ML20151C594
| ML20151C594 | |
| Person / Time | |
|---|---|
| Site: | 07109159, 07109176, 07109177, 07109178, 07109179 |
| Issue date: | 02/16/1988 |
| From: | Betow R LN TECHNOLOGIES CORP. (FORMERLY LONDON NUCLEAR SVCS |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20151C598 | List: |
| References | |
| 29121, LN-88-00107, LN-88-107, NUDOCS 8807220052 | |
| Download: ML20151C594 (3) | |
Text
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' gg RET. URN TO 39848 TECHNOLOGIES c o n r)O R ATI O N 1501 KEY ACAD. COLUMarA. S C. 29201 (803) 25G 4355
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February 16, 1988
(
LN-88-00107 Mr. Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety NMSS United States Nuclear Regulatory Commission Washington, DC 20555
Subject:
Renewal of Certificates of Compliance -
- 9159, 9176, 9177, 9178, 9179
Reference:
Doc.ket 71-9159, 71-9176, 71-9177, 71-9178 and 71-9179
Dear Mr. MacDonald:
LN Technologies is submitting an application for renewal of Certificates of Compliance number 9159 LN 14-1701, 14-170M and 34-170H; number 9176 model LN 14-195L and 14-195H; number 9177 model LN 10-135A; number 9178 model LN 7-100 and number 9178 model 6-80L and LN 6-80H.
This letter consolidates all past applications and ammendments.
All current revisions of these Certificates of Compliance will expire on March 31, 1988.
LN Technologies has renumbered and retitled some procedures referenced in our Certificate of Compliance.
Accordingly we are requesting that editorial changes be made to the cask Certificates of Compliance to reference our new number for cask Certificate of Compliance numbers 9159, 9176, 9177, 9178, 9179, WM-025 "Operating Procedure for Type A Series II Casks", WM-026 "Maintenance and Inspection Procedure for Type A Series II Cank", WM-036 "Soap Bubble Leak Test LN Technologies Type A Series II Shi: ping Cask", and WM-013 "Gamma Scanning of Lead Shielding for LN Type Casks".
The application fee of $750.00 is enclosed (reference 10 CFR 70.12).
Sincerely, M
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4 Roger Betow
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Y A Member of The SNC Group
P LN TECHNOLOCMEO Mr. Charles E. MacDonald, Chief February 16, 1988 Page 2
Enclosure:
Check for $750.00 Attachments:
(I)
Summary of LN Technologies supplements to Cert, of Comp.
9159, 9176, 9177, 9178, 9179 (II)
Cover letter 12/14/84 supplement (1 copy)
(III)
Cover letter 5/14/85 supplement (1 copy)
(IV)
Cover letter 11/22/85 supplement (1 copy)
(V)
LN Technologies Corporation Procedure No. WM-013 4 copies for each C of C.
(VI)
LN Technologies Corporation Procedure No. WM-025 4 copies for each C of C.
(VII)
LN Technologies Corporation Procedure No. WM-026 o
4 copies for each C of C.
(VIII)
LN Technologies Corporation Procedure No. WM-036 4 copies for each C of C.
(IX)
LN Technologies Corporation Drawing No. 5025-M-2005 4 copies for each C of C'.
0 1
A Member of The SNC Group
f LN TECHNOLOG4EJ Summary of LN Technologies supplements to Cert. of Comp.
9159, 9176, 9177, 9178, 9179 i
December 14, 1984 Applying for modifications of all C of C issued in response to the application contained in Docket File Number 71-9159.
May 14, 1985 Re:
USNRC letters dated March 11, 1985, Docket Numbers 71-9154, 71-9176, 71-9177, 71-9178 and 71-9179.
Response to information requested.
November 22, 1985 Re:
USNRC letter dated October 3,
- 1985, Docket Numbers 71-9159, 71-9176, 71-9177, 71-9178 and 71-9179, drawing number 5025M2005 revised to include all information required by 10 CFR 71.
