ML20236L686
| ML20236L686 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon, 05000000 |
| Issue date: | 07/06/1984 |
| From: | Canter H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Shackelton O NRC OFFICE OF INVESTIGATIONS (OI) |
| Shared Package | |
| ML20236L679 | List: |
| References | |
| FOIA-84-744 NUDOCS 8711110017 | |
| Download: ML20236L686 (33) | |
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UNITED STATES JE '
j NUCLEAR REGULATORY COMMISSION RE040N V
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.., s 14soMARIA LANE,sulTE 210
" g,.... + f WALNUT CREEN. CALIFORNIA 94$s6 Jyt O1984 MEMORANDUM 70: Owen Shackelton, Jr., Director
.Of fice of Investigations Field Office, Region V FROM:
H. Center, Chief. Engineering Section
SUBJECT:
COMPLETION OF-TECHNICAL SUPPORT TO OI ON ALLEGATION 99 (Bostrum-Bergen) i The enclosure to this memorandum documents Mr. Wagner's' efforts in support of
. the subject allegation.
A total'of 260 manhours of effort went into' this RITS item V23001. With this~
memorandum, Y23001'is closed as is Region V's effort on Allegation 9.9.
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Harvey Canter, Chief Engineering Section
Enclosure:
As Stated cc w/ enclosure:
T. Bishop
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99 Informatiott in this record was deleted tfon Yf e knf m tion mC f ct e
FOIA.
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'1' Concerns /A11eastions Renardina Bostrom-Beraen/Meddeo Metals 3
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a.
Trackina No. 7: "I signed cff on inspection reports without doing
' the inspection." In regards'to Bostrom-Bergen/Meddco betals materials supplied to the Diablo Canyon Project: " Hostly paperwork
. problems and no inspections on some hardware. Generally, though,
.the overall shop quality at Bostroe-Bergen was very good.
I's.not-questioning the work, just the paperwork."
NRC Findina: The allegation was not substantiated.
A review-of pertinent records established that the former inspector is' credited with performing 650 inspections while he'was' employed at Bostros-Bergen. Fifteen of thd 650 inspections involved safety-related material..These fifteen items were found to'be supplied to Diablo Canyon Unit,2 and involve " stock" material (i.e.
raw material items which do not involve welding). The NRC-Region V staff inspected 14 of.the 15 items and found them to conform with r
reguriesents.,The licensee selected a 10% sample of.the other (non-safety related) inspections related to the inspector and.
performed a reinspection (involving 940 welds).- Seven of these 940 reinspected (non-safety related)' welds were found to have minor deviations (e.g...-undercut) from Code' requirements..Ekesed upon the l
low defect rate (0.7%).the licensee has concluded that the structures 'and components installed at Diablo Canyon have not been adversely impacted by the.former inspector's alleged performance.
The staff concurs with this conclusion based upon a review of licensee actions, independent inspections of the fourteen safety-related items and safety-related installed hardware discussed l
in Section 2.
Without more specific information it cannot be determined conclusively whether the former inspector neglected to do the inspections.
Trackina No. 10: Sending incorrect steel samples to testing laboratories for testing.
NRC Findina: This allegation was not substantiated.
l A review of invoices received by Bostroe-Bergen free various testing j
laboratories during the time period in question revealed only a few instances where material testing was requested. The uaknown material was sent to the testing laboratory in order to obtain chemical and mechanical properties needed to certify the material.
The invoices were reviewed for evidence that would enable traceability to a specific ' piece of hardware. ' Invoices reviewed were from the following testing laboratories:
(1) Sinnet Testina Laboratories One applicable invoice, Invoice Numbe.c 13464 of February 24, 1982. This was for an 18-inch long section of 1-inch.
Schedule 40 pipe, sent for tensile testing and chemical analysis. Signet' Report Number 8738 under Bostrom-Bergen i
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Purchase: Order Number; 11226 for Job Nwsber 2424 (Southwest j
Texas Project).
