ML20236C671
| ML20236C671 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/23/1987 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| WM-87-0282, WM-87-282, NUDOCS 8710270290 | |
| Download: ML20236C671 (27) | |
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W@ NUCLEAR OPERATING M 00121 ' A D 1tt Bart D Withers era m nimad October -23,-1987 Chief Execuuve Omcor WM 87-0282 U. S. ' Nuclear Regulatory Commission ATTN:' Document Control Desk Washington, D.. C. 20555
Reference:
Letter dated 8/20/87, from J..A.
Calvo, NRC, to B. D. Withers, WCNOC
Subject:
Docket No. 50-482:
Response to NRC Questions Concerning the Quality of Spent Fuel Racks, Fabricated -
I by U. S. Tool and Die j
i Gentlemen:
The purpose of this letter is to transmit a response to NRC questions'-
concerning. the quality of spent fuel racks fabricated by U. S.-
Tool and Die.
Attachment -I.to this. letter specifically addresses each of the questions transmitted' by the Reference.
Wolf Creek Nuclear Operating Corporation (WCNOC) found no evidence that the U. S.
Tool. and Die Quality Assurance program was in a degraded
- condition at the time the Wolf. Creek (WCGS) spent fuel racks were manufactured that could 'have adversely effected the spent fuel racks.
Therefore, no additional actions or examinations are necessary. to provide additional assurance that the WCGS spent fuel racks meet the design specification requirements.
j If you have any questions concerning this matter, please contact me or Mr.
l O. L. Maynard of my staff.
l Very truly yours, 8710270290 871023 PDR ADOCK 05000482 Bart D. Withers l
P PDR President and j
Chief Executive Officer i
BDW/jad Attachments cc:
P. W. O'Connor (2) 7 0l l
1 R. D. Martin 0
J. E. Cummins 1
1 P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 An Equal opportunny Employer MTHCNET i
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~AttachmentHI;to;WM'8%0282J 3Page11 'of?5 (October 23, t1,987f '
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Question 1P : Describe the~ extent to which the U.S.E Tool: & Die-QA/QC program
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. was; relied upon to assure rack quality?,
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Response r TThefU.ST: Tool;and Die-(UST&D)-QA/QC program was- ' relied -upon during: them fabrication:.of 'the-spent ' fuel racks, however, g_
Bechtel Power' Corporation' performed u Quality. Audits ofj,the:
UST&D' Quality. Program on a frequent basis. -,Bechtel conducted' 4
.f quality program. audits:.as-well
'as-quality program j
l' verifications ' lin ;' order 'sto assess " the effectivene'ss of the.
l program.
Thec Quality Program Verifications conducted.6y
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Bechtel-were. modified v.ersions of the quality program. audits.
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~
3 These verifications of selected quality program elements of:
J
-- V UST&D were conducted o'n a continuing and progressive basis.
Y' A summary of the audits and quality surveillance conducted by
>Bechtel-in this area is provided in--Attachment II.' -The audits-d and evaluations do not indicate a Quality Program breakdown in..
j f the UST&D Program. -
f Question _ 2: =
Describe your in-factory and/or receipt inspection. of ' the racks..
n j
Response
In-Factory Inspe,ction Program - Bechtel A
Bechtel implemented a quality inspection program which l
monitored.a. wide - spectrum; of the supplier's. manufacturing processf and QA/QC program.
Bechtel; conducted quali ty..
i surveillance inspections-which-consisted of
- reviews, 1
observations, and/or physical ~ inspections at random or at; selected stages of manufacture or construction of the subject racks by UST&D.
These inspection activities were used-to determine if the Work ' accomplished and/or the documents prepared were in accordance with the design specification requirements.
The surveillance inspection did not observe all l
UST&D activities but were intended rather to provide a degree of added confidence that supplied materials, equipment,
- test, or services meet the UST&D
.911ty Program and buyer's 1
s speci fications.
A review of applicable Bechtel inspection reports with particular attention to welding inspections was conducted.
A total of 116 Bechtel Quality Surveillance Reports (QSRs) were i
conducted during the manufacturing of the SNUPPS (i.e.
