ML20154C758
| ML20154C758 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/09/1988 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-88-005, IEB-88-5, TAC-68841, NUDOCS 8809150004 | |
| Download: ML20154C758 (3) | |
Text
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David W. Cockfield Vice President, Nuclear September 9, 1988 Trojan Nuclear Plant Dockot 50-344 License NPF-1 U. S. Nuclear Regulatory Cocmission ATTN: Document Control Desk Wauhington DC 20555 Daar Sir Nuc1 car Regulatory Commission (NRC) Bulletin 88-05, Supplements 1 and 2, "Nonconforming Materials Supplied by Piping Supplies Inc., at Folsom, New Jersey and West Jersey Manufacturinn Company at Williamstown, New Jersey HRC Bulletin 88-05 requires that each licensco review purchasing records and determino whether any American Socloty of Mechanical Engincors (ASME) Codo or American Society for Testing of Motorials (ASTM) matorlais havo boon supplied by West Jorsey Manuf acturing Company (WJM) or Piping Supplies Incorporated (PSI) .
Supplement I reduced the scopo of the review from ASME and ASTM "materials" to ASME and ASTM "fittings and flanges". Supplement 1 also provided clari-fication of licensoo actions concerning identification of fittings and flanges and provided information concerning testing for compliance with ASME and ASTM matorial specifications.
Supplement 2 modified the schedule of licenson actions by temporarily suspending the actions requested in Bulletin 88-05 and Supplement I with several exceptions. Supplement 2 also identified Chews Landing Motel Manufacturers Incorporated (CLM) as a company affiliated with WJM and PSI.
In addition, Supplement 2 provided information concerning the disposition of materials identified as supplied by WJM or pS1 and reporting of the test results.
I GGCr?150004 ADOCg OGOih39 0500 34 PDR f I
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MMMM Document Control Desk September 9, 1988 Page 2 Portland Conoral Electric (PGE) has completed a review of purchasing records as requested in NRC Bulletin 88-05 and Supplements. The results of the review, which included purchase orders and vendor documentation (Certifi-cates of Compliance and Material Test Reports), indicato that no materials, specifically fittings and flanges, have been furnished by West Jersey Manufacturing. Piping Supplies, Incorporated, or Chows Landing Motal Manufacturers, Incorporated for installation in a safety-related system at the Trojan Nuclear Plant.
Sincoroly, I
c: Mr. John B. Martin Regional Administrator, Region V U.S. Nucicar Regulatory Commission Mr. Bill Dixon State of Oregon ,
Department of F.nergy I
Mr. R. C. Barr ,
NRC Resident Inspector l Trojan Nuclear Plant Mr. Diff Bradley Nucioar Management and l Resources Council i l Washington DC l l
Subscribed and r. worn to before no this 9th day of September 1988.
l WAok & 12G Notary Public of 0 gon My Corrmission Expiros: (( c.,[ Mk
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OMB No.: 3150-0011
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NRCB 88-05 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION DUKE COCKFIELD WASHINGTON, D.C. 20555 May 6, 1988 hMY ] O B3b NRC BULLETIN NO. 88-05: NONCONFORMING MATERIALS SUPPLIED BY PI SUPPLIES, INC. AT FOLSOM, NEW JERSEY AND WEST JERSEY MANUFACTURING COMPANY AT WILLIAMSTOWN, NEW JERSEY Addressees:
All holders of operating licenses or construction pemits for nuclear power reactors.
_ Purpose :
The purpose of this bulletin is to require that licensees submit infomation regarding materials supplied by Piping Supplies Incor New Jersey and West Jersey Manufacturin i Jersey and to request that licensees 1)gat Company Williamstown, New(WJM)porated
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take actions to assure that materials comply with ASME Code and design specification requirements or ale suitable for their intended service, or 2) replace such materials.
_ Description of Circumstances:
The NRC has obtained copies of certified material test reports (CMTRs) for material supplied by PSI and WJM that contain false infomation about material supplied to the nuclear industry. A number of CMTRs were apparently used to certify that cocrtercial-grade, foreign steel meets the requirerents of ASME Code Section I!!, Subarticle NCA-3800, by using a demestic forging company's letterhead. There was no evidence that PSI or WJM perfonned or had a subcon-produced steel for these falsified CMTRs. tractor perfom the testing requir The information available to date indicates that WJM started supplying ASME Code components to the nuclear industry in 1976, both directly as well as through intennediaries, and that PS! started intemediaries and through supplying ASME Code components to the nuclear industry directly in 1985.
System Certificate (QSC-385) as a material manufacturer from to November 30, 1985 NovemberIn a 30, 1979 The NPC has concluded that there are potential generic safety implications at PSI or WJM (i.e. facilities that either have received direct shipment of materials furnish e and other compone,nts free holders of ASME Certificates of Authori other subcontractors which incorporated materials supplied by PS! or WJM.
copies g to: Cockfield. Yundt. Valt. Olmst ead. Roller. Burton Lehigh. Mazurkiewicz. LIS.
Erickson. Hoag. Rupe. Lent sch. Saut ter R. Johnson. TNP: coy REL T:NEC CH}OND.
Zir erman. Ward. TNP gov REL FtNRC Bulletin 68-o5 PCE Action - L. W. Erickson (Due 9/9/88) Draft reJponst b V
,f')
pt/ -6 PNSED Action - C. A. Zimmerman ( 9/ p /[
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- l NRCB 88-05 May 6, 1988 Page 2 of 4 Actions Requested:
1.
Review purchasing records for your facility and detennine whether any WJM-or PSI-supplied ASME Code or ASTM materials have been furnished to your facility. The lists of purchasing and receivino companies given in Attachments 1 and 2 have been developed through the NRC's partial review of PS! and WJM documents.
all documents; therefore, the ' review of records should not be li the companies on these lists.
should cover the period since January 1,1985.The records review for PSI-sup the period since January 1,1976. The WJP review should cover 2.
For ASME Code and ASTM materials furnished by PSI or WJP that are either not yet installed in safety-related systems at your facility or are in-stalled followinin safety-related systems of plants under construction, the b or c) g actions are requested: (perform action a and either action J
a.
Provide a list of WJM- and PSI-supplied materials that are found not to be in conformance with the applicable code requirerents or procure-ment specifications and identify the applications in which these materials are used or will be used. Include the raterial specifi-cation, the nature of the corponent (e.o., pipe flange) size and pressure rating; also indicate the chain of purchase, an,d either
( b.
Take actions that provide assurance that all received materials comply with ASME Code Section !!!, ASTM, and applicable procurement specifica-tion requirements, or that demonstrate that such materials are suitable for the intended service. For example, this program should include specific verification that austenitic stainless steels have been received in a non-sensitized condition, or, c.
Replace all questionable fittinos and flanges with materials that have been manufactured in full compliance with ASPE Code Section !!!, ASTM, ard the applicable procurement specification recuirements.
3.
For ASME Code and ASTM materials furnished by WJM or PSI already installeo in safety-related systems in operating plants, the following actions are requested:
a.
Provide a list of the WJP and PSI-supplied materials that are found not to be in conformance with the applicable code reouirements or pro-curement specifications and identify the applications in which the raterials are used. Include the material specification the nature of the component indicate (e.g.,
the chain of pipe flange), site, and pressure, rating; also purchase, b.
