ML20215H997
| ML20215H997 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon, 05000000 |
| Issue date: | 02/07/1983 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20213D283 | List: |
| References | |
| FOIA-84-21 RCP-G-5, NUDOCS 8705070180 | |
| Download: ML20215H997 (96) | |
Text
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NuueER RCP G-5 L (3r*S'S Pacific Gas and Electric Company REVISION 2 i(
m DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 1/25/83 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 8 RADIATION CONTROL PROCEDURE Tm.E; CONTROL OF ACCESS FOR RADIATION W
PROTECTION PURPOSES l
3 APPROVED:
PLANT MANAGER O
DATE SCOPE This procedure discusses physical barriers and administrative controls which are employed to control access to various plant areas for the purpose of radiation protection.
DISCUSSION In order to limit the exposure of individuals to radiation and radioactive materials, it is necessary to maintain control over personnel access into areas of the plant where such exposure is possible. This control consists of a system of physical barriers and warning signs and signals to prevent unauthorized entry into the
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Radiologically Controlled Area of the plant, and administrative procedures which govern authorized entries.
PROCEDURE I
1.
Restricted Area and Exclusion Area a.
The Restricted and Exclusion Area perimeter is fenced with barbed wire and is posted to legally designate the area as private property.
b.
Access to the Restricted and Exclusion Area along the main access road is nonnally controlled by limiting access to the Owner Controlled Area at Avila gate (see Administrative Procedure A-6).
2.
Radiologically Controlled Area (referred to as the " Controlled Area" below).
a.
The normal pennanent Controlled Area of the plant includes the containment buildings, the fuel handling buildings, the outside tankage areas, the solid radwaste storage area, most of the auxiliary buildfnif, and the calibration facility in the The various areas referred to in this procedure are defined in
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Radiation Control Standard No. 4 OC0072 IIII g50 0 870505 f
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paas 2 op 8 N CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES
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Unit No. 2 turbine building. The perimeter of the Controlled Area shall consist of barriers such as fences, doors, gates, etc., which prevent unauthorized entry.
b.
The perimeter of the Controlled Area shall be posted with a sign bearing the words " CAUTION-RADIATION AREA - RADIOACTIVE MATERIALS-at all access points and along the fence at intervals not to exceed 50 feet.
I c.
There is only one path of personnel access nomally used to enter the Controlled Area. This is through access control.
Material and equipment may enter or leave the Controlled Area at points other than access control. However, anything leaving the Controlled Area must meet radiation and contamination requirements for material in unrestricted areas as covered in Radiation Control Procedure G-6.
d.
All work in Controlled Areas will be in accordance with an RWP or SWP. Administrative requirements for RWPs and SWPs, and for entrance and egress from Controlled Areas are discussed in Radiation Control Procedure G-1.
One or more signs may be required to properly identify the e.
radiological conditions within the Controlled Area.
f.
Access to " clean" areas of the auxiliary building, fuel handling building and yard area will be pemitted in street clothes.
3.
Radiation Areas Radiation Areas within the Controlled Area shall be identified and posted using approved signs containing the radiation symbol and wording described in Radiation Control Standard No. 4.
The boundary of the Radiation Area shall be set at 0.8 mrem /hr isodose.
g: If a Radiation Area must be established in an unrestricted area, the boundary shall be established at the 0.6 mrem /hr isodose. A Radiation Area is established for dose rate control.
1.
Personnel may use the tontrolled Area entry point located at the east side of the control room for emergency or other urgent reasons only. When leaving the Controlled Area, however, the nomal access control point should be used, regardless of the point of entry.
OC0072 2111 I
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NUMasm RCP G-5 otAsi.o CANYON P.NEM M. ANT UNfT 43) 1 AND 2 maVWON 2 DATs 1/25/83
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PAGE 3 op 8 Tm.E: CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES 4.
Surface Contamination Areas Areas which contain loose surface contamination equal to or above the limits listed in Radiation Control Standard No. 4 shall be identified and posted using the specified signs and wording. The.
contamination levels at the boundary shall be less than the limits of Radiation Control Standard No. 4. :!f dose rates are also present in this area, additional wording shall be posted to identify the hazard. In this case, the boundaries may be adjusted to meet the more restrictive requirement. Primary contamination control points shall be established at the boundary of the surface contamination area.
2 g: The surface contamination. levels below 100,000 dpm/100cm are not high enough to require respiratory protection.
5.
Radioactive Materials Area Areas which contain radioactive materials in quantities defined in Radiation Control Standard No. 4 shall be identified and posted
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accordingly. The dose rate within this area is expected to be less than 0.8 mrem /hr.
If it is expected to be greater, additional posting is required to identify the hazard. The surface contamination levels are expected to be less than the limits of Radiation Control Standard No. 4.
If they are found to be greater, additional posting shall also be done.
6.
Airborne Radioactivity Area Areas which meet the criteria listed in Radiation Control Standard No. 4 for Airborne Radioactivity Access shall be identified and posted accordingly. If dose rates in excess of 0.8 mrem /hr exist in the area, the appropriate wording to identify the hazard shall also be posted.
7.
High Radiation Areas within the Controlled Area must be identified and posted, using approved signs listed in Radiation Control Standard No. 4.
Any of the previously discussed signs may also be posted along this one to fully identify the hazards. _
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OC0072 3III
NUMBER RCP G-5 DiAal.o CANYON POWER PUNT UNrf NCMS) 1 AND 2 navmoN2 DADE 1/25/83 PAos 4 op 8 TRLL CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES b.
Each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area. Entrance into a High Radiation Area shall be controlled by requiring issuance of a Routine Work Permit (RWP) or SpecialWorkPermit(SWP) c.
Each high radiation area with dose rates between 100 mrem /hr and 1000 mrem /hr should be maintained locked except during periods when access to the area is required, with positive control over each individual entry. This control must be established in such a way that personnel are not prevented from leaving a high radiation area.
d.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- 1) A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- 2) A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
- 3) A health physics qualified individual, e.g., a member of' the Chemistry and Radiation Preotection Department who is qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the RWP or SWP.
e.
Areas accessible to personnel with dose rates in excess of 1000 mrem /hr (High-high radiation areas) shall be provided with locked doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Shift Foreman and/or the Radiation Protection Supervision.
Doors shall remain locked except during periods of access by personnel under an apptoved RWP or SWP which shall specify dose rates in the innediate work area and maximum allowable stay times for personnel in that area. In addition, these doors shall be posted within a sign stating OC0072 4III e
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a O NWB R RCP G-5 otAaLO CANYON POWER M. ANT UNff NCMS) 1 AND 2 REVSON 2 f
OAT 1/25/83 4
PAaE 5 Op 8 Tm.a: CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES
" CAUTION-CONTROLLED ACCESS AREA - CONTACT RADIATION PROTECTION PRIOR TO ENTRY - SPECIAL PRECAUTIONS REQUIRED." In lieu of the stay time specification of the RWP or SWP, direct or remote continuous surveillance, such as closed circuit TV cameras, may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities in the area. Radiation Protection supervision shall specify the name/s of the personnel whu are providing this coverage.
f.
The controls specified in 7.c. and 7.e. shall be established in such a way that no person will be prevented from leaving the High Radiation Area.
g.
For individual areas where the radiation levels are in excess of 1000 mrem /hr (High-hign radiation areas) that are located within large areas, such as containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then those areas shall be roped off, conspicuously posted and a flashing
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amber light shall be activated as a warning device.
h.
Individuals shall be logged in and out of High Radiation Areas by the Control Operator. When a person must make a series of entries to High Radiation Areas as part of his normal inspection round, he need only be logged in the first, and out of the last High Radiation Area he enters, with mention on the log sheet of each High Radiation Area contained in the inspection round. Completed High Radiation Area Entry log sheets are to be forwarded to the Radiation Protection Supervisor.
8.
Lock and Key Controls There are several types of locks on doors and gates associated with the Controlled Area. The type of locks, their locations, availability and use of keys are covered in Administrative Procedure 0-3.
9.
Temporary Controlled Areas a.
Radiation Areas Temporary Radiation Areas may be established either within, or outside the normal Controlled Area. The temporary Radiation
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oATE 1/25/83 PAoE 6 Op 8 ints: CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES Area should be roped off using purple and yellow stranded rope and posted with one or more " CAUTION--RADIATION AREA" signs.
Access to such an area must be authorized by either an RWP or SWP.
b.
Radioactive Materials Areas Temporary Radioactive Materials Areas may be established within or outside the normal Controlled Area. The boundaries shall be identified by purple and yellow stranded rope and posted with one or more " CAUTION-RADI0 ACTIVE MATERIALS AREA" signs. If there is also a potential for surface contamination, then " CAUTION-SURFACE CONTAMINATION AREA" signs shall also be posted. Steps-off pads, survey instruments and protective clothing may be established. Access in either case is governed by RWP or SWP authorization.
c.
Temporary High Radiation Areas
- 1) Temporary High Radiation Areas shall be roped off using purple and yellow stranded rope and posted with Jne or more " CAUTION - HIGH RADIATION AREA" signs.
- 2) Temporary High Radiation Areas may be exempted from the control requirements of 7.0. above for a period of 30 days provided they are properly posted and direct surveillance is used to prevent unauthorized entry. However, after 30 days, temporary High Radiation Areas must either be dismantled or permanently barricaded.
- 3) When establishing a temporary High Radiation Area, noted on the " CAUTION--HIGH RA01ATION AREA" sign the date on which dismantling or permanent barricading must be done.
- 4) All individuals shall contact the Control Operator prior to entering a temporary High Radiation Area and upon exit.
The Control Operator shall log the entry and exit.
- 5) A room or other area is not required to be posted with a caution sign, and control is not required for each entrance or access point to a room or other area which is a High Radiation-Area solely because of the presence of radioactive materials prepared for transport and packaged and labeled in accordance with regulations of the Department of Transportation.
OC0072 6111
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Paea 7 op 8 Tm.a: CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES d.
Surface Contamination Areas Areas having loose, or smearable contamination on floors, equipment, etc., require special control to prevent the spread of contamination. As a general rule, each person is responsible for promptly cleaning up any contamination for which he is responsible. Assistance may be obtained from Radiation Protection personnel.
- 1) Any area outside of an established Controlled Area having contamination levels in excess of unconditional release limits (see Radiation Control Procedure G-6) must be cordoned off using yellow and purple stranded rope or other suitable barriers, and posted as a contamination area. Access points to the area must be equipped with a step-off pad to permit protective clothing changes while entering and leaving the area. Also, survey instruments shall be set up for contamination control checks.
- 2) Within a Controlled Area, barricades with secondary
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step-off pads for contamination control purposes should be set up around areas having smearable contamination levels:
2 a) Greater than or gqual to 1000 dpm/dm beta-gama and/or 20 dpm/dm alpha.
b) Between two contamination areas which differ in contamination levels by a factor of 100 or more, when the distances to be traversed across the areas warrant the use of multiple step-off pads.