1 A Member of The SNC Group
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PROCESS SERVICES NU S CORPORATION November 22,19S5 m
Charles E. Mac Donald, Chief Transportation Certification Branch Diiision of Fuel Cycle and Material Safety NMSS
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U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i
Reference:
Docket Numbers 71 -915 9, 71 -917 6, 71 -917 7, 71 -917 8, and 71 -917 9 i
Dear Mr. MacDonald:
(
This letter transmits the infortnation requested in your letter dated October 3,19S5.
NUS drawing No. 5025 M 2005, sheet 2 of 2, has been revised to include all the informati,n required by 10C F R71 for the proper marking of the subjec t shipping packages.
Additional revisions of this drawing include items 2, 3 and 4 of the enclosure to your letter of October 3,19S5.
NUS drawing No. 5025 M 2005, sheet 1 of 2, has been revised to include a larger cask lif ting and tie-down lug. Calculations using the larger cask lif ting and tie-down lug show that the safety margin is increased over the use of the previous log.
P!c a se f;nd riK!osed eig7t (S) copies of the aforementioned drawings anJ eight (S) copies of the "Type A Cask Lug" safety margin analysis.
Should you have any additional questions cencerning this matter please contact me.
Since rely;
/
l1]sl,lltLg
'y T. M. Ilipsher Manager, Transportation Services enc!o ures: S cepu', NUS Drawing 5025 M 2005 sheet ! o f 2, Re < !sion C shee t 2 o f 2, Revision E
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NUS PROCESS SERVICES CORPOR ATION May 14, 1985 O
Mr. Charles E.
MacDonald, Chief 3
Transportation Cortification Branch l
Division of Fuel Cycle & Material Safety, NMSS US Nuclear Regulatory Commission Washinqton, DC 20555 Re:
USNRC Letter dated March 11, 1985, Docket Numbers 71-9159, 71-9176, 71-9177, 71-9178, and 71-9179
Dear Mr. MacDonald:
This letter is in response to and transmits the information i
requested in the above referenced letter.
This letter and attachments are intended to supplement NUS Process Services' (NUSPSC) application dated December 14, 1984, as supplemented January 8, 1985 r e qu e s t i ng amendment to package designs approved by Certificates of Compliance Nos. 9159, 9176, 917'7, 9178, and 9179.
Specific responses to each comment and request are addressed in Enclosure 1. references the attached drawing and procedures.
Should you have any additional questions, please contact NUSPSC.
I Sincere y, l
(,
~ Zj h W.
M.
Il psher Manager Transportation Services WMil:pw cc:
4 McCoy, NUSPSC R.
Voit, NUSPSC G.
AnLonucci, NUSED Attachnents: Enclosure 1 "Question Responsen" Drawing No.
5025-M-2005 Rev.
9, Sheet I nf 2 (4 copies)
' of 2 (4 copies)
Drawinq No. 5025-:1-2005 Pev.
D, Sheet NUS Procedure WM-Oll, "Soap Hubble Lr a k Test" Rev. E (8 copies)
NUS Procedure WM-025, "Operatinq Procedure for Type A Series 11 Casks" Rev. B (9 copies)
O estse/E -
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NUS PRCJCESS SERVICES O
Decemte r 14, 1984 Mr. Charl es E. MacDonald, C hi ef Transp]rtation Certification Branch Division of Fuel Cycle and Materi al Saf ety, NMSS Uni ted States Nuclear Regul atory Co mission W as hi n gton, D.C.
20555
Dear Mr. MacDonal d:
NUS Process Services Corp 3 ration, by this letter, f orTnally applies for modifi-cations of all Certificates of Conpliance (C of C) issued in response to the application cont ai ned i n Docket F ile Nunte r 71-9159.
Transport Casks covered by this application are identified and cross ref erenced below:
C c' C N o.
NUP AC Desimation NUSPSC Des ianation 9159 NLP AC 14/19) (l,M and H)
NUS14-170 (L,M and H) 9176 NUP AC 14/210 (L and H)
NUS14-195 (L and H) 91 77 NUP AC 10/140 NUS10-135 A 9178 NUP AC 7/100 NUS 7 -100 9179 NUP AC 6 /100 (L and H)
NUS 6-80 (L and H)
A conplete listing of all docunents submitted as part of this application is provided as Enclcsure (1) to this letter.