Take actions requested in 2b or 2c above. However, an evaluttion should be undertaken prior to replacing questienable material in accordance with 2c above that considers the occupational radiation
NRCB 88-05 May 6, 1988 Page 3 of 4 exposure that would be received during the replacement process. This of material should evaluation be considered in developing the method and timing replacements.
c.
Document and maintain for inspection a basis for continued plant operation if the procram requested in item 3b has not been completed within 120 days of the date of receipt of this bulletin.
4 For any PSI- or WJM-supplied materials having suspect CMTRs and used in systems function to that be are not safety-related, take actions connensurate with the performed.
5.
Maintain for inspection the documentation of the specific actions taken for the identified materials.
6.
For operating plants, all scheduled actions should be completed before a restart of fromofthe receipt next this major outage starting after 180 days from the date bulletin. For plants under construction all scheduled actions and the reporting to the planned fuel load date. recuired by 2 below should be completed prior If any addressee cannot meet this schedule, they should justify to the NRC their proposed alternative schedule.
Reporting Requireeents:
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1.
Provide a written report within !?0 days of the date of receipt of this bulletin that either:
a.
States that no WJM- or PSI-supplied raaterials have been furnished for your or facility for use in safety-related systems, if such is the case, b.
Provides the inferration requested in items 2a and 3a above that indicates which materials have been found not to be in conformance with the applicable code requireeents or precurement specifications, confirms completion of other actions recuetted in items 2b or c. 3b and 4, and provides a schedule for completing any remaining actions.
2.
Confirmation of completion of all scheduled actions shall be submitted to the NRC within 60 days of completion for operatin to the fuel load date for plants under construction.g plants and prior The written reports, required above, shall be addressed to the U.S. Nuclear Regulatory Comission ATTN: Document Control Desk, Washington, D.C. 20555, Act of 1954, as amended.under oath or affirvation under the provisions of Section 18?
priate Regional Administrator.In addition, a copy shall be submitted to the appro-
,' This requirement for information was approved by the Office of Management and Budget under clearance number 3150-0011.
NRCB 88-05 May 6, 1988 Page 4 of 4 I I
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If you have any questions regarding this matter, please contact one of the l priate NRC Regional Office. technical contacts listed below or the Regional Adm harles E.[Rossi, b Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts: Ray Cilimberg, NRR (301)492-3220 Ed Baker, NRR (301) 492-3221 Attachments:
1.
Table 1 - Known and Intended Recipients of Carbon Steel Materials furnished by PSI or WJM 2.
Table 2 - Known and Intended Recipients of Stainless Steel Materials furnished by PSI or WJM
- 3. List of Recently Issued NRC Bulletins k
Attachment 1 NRCB 88-05 i May 6, 1988 Page 1 of 2
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TABLE 1 - KNOWN AND INTENDED RECIPIENTS OF CARBON STEEL MATERIALS FURNISHED BY PSI AND M1H Purchaser Receivino Company Nuclear Plant (if known)
Padnor Alloys, Inc. Bechtel Power Corp. Pilgrim Capitol Pipe & Steel Bechtel Power Corp. Midland Pullman Power Products Pullman Power Products Palo Verde Pulltran Power Products Daniel Wolf Creek Pullman Power Products Cleveland Electric Perry Pullman Power Products Bechtel Power Corp. South Texas Pullman Power Products Pullman Power San Onofre Pullman Power Products Pullman Power Vogtle Tyler Davison Bechtel Power Corp. Grand Gulf Osborne Brothers Welding .
Supply General Electric HUB Incorporated Pere Duke Power Oconee HUB Incorporated Bechtel Power Corp.
HUB Incorporated Arkansas Bechtel Power Corp. WNP-2 Chicago Tube & Iron Omaha Public Power Fort Calhoun Chi;ago Tube & Iron District Comonwealth Edison 'raidwood Chic. ige Tube & Iron k' Chicann Tube A fron Cherne Construction Co. Marble Hill Chica,o Tube A Iron Northern States Power ---------
Consumer Power Palisades Drav> Corp. Dravo Corp. Seabrook 001161 !alves Inc. Joliet Valves Inc. ---------
McJunk?n Bechtel Power Corp.
t Guyon A 1 Sys San Onofre Babcock & Wilcox ---------
2TT Grinnell ITT Grinnell - -------
r,uyon Alloys, Inc. Bechtel Power Corp. L Guyon Alloys, Inc. Litrerick Northeast Nuclear Energy Millstone Company Guyon Alloys, Inc. Bechtel c/o PP&L Susquehanna Guyon Alloys, Inc. Duke Power fatawba i
Guyon Alloys, Inc. Bechtel Power Corp. Hope Creek Guyon Alloys, Inc. WNP-2 Guyon Alloys, Inc. Carolina Power & Light :
Guyon Alloys, Ire. Brunswick ,
Paldwin Associates Clinton Guyon Alloys, Inc. South Carolina Electric Y.C. Sun er and Gas Guyon Alloys, Inc. Carolina Power & Licht Guyon Alloys, Inc. Shearon Harris Gulf States River Pend Bellows - -- -- -
Arerican Standard Arrerican Standard - -- - - '
Louis P. Canuso Bechtel/Public Service Hope Creek i
Attachment 1 NRCB 88-05
(. May 6, 1988 Page 2 of 2 TABLE 1 - KNOWN AND INTENDED RECIPIENTS OF CARBON MATERIALS FURNISHED BY PSI AND WJM (continued)
_ Purchaser Receivino Company Nuclear Plant (if known)
Capitol Pipe Il Steel Bechtel Gulfalloy Hope Creek Pechtel Power Corp. Palo Verde Public Service Electric and Gas PSE&G Conax Salem Conax ---------
Consolidated Power
- Pechtel Power Consolidated Power
- South Texas Duke Power McGuire Consolidated Power
- Boston Edison Consolidated Power
- Pilgrim Niagara Mohawk Consolidated Power
- Philadelphia Electric Nine Mile Point Louis P. Canuso Limerick Bechtel Corp. Hope Creek Dubose Toledo Edison Davis-Besse Dubose Dubose Florida Power Crystal River TVA Sequoyah Dubose TVA Dubose Watts Bar l' PPh Susquehanna Dubose SMUD Dubose Rancho Seco Dubose Rochester Gas & Electric Ginna Duke Power Oconee Dubose Power Authority State FitzPatrick of N.Y.
Dubose South Carolina Electric ---------
and Gas i
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- Consolidated Pour is also known as Cor:solidated Piping and Sui
- located in Bimingham, Alabama, Furlong, Pa., and Charlotte, N.C.
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4 Attach.nent 2 NRCB 88-05 May 6, 1988
( Page 1 of 1 TABLE 2 - KNOWN AND INTENDED RECIPIENTS OF STAINLESS "' EE MATERIALS FURNISHED RY PSI AND WJM Purchaser Receiving Company Nuclear Plant (if known)
HUB Incorporated Bechtel Power Corp.
Padnor Alloys Limerick Radnor Alloys ---------
Pullman Power Products Pullman Power ---------
Oravo Corp. Dravo Corp.
