ML20033F382
| ML20033F382 | |
| Person / Time | |
|---|---|
| Issue date: | 12/12/1988 |
| From: | Lewis S NRC OFFICE OF THE GENERAL COUNSEL (OGC) |
| To: | Guillen J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20033D944 | List: |
| References | |
| FOIA-89-482 NUDOCS 9003200235 | |
| Download: ML20033F382 (2) | |
Text
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1C/12/88 Jaime Guillen, NRR Per your request, attached are comments from OGC on the proposed Generic Letter on Nonconforming Materials and Equipment.
Most of these comments were generated by Dick Hoefling of the Enforcement Division and should have already been provided to Ray Wharton or Frank Hawkins.
My additional comments are also included.
Pl ease provide me with the revised package for OGC concurrence before it is presented to the CRGR.
Stephen H.
Lewis cc w/encle R.
Wharton, NRR F.
Hawkins, NRR J.
Goldberg, OGC S.
Treby. OGC R.
Hoef l i ng, OGC 9003200235 900315 PDR FDIA WILLIAM 89-482 PDR v
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RULEMAKING ISSUE my.,_o1, aaouar, 17. 198, The ComissionerJNotation Vote)
..ror:
b(quf From:
Victor Stello, Jr.
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Executive Director for Operations 1
(
i l!'
Subject:
ADVANCE NOTICE OF PROPOSED RULEMAKING, " ACCEPTANCE OF PRODUCTS PURCHASED FOR USE IN NUCLEAR POWER PLANT
+
i STRUCTURES, SYSTEMS AND COMPONENTS"
Purpose:
To obtain approval to publish the enclosed Advance Notice of 4i i
Pro.osed Rulemakine ANPR (Enclosure i for u li ine
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Background:
Recent experience has shown that some products purchased for use in nuclear power plant structures, systems and components are
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substandard, have falsified records, or have been otherwise mis-represented.
The recognition of the potential safety significance of these circumstances has led to the issuance of several NPC l'
bulletinsandinformationnotices(Enclosure 2). These bulletins and information notices were issued to assure that licensees, including Construction Permit holders, were informed and that they were prepared to take actions to prevent inadequate products I'
from being installed in nuclear power plants.
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The Chairman notified Congressman Dingell in the response to the Congressional Subcomittee on Oversight and Investigations report l1 "The Threat From Substandard Fasteners:
Is America Losing It's Grip?" that the Commission was considering publishing an ANPR to CONTACTS: Max J. Clausen, NRR Infrmation in this record was ddeled X20969
.m & %,-(f Information Donald S. Brinkman, NRR Act, excmps I x23216 F0IA-N~ Nh M es+sI s Iae.g.
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This ANPR satisfies that comitment.
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r, Coordination:
The Comittee to Review of Generic Requirements has been briefed on this ANPR and has no objections.
The Office of the General
.i Counsel has no legal objections.
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Vi tor Stell, Jr ecutiva Direct r i
for Operations
Enclosures:
1 4
- 1. ANPR l
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- 2. NRC Information Notices and Bulletins
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3-Commissioners' comments or consent should be provided directly to the Office of the Secretary by c.o.b. Friday, February 3, 1989.
Commission Staff Office comments, if any, should be submitted to the Commissioners NLT Wednesday, January 25, 1989, with an information copy to the Office of the Secretary.
If the paper is of such a nature that it requires additional time for analytical review and comment, the Commissioners and the Secretariat should be apprised of when comments may be expected.
DISTRIBUTION:
Commissioners OGC OI OIA GPA REGIONAL OFFICES EDO ACRS ACNW ASLBP ASLAP SECY l
LIST OF REFERENCED NRC BULLETINS AND INFORMATION NOTICES 1.
NRC Compliance Bulletin No. 87-02 and Supplements 1 and 2:
" Fastener Testing to Determine Conformance With Applicable Material Specifications."
2.
NRC Bulletin No. 88-05 and Supplements 1 and 2:
" Nonconforming Materials i
Supplied by Piping Supplies, Inc. at Folsom, New Jersey and West Jersey Manufacturing Company at Williamstown, New Jersey."
3.
NRC Bulletin No. 88-10:
" Nonconforming Molded-Case Circuit Breakers."
p 4.
" Questionable Certification of Class 1E Components."
5.
NRC Information Notice No. 88-35:
" Inadequate Licensee Performed Vendor Audits."
6.
NRC Information Notice No. 88-46 and Supplement 1:
" Licensee Report of Defective Refurbished Circuit Breakers."
7.
NRC Information Notice No. 88-48:
" Licensee Report of Defective Refurbished Valves."
8.
NRC Information Notice No. 88-97+
"Potentially Substandard Valve Replacement Parts."
I
$$1W$ No.t 6t?0 i
OM4 Wo.: 3150001)
WRC Compifance i
Sviletin 47 02 1
t/WITfD $7 Aft $
NUCLEAR REGULATORY CO*lS$10W 0FFICE OF NUCLTAR REACTOR REGULATION WASHINGTON D.C.
70$$$
Noveeber 6.1987 kRC COMPL1ANCE BULLETIN NO. 87 02:
FA$TENER TESTlha TO DfttRMikt CONFO WITH APPLICABLE MATERIAL $PICIFICA Addressees:
A11 holders of operating licenses or construction permits for nuclea reactors.
purpose:
receipt inspection requirements and internal contro l
cap screws and nuts) in stores at their facilities m i
and cheetcal specification requirements.
_ Description of Circumstanc.el:
Over the past year, some NRC procurement inspections have included 1ection and testing of a small sample of fasteners.This limited program I
was initiated in response to a concern by the Industrial Fastener Institut over the potential use of inferior fasteners in military and industrial appitcations, including nuclear powr of fasteners obtained from San Onofre. plants.The results of NRC testing Palo Verde and Rancho Seco indicates for mechanical and/or chemical properties. Nine o from Palo Verde and San Onofre wre out of specification based o Five nonconforsing bolts came from Palo Verde and wrv all aerked as S Grade 8 but wre actually found to be SAE Stade 8.t.
fasteners from San Onofre wre slightly out of specification for nickel orT thromium.
Tw bolts from Rancho Seco with ASTM A193 87 head markings w determined to have an average ultimte tensile strength of approxima il ksi instead of the specified 175 kai for ASTM A193 37 bolting materia The chemical analysis of these bolts indicated that they wre medium c steel material. Rancho Seco is still investi significance of these substandard fasteners. gating the extent and safety t
87110$0040 l
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Wet Comp 1tance Bulletin 47 02 November 6. lit?
Pape t of 3 In a separate effort. Calvert Cliffs recently tested 1539 fas their discover applications. y that comercial qrade fasteners had been used o owing requireMats for mechanical and/or chemical properties.
ndicated that 399 failed to meet specifi wovid have still fulfilled their safety function.perfernd by cation a on A_ctions to be Taken:
The results of the limited testing described above have demon 1
to obtain additional inforNtion on the adequacy of fastehers used i power plants.
e need n nuclear Within 60 days from the receipt of this bulletin. Itcensees are r provide the following infomtion conceratog their Mceipt inspect equested to testing of fasteners: internal control procedures for fasteners and the n
i n ependent 1.
Describe a) the characteristics currently enartned during rece conform,nce),iew of certified material test re head markings for grade and manufact spbels rev ure r issuance from stock to assure the appropriate use of
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bolts, and/or cap screwsSelect a minimum sample of ten (1
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bolts, and/or cap screws),from curre(nt10)safetyr u s.
and ten be obtained by the licens)ee with the pa in use, elated fasten stock. The sample is to properties are of interest: Fasteners procured to meet the followi A-193 erades 97 88 and 816: SAE J429 A 490; A 3?0 LTM; A.307 grades 5 and I; A.449; A 325 Types 1.2 i A 563i or equivalent.
. 80; 3.
For the selected sample of fasteners in item P. include typical nuts that wov1d be used with each fastener (one a sample of fications of A 194 are of interest.In partievlar, nuts purchas for one t.
4 Chemical testing shall be performed on all samplos.
shall be perforved on each safety related fastener. Mechanical testing shall be performed on each nyt and non. safety related fastener.
fled for this type of testing and appears on the All va vendor list.
Testinp perforved shall be done in accordance with the roved evouirements of the fastener's specification, grade, and class test shall evaluate the ultimate tensile strength properties as required by the fastener's specifica,tionhardness and chemical Each sample shall be tapped with the sample's ID number,. grade. an 1
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Net Como11ance pv11etin 87 0?
f.
November 6,1987 pape 3 of 3 be reported to the WRC utilising the formet show 2 of this bulletin.
j Nnufacturers of safety related fasteners end, to the ette i
of non safety related fasteners.
tion, provide en evaluation of the safetFor any fastener found out of specifica.
atton of the most limiting application. y significance including consider.
j 1
6.
Based on the results of the testing and review of current procedures describe any further actions being taken to assure that fasteners use,d in the plant meet the requisite specifications and requirements and th the operability of safety.related plant components is not affected.
The written reports shall be sutsnitted to the appropriate Regional A under oath or affirmation under provisions of Section 182a. Atomic Energ of 1954, as amended.
Also, the original copy of the cover letters and a copy of the reports shall be transmitted to the U.S. Nuclear Regulatory Co Document control Desk. Washington. 0.C., 20555 for reproduction an l
j lueget under a blanket clearance numberThis reoutst for inforntion 3150001).
duplication may be directed to the Office of Management and Budget. ReC Management. Room 3208. New Executive Office tvilding. Washington, D.C l
, 20503.
t contacts listed below or the Regional Administra office.
t
&h ( km' Charles E. Rossi l
Division of Opera. Director tional Events Assessment Office of Nuclear Reactor Regulation Technical Contacts:
J. T. Conway. WRR (301)4929740 E. T. Baker NRR (301)4924783 J. C. Harper NRR (302)4924]I3 Attachments:
1 Fastener Testing Data Sheet t.
Data Sumary 3.
List of Recently Issued Bulletins
,. _. _ _. _ - _ _. ~. -
t AttacPeent 1 Fastener Testing Date $heet
'$ ample 1De i
Fastener
Description:
i Description of $ ample $tock location:
Matertal Specification as Documented by Licensee Records:
Head Working ($ptcification and Manufacturer):
P
" Class /Procurtrent Level:
General Plant Application (e.g., Pressure Boundary, Structural) 5 Vendor:
0A tequirements !sposed on vender:
Licensee Representative:
i t
Signature _
Date
- The sasple 10f shall have a prefix that contains the licensee facilit I
- 1f applicable, please provide an explanation for y our classification system.
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i Mechentcal Anotysts Chem 9 cal AnalystsI 19#
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I ses; 5-Soffer; 5t-Stiften:
The elements 11sted apply to ASTN A193 #7 or SA193 R7 meterfe1 l
spectffcatten shall he noted with an asterisk. tested, she11 confocus to these reported in the a
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Propertfet fewed cet of i
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Wet Compliance hviletin 87 02
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hovember 6,1987 Ll57 Or RtCCNTLY !$50t0 SULLCTIN5 sulletin Date of ko.
$9bhet issuance issued to i
87 01 Thinning of Pipe Walls in 7/g/87 All licensees for Nuclear Power Plants nuclear power plants holding an OL or CP.
46 04 Defective Teletherapy Timer 10/29/86 All NRC licensees that May hot terminate Dose authorized to use cobalt.60 teletherapy units.
86 03 Potential Failure of Multiple 10/8/86 All facilities (CC5 Pumps Due to Single Failure of Air-0perated Yalve holdtog an OL or CP.
in Minimum Flow Recirculation Line 4
86 0?
Static 'O' Ring Differential 7/18/86 All powr reactor Pressurt $ witches facilities holding an OL or CP.
(,
66 01 Minteum Flow Logic Problees 5/23/86 All $t SW facilities That Could Disable RHR Pumps holding an OL or CP.
85 03 Motor 0perated Yalve Comon 11/15/05 All power reactor Mode Failures During Plant Transients Due to !aproper facilities holding Switch lettings en OL or CP.
45 02 Undervoltage Trip Attachments 11/5/85 All power reactor i
of Westinghouse D8 50 Type l
Reactor Trip treakers facilities holding an OL or CP.
45 01 Steam Sinding of Auxiliary 10/29/85 Muclear power Feodwater Pumps facilities and cps listed in Attachment 1 for actions all other nuclear power facilities for information.
CL = Operating License CP = Constrvction Permit
~,-._,._._--_m
ONI No.: 3150 0011 NRCS 87-02. Supplement 1 UNITED STATts NUCLEAR RESULATORY CO*15$10N 0FFICE OF NilCLEAR REACTOR REGULAtl0N WASHINGTON. 0.C.
20555 i
April 22,1988 NRC BULLETIN NO 87 0?. $UPPLENtKT 2:
FASTENER TESTING TO DETtiqMINE CONFORMANCE WITH APPLICABLE MATERIAL $PECIFICATIONS Addres sees:
All holders of operating licenses or construction pemits for nuclear power reactors.
Purpose:
The purpose of this supplewnt is to recuire addressees to submit additional infemation on the source of fasteners purchased for use in nuclear power plants.
t pescriotion of Circumstances:
licenses or construction pemits for nuclear power regarding the identity of the suppliers and Panufacturers of the safety related ano non-safety related fasteners selected for tasting.
Af ter further consider-of all vendors from which safety related and non safet been obtained within the past 10 years, a reasonable period which will not undue burden on addressees.
ing whether nuclear facility fasteners in use have been suppl with their intended use.
NRC can properly coordinate information with other governm cerned with problems identified in the quality of fasteners.
i Action Required:
Within 90 days from the receipt of this supplementa:
the past 10 years:
1.
A list of the suppliers and manufacturers from which safety-related fasteners have been purchased. including addresses, and the type of fasteners purchased (i.e., the material specifications).
fastener purchases made from fastener suppliers and/or original equipme For those manufacturers, any available infomation concerning the manufacturer or sub tier supplier of the fastener also should be provided.
88041P0142
l NRCB 87 02 Supplement 1 April 22. I988 i
Page R of ?
j 2.
For non-safety-related fasteners the same information as requested in item 1.
The written reports requested above shall be addressed to the U.S. Nuclear Regulatory Comission ATTW: Document Control Desk, Washington, DC 20$56, under oath or affirmtion under the provisions of Section 1824. Atomic Energy Act of 1954, as amended.
In addition, a copy shall be submitted to the appro-priate Pegional Administrator.
This reovirement for inforwation was approved by the Office of Management and Pudget under a blanket clearance number 3150 0011. Coments on burden and duplication my be directed to the Office of Management and Budget. Reports PC503.
Management, Room 3208, New Fxecutive Office Buildin9, Washington, D.C.
1 If you have any questions about this matter. Please contact one of the techni-cal contacts listed below or the Regional Administrator of the appropriate regional office.
Yuk f fM Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts:
J. 1. Conway. NRP.
(301) 492 0970 NRR C. T. Baker,21 (301) 492 37
Attachment:
List of Recently issued NPC Bulletins e
4
-._...__..-.,____-,_s
I Attacteer.t NRC8 87-02 Supplement 1 April 22.1988 Lili 0F RECENTLY 1$$Ut0 NRC PULLET!NS Bulletin Date of No.
$9bfect issuance Issued to 88 03 Inadequate Latch Engagement 3/10/88 All holders of OLs in HFA Type Letching Relays or cps for nuclear Panufactured by General power reactors.
tiectric (Gtl Company 88 02 Rapidly Propagating Fatigue P/5/88 All holders of Ols Cracks in Steam Generator or cps for W designed Tubes nuclear po4r reactors with steam generators having carbon steel support plates.
88-01 Defects in Westinghouse 2/5/88 All holders of OLs Circuit Breakers or cps for nuclear i
power reactors.
87 02 Fastener Testing to 11/6/87 All holders of OLs 4
Determine Confomance or cps for nuclear
(.
with Applicable raterial power reactors.
$pecifications 87 01 Thinning of Pipe Walls in 7/9/87 All licensees for Nuclear Power Plants nuclear power plants hnlding an OL or CP.
86 04 Defective Teletberapy Tiw r 10/29/86 All NRC licensees That May Not Teminate Dose author 17ed to use cobalt-f 0 teletherapy units.
86 03 -
Potential Failure of Multiple 10/S/86 All facilities (CCS Pumps Due to Single holding an OL or Failure of Air-0 wroted Valve CP.
in Minimum Flow tecirculation Line 86-0?
$tatic "0" Ring Differential 7/18/86 All power reactor Fressure $ witches facilities holding an OL or CP.