Eight copies of all listed docunents are provided f or your use.
In preparing this ap?)ication, NUSPSC identified compnents and materi al s in the ori gi n al application where improvenents could be made to increase the overall durability of these packaans or to increase the available saf ety margins. These Charges are included 3s part of our design drawings as options and are Considered to te minor chanons to the ori gi nal design. To ai d yo u i n yo ur re vi ew, Encl os ur e (2) was prepared showing the areas changed by NUSPSC and our j ustification f or l
each change.
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1 m' TITLE G.A?Ot A SCANNING OF LEAD SHIELDING FOR LN TYPE CASKS TECHNOLOGics C Onpon ATiO N L ~ COPYRIGHT O i9$6 BY LN f ECliNOLOG) ES CORPORA F10l ALL RIGHTS RESERVED. NO PART OF THIS DOCUMENT M/Y BE REPRO-DUCED OR TRANSMITTED IN ANY FORM OR BY ANY MEANS, ELECTRONIC OR MECHANICAL, INCLUDING PH0Y0 COPYING, RECORDING OR 3Y ANY INFORMAf!ON STORAGE AND RETRIEVAL SYSTEM, WITHOUT PERMISSION IN WRITING FRON LN TECHNOLOGIES CORPORATION, EXCEPT FOR STRICTLY CONTROLLED DISTRIBUTION, FOR EVALUATION PURPOSES. l l l _ L_ l y_.__ _.4 _j l I l i I l l I I ~ F i l 1 I J I s _Nh !/ ' A fif' Y_d / // . U$L ' (,/ k W'_ m L ~,- ' *.Tr J '. _' + pj..f.') .,. g 1' s s ORIGlh ATO R 0 ATE CHECKED j 'D AT E OA 6~ DATE' M A N A G E R DATE e F g;3j y j w ; / J . no, REvlSION PAGE WM-013 F 2 of 7 l-i TABLE OF CONTENTS Page ~ I ~. 1.0 PURPOSE 3 2.0 APPLICABILITY 3 F 3.0 DEFINITIONS 3
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 3
5.0 PROCUREMENT PROJECT MANAGER 3
6.0 PERSONNEL QUALIFICATIONS 3
4 7.0 EQUIPMENT 4
0.0 CALIBRATION 4
9.0 PROCEDURE 4
10.0 ACCEPTANCE CRITERIA 5
11.0 DISTRIBUTION 6
Pigure 1 7
5 9
3-no.
stvistoM PAGC WM-013 P
3 of 7 1.0 PURPOSE This generic test speci.fication procedure states the mi.nimum requirements for gamma scanning of lead shielding for LN_ Type can%n.
The fabricator shall submit for approval detailed gamma scanning procedures.
2.0 APPLICABILITY f
This generic procedure is applicable to all radioactive shipment casks or radiation shields fabricated for and procured by LN Technologies.
3.0 DEFINITIONS None
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 4.1 AECU 2967, November 1954 4.2 ASNT Recommended Practice No. SNT-TC-1A, 1980 Edition 5.0 RESPONSIBILITIES Procurement Project Manager - shall inspect ar e approve all vendor submitted gamma scanning procedures against this test specification procedo.e.
6.0 PERSONNEL QUALIFICATIONS Personne1 conducting gamma scanning shalI he f ami l ia r with the detailed procedures and shall be certified Level I1 or Level III radiographers in accordance with SNT-TC-1A.
(Reference 4.2) 2
I t o No, REVISION PAGE WM-013 F
4 of 7 J
7.0 EQUIPMENT The gamma detector shall be a model E120 Eberline or equiva-lent with a pancake probe.
The gamma source shall be cither
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IR l92 or Co60 of sufficient activity in curies to obtain reasonable readings.
The source strength will be dependent on the lead and steel thickness being scanned.
8.0 CALIBRATION 1
A calibration plate will be prepared using defect free lead equal to the nominal lead thickness for the specific cask Steel equal to the nominal specified wall thickness will be placed on either side of the lead.
The lead shall be design-ed so that several 1/8" sections of Icad can be removed or added to the calibration plate.
