ML19259D542
| ML19259D542 | |
| Person / Time | |
|---|---|
| Site: | 07100348 |
| Issue date: | 09/21/1979 |
| From: | Cook G MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7910250050 | |
| Download: ML19259D542 (1) | |
Text
MR 7/-0348 THE UNIVERSITY OF MICHIGAN PHOENIX MEMORIAL LABORATORY FORD NUCLEdR REACTOR ANN ARBOR, MICHIG AN 48109 (313) 784 6220
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yILE COPY September 21,1979 M
N Charles E. MacDonald, Chief
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Transportation Branch Ci l,l Division of Fuel Cycle and j
Material Safety
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Office of Nuclear Material Safety and 9
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U. S. Nuclear Regulatory Commission C
Washingtnn, D. C. 20555 Dem Sir:
As discussed in our telephone conversation of September 20,1979, I am sending a copy of the Quality Assurance program that we submitted to the Director of Nuclear Reactor Regulation as required by section 71.51 of 10CFR71. Our i
records indicate that the response was sent to the Nuclear Regulatory Commission on or about May 16, 1979. It is my understanding that due to the timely submission of this proposed plan that The University of Michison continues to have authorization to deliver licensed material to a carrier for transport and that we will not be deleted as a user of NRC approved package designs.
Our current plans are to have a spent fuel shipment sometime in November subject to NRC approval of our proposed route.
If you have questions concerning this correspondence please contact me at 313/764-6223 Sincerely, b.
Gary M. Cook Assistant Recctor Manager 2
3 054 Ford Nuclear Reactor GMC/z xc: W. Kerr R. Burn J. Pagliaro, Region lll NRC 14205 Enci 79102500N
TH E UNIVERSITY QF MICHIG AN MICHIGAN M EMORI AL-PH O ENIX PROJ ECT OF+.c5 or tus Ososcrom PM0 8 M'8 ** 8***' A b LA **** T2 8 '
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Docket No. 50-2 May 14,1979 Director Nuclear Recetor Regulation Nuclear Regulatory Commission Washington, D.C.
20555 The enclosed documents are being submitted os required by Section 71.51 of 10CFR Port 71. Included are o Quality Assurance Program and a procedure for the handling of the BMI-1 shipping package [ USA /5937/B00 when used as the shipping container for spent fuel reactor elements. The University of Michigan is on authorized user of 6
this package.
This p.oposed program hos been reviewed and opproved by the reactor operctions stoff" '
and the facility'Sofety Review Committee. The Ford Nuclear Reactor has been shipping spent fuel from the facility yearty since 1964. The experience gained is generally applicable to the proposed shipment.
Sincerely, W
William Kerr Director Michigan Memorial-Phoenix Project g
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ADMINISTRATIVE PROCEDURE NO.16
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FORD NUCl. EAR REACTOR The University of Michigan Ann Arbor, Michigan 1.
TITLE SPENT FUEL SHIPMENT J
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EQUIPMENT COVERED h c..
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Not Applicable n.,
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PURPOSE b~ : '
6 to The purpose of this procedure is to provide a consistenton safe method for shipping spent reactor fuel elements from the FNR, 4
BACKGROUND AND SAFETY ANAL.YSIS The FNR contracts with an owner of c 'uel shipping cask to transport Rev* 3/79 gent fuel elements back to the U. S. Government for reprocessing.
Planning, coordination and care are extremely important when handling n.
4C;i7 reactor fuel which contains a large inventory of fission products.
Criticality checks on the cask and cask neu:/cn shielding material are not rec;uired. The minumum critical mass for fresh 140 cm U235 Ford Nuclear Reactor (FNR) fuel is 2554 gm U235 based on the initial critical core of September 19, 1957. The core was fully reflected, water moderated, and consisted of 18 standard elements and 4 control rod elements. The maximum number of partially expended FNRfuel elements that can be piaced in the BMI-1 cask is 12.
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PROCEDURE REVIEW This procedure wili be reviewed, revised es required, signed by the Reactor Manager, and deted ennually and whenever revisions cre made. Revisions will be noted in the right hand column. Revised procedures will be issued to procedure holders at the time of revision.
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DEFINITIONS Not Applicable.
