ML19209C960
| ML19209C960 | |
| Person / Time | |
|---|---|
| Site: | 07106698 |
| Issue date: | 09/24/1979 |
| From: | Donnell J NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE |
| To: | Potapovs U NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| REF-QA-99900331 NUDOCS 7910180518 | |
| Download: ML19209C960 (6) | |
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T+ v 572 '5 September 19, 1979 JRD/79/06/ETS U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 Attention:
Mr. Uldis Potapovs, Chief
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Reference:
Docket 99900331/79-01 Gentlemen:
QA Program Inspection Conducted July 31 - August 3, 1979 At the Facility of Excelco Developments Inc.
in Silver Creek, New York Excelco Developments, Inc. (EDI) has furnished us a copy of the inspection report prepared by your office and transmitted to them under your letter of September 6, 1979.
The subject inspection involved a review of fabrication records pertaining to spent fuel shipping casks manufactured by EDI for Nuclear Assurance Corporation (NAC).
We are desirous that the issues raised in the report be resolved expeditiously and take this opportunity to respond directly to the Nuclear Regulatory Commission (NRC) in this matter.
The inspection focused primarily on the fabrication records of four casks, NAC-1A through NAC-lD, which were manufactured in 1973/1974.
Also included in the inspection were the records on the NAC-lE cask, manufactured in 1978/1979; however, the fabrication of this fifth cask has been more thoroughly treated in three separate NRC inspections conducted during 1978.
All deviations identified in those inspections have been satisfac-torily addressed or resolved (
Reference:
Docket #99900331/78-01, 02, and 03).
With respect to casks NAC-1A through NAC-lD, the findings in the present inspection, conducted five years after the fact, must be addressed with appreciation for the quality assurance requirements in effect at the time of manuf acture and the establishment of those requirements through the contractual relationship between NAC and EDI.
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1176
,514
U.
S. Nuclear Regulatory Commission Page Two September 19, 1979 s
In 1973 NAC contracted with EDI for fabrication of four spent fuel shipping casks to the requirements of SAC specifi-ca lon NAC0001 (Revision 1) and NF5 Drawing E10030 (Revision 12).
In accordance with the NAC0001 specification, EDI submitted a Quality Assurance Program Plan for MAC-1 Spent Fuel Shipping Casks.
Included by reference in the plan were EDI'r Quality Control Procedures QC-0202 through QC-0213 and detailed proce-dures for welding, NDT, and acceptance tests for implementation of the program.
NAC approved the plan and retained the United States Testing Company, Inc. as its Ouality Assurance Admini-strator.
To provide guidance for the Quality Assurance Administrator, an NAC Quality Assurance Implementation Manual was issued in February 1974 with specific procedures for a program that would satisfy the requirements of 10CFR50, Appendix B and the then proposed 10CFR71, Appendix E.
The NAC0001 specification incorporates by reference certain sections of the ASME Code, e.g.,
all welds shall be per-formed by qualified welders who mee: the requirements of (have pass.i the test as required by) the ASME Boiler and Pressure Vessel Code,Section IX."
However, since the casks were not required to be "N" stamped vessels, Excelco was not required to meet all Code requirements.
The quality assurance re-quirements imposed upon EDI by NAC and NAC's control of EDI during fabrication of the casks were based on the plan and procedures outlined above.
Contractually, the procurement of the fifth cask, NAC-lE, was to the same requirements as those of the first four.
As a result of the NRC inspection at Excelco in March 1978, the SAC 0001 specification was revised to incorporate a later re-vision of the ASME Code, where it is referenced in the speci-fication.
With the foregoing as background, we offer the following specific responses to each of the infividual items C) in the NOTICE OF DEVIATION:
(A through A.
(Non-Destructive Test Ezaluation) 1.
(Radiographs)
The manufacturing drawings for the NAC-1 Spent Fuel Shipping Cask require five X-rays on each 1176 515
U. S. Nuclear Regulatory Commission s
Page Three September 19, 1979 i
cask - one by the supplier of the inner shell and four by EDI.
During 1974 each of the films was evalwated by a Level III inspector at EDI and accepted.