Louis P. Canuso, Iri. Seabrook Philadephia Electric Peach Bottom L. P. Canuso Inc. Bechtel Power Corp. ---------
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OMB No.t M 50-0011 NRCB C8-0:,, Supplement 1
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'( UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAP REACTOR REGULATION DUKE COCKFIELD WASHINGTON, D.C. 20555 gi 33 g Juneif,1988 "
NPC BULLETIN NO. 88-05, SUPPLEMENT 1:
NONCONFORMING MATERIALS SUPJLIED BY P!PlHG SUPPLIES, INC. AT FOLSOM, NEW
' JERSEY AND WEST JERSEY MANUFACTURING COMPANY AT WILLIAMSTOWN, NEW 1ERSEY Addressees:
All holders of operating licenses or construction pemits for nuclear power reactors.
Purpose:
The purpose of this supplenent is to 1) provide additional infomation con- 1 cerning material supplied by Pipin Jersey Manufacturing Company (WJM)g Supplies, Incorporated (PSI) and Vest '
f , 2) reduce the scope of the requested materials review to only flanges and fittings. 3) delineate actions licensees
- L are requested to take to identify these materials and to determine whether the materials comply with ASME and ASTM design and material specifications, and 4) clarify what actions licansees are requested to take once they identify material that does not comply with the above material specifications.
_ Description of Circumstances:
On June 10, 1988 the NRC staff was informed by Carolina Power & Light (CP&L) that the Shearan Harris Nuclear Plant had tested two flanges from their ware-house that had been supplied by WJM.
belonging to Heat No. 7218, SA-105 material.The two flanges were identified as The CP&L test results did not match those reported on WJM's Certified Material Test Reports (CMTRs) and did not meet the tensile and yield strength requirements for SA-105 material.
Required minirem tensile strength is 70 KS! whereas the measured tensile strengths were 45 KS! and 46 KSt.
l was 77 KSI. The tensile strength reported on the CMTP i
yield strengths were 27 KS! and 31 KSI. Required minimum yield strength is 36 KS! wh CMTR was 50 KSI. The yield strength reported on the Measured thenistry composition was also out of specification, notably (required percent carbon range 0.6 was very low at 0.045 and manganese was measured at 0.32 to 1.05).
Bulletin 88-05 requires that all PSI and WJM supplied material be (Centified and that a detemination be made as to its suitability for the irved or Copies to: Cockfield Yundt, Valt. Olmstead. Roller. Burton. Let m- Mazurkiewicz, LIS.
( Erickson s hoag. Rupe. Lent sch. Saut t er. R. Johnson. L o ?.>. Ward.
TNP GOV REL FINRC CHRONO TNP:COV REL F NRC Bulletin 0J-o5. Suppl. 1 PGE Action - L. V. Erickson (Due 9/9/88) Draf t response by 9/2/88 NSRD Action - S. A. Bauer
NRCB 88-05, Supplemnt 1 June 15, 1900 Page 2 of 3
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actual application. This supplement narrows the scope of review from ASME and ASTM "materials" to ASME and ASTM fittings and flanges. In view of the recent verification that flanges which do not comply with ASME and ASTM speci-ficetions have been supplied to the nuclear industry, the time frames for certain actions are also modified by this supplement.
Actions Requested:
The actions requested in Bulletin 88-05 remain in effect with the followirg additions:
- 1. Review of purchasing records ray be reduced in scope from ASME and ASTM "naterials" to ASME and ASTM "fittings and fijnges" and the review should be initiated and completed promptly.
- 2. The scope of paragraph 2 of Bulletin P8-05 is reduced fron ASME and ASTM "materials" to ASME and ASTM "flanges and fittings." All other provisions of paragraph ? of Bulletin 88-05 remain in effect.
- 3. The scope of paragraph 3 of Bulletin 88-05 is reduced from ASMF and ASTM "materials" to ASME and ASTM "flanges and fittings." For ASME and ASTM flanges and fittings furnished by PSI or WJM already installed in safety-related systems in operating plants, the following actions are requested:
( a. Comence appropriate testing of accessible flanges and fittings promptly to identify confomance of materials to ASME and ASTM material specifications. Test results for flanges and fittings reported to be from the same heat should be compared for consist-ency ans for conformance to the ASME/ ASTM specifications and to values listed on material CMTPs. Any deviation from the specifi-cation requires an appropriate analysis justifying continued operation.
l b.
If any inaccessible flanges or fittings are identified, en analysis must be perfomed justifying continued operation,
- c. All other provisions of paragraph 3 of Bulletin P8-05 remain in effect.
4 For flanges and fittings already identified as having been supplied by PSI or WJM, the actions requested in 3a and 3b above are to be completed within 30 days of receipt of this supplement. For flanges and fittings
! identified after receipt of this supplement, the actions requested in 2a and 3b above are to be completed within 30 days of identifying the flanges or fittings as being supplied by PSI and WJM.
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1/ Based on the discovery by CPAL of nonconfoming flanges and on NRC review of records of WJM's production of numerous flanges purportedly fron Heat No. 7218, licensees should specifically be alert to identify records for ')
( flanges from Heat No. 7218. /
NRCB 88-05 Supplement 1 June 15, 1988 Page 3 of 3
( 5.
Addressees fur +.her by the NRC.are requested to retain nonconforming materials until adv that they are not inadvertently used. Nonconforming materials should be se 6.
Addressees are encouraged to report the results of tests of PS! and WJM supplied nation flanges to the and fittinas *o the INp0 Nuclear Network for dissemi-industry.
Reporting Requirements:
The reporting additions: requirements of Bulletin 88-05 remain in effect with th 1.
The NRC Operations Center should be notified by telephone, 202-951-0550 of the need graphs 3a andfor3b.analysis to justify continued operation as required in para,-
results in a requirement for a report under 10 CFR 50.7?
the Operations quired by 10 CFR 50.72.Center should be in accordance with the reporting times r If the need for analysis to justify continued operation would not result in a requirement for a report under 10 CFR 50 the notification to the Operations Center should be made within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> .
2.
i Includetothe response results Bulletin 88-05. of all tests of PS! or WJM materials in the w The writtenComission.
Regulatory reports required ATTN: above shall be addressed to the U.S Nuclear Document Control Desk, Washington, D.C. 20555, under Act oath.or of 1954, affirmation under the provisions of Section 182a, as amended. Atomic En priate Regional At.d nistrator. In addition, a copy shall be submitted to the appro-This requirenent for information was approved by the Office of Management Budget under blanket clearance number 31EC-0011.
Management, Room 3208. New Executive. 20503. Office Buildi If you have any questions about this mPtter, please contact one of the techn contacts office.
regional listed below or the Regional Administrator of the apprnpriate NRC f/- Y h ,, ~J M harles . Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts: Rey Cilimberg, NRR
( (301) 492-3220 Ed Raker NRR i (301) 492-3221
Attachment:
List of Recently Issued NRC Bulletins
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OMB No: 3100 0011 hRCB 88 05. Supplement 2 k' L*llf0 STATES kbCLEAR kECULATORY COMMIS510h 0FFICE OF NUCLEAR REACTOR REGULATICh gKE COCKFIELD WASHING 10h. 0.C. 20555 AUG 161988 August 3, 1968
. NRC BULLET!ii AD. 88 05. SUPPLEMENT s: N0hC0hFORMING MATERinL5 $UPFLIED BY PlPihG SUPPLIES. Iht. AT FOLSCM, NEW JERSEY AND WEST JEkSEY MAhtFACTURihG COMPAh) AT WILLIAMSTOWN. hEh oERSEY Addressees:
All holders of operating licenses or rsnstructhn permits for nuclear power reactors.