7.
REFERENCES Rev 11/78 7.1 University of Michigan Quality Assurance Procedure.
Rev 11/78 7.2 Cask owner Quality Assurance Procedure.
8.
EQUIPMENT REQUIRED 8.1 Shipping cask.
8.2 Building crane.
9.
RESPONSIBILITIES 9.1 The Reactor Manager will assign personnel to implement this procedure.
10.
PROCEDURE 10.1 Preliminary 10.1.1 Internal Processing 10.1.1.1 Issue University of Michigan purchase order for spent fuel shipment.
10.1.1.2 Verify cask owner's ability to fulfill contract cor=nitments.
10.1.1.3 Set tentative date for shipment.
10.1.1.4 Schedule crane for loading and unloading cask.
(Normally needed: 0800 - 1200 first day; 0800 - 1200 second day.)
10.1.2 Federal Regulations Compliance Rev 11/78 10.1.2.1 Verify that University of Michigan is an Authorized Shipper of the cask being used.
5 Rev 11/78 10.1.2.2 Verify that proper Quality Assurance documentation for the cask is in effect from the supplier.
10.1.3 Send Necessary Shipment Data to Savannah River Operations, Aiken, South Carolina 10.1.3.1 Proposed shipping date.
1213 058 ORIG 5/75 i
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10.1.3.2 Reference proper material descripticn.
Normally Appendix A, Modification 3.
10.1.3.3 Spent fuel element data sheet.
10.1.3.4 Indicate that shipment contains no stainless steel and whether or not fuel element nose cones are cut off.
10.1.3.5 All elements must have a minimum 90 days cooling time.
10.2 Procedure 10.2.1 Smear truck and cask.
(Health Physicist) (Record) 10.2.2 Remove elevator top with crane.
10.2.3 Unbolt cask tiedowns.
10.2.4 Remove cask from truck to elevator with crane.
10.2.5 Lower cask with elevator (following with crane).
10.2.6
~ Roll cask into Reactor Building using fork truck and men.
10.2.7 Remove bolts from cask lid and remove lid.
Health Physicist cust be present.
10.2.8 Smear cask internals including lid and determine whether or not cask may be put into reactor pool.
10.2.9 Determine that proper basket is in cask.
10.2.10 Attach lifting yoke to cask and raise cask to pool floor. Position cask directly above the reactor south pool.
10.2.11 Wet down cask with demineralized water using hose provided.
10.2.12 Lower cask to bottom of pool. Carefully watch all clearances while lowering cask.
10.2.13 Remove lifting yoke from cask and store on pool floor.
10.2.14 Load fuel elements to be shipped into cask.
REVISED 11/78 1213 059 v
AP-16
-5 10.2.14.1 Verify each element serial number before loading.
10.2.14.2 Load elements into baskets keeping each element aligned tdth adjacent elements.
10.2.14.3 Document the location of each ele.r.ent as it is loaded.
10.2.15 Use building crane to install cask lid on the cask.
10.2.16 Use building crane to install lifting yoke on cask.
10.2.17 Carefully align crane for vertical lift and then life cask.
10.2.18 As cask clears the pool surface wash it down thoroughly with deminera'.1:ed water.
10.2.19 Health Physics cust monitor radiation level of fuel cask.
10.2.20 As cask is being lifted out of pool, install all lid i
nuts finger tight.
DO NOT HOLD CASK ABOVE SOUTH POOL ANY LONCER TluN NECESSARY.
10.2.21 Lower cask to beam hole floor and set it on blotter paper.
10.2.22 Smear cask.
10.2.23 Drain cask into thermal column door trench. Collect a water sample from the cask for counting.
10.2.24 Tighten all cask lid nuts and install FNR seals.
10.2.25 Verify cask is not contaminated.
10.2.26 Move cask from the reactor building onto vaiting truck.
11.
REPORTS 11.1 Record and Report Fom For a Shipment of Solid Irradiated Nuclear Fuels must be completed.
11.2 NRC #741 form must be completed and distributed.
O REVISED 11/78
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... p SPENT FUEL S.HIPMENT DATA SHEET 1.