The calibration plate will be it.atalled in a fixture in place of the secondary cover as shown in Figure 1.
The source is placed inside the cask at a distance from the plate equal to the inside radius of the cask.
The radiation detector is placed on top of the plate and radiation readings are taken with the meter set on the lowest scale.
The test is then re-peated modifying the lead thickness in increments of 0.12 5 inches plus and minus the nominal lead th ick ne s s.
At least five points will be measured and a plot of lead thickness v-detector readout is then plotted.
The maximum acceptable reading during the gamma scan shall'be 1 1 times the reading obtained from the nominal lead wall thickness or the e 3: t r a po-lated reading for.90 percent of the nominal lead wal1 thick-ness, whichever is less.
9.0 PROCEDURE 9.1 Mark a 4-inch grid system on the cask and record the
No.
RE VISION PAGE 4
WM-013-F 5 of 7 t
F grid system on paper as a permanent record.
i 9.2 Locate the radiation source along the centerline ax[s of the cask and position it at the midpoint of the plane of the top row of grid squares.
9.3 Take readings at each grid square on the outside of the cask in the plane of the source.
The probe will be in contact with the cask surface when the radiation readings are taken.
9.4 Lower the source along the centerline axis to the midpoint o f the next row of grid squares and repeat step 9.3.
9.5 Repeat step 9.4 until the bottom row of grid squares have been monitored.
9.6 Position the source along the centerline of the cask at a height equal to one cask radius off the bottom.
9.7 Take and record readings every 12 inches around the bottom circumference of the cask.
9.8 Position the source along the centerline of Pa cask at a height equal to one cask radius from the top of the Cask.
9.9 Take and record readings every 12 inches around the top circumference of the cask 9.10 Average and record the six highest readings obtatned in step 9.7.
L
~
No.
PEVISION PAGE WM-013 P
6 of 7 9.11 Average and record the six tiighes t readings obtained in er 9.9.
.r. radlation reading at any point on th e cask circumference shall not exceed the value determined in section 8.0, except as noted in steps 10.2 and 10.3 10.2 The readings obtained in step 9.7 shall not exceed 125 percent of the average reading calculated in etep 9.10, and they shall not exceed 50 percent of th e value determined in Section 8.0.
10.3 The readings obtained in step 9.9 shall not exceed 125 percent of the average calculated in step 9.11, and they shall not exceed 50 percent of the value determined in Section 8.0.
11.
DISTRIBUTION Librnry (2 Copies)
RECO Engi cering, Richmond, VA.
9
.,f no.
REvtSION PAGE i
WM-013 F
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1 of 7 TITLE
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GA101A SCANNING OF LEAD SHIELDING FOR LN TYPE CASKS TECHNOLOGIGS
.C O n pO A ATION COPYRIGHT C 1)S6 BY LN TECllNOLOGIES CORPORATION ALL RIGHTS RESERVED.
NO PART OF THIS DOCUMENT MAY BE RdPRO-DUCED OR TRANSMITTED IN ANY FORM OR BY ANY MEANS, ELECTRONIC OR MECHANICAL, INCLUDING PHOTOCOPYING, RECORDING OR BY ANY INFORMATION STORAGE AND RETRIEVAL SYSTEM, WITHOUT PERMISSION IN WRITING FROM LN TECHNOLOGIES CORPORATION, EXCEPT FOR STRICTLY CONTROLLED DISTRIBUTION, FOR EVALUATION PURPOSES.
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REVISION PAGE NO.
WM-013 F
2 of 7 TABLE OF CO:1 TENTS Page 1.0 PURPOSE 3
2.0 APPLICABILITY 3
1 3.0 DEFINITIONS 3
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 3
5.0 PROCUREMENT PROJECT MANAGER 3
6.0 PERSONNEL-OUALIFICATIONS 3
7.0 EQUIPMENT 4
8.0 CALIBRATION 4
7 PROCEDURE 4
10.0 ACCEPTANCE CRITERIA 5
11.0 DISTRIBUTION i
Figure 1 7
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NO.