86-01 Minimum flow logic Problems
$/23/86 All GE BWP facilities That Could Disable PHR Pumps holding an OL or CP.
OL = Operating License CP = Construction Permit
4 l
OMB No.: 3150 0011 f
NRC4 87-02, Fupplement 2 LINITED STATES NUCLEAR REGULATORY COWIS$10N OFFICE OF NUCLEAR REACTOR REGULATION PASHINGTON, D.C.
20555 June 10, 1988 NRC BULLETIN NO. 87-02, SUPPLEMENT 2:
FASTENER TESTING TO DETERMINE CONFORMANCE WITH APPLICABLE MATERIAL SPECIFICATIONS p
Addressees:
All holders of operating licenses or construction permits for nuclear powr reactors.
i 1
l
Purpose:
The purpose of this supplement is to clarify the type of information addressees were required to submit in response to Bulletin 87-02, Supplement 1 on the source of fasteners purchased for use in nuclear power plants.
Discussion:
The " action reovired" statement of Supplement 1 is revised in its entirety to l
clarify that the intent of Supp1& ment I was to require addressees to provide a list of suppliers and manufacturers from which fasteners may have been pur-chased.
Licensees are not required to contact subcontractors to obtain the L
requested information, nor are they required to sWbmit data on fasteners sup-plied as part of an cricinal component.
The type of fasteners for which vendor /
supplier names and addresses are requested is-limited to ferrous fasteners l.
1/4 inch in diameter or greater.
l A_ction Required:
i Within 90 days from the receipt of Supplement 1 to Bulletin 87-02 (issued on-April 22, 1988), addressees shall provide, the following information concerning the procurement of fasteners:
1.
A list of the suppliers and manufacturers from which safety-related ferrous fasteners 1/4 inch in diameter or greater may have been purchased, Within the past 10 years, including addresses.
For those fasteners purchased from fastener suppliers and/or original equipment manufacturers, any available infonnation that identifies the manufacturer or sub-tier supplier of the 8806090301
NRCB 07 02, Supplement 2 June 10, 1988 Page 2 of 2
(
fasteners also should be provided. Approved Vendor List or Qualified $up.
L piler Lists are the intended sources for this information.
Addressets are not required to search purchase order files, contact subcontractors to obtain the information, er submit data on fasteners supplied as part of an original component.
2.
For nonsafety-related fasteners the same information as requested in the first two sentences of item 1, above, except that a) the time of interest is for fasteners procured in the last 5 years, and b) the search of avail-L able records in this case should include purchase orders unless the licer.see utilizes approved vendor lists or qualified supplier lists in procuring nonsafety related fasteners.
This information collection is under-stood to be on a best effort basis.
Further, addressees are not required to contact subcontractors to obtain the information or to submit data on fasteners supplied as part of an original component.
E The written reports requested above shall be addressed to the U.S. Nuclear Regulatory Contrission, ATih: Document Control Desk, Washington, D.C.20555, Act of 1954, as amended.under oath or affirmation uncer the provisions of Section 182a, A priate Regional Administrator.in acottion, a copy shall be submitted to the appro-This requirement for infermation was approved by the Office of Management and
[.
Budget under a blanket clearance number 3150-0011. Coments on burden and
(
duplication may be directed to the Office of Management and Budget. Reports Management, Room 3208, New Executive Office Building, Washington, D.C., 20503.
If you have any questions about this matter, please contact une of the technical contacts listed below or the Regional Administrator of the appropriate regicnal
- office, si di i
c a
Division of Operational Events Assessrent Office of Nuclear Reactor Regulation Technical Contacts:
J. T. Conway, NRR (301)492-0978 E. T. Baker, NRR (301) 492-3221
Attachment:
List of Recently Issued NRC Bulletins
=
,... ' =.
OMB No.: 3150.0011 NRCB 88005 UNITED STATES NUCLEAR REGULATORY COMMIS$10N OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C.
20555 May 6, 1988 NRC BULLETIN NO. 88-05:
NONCONFORMING MATERIALS $UPPLIED BY P! PING SUPPLIES, INC. AT FOLSOM, NEW JERSEY AND WEST JERSEY MANUFACTURING COMPANY AT WILLIAPST0VN, NEW JERSEY Addressees:
All holders of operating licenses or construction permits for nuclear power
[
reactors.
Purpose:
l The purpose of this bulletin is to require that licensees submit infonnation regarding materials suppl-ied by Piping Supplies, Incor Jersey and to request that licensees 1)g Company (WJM)po New Jersey and West Jersey Panufacturin at Williamstown, New I
take actions to assure that materials
[.
comply' with ASME Code and design specification requirements or are suitable g
(
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 infonnation about material supplied to the nuclear industry. A number of CMTRs were apparently used to certify that commercial-grade, foreton steel meets the requirements of ASME Code Section !!!, Subartic1'e NCA-3800, by using a dowstic forging company's letterhead. There was no evidence that PSI or WJM perfonned or had a subcon-tractor perfom the testing required by Sectfon !!! to upgrade the comercially produced steel for these falsified CMTRs. 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 intermediaries, and that PSI started supplying ASME Code components to the nuclear industry directly and through intennediaries in 1985.
In addition WJM held an ASME Quality System Certificate (QSC-385) as a material manufacturer from November 30, 1979 to November 30, 1985.
l The NPC has concluded that there are potential generic safety implications at l-facilities that either have received direct shipment of materials furnished by PSI or WJM (i.e., pipe fittings and flanges) or received piping subassemblies-and other components from holders-of ASME Certificates of Authorization or other subcontractors which incorporated materials-supplied by PSI or WJM.
8804290255 l
i NRC9 88-05 May 6, 1988 Page 2 of 4 Actions Requested:
1.
Review purchasing records for your facility and determine whether any WJM.
or PS!-supplied ASME Code or ASTM materials have been furnished to your facility. The lists of purchasing and receiving companies given in Attachments 1 and 2 have been developed through the NRC's partial review of PSI and_WJM documents.
It is emphasized that the NRC has not reviewed all documents; therefore, the review of records should not be limited to the companies on these lists.
The records review for FSI-supplied material should cover the period since January 1,1985. The WJP review should cover the period since January 1,1976.
2.
For ASME Code and ASTM materials furnished by PS! or WJP that are either not yet installed in safety-related systems at your facility or are in-stalled in safety-related systems of plants under construction, the followin b or c) g actions are requested:
(perform action a and either action Provide a list of WJM-and PSI-supplied materials that are found not a.
to be in conformance with the applicable code requirements or procure-ment specifications and identify the applications in which these materials are used or will be used.
Include the material specifi-cation, the nature of the component (e.g., pipe flange), size and pressure. rating; also indicate the chain of purchase, W dther b.
Take actions that provide assurance that all received, m *, s comply with ASME Code section !!!, ASTM, and applicable proWW:'..peci fica.
tion requirements, or that demonstrate that such macer $n et suitable for the intended service.
For example, this program shodid' include specific verification that austenitic stainless steels have been received in a non-sensitized condition, or, Replace all questionable fittings and flanges with materials that have c.
been manufactured in full compliance with ASME Code Section !!!, ASTP, and the applicable procurement specification reovirements.
3.
For ASME Code anf ASTM materials furnished by WJM or PSI already installed in safety-related systems in operating plants, the following actions are requested:
Provide a list of the WJM-and PSI-supplied materials that are found a.
not to be in conformance with the applicable code requirements or pro-curement specifications and identify the applications in which the materials are used.
Include the material specification, the nature of the component (e.g., pipe flange), size, and pressure rating; also indicate the chain of purchase, b.
Take actions requested in 2b or 2c above. However, an evaluation should be undertaken prior to replacing questionable material in accordance with 2c above that considers the occupational radiation
_y i
b NRC8 88-05 l
May 6, 1988 Page 3 of 4 exposure that would be received during the replacement process.
evaluation should be considered in developing the method and timinoThis of materiet replacements.
i Document and maintain for inspection a basis for continued plant-c.
operation if the procram requested in item 3b has not been completed within 120 days of'the date of receipt of this bulletin.
A.
For any PSI-or WJM-supplied materials having suspect CMTRs and used in systems that are not safety related, take actions commensurate with the function to be 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 from the next ma,ior outage starting after 180 days from the date of receipt of this bulletin.
For plants under construction all scheduled actions and the reporting reovired by 2 below should be completed prior to the planned fuel load date.
If any addressee cannot meet this schedule, they should justify to the NRC their proposed alternative schedule.
Reporting Requirements:
C 1.
Provide a written report within 170 days of the date of receipt of this bulletin that either:
States that no WJM-or PS!-supplied materials have been furnished for a.
your facility for use in safety related systems, if such is the case, or b.
Provides the information requested in items 2a and 3a above that indicates.which materials have been found not to be in conformance
.with the applicable de reovirements or procurement specifications, confinns completion of other actions requested 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.. ATTH: Document Control Desk, Washington, D.C.20555,-
Act of 1954, as amended.under oath or affirmation under the provisions of Section 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 numter 3150-0011.
S
NRCB 88-05 May 6. 1988 Page 4 of 4 If you have any-Questions regardino this matter, please contact one of the technical contacts listed below or the Regional Administrator of the appro-priate NRC Regional Office.
[
Tharles E. Rossi. 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 Pecipients of Carbon Steel Materials furnished by PSI or WJP 2.
Table ?
Known and Intended Recipients of Stainless Steel Materials furnished by PSI or WJM 3.
List of Recently issued NRC Bulletins
?
NRCB 88-05 May 6, 1988 l
Page 1 of 2 TACLE I - t'NOWN AND INTENDED RECIPIENTS OF CARBON STEEt, MATERIALS FURNISHED BY PSI AND K1M Purchaser Receiving Company Nuclear Plant (if known)
Padnor Alloys, Inc.
Bechtel Power Corp.
Pilgrim Capitol Pipe & Steel Rechtel Power Corp.
Midland Pullman Power Products Pullman Power Products Palo Verde Pullman 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 Rechtel Power Corp.
Grand Gulf Osborne Brothers Welding Supply General Electric Perry HUB Incorporated Duke Power Oconee HUB Incorporated Bechtel Power Corp.-
Arkansas HUB Incerporated Bechtel Power Corp.
WNP.?
Chicago Tube & Iren Omaha Public Power Fort Calhoun District Chicago Tube & Iron Comonwealth Edison Braidwood a
Chicago Tube & Iron Cherne Construction Co. Marble Hill Chicago Tube & Iron Northern States Power
~~----
Chicago Tube & Iron Consumer Power Palisades Dravo Corp.
Dravo Corp.
Seabrook Joliet Valves, Inc.
Joliet Valves. Inc.
McJunkin Bechtel Power Corp.
San Onofre Guyon Alloys Babcock & Wilcox In Grinnell ITT Grinnell
-~~----
Guyon Alloys Inc.
Bechtel Power Corp.
Limerick Guyon Alloys, Inc.
Northeast Nuclear Energy Millstone Company Guyon Alloys, Inc.
Bechtel c/o PP&L Susquehanna Guyon Alloys, Inc.
Duke Power Catawba Guyon' Alloys. Inc.
Bechtel Power Corp.
Hope Creek Guyon Alloys, Inc.
WNP-2 I
Guyon Alloys. Inc.
Carolina Power & Light Brunswick Guyon Alloys. Inc.
Baldwin Associates Clinton Guyon Alloys, Inc.
South Carolina Electric V.C. Sumer and Gas Guyon Alloys, Inc.
Carolina Power & Light Shearon Harris Guyon Alloys, Inc.
Gulf States River Rend-Bellows American Standard American Standard Louis P. Canuso Bechtel/Public Service Hope Creek
=
NRCB 88 05 May 6, 1988 Page 2 of 2 -
TABLE 1. KNOWN AND INTENDED RECIP!ENTS OF CARBON STEEL MATERIALS FURNISHED BY PS! AND WJM (continued)
Purchaser Receiving Company Nuclear Plant fif known)
Capitol Pipe & Steel Bechtel Hope Creek Gulfalloy Bechtel Power Corp.
Palo Verde Public~ Service Electric and Gas PSE&G Salem Conax Conax Consolidated Power
- Pechtel Power South Texas Consolidated Power
- Duke Power McGuire Consolidated Power
- Boston Edison Pilgrim Consolida*?d Power
- Niagara Mohawk Nine Mile Point Consolidated Power
- Philadelphia Electric Limerick Louis P. Canuso Bechtel Corp.
Hope Creek Dubese Toledo Edison Davis.Besse Dubose Florida Power Crystal River Dubose TVA Sequoyah Dubose TVA Watts Bar Dubose PP&L Susquehanna Dubose-SMUD Rancho Seco Dubose Rochester Gas & Electric Ginna Dubose Duke Power Oconee Dubose Power Authority State FitzPatrick of N.Y.
Dubose South Carolina Electric and Gas
' Consolidated Power is also known as Consolidated Piping and Supply located in Btrraingham, Alabama, Furlong, Pa., and Charlotte, N.C.
1
NRC8 88 05 May 6. 1988 Page 1 of 1 TAPLE P - KNOWN AND INTENDED RECIPIENTS OF STAINLESS STEEL MATERIALS FURNISHED BY PSI AND WJM Purchaser Receiving Company Nuclear Plant (if known)
HUB Incorporated Bechtel Power Corp.
Limerick Radnor Alloys Radnor Alloys Pullman Power Products Pullman Power Drsvo Corp.
nravo Corp.
Seabrook Louis P. Canuso, Inc.
Philadephia Electric Peach Bottom L. P. Canuso, Inc.
Rechtel Power Corp.
O Is e
NRCB 88-05 May 6, 1988 LIST OF RECENTLY !$$UED NRC BULLETINS Bulletin p g,,7 No.
Sub.iect Issuance Issued to 88-04 Potential Safety-Related 6/5/88 All holders of OLs Pump loss or cps for nuclear power reactors.
85-03.-
Fotor-0perated Yalve Comon 4/?7/88 All holders of OLs Supplement 1 Mode Failures During Plant or cps for BWPs.
Transtents Due to Improper Switch Settings 87-02, Fastener Testing to 4/22/88 All holders.of OLS Supplenent 1 Determine Conformance or cps for nuclear with Applicable Material power reactors.
Specifications 88-03 Inadeounte latch Engagement 3/10/86 All holders of Ols in HFA Type Letching Relays or cps for nuclear Manufactured by General power reactors.
Electric (GE) Company 88-02 Rapidly Propagating Fatigue 2/5/88 All holders of OLs Cracks in Steam Generator Tubes or cps for W-designed nuclear po4r reactors with steam generators having carbon steel a
support plates.
88-01 Defects in Westinghouse-2/5/88 All holders of Ols Circuit Breakers or cps for nuclear power reactors.
87-02 Fastener Testing to 11/6/87 All holders of OLs Detemine Conformance or cps for nuclear with Applicable Material power reactors.
Specifications l
87-01 Thinning of Pipe Walls in 7/9/87 All licensees for Nuclear Power Plants nuclear power plants holding an OL or CP.
OL = Operating License CP = Construction Permit i
L' OP8 No.: 3150-0011 NRCP 88 05, Supplement !
L UNITED STATES NUCLEAR REGULATORY COMMIS$f 0N 0FFICE OF NUCLEAP REACTOR REGULATION o
i WASHINGTON, D.C.
20555 June 15, 1988 NPC BULLETIN NO. 88-05, SUPPLEMENT 1:
NONCONFORMING MATERIALS SUPPLIED BY PIPING $UPPLIES, INC. AT FOLSOM, NEW i
JERSEY AND WEST JERSEY MANUFACTURING COMPANY AT WILLIAMSTOWN, NEW JERSEY Addressees:
l -
All holders of operating licenses or construction pemits for nuclear power reactors.
_Pu rpos e :
l The purpose of this supplement is to 1) provide additional infomation con-cerning material supplied by Pipin Jersey Manufacturing Company (WJM)g Supplies, Incorporated (PSI) and West l'
, 2) reduce the scope of the requested materials review to only flanges and fittings 3) delineate actions licensees are requested to take to identify these materials and to determine whether the materials comply with ASME and ASTM design and material specifications, and'4) clarify what actinos licensees are requested to take once they identify material that does not comply with the above Nterial specifications.
L Description of Circumstances:
On June 10,.1988 the NRC staff was informed by Carolina Power & t.ight (CP&O that the Shearon Harris Nuclear Plant had tested two flanges from their ware-house that had been supplied by WJM.
The two flanges were identified as belonging to Heat No. 7218, SA 105 material. The CP&L test results did not i
match those reported on WJM's Certified Material Test Reports (CMTRs) and did not meet the tensile and yield strength requirements for SA-10$ mterial.