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(2) 'Anamet Testina I. laboratories
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l One applicable invoice, Invoice Number 102171 of October 29';
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1982. for four lots' of material sent for. chemical analysis and.
tensile testing, under Bostrom-Bergen Purchase. Order.
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d Number 11820 for ' Job 2311 (Diablo-Canyon). Control l Numbers.
1 listed are.31-68,24-700'and 24-731.-
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.(3) Hales Testina I, laboratories i
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'No invoices.during the time period of interest.
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1 All Bostrom-Bergen materials fabricated unoer PG&E, specifications j
were assigned a '" Control Nussber" which identified.a given lot of y
material, and signified that the material'was acceptable for use; j
L Items subsequently fabricated from material.with a control number
.j were identified by-a piece number..It is not possible t'o establish at this time t, hat all test samples were taken from the specified t]
piece or lot number. If the allegation were more -specific as(to piece'aumber, then another sample could be taken for comparisdn of results. However, even lif true, the consequences of the alleged improper test results would not likely be, of conseqt.ence since (1).
1 essentially all of the structural materials of concern were of the l
s'ame material, A36 carbon steel, and (2) only a very'small portion of the materials required lab testing - i.e., those for which the heat number was not known.
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Tracking Number 11: Substitution of foreign produced steel for domestic steel. "Only American steel can be used on nuclear construction work."
i NRC Finding: This allegation was substantiated.
1 PG&E's Final report of March 22, 1984 on these allegations addresses this in Section 4.2.12.
They-found two instances of foreign steel having been used at Bostrom-Bergen and one at Meddco.
Their investigation conclusion is that, in a few instances, both Bostrom-Bergen and Meddco used foreign produced materials.
Requests were made by Bostrom-Bergen for authorization to use this steel prior to fabrication.- The, licensee reviewed these requests and either accepted or rejected them for:the intended application. The inspector concludes that the substitution and use of foregin steel with the same certifications as a domestic steel is acceptable provided prior authorization is obtained from the licensee, ar. in this' instance.
d.
Tracking Number 17: Welders were not continuously certified (during 1
a layoff in 1979, welders executed affidavits on continuous welding).
NRC Finding: This allegation was not substantiated.
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The.AWS D1.1 Structural Welding Code states that the welder's qualification shall be considered in effect indefinitely unless the welder is not engaged in a given process of welding for which he is qualified for a period exceeding six moaths. The Code'alno states that the Engineer, at his discretion, may accept evidence of previous qualification of welders, welding operators, and tackers to be employed., The engineer should accept properly documented i
evidence of previous qualification tests.
This item was previously identified by the Brous and Root Audit of Bostrom-Bergen resulting in a 50.55(e) report. NRC Region IV, in their Report Number 99900726/80-01 of June 24-27, 1980, followed,up i
to assess the cause,.and corrective acticas relative to this' l
50.55(e) report regarding inadequate records of welder qualifications. Region IV concluded that the weakness in the Bostrom-Bergen QA program prior to 1979 with regard to welder certification was' adequately corrected and there are. now adequate e
measures to prevent recurrence.
5 The PG&E final report states that they did their investigation,on welder qualfiication for work performed on Diablo Canyon only. They found 2 welders out of 13 with lapses of employement in excess of 6 months. Both signed affidavits attesting to welder continuity through other employment.
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Tracking Number 26:
"There was no known QA/QC program at 1
Bostrom-Bergen until about six months before I departed."
NRC Finding: The allegation was not substantiated.
Review of documentation revealed that Bostrom-Bergen did have a QA/QC Program' established and implemented during the time period of concern (1979-1980).
The program required by PGE specifications is described in the Bostrom-Bergen Metal Products Quality Assurance Manual (QAM). Implementation of the'QA/QC Program was evident through review of audit records 'and QC inspection reports. The QA department appeared to have sufficient authority and independence to identify quality problems.
The licensee has performed an investigation to assess the adequacy j
of the Bostrom-Bergen QA Program. This included a review of procurement documents issued to Bostrom-Bergen, plus employee interviews. The licensee concluded that the QA Program adequately addressed the specification requirements, the QA Program was appropriately implemented,'and that present and former employees favorably reflect on the integrity and performance of both f.