Each weld film was also evaluated by another Level III inspector, NAC's Quality Administrator, C.
H. McDonnell of U.S.
Testing, and accepted.
Finally, the films were reviewed by the Acomic Energy Commission's (AEC's) inspector, Mr. A.
R.
Herdt, Metallurgical Engineer, in October 1974.
His report states:
"No deficiencies or violations te e noted."
(See Attachment A).
I. T background on the X-ray of the C-2 weld, T.t achment A provides excerpts from inspection rep rts by both U.S. Testing and the AFC dated at vcrious times in 1974.
The reports docu-ment the difficulties encountered in radio-graphing the weld, the radiographic technique developed to solve the problem, and final closure of the ite.m.
In the more recent 1978 NRC inspections of the NAC-lE cask fabrication, no issue was raised concerning the radiographic procedure for the C-2 weld.
On December 23, 1974, the AEC acknowledged "without further questions" NAC's response to the Report of Inspection forwarded to NAC in November 1974.
A copy of the AEC acknowledge-ment is provided as Attachment B.
Given the above documentation, the radiographic techniques and the interpretation of the results must be considered acceptable under the conditions and requirements of 1974.
Current interpretation of the films may be questioned, since the film quality may have suffered some degradation in the intervening five years due to the conditions of storage, e.g.,
temperature, humidity, air pollutants, etc.
1176 516
U. S. Nuclear Regulatory Commission Page Four September 19, 1979 2.
(" Missing" Records in OC Work Package)
Immediately follo.in:
he exit interview of the
'ubject inspection, the following action was taken:
a)
NAC and EDI undertook a review of thu manufacturing / inspection records.
Each document identified in the exit interview as " missing" was found and reviewed.
In all cases the "found" documents verified compliance with the manufacturing specifica-tions.
The difficulty in locating certain records was due largel-23 misfiling.
Copies of the specific " missing" documents cit 2d in the NOTICE OF DEVIATION are attached as follows:
Attachment C - Radiographic records of weld C-51 for casks C and D.
Attachment D - Results of the penetrant tests on weld C-16 on casks A through D.
Attachment E - Results of the penetrant tests on the lead hole plug, weld C-5, on the cask base assembly for casks A through D.
b)
An independent review was made by NAC cover-ing all weld parameter sheets and the in-spection called out (PT or RT) for each assembly (assembly nos. 200 through 239).
In every case documentation was found to verify that the required inspection was performed, either at the time called out or at a later assembly point.
c)
As a part of the review in (b) above, the drawing revision referenced on each weld parameter sheet was compared with the docu-ced history of drawing revisions.
All fabrication was verified to be in accordance with the final revision of the applicable drawing.
Drawing revisions subsequent to fabrication were for error correction or changing "NFS" to "?:AC ".
1176 517
U. S. Nuclear Regulatory Commicsion Page Five September 19, 1979 3.
(Test Procedures)
As described earlier, the quality assurance require-ments, including acceptance tests, were to be in accordance with EDI procedures approved by NAC.
These procedures require that gage calibration be verified prior to testing, but dc not include a specific requirement for documentation of the gage used in each test.
Conformance to the test proco-dures, including verification of gage calibration, was documenced in two AIC inspections conducted during 1974 and in five inspections by U.
S. Test-ing.
For the NAC-lE fabrication and test program, the same acceptance test procedures are applicable.
For these tests the U.S. Testing check list for selected hold points has been reviewed to verify that it contains items sufficient to document conformance to the test procedures, including gage selection and calibration.
Selected documents relative to the calibration of acceptance test instruments are given in Attachment F.
The NAC0001 specification provides that the fabricator is to parform the thermal test and submit the test data to NAC for review and evaluation.
In the forma: letters of acceptance from NAC to EDI covering casks NAC-1A through NAC-lD, NAC verified the acceptability of its evaluations with the following language:
. acceptance is
. based upon inspections performed, surveillance of tests, and review of quality assurance documentation."
N;C has reverified the acceptability of the ther-mal test data for both the original acceptance tesh Pnd the retest performed after three years' service.
The analysis reconfirmed in both in-stances that the test data were within the accep-tance limits specified in che Safety Analysis Report.