Wolf Creek and Callaway) spent fuel racks.
A review of the Bechtel
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'PageL2Nof.51.
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'QSRs was conducted to ' determine which 'were applicable to welding' related' activities - ( 1.'e. - l Welding. Processes,. Weld-k@
, Inspections,and Non-Destructive' examinations')
at. UST&D.-
.A.
Lsummary. matrix of rack-weld-and NDE: activities for the sub' ject-
. racks versus; the -Bechtel QSRs.'is provided.in L httachment : III.-
- The' welding -review -indicated that, there Lwere no =signific' ant M
inconsistencies or outstanding program-1 element. concerns - lfor the racksi manufactured. _ for. Wolfj Creek Generating Station.
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'(WCGS).
p Bechtel'had-' inspection personnel at UST&D which were ' required to. perform designated inspections of the racks identified.by ;
~
L wi. ness and.. hold points.
-Work-could only proceed past:Lhold 7 p
po.tnts including.the_ witness.. points when.' supported < by'a j
. written ' waiver from - i Bechtel. -
. Witness- ! points: < included inprocess NDE, ' weld material-selection, fi t-up, welding for.
r each. procedure. approved by Bechtel Engineering, and. major. weld repairs.
Hold points included the insertion of " dummy" fuel.
assemblies and -measurement of: drag forces,'.finaliinspection of 7 materials, construction' workmanship, cleanliness,. marking, tagging and ' shipment preparation l and review cand. ( signoff for completeness, accuracy of - UST&D' documents.-
All' reviewed '
l ivendoridocuments received at Wolf' Creek. include a Bechtelishop
- inspector's -stampand an associated Bechtel form '(G321-D)
. indexing - the extent of _ the Bechtel inspecto r 's._ Involvement.
No ~ written waivers-were-included /
in.
the'
- received,
. doc umen ta tio n. -
i In-Factory Insp,ection _ Program - SNUPPS o
The SNUPPS (Standardized, Nuclear Unit-Power Plant System) organization utilized the services of a third-party inspection agency to examine the spent fuel' racks manufactured for the Wolf Creek and Callaway facilities.
SNUPPS used the Nuclear Energy Services (NES) examination agency to conduct inspections' of the. racks prior to _ release from.UST&D for l
shipment.
This independent, third-party inspection was
- I
. per formed upon completion of the Bechtel final review.
The NES inspection reviewed copies of tests, examinations, reports, procedure changes or pertinent information documented-j during previous Bechtel or UST&D inspections.
The inspection included physical and dimensional examination of the racks.
In the area of welding, checks of welding procedures, welder quali fic a tic',s, welding processes, weld materials and a spot check of rack assembly weld profiles were conducted.
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e LU JAttachment1I:to WM 87-0282 f
Page 3.Lof 5 l
October.-23, 19871 1
Receipt Inspection - KG&E-I
.o Receipt inspections were performed on all twelve. (12) spent.
fuel racks.; received at Wolf Creek.
The receipt inspections were performed by certified. Daniel. ' International Corporation.
' Quality. Control personnel.in accordance'with (DIC) procedure QCP-I-01.
Deficiencies and nonconformances were documented on-Deficiency ' Reports (DRs) or Nonconformance Reports (NCRs) per i
DIC procedure AP-VI-02.
The. receipt inspections ~ conducted did J
identify material' and documentation deficiencies on three (3) racks.
Since Bechtel had conducted in-factory-inspection of l
welds, DIC was not. required to perform visual weld -inspections of the spent fuel racks-at the. time of receipt.-
'It should be noted' that Kansas Gas &' Electric (KG&E) QA personnel conducted 4
three surveillance of several of the racks. after their arrival. at Wolf Creek.
No major deficiencies were noted per the surveillance conducted by KG&E QA.
Question'3: - What findings were made during your receipt inspection of the
' racks?
I Response:-
During the receipt inspection by DIC Inspection personnel, deficiencies were identified on three (3). racks.