Purpos,e :
The purpost of this supplement is to (1) modify the schedule for actiora addressees were requested tn perforer in bulletin 88 05 and Supplement 1 and (2) provide additional information concerning materials supplied by Piping Suppites. Incorporated (PSI). West Jersey Manufacturing (WJM).
and a recently identified af filiated company. Chews Landing Metal Manu-l facturers Incorporated (CLM).
Description of Circumstances:
On July 22, 1906, the NRC staf f met with representatives of the huclear Manage-ment and Resources Counct) (hUMARC) to discuss the status of licensees' actions in response to Bulletin 88 05 and Supplement 1. During this meetins,. h0 MARC presented information on licensee and NUKARC/ Electric Power Research Institute (EPRI) testing and evaluation methodology of PS!/WJh flanges. This information was suse.arized in a letter to the NRC from NUMARC dated July 25, 1988 and a detailed report and proposal was subsequently sutaitted on July 29, 1988 (Attachment 11.
Based on the reported s,easurement and analytical results to date, the hkC has concluded that for full power licenstcs it is appropriate to suspend. terpc-tarily, the field measurements. testing, records review. and the preparation
. of justificattens for continued operations (JCOs) that were requested by Bul.
letin 88 05 and Supplement I until further notice. Addressees that have not received a full pcwer license are requested to continue the in situ testing
. and the records review. The time frames of interest remain as specified in the original 6u11etin January 1.1976 to present. During the temporary suspension of the reque tLG activities, the NRC will review the measurercrit ano test data and results of aritlysis performed ano ottermine the extent to Copies to: Cockfield. Yundt, Walt. Olmstead. Roller. Burton. Lehigh. Mazurkiewicz.
LIS. Erickson. Hoag. Rupe. Lent sch. Sautter. R. Johnson. S. Bauer. Ward.
f TNP COV REL F NRC CHRONO. TNP GOV REL F NRC Bulletin 88-05. Suppl. 2 PGE Action - L. W. Erickson (Due 9/2/88)
Complete actions per this supplement. Draft response due 9/2/88.
, q.y NSRD Action - S. A. Bauer
.. .. Send to NRC by 9/9/88
. NRCB 88 05, supplement 2 August 3. 1988 Page 2 of 3 which further actions are appropriate to assure the continued safe operation of nuclear power plants. However, addressees should continue to analyze the test results performed to date.
On July' 22. 1988, the NRC s'taff cosipleted its review of PSI /WJM/CLM purchase order and invoice records. Based on this review, the staff has determined thtt 751/WJM/CLM provided product forms in addition to flanges and fittings. The additional product forms are identified in Attachment 2 and a list of nuclear power plants that were identified as possible recipients of PSI /WJM/CLM materials is provided in Attachment 3. The NRC staff also identified Certified Material Test Reports (CMTRs) for A5ME Section !!! materials from CLM. which also should be considered as suspect. CLM was owned by parties involved in PSI and WJM and the persons signing the CMTRs for CLM also signes the CMTRs for PSI and WJh.
. . Attachment 4 provices a listing of additional intermediary suppliers / fabricators
., of PSI /WJM/CLM products. Sulletin 88 05 itientified 1976 as the beginning date for suspect materials provided by PSl/WJM; however, information available to the NRC now indicates that WJM may have provided ASME materials as early as 1962. The NRC is providing the above information to assist the industry in their understanding of the PSI /WJM/CLM issue.
Actions Recuested:
The actions requested in Bulletin 88 05 and Supplement 1 are temporarily sus.
-(. pended with the,following exceptions:
- 1. Addressets that have not received a full power operating license are requested to continue the records review and the in situ testing of installed flanges and fittings.
- 2. Addressess are requested to maintain for inspection the documentation of the specific actions taken for the identified materials.
- 3. Addressets are requested to retain nonconforming materials until advised further by the NRC.
- 4. Addressees are encouraged to report the results of tests of PS! and WJM supplied flanges and fittings to the lhPO Nuclear Network for dissemination to the inoustry.
Reportino Reovirements:
The reporting requirements of Bulletin 88 05 and Jupplement 1 are terporarily suspended with the following exceptions:
- 1. Holcers of full power operating licenses are required to report the results of their records review, testing. and analysis performed As of the date of this supplement in accordance with the 120 cay reporting requirement speci-p fisi in paragraph 1 of bulletin 88-05, i
' 2. Holders of construction permits are required to report the results of the records review, testing, and analysis prior to the planned fuel load date.
L hRCB E8 05. Surrieu nt 2 August 3. 19C6 '
(. Fake 3 of 3 ,
If you
- ave any questions about this matter, please contact one of the technical contacts listed below or the R$gional Aderinistrator of the appropriate NRC regler.a1 ot ticg.
- C Charles L. C Rossi,
.C Dir %
ector Division of Operations) Ever.ts Assessment Of fice of huclear heactor Regulation Technical Centacts: RayC111mberg,hEA (001) 492 3250 LL Laker, hRR (301) 4ff 3221 i
A t ta chn.c r t s .
. L t r to hRC fr.. f.bhARC , etc s'uly 29, 1900
- 2. Frr. duct Fcrr 5 Solo by 1Ji/PS!/ Chews Landir.9 i S. Nuclear Plants Receiving Suspect Materibi c 4 Purchasers Receiving Suspect Material
- 5. List of Recently Issued hkC Su11etir.s t
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/y.' sq
-^J-- "
Attachment No. 1 NRCB 88-05 Supplement 2 NUCLEAR MANAGIMIN1 AND elsOueCis COUNCIL August 3. 1988
.- . . . : .y .. .- . . r ...:. :. ::. .a
. t 's
- t July 29, 1988 Mr. Thomas T. Martin Associate Director for Inspection and Technical Assessment Office of Nuclear Meactor Regulation U. S. Nuclear Regulatory Comission Washington, D. C. 20555
Dear Mr. Martin:
In a meeting held July 22 with NRC. NUMARC requested that utility activities relative to NRC Bulletin 88 05 and Supplement I be suspended.
This suspension request was based on a generic analysis provided to NRC by NUMA1C's letter of July 22. In the subject NRC meeting, NUMARC also presented an analysis of utility and laboratory test data obtained to date. NUMARC's
( letter of July 25 to Dr. Thomas Marley formalized the request for suspension.
In that letter, NUMARC comitted to provide a written report to NRC reflecting the test data and conclusions presented in the July 22 meeting, and providing quantitative statistical evaluations relative to the conclusions presented at this meeting. That report is hereby provided as an attachment.
As noted previously, the NUMARC laboratory testing program will be carried to completion even if utility test efforts are suspended. An update of the attached report will be provided addressing conclusion of the NUMARC laboratory testing program as well as inclusion of field test data not yet reflected.