Moreover, the results of the three year thermal test, as required by the Certificate of Compliance, confirmed that there has been no deterioration in the capacity of the cask wall to transfer heat to the encironment.
1176 318
U.S. Nuclear Regulatory Commission Page Six September 19, 1979 C.
(Documentation of Material Spacification)
The cited document covering the balsa wood used for impact limiters is provided as Attachment G.
In response to Item 4.b., Unresolved Items in the DETAILS SECTION of the subject inspection report, the qualification records of the welders used in fabrication of the casks have been furnished to your office under our letter dated August 17, 1979.
We have reviewed each of the ccaments under Item 4.c.,
Comments, in the DETAILS SECTION of the inspection report.
Several of these comments have been addressed above in our responses to the NOTICE OF DEVIATION.
Most of the remaining items have been resolved as a result of the review of fabri-cation records conducted by NAC subsequent to the inspection, e.g., drawing status and the lead pour certificate of com-pliance.
Other items vill be addressed through Revision 19 to UFS Drawing E10080 which will be submitted to NRC, Trans-portation Branch, for approval as an amendment to the Certificate of Compliance.
We request your consideration of this response as soon as possible and stand ready to answer any additional questions you may have.
Sincerely, UUCLEAR ASSU'.ANCE CORPORATION 03%Q J._
. Donnell, Jr. \\
JRD:cnr Vice President cc:
Mr.
L.
A.
Brooks Excelco Developments, Inc.
Mr.
C.
E. MacDonald, Chief Transportation Branch U.
S. Nuclear Regulatory Commission 1176 519
4 U.
S. Testing Audit Reports of Inspection at Excelco Developments, Incorporated on 10 May 1974 (Report #1018-6, pages 3 and 4) and on 20 May 1974 (Report
- 1018-S, eaces 2 and 3).
RADIOGRAPHIC PROCEDURE A:omic Energy Commission,During the audit at Nuclear Assura it was requested that the tables noted in paragraphs 4.1.1, 4.1.2, 4.2, and 4.5 of Procedure SR-ND-25 be clarified.
This was brought c the attention of the Excelco Quality Assurance Manager who will make this revision and submit it to Excelco.
RADIOGRAPHIC REPORTING PROCEDURE It was also requested during the AEC audit at Nuclaar Assurance th a t the U.S. Testing Representative confirm that Excelco notes on the radiographic report sheets all eraphs even if they are well within code requirements. indications found o work were reviewed.this visit to Excelco radiographic report sheets for During found on radiographs are reported by Excelco.It can be confirned t RADIOGRAPHS OF WELD C-2 Difficulty was weld of the inner cylinder to the topencountered in radiographing the cir This is the last weld in the assembly of the inner-flange, E-3 7 6 9 -3.
outer cylinders to the base section and top flange prior to the lead pour.
Because of the configuration of the assembly it is necessary to have the radiographic source. positioned outside the outer cylinder with the film on the inside weld surf ace of the inner cylinder.
The penetrameter is on the film side.
(1.25"), the copper fins attached to the insideThe ra the outer shell surface of the outer shell, the air gap between the outer and inner shell, the inner shell weld back up strip, (.125"), and the inner shell weld (.3125").
Class 2 equipment,Fcr welds meeting the fabrication requirements IX - 3325 - 1, Appendix IX of Section III.a number 5 pene:rameter is requ To interpret the radio-graphy to a 2T level of quality, the 2T hole for a number trameter is 0.020 inches in diameter 10 pene-Section III and ASTM E-142.
per Paragraph IX-3325 of Radiocraphs taken with the penetrameter were difficult to interpret since the 2 T holg could be seen with difficuity.
coulc not be clearly seen, but 1176 520
ATTACIMENT A P, age 2 of 4 Nuclear Assurance Corporation 1018-6 One radiograph, a techniqua shot, on the weld with a slot was taken using a penetrameter was allowable by Section III Paragraphs 1/4 inch long and 0.010 inca wide.
This IX-3325 and IX-3334.5 of the ASME Code.
Parac aph IX-3334.5 further requires that a 2T hole or smaller shall appear.