Bostrom-l'ergen and Heddco Metals for items supplied to DCPP. This l
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- QA Program review was for the time period 1977 through 1982.
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However, the staff review of the QAM prior to the time period I
covered by the allegation revealed several inadequacies in the QA/QC Program. These were:
(a) no mention of a QC inspector or who will perform QC inspections during fabrication; (b) no QA department identified, only a QA lianager; (c) final inspection performed by a fabrication inspector, i.e. production inspecting their own work;
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'4 (d) no " company, policy statement. establishing the QAM as being.
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applicable to all nuclear projects; and (e) no management approval
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of the QAM.' These' inadequacies were identified in the original'QAM
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A of~ August 20, 1969 and were in effect until March 14,'1975 when the'-
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-QAH was revised.- The revised QAM represented a positive coenitaent 4
by Bostroe-Bergen management to. establish and execute their quality assurance program. The Q4. department was expanded and appeared t.o
'have sufficient authority and independence to identify quality.
problems.
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Trackina Number M :
"To my knowledge, there never were any written o
(welding) procedures to be followed by the welders for any work Aone at the Bostrom-Bergen plant".
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1 NRC Tindina:. Thel allegation was not substantiated.
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Review of Bostroe-Bergen records revealed numerous welding-J procedurer written by Bostrom-Bergen and approved by PG&E,' These welding procedures were stilized by Bostrom-Bergen to. fabricate
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M materisl supplied to the.Diablo Canyon Project. The inspector
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reviewed.the weldina procedures for. compliance to the requirements-1
.,1 the contrar specifiestion and AWS DI.1 Structural Welding ~ Code.
- l Attributes examined were material,; welding process, filler metal,-
1, welding current, electrode-size,' preheat and interpass temperature, j
o and when applicable the supporting procedure qualification records.
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Welding procedures reviewed are identified in Attachment A.
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The inspector interviewed four welders and one welding foreman (See
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Attachments) that where employed by Bostroe-Bergen during the time
'i period of concern. All stated that written welding procedures were
.availabl(. within the welding area, for their use when welding.
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Trackina Number'29: Failure to perform required preheat and
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postweld heat treatements.
NRC Findina: This allegation was not substanitated.
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Review of contract specifications and Bostrom-Bergen procedures I
revealed that only one nuclear job required postweld heat treatment j
(PWHT). Bostrom-Bergen " Post Weld (Stress Relieve) Heat Treatment" l
Procedure Number QAP 26 Revision 0, of April 13, 1976 was reviewed
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and approved for use on the Southwest Texas Project for Comanche '
Peak. Bostrue-Bergen subcpatracted PWHT work to CONSECO, CONSECO-was' audited by Brown & Root and was listed on Bostrom-Bergen's
'l approved vendor's list.
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Preheat, when required, was specified on the applicable welding-procedure, which complied with the preheat requirements specified in i
AWS D1.1.
AWS D1.1 does not require a written procedure describing preheat, only that the requirements for the minimum preheat and f
interpass temperatures he is accordance with Table 4.2 for the l
welding process being used.
Interviews with welders (See j
Attachments) who were welding during the time period of concern
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stated that preheat measurements were always observed by a QC 1
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I' inspector. The QC inepector's initial on the Inspection Report signified that welding tas performed in accordance with the welding procedure including preheat when specified.
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Tracking Number 32: QA/QC plates were used as work besches.
Netc Finding: This allegation was not substantiated.
The alleger gives an example wherein 6011 weld rod was used for tacking, with weld material subsequently removed and the weld ground out. Technically, there are no problems with this practice as long as the original quality of the plates is maintained. However, the alleger's concern that use of QA/QC pirttes in this manner (i.e., as workbenches) is an improper practice appears to be valid.
The inspector concluded that not enough technical justification existed to warrant further investigation.
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Tracking Number 34.
No control of heat numbers. No transferring of heat numbers to sectioned pieces until late 1980.
