
9.1.1.6 Personnel Functions.
ResDonsibilities and Authorities The functions, responsibilities and' authorities of personnel were_ described in Section 12.1 of Reference 1
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for the FSV reactor'and were applicable to the ISFSI for
.the design, construction, testing, and initial loading of I
the ISFSI.-
9.1.1,7 Personnel Oualification Reauirements i-The.. qualification requirements for managerial and technical personnel-responsible for
.the
- design, construction, testing and initial loading of the ISFSI were the same as those presented in Section 12.1 of Reference 1.
l 9.1.2 Lona Term ooerations l
9.1.2.1 Corocrate and Oneratina Oraanization L
. After defueling operations of the FSV reactor to the
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- MVDS, the corporate and technical organizations
,(represented throughout Section 9.1.1) that are dedicated for the support: cf; those efforts were changed to l
accommodate decommissioning of tho' FSV reactor.
The deccumissioning phase organization, with the managerial
' functions, technical functions, and positions is shown in Figure 9.1-1.
This decommissioning organization was also responsible for the operation c.n d m a i n t e n a n c e of the ISFSI throught the-decommissioning period for Fort'St.
Vrain. Upon completion of the decommissioning phase, the
' organization depicted in Figure 9.1 will direct the long term -- operation and maintenance 'of, the ISFSI. It 4-l
'should be'noted that PSC is in the process of. repowering 1
FSV, using natural gas-fired combustion turbines and heat
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-recovery steam generators, and some' functions for the
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long, tern ISFSI,organizatior. will 'be performed 'by personnel assigned' to the repowered facility.
PSC i
corporate personnel, qualified to function in assigned i
-positions,- will be part of the long ters. ISFSI i:
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9.1-3 organization.
Prior to the completion of decommissioning, PSC provided the NRC with the updated long term organizational chart shown in Figure 9.1.2.
This organization will assure the continued safe operation of the ISFSI during all normal, off-normal, and accident conditions.
9.1.2.2 Functions, Responsibilities and Authorities The ISFSI organization has the overall responsibility for the conduct of operations relative to the ISFSI facility.
The functions represented by this' organization have the authority to control various' aspects of the ISFSI facility including engineering and
- design, quality i:
assurance, fuel accountability, maintenance, health physics, training, operations, and decommissioning.
t 9.1.2.3 Relationshins With contractors and Sunnliers The relationships with contractors and suppliers, as required, are the'same as those represented in Section 9.1.1.4.
9.1.2.4 Personnel Positions and Functions The following positions and functions are represented on Figure 9.1-2.
l Cornorate' Executive - This position provides corporate management at the executive level'for the ISFSI and has the authority 'and responsibility to ensure continued safe operations at'the ISFSI facility.
ISFSI Manacer - This position reports to the Corporate l
Executive and is responsible.for management of the ISFSI.
The ISFSI Manager has the authority and responsibility
- for providing resources (or contract support, as needed) as'well as. management,' direction-for safa operation and maintenance of the ISFSI.
Thissposition is responsible for' document control and storage, training, industrial safety and security for the ISFSI and licensing interface with the Nuclear Regulatory Commission. This position is also responsible L for the liaison functf on between the Public Service-Company of Colorado, the Statei and Local governments in accordance with the ISFSI Emergency Response Plan, discussed in Section 9.5.
In addition, this' person functions as the Chairperson of the ISFSI t
Safety Review Committee, as required in the ISFSI Technical Specifications.
The ISFSI Safety Review j'
Committee reports to the Corporate Executivo.
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ISFSI SAR Revision 7 9.1-4 OA 'Manaaer - This position provides'. quality assurance functions for.
the
- ISFSI, including audits and inspections, in.accordance with the FSV ISFSI Quality Program (Ref. 4). This position reports to the Corporate l
Executive.
.The QA Manager is responsible for matters pertaining to the Quality Program for the ISFSI.
The QA Manager also serves as a member of the ISFSI-Safety Review Committee.
Enaineerina Manaaer - This position may be filled by a
- corporate - person - who reports to the ISFSI Manager on ISFSI matters only. This position is responsible for the management of all technical support necessary for-the ISFSI which includes:
civil, electrical, mechanical, nuclear, structural. engineering. The Engineering Manager also' serves as.a member of the ISFSI' Safety Review Committee.
ISFSI Onerations Manaaer - This position may be filled by a corporate person who reports.to the ISFSI Manager on ISFSI matters only. This position is responsible for the day-to-day management of all ISFSI operations including fuel handling, maintenance and surveillance activities.
The ISFSI Operations Manager also serves as a member of the ISFSI Safety' Review Committee.