As previously. stated the 2T hole could be interpreted with dif ficulty.
Based on the acceptance by Excelco of this technique shot, the cir-cumferential weld was radiographed without penetrameters.
All radiographic exposure parameters remained the same for each exposure These radiographs were reviewed by the U.S. Testing Representative and the results presented on the enclosed report f o rm s.
The measured density ranged from 2.7 to 3.i.
Acceptance densi.ty limits are from 2.0 to 3.8.
In general the radiographs are diff' cult to read because of the outer shell and the copper fins.
However, they can be interpreted.
The U.S.
within the ASME Code for allowable indications. Testing Represe It is required, since the radiographic technique is not within that of the approved radiographic procedures, that Excelco write and submit a radiographic procedure, which includes the use of the technique exposure, for this weld.
This procedure will require approval by Nuclear Assurance.
This is an "0?EN ITEM".
REMAIhING RADIOGRAPHS Radiographs of the following were reviewed.
Inner cylinder to base Weld C-1.
Base casting weld neck.
The results are presented on the enclosed report sheets.
graphs were acceptable.
All radio-DYE PENETRANT EXAMINATIONS Dye penetrant examinations records were reviewed for the following areas.
Refe ence is made to Report No. 1018-4 pages 7 and 8 where a check list was presented.
1176 521
ATTACIIMENT A Page 3 of 4 4
SYNDPSIS OF VISIT Radiographs of the inner cylinder weld to the base casting, and the weld neck areas of the top lid flange and the baie cast-ing of cask number 2 were reviewed and were acceptable.
The radiographs of the top lid fler.ge weld to the inner cylindar were not in strict accordanca with the requirements of the Ex-celco radiographic procedure Either a new procedure, or an, or Section III of the ASME Code.
ammendment co the original proce-dure is required for this weld.
This is an "0 PEN ITEM".
The inside Jiameter of cask number 2 was within tolera, ne The BWR Fuel can fitted into the inner cylinder without dit ficul ty Cask number 1 was did not make full inspected after the lead pour.
The BWR fuel can insertion into the inner cylinder (Later lead was found in the inner cylinder and this fuel can did make full insertion. ) Stif feners requirements.
in the can was found. to be out of drawing REPORT OF IISIT
->t PD M 018!NAL This visit was made-to Excelco to review radiographs, documenta-Lead for the lead pour. tion and to inspect cask number 2 prior to its Cask number one had been returned and was subjected to a test whether the BWR Failed Fuel can could be inserted freely into the inner cylinder.
Followingare,theresultsofthisv-! sit.
Radiocrachs Radiographs of the top lid flange to the inner cylinder, lid flange and the bottom cask were reviewed. tom base to t tie bot-The 2diographs of the top lid flan e to inner cylinder weld, Weld C-2, do not meet the requiremen;ts of either the Excelec Pro-cedure SR-ND-25 or Section III o' the ASME Code.
used involves a technique shot where the penetrameter is placedThe tec on the weld.
In this case a Number 7 r enetrameter, table, with a 0.010 slit which is a ccep-1/4 inch icng is used on the film side.
1176 522 Dano O
ATTACIU4ENT A Page 4 of 4 Interpretation is the ability to see the slit.
If this techni-que shot without penetrameters, using the same exposure paramete The Section III, Appendix IX of the Code, allcws the use of the slit with this size penetrameter.
Hewever, for film sida penetra-meters both the slit and at leas: the 2T hole must be se2a.
The use of a :echnique shot is not s tri::ly allowed by the Code but depends upon an agreement between the customer and the f abricator For radiography Welo C-2, the Excel:o radiographic procedure must be ammended to include this technique, or a separate procedure must be written for this one weld.
must be submitted to Nuclear ' Assurance for approval.In either case the p "0 PEN ITEM".
This is an Difficulty was encoun~tered with the original radiography for this wel d.
tions of the cask.This weld is the closure weld for the inner and outer por-inside weld surface of the innerThis requires that the film be placed on the The radiation must pass through the outer cylindercylinder with the source (about 1.25" thick), the copper cooling fins on the outer shell and the inner cylinder before penetrating the weld of the inner cylinder (0.375" thick).