Required minimum tensile strength is 70 KS! whereas the measured tensile l
strengths were 45 KSI and 46 KSI.
The tensile strength reported on the CMTP was 77 KSI.
Required minimum yield strength is 36 KS! whereas the measured i
yield strengths were 27 K$i and 31 KSI.
The yield strength reported on the I
CMTP. was 50 KSt. Measured chemistry composition was also out of specification, notably percent carbon was very low at 0.045 and manganese was measured at 0.32 (required range 0.6 to 1.05).
Bulletin 88-05 requires that all PSI and WJM supplied material be identified and that a detemination be made 49 to its suitability for the intended or i
8806150186 w
NRCB 68-05. Supplement 1 June-15, 1930 Page 2 of 3 1
actual application.
and ASTM " materials" to ASME and ASW fittings and flanges.Th In view of the ficetions have been suppifed to the nuclear industry, the tim L
certain actions are also modified by this supplement.
Actions Requested:
The actions requested in Ru11etin 88-05 remain in effect with the following additions:
1.
Review of purchasing records may be reduced in scope from ASME and ASTM" materials"toASMEandASTM"fittingsandfijnges"andthe review should be initiated and completed promptly, i
2.
The scope of paragraph 2 of Bulletin P8-05 is reduced from 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 related systems in operating plants, the following actio Comence appropriate testing of accessible flanges and fittings a.
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 and for conformance to the ASME/ASTP specifications and to values listed on material CMTRs.
Any deviation from the specifi.
l cation requires an appropriate analysis justifyfog continued operation.
b.
If any-inaccessible flanges or fittings are identified, an analysis must-be perfomed justifying continued operation.
All other provisions of paragraph 3 of Bulletin 88-05 remain in effect.
c.
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 3a
' and 3b above are to be completed within 30 days of identifying the flanges or fittings as being supplied by PSI and WJM.
Jf Based on the discovery by CPAL of nonconfoming flanges and on NRC review of records of WJM's production of numerous flanges purportedly from Heat No. 7218. licensees should specifically be alert to identify records fnr flanges from Heat No. 7210.
s., '
9 e
NRCB 88 05, Supplement 1 June 15, 19P,8 Page 3 of 3 5.
Addressees are requested to retain nonconforming materials until advised further by the NRC. Nonconforming materials should be segregated to ensure that they are not inadvertently used, t
6.
Addressees are encouraged to report the results of tests of PSI and WJM supplied flanges and fittings to the INP0 Nuclear Network for dissemi.
nation to the industry.
Reporting Requirements:
The reporting requirements of Bulletin 8P-05 remain in effect with the following additions:
1.
The NRC Operation: Center should be notified by telephone, 202-951-0550, of I
the need for analysis to justify continued operation as required in para-graphs 3a and 3b.
Where the need for analysis to justify continued operation results in a requirement for a report under 10 CFR 50.72, the notification to the Operations Center should be in accordance with the reporting times re-quired ty 10 CFR 50.72.
If the need for analysis to justify continued operation would not result in a requirement for a report under 10 CFR 50.72, 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 />.
C 2.
Include the results of all tests of PSI or WJM materials in the written response to Bulletin 88-05.
The written reports required above shall be addressed to the U.S. Nuclear Regulatory Comission, ATTN:
Document Control Desk Washington 0.C. 20555, under oath or af'innation under the provisions of Section 1824, Atomic Energy l
Act of 1954, as amended.
In addition, a copy shall be submitted to the appro-priate Regional Administratnr.
This requirement for infonnation was approved by the Office of Management and Budget under blanket clearance number 3150-0011. Coments on burden and dupli-ications should be directed to the Office of Management and Budget. Reports Management, Room 3208, New Executive Office Building, Washington,' D.C. 20503.
L If you have any questions about this matter, please contact one of the technical contacts listed below or the Regional Adninistrator of the appropriate NRC regional office, b
Charles
. Rossi 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
Attachment:
List of Recently Issued NRC Bulletins
t
- c OM8 No: 31C0 0011 hatt 88.C!. Supplemer.t F
~
Ukil(0 STA1(5 kbCLtAR kL6ULATORY C0m15510h DFFICI 0F WUCLEAR ALACTOR REGULA110h WASHlhG10h. 0.C.
20555 August 3. 1968 NRC BUllF11ti h0. 88 05. SUPPLEMtill i:
h0hC0hFORMING MAf[ Lints $UPPLl[0 8Y PlPlhG SUPPilf5. IhC. At FOL50M. htW JLA5[Y AND WE51 JLk5Lt mat 4FACTURiht COMFAh) Al WILLIAMSTOWN. hEh vikS(Y Addre s sees :
All holders of Iperating licensss or construction permits for nuclear power
!=
reactors.
(
Purpose:
l The purpost of this supplement is to (1) modify the schedule for actiora addressees were requested to perfora in 6u11etin 88 05 and Supplement I anc (2) provide additioral information concerning materials supplied by Piping Supplies, incorporated (PSI). West Jersey Mar.ufacturing (WJM).
l and a recently ider.tified af filiated company. Chews Landing Metal Manu.
(
facturers Incorporated (CLM).
L Description of'Circumstantes:
l 0n July 22. 1906, the NRC staff met with representatives of the huclear Manage.
ment and Resources Council (hliMARC) to discuss the status of licensees' actions in response to Bulletin 88 05 and Supplement 1.
During this meeting h0 MARC 1-presented information on licensee and NUMARC/ Electric Power Research Institute (tPRI) testing and evaluation methodology of PS1/WJM flanges. This infors.ation I-was surer.arized in a letter to the NRC tros NUFARC dated July 25. 1988 and a detailed report and proposal was subsequently subeltted on July 29. 1988 j
(Attachment 1).
Based or. the reported s.easurement and analytical results to date, the hkC has concluded that for full power licensees it is appropriate to suspend. terpo.
rarily. the field measurements, testing, records review. and the preparation of justifications for continued operations (JCOs) that were requested by Bul.
1etin 88 05 and Supplement 1 untti further notice. Addressees that have not received a full pcwer license are requested to continue the in. situ testing l
ar.d the records review. The time frames of interest rer.atn as specified in the original Bulletin, January 1. 1976 to present. During the temporary suspension of the requestcc activities. the NRC will review the measurertrit ano test data and results of ar41ysis performed anc otterr.ine the extent to 140C030289 L
139 l
1 NRCt 6C.05. Supplement 2 August 3. 1968-Page 2 of 3 wl.ich further actions are appropriate to assure the continued safe operation of nuclear power piarits. However addressets should continue to analyae the test results perforced to date.
On July it.192. the NRC staf f coa.pleted its review cif FSI/WJM/CLM purchase orcer and invoice records. 6ased on this review, the staff has determinee thct
, PSl/W'P/CLM provideo product forms in adcition to flanges and fittings, the additional product forins are icentifisc in Attachment 2 and a list of nuclear pcwer piants that were identified as possible recipients of P5l/WJM/CLM materials is provideo ir. Attachment 3.
The hRC staff also identified Certified Material fest Ser.crts (CMTRs) for ASME Section 111 materials froe CLM. which also shou be considered as suspect.
CLM was owned by parties involved in PSI and WJh and the persons signing the CMTRs for CLM also signeo the CM1Rs for PS! and kJh. provices a IIsting of additional intermediary suppliers / fabricators of P$1/hJM/C1.M products, hiletin 88 05 identified 1976 as the beginning cate for suspect raterials provided by PS1/WJM; however internation available to the NRC now triolcates that WJM may hate provided ASMC materials as early as 1962. The NRC is providing the etcve information to assist the incustry in their uncerstancing of the PSI /hJM/CLM issue.
ActionsIscQuestej:
The actions requested in Bulletin 88 05 and Supplement 1 are temporarily sus.
penced with the following exceptions:
'f 1.
Addressees that have not received a full power operating license are requested to continue the records review and the in situ testing cf installed flanges ano ttttings.
2.
Addressees are requested to maintain for inspection the documentation of the specific actions taken for the identified materials.
3.
Addressees are requested to retain nonconforming materials until advised further by the hRC.
4.
Addressret are encouraged to report the results of tests of PSI and WJM supplied flanges ar.d fittings to the lhFC huclear Network for disserination to the incustry.
l
-Repcrtino Requirements:
The reporting requirements of Bulletin 88 05 and Supplesaent 1 are temporarily suspended with the folloiting exceptions:
1.
Holcers of full power operating licenses are requires to repcrt the results of their records review, testing. and analysis perturmed as of the date of this supplement in accordance tith the 120 cay reportirg requirement spect-tied in paragraph 1 of bulletin 88 05.
I.
Holders of construction permits are required to report the results of the recores review, testing. ano arislysis prior to the planned fuel lead date.
l 140 a
r hAC6 68 05. Supplement 2 August 3. 19CL Fave 3 of 3 If you have.any q6estions about this matter, please contact one 6f the technical cotitects listed below or the Rtgional A6tinistrator of the appropriate NRC regittial ottico.
0
.<1.C M
Charles L. Rossi. Director Division et Operational [ver.ts Assessment Of fice of Auclear kesctor Regulation Technical Centacts: Eay Cilimberg, hkk (001) 492 3220 Ls Laker. NRR (301) 4ti 3221 At tachn.cr t s :
t tr to NRC fe. f.bhAR' C. etc July 29. 1900 k.
Froduct Ferrs Sola by LJP:/ PSI / Chews Landing 3.
huclear Plants Receiving Suspect Material-4 Purchasers Receiving Suspect Material 6.
List of Recently Issued kkC 6ulletir.s I
p.
I i
I l
9 1
141 a
Attachment No. I t
NRCt 68-05 Supplement 2 NUCL( Ae MANAO(M(W1 AND elsOQeC[s COUNCHLAugust 3. 1988
...., z,
., y s.3. p.. : ; ;
i
.. I ;.a :
1 t
July 29. 1968 Mr. Thomas T. Martin Associate Director for Inspection i
and Technical Assessment Office of Nuc1Aar Reactor Regulation U. 5. Nuclear Regulatory Comission Washington, D. C. 20555
Dear Mr. Martin:
In a meeting held July 22 with NRC. NUM RC requested that utility activities relative to NRC Bulletin 88 05 and Supplement I be suspended.
NUMRC's letter of July 22.This suspension request was based on a generic In the subject NRC meeting. NUMRC also presented an analysis of utility and laboratory test data obtained to date.
letter of July 25 to Dr. Thomas Morley formalized the request for suspension.
NUMARC's 1
the test data and conclusions presented in the July 2 quantitative statistical evaluations relative to the conclusions presented at this meeting. That report is hereby provided as an attachment.
to completion even'if utility test efforts are suspended.As noted pr An update of the testing program as well as inclusion of field test data not yet r We would like to reiterate the importance of timely action in your consideration of NUMARC's request for suspension. Utility resource Continuation of testing is not resource effective and, as docum attachment, would not be expected to resgit in additional insights.
in conjunction with the generic analysis previously provided, the attachmentMoreover.
substantiates that no significant public health and safety concern is represented by th.is issue.
142 w ---
-M
.~
Mr. Th'omas T. Martin
.tu1y 29, 1988 Page t l
F NUp%RC is studying all available information'to determine what industry t
action should be taken to come to final resolution of this issue.
We will discuss our intentions with you and your staff in the near future.
If you or your staff have any questions, please do not hesitate to contact us at any time.
L sincerely, J./A W L William H. Rasin WHR/ reb Director. Technical Olvision Attachment i
cc: Lawrence C. Shao Ofrector, Division of Engineering and Systen Technology l
O. J. Mcdonald Executive Director
(.
National Board of Boiler and Pressure Vessel Inspectors 143
i
.l i
NUMARC CENERIC 7187!NC PROCRAM L
Al$80N$t to ERC SUtttTIN 88-05 INTEAIM At PORT July 29,1988 Prepared By t
Sechtel National, Inc.
San Francisco, California 94105
(
Prepared For
!!ec t ric Powe r 3412 Millview Avenue Palo Alto, California 94203 I
l L
144
~._
An$thACT The NRC Sulletin 88-05 addressed the alleged falsifiestion of Certified Materiale Test Reporte (047ts) by two suppliers WJM and PS2, of piping flanges and fittings. WVMARC, throwgh the technical management of tykt, developed a multifaceted program to assist utilities in addressing this bulletin.
Laboratory testing of suspect material, the coepilation of utility test date and analysis of that data are reported.
These data show in general that, escept for blind flanges, the suspect material meets tensile strength requirements and is eatisfactory for ASME Ceda applications.
The hardness testing results for the same materiale exhibit a broad statter band which would justify application of a testing tolerance band in cooperleen to the AlfN A370 conversion free hardness to tonelle strength.
The field and laboratory testing reewits both eahibit the este broad scatter band.
A laboratory generated best fit curve is weed to relate measured field hardness to tensile strength.
TV e field hardness test data for 1334 items show the asse scatter band as found in laboratory tests, and follows the sene general bell ekspe hardnese distribution se laboratory hardness tests.
The similarity in shapes and the lack of burps at either the low ends or the high ends of these laboratory and field histograms indicates that there is not a concern for low strength material or high strength'esterial.
Applying a best fit approach free laboratory hardness and tensile date to field hardnese data reewits in an es tie 4te of st rengt h.
The best fit approach to the field data indicates that
(
the vast majority are acceptable. Based on the laboratory testing and eatensive field testing, it is concluded there is no materiale probles, escept possibly for some blind flanges.
Slind flanges and other components were addressed analytically in the NVMARC generic analysis report, and it was shavn that in the ' majority of cases there would not be a stress concern even if strength in the order of 60 R$! were to be assumed.
This interin report concludes that the material has acceptable strength and except for some blind flanges is satisfactory for ASKE Code applications. The continued use of these flanges and fittings does not present a safety probles.
Eecommendations are made for follow up activities.
1 l
l l
.g.
1185s 145 l
l -
.~
NUNARC 4tNERIC ftSTINC PSOCRAM kESPONSE TO NRC SVLLETIN 84-0$
INTERIM LEPORT TAPLE OF CONTENTS Illi-ASSTRACT..........................[.....................................
(
TABLE OF CONTENTS..................I......................................
((
LIST OF ILLUSTRATIONS................................................... (([
I KTR O,D UCT I ON.......................................................
1 SACKCROUND....................................................
1 NUMA RC M ULT I F ACE TE D PR OC RAM...................................
1 CENERIC STAESS ANALYSIS (Refer to previous letter of I
transmittal to NRC)........................................
1 RVMA R C ft S T I NC PR OC LAM.............................................
1 METN0DS.......................................................
1 D AT A CO MP I LAT I O N AN D RI S U LT S..................................
2 ANALYS15...........................................................
2 LA50RATORY TESTINC............................................
2 E QUOTI P-TENS! LE CORAE LATION..........................
2 UTILITY TESTINC.......................................g........
3 F l ! LD KAA D NE S S 70 T E N S ? LE....................................
3 S L I N D F LA NCE S.......... e......................................
_3 D ATA QUANTITY AWD STAT!STI CAL $1 CN!FI CAMCE....................
4 TE S T I N G S UMMAR Y..............................................
6 T O LE RANC E S LOWE R AT3 UP PE R....................................
-4 S T A I N LE S S.....................................................
i CO N C L U S I O NS........................................................
S' RE CO NNE ND AT I O N.....................................................
S S U SP E ND R t oo kDS R EVI EW........................................
5 CO MP LEt t LA S PR OCLAM..........................................
S COSP E LE E X I ST I NC F IE LD TE ST DATA..............................
W R I T E F O L LO W-O N RE PO R T........................................
5 e 118$m 146 O
',.. :M q ;,
LIST OF ILLV$thATIONS I
IAll!8 Table 1 Swarnary of Nigh brdness Lielts Table 2 Sumary of Stainless Steel Tests F1CURI$
Figure 1 Misr6 ram of Laboratory Tens!!e Results 3
Figure 2 Equotip as SHN Compared to UTS and ASTM A370 Figure 3 Best Fit Equotip Compared to UTS Figure 4-Histogram of Laboratory Hardness Figure 5 Histogram of Field brdness Figure 6 Best Fit Data Applied to Field b rdness i
e e
4
-lii-1185e 147
r i
Irinopucitow a:
BACEctovRD-The NRC issued Bulletin 88-05 regarding alleged falsification of Certified Materials Test Reports (ONTRs) by West Jersey Manufacturing Co. (WJM) ond Piping Systems. Inc. (PSI). Specific actions were required of utilities. some of these could ef ficiently be addressed by a generic program. NUMARC initiated such e. program. The NRC issued Supplement I to 48-0$ subsequent to reports of two blind flanges having low tensile strength. The supplement required utilities to perform field tests on identified installed WJM/ PSI items.