- 10. Containment Access a.
All containment entries must be made under the authorization of an RWP or SWP.
b.
When the reactor is not in the cold or refueling shutdown condition (as defined in the Technical Specifications), the following general rules apply.
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- 1) The name of each person shall be recorded on the
" Containment Entry Log" kept in the control room prior to entering containment.
- 2) Check the airborne radioactivity status board, and sign the " Airborne Entry Log" if conditions warrant (refer to RCP G-3).
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DC0072 7III
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O NUMBER RCP G-5 OlAR.O CANYON POWER PUWT UNIT WS) 1 AND 2 REVISION 2 OATg 1/25/83 3
mAag 8 OP 8 in1E: CONTROL OF ACCESS FOR RADIATION PROTECTION PURPOSES
- 3) The individual or a member of the group of persons making the entry shall notify the Control Operator immediately prior to enterin~g the containment access hatch. The Shift Clerk will log the time and date.
- 4) Upon leaving the containment building, the individuals (or a member of the group) shall innediately notify the Control Operator. The Shift Clerk shall log the time and date.
c.
When the reactor is in the cold or refueling shutdown condition (as defined in the Technical Specifications), and containment integrity is in effect, the following rules apply:
- 1) Check the airborne radioactivity status board, and sign the " Airborne Entry Log" if conditions warrant.
- 2) Sign the containment entry log sheet at the containment access hatch upon entering, noting the time of entry, and again noting the time when exiting, d.
When the reactor is in the cold or refueling shutdown condition, and containment integrity is not in effect, the normal procedures for a Controlled Area entry apply and logging into the containment is not required.
REFERENCES 1.
Title 10 Code of Federal Regulations, Parts 20, 50 Appendix I and 100.
2.
Radiation Control Standard No. 4, " Control of Access".
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ATTACHMENTS 1.
Form 18-9320, "High Radiation Area Entry Log" l
2.
Form 18-9313 " Controlled Area and Airborne Area Entry Log", Rev.
3/78.
3.
Form 18-9321, " Containment Entry Log" i
DC0072 8III 1
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P GeeE DIABLO CANYON POWEB PLANT 7,.;,' 74yfff' PROCEDURE ON-THE-SPOT CHANGE j
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_ Procedure No.
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-Type of Change: Q PERMANENT (green)
TEMPORARY (yonow); Expiration Date D. R. Clifton Chemistry & Radiation Protection ong,n,,,,
p,,,,,,,, o,,,, n, Proposed Change: (Does this aner the intent of orignal procedure?
Yes No)
(Does' it constitute an unreviewed safety / environmental questiont O YES E NO)
Page 1: Reference to (see RCP G-5) in the first paragraph under " Personal Effects" should i
be changed to (see RCP G-6)
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($8a%nt Staff)
(Plant Management Staff w/SRO Ucense)
Date
- Innediate distributio'n b the Control Room and affected work areas required? O YEs Q No Initial Distribution By:
1 Distributed To: O Control Room C Others Date Received by Document Control db f3 l
PSRC Review and Plant Managers approvst no later than d,
n te above 'plus 14 days a
E Review Date PSMC recommends approvalO vs.O No
, rg Plant Managers Approval N/A
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1 IDEMTIFidATION:
NUMBER l8 ]l 3 l - 10 l l2 lW AUDIT NO. l 8 { 3 t o l 4 l 3 l A l1 Year
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- U INSTRUCTIONS FOR COMPLETING ON BACX OF THIS FORM 2 !a*E*w'IrUm*. aim ANSI N45.2.6 - 1978-
- 6*ialil'8"8anyon Power Plant
' %,I/v Inspector Qualifications
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3a O NCR/ Problem Report Number !
db O Problem has been resolved as described in item 7.
6c O Issued to Track Supplier Audit Finding Reports.
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OlSTRIBUTION (Other Departments to receive information copy when originated - check below)
V. P..Nudear Power Generation O chief. Engineering Research O En 19 0 manage,.Nueea,nant Op eons
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r March 17,1983 H. P. Foley Company Diablo Canyon Nuclear Power Plant P. O. Box 327 Avila Beach, CA 93424 Attention: Jim Thompson QA Manager
Subject:
Tri-State Reports Enclosed With Our Letter of 03/11/83
Dear Jim:
Please consider this as confirming our telephone conversation of 03/15/83.
All infomation, except " Dates Given", on the Tri-State Investigation report is actual / confirmed information supplied by the employer or educational institution.
i Furthermore, unless the information is denoted with " verbal", we maintain writ' ten back-up documentation for all information on the report.
Should you have any questions, please feel free to call me.
Sincerely, C ARACT ENGIN NG & COMSTRUCTION 6
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Roger ates Project Manager RGC:aw cc:
A. E. Moses, H. P. Foley Company /Avila Beach, CA R. J. Messere, Cataract /Newtown, PA
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FIELD REDUISITION - PURCilASE DRDER - RECElflNG REPORT J00 NO.
DATE SilEET SillPPING ADDRESSI REQ.
7177 3/10/83
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FIELD REQUlslTION - PURCHASE ORDER - RECEIVING REPORT JOD NO.
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7177' 3/10/03 4 of 4 PUIDW1 IWm P11C00CIS Ig.-
No.F-7177-12151
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332s6-s3 c o....,. o, d., H.. F7177 12151 Items 1,2,3 d
C Size Grade Johnston ER309 1/16 x 36 3/32 x 36 1/8 x 36 H.c H.,
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1004 ASME SFAS.9 Sect II Part C sPEctricATION ASME SECT III Class 1 1971 Ed.
Test aEsutis Carbon
.063 V
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Manganese 1.78 a-Silicon
.53
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Phos phorus
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Chromium 23.0 s, -
Nickel 13.9 t,.
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Cobalt Tung st en C uminum
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We hereby certify that the above material hos b est MMIX.'
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CERTIFICATION OF TESTS Date 3-31-83 J. h...
N., 33356-83 co.e..... o,d., N.. F717 7-12151 Items 1,2,3, hiL Size Grade Johnston ER309 1/16 x 36 3/32 x 36 1/8 x 36 Heet N..
3791-57 3791-57 3791-57 Peo a.
100#
100#
100#
ASME SFA5.9 Sect II Part C sPECIPtC Af f 0N I
ASME Sect III Class 1 1971 Ed.
Test aEsut.Ts Carbon Manganese Silicon WE Mrnnny c?RTTev TMAT TMTS MATERIAL WAS PRODUCED AND PROCESSED UNDE?
Sulphur THE AUSPICES OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCORDANCE WITH Phoschorus SECT III OF THE ASME NUCLEAR CODE IDENTIFICATICN AND VERIFICATION Chromium SYSTEM AND IS IN CONFORMANCE WITH ALL REQUIRE N S.
Nickel Molybdenum Titonium Columbium Cobolt Tung sten 7 Aluminum
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s
, I, W Bends:
we hereby certify that the above material has been tested /hos not been tested in accordonce with the listed specification or.d is in conformance with all requirements:
CLr@E ASME Quality Systems Certificate L
(materials) Number QSC285 s,...., c. i....
55-Expires on May 20,1083 c.~,., v. i.s. i..
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We hereby certify that the above material has been tested 2Edxxas&Kuxr4 Kin accordence with the listed specification and is in conformance with all requirernents:
We certify that the material supplied was produced a'.d manufactured under s.....ec.i.e...
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3791-57 3791-57 3791-57 p.. a.
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100#
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ASME SFA5.9 Sect II Part C specericArrow TEST REsul T5 ASME Sect III Class 1 1971 Ed.
Carbon Manganese Silicon WE MERERY CERTTFY TMAT TRTS MATERIAL WAS PRODUCED AND' PROCESSED UNDER Sulphur THE AUSPICES OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCORDANCE WITH P ho sphorus SECT III OF THE ASME NUCLEAR CODE IDENTIFICATION AND VERIFICATION Chromium SYSTEM AND IS IN CONFORMANCE WITH ALL REQUIREMENTS.
Nickel Molybdenum Titanium Columbium Cobalt Tung sten
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We hereby certify that the above material has been testedAas not been tested in accordance with the listed specification and is in conferrnance with all requirernents:
3 ASME Qualit Systems Certificate C[4 (materials Number QSC285 s..... c. i.e....
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Size Grade Johnston ER309 1/16 x 36 3/32 x 36 1/8 x 36 3791-57 3791-57 3791-57 Hee s..
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100w ASME SFA5.9 Sect II Part C sP EC17tCATioH TEST REsut.T5 ASME SECT III Class 1 1971 Ed.
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M U O l I ' I E '4 b**~
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We hereby certify that the above material has been testedMXX1tWEKMXC6 Kin accordance with the listed specification and is in conformance with all requirernents:
We certify that the material supplied was produced ar.d manufactured under s....., c. i v...
a qualiti nsurcnce pic;; sm meeting ss.
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- e. Ord., N.. F717 7 12151 Items 1,2,3, A lb L Size Grade Johnston ER309 1/16 x 36 3/32 x 36 1/8 x 36 H.c N..
3791-57 3791-57 3791-57 Paw.d.
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1004 100#
ASME SFA5.9 Sect II Part C sPECtPICATION TEST REsut.75 ASME Sect III Class 1 1971 Ed.
Carbon Mangane s e TMTS MATERTAL WAS PRODUCED AND PROCESSED UND R Silicon
__W MERERY '*ERTTFY TMAT Sulphur THE AUS? ICES OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCORDANCE WITH P hos phorus SECT III OF THE ASME NUCLEAR CODE IDENTIFICATICN AND VERIFICATION Chromium SYSTEM AND IS IN CONFORMANCE WITH ALL REQUIRENS.
Nickel Molybdenum Titanium Columbium
~
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. Aluminum
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fron Tent alum
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A. w ld.d Me T,e...d A. w.id.d 94.
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w. -
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Bend s:
l We hereby certify that the above material has been tested /hos not been tested in accordance with the listed specification and is in conformance with all requirements:
CTl f
ASME Quality Systems Certificate 1l (materials) Number QSC285 l
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33 Expires on May 20,1983 l
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3-31-83 J o h.... N., 33356-83 c o...-. o,4., N o. F7177-12151 Item 4 h
D Sir. 1/8 x 36 Grode Johnston ET'.X, How N.,
3931-57 Pev.fs 1009 ASME SFA5.9 Sect II Part C specipicArten TEST assut.Ts ASME Sect III Class 1 1971 Ed.
Carbo"
.058 e 1.75 a"
Mongonese Silicon
.59 L '"
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S ulph u,
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Phos phor u s 20.1 v
Chromium 10.0 g.,
Nicliel
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was produced and manufactured under s.....e c.ia.i.
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CERTIFICATION OF TESTS Date 3-31-83 J
ha...
N.. 33356-83 c...
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Item 4 h.
Size 1/8 x 36 Grade Johnston ER308 H.o N..
