ML19312D620
| ML19312D620 | |
| Person / Time | |
|---|---|
| Site: | 07100348 |
| Issue date: | 02/29/1980 |
| From: | MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| To: | |
| Shared Package | |
| ML19312D614 | List: |
| References | |
| 15565, NUDOCS 8003250100 | |
| Download: ML19312D620 (16) | |
Text
.
O MICHIGAN MEMOMIAL PHOENIX PRO 5ECT TH E U NIVERSITY CL: MICHIGAN QUALITY ASSURANCE PROGRAM m.w..
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FORD NUCLEAR REACTOR
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TABLE OF CONTENTS Page Section I
-TITLE PAGE TABLE'OF. CONTENTS i
REVIEW-11 1.-
INTRODUCTION 1
2.
PROGRAM REQUIREMENTS 1
3.
SAFETY ANALYSIS 5
4.
DESIGN CONTROL 6
5.
PROCUREMENT CONTROL 6
6.
MATERIAL CONTROL 8
7.
PROCESS CONTROL 8
8.
INSPECTIONS 9
9.
TESTS 9
10.
DOCUMENTATION 10 11.
AUDITS I3 LIST OF FIGURES 1.
FORD NUCLEAR REACTOR QUALITY ASSURANCE ORGANIZATION
'2.
. FORD NUCLEAR REACTOR MODIFICATION REQUEST 9
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.5 REVIEW This progran will be reviewed, revised as required, signed.by the Pcactor Manager, and dated annually and whenever revisicns are made. Revisions will be noted'in the right hand coltan. Revised procedures will be issued
- to procedure holders at the tir.e of revisicn.
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Reactor Manager Date Revised Sections RakR. W s/a/79 o & b w AL.
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' INTRODUCTION
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purpose lThe purpose of this program in to provide requirements for managing, conducting, and auditing the quality assuranco program at the Ford Nuclear Reactor (FNR).
'l.2 Applicability The quality assurance progran applius to replacements of and modifications to safety related items subsequent to the date of implementation and to those. quality-af fecting activities
- )
related 'to shipping packages for radioactive material. Quality assurance documentation is not required for the facility an-built and for safety related changes mado prior to program impicmentation.
1.3 Safety Ralated Items Safety related items associated with the FUR are the reactor pool, the primary coolant system, and the instrumentation systems listed in Technical Specifications, Tables 3.1 and 3.2.
1.4 References 1
1.4.1 American national Standaulu instituto (ANSI) U402-1976, Quality Assurance Prcgram Requirementn for Research Reactorn.
1.4.2 10CFR 71, Appendi:< E.
2.
PROGi4AM REQUIREMENT",
-2.1 Responsibility LThe Safety Review Committee is responsible for antablishing gp the facility's quality assuranco ' policies, goals and objectivos, The Reactor Manager retains overall authority and responsibility g,
for the Quality Assurance program.
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2.1.1 -
~ Reactor Manager Qualification Pcquirements The Reactor Manager must have a bachelor'n degree in engineering or physics, have experlenen in working with nucicar reactors-including progressively respon-()
sible supervisory experience, demonstrate knowledge of nuclear engineering principles and practicos, and demonstrata the ability to be licensed by the Nuclear Regulatory ' Commission as a Senior Reactor Operator.
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12. 2,
-Quality Assurance Organization The FNR Quality Assurance Committee is responsible for the implementation of quality assurance requirements on'a project
- basis (Described in Sections 3 - 11). Permanent committee members include the Reactor Manager (Chairman), Assistant
- Reactor Manager, and Supervisor of Reactor Operations. Ad hoc project members include a design engineer and a quality engineer. These. functions may not be combined, but may be filled by one of the permanent committee members.
Members of the Quality Assurance Committee who'are responsible for verification of conformance to established requirements gg will not have direct responsibility for performing the work being verified.
The FNR Safety Review Committee serves to provide technical advice and must grant final approval of project safety analysis and design prior to impicmentation.
2.2.1 Reactor Manager. The Reactor Manager is responsible for:
a.
Assigning ad hoc Quality Assurance Committee members, b.