We would like to reiterate the importance of timely action in your consideration of NU'tARC's request for suspension. Utility resource expenditures of sajor proportions are presently continuing without abatement.
Continuation of testing is not resource effective and, as documented in the attachment, would not be expected to retult in additional insights. Moreover, in conjunction with the generic analysis previously provided, the attachmelit substantiates that no significant public health and safety concern is represented by this issue.
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NUMARC CENERIC TESTINC PR NRAM <
RESPONSE 70 NRC BULLETIN 84-05
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INTERIM REPORT !
July 29,1988 l t
Prepared By techtel National, Inc. !
San Francisco, California 94105 I
Prepared For Ele c t ric Powe r 3412 Hillview Avenue Palo Alto, Califorr.ia 94203 i
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ABST RACT The NRC Bulletin 88-05 addressed the alleged falsification of certified
- Materials Test Reports (QTTRs) by two suppliera, WJM and pg!, of piping fle*nges and fittings. WVMARC, through the technical management of EPRI, developed a multifaceted program to assist utilities in addressing this bulletin. Laboratory testing of suspect material, the compilation of utility test data and analysis of that data are reported. These dets show in general that, except for blind flanges, the suspect material meets tenelle strength requiremente and is satisfactory for ASME Code applications. Tks hardness testing results for the ease saterials exhibit a broad scatter band which would justify application of a testing tolerance band in eenparison to the ASTM A370 conversion free hardness to tensile strength. The field and laboratory testing results both exhibit the same broad scatter hand. A laboratory generated best fit surve is used to relate mescured field hardneea to tensile strength.
The field hardness test data for 1334 items show the same scatter band as found in laboratory tests, and follows the same general bell *)bape hardnes e distribution as laboratory hardnese tests. The similarity in shapes and the lack of bumps at either the low ends or the high ends of tusse laboratory and field histograms indicates that there is not a concern for low strength material or high strength esterial. Applying a best fit ap,mroach from laboratory hardness and tensile data to field hardness data results in an estimate of strength. The be s t fit approach to the field data indicates that the vast majority are acceptable. Based on the laboratory testing and entensive field testing, it is concluded there is no materiale probles, except possibly for soee blind flanges.
Slind flanges and other components were addressed analytically in the NUMARC generic analysis report, and it was shown that in the majority of cases there would not be a stress concern even if strength in the order of 40 Kf t were to be assumed.
This interin report concludes that the material has acceptable strength and except for some blind flangee is satisfactory for ASHI Code applications. Th e j continued use of these flanges and fittinge does not present a safety problem.
Recommendations are made for follow-up activities.
i
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- 1185e l
- _ - . - - ___ . ,_,___._.___-.,m._ .-
_ _ . . _ . _ __ . , _ _ . . . ___.._,___.c__- . . , _ _ _ . . . .
i
/ LIST OF ILLUSTRATIONS i
'A TABLE S l s
Table 1 Summary of High Nardness Limits Table 2 Summary of Stainless Steel Tests O
FICURE S l
Tigure 1 Histogram of Laboratory Tensile Results Figure 2 Equotip as SHN Compared to UTS and ASTM A370 rigure 3 Best Tit Equotip Compared to UTS Tigure 4 Histogram of Laboratory Hardness Figure $ Histogram of Field Hardness
( Figure 6 Best Tit Data Applied to Field Hardness i
/
-lii-i 118 5e t
INTRODUCTION BACKCROUND The NRC issued sull O 88-05 regarding alleged falsification of certified Materials Test Reports (WrRs) by West Jersey Manufacturing Co. (WJM) and piping Systems, Inc. (ps!). Specific actions were required of utilities. S on.e
- of these could ef ficiently be addressed by a generic program. WUMARC initiated such a program. The NRC issued supplement I to 88-05 subsequent to reports of two blird flanges having low tensile strength. he supplement required utilities to perform field tests on identified installed WJM/pS! items. he supplement also focused effort on piping flanges and fittings. he NUMARC program was modified to coordinate and standardine field testing methods and to compile utility generated dets. Concurrently, the generic WUMARC laboratory testing program has been in progress.
NUMARC MV1TIFACETED PROGRAM Recause several actions were required by 88-05 which could be efficiently addressed in a generic manner, NUMARC undersook the activities described herein as well as the testing and test data analysis which are the subject of this report.
A. Review of records to permit scope limitation.
- 3. Review of records to identify interwediate and secondary supply routes.
C. Interface with Authorised Inspection Agencies and the National Board of
( Boiler and pressure Vessel Inspectors.
D. Generic stress analysis of fittings end flanges.
E. Testing, data coepilation and evaluation.
CENIRIC STRES$ ANA1,Y$!$
The generic stress analysis has been completed, reviewed with and provided to the NRC. We analysis indicates that there is little concern for the stress integrity of the fittings or flanges even if the materials were of substantially lower strength when corpared to the strength requirements of 5 A-10 5. This report was formally transmitted to the NRC by NUMARC on July 22, 1988.
The testing program is described in the following sections of this report.
NUMARC TESTINC PROCRAM METHODS This program contains two main elements: first, comprehensive laboratory testing of suspect items contributed by utilities; and second, utility generated data of destructive laboratory tests and in situ tests of installed suspect items.
/
1185e best fit approach are discussed below subsequent to a brief analysis of the
( '
utility field data. The histogram of laboratory hardness data expressed in EQUOT!p values is shown in Figure 4 L'T!LITY TEST!NC The utility-provided laboratory data le consistent with the generic program
. test data. The utilities have provided one set of data on a blind flange,
- Neat 7218, which is consistent with the two teste cited in 88-05 supplement 1.
This data point is not yet in the computer printout. Other than this, no
. substrength saterial has been reported based on tensile teste. These utilities have reported tenelle strength for 108 itese. Eight itees slightly below 70 KS! have been reported. The remaining 101 values exceed 70 KSI. In one case the utility engineer indicated there was a subsite specimen removed from installed flange and was transverse to the primary working direction rather than parallel. These s!(ghtly low values are readily emplained by the test direction, and by published data which confirms that tensile test results from product testing may be se such as 10 percent below the minieue specified strength. None of these utilities reported attength values are a concern.
The utility generated hardneee data is shown in the histogras of Figure 5.
This histegram has the save general bell shape se the histogram of laboratory hardnese data. In simple teres, the bell ekspes in both laboratory and field histograms and the lack of bumpe at the low hardnese ende of the histograms indicatee that there le net a rencern f ar low strength saterial. Thi s me a n s that the voet majority of field iters would exceed 70 K51 if tested and that the remainder would be within the expected tolerance band. The conclusion is that installed items are acceptable and do not present a saterial concern, except fer eene blind flanges.
T!!LD RARDNESS TO TEN $1LE It le appropriate to coepare the best fit curves of laboratory hardness and tensile results and apply the results of that plot to the utility generated hardness data. When this le done, refer to Figure 6, all itees are shown to be acceptable. It rust be realised that a best fit curve of field hardneee should never be used to reject inetalled itere, because sore (toes which fall below the line can be within the acceptable tolerance band. This is shown by the f act that the original data had some acceptable iters below the best fit curve. Th e be s t fit curve eay be applied to warehouse itees prior to (notallation, and should not be the sole justification for removal of installed (tese. This curve increasee the confidence that the installed itees are se initially intended to be. ;
SLIND TLANCES The be s t fit curve applied to field data, or a field har6 ness test tolerance does not eliminate the f act that there are data in the histogress (but not yet in the competer data base) which indicates that blind flanges say be a concere f or strength reasons. However, the strese analyttest dets provnded to the NR; indicates that these substrength blinds are not a stress problem for service conditions.