A summary is-listed below:
o DR 1SD9321CR, Rack M120-20:
Page 3 of 12 for the Liquid Penetrant Examination is not traceable.to other documentation or materials.
o DR 1SD9,9CR, Rack M120-26: There was no identification tag attached - to the rack. o DR 1SD9767CR, Rack M120-27: Rack had surface damage along with a missing identification tag. A review of the Material Receiving Reports (MRRs) and other spent fuel related reports onsite was conducted to determine any other deficiencies identified prior to or after receipt at Wolf Creek. Thi s review included Supplier Deviation Disposition Requests (SDDRs) which were submitted from UST&D to Bechtel for their disposition / approval. There were twenty-three (23) SDDRs approved by Bechtel included in the received documents on the spent fuel racks. Several of the inspections at WCGS resulting in noted deficiencies were the result of
^ l Attachment I t'o WM 87-0282 Page.4-of 5 ' Oc tober-23,-1987 l' identified spot weld : protrusions first identified 'l F on' Callaway : Spent Fuel 4 Racks.- 'A total of. fourteen (14) deficiency (DR): and nonconformance (NCR) L -reports were initiated at'WCGS concerning the racks. The three7. deficiency reports initiated. during the receipt inspection are part' of the fourteen. Of. the-fourteen (14), six -(6) Deficiency /Nonconformance ' Reports initiated were' weld-related. Three (3) of the six (6) were identification 'of. linear. -weld discontinuity and three (3) were identifying concerns regarding ' spot } weld metal protrusions on 'the inside' surface of rack cells. 1 A completo summary by rack versus deficiency report (s) j initiated is located in Attachment IV. .i i 'I Question 4:. If your. receipt inspections found deficiencies in the racks, what corrective actions were taken? j
Response
The ' deficiencies concerning the racks identi fied during ;the' receipt inspection at WCGS racks were corrected and closed. The other deficiencies. related to weld activities' were also. corrected. A summary of the initiated deficiency reports 1 dislaositions and. corrective action is located in Attachment V. The weld related' deficiencies identified.in the.three reports concerning: spot weld material protrusions were-corrected by Rework Plan C-175-1, Revision 0. Two of three reports concerning linear' discontinuities were closed by completion of rework while the third identified linear discontinuity condition was evaluated as a use-as-is disposition. QuerH on 5: Describe any additional actions or examinations - you plan to undertake to assure that your racks meet the original design and regulatory requirements.
Response
Wolf Creek Nuclear Operating Corporation (WCNOC) has a high level of confidence that the WCGS Spent Fuel Racks meet the original design specifications and associated regulatory requirements. This is based on the following: o Bechtel Quality. Audit and Surveillance activities of the UST&D Quality Program in the vendor's shop did not indicate a QA program breakdown. l l L
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- Attachment ILto WM._..
.o a. ;; 87-02821 4 0: ):7. 4 lPage 5E of 5 l D.0ctober{ 23, :.1987 J s, p ^~ '.o. Bechtel)i monitoring.and - review:. ;of Q UST&D. ' ; manufacturing L processes,. procedures. and. documentation'was1 considered to. g be comprehensive Land.provided additional-' assurance ~ that. the ' 7 <7 UST&D quality' program was effective.; o NES J third-party-inspections of;the Lracks for compliance to o C specification requirements " prior ~(to;;. shipment ~ provided
- additional confidence that..the - UST&D
- .QA'. Program =2was effective.:
' ~ 4 H o: ' 0wner/ constructor' inspections and surveillance ' conducted 1 on the' c racks :' at ; receipt and during installation did not reveal Levidence 'of ' fabrication " defects-Tof-a. nature that: would ' indicate 'the-supplier's QA program:was ineffective. All. specific hardware deficiencies identified were resolved.. ~4 - prior'to plant startup.- lAs? a' result,; ' WCNO.C. has determined that no ' additional'.. <actionsTori examinations-areg required Lat ;this. time'.;to ~ - ' provide;:assuranceo that:1the~ WCGS racks meet the original . design and regulatory requirements. 1 o ic a 1 5 1 j l j a _____.___._1.1.__. __.u___
e e 4 i D ATTACHMENT II .k a i i l J l l i 1 i 1
ar ,7 [ k Att'achment II to WM'87-0282 .Page.1 of 2: October 23, 1987
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Bechtel' Audit Summary. Scheduled Bechtel audits performed aat Wachter Associates /U.S. Tool & Die as - follo ws : - ' Audit Audit Finding /' Corrective Action-Date. Quality Element ## Resolution 7/23/80 .AFR #1 7 Closed - reaudit'3/23/81 AFR #2 10 Closed - reaudit 8/8/80 AFR #3 12 Closed - reaudit 8/8/80 AFR #4 15/16 Closed reaudit 8/8/80~ .AFR #5~ 18' Closed -.reaudit 3/23/81 7/24/81 AFR #1 1 Closed.- reaudit 1/4/82 AFR #2 9 Closed - reaudit 8/28/81 AFR #3 -15 Closed - reaudit 11/23/81 AFR #4 16 Closed - reaudit 11/23/81 AFR'#5 18 Closed - reaudit' 11/23/81 7/8/82 AFR #1 18 Closed - reaudit 8/11/82 1 QualitE_,P_rogram Verifications (QPVs) - -l The Quality Program Verification is a modified version of the Quality Audits. QPVs were documented by means'oria Quality Surveillance. Report. (QSR). QPVs performed at US Tool & Die by Bechtel are as follows: j Quality l Surveillance Quality' Reports'(QSR) Element Results/ Resolution QSR #3 4 Unsatisfactory QSDR#-1 (Closed by QSR #8) QSR #8 4 Satisfactory QSDR8-1 (Closed) QSR #4 12 Satisfac tory 9 Satisfactory QSR #29 6 Satisfactory 9 Satisfactory 11 Satisfactory QSR #30 7 Satisfactory QSR #34 9 Satisfactory 12 Satisfactory 14 Satisfactory 7 Satisfactory QSR #38 4 Satisfactory 7 Satisfactory 9 Satisfactory 12 Satisfactory QSR #44 9 Satisfactory QSR #46 12 Satisfactory
r-r I Attachrnent II to WM 87-0282' Page 2;.of.2: October. 23, 1987-i Quality. Surveillance -Quality Reports (QSR) Element Results/ Resolution j QSR #52 9 Satisfactory 12. Satisfactory 4 Satisfactory-
- QSR '#53 7
Satisfactory QSR #62 4 Satisfactory 9 Satisfactory l 12 Satisfactory l QSR #72' 4 Satisfactory 1 6.- Satisfactory -i 9 Satisfactory 12 Satisfactory QSR #82 15 Satisfactory 9 Satisfactory 12 ' Unsatisfactory QSDR' b2-1(Closed by QSR #83) QSR #83 '12 Satisfactory QSDR* 82-1 (Closed) 16 Satisfactory -QSR #84. 4 Satisfactory r 6 Satisfactory [ 7 Satisfactory l QSR #99 4 Satisfactory -6 Satisfactory J 7 Satisfactory 9 Satisfactory l 12 Sati s factory ' 15 Satisfac tory 16 Satisfactory -QSR #105 9 Satisfactory 6-i l ' Quality Surveillance Deficiency Report - QSDR
- Quality Element corresponds to criteria in 10 CFR 50, Appendix B k
4 ~ - _ _
t e e t ATTACHMENT III I i i 1 i i i i --mm__ _-_---__.m.___.______m.__
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87-0282- . Attachment III to WM .Page'1 of 6 October 23, 1987 -l i
- Matrix for Selective Surveillance Activities ; Relative. to' UST&D. Welding '
L! Processes, Weld Inspections, Non-Destructive Examinations'and Release for.- 71 Shi;aent 4 -All' -116 LQSRs.. were reviewed for specific welding, NDE and Bechtel/SNUPPS: i release for shipment and compiled'in: the matrix formats., ~ Please - no te that-reports for surveillance for activities other than welding,' NDE and release i for shipment were not. included in the matrix. The matrix' covers . manufacturing. activities for both WCGS and Callaway. Spent Fuel Racks. ) ~ i ) 1 a
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- 1. _ :.Nonconformance Reports (NCRs):
r 1 l7 .NCRs' Identified for the. Spent Fue1~ Racks: Ten. NCRs were11dentified f for th'e WCGSiSpent Fuel storage' racks; y L1. 4 13/16/82) L1SN4214CW# ! Rack:' M120-27, ' contrary: to the i Bechtel' Specification 110466-C-175, i mostLapot1 welds. connecting. envelopes protrude into the in' side ~ surfacestup :.'to ;
- approximately,1/32 inch..