The supplement also focused effort on piping flanges and fittings. The FUMARC program was modified to coordinate and standardise field testing methods and to compile utility generated date.
Opacurrently, the generic WUMARC laboratory testing program has been~in progress.
WUMARC MULTITActTED PROCRAM Because several etions were required by 88-0$ which could be ef ficiently addressed in a generic manner, WVMARC undertook 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.
5.
Review of records to identify intermediate and secondary supply routes.
C.
Interf ace with Authorised Inspection Agencies and the National Board of Soller and Pressure %%ssel Inspectors.
i D.
Generic stress analysis of fittings and flanges.
l E.
Testing. data compilation and evaluation.
l CENERIC STRISS ANALY$15 The generic stress analysis has been completed, reviewed with and provided to the NRC. The analysis indicates that there. is little concern for the stress integrity of the fittings or flan 6es even if the materiets were of substantially lower strength when toepared to the strength requirements of S A-10 $.
This report was formally transaltted to the NRC by NUMARC on July 22, 1984.
p The testing progran.is described in the fotlowing 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.
- 118 5m
~1-148
fit opproach are discussed below subsequent to a brief analye(s of the best utility field data.
The histogram of laboratory hardnese dets orpressed in EQUCTlp values to shown in Figure 6 MILITY ftSTlWC The utility provided laboratory dets le consistent with the generic progree test date.
The utilities have provided one set of date on o blind flange, West 7218, which is comeistent with the two tests cited in 88-05 Supplement 1.
1his data peint le not yet in the computer printout. Other than this, no esbetrength esterial has been reported beoed on tensile tests. These utilities have reported tenelle strength for 108 items. Eight items slightly below 70 K51 have been reported. The remaining 101 values enceed 70 E81. In one case the utility engirteer indicated there was a subsise specimen removed free installed flange and wee transverse to the primary working direction rather than parallel. These slightly low values are readily emplained by the test direction, and by publiebed data which confirins that tensile test results from prodvet testing'esy be as such as 10 percent below the minious specified strength. None of these utilities reported strength values are a concern.
The utility generated hardnese data is shown in the histogree of Figure S.
This histogras has the same general bell shape as the histogree of laboratory hardness data.
In simple terse, the bell shapes in both laboratory and field l
P histogress and the lack of bumpe et the low hardness ende of the histograma indicates that there is not a concern for low strength material. This seans that the voet majority of field itsee would escoed 70 K51 if tested and that the remainder would be within the espected tolerance band. The conclusion is that installed items are acceptohle and do not present a esterial concern, encept for sose blind flatges.
F!tLD HAPDbT$$ TO TEN $1LE It is appropriate to compare the best fit curves of laboratory hardness and tensile results and apply the reewits of that plot to the utility generated hardnesa data. When this is done, refer to Figure 6, all items are shown to be ac c e pt able. It suet be realised that a best fit curve of field hardness should never be weed to reject (notalled itsee, because sosie itses which fall below the litie can be within the acceptable tolerance band. This is shown by the fact that the origittal data had some acceptable items below the best fit The best fit curve may be applied to warehouse items prior to curve.
installatiten, and should not be the sole justification for removal of installed items. This curve increases the confidence that the installed items are as initially intended to be.
ll q
SLIND TIAMCtl The best fit curve applied to field data, or a field hardness test tolerance does not elir.inate the fact that there are data in the histogress (but not yet in the computer data base) which indicates that blind flanges may be a concern
)
for strength reasons. McVever, the stress analytacal data provided to the NRC indicates that these substrength blinds are riot a stress problem for service conditions.
l nek 150
~
4 The lowest hardness test result la either laboratory er fleid, seide free the euepect blind flanges, is 350 L.
This is the leveet of a continuous D
spectrue et values.
The 13 suspect blind flenges are at approminately 330 Lo and appear to be a vaigue group separate free the general psyulation of acceptable material. '
i DATA QUANTITY AND STATISTICAL 81CNIFICANCE
" Analysis indicates that there are sufficient field dets open which to draw conclue lone. There is no need for edditional field hardness data. There se
)
also substantial tonelle test data which permits interin conclusions.
New parametric tolerance lielt statistical caleviations were used. The laboratory tensile results of 123 items provide 95 percent confidence that more than 97 percent of the population ~enceede 60,600 poi tensile strength.
The utility provided 108 tensile test resulte provide 95 percent confidence that more than 97 percent of the population esteede 66,400 psi tensile strength..
Aaeueing the materiale tone free the same population, combining both sets of tenelle data provides 95 percent confidence that more than 98 percent of the population escoed 60,600 poi ultimate tensile strength. Similarly, there is 95 percent confidence that more than 98 percent of the population is less than 93,200 poi ultioste tene!!e strength.
TEST 1HG $UHKARY L
The laboratory tensile data indicates there is no technical congern for the l
SA 105 material. The eisilarities between the laboratory hardness distribution I.
histogram and the field hardnese histograms indicates that there should be no concern for installed (tees given that the laboratory tensile tests indicate no concern for this materiel. The best fit curve of hardness to tensile conversions applied to field hardness teste else indicates that there is no concern for SA 10$ material.
TOLER.ANCES LOWER AND UPPER The data indicate that the're is no rest concern for SA 105 material. The blind flangee of evepect esterial which have low tensile values have hardness at a pproximately 330 Lg.
Regarding high hardness. Table I shows the precedent to install materials over 187 BHN to 207 SHN which are sonnen in nuclear plant piping. This table shows that 237 SHN is a value commonly applied to fabricated itese, welds, base metale and NA2, where N 5 stress corrosion cracking (SCC) is a concern in the 2
petrochemical industry. Such SCC'is not a concern in light water resetor piping and thue a specifi,c upper limit should not be imposed. The Structural Welding Code sp* plies a 265 SMN limit on submerged are welds and KA2 to assure adequate strength, ductility and toughness. When recognised standards apply values such as 237 and 265 SMN to fabricated, welded and instelled items, a specific upper hardness limit le not justified.
This paragraph is dieeussed in SMN torna because the Code uses SHN terms.
The principle high hardness concern is weldsbility. If the installed item has acceptable veld inspections, has suetsined bolt-up loads, hydrostatie teste, proof testing, functional test and whatever p51/151 that is applicable, then 1185e
-4 L
151
e there are objective reasons to use as (s.
high hardness items with acceptable welds and KA3 are einime).The benefits of replac the risks in any replacement are greater. The ALAAA sensiderutions also In cont rast,
indicate that high hardn plant unique overriding.ess items not be replaced unless there is a c onc e rn.
L STAINLISS STEEL l-There is e relatively small amount of stainless steel installed, and very lit tle in warehouses.
To date, all tests performed on stainless steel have been acceptable.
Approximately four desen items have been tested.
results are acceptable, all chemical analyses are ecceptable end allAll tensile eensitisatien tests are seceptable.
Approminately 10 desen magnetic checks were also acceptable.
Only one of all these test resalts is slightly lowi that is, one yield strength value was 24.1 R$1 vs. 30.0 R$1. and this difference is insignificent.
These tests are summarised in Table 2.
While the abso!"te number of te ix tuits is not as great es for carbon steel the results inoicate there is no ei..ern.
~
CONCLUS10HS The strength of SA 105 material and stainless steel items which were suspect is mot a concern.
4
_RE COMMI NDATIONS 1.
The test results to date indicate there is no toneern for materials and thus field testing may be suspended as there is sufficient data for evaluation.
The generic stress analysis also indicates there is me 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.
Thus, it is appropriate to suspend document reviews and field testing.
2.
The laboratory progree should be completed subject to constraints of available material.
3.
The existing utility generated data should be compiled and analysed in the WVMARC program.
4.
A summary report should be generated.
l 1135m 152
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i LABORATORY HARDNESS VS~
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TENSILE STRENGTH 8
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<344 348 344 381. Ste. 410 434 437 456 463 475 Het SSS 360 all 409 483 436 449 ett 474 det HARDHESS CATEGORIES l
Data as of 7/22/88 ij FIG. 4 HIS70 CLAM OF LA80RATORY
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Observations
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k Data as of 7/19/88 FIC. 6 SIST FIT DATA APPLIED 70 FIELD HMtDNESS STRENGTH EST!.M TE 158
4' s
TA$L8 3 smur or n:GN *Atwass units Se MAX. MARDNESS LIMITS BHN
~
SA 350 e
g,7 SA 105 PRE 1972 g/A SA 105 POST 1972 137 ONLY IF QUENCHED l'
SA 234 WP,8-SUPPLEMENTARY 197 SA 181 M/A SA 182 F1 192 F2 192 F 11 207 F 22 207 AWS D1.1 WELD & MA2, MV280 265 NACE MR-01' 75 Re22 237 BASE METAL, WELDS, hag s
159
TABL8 $
S N Y OF $TAINLg$$ gtggt ygggg S
STAINLESS RgsytTg 7/19/88 TENSILE 9
HARDNESS g
CHDGSTRY g
SENSl?!!ATION 33 MAGNETIC 120 1
4 160 l
l l
i Attachment t l
kRC8 St.05. Supplement 2 August 3. 194t t
Product Forms Solo 81 WJk(P51/ Chews LandinsI Flanges Falf Couplir.gs full Couplings
. Plate kings Penetration Plates.. $Al16. 6870 Seal Fictes.. $A516. 647 g
Socket held act:1es (CLM)g (Ferryl Long Drein less.. A162f11 & F22 Radiograph Plu Square bar.. gs (CLM) 1016 Spacers
$ ample Probes Class 1.. $A312.1304 (Perry) (CLM) i Guide Lves.. $A240,1304 loctet Welded Nelf Couplings Class 1.. $A182. F3C4L (Vogtle)
$pecial kortles Pipe Caps.. $A234 Lves.. $A240, 1304 (Pelo Veroe) tugs.. $All6. GE70 (Palo Verde)
Socket Weld Couplings Plate. $A36 (Perry)
Special 8085.. A234. A10$. A739
(
Scits.. $A193. gal? (Confrentes/$ pain)
Ir.strument Penetration ind Plate.. $A516. GR70 (Perry) hanger Lugs.. $All6. GATO (Drave /$$te unknownl Socket Wale bcss.. Class 1 ** SAlti, f316 ($eabrook) (CLM) fransiticr. Flece.. $A105 (Vogtle) 1hermowe)):.. A382 (Dravo /Muntar/$lte unknown) (CLM) lar $tock.. A106 (Dravo / fellow Creek) (CLM)
I This is a coeplete list of all product forms identified during the NRC staf f's review of available recores.
e I
$pecific r:bclear pcwer plants or customers are noted in cases where the preduct fore appeared to be a unique or special order and not w1oe spread.
I Indicates that material was sold by Chews Landing Metal kanufacturers Inc.
161
_ _ _ _ _ _. _ _ _ _ _. _ _ _ _ _ _ _. _ _., _ _. _. _ ~ -., _ _. _ _ _ _ _ _ _. _,.,. -..,
,<-__r___.
l
- 8C0 48 05. 56pplement i Av9bst 3. 1964 l
hi.!Lar,_ Plants neceivink SusDect Materf al l l
Seaver t' alley i
8ellefonte Growns ferry Ca.Iltway Calvert Cliffs Cec 6 01able Canyon Duane Arnold fermi Match Monticello North Anna d
Prairie Islane Quad Cities Shorsham fursey Point.
Waterfore Yellow Creek liner
(
I 1
I 1
I 1
These ruclear pcwer plants are k addition to those previously identifi'd as receiving suspect materia).
162
l 1
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Attethment 4
- Ct 80 0$. $vppleeent t August 3.2)hti Purchesars $atelvine lusoect Meteriel l terr.149ece rs, let.
M.W. kellon (became Division of Pullman)
Lebe trie 'rcr. & Netal (c.. loc.
i Liberty.Envipment. Co.
s V4tal sellows (listed as 6ellows in Bulletin) t
' Power Piping (c.
)
$tendercs hpe & $vppl 1
11054 Pipe $vpply Co. y Co.. loc.
Inc.
1pler Lawson (liste6 in error as fyler Cavison in tulletin)
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t l
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(
I These purchasers are in accition to tiiose previously identif teG and are known to have received meterfel fer nuclear applications.
l 163
-.---- - -..-- -----e
Attachment $
RPCS 48 05. $9tplement 2 A6 gust 3. 1988 Ll$f OF AEC(NTLY 155Vl0 hkt 80LtL11N5 ETie tin cate or he.
Subject
, issuance issued to 88 08.
Thers.al Stresses in Pipin6 t/4/68 All holders of OLs
$6pplement 2 Connected to nesctor Coolant Systees or cps for light.
wcter cooled r.uclear i
power reactors.
86 09 Thimble Tube thinning in 7/26/68 All holders of OLs Westinghouse 8eactors of cps for [.deligned nuclear pewer reactors that utiliae bottom mounted instrumentation.
86 08 It.sreal $ tresses in Pipit.g 6/24/88 All holoers of OLs Supplement 1 Connected to Feactor Coclant or cps for light.
Systeel Water cooled nuclear power reactors.
44 08 thersal Stresses in Piping 6/02/f4 All holders of GLs Ccnnected te Reactor Coolant Systems or cps for light.
water. cooled nuclear power reactors.
68 0$.
Nonconforming 04terials C/15/64 All holders of Ots
$6pplement 1 Supplied t.y Fiping Supplies, or cps for nuclear l
Inc. at Folsom New Jersey power reactors.
and West Jersev Mcnuf acturirg CompanyatWilliamstown.
l New Jersey 68 07 Power Osciliations in 6/15/88 All holcers of Ots toiling koter Reacters (tWRs) or cps for 8Wes.
Lt.06 4ctions to be Taken fer 6/14/88 All Akt licensees the Irer sportatter. of authorized to l
1 Mooal f.o. Spec ?.i s'e nu f a cture.
Aasiegraphic (sposure Device distritsute, or operate radiographic i
exposure devices or secree changers.
- Operating License CP = Construction Pers.it i
I
'164
_ _ y.._ _ _ _. _ _ _ _ _. _ _ _ _.
UNITED STATES NUCLEAR REGULATORY Com!$$10N 4
1 0FFICE OF NUCLEAR REACTOR REGULATION WASHINGTON A C. 20555 November it. 1988 NRC Sulletin No. 88-10: NONCONFORMING MOLDED-CASE CIRCUIT BREAKER $
Addressees All holders of operating licenses or construction pemits for nuclear power reactors.
Purpose:
The purpose of this bulletin is to request that addressees take actions to providereasonableassurancethatmoldedcasecircuitbreakers(CBs),in-cluding CBs used with motor controllers, purghased for use in safety-related applications wjthout verifiable traceability to the circuit breaker manu-facturer (CBM) perfore their safety functions.
Description of Circumstances:
NRC Infomation Notice No. 88-46. " Licensee Report of Defective Refurbished
[
Circuit Breakers.* dated July 8,1988 and Supplement 1 thereto dated July 21, 1988, discussed a report by Pacific Gas and Electric Company that indicated Systems. Inc. through a local electrical distributor.thatitsDiabloCanyonNuclearPow These CBs $quare D l
molded-case, type KHL 36125) were intended for use in non-safety-related app 11-cations at the Diablo Canyon Nuclear Power Plant. Square D Company reported that an inspection and testing of these breakers detemined that the CBs were refurbished Square D Company equipment.
Furthermore. Square D reported that several of the circuit breakers tested did not comply with Square D or Under-writers Laboratories. Inc. (UL) specifications for all of the electrical tests I
performed.
Information Notice No. 88 46 also listed several California com-panies that were involved in supplying surplus refurbished and possibly defective refurbished electrical equipment to the nuclear 1r.dustry.
During recent NRC inspections, additional examples were identified that indicate a potential safety concern regarding electrical equipment supplied to nuclear power plants. The NRC is concerned that equipment being procured as new and assumed to meet all applicable plant design requirements and/or original manufacturer's specifications may, in fact not conform to these requirements and specifications.
{
.o 1.
Refer to Attachment 2 for Definition of Terms 8811180315 l
9 4
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_..,.,,.-_,m-m_~.-
~.
page 2 of 7 j
The actions requested in this bulletin are 11 sited to molded-case CBs. Molded.
case CDs are tested and calibrated at the manufacturer's plant in accordance with reco'gnized industry standards, such as UL-459, ' Molded Case Circuit Breakers and Circuit Breaker Enclosures,' and National Electrical Manufacturers Assoct-i atton (NEMA) AB1, ' Molded-Case Circuit Breakers.' Since molded-case CBs have j
factory calibrated and sealed elements, any unauthortred modification or re.
furbishing of these CBs could jeopardine their design capability and reliability.