REVISION PAGE WM-013 F
3 of 7 1.0 PURPOSE This generic test specification procedure states the minimum requirements for gamma scanning of lead shielding for LN_-Type casks.
The fabricator shall submit for approval detailed gamma scanning procedures.
2.0 APPLICABILITY I
This generic procedure is applicable to all radioactive shipment casks or radiation shields fabricated for and procured by LN Technologies.
3.0 DEFINITIONS None
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 4.1 AECU 2967, November 1954 4.2 ASNT Recommended Practice Nc, SNT-TC-1A, 1980 Edition 5.0
_R_E.S PONS I B I LI T I ES Procurement Project Manager - shall inspect ar 6
.pprove all vendor submitted gamma scanning procedures against this test specification precedure.
6.0 PERSONNEL QUALIFICATIOt{_S_
Personnel conducting gamma scanning shall be familia r with the detailed precedures and shall be certified Level 17. or Level III radiographers in accordance with SNT-TC-1A.
(Reference 4.2) h
L-er r
NO..
REVISION PAGE WM-013 P
4 of 7-7.0 EQUIPMENT The gamma detector shall be a model E120 Eberline or equiva-lent with a pancake probe.
The gamma source shall be ei tJTe r IR l92 or Co60 of suf fi.cient activity in curies to obtain~
reasonable readings.
The source strength will be dependent-on the lead and steel thickness being scanned.
8.0 CALIBRATION A calibration plate will be prepared using defect free lead equal to the nominal lead thickness for the specific cask.
Steel equal to the nominal specified wall thickness will be placed on either side of the lead.
The lead shall be design-ed so that several 1/8" sections of lead can be removed or added to the calibration plate.
The calibration plate will be installed in a fixture in -p1. ace of the secondary cover as shown in Figure 1.
The source is placed inside the cask at a distance f rom the plate equal to the inside radius of the cask.
The radiation detector is placed on top of the plate and radiation readings are taken with the meter set on the lowest scale.
The test is then re-peated modifying the lead thickness in increments of 0.l25 inches plus and minus the nominal lead th ick n e s s.
At least fivo,roints will be measured and a plot of lead thicknes s vn detactor readout is then plotted.
The maximum acceptable reading during the gamma scan shall be 1.1 times the reading obtained from the nominal lead wall thickness or the extrapo-lated reading for.90 percent o f the nominal lead wall thick-ness, whichever is less.
9.0 PROCEDURE 9.1 Mark a 4-inch grid system on the cask and record the
NO.
AEvlSION PAGE WM-013 P
5 of 7 grid system on paper as a permanent record.
9.2 Locate the r.3 d ia t io n source along the centerline ax5s of the cask and position it at the midpoint of the plane of the top row of grid squares.
9.3 Take readings at each grid square on th e outside of the cask in the plane of the source.
The probe will be in contact with the cask surface when the radiation readings are taken.
9.4 Lower the source along the centerline axis to the midpoint of the next row of grid squares and. repeat step 9.3.
9.5 Repeat step 9.4 until the bottom row of grid squares have been monitored.
9.6 Position the source along the centerline of the cask at a height equal to one cask radius off the bottom.
9.7 Take and record readings every 12 inches around the bottom circumference of the cask.
5.8 Position the source along the centerline of ta cask at a height equal to one cask radiua from the top of th e ca u,.
9.9 Take and record readings every 12 inches around the top circumfercr ce of the cask, s
9.10 Average and record the six highest readings obtained in step 9.7.
s
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No.
REvlSION PAGE WM-013 F
6 of. 7 9.11 Average and record the six highest readings obtained in step 9.9.
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10.0 ACCEPTANCE CRITERIA 10.1 The radiation reading at any point on the cask circumference shall not exceed the value determined in section 8.0, except as noted in steps 10.2 and 10.3 10.2 The readings obtained in step 9.7 shall not exceed 125 percent of the average reading calculated in step 9.10, and they shall not exceed 50 percent of the value determined in Section 8.0.
10.3 The readings obtained in step 9.9 shall not exceed 125 percent of th e average calculated in step 9.11, and they shall not exceed 50 percent of the value determined in Section 8.0.
11.