/
11859
( there are objective reasons to use as is. The benefits of replacing installed high hardness items with acceptable welds and KAZ are minimal. In cont rast ,
the risks in any replacement are greater. The ALAAA considerations also indicate that high hardness items not be replaced unless there is a plant-unique overriding concern.
STAINLESS STEEL There is a relatively small amount of stainless steel installed, and very little in warehouses. To date, all tests performed on stainless steel have been acceptable. Approminately four dosen items have been tested. All tensile results are acceptable, all chemical analyses are acceptable and all sensitisation tests are acceptable. Approximately 10 dosen magnetic checks were also acceptable. Only one of all these test results is slightly lows that is, one yield strength value was 28.5 Ks! vs. 30.0 Kst, and this ettference is insignificant. These tests are summarised in Table 2.
While the absolvie number of test results is not as great as for carbon steel, the results indicate there is no concern.
CONCLUSIONS The strength of SA 105 material and stainless steel items which were suspect is not a concern.
R E CONNI NDATIONS
- 1. The test results to date indicate there is no concern for materials and thus field testing may be suspended as there is suf ficient data for evaluation.
The generic stress analysis also indica;es there is no concern for plausible low strength materials because it has been shown that even if substrength materials were installed, the vast majority of these cases would be acceptable. Thu s , i t is appropriate to suspend document reviews and field testing.
- 2. The laboratory program should be complete,! subject to constraints of available material.
- 3. The existing utility generateJ data should te compiled and analysed in the NL% ARC progras.
- 4. A summary report should be generated.
1
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Data as of ;
7/22/88 I l
FIC 1 HISTOGRAM OF I LAMRATORY TEN 51LE RESULTS
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.( s TABLE 1 St,DNAAY OF HICH HARDNESS LIMITS MAX. HARDNESS LIMITS BHN SA 350 197 SA 105 PRE 1972 N/A SA 105 POST 1972 187 ONLY IF QUENCHED
't SA 234 WP,B-SUPPLEMENTARY 197 SA 181 N/A i
SA 182 F1 192 i
F2 192 F 11 207 F 22 207
- AWS D1.1 WELD & HAZ, NV280
- 265 i
NACE MR-01 75, Rc22 237 RASE METAL, WELDS, HAZ i
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l Attachment 0
( hRCS 88 05. Supplement 2 August 3. 1988 .
i Product Forms Sold By WJh/P51/ Chews Landinal
+
' Flanges * '
Half Couplirigs Full Couplings Platt kings Penetration Plates . 5A516. GR70 Seal Flates . 5A516. I.R?g (Farryl' Socket held Nortles (CLM)
Long Orain Sess .. A16"F11 & F22 Radiograph Plugs (CLM)
Square 6ar . 1018 Spacers Sarple Probes Class 1 . 5A312. T304 (Ferry) (CLM)
Culde Lugs . 5A240, 1304 locket Welded Half Couplings Class ! . 5A182. F3C4L (Vogtle)
Special kortles Pipe Caps . 5A234 Lugs . 5A240. T304 (Palo Veroe)
Lugs .. SA516. GR70 (Palo Verdel Socket Weld Couplings Plate .. SA36 (Perry)
( 5pecial loss .. A234. A105. A739 1
Scits . 5A193. GR87 (Confrentes/ Spain)
Ir.strument Penetration End Plate . 5A516. GR70 (Perry) hanger Lugs . 5A516. GR70 (Drave /51te unknown) 5cchet Welo boss .. Class 1 . 5A182. F316 (Seabrook) (CLM)
Transiticr. Flece . 5A105 (Vogtle)
Thermowells .. A182 (Cravo/ Hunter / Site unknown) (CLM) f ar Stock .. A105 (Oravo/ Yellow Creek) (CLM) i l
l l
l 1
I This is a cceplete list of all product forms identified during the NRC staff's review of available recorcs.
I 5pecific ruclear pcner plants or customers are noted in celes where the precuct form appeared to be a unique or special order and not wice spread.
3 Indicatts that material was sold by Chews Landing Metal Manufacturers Inc.
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Attacheent 4 NRCE 80 05. Suppleeent 2
( August 3.19M Purchasers peceivina Su;;ect Material I Barr . Saurcers. Inc.
o M.W.*kellon (became Division of Pullman)
Lale Erie Ircn & Netal Co., Inc.
Liberty Equipment. Co.
o Metal sellows (listed as 6ellows in fulletin)
' Power Piping Co.
Standarcs Fipe & Supply Co., Inc.
liosa Pipe Supply Co., Inc.
lyler Cawson (listto in error as Tyler Cavison in Bulletin) k l
l I.
I These purchestr6 are in accition to thost previously identif ttu and are known to have received riterial fcr nuclear al;plications.
I
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Portland General Electnc Nsclear Divison MEMORANDUM August 19 1988 LWE-341-88 TO: T. D. Walt
~4 FROM: L. W. Erickson
)
SUBJE T PGE Response to NRC IE Bulletin 88-05 throush Succlement 2 As required by USKRC IE Bulletin 88-05 and Supplements, a '
review of procurement records has been completed. As detailed in the attachment to this memorandum, the vendor documentation associated with all orders for pipe fittings (including flanges) that may have been utilized in safety-related applications was reviewed. Purchase Orders (Pos) were reviewed to determine if any of the material may have come from West Jersey Manufacturing Company (WJM); Piping Suppliers Inc. (PSI); or Chews Landing, as identified in the Bulletin and Supplements. No records were found which indicated that the above firm (s) were associated with mate-rials supplied to Trojan for which documentation was required.
The effort consisted oft
- 1. Searches by Purchasing and Materials Management for any direct POs to the three firms and of POs to selected third party suppliers who might have furnished fittings originally supplied by WJM.
PCI. or Chews Landing.
- 2. A search by NPE consultants (Bechtel) for POs for safety-related coulement that contains fittings that may be documented as having been supplied by the three firms. The search also identified POs for RDC material (fittings) which might have indirectly come from WJM. PSI. or Chews Landing.
Copies of Pos identified were furnished to the Trojan Review Team. The POs were reviewed for the equipment that was identified f rom the NPE files as potentially having pipe fittings installed / furnished by the vendor. None were noted for safety-related equipment which required the vendor to have or maintain records to indi-cate the source of supply of any of the fittings used. .
99 Trojan Excellence-Our Way of Doing Business
LWE-341-88 August 19, 1988 Pare 2
- 3. A search by the Trojan Review Team for all Trojan originated Pos, Blanket (Term) Pos, and Local POs since January 1,1976 that procured pipe fit-tings. The Trojan Review Team then examined, in detail, all the vendor documentation (Certifi-cates of Compliance Material Test Reports, etc.)
associated with all the POs identified from all sources to determine if WJM, PSI or Chews Landing had been involved in any wcy in the procurement.