In addition there wel d.
is.a back up ring on the inner cylinder shell, and additionalThere was scattering of the radiation due to the cask ou interference from the copper fins.
For this reason the above technique was deveio ed.
r No indications were noted on these radiographs.
Radiographs of Weld C-1, the inner cylinder to the base casting were in accordance with the requirements of Section III of the ASME Code.
These radiographs were acceptable.
Radiographs of.'the weld neck areas of the top fiange li d and the These radiographs were acceptable. bottom cas ting were taken NOTE Excelco Develonment Procedure SR-ND-25, " Radiographic Examination re'ised June 14, 1974 was approged by U.S.
iesting procedure,"
v on 12 July 1974 and NAC approval was transmittec to _xcelco on c
15 July 1979.
Item closed.
ATTACHME':T A Page 1 of 1 Atomic Energy Co:Unission (AEC) Report of Inspection at Excelco on 12-14 June 19 74 (Report 70-1510/74-2, Page-I-3) and on 15-17 October 1974 (Report 70-1510/74-3, Page I-
/74-2 Reoort g
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Radiceraohv The inspector reviewed the radiog aphic procedure, SR-ND-26 and :he radiographic acceptance standard.
~
"spe c ::: reviewed :he radiographs and associated doc =enza: ion for the C-1 and C-2 velds,
the caci. flange and base castic; and the inner cylindc-len;i
'u vald sca= =anufactured by Tren: Tu'oe f:
the nunbers 1 and 2 spen:
fuel shipping casks.
The radiog sphs were reviewed for joint identification, date, paraneter size, quality of radiograph density and apparent quality of weld.
The inspector noted that difficulty was encountered it radiographing the circunferentia.1 veld on the inner cylinder to the tap flange, veld C-2.
This is the last veld 1.n :he assenbly of the outer-inner cylinder to :he base seccion and rop flang: prior to the lead pou.
3ccause of the configuration of the assenbly the radiographic source was positioned ou cide the outer cylinder vith the fil on the inside veld surface of the inner cylinder with the penetranater on the film side.
This radiographic technique is a code variance and not entirely withir that of the approved radiographic procedure.
The licensee agreed that Excelco should prepare and sub it for approval of IU.C details of the C-2 veld radiog aphic technique and qualifica:1cn w be included in the radiographic procedure.
The inspector inforned the licensee tha: this iten is unresolved and would be er-%ed d.uring the ner inspection.
No other najor discrepancies were noted.
/74-3 Pecort c.
Radiorrachv Excelco has reissued and NAC has approved the radiographic ---<.ation procedure, SR-Nre-25.
The procedure now contadas the details on the C-2 veld radiographic technique.
~~he inspec:or reviewed the revised radiographic procedure, radi:g aphs and associated docu=enta-tion for the C-1 and C-2 velds, the cask flange and base castings and the inner cylindrical longtu '--' veld sean ufactured by d
Trent Tube for the nu=bers 3 and 4 spent fuel shipping casks.
"he radiographs were reviewed for joint identification, date, penetrcneter size, quality of radiograph density zad apparent quality of velds.
No deficiencies or violat. ions were noted.
The inspector considers the unresolved iten on radiographic procedure closed.
1176 524
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Thank you for your letter of Decc=ber 2,1974, infor=ing us of steps you h ve taken to correct the violation conce
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We appreciate your cooperation with us.
Very truly yours,
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ATTACHMENT F COPIES OF SELECTED DOCUMENTS RELATING TO THE CALIBRATION OF ACCEPTANCE TEST ISSTRUMENTS Copies of selected pages of Excelco acceptance test procedures and U.S. Testing Witness Check Lists are attached.
Documents include:
1.
Hydrostatic Test Specifications - Page 1 and Data Sheet.
2.
Pressurization Test Specification for Double O-Ring Seal - Page 1 and Data Sheet.
3.
U. S. Testing Check List for NAC-lE, Witness Point 4.
Note items 5, 6, and 7.
4.
U.
S. Testing Check List for NAC-lE, Witness Point 8.
Note item 4.
5.