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ASME SFA5.9 Sect II Part C 3PECINCATION TEST RESULT 5 ASME Sect III Class 1 1971 Ed.
Carbon Mongonese
__E HEREBY CERTIFY THAT THIS MATERIAL WAS PRODUCED AND PROCESSED UNDE 3 W
Silicon Sulphur THE AUSPICES OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCCRDANCE WITH Phosphorus _S_ECT III OF THE ASME NUCLEAR CODE IDENTIFICATICN AND VERIFICATION Chromium SYSTEM AND IS IN CONFORMANCE WITH ALL REQUIREMENTS.
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Heat Teeat:
Hardne s s:
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We hereby certify that the above material hos been testedAos not been tested in accordance with the listed specification and is in conformance with all requirernents:
ASME Quality Systems Certificate (materialsj Number QSC285 -
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No.
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Carboa
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We hsreby certif,. that the obove material hos been tested /J:nc stip=:cXn(pd in accordance with the listed specification and is in conformanc e with all requirernents:
'Ve certify that the material supplied s.....e c nr.i.
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.o,d.N..F7177-12151 Item 4
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3931-57 P. ad.
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ASME S A5.9 Sect II Part C SPECIPICATION TEST R E5Ut.75 ASME Sect III Class 1 1971 Ed.
Carbon Manganese Silicon WE HEREBY CERTIFY THAT THIS MATERIAL WAS PRODUCED AND PROCESSED UNDER Sulphur THE AUSPICES OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCCRDANCE WITH Phos ph orus SECT III OF THE ASME NUCLEAR CODE IDENTIFICATICN AND VERIFICATICN Chromium SYSTEM AND IS IN CCNFCRMANCE WITH ALL REQUIREMENTS.
Nickel Molybdenum Titanium Columbium Cabalt if Tung sten ef h"hlutninum kk\\ b Copper O W 3J Iron IIO T ont a tum Tin APPPnvsn 3
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We hereby certiiy that the above material has been testedAas not been tested in accordance with the listed specification and is in conforman:e with all requirernents:
ASME Quali Systems Certificate s,...., c. u...
(materials Number QSC285-c....... t..... i..
Expires on May 20,1983 55-7 3.
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We hereby certify that the above material has been tested,i:g mthymo(nod in accordarice with the listed specification and is in conformance with all requirernents:
We certify that the material supplied was produced and manufactured.under s,....# c.i.e.....
c....,.s t.. a... i..
a quality assurance pregram meeting I
55-the requirements of NA 3700/NCA
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- j. h;.j C f. Ng.~ip. - ?f;,-iTELEPHONE(213)946.1764spiggyrf'gggy p CERTIFICATION OF TESTS k
Date 3-31-83 J.hn.t on N., 33356-83 c....
. o,4., N.. F7177-12151 Item 4 h
Size 1/8 x 36 Grade Johnston ER308 HeatN..
3931-57 Peoad.
1004 ASME SFA5.9 Sect II Part C 3P E CINC ATION ASME Sect III Class 1 1971 Ed.
TEST R Esut.T5 Carbon Manganese Silicon WE HEREBY CERTIFY THAT THIS MATERIAL WAS PRODUCED AND' PROCESSED UNDER Sulphur THE AUSPICES OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCORDANCE WITH _
P ho s pho,u s SECT III OF THE ASME NUCLEAR CODE IDENTIFICATICN AND VERIFICATION Chromium SYSTEM AND IS IN CCNFORMANCE WITH ALL REQUIRE.E TTS.
Nickel Molybdenum Iitanium Columbium Cobalt Tung sten
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We hereby certify that the above material has been testedaas not bee tested in accordance with the listed specification and is in conformance with all requirernents:
ASME Quali Systems Certificate s,...,, c...,..
(materials Number QSC285-55-c...,.t....i..
Expires on May 20,1983
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M Claims for error $. deficienCtes arnoeffections, e}c must be made within 30 days after rece,ct of goods.
Matenal orgving detective tot suitacte use ma be rectaced. No cfawns for labor or damages ma be attowed and no resoonstbe8<ty assumed for delays of.
camers or delays ans,ng from hres. stnhes, or omer causes unavoidacte or eeyond controt of me Comoany Goocs covered by inis invoice were produced in comonance wth an sooncacio recuwements of tne Fast t aeor Standarda Act of 1935, as amended,and mth au aoOhcaele recutapons meteunder.
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Orange County (714) 994 2551 San Diego (714) 296-6214 COHONA, CA 91720d,to voun ACCouNr. ettasE lf,.
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DATE SHEET SHIPPING ADDnESS: FUL{NN) pQQC[1 PMS RE O."-
" ' 1 of 3 c/o Pacific Gas & Electric Cmpany R:E::
7177 3/8/83 7177-12152 DISCOUNT TERMS SHIPPING TERMS Diablo Canyon Power Plant JoD COST Cipr?
siiiifoNiitTCih 7 Miles 11 orth of Avila Beach, CA 93424 121
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VIA VENDOR:
T 3 Y (py JONS101 STN MAIL 4 IE5 0F lNVOICfS 103 10140 Rcmandel Ave. P.O. DOX 3284 P.O.13a# 367 1.-213-946-1764 FRmA Santa Fe Springs, m 90670 Avila Depch, CA 93424 I T[Lt OTY.
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300f 3/32" S/S COVDIED ELDCIIKDE E-309-16 lb. 4 47 00 i
<a, TESTIIG OINCES 90 00 c::;90 00 r
a SPECIAL REQUIRH4DirS O
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SUPPLIER SIIALL FURNISl! 'IIIREE G) PIES OF A MILL TEST REPORT SIQ1W BY. MMUF1CIURDl'S REPRESDfrATIVE. -
ed ET2. MILL TEST REPORTS SilALL DE TRNTADIE 'IO OUR PUROIASE ORDER aq MO ITai IU4BER.
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AIL COATED RCD SilAIL BE FURNISIIED IN IIErtEPICAIL1jH:;!iIIR.COtffAINEIE_
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Te4echone (213) 9461764
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For billing inquiries, call rnain office - (714) 735 3210 s
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. Los Angeles (213) 944 9981 Corona (714).735-3210 P.O. BOX 315 Orange County (714) 994-2551 San Diego (714) 296-6214 CORONA, CA 91720 To voua Accouwr et Ass Riverside (714) 359-7530 Escondido (714) 745-4732 sHow Twis muusen ou Fresno (209)'486-3373 Visalia (209)651 1445 vous asuiTTAnca:
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c CERTIFICATION OF TESTS
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- Dat, 5-10-83 33759-83
- .sn.r.
N.,
Cwse.m.es O.d.e No. F7177-12152 Item A Mfr: Stoodv Size 3/32 Grade E309-16 H2., N..
3193 Psvad.
300#
sPECIPicATIO~ ASME SFAS.4 Sect II Part C ASME Sect III Class 1 1971 Ed.
NB2130 NB2400 Tasr assutTs Carbon Manganese S;I;can WE HEREBY CERTIFY THAT THIS MATERIAL WAS PROCESSED UNDER THE AUSPICES Sulphur OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCCRDANCE WITH SECT III OF Phosphoru,THE ASME NUCLEAR CODE IDENTIFICATION AND VERIFICATION SYSTEM AND IS Chromium IN CONFORMANCE WITH ALL REQUIREMENTS.
Nickel Molybdenum Titanium ma m am a
Columbium II f4 E E I
Cebsli E E M 1.1 E
Tung sten
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Aluminum j
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sten Tantalum i
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A. w.ided Me.e Tee.t.d A. W.ld.d it.e, T=.e.d Tensiles:
v f.id T... ii.
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Red..d Ae As Welded:
Heat Treat:
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l We hereby certify that the above material has been tested /h s na een tested in occardance with the listed specification and is in conformance with all requirernents:
I s,....e c.i.e...
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ASME Quali Systems Certificate c.....t......i..
(materials Number QSC285 i
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Expire on May 20,1983
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INDUSTRY, CALIFORNIA
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CE8TIFIED MATERIAL TEST REPORT
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Jo.han9_U.S.tAipless Welding Date Khy_5.,_.1983 10140 Ro_maDdel Ave.
Certification No 481-83 Santa Fe SpIiDSL CA_20670
~
Cust:mer P. O. No.
15581 Item No.
1 Stoody Product Name 3/32" Stoody 309-16 Stainless Electrode Specification ASME Section II Part C, Classification E309 SFAS.4 and Section III NB2130 NB2400 1.ct No.
3193 Stoody Order No.
68593 Weight 300 lbs.
CHEMICAL ANALYSIS - PERCENT BY WElGHT Actual Chemical Analysis of Undiluted All-Weldmetal Deposit
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per Schaeffler Diaeram 8%: per Macne Gace 8FN Remarks:
We certify that the above material is in confonnance with the acclicable reauinments of Section II Part C and Section III. Nuclear Power Plant Components of the ASLE Boiler and Pressure Vessel Code, 1971 Edition throup.h Winter 1973 Addenda.
i Quality System Certificate (Materials) No. OSC-304 expires November 18, 1983.
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m PULLMAN POWER PRODUCTS PO#:
F717 -
52 h0DY COMPANY l
JOHNSTON STAINLESS SHIPPER #:
33759-83 I
DATE SHIPPED:
5-10-83 ITEM A APPROVED
$ '.b By Puum ro*u e Pau'i'Bente QA Quality Assurance Specialist P.c.&E. Detdo Canyon PW b!
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=-
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C O NTI N u C D P AG C.
DATE Certification No.: 481-83 2
5/5/83 l.
Material: 3/32" 309-16 Int: 3193 i
As Welded Mechanical Procerties (AC)
Ultimate Tensile Strength, ksi 89.1 Elongation in (1) inch, (%)
42 As Welded Mechanical Properties (DC)
Ultimate Tensile Strength, ksi 86.5 Elongation in (1) inch, (%)
41 o
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Paul Bente Quality Assurance Specialist IdN D
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pugw AN POWER 65 Q.A.
PA&L Deon Caw M ecC y.'TQ'-2 3
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LA8OR ATORY NO.
43456-6-1 olvisiON OF M AGN AFLUX CORPORATION.,
6800 E AST WASHINGTON BOULEVARD LOS ANGELES, CAL'FORNrA 90040 cArgngpoRico 4-28-83 TELEPHONE (2133 724 3811 k.
evaCwAsc onocR No.
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saupi.c sususTTro, 309-16 Weld Plates MATERI AL 5PECIFICATloNa ASME SFA 5. 4 TestucTwoo ASTM E8 CERTIFIED TEST REPORT l
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3/32" Lot 3193
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.0495 3500 70700 4410 89100
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I Requirements shes n are per P.O.
g' h*;N D I.,F(TON MAXIMUM REQUIREMENTS fOhkbfYI l
l l
alNluUu REQUIREMENTS l 4. V ' t-l 80000' I 30 i
i YlELD STRENGTH OETERMINE AT: O.2% offset FRACTURE CODE:
ELONGATION GAGE LENGTH:Linches F) Flave present.