The NRC is concerned that the reliability and capabilities of refurbished CBs purchased as comercial grade (non Class 1E) for later upgrading to safety-related (Class 1E) applications may.not meet the minimum commercial grade standards.
In addition, the NRC is concerned about the reliability and capa.
bilities of comercial grade CBs upgraded to safety-related because of some I
observed inadequacies in the dedication process and numerous failures found during the testing of some of these CBs.
In order to properly dedicate electrical items procured as commercial grade for subsequent use in safety-related applications, the dedication process should build from the comercial grade quality, include a proper evaluation of seismic and environmental quali.
fication, confim critical parameters, and include testing as appropriate.
Molded-case CBs purchased from the CBM or that can be traced to the CBM are of lesser concern than other molded-case CBs because CBs from the CBM, whether safety related or comercial grade, are manufactured under controlled conditions Safety-related CBs to confom to a proven design.
the CBM are controlled under quality assurance (QA) purchased as Class 1E from programs that conform to Appendix B of 10 CFR Part 50. While upgrading programs may vary in quality, tie controls exercised by the CBM over the manufacturing activities provide reasonable assurance that improperly refurbished components have not been in-troduced and passed through the upgrading process.
Furthemore, the redundancy of safety systems and the in service use of CBs provide a reasonable basis for accepting installed replacement CBs that have been procured from the CBM or that can be traced to the CBM.
The NRC currently believes that the concerns addressed in this bulletin do not apply to electrical equipment (safety-related and commercial grade) originally installed in plants.
This equipment appears to have been procured during plant construction from CBMs with full certification. The large quantities of electrical assemblies or components procured under bid packages during plant construction reduce the possibility of any original plant equipment being sup-plied by vendors doing refurbishing.
Although the actions' requested in this bulletin only apply to safety-related molded-case CBs, the NRC intends to monitor industry programs to ensure that other molded-case CBs, which may have been installed as replacements, installed during modifications, or are being maintained as stored spares, are suitable for their intended service. Addressees are encouraged to participate in a jointprogram.
If industry programs are either not timely or not sufficient, additional regulatory actions will be taken, as appropriate.
o.
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NoNmYr'5t,193 page 3 of 7 The NRC requested and received cossents from the Nuclear Management and Resources These coments were considered and some)w, ation (NEM),lletin and the Underwriters Laboratories, Inc. (UL during the preparation of this bu this bulletin.
NEM has comented to the NRC that determination of the critical performance characteristics of durability and short-circuit capabilities of CBs requires destructive testing of selected breakers that are representative of Cls to be i
placed in service.
Because a refurbished breaker may not have been refurbished under controlled conditions to conform to a proven design selected breakers will not infer anything about a refurbished CB. destructively testing UL provided specific coments on the tests in Attachment 1 of this bulletin.
In addition, they stated that. *1t is UL's opinion that the test program is not adequate to provide assurance that the tested non-traceable, circuit breakers would be suitable for their intended purpos,e.' Although the test program described in Attachment 1 of this bulletin does not provide complete verification of all the performance requirements and characteristics of molded-cast CBs (such as seismicity or fault clearing capability), the NRC considers the test program to provide a reasonable assurance of performance requirements and characteristics most important to ensuring reactor safety.
i This, considered in conjunction with (1) the limited number of nonconforming C8s that may remain installed in safety-related s bulletin,ystems following implementation of the actions requested by this (2)theexistenceofredundantsafety-relateds power reactors that are required by NRC regulations, (3) ystems in nuclear the license required in service testing of installed CBs performed to demonstrate the C8's functional perfomance, and (4) the low frequency of occurrence of seismic events and severe electrical faults, provides a reasonable assurance that nuclear power reactors can be operated without undue risk to the health and safety of the public.
The NRC investigation of this issue is not complete.
A supplement to this bulletin may be issued to include other electrical equi: cent or a longer pro-curement review period if warranted by the results of tie ongoing evaluations or the results of testing requested in this bulletin.
Actions Requested:
1.
All addressees are requested to perform the following review by March 1,1989:
Identify all molded-case C8s purchased prior to August 1, 1988, that a.
are being maintained as stored spares for safety-related (Class 1E) applications or comercial grade CBs that are being maintained as stored spares for future use in safety-related a sp ications; this includes C8s purchased from a CBM or from any other source. If the number of these stored spare CBs is less than 50 at a nuclear plant site then randomly select CBs purchased between August 1,1983 and Tugus,t 1,1988 that have been installed in safety-relatej applica-tions as replacements or modifications to forin a minimum sample of 50 CBs per nuclear plant site.
4 D
4
- - - -. - -,. - -. _ _ _ _ _ _ _ _ _ _. - -,.,,.. ~ - - - - -
,,,n.,,,,.,._.-,,,n.,.,
,,..,,_n.-_w,
--_y,p gg y b.
Verify the traceability of these CDs.
1 Ioantify the number manufacturer, model number, and to the ext c.
possible the procure, ment chain for all those CBs identified that cannot be traced to the CDM.
each system in which they are/were installed.For installed C88, also identif 2.
All holders of operating licenses who identify installed CDs per it above or item 4 below that cannot be traced to a CBM are requeste prepare, within 30 days of the completion of each item requested in this bulletin have been completed. justifying an analysis 3.
All addressees who identify 80 percent or more C8s traceable to per item 1 above are requested to test the CBS that are not traceab the CBM in accordance with the testprogram described in Attachment 1 Any installed CBs that fail any of tuse tests should be replaced w C8s that meet the criteria of item 7 of the actions requested or C8s that pass all tests in accordance with the testing program described in Attachment 1.
of the tests described in Attachment 1, continue with item 4 proceed to item 6 of the actions requested.
8 otherwise, before startup from the first refueling outage be Holders of construction permits are requested to complete t ram program before fuel load.
4.
All addressees who identify less than 80 percent of the C8s trac the CBM per item 1 above or who identify a failure rate of more t percent for the C85 tested per item 3 above are requested to perform following actions:
Identify all molded-case CBs that have been purchased be a.
1983 and August 1,1988, and installed in safety related applic as replacements or installed during modifications.
b.
Verify the traceability of these C8s.
Identify the number, manufacturer, model number c.
are/were installed, and to the extent,possible,,the procurement c for all those CBs identified in (44) that cannot be tr 5.
per item 4 above are requested to replace the meet the criteria of item 7 of the actions requested or to test them in accordance with the program described in Attachmerit 1; C8s th of these tests should be replaced with C8s that meet the criteria of item 7 of the actions requested or CBs that pass all tests with the test program described in Attac,hment 1.
nce l
)
i
November it. 1983 i
Pope 5 of 7 Holders of eforating licenses are requested to replace er to test at ieast omha f, or an if the totai number is its: than n, of these installed CBs before startup from the first refuelinJ outage beginning i
after March 1. 1989.
The remaining CBs should be replaced or' tested before startup from the second refueling outage beginning after March 1. 1989.
Holders of construction Pemits are requested to replace or to test these installed C8s before fuel load.
6.
Information generated while performing the actions requested in items 1.
i
- t. 3. 4. and 5 above should be documented and maintained for a period of 5 years after the completion of all requested actions.
4 7.
With the exception of actions taken in response to items 3 and 5 of the actions requested above, molded-case CBs installed in safety related ap-p11 cations after August 1,1988 should be:
Manufactured by and procured from a CBM under a 10 CFR 50. Appendix 9.
B. programs or b.
Procured from a CBM or others with verifiable traceability to the CBM. in compliance with applicable industry standards and upgraded to safety-related by the licensee or others using an a,cceptab e dedi-cation program.
The NRC encourajes addressees to significantly upgrade i
their dedication programs throug"i a joint industry effort to ensure their adequacy and consistency. The NRC will monitor thste industry initiatives and if they are not sufficient or not timely, or if prob-lems with the dedication of comercial grade equipment for safety-related use continue, the NRC will take appropriate regulatory actions.
8.
Addressees that cannot meet the schedule for the actions requested above and/or the corresponding reporting requirements below, should justify to the NRC their proposed alternative schedule.
Reporting Requirements:
1.
All holders of operating licenses are required to provide a written report by April 1.1989, that:
Confims that only molded-case CBs that meet the criteria of item 7 a.
of the actions requested are being maintained as stored spares for future use in safety-related app 1' cations.
b.
Sumarizes the total number manufacturer, model number, and to the extent possible the procurem,ent chain of those CBs that could not be traced to the CBM in items 1 and 4 of the actions requested.
For installed CBs. also identify each system in which they are/were in-stalled.
If item 4 of the actions requested has not bee 4 completed e
4 e
9
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November it.19']
i Paee s.f 7
)
by Aprt) 1 y
actions req 1949, due to the schedule for tests in item 3 of the i
uested, this infomation should be updated within 30 days of the completion of item 4 to address those additional C8s that could not be traced to the C8M.
c.
Confirms that items 1. t. 3 have been completed or will,be implemented as requested,4. 5 j
i t.
All holders of operating licenses are required to submit a report that 3 and 5 of the actions requested within 30 days after startu first and second refueling outages beginning after March 1 p from the i
1989. For manufacturer, model numberC8s that pass these tests the only informatio and to the extent possible the i
chain of C8s tested (sumar,y report format is acceptable). procurement values of test parameter (s) at which the failure s) occu!
as the correspondin!) manufacturer, model number,(and to the as well the procurement cha'n.
3.
All holders of construction permits are required to provide a written 1
report by April 1.1989 that i
s Confirms that only molded case C8s that meet the criteria of item 7 a.
i of the actions requested are being maintained as stored spares for I
future use in safety-related app 1' cations.
I b.
Sumarizes the total number manufacturer model number, and to the extent possible the procurem,ent chain of those CBs that could not be traced to the C8M in items 1 and 4 of the actions requested.
i i
For installed C8s. also identify each system in which they are/were installed.
If item 4 of the actions requested has not been com-pleted by April 1 of the actions req.1989, due to the schedule for tests in item 3 uested, this information should be updated within 30 days of the completion of item 4 to address those additional C8s that could not be traced to the C8M.
c.
Confirms that items 1. 3. 4
- 5. 6 and 7 have been completed or will be implemented before fuel Ioad.
4.
All holders of construction permits are required to submit a report that of the actions requested within 30 days after fuel load.sumartre these tests, the only information required is the number, manufacturerFor CBs model number, and to the extent possible, the procurement chain (sumar,y report format is acceptable.
For C8s that fail these test (
the report should indicate the test (s))and the values of test parameter the failure (s) occurred, as well as the corresponding manufa at which number, and to the extent possible, the procurement chain. '
rer,model
gggg,,7q ra,.,.f The written reports re Regulatory Comission. quired above shall be addressed to the U. S. Nuclear ATTN: Document Control Desk. Washington. D.C. PC555 under oath or affirmation under the provisions of Section 182a. Atomic Ener.
~;
Act of 1954, as amended.
propriate Regional Administrator.In addition, a copy shall be submitted to'the ap i
i This request is covered by Office.of Management and Budget Clearance Neber 3150 0011 which expires December 31, 1989. The estimated burden hour is 1000 to 10.000 man hours per plant response. including assessment of these require.
ments, searching data sources, testing and analysing the data, and preparing the required reports. Coments on the accuracy of this estimate and suggestions to reduce th. burden may be directed to the Office of Mana Room 3208. New Executive Office Building. Washington. 0.C.gement and Budget.
. 20503. and to the U.S. Nuclear Regulatory Comission. Records and Reports Management Branch.
Office of Admin'stration and Resource Management. Washington. 0.C., 20555.
If you have any questions reqarding this matter please contact one of the technical contacts listed be' ow or the Regional, Administrator of the appropriate NRC regional office.
L harles E. Ro<ssi. Director l
Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical contacts: paul Gill. NRR (301)492-0811 Jaime Guillen. NRR (301)492-1170 Attachments:
1.
Test program for Molded Case Circuit Breakers 2.
Definition of Terms 3.
List of Recently Issued NRC Bulletins l.
(
l 9
- ~
._,_,,,s_
.._,c,,
NRCS CC-10 November 22,1908
+
Page 1 of 4 TIST PROGRAM FOR MOLDED-CASE CIRCUIT BREAKER $
1.0 Test Procras Objectives The objective of this proposed test program is te verify the reli-ability and capabilities of molded-case circuit breakers (CBs).
For the safety of personnel and others involved with the activities related to these proposed tests, appropriate safety practices, such as AN5!/NFPA 70E, Electrical Safety Requirements for Employee Workplaces." Part !!. should be followed.
These proposed tests have been based on tests described in industry.
standards, such as NEMA AB-1. ' Molded Case Circuit Breakers." NEMA AB-2. "Procedares for Field Inspection and Performance Verification of, Molded Case Circuit Breakers Used in Conrnercial and Industrial Applications." UL 48g " Molded Case Circuit Breakers and Circuit Breaker Enclosures." and NETA STD ATS-1987. ' National Electrical Testing Association. Acceptance Testing Specifications.'
2.0
_ Test Procedures for C8s s
The following tests should be performed in the sequence listed..C8s failing any of these tests should be considered unacceptable for safety-related appitcations.
2.1 Mechanical Test i
The C8 should be operated, reset, and closed a minimum of five times, to ensure that the latching surfaces are free of any binding.
2.2
_ Individual Pole Resistance or M1111 volt Droo Test (Ref. NETA 5TD ATS-1987 5 NEMA AB-2)
The contact resistance of each pole of the C8 should be measured at ambient temperature. Three readings of each pole should be taken with the C8 operated without load between each reading. The average of three readings for each pole should be calculated and compared with the manufacturer's contact resistance data or with those values of siellar CBs from the same manufacturer.
Also the average value for each pole should be compared with the average, of the otMr poles and the difference between the poie values shou d not exceed 50 percent of the lowest values or A millivolt drop test may be performed by applying a direct current across the closed CB contacts and measuring the voltage trop due to the contact resistance.
The millivolt drop test shou 4 th performed o
- at room temperature.
Direct current should be appited across each e
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November it. 1988 Page 2 of 4 pole and the utilivolt drop and test current recorded for each pole.
Threa readings of each pole should be taken with the C8 operated with.
out load between each reading.
each pole should be calculated and compared with the manuf value for acceptance of the breaker.
2.3 Rated Current Hold-!n Test (Ref. NEMA AB-18 E 489) i This test should be conducted at 2005 rated current and at en ambient air temperature of 25'C 13'C. and followed by a test at 1
1355 rated current and at an ambient temperature of 25'C
- 3'C.
Equal 2005 rated currents should be applied to all poles of the C8.
The C8 must not trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for C8s rated 50 amperes or below i
or within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for C8s rated over 50 amperes durins this test. At the end of the 2005 rated current test the current should be incre to 1355 and the CB should trip within I hour for C89 rated 50 amperes or below or within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for CBs rated over 50 amperes.
2.4 Overload Test (Ref. NEMA AB-14 UL 489)
This test consists of one operating cycle (i.e., closing action s
followed by an opening action) of the C8 at 6005 rated current.
This test may be conducted at low voltage.
There should be no electrical or mechanical breakdown of the CB during this test.
2.5 Instantaneous Trio Test (Ref. NEMA AB-14 UL 489) 2.5.1 Fixed Instantaneous Settine C8s Each pole of the CB should be tested for pickup of the instantaneous unit.- Each pole must be between 755 and 1255 of the instantaneous trip rating. The trip time should not exceed 0.1 seconds (6 cycles).
- 2. 5. 2, Adjustable instantaneous Settine C8s This test is the same as that in Section 2.5.1 exce must be tested at the lowest and highest settings. pt that each pole The trip value for the lowest setting should be between 755 and 1255 of the lowest setting, and the hi and 1205 of the highest setting. ghest setting should be between 805 2.5.3 Short-Time Trio settine Test This test is applicable only if the CB is equipped with the short-time delay trip. This test should be conducted at an ambient air temperature of 25'C
- 3'C.
The operation of the short-time delay unit should be within 905 and 1255 of the overcurrent tetting of the CB as shown on the manufacturer's time-current curves.