Scheduling and chairing project reviews.
Assigning drawing and document nunbers as required.
c.
r d.
Submitting safety analysis and project design to the FNR Safety Review Committee for approval.
e.
Submitting Licence and Technical Specification amendments to the NRC as required.
f.
Resolving disputes involving quality arising from differences of opinion between Quality Assurance Committee members and personnel performing the work being verified. Issues which cannot be resolved by the Reactor Manager will be presented
- to the Safety Review Committee for final resolution.
2.2.2 Supervisor of Reactor Operations. The Supervisor of Reactor Operations is responsible for:
a.
Maintaining a project file which contains copies of all records associated with the project.
b.
Maintaining measuring and test equipment properly calibrated.
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Safety Review Committee I
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Quality Assurance Technical Specifications Committee Auditor Reactor Manager
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Supervisor Reactor Manager Members Reacter' Operations Design Quality Engineer Engineer FIGURE 1
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FORD NUCLEAR REACTOR QUALITY ASSURANCE ORGANIZATION ORIG 5/78
AP 4
e 2.2.3 Design Engineer. The design engineer is responsible for:
a.
Performing a safety analysis including Technical Specificaticn and standards requirements.
b.
Develcping the required design.
c.
Preparing informatial requird for procurenent documents.
d.
Ccntrolling procured material upcn arrival at the facility.
- e. - Preparing procedures for installation and tests.
f.
Corpleting drawings, system descripticns, procedures, regulaticns, and changes to the Technical Specifications and License as required.
g.
Maintaining a corplete file with the Supervisor of Feactor Operations of all work related to the modification.
2.2.4
. Quality P.ngineer. The quality engineer in respcnsible for:
a.
Verification of design alcquacy.
b.
Dispositicn of ncn-cenfonning materials and parts.
c.
Performing. inspections d.
Verificatien of tests.
2.3 Project Review Mceting The Quality Assurance Carmittee will ncet to review reject safety analysis, design, installation tests, and final docu-mentation package. The means for implanenting Sections 3 - 10 will be established on a project basis at the review meeting.
2.3.1 Design Mequacy. Designs will be reviewed for reactor physics implications; thermal,, hydraulic, and mechanical stress;' accident analysis; material ccupatibility; accessibility for in-service inspecticn, maintenance, and repair; and interfaces with other systems.
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- 2.4 Om1Vty Assurance Program Assessment '
'Ihe Safety Review Comtittee will assess the scope, status, implmentation, and effectiveness of the Quality Asstirance Program to assure that the program is adequate and corplies
- g with 10CFR 71, Appendix E.
A consultant will be retained by the facility to perform an annual audit of the Quality Assurance Program. The ccnsultant will-be an individual presently or recently engagcd in the managcment of a reactor of carparable power level and type. The consultant will provide a report of canclusions drawn fran the audit to the Safety Review Carmittee.
2.5 Training-An indoctrination and training program will be es+nh1ic:had for Quality Assurance Camtittee merriers on a project basis such that:-
2.5.1 Personnel responsible for performing quality-affecting activities are instructed as to.the purpose, scope, and implanentatica of the quality-related manuals, instructicns, and procedures.
g 2.5.2 Personnel performing quality-affecting activities are trained and qualified in the principles and techniques of the activity being perfoured.
2.5.3 The scope, the objective, and the trethcd of implementing the indoctrination and training program are docurented.
2.5.4 Proficiency of personnel performing quality-affecting activities is maintained by retraining, reexamining, and/or recertifying.
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2.6 Experimental Equiprent The quality assurance program will provide controls over tie fabricaticn and installation if c:q>arimental equipment to tFa extent that these relate to u actor safety.
2.7 Corrective Action Significant ecoditions detrimental to the quality of safety-related. items, such as. failures, malfunctions, and deficiencies, will be prarptly identified, the cause determined, and currective acticn taken to preclude repetition.
2.8 02ality Assurance Manual Provinicns will be established to centrol tl'a distribution of g
Quality Assurance !!anuals and revisicns thereto.
v 3.