(gl Broke through gage marti c
$2E ED OF TESTING: 0.05 in/ min APPROVED h,(G)
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ME AT TRE ATED AS FOLLOWS:
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MAGNAFLU QUALI ERVICEO sos CHEMICAL
- MECH ANICAL
- METALLURGICAL
- F AILURE ANALYSIR
- NONOS.
JCTIVF 75 INM
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l CERTIFICATION OF TESTS
~
Date 5-10-83 33759-83
- .i e...
No.
Cv.tomers Oed.r No. F7177-12152 Item A Mfr: Stoody Site 3/32 Grade E309-16 Heet N..
3193 Pevad.
300#
{
ASME SFA5.4 Sect II Part C ASME Sect III Class 1 5
LL specipicATioM 1971 Ed.
NB2130 NB2400 TEST RESULT 5 j
Carbon Mongonese Silicon WE HEREBY CERTIFY THAT THIS MATERIAL WAS PROCESSED UNDER THE AUSPICES S ulp hu, OF OUR QUALITY CONTROL PROGRAM AND IS IN ACCCRDANCE WITH SECT III OF Phosphorus THE ASME NUCLEAR CODE IDENTIFICATION AND VERIFICATION SYSTEM AND IS
~
Chromium IN CONFCRMANCE WITH ALL REQUIREMENTS.
Nickel Molybdenum Titanium Columbium Cobolt Tung sten Aluminum f
pper APPonuem 0
Iron I
Tantoium N*==
- - - }
Tin oA
~l Venedium a c ar nw -
I Hydrogen o -
- I Nitrogen s
l Onygen C C "TP.' c s l
Ferrite l
X Ray l
Charpys:
A. w.ided H..,T.....d A. Weld.d Hee. Tee...d I
Tensiles:
v i.id T.... i.
ti...
v2.id T.a. s t.
Ei..
R.d.
4 A,..
As Welded:
Heat Treat:
Hardne s s:
OMI V
..- s
-mn!'W}liliN Vil"'
l Bend s-We hereby certify that the above materh h n
dAos not be n te ted in accordance with the listed specification and i
is in conformance with all requirernents:
ASME Quality Systems Certificate s.... c.i.r...
l c..,.,t.,...i.,
(materials) Number QSC285 55.
Fries on May 20,1983 l
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STOODY COMPANY
, 34 f.(~
INDUSTRY, CALIFORN!A
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CERTIFIED MATERIAL TEST REPORT h:
Johnston StAi.nless Welding Date Aby 5.,._1933 10140 Ro_mandel Ave-Certification No 481-83 Santa Fe Springs. C4_2.0670 Cust:mer P. O. No.
15581 Item No.
1 Stoody Product Name 3/32" Stoody 309-16 Stainless Electrode Specification ASME Section II Part C, Classification E309 SFAS.4 and Section III NB2130 NB2400 Lot Nr.
3193 Stoody Order No.
68593 Weight 300 lbs.
-CHEMICAL ANALYSIS - PERCENT BY WEIGHT Actual Chemical Analysis of Undiluted AllWeldmetal Deposit C
j Mn Si j
Cr
/
Ni Mo Ch+Ta P /
,/
Y' V
/
tl
\\/
V V
0.08 1.24 0.57 23.82 17.62
<0 n1 n_nd n_n11 n_nno Co V
TI Cu 0.03 0.03 0.03 0.04 R"d ' per Schaeffler Diacram 8%: Der Macne Gace 8FN Remarks:
We certify that the above material is ir _conformance with the anolicable recuirennts of Section II Part C and Section III. Nuclear Power Plant Components of the ASME Boiler and_.,_
Pressure Vessel Code,1971 Edition through Winter 19733ddenda.
.~.
Quality System Certificate (Materials) No. OSC-304 expires November 18. 1983.
_ eMl Y n n h fl,
pg (NI-U D""
7121h PULLMAN POWER PRODUCTS PO#:
h00Y COMPANY.
JOHNSTON STAINLESS SHIPPER #: ~ 33759-83 DATE SHIPPED:
5-10-83
^
APPROVED f'
6 gy Paul Bente "5
Quality Assurance Specialist P C&E. Deens Conven Preact i
fC/C 5**
TOC OY CO M PANY
)fb C O NTIN U CQ PAGC QATC Certification No.: 481-83 2
5/5/83
(
Material: 3/32" 309-16 tot:
3193 As Welded Mechanical Properties (AC)
Ultimate Tensile Strength, ksi 89.1 Elongation in (1) inch, (%)
42
)
As Welded Mechanical Properties (DC)
/
/
Ultimate Tensile Strength, ksi 86.5 Elongation in (1) inch, (%)
41 g
As Paul Bente Quality Assurance Specialist EORM N APPROVED PULLMAN PQWER PROOUC15 QA.
P G 48 h Canyon %
[
e. 7.y$ >
M QuctlityServices N
LABORATORY NO.
43456-6-1 of.vtSION OF M AGNAFLUX CORPORATION P 6800 E AST WASHINGTON 80ULEVARD 4-28-83
- LOS ANGELES. CAllFORNIA 90040 oArcarpomfro
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TELEPHONE (2131724 3811
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52509 punCsasc onoca N o.
STOODY COMPANY smppC R NQ.
saupt.c susuiTTso, 309-16 Weld Plates uars niat. setCIFICATION : ASME SFA 5. 4 Test METHoo ASTM E8 CERTIFIED TEST REPORT l
vtELD STatNGYN l
ULTsuATE STRENGTN:
ELONGAflCN REQUCTION AREA t a.Tss. Cat om.
StatsstS STatSSED IACrualLOAD poum0Spta ACTUAL LOAD pouN05 Pim mtDUCED g
g PtmCENT 5 Uwet')
DeutNSON Apta j
POUNOS sQ. IM
- OUNOS so IM.
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R30M TEMPERATURE TENSILE TEST 3/32" Lot 3193 h
.251
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.42 42
.172 53 (oc)
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.41 41
.173 52 Requirenents s h n are per P.O.
g' h*;M D s
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MAXtMUM REQUIREMENTS CO M I d [~ V I \\ A '# I' \\ *
- I MINIMUM R EQUIR EM ENT5 I 80000' I 30 I
i i
YlELD $7AENGTH OETERMINE AT: 0. 2% offset FRACTURE CCOE:
sLONGATION GAGE LENGTH: 1 inchet l
(F) Fleve present.
(g) Broke through gege mark or s>EE3 OF TESTING: 0,05 in/ min APPR0VED (Gi Broke oun.oe gew ounioe m.ooie heit at g.,
=E AT TREATED AS FOLLOWS m.m.
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w1TNI35ED 8Y:
PULLMAN POM4 PROQUCT$
Q.A.
P.C &E. Diece. Canyon Pro, ct L.C. S 8:
C.
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- 3 MAGNAFLU%/OUALI ERVICES
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d THE HOWARD P. FOLEY COMPANY FUMBER:
y NONCONFORMANCE REPORT Page L of 2 k802-824Rev.1
- a DESCRIPTION: QUALIFICATION / CERTIFICATION OF AITAOletENTS DAT
- THE HOWARD P. FOLEY COMPANY / CATARACT ENGINEERING and CONSTRUCTION INSPECTION PERSONNEL Yes No O (1-5-83 HOLD TAG #
RD10VED
' /REF. HPF/IR NUMBER:
N/A BY DATE UNIT I Q UNIT II Q / LOCATION VARIOUS CLASS I g NON-CLASS I Q INSPECTION CRITERIA:
DRAWING SPECIFICATION O PROCEDURE @
DOCUMENT TITLE AND NUMBER:
QCP-6A, Rev. O DESCRIFTION OF NONCONFORMANCE: (Including Cause)
H.P. Foley's procedure for certification of Quality Control personnel (QCP-6A) was approved and has been in effect since Dec. 7, 1982. Contrary to this procedure, numerous Quality Control personnel have been performing and documenting Class I inspec-tions prior to the issuance of the required certification in their associated work areas.
(Contin ed on Page 2)
I f
'INITIATID BY b
t SAR -
Q.C. SUPERVISOR RavLEW DATE DISPOSITION:
- 1) Contact previous employers of applicable inspectors to determine experience and levels of Certification. ---.
- 2) Evaluate previous experience and education to determine appropriate level of certification for each inspector.
(Continued on Page 2) 3 ML s/.kr 2&dL s k & A 2 4 s-so-n i
DISPOSITION BY DATE QUALITT REVIEW DATE P'G.& E. CO.'
DATE I
DISPOSITION ACCOMPLISHE Close to File (date) n-K-Ts 0
Rt,dN
)Q.C. SUPERVISOR nl.~k tw-eg~
A VERIFIED BY 4WffE
'DATE' i
FOR INF0gsq0N CNLY 1
.w.
o I
/
THE HOWARD P. FOLEY COMPANY NO.
NONCONFORMANCE REPORT - CONTINUATION SHEET 8802-824 Rev 1 CONTINUATION OF: DESCRIPTION OF NONCONFORMANCE E3 PAGE 2 OE 2 PROPOSED DISPOSITION O
. DISPOSITION ACCOMPLISHED C DATE 6-6-83 DESCRIPTION OF NO CONFORMANCE:
(Including Cause) (Continued from Page 1)
Between 12-7-82 and 3-10-83, it was also noted that Level I inspection personnel did not require a Level II co-signature (Ref. Memo Dated 3-9-83). This Nonconformance enconcasses both the H.P. Foley direct inspection personnel and the sub-contracted Cataract personnel (Ref. P.G.& E. Audit 83043A for previous review of Cataract personnel). Due to the two distinctions (Foley/ Cataract) the disposition to this Nonconformance should be in two sub-catagories; one for H. P. Foley inspection personnel and the second for Cataract inspection personnel.
NOTE: Original NCR 8802-824 was inadvertantly misplaced.
DISPOSITION INCLUDING MEANS 'IO PREVENT RECURRENCE:
(Continued from Page 1)
- 3) Reinspect 10% of work of inspectors which cannot be certified to determine acceptability and document results.
- 4) Through interviews with inspection supervision determine competence and performance level of inspectors whose certifiability,is questionable.
(See items 2 & 3 above)
- 5. It is not required that a Level I acceptance or rejection be cosigned by a Level II when no evaluation of results is requirad. --
- 6) Future screening of potential inspectors will be performed by H. P. Foley's OA Department prior to employment to determine the appropriate level of certification.
GOSO to File (date) m.y
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PACIFIC GAS AND -E LE C T RIC C O lviPANY r G., T.