4 4
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6
November it.133 page 3 of 4 2.6
_ Time Delay Overcurrent Tris (Ref. NEMA AB-2)
This test should be conducted at an ambient air temperature of 25'C a 3*C.
be applied to each pole of the CB.A current of 3005 (at lo time-current curves.should be compared with the time show l
are not within the time band shown on the CD manufa i
in Table 1 and the acceptance of the C8s must b i
criteria listed below:
e TABLE L VALUE5 FOR OVERCURRENT TRIP TEST IAT 3001 0F RATED CONTINUOUS CURRENT OF CIRCU 1REF. NEMA AB-Z)
~
Breaker Range of Rated Voltage Continuous Current Volts Amperes Maximum Tripping Time In Seconds 240 15 45 240 e
e 50-100 50 70 600 l
600 15-45 i
50-100 70 125 240 240 110-225 250-400 200 300 600 600 110-225 600 250-400 250 600 450-600
'300 600 700-1200 350 600 1400-2500 500 3000-5000 600 650 Minimum Tiinoine Time:
than Indicaled by the manufacturer's time-current curves f C8 under test, the Cl should be ratested after it has been cooled to 25'C.
coordination with upstream and downstream CB s If no problem with coordination is indicated, then the C8 is ac-ceptable.
'(
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NACS 88-10 '
November it. 19 3 Page 4 of 4 Maximum Trimeine Timet If the tripping time exceeds the tripping time shown on the manufacturer a time evrrent curmaximum i
1s below the time shown in Table 1. check the Cl time ves but protection requirements of the circuit (such as cable penetration.
etc.) to ensure that the CB provides the protection a,s well as the coordination with upstream and downstream Cts.
If the Cl provides the necessary protection and coordination, then the Cl is accepta Maximum Allowable Time:
If the tripping time of the CB exceeds the trip time shown in TabTe 1. the breaker is unacceptable for Class It applications.
2.7 Dielectric Tests (Ref. NEMA A8-18 (A. 4891 volts (805 x ;2 x rated voltage + 1000 volts)). o for 1 minute withstand.
(1) line to load teminals with CB open (2) line to line ten with C8 closed, and (3) pole to ground with C8 open. and (4) pole to ground with C8 closed.
l I
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,NRC4 46-1,0,,
N FIN!T10N OF TERMS
_ CIRCUIT BREAKER MNUFACTURER (CSM}
The manufacturing facility that actually produced the circ purchased.
reaker being YERIFIABLE TRACEA8!LITY Documented evidence such as a certificate of com compliance is provided by any party other than If the certificate of such certificate must be verified by an audit or other appropriate means. the licensee or pe. the va PEDICATION PROCE$$
i
,I
{
to safety related (Class IEThe process by which comerci safety-related applications.) and is thereby considered qualified f ent is upgraded The dedication process must include:
s'.
A technical evaluation to detemine the characte
)
to fulfilling the safety function (s).
critical g
b.
An acceptance process to ensure that those critical cha are met.
i eristics i
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November 88. 1988 LIST OF RECDfTLY 155UtB NRC BKLETINS
)
O l
su11stin pate er No.
Subject issuance Issued te 84-05 Supplement 8 Nonconfoming Materials i
Supplied by Piping Supplies
$/3/88 All holders of OLs Inc. at Folsom end West Jersey New Jersey,
or cps for nuclear Manufacturing power reactors, Company at W1111emstown.
t New Jersey 88-08 Thermal Stresses in Piping Supple. ment 2 Connected to Reactor Coolant 8/4/88 All holders of OLs Systems or cps for Itght-water-cooled nuclear power reactors.
88-0g Thimble Tube Thinning in 7/26/88 Westinghouse Reactors All holders of OLs or cps for W-designed nuclear power reactors that utiliae bottom mounted instrumentation.
88-08 Themal Stresses in Piping Supplement 1 Connected to Reactor Coolent 6/24/88All holders of OLs Systems or cps for light.
water-cooled nuclear power reactors.
88-08 Themel Stresses in Piping Connected to Reactor Coolant 6/22/88All holders of OLs Systems or cps for light-water-cooled nuclear 88-05 power reactors.
Supplement 1 Nonconfoming Materials Supplied b'r Piping Suppites 6/15/88 All holders of OLs t
Inc. at Fo som and West Jersey New Jersey,
or cps for nuclear Manufacturing power reactors.
(
Company at Williamstown.
88-07 Power Oscillations in Boiling Water Reactors (8WRs) 6/15/88 All holders of OLs or cps for BWRs.
l OL = Operating License CP = Construction Pamit l
J u
i e
m et e o e
m
n%s ee-4U l
i C vember it. 1988 LIST OF RfCDfftY ISSUED NRC SULLETINS
~
sv11stin
- D.
Subject pate of 88-06 tssuance Issued to Supplement t Nonconforming Materials Supplied by Piping Supp1fes 4/3/88 Ali holders of OLs Inc. at Folsom and West Jers. New Jersey,
or cps for nuclear a
Manufacturing power reactors, Compapgr at WI fasstown.
New Jersey 88 08 Thermal Stresses in Pfptng Supple. ment 2 Connected to Reactor Coolant 8/4/88 All holders of OLs Systems or cps for 11ght-k water-cooled nuclear power reactors.
88-0g-Thimble Tube Thinning in 7/26/88 Westinghouse Reactors All holders of OLs orCPsforydesigned nuclear power reactors that utilize botton mounted instrumentation.
84 08 Themal Stresses in Piping Supplement 1 Connected to Reactor Coolant 6/24/88 All holders of Ols Systems or cps for light.
water-cooled nuclear power reactors.
88-08 Thermal Stresses in Pfptng Connected to Reactor Coolant 6/22/88All holders of Ols Systems or cps for Ifght-water-cooled nuclear power reactors.
88-05 Nonconforming Materials Supple. ment 1 Supplied b'r Pfptng Supplies 6/15/88 All holders of OLs Inc. at Fohsom and West Jersey. New Jersey,
or cps for nuclear Manufacturing power reactors.
Company at W111taastown.
New Jersey 88-07 Power Oscillations in toiling Water Reactors (8WRs) 6/15/88 All holders of OLs or cps for 8WRs.
OL = OperatinC License CP = Construction Peruft 1
g 1
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i e
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1 UNITED STATIS NUCLEAR RtGULATORY CO*155!0W 0FFICE OF WUCLEAR REACTOR REGULATION WA$MINGTON, D.C.
P055C April 26, 1988 NRC INr0 PEAT 10N NOTICE NO. 68 19:
00E$710hAtLE CIRTIFICATION OF CLA55 It COMPONENTS Addressees:
All holders of operating licenses or construction Pemits for nuclear power reactors.
o
_Furpose:
This infomation notice is being provided to alert addressets to a possible problem with the certification of Class It components furnished by Planted Paintenance Systers (PMS) of Pt. Vernon, Illinois.
It is expected that recipients will review the inferration for applicability to their facilities l
and consider actions, as appropriate, to avoid similar problems. However, f:
suggestions contained in this information notice do not constitute NRC
(
requirements; therefore, no specific action or written response is required.
Description of Circumstances:
On April 1, IPFt. Wolf Creek Nuclear Operating Corporation (WCN0C) submitted a written 10 CFR Part 21 Notification to NRC Region !Y concerning 60 Class It fuses that had been procured from PMS. One of the requirements o' the purchase order (P0) issued to PMS was that the P0 items were to be supplied in accord.
ance with the requirements of a specific fuse qualification specification for Class 1[ ecuipment.
This specification contained detailed requirements including materials, environnental qualification, seismic qualification, and inspection /
test recuirements. The PMS Certificate of Compliance supplied with the order certified Dat all of the procurement document requirements had been met and no deviations from the reoutrements had been identified.
The fuses were placed on hold by WCN0C because a required Quality Department surveillance had not been performed. A subsequent WCN0C surveillance revealed that the records in PM5's possession did not support the statement on the PMS l
Certificate of Compliance that all P0 requirements had been met. Qualificatter.
specification requirements were not covered by PM5 quality assurance records with respect to infomation on environmental cualification, radiation levels.
I and seismic qualification.
In addition, it could not be established that a l
required continuity / resistance check of each fuse had been performed before the fuses were shipped.
O.
l 8804220217
i IN 8819 April 76.1988 i
Page P of P Disevssion:
The WCNOC 10 CFR Part 71 notification has broupht into question the validity of the Certificate of Compliance issued by PMS for Class It fuses that they supplied. Accordingly, licensees may wish to review Class lf component pro-curemnts from this vendor to ensure that appropriate bases exist for the use of the components.
t No specif,1c action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical contact listed below or the Regional Administrator of the appropriate regional office.
M[ b' i
Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical
Contact:
Joseph J. Petrosino, NRR
(.,
(301) 492-0979
Attachment:
List of Recently Issued NRC Information Notices l
4 i
Attachment 1N 88-18 April 26 1988 i
Pete1of1 L15T OF RECENTLY Il$UED NPC INFORMATION NOTICES TnTomation case of Notice No.
Sub.4ec t Issuance issued to c
88 18 Malfunction of Lockbox on 4/25/88 All WRC licensees Radiography Device authorized to manufacture, distribute, and/or operate radio.
graphic exposure devices.
88 17 Surr.ary of Responses to NRC 4/22/88 All holders of OLs Bulletin 87 01, ' Thinning of or cps for nuclear Pire 6'a11s in Nuclear Power power reactors.
i Plants" 86 16 Identifying Waste Generators 4/??/88 Radioactive weste in Shipments of Low t rvel collection and Paste to Land Disposal service company Facilities licensees handling prepackaged waste, and licensees operating low level waste disposal facilities.
88 15 Availability of U.S. Food 4/18/88 Medical. Academic, and Drug Adn.inistration and Coerercial (FDA). Approved Potassium licensees who pessess lodide for Use in Energencies radioactive iodine.
Involving Radioactive ' odine 88-14 Potential Problems with 4/)8/88 All holders of OLs Electrical Relays or cps for nuclear Power reactors.
88 13 Water Hansner and Possible e/18/88 All holders of OLS Piping Damage Caused by or cps for nuclear Misapplication of Kerotest power reactors.
Packless Metal Diaphragm Globe Valves
' 88 12 Overgressing of tiectric 4/12/88 All holders of OLs Motor Bearings or cps for nuclese power reactors.
4 OL
- Operating License CP = Construction Pennit
's i
UNITED STATES WUCLEAR REGULATORY C0*!$5!0N OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON. 0.C.
20555 i
June 3. 1988 t
I NRC INFORMATION NOTICE NO. 88 35:INADE00 ATE LICENSEE PERFORMED YENDO l
Addressets:
All holders of operating licenses or construction Pemits for nuclear poner i
reactors.
Purpose:
probletrs resulting from inadequately perfomed licensee facilities which may not reveal the vendor's' fa i
portions of its quality assurance (0A) program.ilure to implement critical It is excetted that recipients i
will review this infomation for applicability to their facilities and consider actions, as appropriate, to avoid similar problems.
However suggestions contained in this information notice do not constitute NRC requirementsi therefore, no specific action or written response is required, i
k Descriotion of Circumstances:
NRC reviews during Januar Compan. Incorporated (PSI)y-April 1988 of documents obt plies of Folsom E
that indicate potential generic safety iglications with pip flanges supplied by PS! and WJM to nuclear power plants.
IThis issue is by Piping Supplies. Inc. at Folsomdiscussed further in NRC Bulletin No. 8 Company at Williamstown New Jersey,.")New Jersey and West Jersey Manufacturing reports (CMTRs), certificates of cogliance, and hea i
during the perfomance of its own audit. believes the inconsistencies fo The NRC An NPC inspection on June 10-15 and June 24-28, 1985 at the Nuclear En that did not confom to the NES QA program implementat i
Part 21 violation (reference NRC inspection report 90901018/8501). The NRC perfomed these inspections at the request of the l
of canisters to collect. transport, and store the Three Mile Island Unit-2 core debris.
of the implementation of the OA program at the NES faci North Carolina because of the collective imt4ct of the numerous from the vendor's program.
and Bechtel Power Company had,iointly performed surveillance a On the 8805270306 e
IN A8 35 June 3, 1988 Page ? of 3 cover sheet of the report the results of the surveillance were sumarized as unsatisfactory. However, no nonconformances were issued to NES, nor was the i
vendor requested to perfom any corrective actions other than to develop a specific non destructive testing examination procedure which, required by contract, shovid have already been established.
An NRC inspection on November 16 20, 1987 at the Nuthem International Indus-tries, Incorporated (N!) facility in Mount Vernon Illinois identified six nonconfoming areas of implementation failures (re,ference NRC inspection report 99900779/87 01).
Considering a nutter of identified problems, substantiated allegations, and the breakdown of the 0A program in certain areas, the NRC became concerned about the validity of N!'s certificates of conformance.
Before the NRC audit, inspections had been perfomed by several licensees.
NRC's review of the audit reports produced by licensees indicates that only one licensee identified any deviations, and that that licensee failed to correctly interpret the audit findings.
An NRC inspection on August ?S-?9, 1986 at the Amerece Corporation facility in Union, New Jersey (Amerece is the manufacturer of Agastat 7000 teries timer
?>
relays) identified that the vendor had failed to adequately establish and implement a OA program in several areas.
One violation of 10 CrR Part 21
[E and nine nonconfomances to the vendor's OA program were identified freference
(
NRC inspection report 99900?96/86 01).
The NRC inspection found, in part, that "The failures are indicative of a lack of management involvement in the Quality assurance functions...."
A review of several audits previously perfomed by licensees indicated that licensees had identified few or no problems with either the vendor's QA program or its implementation.
An NRC inspection on July 11 12 and August 5-9, 1985 at the Air Balance incor.
porated facilities at Westfield, Massachusetts and at Wrens, Geor the vendor had failed to (4) establish a 10 CFR Part 21 program, gia found th implement a OA program, and (c) obtain QA program support from management. Two violations of 10 CFR Part ?! and 17 nonconfoming items were identified f reference NRC inspection report 99901005/85 01). Again, a review of several audits that licensees had previously perfomed indicated that licensoes had identified few or no problems.
~
A recent NRC inspection of Elgar Corporation identified several concerns with the vendor's QA program.
These include 1) failure to perfom independent
' design review (1? of 55 engineering change notices audited were prepared, reviewed, and approved by the same individual), 2) failure to ensure that the cumulative effects of multiple design changes on an individual drawing did not adversely affect the ability of the eovipment to perfom its intended function, 3) failure to maintain previous versions of revised drawings, di failure to establish duties and authorities of engineering personnel, and 5).
failure to perfom 10 CFR Part 21 evelvations of identified design errors and deviations. Again, a review of audits licensees had previously performed indicated that these concerns were not identified.
m
.n..
e IN 88 35 June-3. 1988 Page 3 of 3 Delaval. Inc. (Delaval) notified the NRC of potential pr engine control devices in the air start lube 011. jacket water, and crankcase systems in their OSR or D$RV standby diesel generators.
i of reported failures. Delaval performed an audit of the manufacturer of these components. California Controls (Calcon) which identifted a concern regarding the implementation of the Calcon OA program. Delaval concluded that there was i
The NRC staff is not certain as to whether any) license Calcon.
_ Discussion:
The NRC is concerned that the inspections discussed above appear to indicate that licensees may not be~ adequately implementing their established 10 CFR Part 50 Appendix B program requirements, particularly Criterion VII.
are reminded that it is their responsibility to ensure, by such actions asLicensees 1
verifying the validity of and the basis for such manufacturer / vendor records j
as CMTRs. certificates of compliance, and heat treat records, that purchased equipment and components are able to perform their intended functions.
sees are further reminded that, as discussed in 10 CFR Part 50 Appendix 8 Licen-i 1
Criterion VII, "the effectiveness of the control of quality by contractors consistent with the importance, complexity, and quantity o se rvices. " On the ba that, in some cases. sis of the NRC inspections discussed here, it appears licensee audit efforts have not been effective.
believes that additional attention in this area may be appropriate.
The NRC No specific action or written response is required by this infonnation notice If you have any Questions about this matter, please contact the technical contact listed below or the Regional Administrator of the appropriate regional office.
& E(m'.
Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical
Contact:
Joseph J. Petrosino. NRR (301) 492-0979
Attachment:
List of Recently Issued NRC Information Notices
-*]
I.
UNITED STATES NUCLEAR REGULATORY CO* 15$10N 0FFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C.
20555 July 8, 1988 NRC INFORMATION NOTIC[ NO. 88 46: LICENSEE REPORT OF DEFECTIVE REFURBISHED CIRCUIT BREAVERS Addressees:
All holders of operating licenses or construction pemits for nuclear power reactors.
_ Purpose :
.This information notice is being provided to alert addressees of licensee reported information that defective refurbished electrical equipment, such as circuit breakers (CBs), may have been supplied to nuclear power plants.
to their facilities and consider actions as appropriate, to avoi problems.