DISTRIBUTION Library (2 Copies)
RECO Engineering, Richmond, VA.
9
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AcvisioN PAGE WM-013 P
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1 of 7 TITLE GAPJ1A SCANNING OF LEAD Sil.T.ELDING TCCHNOLOGtGS FOR LN TYPE CASKS
.C ompo A ATION 1
l 1
COPYRIGilT C 1936 BY LN TECilNOLOGIES CORPORATION ALL RIGliTS RESERVED.
NO PART OF TlilS DOCUMENT MAY BE REPRO-DUCED OR TRANSMITTED IN ANY FORM OR BY ANY MEANS, ELECTRONIC OR MECliAN IC AL, INCLUDING Pif0T0 COPYING, RECORDING OR BY ANY INFORMATION STORAGE AND RETRIEVAL SYSTEM, WITil0UT PERMISSION IN WRITING FROM LN TECilNOLOGIES CORPORATION, EXCEPT FOR STRICTLY CONTROLLED DISTRIBUTION, FOR EVALUATION PURPOSES.
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REVISION PAGE WM-013 P
2 of 7 t
TABLE OF CONTENYS Page 1.0 PURPOSE 3
2.0 APPLICAbfLITY 3
3.0 DEFINITIONS 3
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 3
5.0 PROCUREMENT PROJECT MANAGER 3
6.0 PERSONNEL QUALIFICATIONS 3
7.0 EQUIPMENT 4
8.0 CALIBRATION 4
9.0 PROCEDURE 4
10.0 ACCEPTANCE CRITERIA 5
11.0 DCSTRIBUTION 6
Figure 1 7
9
I.
NO.
REVISION PAGE WM-013 F
3 of 7 1.0 PURPOSE This generi.c test specification procedure states the minimum requirements for gamma scanning of lead shielding for LN yype casks.
The fabricator shall submit for approval detailed gamma scanning procedures.
2.0 APPLICABILITY This generic procedure is applicable to all radioactive shipment casks or radiation shields fabricated for and procured by LN Technologies.
3.0 DEFINITIONS None
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 4.1 AECU 2967, November 1954 4.2 ASNT Recommended Practice No. SNT-TC-1A, 1980 Edition 5.0 RESPONSIBILITIES yr39urement Project Manager - shall inspect and approve all vendor submitted gam:na scanning procedures against this test specification procedure.
6.0 PERSONNEL QUALIFICATIONS Personnel conducting gamma scanning shpll be familiar with the detailed procedures and shall be certified Level II or Level III radiographers in accordance sith SNT-TC-1A.
(Reference 4.2)
NO.
REVi$10N PAGE l.
WM-013 P
4 of 7 7.0 EOUIPMENT The gamma detector shall be a model E120 Eberline or equiva-lent with a pancake probe,.
The gamma source shall be eitbar IR 192 or Co60 of sufficient activity in curies to obtain~
reasonable readings.
The source strength will be dependent on the lead and steel thickness being scanned.
8.0 CALIBRATION A calibration plate will be prepared using defect free lead equal to the nominal lead thickness for the specific cask.
Steel equal to the nominal specified wall thickness will be placed on either side of the lead.
The lead shall be design-ed so that several 1/8" sections of lead can be removed or added to the calibration plate.
The calibration plate will be in s t a l.le d in a fix tu re in place of the secondary cover as shown in Figure 1.
The source is placed inside the cask at a distance from the plate equal to the inside radius of the cask.
The radiation detector is placed on top of the plate and radiation readings are taken with the meter set on the lowest scale.
The test is then re-peated modifying the lead thickness in increments of 0.125 inches plus and minus the nominal lead th i.ek ne s s.
At least five points will be measured and a plc* of lead thickness vs detector readout is then plotted.
The.r.aximum acceptable reading during the gamma scan shall" be 1.1 times the reading obtained from the nominal lead wall thickness or the extrapo-lated reading for.90 percent of the nominal lead wal1 th ick -
ness, whichever is less.
9.0 PROCEDURE 9.1 Mark a 4-inch grid system on the cask and record the 9
cm N o.