24s manct stater. san rm.cisco.catircaniA s4tes. <4ts: 7ti 42 :. inx sicar.ssar P. O. Box 177
... _,., ^
Avila Beach, California 93424
- i. - ~_
~~
(805) 595-2324
~~
~
., June 14, 1983 4e
. H[ P. Foley Company P. O. Box 327 Avila Beach, California 93424 Attention: Paul Bourque Nuclear Project Director Diablo Canyon Project Specification 8802 Welder Qualification and Production Welding Superstrut Gentlemen:
In regards to your questions referencing Specification 8802, Paragraph.6.1, the H. P. Foley. Company shall be required to meet the following requirements:
A.
The H. P. Foley Company shall meet the requirements of AWS D1.1-75.
B.
AWS Dl.1-75 does not specify subgrades of A570 material, (i.e. A570 grade A-E, reference section 8) AWS has stated that A570 grade C is considered a material which is prequalified based on its weld-l ability, therefore, you are to consider A570 grade C as part of the group 1 material.
C.
Dr. Moss Davis (AWS) agrees that flared single level groove welds shall be considered fillet welds which are prequalified under pro-I visions of AWS 01.1-75.
l l
0.
AWS 01.1-75 has no provisions for practical testing of partial pene-tration flared V-groove welds, therefore, we consider them to be a reasonable facsimile of a partial penetration V-groove weld, which is prequalified.
nue to our concern for meeting the minimum effective throat for this joint
.)nfiguration, we request the !!. P. Foley Company to perform the attached weld test.
I l
I DCC
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lswardP.Foley June 14, 1983.
7 ','
st that the H. P. Foley Company revise QCP-5A revision 9, when the' We reque test has been completed and accepted.
e Sincerely.
fy, D. A. Rockwell Assistant Project Superintendent
Attachment:
Weld Test PROJECT DIRECTOR'S ROUTitlG:
Orfeinal:
Kr/ A Copies:
P. BOUROUE, Prof. Dir.
- S. MOSES, Sr. Prof. Mor.
/
G. BROWN, il10ht P.M.
/# R. WILSON, Qual. Dir.
A F. LEE, Schsd. M0r.
7 C. NEEDHAM, En0. M0r.
J. ROBISON, Asst. P.M.
O. GOGGiti, Struc. M0r.
Action By: 7hi/C<w//Ms llAh e
Date Due:
e een emme l
j DCC d ;3 0 2 l
_,e-.-.e..
~
PARTIAL pef ETRATI0t{ FLARED V-GROOVE WELD TEST
.H. P. Foley Company is required to perform the following production tests to meet qualification ~ requirements for partial penetration flared V-groove welds.
- 1) dTest material's' hall be "Unistrut" or "Superstrut" made of AhTM 570 grade C naterial.
- 2) Test assemblies shall be a minimum of 6" length.
- 3) Welding shall be done in the flat position (IG).
- 4) Each classification and diameter of electrodes used in production shall be tested.
- 5) Test assemblies shall be sectioned in three locations; cut a mtd length and one inch from the ends.
The one inch ends shall be dis-carded.
- 6) Acceptance of the test assemblies is based on obtaining a 1/8" minimum effective throat on all cut surfaces.
9 e eee eeee a
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To:
All Q.C. Inspectors
^*
From:
L.R. Wilson
Subject:
Existing Work July 11, 1983 The purpose of this memoranden is to clarify The Howard P.
Foley Company's responsibilities relative to the existing facility.
Diablo Canyon has been under construction or modification since 1968. At that time 10CFR50 had not been enacted, the ANSI standards were not conceived and the commercial nuclear industry was in it's infancy. The facility has been
~ constructed to various editions of the codes, all of which have different acceptance criteria chan the codes in use today.
The early construction was conducted and inspected in accordance with an approved PSAR and Quality Assurance program which was designed to provide assurance that the work in place was accomplished in accordance with the design criteria. There is no evidence to indicate that the existing facility does not meet the design criteria that it was constructed to.
l The Howard P. Foley Company 1,s currently performing l
modifications to the facility. Our contractual responsibility is obviously limited to the work which we are l
THE performing and does not extend to previous work which has HOWARD P. FOLEY been performed by others.
COMPANY We do not want to dilute our efforts at fulfilling our Contractual responsibilities to the Owner by reviewing history; however, there may be cases where, in the inspection of The Howard P. Foley Company modifications, an item of concern is noted in the existing work.
The Owner has stated that they want us to report conditions which are clearly deficient and would impair the ability of the Plant to function as designed.
In these cases we should report the concern to the Owner.
l You are expected to utilize your professional judgement and experience when evaluating existing conditions and avoid reporting trivia that does not affect the safe and reliable operation of the plant.
I
, n 5 #C L w% L%
Rick Wilson Quality -Director
~
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To:
All Q.C. Inspectors From:
L.R. Wilson
Subject:
Existing Work July 11, 1983 The purpose of this memorandum is to clarify The Howard P.
Foley Company's responsibilities relative to the existing facility.
Diablo Canyon has been under construction or modification since 1968. At that time 10C7R50 had not been enacted, the ANSI standards were not' conceived and the commercial nuclear industry was in it's infancy. The facility has been constructed to various editions of the codes, all of which have different acceptance criteria than the codes in use today.
The early construction was conducted and inspected in accordance with an approved PSAR and Quality Assurance program which was designed to provide assurance that the work in place was accomplished in accordance with the design criteria. There is no evidence to indicate that the existing facility does not meet the design criteria that it was constructed to.
1 The Howard P. Foley Company is currently performing modifications to the facility'. Our contractual responsibility is obviously limited to the work which we are
+
THE performing and does not extend to previous work which has HOWARD P. FOLEY been performed by othere.
COMPANY We do not want to dilute our efforts at fulfilling our Contractual responsibilities to the Owner by reviewing history; however, there may be cases where, in the inspection of The Howard P. Foley Company modifications, an item of concern is noted in the existing work.
The Owner has stated that they want us to report conditions which are clearly deficient and would impair the ability of the Plant to function as designed.
In these cases we should report the concern to the Owner.
You are expected to utilize your professional judgement and experience when evaluating existing conditions and avoid reporting trivia 1: hat does not affect the safe and reliable operation of the plant.
.f St 0 %
Rick Wilson Quality Director 2
caS
~..* ~
__..___.-._.__._.._~_~_.~_~^~.;"*:.KTL.:
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I
- vrence 7647 5.
OPEN ITEM REPORT sn.
oc Rev.1/83 (q 1 IDENTIFICATION:
NUMBER 8 3 2
8 AUDIT NO. l 8 l 3 l 2 l 9 l 1 l A l
)
Year Sequence O N/A
%)
INSTRUCTIONS FOR COMPLETING ON BACK'OF THIS FORM 2
""'**w"*'**'*aH 8 8 H, P. Fo l ev P ro c. 17 & ANSI N45.2.'9
'Diablo C'anyon Power Plant nem.,
.n..a..... o.a.,im.ni 3
""""r Maintenance of OA Records - Crit. VI & XVII H. P. Foley once.ei.. e,,,.oi.m p
Numerous closed out work recuest osckanes are stored in the H. P. Folev vault.
No R
duplicate storage for these records is available.
Fire resistant cabinets are O
4g provided for storage of a large number of these packages; however, many records L
are stored in pasteboard boxes temporarily until additional fire (continued)
E 5mata aaoivuaa y
Provide fire resistant cabinets for storage of the affected records promotiv.
' a "* a*' 8 5
H. R. Booth
^a*'
M. /. Tm _,-, k< o.. 8[9 ((3 l
TO BE COMPLETED BY RESPONSIBLE DEPARTMENT WITHIN 15 WORKING DAYS OF ITErvi fuATC
/
6a S toep/ Problem Report Number ! MI VA E ~ 8 I'77 7
6b O Problem has been resolved as described in item 7.
6c O Issued to Track Supplier Audit Finding Reports.
6d O For Quality Assurance Department use only:
Asugn.4t.
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R E
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RETURN TO QUALITY ASSURANCE DEPARTMENT y
9
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I DISTRIBUTION (Other Departments to receive information copy when originated - check belowl O V. P Nucieer Power Generation O Chief. Engineering Research O En *neering
~
O Menseer. Nuclear Plant Operations O Menseer.Meterials Station construction NM
-- ~ oProienu.ne.ei O ment u.,. and/- ment Sopt.
e contract.
i adene.or.OntyAe.orene O Auth-ined in eaor u-ASuE itemii a Other
)^ &
~
~
OIR #83-128 ACTIVITY AUDIT NO: 83i91A Page 2 of 2 4 '- Problem, continued resistant cabinets are available. It is understood that 10 additional cabinets are on order.
Personnel QA record files are stored in J. Thompson's office (no duplicate storage) in non-fire resistant cabinets.
Current storage of the above described records does not meet requirements of H. P. Foley QA Procedure 17, paragraph 3.6.
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't (3)(L)
( 0)(_I)(1)-(3) t PRdHECT OR FI. ANT (S):
Diablo Canyon Unit No. 1&2 ORGANIZATION AFFICTED:
Pipe Support Design Engineering INDIVIDUAL RESPONSIBLE FOR RESOLITIION: G.V.Cranscon Proj ect Eng.
SUBJECT (ITEM / ACTIVITY):
es gn.
sta at n Inspection
REFERENCES:
AWS, AISC, M-9, Pull =an Weld Proceedures DISCREPANCY:
See attached sheets (5)
PROPOSED. ACTION:
Make necessary changes in Design Guides and ESD 223 and Pullman Weld Proceedures to bring the:n up to AWS requirements for pre-qualified partial & full penetration welds.
SCHEDIl LED COMPLETI N:
/ j Cs Initiated by:
p Date:
/0 f x
Approved by: _
k _ _ e-Date:
/0 / 7 / 7~I
((-
ii The Diablo. Canyon 1MMjh.*nh.e'oem{tm6nt *to observe welding ACTIONS TAKEN:
J,,"f."i r... o Jr.,g.jq17 yg>2s' S'." ?",tij_M. bp'a.. ~.
. -. - ~.
nc'y 'UF{R
~
.f duplicatgg,p h r t.
y M Q Q d E ^rYj." Cons du'etion~k 'n Page 5 0
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CLOSED M -**
Approved by:
Date:
/0 U Concur *8f Date:
/rt/r/h7 Chiaf, Engineering Quality Control
//
- O ly required if initiated bv E00. '
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MID FESRBI,-IEUMSG DOCIMENDEN, INSDIIATION WM44jjai di ?:;...'W %i Jg.,
WM@10f.# U E V'.
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RC35tassc,w[/4/8 Mttan fmn 7/5/83 paper.
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IL 1 E r u n.a muzz, mu> nanz-v ancove mzos DesIm
- h.,f
' Bechtal San Frant-4=m Office-Per Dan Curtis by phone AWS table i. 5..EM.. c.2.3.1.4 applied to radius of tube steel obtained fran table in a paper
..5
" ' ; ~ J " entitled "A Designers Guide to Walchi Joints" written by: Mark Michaels of =v4== outside corner radii ' table 3.3'.
tbte: 'the wrd = vim radii. This is rot good engineering practice.