However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances:
Pacific Gas and Electric Compan purchase order for 30 new, non.y (PG&E) has infomed NRC that it placed a safety-related, molded-case, KHL 36125-type CBs manufactured by the $quare D Company (Square D) with a local electrical distributor.
tions at PG&E's Diablo Canyon Nuclear Power Plant.These CBs were int According to PG&E, the distributor in turn placed the order with a local sup-plier who bid the lowest price and promised the quickest delivery.
were delivered directly to the Diablo Canyon plant by the supplier; the dis-The CBs tributor did not have an opportunity to inspect the CBs.
Square D aware of vintage KHL 36125-type CBs.the purchase order, questioned its failure to receiv With PG&E's permission, Square D inspected the CBs and detemined that PG&E had been given refurbished, rather than new, CBs.
Square D tested and performed detailed examinations of the CBs, and the results repoited by PGtE follow.
A.
Physical Examination The yellow side. labels used on the CBs were suspect in that the CB model The CBs departed from normal appearance in other respect 8807080006 o
IN 88 46 July 8, 1980 Page 2 of 3 i
The individual CB cases and each of the Cl components appeared to
$quare D products; however, the individual CBs incorporated comp of different years of manufacture.
opened and reassembled.
Each CB bore evidence of having been L
B.
_ Electric Testino_
m Square D subjected the CBs to five electrical tests.
i for all of the tests, and several of the CBs wtre ou None of the C8s each of the tests.
stances in which they are designed to trip.At least four of the CBS f t
Discussion:
In the past, there have been instances in which licensees purchased co grade components, such as CRs, relays, trip units, and other electric nents, from electrical distributors and have received components that did no meet the original purchase order requirements.
information indicating that the problem of surplus or defective refurNRC has re Electric, Westinghouse, ITE, Cutler Hantner, and Sylvan
, General The electrical suppliers involved in refurbishing and sales of circuit bre including the Diablo Can California corporations. yon, Square O circuit breakers, apparently include five These companies are (1) General Circuit Breaker &
Electric Suppl national, Inc.y, Inc., (2) NLC Electric Supply Co., Inc., (3) Pencon Inter-
, doin California Breakers,g business as General Magnetics / Electric Wholesale, (4)
I Inc., and (5) Anti-Theft Systems, Inc., doing business as ATS Circuit Breakers and as AC Circuit Breaker-Electrical Supp"y.
NRC has an investigation and vendor inspection in progress at the nies.
On the basis of the information developed to date, a preliminary list of customers of the five companies including a list of nuclear utilities available) is provided in Attachment 1 contains a. list of original equipment manufacturers whose names my.
I equipment sold as new equipment.
have been used on surplus or refurbished 2 is only preliminary and is provided to assist licensees in rev L
potential of having procured suspect electrical equipment at their facilities Licensees are reminded of the requirements to ensure that procured the relevant ~ specifications and codes and are suitable for the inten cation.
Licensees should consider, as a matter of prudence materials, equipment, and components.of and to verify with their auth Licensees may meet these re by effectively implementing their quality assurance (QA) programs,quirem in the areas of vendor evaluations, vendor survalliances, receipt inspe particularly bench tests, and post-installation tests.
l
--4 IN 88-46 July 8, 198P l
Page 3 of 3 NRC is gathering additional inforuation to detemine wha neces sa ry.
of the situation as soon as possible.
to followup on this inforination notice when the NRC has sufficient inform to define requirements.
No specific action or written response is required by this inf cal contacts listed below or the Regional Administrator of the appropriate regional office.
fe Yos Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts:
K. R. Naidu NRR (301) 492-0980 Jaime Guillen. NRR (301) 492-1170 Attachments:
1-Preliminary List of Customers (Intermediate Suppliers) of Suspect Electrical Equipment
?.
Preliminary List of Original Equipment Manufacturers Phose Names May Have Been Used on Surplus or Refurbished Equipment Sold as New Equipment 3.
List of Recently Issued NRC Infomation Notices e
j
. _ ~
1N 88 46 July 8, 198P Page 1 of P PREllMINARY LIST OF CUSTOMERS (INTERMEDIATE SUPPLIERS) 0F SUSPECT ELECTRICAL EQUIPMENT Organization location NuclearUtiliti (if available Westinghouse Electric St. Louis, P0; Boston, MA; Supply Co. (WESCO)
Boise, 10; Atlanta, GA; Charleston, SC; Panama, FL; Santa Cla.a, CA; Fresno, CA; Sacramento, CA; Shreveport, LA; Green Bay, Wl; Elk Creek, IL; Albuquerque, NM; Mobile, AL; Ft. Worth, TX; Baton Rouge, LA; Birmingham, AL; East Hartford, CT; Kokomo IN; Jackson, MS; Milwaukee, WI; Beaumont, TX; Nashville, TN; Skelton, WV; Albany, NY; Hartford, CT; Portland, ME; St. Paul, MN; Minneapolis, MN; other locations Power Conversion Huntington Beach, CA Rockwell International Los Angeles, CA Arkansas Power and Light Little Rock, AP ANO Southern California San Clemente CA; SONGS Edison other locations Phoenix Electric Phoenix, AZ Rensenhouse Electric Topeka, KS Breaker and Control Houston, TX General Electric Company Baltimore, MD; Houston, TX; Landover, M0; Chantilly, VA; Emeryville, CA; Elmhust, IL Southern Electric Alexandrie, LA Supply Company Cleveland Electric Company
IN 88 46-July 8, 1983 Page t of t PRELIMINARY 11$7 0F CUSTOMER $ (INTERMEDIATE SUPPLI 0F SU$PECT ELECTRICAL EQUIPMENT Organization Location Nuclear Utility (if available)
$tokley Enterprises Norfolk, VA Taylor Electric Company Portland, OR Graybar Ventura, CA; Atlanta, GA Hughes Aircraft El Segundo, CA Houston Electric Houston, TX Distribution Company ITE Electrical Products Atlanta, GA; knoxville, TN Knudson Corporation Los Angeles, CA
-Georgia Power Company Milledgeville, GA i
l
' 7" I
IN 88 46 p
July 8. 1982
[
Page 1 of 2 l
PREl.!MINARY LIST OF ORIGINAL EQUIPMENT -
MANUFACTURERS WHOSE NAMES MAY HAVE BEEN USED ON SURPLUS OR REFURBISHED EOUIPMENT $0LD AS NEW EQUIPPENT Manufacturer Model Number Equipment Description Square D B19.5; B22 Heater for overload relay General Electric 12HGA11552 Auxiliary relay Exide Company NX400 Spectro Inc.
V00014 Mercury lamps
'Bussman Company-REN15 15-amp 250 V fuse Bussman Company N05-30 30-amp 600-V fuse (unknown)
FSN 5925-628 0641 Circuit breaker Westinghouse 08-50 Trip unit Westinghouse DB-25 400 amp circuit breaker Westinghouse HKB3150T Trip unit Westinghouse KB3250F Frame -
Westinghouse FB3020 Circuit breaker Westinghouse FB3070 Circuit breaker Westinghouse-FB3050 Circuit breaker Westinghouse EHB3040 Circuit breaker
- Westinghouse EHB3025 Circuit breaker
-Westinghouse LBB3125 Circuit breaker Westinghouse HKA31250 Trip unit Westinghouse JA3200 Circuit breaker Westinghouse EHB2100 Circuit breaker
' Westinghouse CAH3200 Circuit breaker i
~
j-3
'4 Attachment ?
IN 88 46 July 8, 1988 Page 2 of 2 PRELIMINARY LIST 0F ORIGINAL EQUIPMENT MANUFACTURERS WHOSE NAMES MAY HAVE BEEN USED ON $URPLUS OR REFURBISHED EQUIPMENT SOLD AS NEW EQUIPMENT Manufacturer Model Number Equipment Description Westinghouse 225N Navy trip units ITE EF-38100 100-amp circuit breaker General Electric AK-2-75-3 Circuit breaker General Electric AK-2 Circuit breaker General Electric AK-1-50 circuit breaker General' Electric AK-1-75 Circuit breaker General Electric B; TD0; TFil Circuit breakers General Electric TCVYFS Circuit breaker ITE ET; KA Circuit breakers Cutler Hamer Circuit breakers finsco/Sylvania Circuit breakers Bryant Circuit breakers Murry.
Circuit breakers Federal Pacific Electric-Circuit breakers Company l
e
__.__.1--.
~ - - - - - - ~ - - - - " - - ' - ' - " ' ~ ' ^ ^ ' ~ ~
~
1.-
i L
IN 88 46 L
July 8, 1988 Page 1 of 1 l
a L
LIST OF RECENTLY !$$UED NRC INFORMATION NOTICES Infomation Date of Notice No.
Subject Issuance Issued to L
88 45 Problems In Protective 7/7/88 All holders of OLs Relay and Circuit or cps for nuclear Breaker Coordination power reactors.
88-44 Mechanical Binding of 6/24/88 All holders of Ols Spring Release Device or cps for nuclear l
in Westinghouse Type power reactors.05-416 Circuit Breakers 88-43 Solenoid Yalve Problems 6/23/88 All holders of OLs or cps for nuclear power reactors.
88-42 Circuit Breaker Failures 6/23/88 All holders of OLs Due to Loose Charging or cps for nuclear Spring Motor P'ounting Bolts power reactors.
(.
88-41 Physical Protection 6/22/88 All holders of OLs Weaknesses Identified or cps for nuclear Through Regulatory Ef-power reactors.
fectiveness Reviews (RERs1 88-40 Examiners' Handbook for 6/22/88 All holders of OLs Developing Operator or cps for nuclear Licensing Examinations power reactors.
88 39 LaSalle Unit 2 Loss of 6/15/88 All holders of OLs Recirculation Pumps With or cps for BWRs.
Power Oscillation Event 88-38 Failure of Undervoltage 6/15/88 All holders of OLs Trip Attachment on General or cps for nuclear Electric Circuit Breakers power reactors.
88 Flow Blockage of Cooling 6/14/88 All holders of Ols Water to Safety System or cps for nuclear Components power reactors.
88-36 Possible Sudden Loss of RCS 6/8/88 All holders 'of Ols Inventory During Low Coolant or cps for PWRs.
Level Operation OL = Operating License CP = Construction Pemit
y; as
.l:
'O UNITED STATE $
NUCLEAR REGULATORY COP 9115$10N 0FFICE OF NUCLEAR REACTOR REGULATION idA$HINGTON. 0.C.
20555 JULY 21 1988 Npt INFORMATION NOTICE NO. 88-46. SUPPLEMENT 1: LICENSEE REPORT OF DEFECTIVE REFURBl$HED CIRCUlf BREAKERS Addressees:
All holders of operating licenses or construction permits for nuclear power reactors.
Purpose:
This infomation notice supplement is being provided to present additional infomation regarding customers of the five California electrical-suppliers discussed in NRC Infomation Notice (IN) No. 88-46 that may have supplied defective refurbished electrical equipment, such as circuit breakers (CBs),
to nuclear power plants.
It is expected that recipients will review this f
information for applicability to their facilities and consider actions, as
(
appropriate, to avoid similar problems.
However, suggestions contained in this infomation notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances:
IN 88-46 discussed a report by Pacific Gas and Electric (PG4E) that defective refurbished C8s were suoplied to PG&E's Diablo Canyon Nuclear Power Plant by a California electrical supplier. The IN listed four other California' companies involved in refurbishing and supplying possibly defective circuit breakers to nuclear power plants.
Sn addition, the !N provided a preliminary list of customers of the five companies and a list of original equipment manufacturers whose names may have been used on surplus or refurbished equipment sold as new equipment obtained during NRC investigations and vendor inspections in progress at the subject companies.
Discussion:
The NRC has obtained additional infonnation from its inspections and investi-gations related to this issue. Attachment 1 provides a list of shipments of circuit breakers to nuclear power plants or nuclear utilities by the subject electrical suppliers.
This list was compiled based on a partial review of records obtained from the live California electrical suppliers discussed in 1H 88-46. The majority of the sales were through distributors; however, direct sales and shipments to nuclear utilities have been identified.
Except for certain sales to San Onofre for safety-related use, the safety classifi-cation of the electrical equipment as sold appears to be commercial grade.
l 8807200162
=
m-i,
i..
IN 88-46. Supplement 1 July 21 1988 Fege t o,f t The NRC is continuing its investigations and review of records on this issue and, if warranted, a further generic comunication will be issued.
No specific action or written response is reevired by= this information notice.
If you have any questions about this matter, please contact one of.the techni-cal contacts listed below or the Regional Administrator of the appropriate regional office, i
i s
et Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts:
K. R. Naidu, NRR (301) 492 0980 Jaime Guillen. NRR (301)492-1170
(-
Attachments:
- 1.. Shipments of. Circuit Breakers to Nuclear Power Plants or Nuclear Utilities' 2.
List of Recently Issued HRC Information Notices i
i I
e 0
a
IN 88-46, Supplement 1 July 21,f 4 1988 Page 1 o SHIPMENTS OF CIRCU1T BREAKERS TO NUCLEAR POWER PLANTS OR NUCLEAR UTILITIES The following list represents shipments of circuit breakers to nuclear plants or utilities from five suppliers in the Los Angeles area.
The majority were sold through distributors; however, direct sales to the utilities are identi-fied.
Except for the direct sales to San Onofre, classification of the circuit breakers as sold appears to be conmercial grade.
Plant or Sold to and l
2 Utility items (Oty)
Date Purchase Order Nos, invoice Company Palisades W EB1020 (?)
9/14/87 WESCO Lansing, MI I 10995 ATS P03255-87089 Harris ITE EF3B125(2) 7/9/88 WESCO, Raleigh, NC WO 24781 CAL BKR ITE EF3B125(2) 3/2/88 P0s 053645-00171 WO 25377 CAL BKR i
1 ITE EF3B125(f) 3/14/88 DS3645-08047 WO 25811 CAL BKR 3
Dresden W FA 2100 (2) 12/21/87 WESCO Elmhurst, IL
! 14174 HLC Quad Cities W EH 2050 (3) 1/18/88 WESCO Davenport, IA I 14673 HLC l
/
D/S$106-259401 3
(
W EH2070 (1) 3/10/88 WESCO Davenport, IA Unknown GEN BKR 505106-M031010 Connecticut W HFB 3050 (3)
C/12/87 Economy Elect I 12585 HLC Yankee l
Manchester, CT D508127 995428 Mark 860590 W STARTER CONTROLS 6/25/87 06157-730176 1 11752 A200H1CAC(13)
A201K1CA (8)
A201K2CA (4) l AN13A (6)
W HFD 3020 (12) 6/16/87 06167-740072
! 11760 Braidwood W MA3600 (1) 7/15/86 WESCO Elmhurst, IL I 07721 L
w/ bell alann Ginne W FA3125 (3) 9/26/84 WESCO Rochester, NY I 30501 GEN MAG
{
93095 l
W EA2090 (3)
! 30371 W FA3125 (3)
Clinton 50 00220 (10) 7/18/84 WESCO Peora, IL
! 29708 (Baldwin Associates) 91586 Rancho Seco W JB3100 (2) 8/8/84 WESCO Socramento, CA I 29971 1
(SMUD)
W/LINE & LOAD LUGS 90629 FPI NEF433030 (1) 3/6/87 SMUD I 27090 GEN BKR i
RN870356713 1
i
3 ~,
IN 88-46 Supplement 1 July 21,,1988 Page 2 of 4 Plant or Sold to and Utility items (Otyi Date Purchase Order Nos.
Invoicol I
_ Company SONGS GE TED134030VL (1) 6/10/88 Southern ca. Edison i 102174 ECD 88068300 IT 8QPB030 6/9/88 8WO68023 1 102193 ECD Lilco FPE NF631100(2) 6/12/86 Gra
! 7297 HLC NY(ybarHauppauge, 540-BLP901363)
Mississippi W F2020 (1) 1/30/86 WESCO, Mobile, AL I $585 HLC Power Co.
DS-3725 860126 PG&E VEH2100(1) 3/5/86 AMFAC, Stockton, CA ! 6076 HLC D7232 8980 FPE NE224060(2) 4/11/88 CED. San Luis Obispo,! 15703 HLC CA 7605087444D WHMC3800F(1) 1/28/88 7605-D763670
! 14829 HLC BMC800 (1 LOT)
LUGS (3)
/
ITEEE3B050(1) 11/3/87 76050-761160 1 13783
(
EE30030(1)
W E83050-(1) 10/2/87 7605-D2091900 1 13333 FPE NE224100 (2) 5/13/88 7605-0879760
! 16309 Detroit Ed. IT EH38100 (1) 3/18/88 Detroit Ed. Monroe I 11510 ATS Pwr plant (190501)
SD989316(2) 11/23/87 Splane Electric WO 02160 ATS Detroit,M1(111275)
Ceco IT EF38070 6/3/87 Graybar Melrose Pk,
! 10684 ATS I
IL (328M502114CS)
W EH2070 (4) 12/22/87 WESCO Davenport, IA I 31399 GEN BKR WS$106 258143 Consumers WHOEA2030(1) 3/30/88 WESCOLansin9,MI i 11530 ATS Power Co.