NRC Finding: This allegation was not subt.tantiated.
PGE's Final Report of March 22, 1984 addresses altered heat nunibers and states in Section 4.2.9 that the QA Program from December 14, 1977 to Augur,t 3, 1983 required large material to have a control number, and required this control number to be transfered when components are sectioned during fabrication.
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An URC Region V inspector confirmed the existence of this practice; refer to Section 2.a of this report. Bostroe-Bergen Fabrication and Erection Drawings originate f rom PG&E Design Drawings. The inspection showed that Bot,trom-Bergen items are identified by a piece (mark) number. These numbers are tcansfered to the Bostrom-Bergen drawings which in turn are identified on PG&E Lift Drawings located at the jobsite. The heat numbers are traceable to these Piece Numbers.
Bostrom-Bergen's QA Program addressed control and traceability requirements. Evidence of implementation was presented in PGE's Final Report by review of NCR's, Hold Tag Logs, Receiving Inspection Reports, Internal Audit Reports, Shop Travellers /Inspectf.on Reports, and Mi.nor Variation Reports.
Therefore, there appears to be no substance to this allegation.
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Tracking Number 36: Deficient welding of a " railway support system" l
on the overhead fuel handling crane.
NRC Finding: This allegation was not substantiated.
The inspectors' examination of documentation revealed that Quality Class 1 (safety-related) fabricated rails or supports supplied by Bestron-Bergen to the Diablo Canyon Power Plant did not require welding. Bostrom-Bergen did supply non quality Class 1 (not i
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safety-related, no QA requirements) rail supports and monorail l
' tracks that required welding; however, the drawings indicate that the majority of these items were bolted connections as opposed to a welded structure. The inspector reviewed documents rel'ated-to fabrication of crane rails and supports for evidence of l
Bostrom-Bergen supplied items. The. location of these items and a description of the findings are as follows:
(1) Fuel Handling Buildint l
(a) overhead Fuel Handling Crane Extaination of construction drawings revealed that the overhead fuel headlidi crane was supplied by Murphy 1
Pacific for Unit 1 and by American Bridge for limit 2.
No hardware was supplied by Bostrom-Bergen.
(b) Monorail Track 1
The moncreil track was fabricated by Bostrom-Bergen utilizing ~ bolted connections, i.e. no welding operations were required. The monorail track is not a Quality Class 1 safety-related item.
'(c) Manipulator Crane Rail 1
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q The manipulator crane rails were supplied by Kruse Metals.
l However, Bostrom-Bergen did supply one support beam (14W53X17) for this item; no welding was involved.
(2) Contaionent Building (Ucits 1 and 2)
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(a)-PodarCraneRail r
Th'e polar crane rail description and fabrication f
requirements are specified on PG&E Drawing Numbers j
DC 663243-429-2, DC 663243-428-2, DC 663366-119-2, and 1
DC 663366-11e-2. Review of these drawings revealed that no welding was required to fabricate the crane rails. The s
rails were rolled to a specified radius by Bostrom-Bergen then shipped to DCPP where the rails were assembled using rail clamps supplied by Bostrom-Bergen.
(b) Manipulator Crane Rail I
1 The manipulator crane rail was fabricated by Westinghouse Corporation.
Bostrom-Bergen supplied the anchor bolt assemblies which consisted of bolts, rods and plates. No welding by Bostrom-Bergen was involved.
(3) Auxiliary Buildina Monorails Bostrom-Bergen supplied hardware for fabrication of monorails that were connected in the field. No welding was performed by 1
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Bostrom-Bergen.;. This work was performed to Specification 8828
" Specification;for Architectural: Final Work" which is not
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safety-related.
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.. e Fabrication requirements.amanised by the inspector are
. contained in PG&E Drawing Numbers DC 663388-74-2, -75. -76,**-77 and 78, DC 663388-83-27through 86-2, and DC 663398-15-1.
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(4) : Turbine Buildina Monorail Bsans I
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The inspector examined PG&E Drawing Numbers DC 463388, I
. sheets 16. throagh 27 for Unit 1, and sheets 33 through 43 f;or Unit 2.