SAFEIY ANALYSIS
. As a preliminary step in any safety related modificaticn, a safety Rev 2/80-m -w o*-
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analysis will be performed. The' safety analysis will analyze the safety implications'of the modification. Verification must.be provided that the probability of occurrence or consequences of an
. accident have not been ' increased, the possibility of an a'ccident
- or malfunction of a differnet type has not been created, and the margin of safety in Technical Specificaticas has not decreased.
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4.
DESIGN COTTiOL Applicable codes, standards, and regulatory requirments will be incorporated into the design of safety related items and experiments.
Design adequacy will be verified by design review, alternate calmlntions, or a test progran. Verificaticn should include checks of such characteristics as ccmpatibility of materials; suitability of application of materials, parts, and processes; accessibility for in-service inspecticn, maintenance and repair; proper interfacing of subsystems; and co@leteness of acceptanc 2 criteria.
4.1 Provisions will be established cn a project basis which clearly delineate the sequence of acticns to be accomplished in the preparation, review, approval, and control of instructions, procedures, and drawings.
4.2 The Quality Assurance Ccrnnittee will review and concur with inspecticn plans; test, calibration, and special promss proccdures; drawings and specifications; and changes tlereto or acceptable alternatives.
4.3 The revim, apprcnal, and issue of documents and changes thereto, g
prior to release will b2 procedurally controlled to assure they are adequate and the gaality requirements are met.
4.4 Changes to doc m ents will be reviewed and approved by the Quality Assurance Ccrmittee.
4.5 Approved changes will be incitded in instructions, procedures, g
drawings, and other docu:r.ents prior to inplementaticn of the change.
4.6-Dcv,=mts will be available at the locaticn where the activity will be performed prior to ccnmencing work.
4.7 A master' list or equivalent will be established to identify the current revisica number of instructions, prccedures, specifi-cations, drawings, and procurc=ent documents. This list will be g
updated and distributed to pri ctermined, responsible personnel to preclude use of superseded docu:nents.
5.
PRCEUPEM CGITROL Applicable codes, standards,. and regulatory requircaents will be included in procurement dccutents. To the extent determined by the safety requirenents of the final systcm, procurcment documents will Rev 2/80 g
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require contracters or subcontractors to prcuide appropriate quality
- assurance controls, which may include, but are not limited to, functions such as' inspections, tests, and controls over materials, processes and ncnconfonnances.
5.1 Procedurcs will be establishal on a project basis that clearly delineate the acquena of actions to be accmplished in the h
preparation,. review, approval, and control of procurenent documents. Changes -to procurcrrent documents will be subject to centrols ccmnensurate with those for the original procurements.
5.2 A review and ccncurrence of the adequacy of quality requirements stated in procurment documents will be conducted by the Quality Assurance Ccmnittee. The review will detennine that qmlity g
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requirements are correctly stated, inspectable, and controllable; there are adequate acceptance.and rejection criteria; and the procurement doctznent has been prepared, reviewed and approved in accordance with Quality Assurance ProrJram requirements.
G 5.3 The review and approval of procurc: rent documents will be U
documented prior to release and available for verification.
5.4-Procurment doctunents will identify the applicable 10CFR 'll, Appendix E requirements which rtust be carplied with and deWhM
-g in the supplier's quality assurance prcyrtan. The supplier's quality assurance prceram or applicable portions thereof will be reviewed and concurred with by the Quality Assurance Ccnndttee prior to initiation of activities affected by the pecgram.
'f Procurement doomants will contain or reference the design basis 5.5 technical regttircrents including the applicable regulatory
-h requirements, material and cmpone ' identifiestion requirerents.
drawings, cpecifications, ccdes an industrial standards, test and inspection requirements, and rpecial prccess instructions.
5.6 Procurunent doctznents will identify the documentation (e.g.
draWngs, specifications, procedures, inspection and fabrication OS -
plan, inspection and test records, perscnnel and procedure qualifications, and chanical and physical test results of material) to be prepared, maintained, and subnitted to the facility for review and approtral.
5.7 Procuronent documents will identify those records to be retained, controlled, and maintained by the supplier, and those delivered -
to the facility prior to use or installation of the hardware.