VendorLwelds. vary from the: 0.125 Linch radius for.-lead-in-W ' L inters'ections.1 ' The racks' meet-the specifications and the specific; requirements.of? rework plan; C-175-1, ireference Bechtel 'letterj #BLKE. 746, 6/02/82. Closed /10/9/82. Q,, J2.' - ;3/16)82' 1SN42_15Cyn ' Rack: M120-22 j ' Spot Weld' pro'trusions Lwerelnoted onithe. inside surface (approximately 11/32Linch)., is ' C-175-1E and Independent' H inspec tion, by.; NES, Westinghouse Nuclear. Fuels 1 Division l , '(W NFD)' SNUPPS,1KG&E (See Item,# 1, 1SN4214CW abo' e). - j v .Dispositioned: ' "use 'as is" per rework plan.. Closed'10/11/82. -j
- 3.-
7/6/82 L1SN52970 : l ~ . Rack: M120-20 and'21 cDents &Lscratches!on" lead-in' guides UseD As'Is based' on A/E determination that-the dents and scratches do' not impair 'the function of s the lead-in; guides of the spent fuel racks. Closed 8/18/82..
- 4.
- .10/18/82$.[1SN6769C - Racks
- .M120-20, 21, 22,:24, 26, 27, 28, 31,J23-Iron,' contamination wast noted.
Rust appears to be' minor-in magnitude. Bechtel-
- determined that the rust ~was minor surface' stains and would not affect the material properties or. function of 'the. rack.
Use-as-is-and closed on - 11/17/82. 5. 10/28/82 -1SN6930C Racks: M120-26 3 2-linear-discontinuities were discovered on welds between cell' walls. Bechtel ~ disposition was to repair the discontinuities in the two welds. U. S. Tool & Die authorization received.- Work completed and the NCR closed on 1/3/83. ~ 6. -12/2/82 --1SN7445C Rack: M120-20 One '(1) 111near discontinuity was discovered in a weld between a cell wall and.its -base. plate. Inspection was. visual. The identified discontinuity is not considered to; be a "significant - nonconformance" as defined in KWCLC-2233 The proposed
- disposition. discontinuity ground out and rewelded using approved applicable _. weld procedure,;
was ' acceptable -to Bechtel. The work was completed and the NCR was-closed' on 1/03/83 W-_ -_-_____~~a.
~ 3 ' Attachment V to WM 87-0282 .Page 2 of 7 - October 23, 1987-- 'I 'l 7.. 2/10/83 1SN8582CW Rack: M120-20 i Two' (2) linear discontinuities written per KG&E' Request l via E NCR 1NN51091J.. Inspection. was visual. A/E determined a use-as-is-disposition was applicable.since :)' the crack or linear indication was superficial. fusion between adjacent plates and 2)- the pinhole or crack' described.in attachment-did not affect the structural integrity of the rack. Closed on 2/23/83 8. 3/25/83 1SN96800- Rack: M120-28 l ' Damage to cell walls & lead in guides during transport to Fuel Building. The fuel cell will be repaired to its original design condition. .The dont in the l lead-in guide .ll.not affect its function (theidented side is not used ' as a fuel lead-in guide). The work was completed and the NCR was closed on 4/12/83. 9. 6/14/84' 1SN55190M** Rack: M120-21, 26, & 27 Per Telex"from y NFD on 6/7/84, some of the fuel cells 'were found to be out of . tolerance..E NFD reque,ted additional measurements. .0.060 i Based 'on the measurements cells were identified for repair by placement of a inch shim in the indicated' corner or by using an NFD approved self-leveling device. I Closed 6/26/84. 10. 8/21/84-ISN55295M Racks : M120-21, 22, 23, 24, 26, 27, 28, and 29 13 cells. exceed verticality as required by 'E NFD per readings of 1SN55190M The cells were rejected for use. Administrative controls are to be imposed by the owner to preclude the loading of fuel into the cells. The owners may use 12 of the. cells provided that they are repaired or remeasured per the NCR disposition. Closed 9/24/84 NCR Definition: Reports written to document nonconforming conditions, that is, departures from approved . project requirements and include physical d e fects, test
- failures, incorrect or inadequate documentation or deviations from prescribed processing, inspection or test proc ed ures.