The drawings indicated that hardware fabricated by
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Bostrom-Bergen utilized mainly bolted connections.: 'Some
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welding was required on stiffeners and end stops. However,-
J this, work was performed to architectural specification'8828 j
+ which is not safety-related.
- (5) Radwaste Monorail Track Supports
'Bostr'om-Bergen supplied the monorail track supports.in-a.
'accordance with PG&E Drawing Number DC 663366-826-2. The support fabrication involved welding of various components.
However, this. is a non-Class lisystem, with work being performed to architectural specification 8828 which is'not.
. safety-related.
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Trackina Number 38:
"It was also conson knowledge that. welding was
- done on wet (steel)."
'NRC Findina: This allegation was not substantiated.
The alleger stated that he had welded en wet steel (e.g., due to rain). It is not possible at this time to prove or disprove his s tr.tement. However, Bostrom-Bergen representatives stated that the general practice had been to cover the work area to provide protection.from rain. It is also unlikely that most welders would weld in the rain because of the increased potential for electrical shock.
The reason why it is undesirable metallurgically to weld on wet steel is that the vapors formed can be harmful in certain circumstances. The water. vapor from the wet steel tends to break
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down into hydrogen and oxygen. The oxygen is of little concern in the. type of welding being discussed, but hydrogen can be dissolved into the molten metal and diffuse into the heat-affected zone of the a
weld.- If the hydrogen cannot escape, pressure buildup can result in cracking under the weld bead. However, susceptibility to hydrogen cracking is usually found only in microstructure with hardness over 30 R, ' The A36 steel being used for the structural welding of conc $rn here is not usually susceptible to hydrogen cracking.
Therefore, even if a small amount of welding was done on wet steel i
fabricated by Bostrom-Bergen, the consequences are not considered to
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be of concern, s
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'Trackina Number 39: Use of improper weld rod type (welding root
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pass with 6011 and covering with 7018).
1" Weld material should have
- been 7018."
NRC Findina:.This allegation was not substantiated.
More specific information. is needed in order to determine whether or
.not this welding practice was in compliance with the, welding procedure.. Most nuclear contracts specify a low hydrogen electrode-l
'(7018).for safety-related items. However, for items that are not safety-related or for non-nuclear applications, it is not unusual to use 6011 to: weld the root pass and weld out with 7018. Technically, the mechanical strength.of the weld joint would not be impaired by.
welding with this combination of electrodes.
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Trackina Number.40: The use of 30' rather than 45' weld bevels.
NRC Findina: This allegation was not substantiated.
4 More informatioatregarding weld. joint configuration requirements is needed to properly assess this concern. For example, did the welding procedure specify a 45' single bevel joint, or a 30' single V-joint?; The latter would give an included angle of 60*.
In any.
event,: there is no. reason why a qualified welder could not make an acceptable weld on a 30' weld bevel joint.
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Trackina Number 44:
Improper filling of holes in steel by removing coating on 7018 weld rod.
NRC Findina: This allegation was nest substantiated.
The. object of any welder is to produce a quality weld, i.e. a weld that'is made in compliance with the welding procedure and is free of defects. This cannot be accomplished by. welding with a 7018 veld
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. rod stripped of its protective coating; the large amount of porosity produced would be cause for rejection during visual inspection.
The alleger, who is not a welder, states that this was done intentionally by himself ~and other welders during plus welding of
-misdrilled bolt holes, At this time, there is not enough evidence to determine (a) if the allegation in true, (b) if this practice is applicable to nuclear a
work, and (c) how the stryctural integrity is affected.
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2.
Inspection at Diablo Canyon
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a.
Visual Inspection of Installed Hardware j
l The licensee, at the inspector's request, located and identified
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Bestron-Bergen hardware installed in safety-related systems. The inspector visually examined these iteus for evidence of material damage and weld quality. No material damage we' identified. Weld 3
location, length, size and shape were within <
truction
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specifications; weld reinforcement, appearan' J type (butt or j
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fillet)'were as required.e The areas inspected during this walkdown-Ew-and the type of hardware inspected were as follows:
.i (1) Turbine Buildina-- Component Cooling Water (CCW) heet exchanger barrier, rupture restraints for CCW heat exchanger barrier,,
leveling plates for the 4160 volt vital Bus E in the switchgear room, and diesel generator 1-1 embed plates.