U. S. Testing Check List for NAC-1E, Witness Point 7, with documentation of the ve-ification to each item.
6.
Thermal Test Procedure - Page 2 and a copy of a thermal test certification providSd by Excelco.
This particular certification was for NAC-1A.
i176 536
ATTACHMENT F EXCEL.00 del'El.0Pi.iEllTS, li!C. OPEMilliG lllSTRUCT10ll ogsaarisc insTaucTion D^75 '5505o
'~5'au
o~
No i.
1/21/74
"55
h"iDR0 STATIC TEST SPECIFICATIONS h/26/7h isssgo By PAGE
.3 QUALITY Agr CONTROL i.
~
.aNAGER 1.0 SCOPE 1.1 This specification covers the procedure to be followed to accomplish the hydrostatic test on assenblies and su b -
assenblies to the requirenents of the Nuclear Assuranca Corporation.
2.0 R EEP2NCES m..
2.1 Excelco Dev., Inc. S.O.
3769 2.2 Nuclear Assurance Corporation, NAC0001 Rev. 1 30 EQUIPME!'T 31 Water Pressure pump and denineralised water.
32 Relief valve set to relieve at test pressure at plus 3 per cent.
33 Indicating Pressure Gauge.
331 The indicating pressure gauges shall preferably have q).
dials graduated over a range of double the intended maxinun te s t pre ssure, but in no case shall the lower 20% of the pressure gauge be used to indicate the te s t pre s sure.
pp.3.4 Pressure gauges shall be calibrated within the past 6 m.caths prior to te st.
3.$
Valve for isolating cask fron pressure punp.
1176 337 h.0 PREoARATICN PRIOR TO HYDROSTATIC EST 41 The assembly cr subassenbl7 shall be nade pressure ti ;ht.
This nay be accenplished bf using blind flanges, screwed plugs, or by the velding of tenporary covers on openings that cannot be closed by other neans.
The nethod shall be specified on the drawing, giving detailed instructions regarding weld procedures, location of vents to purse air pockets and other infornation neecasury to achieve a cressure
ATTACIDIENT" F EXCELC0 DEVELOPMEHTS,100. OPERAilHG INSTRUCTIO!!
susu '
EfDR0 STATIC TEST SPECI-
'"""uc t'o ' No-o^rc issuro Pect tio
.rICATIO:IS 1/21/7h SR -?? -o. a oc nz-issuto E
i.
h/26/7h EfDR0 STATIC 3ST RECORD 2bricator 7
D s. ; c Customer P.O.
IIo.
S. O. Ilo.
?crt ?!ame Part Ilo., Serial lio, d
w-Dwg. No.
Revision dela Test ri,JC Test Disscsicion ITo.
Pressure Tenn.
I Accent He jec t m.,,
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'1176 538 Operator Date Inspector Date
ATTACE'4ENT F EXCELCO DE'lELOPi.iEiiTS, ll!0. OPERATl!!B !!!STRUCTION OP E R ATING INSTRUCTION O'"
- ~~'O' C
1/22/74 S**'
S..
_ _ -227 PRESSURIZATION TEST SPECIFICATION D'7c Rt '55sto rr FOR DOUBLE 0-RING SEAL 4/26/74 issute By PA t
-.o ner QUALITY CONTROL 1
3
.,ANAGER i
i 1.0 SCOPE 1.1 This specificatica covers the procedure to be followed to accomplish the pressurization test on the double 0-ring seal of the cask to the recuiremen ts of the Nuclear Assurance Corporation, NAC-1 Spent Fuel Snipping C ack.
~
" ~ " ' "
P90li On!@
2.1 Excelco Dev., Inc. S.O.
3941 2.2 Nuclear Assurance Corporatica, NAC 0001 Rev.
3 t-
,)
30 ECUIPMENT 31 Pressure Pump, or gas bottle with pressure regulator.
32 Indicating Pressure Gauges
>- 3 2.1 The indication pressure gauges shall preferably have dials graduated over a range of double the intended maximun test pressure, but in no case shall the lower 20% of the pressure gauge be used to indicate the test pressure.
- n 3 3 Pressure ganges shall be calibrated within the past 6 months prior to test.