NCRs were those nonconformances dispositioned a requiring client or A/E approval according to the Design and Construction QA Program. I
- KG&E Surveillance Report #S-531, 7/9/82, NES Inspection of Racks M120-20, 21, 26, 27.
No Open Items issued. l
- Measurements used to resolve SDDRs C-175-1-27, 28, 29, 30, 31 - MRR-75971.
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- Page13L'or:7.
4 l0ctobert23 -3 987. 1 'y l 9:. .2i. - Deficiency Reports JDRsf q N EDRs Identified for the. Spent Fuel Racks! ~ sThe'reTwere four"(4): Deficiency Reports generated 'by DIC concerning the Spent Fuel' Racks.; 1 ,a
- 1.e 2/4/82 - 1SD9321CR*
- -. Rack:'M120 'm Page.3-of.121for. the'. Liqdid. Penetrant ~ Examination ' is ' ' not. traceable,to4 other' 1
~ documentation or ~ materials. ;. The corrected L documentation was received. .The'DR.was; ?, closed'on 4/7/82. .c '2. 2/11/82: - 1SD9359CR* l-crack: M120-26L L No.L.'identificatiori tagfattached to rack. The tag was received and attached tof the; ' rack using.an ' approved welding procedure. The work was-performed and the ' 'DR : was -
- closed on 8/5/82.
3. 2/11/82 - ISD9374Can - Racks'M120-20, 21l,.'and.26-
- DIC was. notified;by Bechtel, BLSE-10,232,- - of the Spent ~ Fuelt Rack Rework Plan, C'
175-1: R/09' on} 2/2/82, ' for welds at top edge of. Spent Fuel Box ' Walls not ~ ground smooth.as=. required by Bechtel' Spec. C-175, Item 7.8. The. work.was completed 'in 1accordance with' the' Rework Plan and. the DR.was closed on 6/29/82.. ,q 4. 3/10/82 :- 1SD9767CR ~ Rack:: M120-27
- Received - without ' identification (not traceable to
' material) and damaged . identification. The identification tag has been located on the rack and the damage. m was determined to be surface blemishes of.a. non-reportable ~ nature. The DR was closed'on-4/07/82.-
- DR Definition:
Reports written to document a deficiency in characteristic, documentation or. procedure 1 rendering the quality o f. an item unacceptable or indeterminate. DRs were Tnonconformances dispositioned-by the Discipline Engineer and did not require client or, A/E. approval;(Also known as Cat. B'NCR). .# -KG&E. Surveillance S-452 3/1/82 i Storage & Maintenance of Racks 'I p
- No10 pen Items
- KG&E Surveillance S-519 6/30/82 Rework plan
..No Open Items "### See : Rework Plan Summary in Section 4. " i.