Preliminary contamination survey A. Cask by B. Truck bed by 2
Cosk internal smear A. Underside lid by B. Cask cavity by MUST BE COMPLETED AND SATISFACTORY BEFORE CASK CAN BE LOWERED INTO POOL 3.
Proper basket in cesk by 4.
Cosk wet down by 5.
Fuel Elements loaded Position Fuel #
Position Fuel #
1 7
2 8
3 9
4 10 5
11 6
12 6.
Cask lid in place by MUST BE COMPLETED BEFORE RAISING CASK FROM BOTTOM OF POOI.
7.
Cask wash down by 8.
All cask lid nuts installed by MUST BE COMPLETED BEFORE LOWERING CASK TO BEAM PORT FLOOR 9.
Final Cesk contamination survey A. Lid by B. Cask body by C. Cask pictform by D. Floor crea by 10.
Radiation level A. Cask sides by B.
Cask top by Data Sheet Complete by date Reviewed by date NRC @41 form completed by Ih Orig 3/79 1213 061 142C5 v
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MICHIGAN MEMORIAL PHOENIX PROJECT THE UNIVERSITY OF MICHIGAN QUALITY ASSURANCE PROGRAM
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f TABLE OF CONTENTS Page Section TITLE PAGE TABLE OF CONTENTS i
REVIEW il 1.
INTRODUCTION 1
2.
PROGRAM REQUIREMENTS 1
3.
SAFET( ANALYSIS 4
4.
DESIGN CONTROL 4
5.
PROCUREMENT CONTROL 4
6.
MATERIAL CONTROL 5
g 7.
PROCESS CONTROL 5
8.
INSPECTION 3 5
9.
TESTS 6
10.
DOCUMENTATION 6
11.
AUDITS 9
LIST OF FIGURES 1.
FORD NUCLEAR REACTOR QUALITY ASSURANCE ORGANIZATION 3
2 FORD NUCLEAR REACTOR MODIFICATION REQUEST 8
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This program will be reviewed, revised as required, signed by the Reactor Manager, and dated annually and whenever revisions are made. Revisions will be noted in the right hand column. Revised procedures will be issued to procedure holders at the time of revision.
Reactor Manager Date Revised Sections pggh.
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INTRODUCTION 1.1 Purpose The purpose of this program is to provide requirements for managing, conducting, cnd cuditing the quality assurance program for the design, construction, testing, modification, and maintenance of safety related items and experiments ossociated with the Ford Nuclear Reactor (FNR).
1.2 Applicability The quality assurance program cpplies to replacements of and modifications to safety related items subsequent to the date of implementation. Quality cssurance documentation is not required for the facility as-built and for safety related changes made prior to program implementation.
1.3 Safety Related items Safety related items associated with the FNR 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 g
1.4.1 American National Standards Institute (ANSI) NM.-1976, Quality Assurance Progrcm Requirements for Research Recctors.
2.
PROGRAM REQUIREMENTS 2.1 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), Assistent Reactor Manager, and Supervisor of Reactor Operations. Ad hoc project members include o design engineer and a quality engineer. These functions may not be combined, but may be filled by one of the permanent committee members.
The FNR Safety Review Committee serves to provide technical adviceand must grant final approval of project safety analysis and design prior to implementation.
2.2 Responsil:llities 2.2.1 Reactor Manager.
The Reactor Manager is responsible for:
f Assigning cd hoc Quality Assurance Committee o.
members.
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Scheduling and chairing project reviews.
Assignirg drawing an'd' document i. umbers as required.
c.
d.
Submitting safety enclysis and project design to the FNR Safety Review Committee for opproval.
Submitting License end Technical Specification e.
1 omendments to the NRC as required.
I 2.2.2 Supervisor of Reactor Operations. The Supervisor of l
Reactor Operations is responsible for:
l Maintaining a project file which contains copies of l
o.
cil records associcted with the project.
l b.
Maintaining mecsuring and test equipment properly L
calibrated.
I 2.2.3 Design Engineer. The design engineer is responsible for:
f Performing a safety analysis including Technical i
c.
l.
Specification cnd standards requirements.
b.
Developing the required design.
Preparing informction required for procurement I
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documenh.
d.
Controlling procured material upon arrival at the
- facility, Preparing procedures for installation and tests.
e.
f.