The conservative approach dictates that the minir:um radii be used to ensure the safety of the wld joint. It should also be noted that Mark Michaels paper on the design cf welded joints has, to my knowledge never been approved by the Engineering De" Ant and issued as a control dcc-ument to engin - ing for use on Diablo Can p n.
Bechtel Site-Per a handbook supplied by the tube manufactures institute, all tubing ranufactured in the U.S.A. is made or rolled with a radius of 2t to 3t for all sizes. Having assuned 2t to be the miminun, all < ale,ilations were made to AWS. table 2.3.1.4 us 2t = R.
Per site investigations, Jeff Van Klmpenburg, Ken Palmer and myself discovered sme tubing cn site (Diablo Canyon) has a mininra radius of li t.
Therefore, all welds of this type per this design group are not s
conservative.
Westinghouse-Through review of drawings issued, their designs are also in question.
2.
PARIIAL Ato FUIL PENETRATION GROCVE WEEDS DESIGN S Vr1 m Q drawings supplied to field, very few CJ.f any are designed correctT1 Symbols indicate ccxrplete joint welds.
7 This is true for all joints requiring preparation, tb angle for prep-2d' aration has teen indicated and it is ret cbvious that the des -
aware of the m4mimum joint requirements per Z.J.
Fig. 2.10.1.
However, on joints created by natural intersect.wn at 2 cmbers, it is obvious that the joint in many cases is a partial per ANS and not a full penetration w id due to angle created by intersecting members being to sull for a full penetration weld to be made.
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anchtial site-one group has tried to atmply with AWS. requiranents in desiMbg both S and E per 2.1.3 and 2.10.3.1 table 2.10.3 and Fig. 2.10.1 and the included dihedral angle either on preparation or by natural creation of members inn-cting. Itmever, Pullman QC.have continually refused to check weld per call out because ESD does not provide them with a s h are for performing verification. They have required the (E) effective throat call out to be rernoved.
Westinghouse-See atmmnts for Bechr.el, San Francisa:).
3.
SIGNED JOINT FIIIET WEIDS DESIGi Bechtel San Francisco-Per drawings supplied to field and continued use of fillet all around call out instead of a specific call out adjusting the leg size for the dihedral angle adjust:nent. It's obvious that the dihedral angle has not been considered in the joint design or if it was, it was done incorrectly.
Bechtel Site-one group has tried to be consistent in adjusting the inner and outer fillet leg size based on dihedral angle so that the effective throat on all sides is the sam. This allows the joint to be analyzed as though it is an equal leg fillet all around with only a leg adjustrnent to obtain this when welded. This is shown on drawing, so ccnstruction only has to make what is shown and not interpret what is shown using a table which is not usually at hand.
Westinhouse-See Bechtel San Francisco.
- 1. FIARE BEVEL A!D IGRE-V GOOVE WFW DRAWDC IHRESENIATION Bechtel San Francisco-No partial welds havq been shown since S(E) have been cmitted. AWS 2.1.3 and 2.10.3.1 and 2. M.3 state that (S) groove wid depth and (E) effective throat shall be spar 4f4ad on shop or working drawings. 'Ihe hanger drawings sent to the field are both shop and working drawings. Also, M-9 states that only pre-qua1474ad joints should be used on-Diablo Canyon. Many inmanagenent c:ntend that this job is not covered by AWS code. Ih ever, M-9 states that it is governed by AISC 7th, Ed.. In AISC
~
section on welded joints, page 4-131, paragraph 4, AISC states that small deviations are possible per AWS crade and other joint forms and welding pro-cedures may be ertployed provided tray are tested and qualified in accordance with AWS Dl.1-72. Therefore, Diablo is governed by AWS D1.1-72.
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FLARE BENEL
_ FL ARE -V S=Padius of tube E= Effective Throat per table 2.3.1.4 MS Bechtel Site-one group has emplied with call outs above. Ecwever, Pulbran QC per ESD 223 have required the renoval of S (E) frcm all drawings.
This was because the ESD does not provide a procedure for them to use to verify the welds above.- The syrrbols left, after removal of S (E) indicate full pereL.ation welds even though, QC states 'this is not the case.
Westinghouse-See Bechtel San Francisco.
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Now indicated Per AWS this is a full peratration weld.
L Should show S(E) l\\
- (
With consideration given to AWS section 2.3.1.3 in specifing S(E) and Bechtel Site-one group on,si_te,has tried to ccuply with the above call out per AWS 2.3.1.3.
However, they have neet continued resistance frcm QC in that the weld specs used for installation were written for piping per AWS chapter 10, Fig.10.13.1.1A is 371s* differs frcm the prep angles for structural steel specified in Fig. 2.9'.1 and 2.10.1, which usually indicate a minimum angle of 45*.
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.s. see af rma me amIm ammwIcu Beditel San Francisco-Per Drawings are slown as fillet all arcund for all angles. Per AWS fillets are limited to a m4"4-dihedral angle-of 60* and a -r4== ex*=1 dihedral angle of 135'. All' fillet made boycnid these angles are considered partial penetration welds since AWS requires a reduction of effective threat of 1/8" when angle is less than CO* and greater than 45' and k" reducticn when less than 45' but greater than.,30'. 30' is the minimum dihedral angle for structural steel except tube steel which has a minimum angle of 15'.
Per ESD 223 the leg is adjusted for dihedral argle b't no ine has been aMad to account for throat re-duction required by design resulting in adequate effective throats per AISC and AWS.
Bechtel Site-one group has mnsidered dihedral angle. To facilitato design, joint was sized assuming a constant effective throat size. After sizing effective throat requirements then using dihedral angle the 2 non 90*
sides were adjustad so that the installed effective throats would be wM per design. Fillets are not called cut when dihedral" angles are less than 60'.
Partial penetration mlds are sicwn.
11 2) 3) INSIALIATION AND CC INSPECTION All installation has been made per Pullman's weld procedures. Per a copy obtained frcm Pullman QC of these procedures. These procedures as written stata that they are for the installation of pipe and pipe attcchments.
No mention is made of their use in installation of pipe swJ. All prep angles and joint dera41n are written for pipe, no notes or rtodifications are indicated for their use in installing pipe support steel. CC has been supplied with these gv=a'res and ESD 223 to inspect pipe support welds. They have been supplied no infonnation as to the correct insta11atien of pre-q'=1 M4ad joints per AISC or AWS. n2rthernere, per ESD 223, they have been instructed to check scxne weld joints and not others.
A joint formed by flare-be el_or flare-v welds on all sides such as 2 tubes crossing does not require checking and per ESD 223 when the size of a flare-bevel or flare-v is shown, the nicthod of wld measurement per ESD 223 does not supply the effective throat or any dimension which can be used to detennine the effective throat.
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'6,
-. P. r. structaral and 15' for tube steel. Also no throat increase is included to N. I j'.* compensate 'for 'requiried throat rdv+4r=w based en dihedral angle per ANS t
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Per attachrtant J of ESD 223, of what use is the measurement of S ? Per AWS unless S=R.
R= Radius of tube, E can not be determined through use of table 2.3.1.4.
Also upon review of this attachnent and table of maxinn radii of tube steel in paper by Mark Michaels, it can be shown that table T,was and is ha w upon the maxinzn radius and not the mininun resulting in a non-conservative design.
ACTION TAKEN:
and Engineer. The resolution of this issue was monitored by Project QA.
See chron No's 023208, 024230, 031964 and 033851 plus attached QA " Work plan and log" sheets in which no discrepancy was noced.
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.Y INTEROFFICE CORRESPONDENCE
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Y [. j.x J f u~ [ r e
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DATE September 20, 1983 O
D ro WPS Manual Holders
,,J g
FRC M H.W. Karner, QA/QC Manager (X #
')
'I O,
sus;Ec7 GENERAL WELDING STANDARD.
i
-Qvr,sWeptensbembl.,983) a new section entitled " General Welding Standard" was added to the Welding Procedure Specification Manual.
As stated in the scope of the GWS it is to be used to supplement the individual WPS's. This means that the joint details shown in the WPS and the GWS are acceptable for use.
-- _Tbjoi edet'affrittowr4rve tteGi6tardsnahtisfi.ts1lLdr,fogf1(Sye l d i n g,
namely Ruptur.e'.Restr.aifits.and;;worhta BGa&speci#tcattor.;883S)the f
h' H.W. Karner QA/QC Manager HK:jg F O R gg ? O W "u iO M sn
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Pullman Power Products JP GWS
- ccseur se.
- P9t?AMEO EY M. MacCrae l Ape 9cVED BY e H. Karner lAi! M 6-29-83
.l OIABLO CANYON NUCLEAR POWER PLANT 70 SE USEC p4Gg cNt.Y cn.:cs
- 717.,
Nc.
COVE., SHE _
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TITLE:
GENERAL WELDING STANDARDS W
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etv sion perpasco av wagovco av ine r ass seseni,rien Is. '
l 8-2 ' i'n' M. MacCrae H. Karner M
Initial Issue This GWS " General Welding Stanard" supplements a series of individual Welding Procedure Specifications and i
will be distributed as part of these specifications.
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.qt m-.Og un FOR N l
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4WS c
V SECTION NO.
r;RE?ARE0 SY:
M. MacCrae i APPROVE 0 SY:
H. <arner i OATE:
6-29-a3 GENERAL TO BE USED PAGE WELDING STANDAR05 ONLY ON JOBi 7177 NO.
1 of 10 1.0 SCOPE 1.1 This General Welding Standard for joint detail _s.supphsnen.tMEpei4ess of individual Welding Procedure Specific'ations (WPS's). Each WPS'is qualified in accordance with ASME Section IX.
1.2 4,IncitrdedWM'thisc.statutard-3re;th.ditfpidl.'-j.ointc..detatisrand th.qLitw,
aU:cwable. variations for pipe welds,. pipe. hanger member welds 'and ' pipe
@ttacbment1 welds. c 1.3 This standard applies to all WPS's with the exception of AWS welding procedure specifications.
2.'O JOINT CONFIGURAT. IONS 2.1.
Weld end preparations shall conform to one of those on the following pages, as applicable. For pipe to pipe joints. both sides shall confore to the pipe side of the applicable configuration and thickness.
All welds shall be made in accordance with the position and other variables 'given in the applicable WPS.
2.2 Pages 9 and 10 contain miscellaneous joint configurations that shall only be used for pipe hangers and attachment welds, within the remaining variables specified on the applicable WPS.
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l Pullman Power Products Gws SECTION.10.
PREPARED 3Y:
M. MacCrae l APPROVED SY:
H. Karner i OATE: 6-29-33 GENERAL TO BE USED PAGE WELOING STANDARD ONLY ON JOB #
'7177 NO.
2 of 10 K-Insert (KI) t = Wall Thickness Y max = The Greater of t +.15 or 1.15t C = Counter bore X = 3/16" inimum Trp A she-5 MAX.