'(2) Auxiliary Buildina - Auxiliary Feedwater pump 1-1 missile shield, Safety Injection pump 1-1 and 1-2 embed slabs, containment spray embeds, Residual Heat Removal pump 1-2 anchor bolts, and Boron-Injection Tank anchor bolts.
(3) Unit 1 Containment - Main Steam Generator W line rupture I
restraint Number 1047/10RT, embed plates for fan coolers, embeds for pressurizer wall and platforms, and annulus platform beams.
The inspector did not' identify any discrepant material or i
installations.
b.
Review of Quality Records The records of Bostrom-Bergen supplied hardware are located in the site QC vault. The inspector reviewed the following records associated with the safety-related items inspected during the walkdown:
(1) Steam Generator Line Rupture Restraint Number 1047/10RT drawings which included:
Embed Plates, Job Number 1818, Sheet 465 Main Steam Restraints, Job Number 2241, Sheet 1 Feedwater Restraints, Job _ Number 2241, Sheet.2 Snubber Support Structure, Job Number 2241, Sheet'3 (2) Bostrom-Bergen Shop Inspection Form F of 6-12-73 (3) Certified Material Test Reports (CMTR's) for the following items:
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Embed Plate Mark, Number B465, C465 and K465, Kaiser Steel Heat Number 147397; Mark Number A465, Kaiser Steel Heat Number 69869; and Mark Number A465 Kaiser Steel Heat Number 50117 1
Embed Plate Coupling Nuts, Mark Number A465, Schmitt Steel j
Heat Number 330B292 (4) BBMP Inspection Form F of August 20, 1969
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-(5). Main'$ team /Feedwater Restraint Materials CNTR from the L
following suppliers (Heat Numbers listed):
j U. S. Steel:. 064552, 2G7399 Oregon Steel: D9160, D8430 Kaiser Steel: 77816, 350916, 20165, 86999, 61102, 346080, 69831, 252094' q
0 Schmitt Steel:
787441, N71483, 1R1397 Bethlehem Steel: 402E4401 Republic Steel-' 8875464 Jorgensen Steel: 'D81508
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' This review indicated the material to be traceable from the insta.11stion location to the Bomon-Bergen inspection reports and the steel supplier's CMTR. The inspector did not identify any evidence.of falsifiestion of the CMTR's reviewed.
In addition, the. inspector reviewed documentation related to specific Bostrom-Bergen job numbers and randomly selected Certified Material' Test Reports (CMTR's). Appendix B is a list 1
of documentation reviewed. No evidence of falsification was identified.
c.
Annulus / Platform Modifications Bostrom-Bergen supplied material for fabrication of the annulus and platforms located in the Unit I and 2 containment' buildings. These are Quality class 1 safety-related structures. During the period following installation, new concerns regarding seismic integrity resulted in modifications to meet new design requirements. The inspector discussed the eatent of these changes and their effect on the quality of Bostrom-Bergen material. This included a review of a-over 30 design drawings illustrating locations of new connections and members. The following is the sequence of activities performed by the licensee during these modifications:
(1) 100% walkdown to inspect existing field conditions.
(2) 100% analysis to modify existing structures (Phase 1 work was based on theoretical loadings).
(3) Approximately 90% of the connections were strengthened. This.
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included new welds, anchor bolts, braces, beams,. columns, and stiffener plates.
(4) 100% of new modifications and existing structures were inspected and reinspected if discrepancies existed which
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required repair.