Completing drawings, system descriptions, procedures, regulations, and changes to the Technical Specifications and License es required.
g.
Maintaining a complete file with the Supervisor of Reactor Operctions of all work related to the modification.
2.2.4 Quality Engineer.
The quality engineer is responsible for:
a.
' Verification of design adequacy.
b.
Disposition of non-conforming matericIs and parts.
c.
Performing inspections.
d.
Verification of tests.
2.3 Project Review Meetings The Quality Assurance Committee will meet to review project safety h
analysis, design, installation tests, and final documentation package.
The means for implementing Sections 3 - 10 will be established on a project basis at the review meeting.
ORIG S/78 1213 066 p
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Sofety Review Committee i
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Quality Assurance Technical Specifications Committee Auditor Reactor Manager O
Assistant Ad Hoc Project Supervisor Reactor Manager Members Reactor Operations Design Quality Engineer Engineer FIGURE 1
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FORD NUCLEAR REACTOR OUALITY ASSURANCE ORGANIZATION ORIG 5/78 7
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' O 2.3.1 Design Adequacy.
Designs will be reviewed for reactor physics implications; thermal, hydraulic, and mechanical stress; accident analysis; material compatibility; accessibility for in-service inspection, maintenance, and repair; and interfaces with other systems.
2.4 Experimental Equipment The quality assurance program will provide controls over the fabrication and installation of experimental equipment to the extent that these relate to reactor safety.
2.5 Corrective Action Sisa!ficant conditions detrimentel to the quality of safety-related items, such as failures, malfunctions, and deficiencies, will be promptly identified, the cause determined, and corrective action taker to preclude repetition.
3.
SAFEW ANALYSIS As o preliminary step ;n any safety related modification, a safety analysis will be parformed. The safety anal sis will analyze the efety implications g
of the modification. Verification n est be provided that the probability of occurrence or consequences of an accident have not been increased, the possibility of an, accident or malfunction of a different type has not been created, and the margin of safety in Technical Specificaricns has not decreased.
4.
DESIGN CONTROL Applicable codes, standards, and regulatory i quirements will be incorporated into the design of safety related items and experiments.
Design adequacy will be verified by design review, alternate calculations, or a test program. Verification shculd include checks of such characteristics as compatibility of materials; suitability of application of materials, parts, and processes; accessibility for in-serv *ce inspection, maintenance and repair; prcper interfacing of subsystems; and completeness of acceptance criteria.
5.
PROCUREMENT CONTROL, Applicable codes, standards, and regulatory requirements will be included in safety related item procurement documents. To the extent determined by the safety requirements of the final system, procurement documents will require contractors or subcontractors to provide apprcpriate quality Q
assurance ' ontrols, which may include, but are not limited to, functions such c
as inspections, tests, and controls over materials, processes and nonconfo7 nances, p
ORIG 5/78 1213 068
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Changes +o procurement documents will be subject to controls commensurate with those for the original procurements.
Assurance will be provided that procured items or services conform to procurement documents by such measures os source evaluation, contractor furnished evidence, inspection at source, or inspection upon receipt, as appropriate.
6.
MATERIAL CONTROL.
Control of the identification, handling, storage, thipping, cleaning, and preservation of safety related material and equipment will be established as deemed necesscry by the Quality Assurance Committee.
6.1 Nonconforming Material and Parts Nonconfnrming materials and parts will be identified, segregated, and disposed of. Disposition will be accomplished after o review by the Quality Assurance Committee and will consist of acceptance, repair, rework, or rejection.
7.
PROCESS CONTROL i
tep Processing of materials for safety related items will be accomplished under controlled conditions in accordance with cpplicable codes, stondcrds, and specifications. Controls will be cpplied to the extent oppropricte, with particular emphasis on those for specific processes, such as crimping, soldering, welding, hect treating, cleaning and nondestructive examination.
Procedures, equipment and qualifications of personnel will be defined for those special processes not covered by existing codes or standards.
8.
INSPECTIONS Inspection requirements cpply to procurements, construction, modification, maintencnce, and experiment equipment fabrication, and will include, to the opplicable extent the following:
Inspection procedures, specifying the characteristics to be a.
inspected, sampling plans, and ceceptance criteria.
b.