M IMAX A) t = 1/8" or less
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i NOTES:
- 1) All Weld Sevel Cegree Measuremen s are _2f, exce: as notec.
- 2) The K-Insert is a standard 1/S" X 5/32" wi n a slign: r:cius I
n the edces.
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3 Pullman Power Products awS V
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SECTION NO.
P:.EPARED BY:
M. MacCrae i APPROVED BY:
H. Karner i DATE: 6-29-83 I
i GENERAL TO BE USED PAGE WELDING STANDARD ONLY ON JOBe 7177 NO.
3 of 10 1
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sWs SECTION NO.'
t."EP' RED SY:
M. MacCrae i APPROVE 0 BY:
H. Karner i OATE: 6-29-53 I
)
GENERAL TO BE USED.
PAGE WELDING STANDARD -
ONLY ON J08#
7177 NO.
4 of 10 Open Sutt (08) t = Wall Thickness Y max = The greater of t +.15 or 1.15t C = Counter bore X = 3/16" minimum A) t = 1/8" or less e a Tf? A.E'.c 45 MAX 3 WX.
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- 07ES:
- 1) All Weld Fevel Decree Measurements are - 2':c. er en as n :ed.
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E) If E7018, E8018 cr E9018 are used for the rect, ne backsice j
must be removed to sound metal and rewelded.
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SECTION NO.
I ?;EP AT<ED BY :
M. MacCrae i APPROVED SY:
M. (arner DATE: 6-29-e3 1
1 l
GENERAL TO BE USED PAGE
. WELDING STANDARD ONLY ON JOB #
7177 NO.
5 of 10 OPEN Butt (Continued)
- 3. Branch Connections and stanchiens Ia8 _i I/*2.
370 min.
/
- 2-1/2*
j 60* max TYP.?
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S_,g Pu:.Iman Power Produc'ts as P
I.
SECTION NO.
I ?REPARED BY:
M. MacCrae t APPROVED SY:
H. Karner i OATE: 6-29-83 i
GENERAL TO BE USED PAGE WELDING STANDARD ONLY ON JOBf 7177 NO.
6 of 11 Backing Ring (BR) t = Wall Thickness Y = The Greater of t 1 15 or 1.15t 4
b l
A)
For t 3/4" and less x
- L57 M:N -
46 MAX,
31 MAX 3 0 M A x' 174, + pgu y
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COMP.
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NOT'ES:
- 1) All Weld Bevel Degree Measureme,nts are i 24
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SECTION NO.
- REPARED SY
M. MacCrae 1 APPROVED SY:
M. Karner i DATE: 6-29-53 GENERAL TO BE USED PAGE
. WELDING STANDARD ONLY ON JOSf 7177 NO.
7 of 10 Backing Ring (BR) (Cont?d) 1/16" Max. gap, at any one point between the I.D. surface and the backing ring-(See Note 1)
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NOTES:
1.
A uniform mismatch of 1/32" max. all around tge.,foin (dy k eptable.
~
sq,d 2.
If this dimension cannet-te he 4%faitggd Afrig should be used and cut to fit, or multiple rings m SV'dsed.
If multiple rings are used s(ddi311. apolies - it also must be seal welded and and ground clean prior to final fit-up:
junction point mus; 1/8" Max. gao TIa.ip ground clean pAior to final fit-uo.
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7 Pullman Power Products sws i
I i
SECTION NO.
I r.:rARED SY:
- a. G. Fink i A?? ROVED BY :
R. G. ?1nt i DATE: 6-29-63 i
GENERAL TO BE USED PAGE WELDING STANDARD ONLY ON JOBf 7177 NO.
8 of 10 Socket & Fillet Welds t = Minimum Wall X Min = the smaller of 1.4 :
or thickness of hub but not less than 1/E Cx = 1.25 t but not less than 1/8" Y Min = The smaller of t or 1/4" C
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SECTION NO.
.I ". re-O BY:
M. MacCrae I APPROVED SY: H.-Karner i DATE: 6-29-83 GENERAL TO SE USED PAGE WELOING STANDARD ONLY ON JOB #
-7177 NO.
9 of 10 Pipc hanger member welds and pipe attachment welds - The para-meters of the joint configurations below may vary as follows:
T = a) Maximum qualified thickness of WPS b) Unlimited for fillets 3 = 0 - 90
=
X = 0 - 3/16 Y=0-T Based on Full or Partial Pen Requirements I
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Straight Beve'l~'
^ s'-kg i f NOTES : /1) The actual beveled area may be prepared as a:
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Double Bevel
-1 J-Bevel C.
FlanopdplQead'\\$*,g,c T
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Otherf 4tAin above limits l
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For welds w'ii;h backing X shall be 0-3/8" i
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SECTION NO.
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M. MacCrae I APPA0Vi0 BY:
M. Karner i SATE: 6-29-53 f,,3
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GENERAL TO BE USED.
PAG E -
WELD STANDARD ONLY ON JOB!
7177 NO.
10 of 10 Flare Sevel@, partial penetration weld (tube steel, flange ends, a E.
etc.)
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037390 INTEROFFICE MEMORANDUM Diablo CanyonProject PACIFIC GAS AND ELECTRIC COMPANY BECHTEL POWER CORPORATION To R.D. Etzler Da November 17, 1983 nom G.V. Cranston Fde No. 929, CA-2 of SFPD/ Project Engineering suo,.ci Welding on Two Parallel Sides of Structural Tube At 221/15/B1 smne 8-1658 ATTENTION:
D.A. Rockwell The veld' symbol shown in Sketch No. 1 of the attachment has often been used with the welding of structural tubing. This weld should be interpreted to include the corners of the structural tubing as shown in the Sketch No. 2 of the attachment.
For pipe supports already constructed with such welds and for which as-built drawings have not yet been issued, please mark on the as-built drawings the actual weld lengths L1 and L2 as shown on Sketch No. 3 of the attachment.
As built drawings issued after November 28, 1983, without reference to weld length, will be interpreted as if the welds include the corners of the structura1 tubing. Please note that this is not a retroactive requirement.
Pipe support as-builts issued before November 28, 1983, which may be affected by this symbol interpretation, will be evaluated by Engineering on a case-by-case basis and, if needed, additional as-built information will be requested.
Please acknowledge receipt of this welding clarification by November 28, 1983.
- f 8
q G... Cranston Project Engineer ~ go 4
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Response Required: Yes Response Due Date: November 28, 1983 g
h HSAmin/SCSaha:bjm M k
Attachments: Welding Details ( one sheet )
e s
cc: PGAntiochos (w/a)
LMangoba (w/a)
TQuan (w/a)
)
EHJadeirab (w/a)
UManegold (w/a)
J',Shryock (w/a)
MElepp.ke (w/a).
JRManning (w/a)
GThomas (w/a)
JALongworth (w/a)
VPMercado (w/a)
PWerts (
)
g g C, 9
[42MemoMl],
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-mM Mh 037390 ATTACIDENT
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WELD TO INCLUDE THE' CORNER I
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ELEVATION SKETCHf1 l
SECTION A-A SKETCH #2 FOR EXISTING WELDS, THE AS-BUILT SHALL e
SPECIFY THE ACTUAL WELD LENGTH h& L 2
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X
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6 3.. Y A
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DCC 9039 c.
INTEROFFICE MEMORANDUM DiabloCanyonProject PACIFIC GAS AND ELECTRIC COMPANY BECHTEL POWER CORPORATION To M. Imppke Da'"
D W wr 5, 1983 Fro'" D.J. Curtis Fde No.925 of Onsite Project Erxpneering Group s.nntWeld Inspecid.on 4.
Jobsite Extension 3064 This merro is to h=nt our conversation this norning. Per condersations with H. Karrer, Pullman Power Products QA/QC Manager, and K. Palmer (PIGC)
ESD 223 S e 4 ms 1.1.1, 4.1, 6.1.4.1 and 6.8.2.3, and the weld processing sheets, Pullran QC Reverifications are rade of weld sizes by Pullman Power Products duriry the as-bi41dify process.
Thank you,
.s. -
DJCurtis/jb Reply Requested: tb Attachrents: Noru cc:
H. Karre.r (PPP)
K. Palmer (GC)
L. Mangoba (OPEG) l S. Chitnis (Sno) i l
l sPE -o4.u,:.
INTEROFFICE MEMORANDUM Diablo CanyonProject PACIFIC GAS AND ELECTRIC COMPANY BECHTEL POWER CORPORATION T*
M. Ieppke Da'e D - b e 5, 1983 Fro'a D.J. Curtis Fele No. 923 of Onsite Project Engineering Group sun, e: "A Designers Guide to Welded Joints" by M. Michaels 4,
Jobsite Emns on 3064 This meno is to h_=nt our conversation this norning. Per that conver-sation I confimai to you that Mark Michaels paper entitled "A Designers Guide to. Welded Jois.s" was not used as a design doctrnent and had a very limited distribution.
Mark Mic'aels originally prepared this paper as a training exercise. It's h
purpose was to increase his welding knowledae. It had been subnitted to Engineering (SMD) for w.e l and possible in-pation into a wut.ca+1ated a
support marn=1 that was being considered in Sevi.czarr of 1982. This draft paper was not aypwval by Engineering due to scue irregularities that had been identified in the paper and dis +,4h+4mn of the paper was not made.
Thank you, P
y D.J. Curtis DJCurtis/jb Beply Requested: tb Attauments: None cc:
S. Chitnis (SMD)
L. Ma=4= (OPEG)
V. Juneja (SMD) e
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C RRECTIVE ACTION REQUEST No. 004
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ISSUED TO:
Howard P. Foley Company ISSUED BY: 3. natheein. cA sunervisor H.P. Foley Q.A. Personnel Title Rick Wilson DateInitialedj Responsible Production Management & Discipline 02-11-84 Date Response Due REQUIR1! MENT:
(State Document, Section and Paragraph and Requirement Violated) cD-M77-6 REV. O. Paracraoh 5.6..." Certification form, HPF/QC (Exhibit.B) shall be used to document the type of certification for each individual."
OcP-6 REV. 4. Paracraoh 4.2.5.2 " Personnel certifications shall'be documented..."
DEFICIENCY:
(State Deficiency, Items Involved, etc.)
c'entrary to the above recuirement, inspection personnel were not issued written
-ertifications prior to performing inspection activities.
I i
RECOMMENDED, CORRECTIVE ACTION:
Peview and evaluate personnel to determine if they were certifiable under the procedure in effect at the time.
- 2. Mk ^
> Ivin 2PW D
</'/n Q.D. Approval for Issuance.
Date Representatives Acknowledgement Date MANACEMENT RESPONSE:
(State cause of'de51ciency and Corrective Action)
~
Peview of personnel records indicated *that during this time frame of the newly imposed nrocedure recuirements for written certifications, the written certifications apparently i nmma hehi nM the actual time of' qualification, (CONTINUED' ON PAGE 2)
Date Corrective Action to be Completed N/A W
~
(Approved)
Not Approved h8W', /bA= v 0&
llI!fl4 l
sentatiive Responding
/ Date Q.D. Review Date
. IMPLEMENTATION OF CORRECTIVE ACTION Satisfactory Unsatisfactory.