a :. .. Attachment-V to WM' 87-0282 4 i .Page 4-of 7 October, 23, 1987 3 SDDRs (Supplier. Deviation Disposition Requests)-- - SDDRs Identified for the Spent' Fuel' Racks: Twenty-three (23) SDDRs written concerning the spent fuel racks are listed below. -All' ' SDDRs were dispositioned as noted below. SDDRs Items #12 through #23 were concerning . rack cell verticality 'and were found to be acceptable by Westinghouse and/or Bechtel. j 1. 10466-C-175-1 4,;All racks Materials purchased to the latest year designation of ASTM A240, A479, A276, A480,- A193 & A194 instead of the 1975 year designation required by 10466-C175. ' Bechtel - stated' that the material meets all engineering requirements. I 2. 10466-C-175-1-5,_ Racks: M120-21, 27, 25, 31, 23, 29 i Assembly channels, fabricated in two. pieces rather than.one continuous piece of material. Bechtel allowed use of the two angled pieces which are formed from' sheet j material add welded at the web center. 3. 10466-C-175-1-6, Racks: H120-20, 26, 21 { .960" to.125" radius tolerance be established and blending of intersection. edges into the cell walls. This should provide' a finish to avoid causing possible i contact with fuel assemblies. A 0.060 inch to 0.125 inch radius and blending of interior section edges into the cell walls were approved by Bechtel as meeting the specification. l 4. 10466-C-175-1-7,. Racks: M120-20, 26, 21, 27, 22, 25, 31, 24, 28, 23, 29, 30 l Lead in guide to rack assembly to use a continuous weld and eliminate the blended step created by intermittent weld. Bechtel-concurred with-the proposed disposition to use a continuous weld thereby providing a more uniform transition over the full distance where the lead in guide and cell wall built together. '5. 10466-C-175-1-9, Racks: M120-20, 26, 21, 27, 22, 25, 31, 24, 28, 23, 29, 30 Continuous tack weld where bottom plates and box intersect at notched locations. I Bechtel concurred with the proposed disposition to use the continuous tack weld versus a square groove. .6. 10466-C-175-1-10, Racks: M120-20, 26, 22, 24, 28, 30 Use a.25 inch fillet weld flush or groove weld flush rather than a single bevel groove that extends through the parts. Bechtel's disposition was to use a 0.25 inch groove weld meets the intent of the detail drawing. L 7. 10466-C-175-1-11, Racks: M120-20, 26, 21, 27, 22, 25, 31, 24, 28, 23, 29, 30 ' Bottom plates welded to box cells. The dimension cannot be held if plate is flush to cell. Bechtel approved a change to dimensions but did not specify the tolerance. I wn._ ..._.-_m.
W I' t I ' Attachment V to WM ' 87-0282 ] Page 5 of 7 I- ~ 0ctober' 23,'1987 8. 10466-C-175-1-16,.Rackt.M120-20 Rack assembly.090 inch over maximum final dimension of 147.91 inches. Bechtel accepted the noted deviation since it did not affect installation fit or function of the ' rack. 9 10466-C-175-1-24, Rack: M120-23 Rack assembly.150 inch over maximum tolerance of,147.91 inches at final dimension .1 inspection;. ' Bechtel approved the. proposed disposition since the out-of-tolerance. does not impair integrity or function of the rack. 10. 10466-C-175-1-14, Rack: M120-30 Several rack-cells damaged at U.S. Tool & Die during handling and movement of rack.- Bechtel approved the repair and rework of cells since the accident did not impair the structural integrity of. the rack. -1 1.., 10466-C-175-1-32, Rack: M120-30 Rack. assembly.060" .090" over maximum ' allowable of 147.91 inches. Becht'el approved the' deviation since the out-o f-tolerance dimension does - not impair einte trity or faration of,the rack. c 12. 10466-C-175-1-15, Fack: M120-20 i Not all cells meet the.125 inch radius circle for plumb (14 cells out of 80) AA7, AA9, DB2, CC9, DD2, DD6, DD10, JJ5, RR1, #RR3, RR9, SS2, SS4 Acceptable to Bechtel, the disposition was coordinated with Westinghouse per SLBE 81-601 dated 6/23/81. -13. 