Description of process monitoring action for those situations in j
which inspection is impossible or disadvantageous.
Specificction of mandatery inspection hold points.
c.
i d.
Procedures for identifying inspection and test status, so that only items that have passed the nquired inspections and tests are used, Q,
installed, or operated. No, conforming items will be electly identifled.
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.. 0 Procedures for required in-service inspection of completed systems, e.
structures, and components.
9.
TESTS
'ihe test prograa will cover required tests, including prototype qualification tests, proof tests prior to installation, and functioncl tests.
Test procedures will specify appropriate prerequisite and monitoring requirements, equipment to be used, persennel training requirements, suitable environmental conditions, and provisions for data at.s isition and u
documentation as cpplicable.
9.1 Mecsuring and Test Equipment Tools, gages, instruments, and other measuring and testing devices used in activities affecting the quality cf safety-related items will be available, properly controlled, properly calibrated, and adjusted at the required intervals.
10.
DOCUMENTATION t
All activities offecting scfety-related items will be formally identified and h
documented. Documentation will include the cpplicable procedures, reviews, and other measures to be applied.
10.1 Design Documentation Facility drawings, procedures, and regulations will be completed and
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updated as on integral pcrt of a facility modification. All or part j
of the drawings and documents described below may be required es I
determined at the design review.
10.1.1 Focility Drawing Index. New drawings will be added to the facility drowing index as required to complete o modification. The Recctor Manager will assign drawing i
numbers at the project review meeting.
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10.1.2 System Description. A brief but complete description of the modification st= ting its purposes, function, operation, and maintenance requirements.
I 10.1.3 Block Diagram. A bcsic logic block diagram that indicates the major mechanical or instrumentation components.
10.1.4 Detailed System of Circuit Schematic Diagrams.
Mechanical or instrumentation diagrams in sufficient detail to perform maintenance and repair.
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O 10.1.5 Design Notebook. A notebook kept by the design engineer contcining ossumpt, ions, design basis, dato, observations and sketches.
10.2 Document issue and Change 10.2.1 Ford Nuclear Reactor Modification Request.
A mcdification request may be requested by any staff member for changes to the physical facility, procedures, or regulations.
The requester is responsible for completing the modification descript:on and safety implications to the extent that he is owcre of them.
All changes to drawings, procedures, end regulations will be made via modification requests. The reviewed modification request number will serve as the authorizction for.,ew drawings and making changes to existing drawings. The Reactor Manager will complete sections 5 and 6 as items are completed.
10.2.2 Drawing Title Block. Each facility drawing will contain a title block with the fcllowing information: A title block will be added to existing drawings if required.
O leiodReq
!ssue Design Reactor LTR Date N umber Description Draftsman Engineer Manager 10.3 Quality Assurance Records
.ss)
The Quality Assurance Program includes documentation of activities affecting quality of safety relcted items. Records will be retained for ORIG 5/78 1213 071
-a-FIGURE 2 FORD NUCLEAR REACTOR MODIFICATION REQUESTNO.
1.
Modification
Description:
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 an accident or malfunction of different type created.
3.3 Margin of safety in Technical Specifications decreased.
~
4 Design Engineer:
1213 072 Quality Engineer:
5.
Project Record Requirements:
Required '
Completed O
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 Change 5.10 NRC Apnroval 10CFR50.59(C) 5.11 Procurement Review
- 5. 12 Material Control Review 5.13 Process Control Review 5.14 Inspections 5.15 Tests 5.16 Non-Conforming Materials F
5.17 Failure Records 6.
Comnia ted.
Date:
ORIG S/7A
the life of the system, equipment, or. experiment and will be identified and retrievable throughout their retention period.
The Supervisor of Reactor Operations will maintain a project file for each safety related item which includes-c.
Modification Request.
Each review item completed and dated when completed. Final review approved by the Reactor Manager.
b.
Safety Analysis c.
Design Review d.
Procurement Review e.
Material Control Review f.
Process Control Review g.
Inspections h.
Tesh I.
Non-conforming Materials i.
Failure Records 11.
AUDITS An audit will be performed annually of each safety related project begun, in progress, or completed during the year.
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