COMMENTS:
. I.N u
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HFF/ CAR p
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THf HOWARD P. FOLEY CCMPANY O R,i u n.,
CORRECTIVE ACTION REQUEST NO.
CONTINUATION sxEET 004 DEFICIENCY Q
RECOMMENDED CORRECTIVE ACTION Q
PAGE 9 OF 2 l
MANAGEMENT RESPONSE B
DATE IMPLEMENTATION OF CORRECTIVE ACTION g g_g,g MANAGEMENT RESPONSE:
(CONTINUED FRdM PAGE 1)
. J.
3 -
and in some cases were never. issued, however the u?.timate responsibility for keeping personnel informed of Quality Requirements rested vith.the supervision directly res-ponsible. for the individual.'- Personnel' newly hired were advise'd of all"the Quality Requirements pertinent to their intended area of activity prior, to the'ir beginning
}
work. Also, re-evaluation of personnel records revealed that the personnel were certifiable in accordance with the procedures.in effect at that' time prior ~to per-forming inspection activities.
No Corrective Acb on is requi,re.d. Current procNdures are being strictly' adhered to
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ATTAC11 MENT TO !!PF/ CAR-004 INSPECTOR QUALIFICATIONS Pcga 2 4
- #8 I er ca uons Inspector Education Experience Issued /Date Employment I
J. Nighswanger 4-1-81 High School 5 12-79 Inspector, Civil No Level f
Continental Can 6-2-81
{
to 1-22-82 Elect. No Level 11-6-81 S. Ryan 9-3-78 High School 9 5-80 C.C. Inspector, PT Level I 5-21-81 l
to AAS, Welding H.P.F.
PT Level II 11-3-81 9
I present Tech.
5 Present Mechanical Civil No Level Inspector, 4-20-81 H.P.F.
Mech. No Level 4-21-81 I
R. Simas 4-6-81 High School 6 8-75 Welder, Mech. No Leve to AAS, Welding Caetana Co.
1
+
9-20-82 Tech.
4 9-79 Machinery f
maintenance, i
United Lumber Co.
i M
C. Stephen 8-3-78 High School 2 7-77 Q.C. Inspector, e
to Cheatrol Corp.
7-11-80 10 7-78 Q.C. Inspector.
' Tech-Sil Corp.
A. Twiddy 4-28-81 High School 6 11.--80 Maintenance Asst.
ch.
7-6-81 to Crstwood Hanor 4
il 7-20-81 9-7-83 1 5-79 Laborer, Ross Co.
ech. Weld 7-7-82 6 9-78 Painter, PC&E I
l
-I O. Vogt 7-17-77
~ High School 1 10-76 Q.C. Inspector,S&Q PT Level II 4-17-78 i
3 10-74 Q.C. Inspector, PDM to 8-11-80 10-68-12-73 Q.C. Director, l
f San Bernadino l
j Materials Co.
j 7 10-68 Quality Eng.,
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Aero Jet Co.
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1958-1965 Q.C. Inspector,Aero
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7 ATTAC11MNET TO IIPF/ CAR-004 INSPECTOR QUALIFICATIONS Pagn 1 Inspector Education Experience pg et D e R. Boase 11-27-78 liigh School.
1939-1972 Aircraf t Technician None to
& Testing - Assume 10% of time
,10-8-80 spent for testing & examination.
33-3.3 years related experience R. Churchman 5-12-80 liigh School '
.1975-1979 ' Residential remodeler Hechanical - No to plumbing and electrical.
Level 4-20-81 8-23-82 I
Civil - No vel 4 L. Clover 9-30-76 High School 8 2-78 Field Clerk, HPF Non
~
to B.S. Degree 2 7-79 Q.C. Inspector, HPF g
8-15-77 2-20-78 k
to 9-6-79 i
5 H. Easton 9-24-80 High School 8 10-79 Asst. Field Eng.,
Hec Level to B.S. Degree L.K. Comstock 4-20-81 5-28-81 8 8-78 5 Laborer, El No Level Howard Elect.Co.
4-21-81
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6 12-75 Eng. Clerk, NPS Const Co.
).
I K. Moses 2-4-80 High School N/A Performed no to independent 5-6-80 inspection (Trainee) f f
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Stf Ft.!ER CATE GF FFCDUCTtS) CR SEEVICE(S)
'DATE OF' Nr.PtE AND LOCATION
'OUALIFICATION, CUALIFTED FOR:
EXPl!!ATION-CoretENTS g
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'i ASG Engs neer s ng Co... In:.
7-13-83i Manufacture ef +,rrova and 6-11-il5
- (.t' 46a0 East LsFatma Ave.
non-t err %s ocit:ng. at thsv Anenese. Calaf.
- 3206
. Iocetters oniv.
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.I Allov Feds /Cheatrm Coro, 7 0-53 t*znuf acturer of f errous.an.1 9-R-94 Wilson Ave.
non-f e-rous **elcang and crazing b
Hanover. PA.
17031 matort al at thts location ontv.
.p Anchor Packing Co.
7-13-91 Anchortate passet maternal.
' tJoan '
+
2* BOG S. Avalon Nottftcatton Carson. Caltf.
by P.G.& E.
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Allied Nut S Bolt S-15-93 Studs. Nuts and Solts.
Upon
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Nottfacatton by F.G.& F..
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DATE OF L
t.AME t.ND LOCATION OL%t.3FICATION OUAL IF I CATIO'J ErPIEATION COMMFNT3
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5ethlehem Steet 10-10-e0 Structural Steeg boon Fethlenee. FA.
Notafication
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bv F. f3. % E.
bathlenea Steel 1(-12-83 Caenon 5 teel Flete.
000n Eoarrews. Fosnt. ND.
Low Allov Steet Notaficatson
- Froducts, by P.G.% E.
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Bethlenem Steel 30-12-80 Reinforcino Eteel.
Ooon Steeltown. FA.
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44056 oroducts at thi s location.
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'N s
72550 Old Soeth Miles Rd.
Inspection.
Eolon. OH.
a4339
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ctructural Eteel Uoon Leedv ts Eo! t a n;r heter t al.
Netti3citaon TE7' Ccurres ev p.g.*
i LrF F,' P -
NTs.
'9 3 CP 3:1 1 e,1
-7 :
5t-;ctve-! 3: eel
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?-27-15 q
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e 9r' Eme:en.
Call:n. 71 e s 751:s t
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EXFIAATION COMMEN T'3
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Coast aelWan? Scoolv I C-l a r !'
Acceive. handle sterapw.
Won
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916 West Pettoravaa Fd.
sntoment contreal, maternal Notaftcat8on Santa Maria. C4 93454 scentificetten. and man 3*ve by F.G.& E.
recero teeosng.
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Cra 3cro Fatting Co.
7-10-27 Ferrous and non-4errous P-31-84
(
29500 Ecl on Fd.
seamless tubular crocucts.
Solon. O4 44179 Storage ano receiving Insoection at 71a00 Aurora Fd.
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44109
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Dragon Valves 7-18-83 Stainless Steel G:ome Valves.
5-6-84 17457 Excelstor Ave.
Nor w a l f.. Cal 1f.
(
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Ducommon Netals Co.
5-8-93 Euoolier' of f errous structural 1-10-R6 4890 So. Alameda St.
shaoes. seamless L welded with -
Los Angeles. CA.
90051 out filter metal t.ubul ar
(,
products et t hi s l ocat n on onl y.
Durkee Testin9 Lab 8-12-83 Testano of materials.
Uoon 1500 W.
179th St.
Notification Garoe a.
Cel:4
- 0247 by F'.G.% E.
(
Fore *ost Threaceo 3recucts 10-5-63 Eciting Metectal.
Uoen loi!E E. wrIn t g
tht i + 1 c a t i on Incestr.. CA.
21743 by F.G.% E.
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(* ggsv!CE tH DATF. GF g
g hAME AND LC'_ATION 0%LIFICAT ION OUALIFIED OF.:
EXFIAATION COMMENTO
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Halts Fantenang Systems P-!!-93 Anchor bolts. e.eege ancnom.
Doon
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wath letter of comelganee NotafIcat3on f r oni Tuits. 06la.
by F'.G.% E.
t Imoertal Clevrte Co.
P-9-33 Tubulae r>r odu-+ c.
Uson (Imcernal Eastman)
Nottitcattnn 6515 West Howard St.
by P.G.& E.
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. Chicago. Ill.
60648 Earle M. Jorgenson Co.
7-7-83 Structural Ste,1 Flates and a-15-66 4
,LC*t50 S. Alrmede St.
Snapes.
Los Angelvs. Cataf.
- 0054 rrautbramer - Branson e-9-03 Calibration of ultrasonic Uoon 6924 Canby Ave.
testang ecutDment.
Nottfacation e
'f' r/
Reseda. Cataf.
by P.G.S. E.
(
Lincoln Electric Co.
7-25-83 Manufacturer of ferrous 5-6-04 02901 St. Clatre Ave.
Welding Maternal.
(
C1 evel anc. OH.
44117 and 6500 Hei.Iev Rd.
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Mentor. OH.
44060 s
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E V ' t. ! EE LATE OF FFCDUCTtS) OR cEgv1CEt9
^
DATE OF NAME AND LCCAT10H.
QUALIFICATIOr4 OUALIFIED FnF.:
EXPIRATIOr4 COrMENTS
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neodcct Metals 7-7-97
_ \\auf actured Sneet Snanes tason
!!6 6 Havean St.
,, and F ar* s.
Notificatten Hav a d.
Calsf.
H544 t3v P.6.& E.
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Metallur pacal Testang Coro.
12-21-83 Testing of Matersals.
Uoon 15750 Salt Lake Ave.
N6t'ifacKtson City of Industry. Ca. 91749 by P.G.& E.
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l Midland-Ross' B-22-83 Suoerstrut.
7-1-04 Netal Framing Diviston
?j " /.
ao2 Eisenhower Dr.
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46526 c
National f.n r Palance of Testing. Balancing.
Uoon
'y San Franc 1sco Ad,4usting of HVAC Notificatto9
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- Systems, by P.G.h E.
So. San Fr ancisco. Ca. 94090 12-13-83,
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-rlsbrat ten cf tite =sens e Unen
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testing ecutoment Nattftcation Valle n.
C.3 c.15 C O by F.G.*> E.
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LATE OF r1AME A'4D LOCATIO'd OVALIFICATIOrd OUAL1FIED FM EXPIRATION COMMENTS
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Steel Cor o.
e-12-93 Manufacturer of t err ous struc+ -
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8 10-93 Manuf ac*urer of carbon L l ow.
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Nottfacatton One North Proadway bar & plate at this location by P.G.& E.
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