053255-14766 Southern ITFJ38225(1) 4/22/88 SCE Construction
! 34435 AC BKR Cal. Edison Forces (117053L)
! TEE 3B070(3) 117055L 1 34436 EE2B100 (1)
EE28050(2)
EE2B030(1)
GE TEF134015 6/15/78 GESCO El Monte'. CA
! 11734 HLC W EB2030 (2) (1) 5/2/88 Southern ca. Edison 1 101586 ECD H1238007 SD SBW 12 1/28/88 20048013 1 100384 CONTACTOR(1)
SDLO-3CONTACTOR(1)
YEPCO ITEF3H050(1) 6/9/88 Electrical Supirs WO 28849 CAL BKR
?
.r IN 88 46, Supplement 1 July 81, 1988 Pa9e 3 of_4 Plant or
$old to and I
2 Utility items (Oty)
Date Purchase Order Nos.
Invoice, Company Carelina 1T EF38125 (2) 2/9/88 WESCO Raleigh, NC WO 24781 CAL BKR Power 8 053645-80171 Light EF38125(2) 2/26/8C WO 25377 EF38040(6) 3/11/88 053645 08047 WO 25811 Omaha Pub. GE THEF136ml100(2) 1/22/85 GESCO Omaha, NE I 31695 GEN MAG Pwr Dist 86607 Boston Ed. W EH2050 (1) 3/18/85 WESCO Boston, MA I 32348 GEN MAG Arkansas IT E428020 (2) 1/28/88 Treadway Elect.
Little Rock, AR L19ht 12170 IT QJ2B200 (2) 1/28/88 12150 WO 24373 GE TEB122015WL (1) 1/28/88 1216D WO 24376 IT OJ2B200 (2) 2/2/88 12450 WO 24505 W MCP331000R-(4) 2/17/88 13290 WO 25104 C
IT OJ2B200 (2) 2/24/88 1357D WO 25268 GE TF81320904 (1) 3/1/88 13910 WO 25485 W MCP431550CR (2) 3/1/88 13920 WO 25529 W 8AB3060H (1) 3/11/88 14640 WO 25913-5DFAL365016M(2) 3/31/88 15890 WO 26447 IT OJ2B200 (2) 4/8/88 16370 WO 26707 a
1T OP18020 (2) 5/6/88 1754D WO 27676 a
GETE111015(1) 5/18/88 18050' WO 28164 IT OJ2B200 (2) 6/7/88 1869D WO 28757 GE TED1340604 (1 6/16/88 1930D WO 29038 W 6560148G03 (1) )
3/15/88 1480D
! 52997 MOTOR OPERATOR IT OJ28200 (2) 6/7/88 18690 1 53437-GE TE8122050WL (1) 6/30/88 19950
! 54164 GETHED136100R(1)11/30/87 9975D WO 22497 GE TE0126050 (1) 7/15/87 93240 WO 18318 a
IT QJ38200 (3) 7/31/87 93690 WO 18774 17 OJ28200 (3) 7/31/87 93690 WO 18774 GE THE01360604 (2) 8/7/87 94300 WO 19041
=
IT 003B200-(1) 8/13/87 9473D WO 19245 GE TNGB2120 (3) 8/7/87 9430D WO 19041 IT OJ3B?00 (6) 8/16/87*9424D WO 19042 1T QJ2B200 (10) 8/16/87 9424D WO 19042
j;,
IN 88 46 Supplement 1 July 21, 1988 Page 4 of 4 Plant or Sold to and i
Utility items (Oty)
Date Purchase Order Nos.. InvoiceI 2
Company Florida IT JL3B400 (2) 12/23/87 149278 WO 23293 CAL BKR Power Corp.
Houston IT HE99040 (4) 8/20/87 Aucoin & Miller WO 19474 CAL BKR Power &
Houston, TX 0153721 Light L
I 1
-Notes
! - invoice; WO - work order 2' ATS - ATS Circuit Breakers, Inc CAL BKR - California Breakers, Inc.
I ECD - Electro Components Distributors GEN BKR - General. Circuit 8reakers and Electrical Supply, Inc.
GEN PAG - General Magnetics / Electric Wholesale l
HLC - HLC Electric Supply Co.
[
AC BKR - AC Circuit Breaker - Etectrical Supply 3 Shipped to final destination from the distributor l
l
)
1 IN 88 46, Supplement 1 July 21, 1988 Page 1 of 1
.l L!$7 0F RECENTLY !$$UED NRC INFORMATION NOTICES Information Date of Notice No.
Subject issuance issued to 88-51 Failures of Main $ team 7/21/88 All holders of OLs Isolation Yalves or cps for nuclear power reactors.
88-50 Effect of Circuit 7/18/88 All holders of OLs Breaker Capacitance or cps for nuclear on Availability of power reactors.
Emergency Power 86-49 Marking, Handling, 7/18/88 All holders of OLs Control, Storage and or cps for nuclear Destruction of Safe-power reactors and guards Infomation all other licensed activities involving a fomula quantity C.
of special nuclear seterial.
88-48 Licensee Report of 7/12/88 All holders of OLs Defective Refurbished or cps for nuclear Valves power reactors.
88-47 Slower-Than Expected 7/14/88 All holders of OLs Rod-Orop Times or cps for PWRs.
88-46 Licensee Report of 7/8/88 All holders of OLs Defective Refurbished or cps for nuclear Circuit Breakers power reactors.
88-45 Problems In Protective-7/7/88 All holders of OLs
. Relay and Circuit or cps for nuclear Breaker Coordination power reactors.
88-44 Mechanical Binding of 6/24/88 All holders of OLs Spring Release Device or cps for nuclear in Westinghouse Type power reactors.
DS-416 Circuit Breakers 88-43 Solenoid Yalve Problems '
6/23/88 All holders of OLs or cps for nuclear power reactors.
OL = Operating License CP = Construction Permit
1-1
)
UNITED STATES
{
NUCLEAR REGULATORY COPNIS$10N s
c 0FFICE OF NUCLEAR REACTOR REGULATION i
July 12, 1988 NRC INFORMATION NOTICE NO. 88 48:
LICENSEE REPORT OF DEFECT!YE REFURBISHED VALVES Addressees:
All holders'of operating licenses or construction pemits for nuclear power reactors.
Purpose:
This information notice is being provided to alert licensets to potentiel problems with refurbished valves.
It is expected that recipients will review this information for applicability to their facilities and consider action, as appropriate, to avoid similar problems.
However, suggestions contained in this 4
information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances:
In Ap. il 1988, Pacific Gas and Electric (PG&E) informed the NRC about a poten.
tial problem concerning-Vogt 2-inch valves (Vo i
were leaking steam at the bonnet and packing. gt Figure No. SW 12111), which
.t According to PG4E, the valves were purchased from a local supply company in May 1986 and installed in non.
safety-related applications. Although the supply company is now out of business, additional infomation was obtained by PGLE that indicated that the valves, although'su Vancouver, oplied as new, were actually shipped from CMA International of Washington, a valve salvage supply house.
Henry Vogt Company exaNned the valves at the Diablo Canyon plant and detemined that it had l
not manufactured the valves.
The valves at Diablo Canyon had square flanges,
.and all Vogt-manufactured valves have round flanges.
Discussion:
NRC again stresses the importance of the icensee's role in ensuring that procurement activities for both safety-related and non-safety-related com.
ponents and materials are given attention consnensurate.with their importance.
Had an adequate review of the-source of the valves been performed, this problem would'have-been identified and salvage valves would 'not have been installed.
On the basis of discussions with Vogt representatives, these valves would 'ot n
be appropriate as replacement valves in safety-related applications. These valves are full-port design; that is, the valve port is the same size as the 8807120291 e
4-w
+
3, i
IN 88-48 July it. 1988
\\
l Fage t of t l
l inside diameter of the pipe.
Vogt valves designed and sold for safety related use are standard-port design; that is, the valve port is slightly smaller than the inside diameter of the pipe.
Vogt representatives were not aware of any full port design valves sold for safety-related applications to nuclear power plants.
No specific action or written response is required by this informstion notice.
If you have any questions about this matter, please contact the technical contact listed below or the Regional Administrator of the appropriate regional office.,
Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Te'hnical
Contact:
Edward T. Baker. NRR c
(301) 492 3221
Attachment:
1.ist of Recently Issued NRC Information Notices e-9
_w,.,,,,,,,_
~
Attachment IN 88-48 July 12, 1988 Page 1 of 1 LIST OF RECENTLY !$5UE0 NRC INFORMATION NOTICES Infomation Date of Notice No.
Sub.iect Issuance issued to 88 47
$10wer-Than-Expected 7/14/88 All holders of OLs Rod Drop Times or cps for PWRs.
88 46 Licensee Report of 7/8/88 All holders of OLs Defective Refurbished or cps for nuclear Circuit Breakers power reactors.
88-45 Problems in Protective 7/7/88 All holders of OLs Relay and Circuit or cps for nuclear Breaker Coordination power reactors.
88-44 Mechanical Binding of 6/24/88 All holders of OLs Spring Release Device or cps for nuclear in Westinghouse Type power reactors.
D5 416 Circuit Breakers 88-43 Solenoid Valve Problems 6/23/88 All holders of OLs or cps for nuclear power reactors.
88-42 Circuit Breaker Failures 6/23/88 All holders of Ols Due to Loose Charging or cps for nuclear Spring Motor Mounting-Bolts power reactors.
88-41 Physical Protection 6/22/88 All holders of Ols Weaknesses Identified or cps for nuclear
' Through Regulatory Ef-power reactors.
fectiveness Reviews-(RERs) 88-40 Examiners' Handbook for 6/22/88 All holders of OLs Developing Operator or cps for nuclear Licensing Examinations power reactors.
88-39 LaSalle Unit 2 Loss of 6/15/88 All holders of Ols Recirculation Pumps With or cps for BWRs.
Power Oscillation Event 88-38 Failure of Undervoltage 6/15/88 All holders of OLs Trip Attachment on General or cps for nuclear Electric Circuit Breakers power reactors.
OL = Operating License CP = Construction Pemit G
,,.,,i,.
UNITED STATES NUCLEAR REGULATORY COMMISS!9N OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C.
20555 December 16, 1988 NRC INFORMATION NOTICE NO. 38-97:
POTENTIALLY SUBSTANDARD VALVE REPLACEMENT PARTS Addressees:
All holders of operating licenses or construction permits for nuclear power reactors.
Purpose:
This information notice is being provided to alert addressees about reports concerning the manufacture and distribution of valve replacement parts for Masonellan-Dresser Industries (M-D) valves that were determined not to be genuine M-D parts and possibly are substandard.
It is expected that recipi-ents will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems.
However, sug-gestions contained in this information notice do not constitute NRC require-ments; therefore, no specific action er written response is required.
Description of Circumstances:
On.0ctober 21,19C6, Consumers Power Company (CPCo) submitted a 10 CFR Part 21 report to the NRC regarding valve internals for M-D valves that were found not to be manufactured by an authorized M-D manufacturer. CPCo reported that it had identified approximately 65 questionable valve internals (e.g., valve stems, plugs / discs, cages, seat rings,-and retainer pins) after an M-D field service-representative pointed out that several valve internal parts for an M-D turbine l
bypass valve at CPCo's Palisades Nuclear Plant were not genuine M-D parts.
. Discussion:
During the 1986 Palisades refueling outage, CPCo sent the subject turbine-by-pass. valve to an M-D authorized facility for refurbishment after experiencing leakage problems with the valve.
CPCo also sent to the M-D authorized facility the. valve replacement parts since the parts were in-stock items at the Palisades warehouse. After the valve-was refurbished and reinstalled, CPCo continued to experience leakage problems with the valve.
However, CPCo decided td~tontinue operating with the -leakage and to wait until the 1988 refueling outage to re-solve.the problem.
E812120047 v
IN 88-97 December 16, 1986 Page 2 of 2 During the 1988 refueling outage, CPCo decided to perform the valve refurbish-ment at the Palisades plant and requested onsite technical support from M-0.
During the valve disassembly process, the M-D field service representative L
pointed out that some of the valve internals had different dimensional and L
metallurgical characteristics from typical M-D parts.
The installed parts had i
been provided by CPCo and installed in the bypass valve at the authorized M D facility during the-1985 outage.
The M-D representative also identified ad-
'ditional valve internal parts in the Palisades warehouse that he stated were lL different from typical M-D parts.
CPCo believes that all the parts came from the san.e purchase order.
Subsequent CPCo investigations determined that the authorized M-D distributor procured some of the valve parts.from manufacturers t
that are not authorized to make M-D parts.
On November 18, 1988, M-D transmitted a letter to the NRC regarding this issue
( Attachment 1) indicating that a potential for malfunction of. M-D valves exists if parts manufactured by unauthorized companies are installed.
l The 10 CFR Part 21 notification submitted by CPCo, the attached M-D letter, and the NRC staff reviews have brcught into question the ability of 6 valve to perform its safety-related function when internal parts are substandard to the valve manufacturer's authorized replacement parts. Accordingly, ad-dressees may wish to review whether they have an adequate basis for accepting valve replacement parts, especially those purchased for safety-related appli-cations, and to contact the appropriate manufacturers or distributors to confire L
the authenticity of any questionable parts.
No specific action or written response is required by this information notice.
L If you have any questions regarding this matter, please contact one of the technical contacts listed below or the Regional Administrator of the appropri-ate regional office.
W ar@sE.
s f, Director i,
Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts:
Joe Petrosino, NRP l
(301)492-0979 4 2-1 b Attachments:
1.
Letter to NRC from M-D 2.
List of Recently !ssued NRC Information Notices L
l
Attacipent 1 IN 88-97 Page 2 of 2 SUBJhC1:
10CFR21 Report-Masoneilan Valve Parts Deficiencies PAGE 2 In addition the potential for additional counterfeit parts exists in the realm of-turned machine parts such as:
Valve plugs Bushings Cages Packing box components Counterfeit machined parts are often difficult to distinguish from original equipment parts.
An independent investigation by Masoneilan is under way to determine if similar circumstances have occurred with other Masoneilan representative organizations.
We are auditing the Manufacturer's representatives with a significant installed base of Masoneilan valves in Nuclear Power facilities in'various geographical _ territories.
Our-concern is.for the potential of other similar circumstances in Nuclear Power facilities.
Very truly_yours, MASONEILAN-DRESSER INDUSTRIES Y
W.T.
Allen
' Quality Manager Masoneilan North American Operations WTA/mk 1
cc:
L.W.
Kinderman J.E.
Conway R. Cameron o
enmum n-iii-an
l IN 88-97 December 16, 1988 Page 1 of 1 LIST OF RECENTLY ISSUED NRC INFORMATION NOTICES Informa tion Date of Notice No.
Subject issuance issued to J
88-96 Electrical Shock Fatalities 12/14/88~
All holders of OLs at Nuclear Pc:;er Plants or cps for nuclear power reactors, l
88-95 Inadequate Procurement 12/8/88 All holders of Ols i
Requirements imposed by or cps for nuclear Licensees on Vendors i
power reactors.
88-94 Potentially Undersized 12/2/88 All holders of Ots Valve Actuators or cps for nuclear power reactors.
88-93 Teletherapy Events 12/2/88 All NRC medical licensees.
88-92 Potential for Spent Fuel 11/22/88 All holders of OLs Pool Draindown or cps for nuclear power reactors.
88-91 Improper Administration 11/22/88 All holders of OLs and Control of or cps for nuclear Psychological Tests power reactors and all fuel cycle facility licensees who possess, use, import, export, or transport formula quantities of strategic i
88-90
-Unauthorized Removal of 11/22/88 All NRC' licensees Industrial Nuclear Gauges authorized to possess, use, manufacture, or
~
distribute industrial nuclear gauges.
88-89 Degradation of Kapton 11/21/88 All holders of OLs Electrical Insulation i
or cps for nuclear power reactors.
88-88 Degradation of Westinghouse 11/16/88 All holders of OLs ARD Relays or cps for nuclear l
power reactors, OL = Operating License CP = Construction Permit l
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