5.8 Procurment documents will contain the facility's right of h
acccas to supplier's facilitics and records for source inspecticn and audit.
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MATERIAL COtfrPDL Control of the identificaticn, handling, storage, shipping, cleaning, and preservation of material and equignent will be established as d W ne ssary by the Quality Assurance Ccmnittee.
6.1 Ncnconforming Material and Parts Nonconforming materials and parts will be identified, segregated, and disposed of. Disposition will be acconplished after a review by the Quality Assurance Ccmnittee and will ccnsist of acceptance, repair, rescrk, or rejection.
6.2 Specini handling,' preservation, storage, cleaning, packaging, and shipping requirements will be established and accmplished g
by qualified individuals in accordance with predetennined work and inspection instructions.
@l 6.3 All necessary shipping papers will be prepared as required.
6.4 All conditions of the Nuclear Regulatory Ccmnission package h
approval and the United States Department of Transportation shipping requireirents will be satisfied prior to shipment.
6.5 Departure time, arrival time, and destinaticn of a pacPaJe will h
be establish 2d and monitored to a degree consistent with the safe transportation of tle package.
7.
PTOCESS CONTPOL Processing of materials will be acccnplished under controlled conditicns
- in accordance with applicable codes, standarr3s, and specifications.
Ccntrols will be applied to the extent appropriate, with particular emphasis cn those for specific procesces, such as crimping, soldering, welding, heat treating, cleaning and nondestructive examination.
Procedures, equignent and qualifications of personnel will be defined for those specini processes not covered by existing codes or standards.
7.1 Special processes such as welding, heat treating, nondestructive testing, and cleaning will be procedurally controlled.
7.2 Identification of the inspection, test, and cperating status of g
structures, systens, and components will be centrolled so that they are known throughcut the manufacturing and installation
- process.
7.3 Applicatien and removal of inspectica and welding stamps and status indicators such as tags, labels, and states will be procedurally controlled.
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INSPECTICNS Inspection requirements apply to procurements, construction, modification, maintenance, and experinent equipnent fabricaticn, ard will include,.to the applicable extent the following:
La.
Inspection procedures, specifying the characteristics to be inspectcd, sampling plans, and acceptance criteria.
b.
'Descripticn of process recnitoring action for those situations in which inspecticn is inpossible or disadvantageous.
Specificaticn of mandatory inspection hold points.
c.
d.
Procedures for identifying inspection and test status, so that cnly itms that have passed the required inspections and tests are used, installed, or operated. Ncnconfonning items will be c1carly identified.
Procedures for required in-service inst.cction of cmpleted e.
systems, structures, and corponents.
8.1 An inspection program which certifies conformance of quality-g affecting activities'with requirements will be established, documented, and accceplished in accordance with written controlled procedures.
8.2 Inspectica personnel will be independent fran the individuals perfonning the activity being inspected.
8.3 Measures will be taken and documented to determine the vaHaity-
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of previous inspections perfonrad when reasuring arid test equiprent is found to be out of calibration.
9.
TESTS The test prcgran will cover required test.s, including prototype qualification tests, proof tests prior to installaticn, and functional tests.
Test procedures will specify appropriate prerequisite and monitoring requirements, equipment' to be used, persamel training requirments, suitable envircreental cmditions, and provisions for data acquisiticn i
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.and docmentation as. applicable.
f.
9.1' Measuring and Test Equipment
'Ibols, gages, instruments, and other measuring and testing devices i
l used in activities affecting the quality of safety-related items Ewill be available, properly controlled, properly calibrated, and adjusted:at the required-intervals.
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DOCLMNTATION All activities affecting safety-related itms' will be formally identified and documented. Documentation will' include the applicable procMures, reviews, and other measures to be applied.
10.1 - Design Documentation Facility drawings, procedures, and regulations will be cmpleted
- and updated as an _ integral part of a facility modification. All or part of the drawings,and documents described below may be
' required as determined at the design review.
10.1.1 Facility Drawing Index. Ucw drawings will be added to the facility drawing index as required to cmplete a modification.- The Reactor Manager will assign drawing nutbers at the project review necting.