34 valve for isola ting cask frcm pre ssure system.
40 PRE?ARATION PRIOR TO PRESSURIZATIO.'T TEST k.1 The casembly shall be made pressure tight.
This may be
~
accenplished by using bli.ni. flanges, screwed plugs, or by the welding of temporar-verc on openings that e
cannot be closed by other neans.
k.2 Pressurization will then be effected with the aid of the gasket leak valve to include the inner and outer C-ring seals.
=
1176 539
ATTACHMENT'F EXCELC0 DEVELO?i,IE.!!TS, lii0. OPERATli.'8 liiSTRi!CTI0il 5 * *:' PPZSSURICATIO:I TEST
~155UID Pact No.
INsM.
- oN No Dan SPECIFICATI0:I FC.9 DOUBLE 0-RI:i]
1/22/7!1 o :. r, cc SR __-227 fr 0
"*'55
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er
._ s PRE 25t' (IZATIO:I TEST RECORD Fabricator Date C is t ome r P.O. IIo.
S.O. IIo.
Part liene i
i Part tio., Serial IIo.
Dwg. No.
Revision Test Test Disposition Item Pressure Tenp.
Accept. nejec; Remarks
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'i 6
l d
4 Operator Date Inspector Date gggf Wddn'NYL i176 540
ATTACFJiENT F CHECK LIST Fabrication of Nuclear Assurance Spent Fuel Shipping Cask.
Witness Point No. 4 Hydrostatic Test 1.
Verify that the test procedure is in the test area.
2.
Verify that all operations of the work traveller preceding this test have been signed-off.
3.
Verify that the test and the procedure are identified on the work trav211er.
4.
Verify that demineralized water is used for the test.
- -- 5.
Verify that the pressure gauge has the correct pressure range.
- 6.
Verify that the pressure gauges calibrations are current.
--7.
Verify that the test is conducted in accordance with the requirements of the test procedure.
8.
Inspect the cask.
~
9.
Verify that Excelco has accepted the test and has completed the test report.
10.
Verify that the test report and work traveller are properly signed.
ii76 541
ATTACHMENT"F 9
CHECK LIST Fabrication of Nuclear Assurance Spent Fuel Shipping Cask Witness Point 8 Thermal Test A.
Test Praparation.
1.
Verify Thermal Test Procedure is noted on traveller.
2.
Verify that all operations prior to the Thermal Test on the traveller are signed-off.
3.
Verify that Thermal Test procedure is available in the test area.
P-- 4.
Verify that all test instrumentation used to control Thermal systems and to obtain data have been calibrated and that the calibrations are current.
5.
Verify that t.'iermo-couples are installed as required.
6.
Verify that all instrument and electrical systems have been checked for continuity.
7.
Verify test set-up is complete ar.o ready for testing.
B.
First Thermal Test (Neutron Shield Tank Empty) 1.
Verify demineralized water is used to fill inner cavity.
2.
Verify that the cask is heated in accordance with the procedure requirements.
1176 542
-)-
ATTACIDIENT F UNITED STATES TESTING COMPANY, INC.
S
)-
aQi CHECK LIST
-),
f Fabrication of Nuclear Assurance Spent Shipping Cask Witness Point No. 7 jggga C /, 7 j //,4yc 4
Helium Leak Test 1.
Verify that the test prqcedure is identified on the work traveller.
_VurnaD 2.
Verify that the test pro l'cMure is available at the test area.
d^</AG 3.
Verify that test data recording sheets are available at the test area.
VlY-rfido 4.
Verify that all traveller operations prier to the helium leak tests bkr&<G;.o have been signed-off.
5.
Verify that test pressure gauges were calibrated.
t/ce '<O n
6.
Verify that the helium leak te/s' equipment was calibrated against a En nsdo standard leak.
7.
Verify that the helium leak test is being conducted in accordance with the procedure requirements, f
8.
Verify that test results are recorded a;d accepted by Excelco QA.
/~n t/< sa c 9.
Verify that the traveller is properly si,f&
cnedeoff for this operation.
V f/f.o 1176 543 g
ATTACHMENT'F.