REVISION PAGE WM-013 P
5 of 7 l
grid system on paper as a permanent record.
9.2 Locate the radiation source along the centerline axis of the cash and position it at the mi.dpoint of the plane of the top row of grid squares.
9.3 Take readings at each grid square on the outside of the cask in the plane of the source.
The probe will be in contact with the cask surface when the radiation readings are taken.
9.4 Lower the source along the centerline axis to the midpoint of the next row of grid squares and repeat step 9.3.
9.5 Repeat step 9.4 until the bottom row of grid squares have been monitored.
9.6 Position the source along the centerline of the cask at a height equal to one cask radius off the bottom.
9.7 Take and record readings every 12 inches around the bottom circumference of the cask.
- 9. 4 Position the source along the centerline of the cack at a height equal to one cask radius from the top of the cask 9.9 Take and record readings every 12 inches around the top circumference of the cask.
9.10 Average and record the six highest readings obtained in step 9.7.
- f..
No.
REVISION PAGE l
WM-013 F
6 of 7 9.11 Average and record the six highest readings obtained in step 9.9.
_~
10.0 ACCEPTANCE CRITERIA 10.1 The radiation reading at any point on the cask circumference shall not exceed the value determined in section 8.0, except as noted in steps 10.2 and 10.3 10.2 The readings obtained in step 9.7 shall not exceed 125 percent of the average reading calculated in step 9.10, and they shall not exceed 50 percent of the value determined in Section 8.0.
10.3 The readings obtained in step 9.9 shall not exceed 125 percent of the average calculated in step 9.11, and they shall not exceed 50 percent of the value determined in Section 8.0.
11.
DISTRIBUTION Library (2 Copies)
RECO Engineering, Richmond, VA.
k O
r-NO.
REvtSION PAGE WM-013 P
7 of 7 FIGURS 1
- PANCAKE Pil0BE CASK LIO l/
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gPAflCAKE PROBE Q
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SO U R CE ENLARGEMENT A - NO SCALE
NO.
REVISION PAGE WM-;13 F
1 of 7 TITLE 4
GA?O1A SCANNING OF LEAD SHIELDING TECHNOLOGIGS FOR LN TYPE CASKS
.C ompon ATION i
i I
i COPYRIGHT C 1986 BY LN TECHNOLOGIES CORPORATION ALL RIGHTS RESERVED.
NO PART OF THIS DOCUMENT MAY BE REPRO-DUCED OR TRANSMITTED IN ANY FOPJi OR BY ANY MEANS, ELECTRONIC OR MECHANICAL, INCLUDING PHOTOCOPYING, RECORDING OR BY ANY INFORMATION STORAGE AND RETRIEVAL SYSTEM, WITHOUT PERMISSION IN WRITING FROM !.N TECHNOLOGIES CORPORATION, EXCEPT FOR STRICTLY CONTROLLED DISTRIBUTION, FOR EVALUATION PURPOSES.
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jfjAUbigb 4h ti -t'blb w.nts Y9fs b?.WYAIb 'YV bl
'N T:y
'!-) i M V
Of?iG'fNATOR DATE CHECKED
'OATE l' OA F DATE 7 MANAGER DATE
N O.
REvlSION PAGE WM-013 F
2 of 7 TABLE OF CONTENTS Page
~
L.0 PURPOSE 3
3 2.0 APPLICABILITY 3.0 DEFINITIONS 3
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 3
5.0 PROCUREMENT PROJECT MANAGER 3
6.0 PERSONNEL QUALIFICATIONS 3
7.0 EQUIPMENT 4
8.0 CALIBRATION 4
9.0 PROCEDURE 4
10.0 ACCEPTANCE CRITERIA 5
11.0 DISTRIGUTIO.
6 Figure 1 7
9
NO.
Rf. VISION PAGE WM-013 F
3 of 7 1.0 PURPOSE This generic test specification procedure states the minimum requirements for gamma scanning of lead sh i.e l d i n g for LN,-Type casks.
The fabricator shall submit for approval detailed gamma scanning procedures.
2.0 APPLICABILITY a
This generic procedure is applicable to all radioactive shipment casks or radiation shields fabricated for and procured by LN Technologies.