The costa (through July 1988) associated with this effort are summarized as follows:
Man-Hours Cost Bechtel Assistance to NPE 60 3 7,000 Basin Engineering 400 S/T + 85 O/T 12.300 (QA Contract) assistance to Trojan PGE Man-Hours Specifically 352 9 $25/hr. 8,800 Charged to Activity Code B88-05 897 3 28,100 This completes the current efforts in responding to IEB 88-
- 05. If you have any questions, please contact Bruce Turbitt at Trojan Extension 568.
4A k)$ fh CHB /DBF/BRTimih Attachment (42 pages) c J. H. Anderson w/ attach.
D. W. Ccektield wo/ attach.
D. C. Kemery wo/ attach.
G. A. Lieuallen w/ attach.
H. H. Malmros w/ attach.
t R. N. Sherman w/ attach.
C. P. Yundt wo/ attach.
File: GOV REL 12-1 (Bulletin 88-05) w/ attach.
Portland General E'ectnc Nuctar Omsen MEMORANDUM August 12, 1988 To: D. B. Forrell FROM Procurement Documentation Review Team O M c [
SUBJECT:
Results of Purchase Documentation Review Performed !
in Accordance with the Requirements of the Nuclear Regulatory Connission Bulletin 88-05
REFERENCES:
N.R.C. Bulletin No. 88-05 "Nonconforming Materials Supplied by Piping Supplies Inc. at Folsom, New Jersey and West Jersey Manufacturing Company at Williamstown, New Jersey" Memorandum LWE-240-88, dated June 15, 1988 Memorandum LWE-265-98, dated June 24, 1988 REVIEW TEAM MEMBERS: (Herein referred to as th6 "Review Team")
Dennis Kemery - Lead Chuck Allen Bill Shearer Mark Newman <
Roger Dole Ed Kennedy Charmane Bredeen TASK OBJECTIVES To determine whether any ASME Code or ASTM material procured by Portland General Electric (PGE) for use at the Trojan Nuclear Power Plant was documented as having been supplied by West Jersey Manufacturing (WJM) at Folsom, New Jerseyt Piping Supplies Inc.
(PSI) at Williamstown, New Jersey; or Chews Landing.
SCOPE The procurement documents that were reviewed were for the purchase of ASME Code and ASTM stainless and carbon steel pipe, flanges, fittings, etc. (herein referred to as "subject material") procured by Portland General Electric since approximately 1970.
Trojan Excellence-Our Way of Doing Business
Procurement Documentation Review Results August 12, 1988 Page_2 TASKS The following describes the tasks performed to identify the procurement documents that required review.
Tasks I through IV below describe the activities performed to assure that all stock material purchase orders (Pos) were reviewed. Tasks V through VII below describe the activities performed to assure that all request for design change (RDC) Pos were reviewed.
The term "Review," as used in the context of this report and an it applies to purchase orders, is defined as: "Physically viewing every Test Report contained within each purchase order package regardless of whether or not it was specifically written for ASME Code and/or ASTM material.
TASK I Prior to the advent of the currently used computerized filing system (1983), all stock material was recorded upon stock record cards (SRC) that are maintained in the warehouse "TUB" files. The SRC'u that identify subject material were reviewed to determine the vendor. This review resulted in a list of 31 vendors.
Having identified the vendors, it was then possible to retrieve a list of all purchase orders written for each vendor from the rolodex file - maintained by material control personnel since the department's beginning. This PO list (a xerox copy of all applicable rolodex file cards) was then reviewed to highlight all purchase orders dealing with the subject material. The microfilm roll and batch number for each PO was then entered on the PO list. The reviewers then solected the proper microfilm roll.
located the listed PO, and performed a review of all attached Quality Assurance Documents. Purchase orders not yet filmed were located either in the PO Open File, the Technical Services Center vault, or in the Non-Q PO files maintained above the Material Control Department office.
TASK II Since 1983, all purchase orders were entered in the computer system rather than on the SRC's. As such, it was necessary to order a master printout of all ASME Code and ASTM materialt e.g.,
t i
Procurement Documentation Review Results August 12, 1988 (
i Page 3 piping, flanges, elbows, couplings, ete'., in order to identify and ;
list any additional vendors supplying subject material that was t not identified per Task I above. The master printout is sorted by (
transaction (store codes) number with material description, Q-code, and vendor name as supplemental information. All subject material listed on the master printout was highlighted and the vendor for each identified. The resulting list of vendors gleaned from the master printout were then compared to the list of 31 ,
vendors identified in Task I. Two newly identified vendors were i j added and the procedure in Task I was followed.
I 4 TASK III '
i Because the master printout mentioned above did not include an !
1 l
identification of 1983 PO activity, it was necessary to review, in l their entirety, all microfilm files of Blanket (Tern) purchase orders in order to assure complete coverage of stock material purchase documents. ,
i
! TASK IV {
l For approximately one year, PCs for vendors whose names begin with l 1 A through F were not entered on the cards in the rolodex file.
They were entered, instead, on the computer. As such, a printout 4 was ordered that listed all PO activity for each affected vendor, "
i This printout was then reviewed to identify any additional l purchese documents yet to be reviewed. All additionally identi- ,
l fled purchase orders (65) were reviewed in accordance with the .
- procedure identified in Task I for PO review. [
2 TASK V I I
l i A review of all Request for Design Change (RDC) related Pos was accomplished by a separate review team at the PGE Portland l Office. The resulting list of 356 subject material Pos was then sent to the review team at Trojan for further review. Of the 356 i PO copies received, 174 had already been identified and reviewed.
The remaining 182 Pos were located and reviewed per the procedures defined in Task I.
I I
I of the 356 PO copies sent from PGE Portland, 83 additional vendors I were identified as possibly having supplied ASME Code and AS7?t l material to Trojan. The procedures described in Task I, second i
j
- paragraph, were then followed. I l
I
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Procurement Documentation Review Results August 12, 1988 Page 4 TASK VI All open purchase orders identified as requiring review were retrieved from the Open PO File located at the Northwest Warehouse (Pebble Springs) and reviewed.
TASK VII The lists of purchasers identified on Tables 1 and 2 of NRC Bulletin 88-05 (Attachments 1 and 2, respectively) were reviewed to determine whether any subject material was procured fron them.
PGE Portland Purchasing department personnel identified 11 vendors listed on Tables 1 and 2 from whom PGE has procured material.
Copies of the RDC Purchase Orders (without support documentation) for these 11 vendors were retrieved form the Portland office and submitted to the Review Team. After making a comparison of these RDC Pos to the Pos already reviewed, it was determined by the Review Team that 59 additional PCs needed review. In addition, copies of the rolodex file cards were made for two vendors who had not been previously identified as having supplied subject natorial to Trojan. This list of Pos from the two vendors plus the list of Pos not yet reviewed from the 11 vendors were reviewed as per the procedures identified in Task I.
RESULTS OF REVIEW There was no evidence found during this review that would indicate that West Jersey Manufacturing Company, Piping Supplies Incorporated, or Chews Landing had performed any testing on the ASME Code or ASTM materia.1 procured by Portland General Electric for use in the Trojan Nuclear Power Plant. There were no instances found where the words "West Jersey Manufacturing,"
"WJM," "Piping Supplies Incorporated," "PSI," or "Chews Landing" appeared on any certified material test report, certificate of compliance (conformance), or other like reports that were reviewed.