Radiation Safety Officer -
This position may be filled by a corporate person who reports to the ISFSI Manager on ISFSI matters only.
This position'is. responsible for radiation safety at. the ISFSI.
The Radiation Safety Officer' is responsible for ISFSI - radiation protection activities.
The Radiation ' Safety Officer also. serves as a member of the ISFSI Safety Review Committee.
The Radiation Safety Officer advise's the ISFSI Manager on all matters pertaining to radiological safety, including
. identification of potential radiological concerns.
9.1.2.5 Personnel Oualification-Recuirements Personnel qualification requirements for the various positions detailed in Section 9.1.2.4 are represented 'in-Table 9.1-1.
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ISFSI SAR Revision 7 Table 9.1-1 (Page 1 of 2)
OUALIFICATIONS l
1.
Cornorate Executive l The qualifications for Corporate Executive in charge of the ISFSI are determined by Public Service Company of Colorado based upon both managerial and technical experience.
2.
ISFSI Manaaer The ISFSI Manager, at the time of appointment to the position, j
should have a minimum of eight. years in responsible positions, of which one year shall be nuc3 ear power plant experience.
A maximum of-four years of the remaining seven years of experience should be fulfilled by satisfactory completion of academic' training.
3.
Enaineerina Manaaer
-The Engineering Manager shall have a minimum of a Bachelor's-Degree in Engineering or the Physical Sciences and have a minimum of. three years of professional level experience in nuclear -services, ' nuclear plant operation, or nuclear engineering, and the necessary overall nuclear. background to determine when to call consultants and contractors for dealing with complex problems beyond the owner-organization expertise.
4.
Radiation' Safety Officer The Radiation Safety Officer (RSO) shall have a Bachelor's
' Degree or the equivalent in a science or engineering subject, including some formal tre.ining in radiation protection.
The
. RSO should have at least five years of professional experience in applied' radiation protection.
(A master's d69ree may be considered equivalent to one year of professional experience, and - a ~ doctor's degree may be considered - equivalent to two years of professional experience where course work related to radiation protection is involved.)
At least three years of' this' professional experience should be in applied radiation
. protection work in a
nuclear facility dealing with radiological problems similar to those encountered in nuclear
. power stations.
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' Revision 7 Table 9.1-1 (Page-2 of 2)
QUALIFICATIONS l
5.
QJi Manaaer The QA Manager shall have a minimum of five years experience l
in a
responsible position that ' includes coordination, direction, and supervision of personnel or contractors.
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formal education in an Engineering or the Physical Sciences field, and a working knowledge and understanding of nuclear
. plant
- design, operation and construction practices are required.
A. balance of experience in quality assurance related activitics and-in regulatory / compliance requirements is-preferred.-
6.
ISFSI Operations Manaaer The ISFSI Operations Manager, at the time of appointment to the position, should have a minimum of eight. years of responsible power plant experience, of which a minimum of three years shall be nuclear power plant experience.
A maximum of two years of the remaining five years of power plant experience may be fulfilled by satisfactory completion of academic or.related technical training on a one-for-one time basis..
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CORPORATE l
EXECUTIVE 4
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s ISFSI SAFETY g-i REVIEW COMMITTEE i
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i PROGRAM
- DIRECTOR i.
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18FSI MANAGER ** -
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PROJECT
- ENGINEERING
- RADIATION
- OPERATIONS
- ASSURANCE MAN.AGER PROTECTION MANAGER MANAGER DECOMMISSIONING MANAGER
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QA MANAGER **
ENGINEERING RADIATION SAFETY ISFSIOPERATIONS MANAGER **
OFFICER **
MANAGER **
M M
ENGINEERING ASSURANCEDSOPUNES DISCIPUNES SUPPORT DSCIPUNES OPERATIONS DSOPUNES oA DiaC PUNES MECHANICAL HEALTH PHYSICS FUE'.HANDGS UCEN81NG ELECTRICAL TRAINING MAINTENANCE INDUSTRIAL SAFETY NUCUEAR SECURMY SURVElu R CE RECORDS DecomMg N
o-Corporate i
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- Executive l
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ISFSI Safety f
Review Committee l
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' QA' Manager i
ISFSI Manager Clerical
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- Radiation
- Engineering
- ISFSI.
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Safety Officer ~
Manager Operations i
Manager l
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- May be filled by Corporme Figure 9.1-2
_ _ _ ' Repons to ISFSI ISFSI Organizational Chart
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r Manager on ISFSI maatsers only.
Fort St. Vrain Nuclear Cau4ing Station g50 Long Term Operations
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