10.1.2 System Descripticn.. A brief but emplete description of the modification stating its purposes, function, operation, and maintenance requircrrents.
10.1.3 Block Diagram. A basic logic block diagram that indicates the major Irechanical or instru:entation cmponents.
10.1.4 Detailed Systcra of Circuit Schenutic Diagrams.
Pcchanical or instruncatation 6ingrans in sufficient
' det' ail to perform maintenance and repair.
10.1.5 Design Noteboot:. A notebook kept by the design engineer containing assurptiens, design basis, data, cbservations and sketches.
10.2-Document Issue and Change _
10.2.1 Ford Nuclear Reactor Mcdification Request. A trMification request may be requestd by any staff member for changes to the physical facility, procedures, or regulations.
'1he requester is respcosible for canpleting the modifi-cation description and safety. inplications to the extent that he is aware of them.
All changes to drawings, procedures, and regulations will
.be made via modificatica requests.- The reviewed modifi-caticn request nurrber will serve as the' authorization for new drawings and Iraking changes to existing drawings.
The Reactor Manager will canplete sections 5 and 6 as itms'are ccmpleted.
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FIGURE 2 FORD NUCLEAR REACTOR MODIFICATION REQUES1 NO.
1.-
Modification
Description:
t
'2.
Requested By:
Date:
. 3.
Safety Analysis:
Yes No 3.1 Probability of occurrence or consequences of on occident for equipment important to safety increased.
3.2 Possibility of on occident or malfunction of different type created.
3.3 Margin of safety in Technical Specifications decreased.
4.
Design Engineer:
l Quality Engineer:
l S.
Project Reccsd Requirements:
~
Completed Required Yes No Date initial Comments:
5.1 Safety Analysis 10CFR50.29(C) 5.2 Design Review 5.3 Drawing Revision 5.4 New Drawings 5.5 Manual Change 5.6 Procedure Change Tech Spec 6.4, 5.7 SRC Approval 10CFR50.59(C)
- 5. 8 -
Tech Spec Change 5.9-License Ch,nge
'5.10 NRC Approval 10CFR50.59(C) 5.11 Procurement Review 5.12
. Material Control Review 5.13 Process Control Review 5.14 Inspections 7
. 5.15 -
. Tests.
5.16
.Non -Conforming Materials 5.17 Failure Records 6.
Completed:
Date:
ORIG 5/78 a
m
4 10.2.2 Drawing Title Block. Each new or revised feility drawing will contain a title block with the following informaticn: -A title block will be added to existing drawings if required.
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Mod Req
!ssue Design Reactor
. LTR Date Number Description Draftsman Engineer Manager ll t
10.3 Quality Assurance Records
'Ihe Quality Assuranco Program includes documentation of activities affecting the quality of safety related items and those quality-affecting activities related to shipping packages for radioactive material. Records will be retainM for the life of the system, equiprent, or experiment and will be
' idenH fiarl and retrievable throughout their. retentian period.
'Ibe Supervisor of Reactor Operations will maintah a project file for each safety related iten which includes:
- a..
Modificaticn Request.: Each review item car @leted and dated when ccmpleted. Final review apprcried by the Peactor Manager.
b.
Safety Analysis
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-D sign Paview
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. I tocurement Paview t
e.
aterial Control Review Rev 2/80
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Process Control Review g.
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Ncn-ccnforming Materials j.
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Procedures 1.-
AUDITS An audit will be performed annually of each safety related project begun, in prcgress, or corpleted during tha year.
11.1. Audits will be perfctmed in accordance with preestablished g
written procedures or check lists and ccoducted by trained personnel not having direct respcnsibilities in the area being audited, 11.2 Audit results will be documented and reviewed with nuuagenent h
having respcnsibility in the area audito3.
11.3 Bespcnsible manancrent will take the n2cessary acticn to correct b
the deficiencir,, reveui~1 by tie audit, 11.4 Deficient arcia will be reaudited on a tirely basis to verify inplorentaticn of corrective actions which minimize recurrence of deficiencirs.
Rev 2/80 15565
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