Most purchase orders selected for review listed several line items. As such many of the test reports reviewed were for items such as round stock, valves, angle iron, bonnets, discs, plates, tubes and other ASME Code and ASTM materisis not specifically sought out during this review. No test reports for these materials contained the above listed manufacturer's names.
I I
Port!and Generd E'ectre Nucter Omsion Procurement Documentation Review Results August 12, 1988 Pace 5 ,
i QUANTITIESt_
i Number of purchase orders reviewed: 1730 I Approximate number of test reports reviewed (conservative): 5000 .
Number of vendors identifiedt 138 ;
i 14HS/aev !
Attachments (37 pages)
Attachment A List of Vendors identified as having teen involved ;
in the procurement process for the subject material Attachment B List of purchase orders, by vendor, reviewed f ct L. W. Erickson l C. H. Brown M. R. Snook D. D. Wheeler D. C. Kemery i C. C. Allen File: GOV REL 12-1 (Bulletin 88-05) l l
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c Trojan Excellence-Our Way of Doing Business (
JCFC Attachment A to tkrnorandum tu D. B. Ferrell Dated Agust 12, 1988
- 1. ALASMAN COPPCR AND DRASS
- 0. ALLEN NUCLCAR
- 3. AMCR!CAN HCAT RCCLA! MING AGENCY
- 5. AMCR!CAN STANDARD
- 6. AMERICAN STEEL INC.
- 7. AMFAC PIPE AND SUPPLY
- 0. AMFAC P!PC AND STEEL PRCDdCTS
- 9. ANCHOR / DARLING VALVE
- 10. ANTEC CORP.
- 11. ATWOOD & MORRILL
- 10. DADCOCK & WILCOX
- 13. EiASIC CONTR(/LS & VALVE
- 14. DCROEN PATTERSON
- 15. DEST FIRC & STECL
- 16. D.I.T.
- 17. Ii!NGr%h INTL.
- 01. DRCC6S INCTRUMCNT
- 20. CAPITOL P!PC AND STEEL PRODUCTS OC. CHICACO TUTE & IRON 04 DR. CHON3 CHIU
- 25. CIRCLE CEAL CONTROLS
- 26. CCAC' !NOUSTRIAL 27 C0ll COMF ANY
t A 6f &
- 28. COLEMAN INDUSTRI AL SUF T LY
- 29. CONAX CORPORATION
- 30. CONSOLIDfTED POWEP
- 01. CONSOLIDATED SUPPLY
- 32. C.S. CONSTANT CO.
- 33. COPEG-VULCAN INC
- 34. CRANE MFG & SUPPLY
- 35. CROSB / VALVE
- 36. DELAVIAL TURBINE
- 37. DRAGON knLVE
- 38. DOW CHEMICAL
- 39. DUE'OSE STEEL INC.
- 40. ZAGLE METALS
- 41. ESCO NW CORP OR ESCO CORP
- 42. EVERSON STEEL
- 43. EXPANSION .10!NT 44 FAMILIAN NORTHWEST
- 45. ARTHUR FORGYTH CO.
- 46. FLANDERS FILTERS
- 47. ' LOW CONTROL
- 40. FOU3HT & CO. INC.
- 49. CAS ADV. GYCTEMS
- 50. GENERAL ATOMIC COMPANY
- 51. SILMORE STECL COMPAt!Y
- 52. HENRY PRATT CO
- 53. MENRY VCPT Mf0H
- 54. HOLE '. N O .
3 orG
- 55. HYDRAULIC INST. SUPPLY
- 56. HUD INC.
- 57. ILLINOIS WATER TREATMENT CO.
- 58. INDUSTRIAL PUMP SALES
- 60. INDUSTRIAL VALVE
- 61. INGERSOL-RAND CO.
- 62. INTL. SENSOR TECH.
- 63. INVENTORY MANAGEMENT CORP.
- 64. ION TRACK INST.
- 65. ITT DARTON INST. CO.
- 66. ITT ORINNELL
- 67. JOHNSON SCREEN DIVISION
- 60. f(EENAN SUPPLY INC.
- 69. KEROTEST MFG. CORP.
- 70. KILSBY TUTE SUPPLY
- 71. KILSDY-ROBF.RTS cot?PANY
- 70. 1ING BEARIP3
- 73. KURZ INSTRUMENTS
- 74. LIBERTY EQUIPMENT & SUPPLY
- 75. LIMITORQUE CORP.
- 76. M-CO NORTHWEST
- 77. MARLO CO'
- 70. MARMON KEYSTONE CORP.
- 79. MCCULLOCH & SONS
- 00. MIDCO U1. PAUL MONROE HYDRAULICS O2. NPS INDUSTRIES
4 of6
- 03. NAMCO CONTROLS
- 84. NORTHWEST FIPF, & SUPPLY
- 85. NORTHWEST TRADEWINDS D6. PACIFIC SCIENTIFIC
- 07. PACIFIC TANK
- 88. PARMOUNT SUPPLY CO.
- 09. PEERLESS PACIFIC CO.
- 90. THE PERMUTT CO.
- 91. PENNSYLVANIA POWER & LIGHT
- 90. PETERSON INDUSTRIAL
- 93. PHILADELFHtA ELECTRIC 94 PLATT ELECTRIC
- 95. PORTLAND CENERAL ELECTRIC
- 96. PORTLAND VALVE & FITTING
- 97. POWER DIVISION
- 98. HENRY PRATT CO.
- 99. PROTECTIVE PACKAGING 100. PUBLIC SERVICE ELEC. & GAS 101. PUCET SOUND PIBE 100. PULLMAN CONSTRUCTION IND.
103. QUALIFIED COUIPMENT 104. REYNOLDS ALUMINUM 105. ROCKWELL INTL. CORP.
106. ROGERS MACHINE CO.
107. ROOSE. LCLAND N. CO.
100. ROSEMCONT INC.
109. SARAN LINED P!PE
C or&
110. SEAPORT CONTROLS (ITT BARTON) 111. SKINNAR VALVE DIV.
112. STACK STEEL 113. STANDARD SUPPLY CO.
114. STEAM SUPPLY & RUBBER 115. TARGET ROCK CORP.
116. TEK-MATION 117. THOMAS A. SHORT CO.
110. TERRY CORP.
119. TIOGA PIPE & SUPPLY 120. TRANTER INC.
121. TRI-LE'T IND.
122. TUDE TURNS 123. TUFLINE DIVISION 104. UNIT PROCESS CO.
105. U.S. FLEXIBLE TUBING 126. U.S. STEEL SUPPLY CORP.
107. UNITED STATES STEEL 12S. VAuVE SERVICES 129. VICTCREEN CORP.
150. VIKING AUTO SPRINKLER 131. HENRY VOGT MACHINE 102. WAGNER ENGINEERING 100. WALLACE & TICRNAN DIVISION 134. WALWORTH CO.
135. WASHINGTON PUDLIC POWER 106. WCS*INGHJUSE ELECTRIC
O b Of b 107. WOODWARD-GOVERNOR 108. WYLE LADS 139. XMOX CORP.
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