EXCEI.00 DE'!El.0PMEHIS, ll10. OPERAilMS IDSTRUCT10'1 S;e;t:T c'.:r. -.o..* 3.i_ * *:' ' m 0..;0 P 'fn E
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4 3.1 5 A cet ar-three thernoccupie s mounted circumfeNentially on the neucron shield tank surface adjacent to the thernoccuples on the in :enal surface.
They shall be silver solder braced to a stainless steel plate and the plate welded to the surfano.
3.1.6 A set of three thermoccuples mounted on the 39 1/4 0.D.
neutron shield tank at it's midpoint and in line with the other external thermoccuples.
The thermocouple s shall be silver solder braced to a stainless steel plate and the plate welded to the surface.
3.1.7 One thermocouple is to S= located 1 the 1.2,5 inch thick outer shell penetratini neutron shield tank through
.ne a drain plug opening that is located 135 from twelve o' clock.
Near the drain plug, there shall be a therno-couple located on the neutron shield tank.
3 1.8 One thermocouple which records the test area snbient temperature.
3 1.9 A pressure gage shall be installed in one of the upper neutror shield tanks.
i 3 1.10 A pressure gage and a 240 PSIG relief valve shall be installed in the test head.
3 111 Pressure gages shall be nonitored and recorded by te sting personnel.
40
- fEST PREPA?.ATION k.1 Wattmeter, thermocouples, potentic=eter, pre ssure gage s and 7--
other te st equipment shall be cal _brated pricr to test.
4.2 Cask shall be positioned abcve groEnd in the horizontal position and shall be configured as shown on test schenatic drawing 13367/2-35 The tes; head shall be insulated after the cask is set-up for testing.
4.3 Thernoccuples shall.be located and installed per 314,315, 3 1.6 and 3 1.7 h.4 The heater units shall be inserted in the test head and the test nesd secured in place.
E.5 All instrunentatica and electrical systens shall be cnnected and checked for continuit7, Das 13367/2-37.
' i176 T44
ATTACHMENT F T
EXCELCO DE'/ELOPT.IEllTS, ITic. OPERATliiG IflSTRilCTl0ll i
j SveJECT
- a s' R u C f.C *. Nc D a rf isstro Fa:t NO i
1/22/74 I --J) i THIFJiAL TEST CEhTIFICATION SR oo-173 4/26/74 c
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c._ m..n r r m_ 0 a..
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rate 10/7/74 r
Fabricator Excelco Developments Inc.
S.0.#
3769 Customer Nuclear Assurance Corp.
P.O.#
UAC-1 Ite Tested Shipping Cask #1 Dug No. 1C080 Spec.NAC0C01 Rev. No. 1 The above lieted iten has been Thermal Tested in
)
accordance with Excelco The.~_al Test Procedr e QC-SR-FP-173 Date of F,IRST THEPSAL TEST 10/5/74 0perator A.Acksel Icte of SECOND THER'U.L TEST 9/28/74 Operator A.Ackcel 1._
First thernal test originally conducted on August 22,197i.
Second thornal test originally conducted on September 13,197h.
However, this test required a re -run be cause interior position l
of thernoccuples were not correct.
This test was condut ted
~
1 on September 23,197E.
1.-
After this test, the first the rnsl te s t was re -run cn Oc t. 5, 197h to verify that data from the* original tes; was valid.
This i
repeat test verified the original test data.
I 1
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ATTACHMENT G
] W JE.3 G O W J G Q CC C T S t] i gg FJ2DJJO y$y C3GC'vCPAR3V
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2URSES.
P. O.EOX C32 POUGHKEEP312, N3W YOFiX 12302i EM 471-0500
- E37ASL15HED 1C33 CERTIFICATE OF C O M P LT A N C E
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It is hereby certified that all
- ..g..'_.
of the articles called for in
- t your P. O. #
A-417 9 are in accordance with the re-
\\
quirements, specifications and ' '
~
drawingo listed in the aubject order. Any exceptions are as detailed in " Notes" belcw.
LUMB, WOODWORKING COMPANY, INC..
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T'itle:
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Date:
May 21,1974 N O T E S:
1176 546 O
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