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I i-- l; + I .(5)' 100% re-analysis based on new load inputs from other disciplines e.g'. pipe hanger engineers (Phase 2 work was based i I on actual loa' dings). (6) Further modifications, if required, after reverification of,* ) loads resulting from Phase 2 work. I 4 ~' The result of this effort was that Bostron-Bergen-welded connections have been inspected, modified, reinspected, and upgraded to meet.the j new design requirements. This general scope of work was also l performed on all structures for Unit I and Unit 2, such as the l Turbine Building, Auxiliary Building, and Fuel Handling Building. These modifications were continually inspected by NRC Region V and i NRC contractor personnel for Itcensee compliance with design requirements. Attar:heent C is a listing of the NRC inspection l reports. j I l i i I l h I e r ) i
ATTAC10ENT A W lffna Praesdurss'Riviewad j ~ t f ' / SW-17 SM-41 FC-13*- SM-82, Rev. 2** 4M-25 -SM-42 FC-15 SM-66, Rev. 0**- SM SM-49 FC-16* SM-4 SM-51 FC-17* SM-5 SM-54 FC-20 I. SM ~SM-56 FC-21 6 7. p l SM-10 SM-57 FC-22 SM-11 SM-58 FC-23 SH-12 of 12/23/74 - SM-59' FC-24 SH-12 of 2/7/75 SM-59, Rev. 2 FC-34 SM-13 SM-60 FC-35 I s. SH-15 SM-60, Rev. 2 SU-l' . SM-16. SM-61 SU-2 SM-17 SM-62 SU ' SM-20. FC-1 SU-4 SM-21 FC-3 SU-5 SM-22 FC-3, Rev. 1 SU-6 SM FC-4 ES-1 I SM-24 FC-4, Rev. 2 SM-19* SM-29 FC-5 SM-53* i SM FC-6 SM-14* SM-31 FC-7 ,FC-41* SM-32 FC-8 FC-18* SM-35 FC-9 SM-28* .SM-36 FC-10 AWS-GMAW-2* (Meddco Metals) SM-37 FC-11 SM-74, Rev. 6* SM-40 FC-12 SM-82, Rev. 0** Utilized on PG4E Job Number 2311 - Rupture Restraints. Utilized on PG6E Job Number 2568 - Miscellaneous structural items; e.g. anchor plates, stairways, structural framing, roof framing. __.m_m.______.____
{, y s jQ' p q ot; .n j o SS j ATTACHMENT B s 1 Documentation Reviewed for Evidence of Felisfication I I 1.- BBMP Job' Number 2056 for Unita I and II, Material for Containment Piping j l Penetrations.. Documentation Reviewed: BBMP Shipping List of 11-3-72' J P ani 11-8-72; Shop Inspection Forms of 11-3-72,'30-16-72, and 11-8-72;. l j Mawley Forge CNTR, heat No. LG; U. S. Steel CMTR, heat Nos. 2P5112, ~2P5194, 2P4563,,2P330. i- . (- s l /2. '5BMF Mob Number 2057 for Units'I and II, Material for Reactor Read l Supportst.. Document'ation Reviewed: BRMP Shipping Lists of 1-11-73, ~ 12-22-72, and:10-10-72;- Shop Inspection Forms of 1-11-73, 12-27-72 and q 11-13-72;; Pacific' States' Steel CMTR, heat. No. 37166; Pacific Metals -LMTR, best.Nos. M84018, 3279; 3ethlehem Steel CMTR, heat Nos. 401J7251, p~ l' ,485A2111; Kaiser Steel CMTR, heat Nos. 244793, 69445. l t-3.- . BBMP. Job Number J101 for Unit I, Material for Annulus Banger Frames.