10466-C-175-1-17 Rack: M120-26 43 cells out.of 120 exceed the.125" radius circle for plumb. i 3 cells exceed W verticality tolerance. Acceptable to Bechtel, the disposition was coordinated with Westinghouse per SLBE 81-601 dated 6/23/81. 14 16466-C-175-1-18, Rack : M120-21 37 cells out of 80 exceed the.125" dimensional criteria and 2 cells exceed W verticality tolerance of.125 inch radius circle for plumb. Acceptable to Bechtel, the disposition was coordinated with Westinghouse per SLBE 81-601 dated 6/23/81. 15. 10466-C-175-1-19, Rack: M120-27 47 cells out of 120 exceed the.125" dimensional criteria and 5 cells exceed W verticality tolerance of.125 inch radius circle for plumb. Acceptable to Bechtel, the disposition was coordinated with Westinghouse per SLBE 81-601 dated 6/23/81. 16. 10466-C-175-1-20, Rack: M120-22 43 cells out of 100 exceed the.125" dimensional criteria and 5 cells exceed W verticality tolerance of.125 inch radius circle for plumb. Acceptable to Bechtel, the disposition was coor U aated with Westinghouse per SLBE-
' Attachment V to WM 87-0282 Page 6 of 7 October 23, 1987 17. 10466-C-175-1-25, Rack: M120-25 54 cells out of 120 exceed.125" dimensional criteria and 9 cells exceed the.125 inch radius circio criteria. Use As Is by W 1etter SNP-4618, dated 5/5/82. 18. 10466-C-1-26, Rack: M120-31 36 cells out of 120 exceed the.125" dimensional criteria and 2 cells exceed W verticality tolerance of.125 inch radius circle for plumb. Accepted by Bechtel in accordance with provisions of Westinghouse letter SNP-4618, dated 5/5/82, 19. 101466-C-175-27, Rack: M120-24 86 cells out of 120 exceed the.125" dimensional criteria for plumb. Accepted by Bechtel based on meeting with Bechtel, KG&E, SNUPPS & W on 8/11/82 for evaluation of calculations performed by Westinghouse Nuclear Fuels Division per telecopy dated 8/19/82. 20. 10466-C-175-1-28 Rack: M120-28 88 cells out of 120 exceed the.125" dimensional criteria for radius. Accepted by Bechtel in accordance with the provisions of Westinghouse telecopy to Bechtel dated 8/19/82. ~ 21. 10466-C-175-1-29, Rack : M120-23 100 cells out of 120 exceed the.125" radius circle for plumb. Accepted pr Bechtel in accordance with provisions of Westinghouse telecopy to Bechtel dated 8/19/82. 22. 10466-C-175-1-30,. Rack: M120-29 92 cells out of 120 exceed the.125" dimensional criteria for plumb. Accepted by Bechtel in accordance with the provisions of Westinghouse telecopy to Bechtel dated 8/19/82. 23, 10466-C-175-1-31, Rack: M120-30 71 cells out of 120 exceed the.125" dimensional criteria for plumb. Accepted by Bechtel in accordance with the provisiens of Westinghouse telecopy to Bechtel dated 8/19/82. - SDDR Definition: Formal document submitted by the vendor to Bechtel Engineering requesting a deviation from the required specification / standards with justification that the deviation will not a f fect form, fit or function of the finished product. SDDRs were approved by Bechtel Engineering, returned to vendor subsequently becoming part of the document package submitted to the buyer. ' Exceeds W verticality tolerance ri
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m 1 ~,t, EattischAentEV3o WM: 87-0282.: M; m Page371of:7-
- October 23,'
- 1987J
%t j T f I s ,I 4.,. . REWORK PLAN
SUMMARY
h-fework.fof(spentLfuel; racks-numbersM120-20!726, 'and 21 was completed per' the : Bechtel-R ~ 4 F Rework Plan' C-175-1, c. Rev.- 0.. s - Rework consisted of grinding the top :. edge -of. the _ ' fuel. box: walls :: providing.: a1smo6th '] blended: lead in ' edge _with a minimum of- 0.12 ' inch radius, p. 1, C. S Fuel; lboxesiwere visually. inspected' for;large, ' roughI or sharp spot weld' projections:and; 7 corrected by 'grindingi to : produce a weld surface condition. equivalent to 'other acceptable 1
- - ; spot';. welds.
4RNwork.was; performed by site,.personnelCand inspected ' by a qualified supplier -inspector.- l -;The^ rework planLwas~compidted.and: closed.out in June 24, 1982.' s 4 7 g. j ~. ' j t l } } iL-A L.^. __ '_ _ l l_^... - - - _ _. _}}