3.0 DEFINITIONS None
4.0 REFERENCES
AND APPLICABLE DOCUMENTS 4.1 AECU 2967, November 1954 4.2 ASNT Recommended Practice No. SNT-TC-1A, 1980 Edition 5.0 RESPONSIBILITIES Procurement Proje:t_ Manager - shall inspect and approve all vendor submit ted gainma scanning pro:edures against this test specification procedure.
6.0 PERSONNEL QUALIFICATIONS Personnel conducting gamma scanning shpil be familiar with the detailed procedures and shall be certified Level II or Level III radiographers in accordance with SNT-TC-1A.
(Reference 4.2)
No.
RE vlSION DAGE WM-013 P
4 of 7 a
7.0 EQUIPMENT The gamma detector shall be a model El2O Eberline or equiva-lent with a pancake probe.
The gamma source shall be either IR L 92 or Co60 of suf ficient activity in curies to obtain' reasonable read i ng s.
The source strength will be dependent on the lead and steel thickness being scanned.
8.0 CALIBRATION J
A calibration plate will be prepared using defect free lead equal to the nominal lead thickness for th e specific cask.
Steel equal to the nominal specified wall thickness will be placed on either side of the lead.
The lead shall be design-ed so that several 1/8" sections of lead can be removed or added to the calibration plate.
The calibration plate will be installed in a fixture in place of the secondary cover as shown in Figure 1.
The source is placed inside the cask at a distance from the plate equal to the inside radius of the cask.
The radiation detector is placed on top of the plate and radiation readings are taken with the meter set on the lowest scale.
The test is then re-peated modifying the lead thickness in increments of 0.l25 inches plus and minus the nominal lead thickness.
At least five points will be measured and a plot of lead thickness vs detector readout is then plotted.
The maximum acceptable reading during the gamma scan shall~be 1.1 times the reading obtained from the r,ominal lead wall thickness or the extrapo-lated reading for.90 percent of the nominal lead wall th ick-ness, whichever is lesc.
9.0 PROCEDURE 9.1 Mark a 4-inch grid system on the cask and re cord the
i NO.
REVISION PAGE WM-013 F
5 of 7 J
l grid system on paper as a permanent record.
9.2 Locate the radiation source along the centerli.ne axis of l
l the cask and position it at the midpoint"of the plane of l
the top row of grid squares.
l 9.3 Take readings at each grid square on the outside of the l
cask in the plane of the source.
The probe will be in contact with the cask surface when the radiation i
readings are taken.
i 9.4 Lower the source along the centerline axis to the midpoint of the next row of grid squares and repeat step t
J 9.3.
9.5 Repeat step 9.4 until the bottom row of grid squares have been monitored.
9.6 Position the source along the centerline of the cask at a height equal to one cask radius off the bottom.
9.7 Take and record readings every 12 inches around the bottom circumference of the cask.
9.8 Position the <;oo r c e along the centerline of th e cask at a height equal to one cask radius from the top of the cask.
L i
9.9 Take and record readings every 12 inches around the top circumference of the cask.
~
1 9.10 Average and record the six highest readings obtained in step 9.7.
r I
r 9
h..,_
y h
NO.
REVISION PAGE WM-013 F
6 of 7 9.11. Average and record the six highest readings obtained in step 9.9.
_~
10.0 ACCEPTANCE CRITERIA 10.1 The radiation redding at any point on th e cask circumference shall not exceed the value determined in section 8.0, except as noted in steps 10.2 and 10.3 10.2 The readings obtained in step 9.7 shall not exceed 125 percent of the average reading calculated in step 9.10, and they shall not exceed 50 percent of the value determined in Section 8.0.
10.3 The readings obtained in step 9.9 shall not exceed 125 percent of the average calculated in step 9.11, and they shall not exceed 50 percent of the value determined in Section 8.0.
11.
DISTRIBUTION Library (2 Cott.s)
RECO Engineering, Richmond, VA.
O
e-0 3 REvlSION PAGE No.
WM-013 P
7 of 7 F I G l1 R t-: 1 pat / CAKE PROBE 7 l-
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