- 1 E Documentation Reviewed: BBMP Shipping lists of 3-39-73 and 3-1-73; Shop Inspection Forms of-3-28-73 and 3-1-73; Kaiser Steel CMTR, beat Nos. 146097, 246798, 69869;lBethlelsen Steel CMTR, heat No. 153W422. g.: 4. BRMP Job Number 2158 for Uait II - Material for Pipe Restraints. Documentation Reviewed: BBMP Shipping Lists of 1-30-74, 2-1-74, and 9-14-74; Shop. Inspection Forms of 1-30-74 and 9-14-74; Kaiser Steel CMTR, heat Number 50890; Bethlehem Steel CMTR, heat Number 17422408. t 5. BBMP Job Number BB534 for Units I, II, Material for Pipe Restraints in Auxiliary Building._ Documentation Reviewed: BBMP Shipping Lists of 7-2-75; 1-29-75, and 1-8-75; Shop Inspection Forms of I-29-75; Final Inspettic/n Checklist of 7-2-75; Precision Neat Treating Company Certs; p, Ducommun Metals CMTR, heat Number 20812; U.S. Steel CMTR, heat U Number's 94E619, 97E823. 6. BBMP Job Number BB538 for Unit II, Two'W14X370 Studded Beams. Documentation Reviewed: BBMP Shipping List of,9-14-74; Shop Inspection j Form of 9-16-74; Kaiser Stee'l OfTR, heat Number 351656; Nelson Stud Welding Company Product Certification of 12-2-74. 7. .BBMP Job Numbers BB547 and 548 for Unit I, Material for Reactor Missile Ebield. Documentation Reviewed; BBMP Shipping List of 11-22-74; Shop Inspection Forms of-10-25-74 and 11-8-74; Oregon Steel CMTR, heat Nos. I D465, D9745, and E91; Kaiser Steel CMTR, heat Numbers G1298 and 11870. 4. BBMP Job Number BB662 for Units.I and II, Material for Pipe Restraints, Containment Structure. Documents Reviewed: BBMP Shipping Lists of 5-27-76 and 10-21-76; Inspection Traveler; Shop Welding Inspection j^ Report; Shop Inspection Form; Final Inspection Checklist of 5-28-76; Bethlehem Steel CNTR, heat Numbers 3P804,170268; U. S. Steel CMTR, beat Number 91A053; General Pipe and Supply Company CMTR, beat Number K33080; Signet Testing labs' Charpy Impact Test Reports; Consolidated Engineering Laboratories Ultrasonic Test Reports 12 through 21.
\\ l 4 1~ t I 9.1 Mill Test Reports: L a.- ~ Wide Flan 8e'(WF) Beans i. Beat No. Size. Lenath (ft) .1255299 $4x455 59' 173Z061 .30x108 47 1R4790-12x161 45 -70A017 14x1b3 60 75A025' 18x96 60 79221. 4x13 60 98E002 8x28 60 508235 12x92 40 E90147 14x342 60 K16989 36x300 60 'E95397 14x202 60 b. Channels Best' No. Size Lenath (ft) 10P190 10x15.3 60 12397' 9x13.4 60 125S497 6x15.1 20 3N638 3x4.1 20 65A217 12x20.7 60 92C510 15x40 40 B13800 6x15.3 40 705438 5x9 60 T31635 10x8.4 40 66A336 10x21.9 40 - a c. Angle Beat No. Size Lenath (ft) 10S415 4x4x4 50 18E126 5x5x5/8 60 1P710 3x3x\\ 20 20E241 4x3x5/8 60 252199. 6x6x3/8 40 331P876 4x4x3/4 20 355460 6x6x1 91D158 6x6x\\ 40 A8610 24x14x3/16 38488 4x4x3/8 l l l. 1 y i .l
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b 1 ATTACHMENT C NRC Inspection Reports on Diablo Canyon Desian Verification Program The followin8 inspection reports address independent inspections performed by MRC Re8 ion V and NRC contractor personnel for licensee compliance with design - det. ail requirements. Docket Number 50-275 Docket Number 50-323 Unit 1-Report Numbers Unit 2 Report Numbers 81-04 81-04 '81-17 81-11' 81-20 .81-14 82 82-01 82-07 82-06 82-10 82-08 82-13 ' 82-09 16 82-11 82-22 82-13 82-26 82 '17 .82-35 83-01 82-39 83-03 83-02 83-04 83-04 83-05 83-05 83-07 83-06 83-12 83-08 .83-17 83-15' 84-01 83 84-02 .83-24 84-04 l 4 = ) i ) k i i i L______..-- l
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