ML20215J059

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Requests Transfer of Lead Responsibility for Engineering Acceptability of Cable Tray & Conduit Support Matls Supplied by Midland Ross to Nrr.Engineering Assessment Should Include Acceptability of commercial-grade Matls
ML20215J059
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 12/16/1982
From: Crews J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20215J042 List:
References
FOIA-86-151 NUDOCS 8610240279
Download: ML20215J059 (2)


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/'e arou,}o UNITED STATES f ' 3.r.,g NUCLEAR REGULATORY COMMISSION i-REGION V g, * *v [. #

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14s0 MARIA t.ANE, EUITE 210 wAtwuT eneux.cAtironnia sases December 16, 1982 MEMORANDUM FOR: Darrell G. Eisenhut, Director.. Division of Licensing, NRR FROM:

Jesse L. Crews, Director, Division of Resident.

4 Reactor Projects and Engineering Programs i

SUBJECT:

REQUEST.IOR TRANSFER OF LEAD RESPONSIBILITY FOR ENGINEERING ACCEPTABILITY OF CABLE TRAY AND CONDUIT SUPPORT MATERIALSiL i

SUPPLIED BY MIDLAND-ROSS, SUPERSTRUT, OAKLAND.' CALIFORNIA ;.

,i FACILITY i

By' memorandum to you Loday (copy attached) I forwarded ~infomation regarding, cable tray and conduit support materials supplied by the Midland-Ross,

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Oakland, California facility.

This information' resulted.from recentu. o

.. g inspections conducted at the Midland-Ross facility and. Pacific Gas ar.d Electric.

Company offices by Regions IV and V,respectively.

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The purpose of this memorandum is to request that NRR assume lead responsibility regarding 4. lie engineering acceptability of cable tray and conduit cupport materials supplied by.the Midland-Ross, Oakland, California facility'fot

.usc in Class TE systems of the Diablo Canyon and other nucicar power plants.

We anticipate that engineering assessments by NRR will include consideration of the following:

1.

Acceptability of off-the-shelf, connercial grade materials for use i

in the fabrication of class 1E supports.

2.

Extent of special process control required for shop welding of support components.

3.

In consideration of 1, and 2, above, the extent of inspection, analyses, and/or testing (i.e., in situ load testing, etc.) required to demonstrato or qualify installed components in accordance with design considerations, I have discussed with members of the RIV and IE staffs the need to consider generic notification of NRC licensees regarding this matter.

Each has agreed to cooperate in the preparation of such a notification (e.g., IE Information Notice, Circular or Bulletia).

Region V will provide information to NRR as necessary in support of their, evaluation and analyses.

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We further recommend that NRR consider the extent to which this matter should be addressed in Phase II of the Diablo Canyon IDVP and take action as mi appropriate to assure such consideration.

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i Darrell G. Eisenhut /

December 16, 1982

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Should you or your staff have questions regarding this request'. please "

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't co.itact either me or Phil Morrill of nyy staff.

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. Crews r6c~ Ior-l

/ Division of Resident, i

/ Reactor Projects and.

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Engineering Programs i

Enclosure a/s i

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T. A. Ippolito, NRR 1

G. W. Knighton. NRR B. C. Buckley, NRR R. L. Baer, IE U. Potapovs/L. E11ershaw, RIV Directors, Division of P an,d RP. RI RII RIII, RIV i

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UNITED STATES NUCLEAR REGULATORY COMMISSION a

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.I neGION V 1450 MARIA LANE. SUITE 210

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WALNUT CREEK CALIFORNIA 94505 December' 16. 1982 MEMORANDUM FDR:

D. G. Eisenhut. Director. Division of Licensing

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FROM:

J. L. Crews, Director, Divisien of Resident. Reactor Projects n

and Engineering Programs I

SUDJECT:

APPARENT DEFICIENCIES IN MIDLAND-ROSS "SUPERSTRUT"' MATERIAL : D

I USED FOR CLASS 1 CABLE TRAY AND CONDUIT SUPPORTS 3.1HJ %T ; i-The purpose of this memo is to fonvard the following infomation with
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recomendation that appropriate board notification be considered.- This matter:

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.n : o was discussed by telephone with members of your staff (T.. Novak. B. Buckley.cn. -

and H. Rood) on December 15 and 16,1982.

." ' e Due to allegations regarding inadequacies in materials and welding, an inspector from the NRC Region IV Yendor Program Branch (VPB) conducted an inspection : ': 4 i

t of the Midland-Ross Superstrut manufacturing facility in Oakland, California,*

F during the period December 6-8. 1982. This facility manufactures mild steeli -

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fittings, brackets, and channels, some cf which are used to constructicable :

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tray, conduit, and instrument supports in nuclear power plants. The Region IV i

inspector informed the Region V staff of his findings at the Midland-Ross N. - i :.

Oakland facility which included:

(1) there was no fonnal Quality. Assurance (QA) program prior to 1979. (2) there were no records of the. qualification i of welding operators or welding procedures. (3) prior to 1980, spot welds were -

not sample tested and not controlled by procedures, (4) there was 'no; traceability n

of material, (5) there were no quality records before 1980, and (7) generally;.4 ~

the current QA program did not meet the intent of 10 CFR 50. Appendix.B criteria'.-

The VPB inspector also informed the Region V staff that the Superstrut material'-

I manufactured at the Oakland facility had been used at nuclear power plants: !

in Region V. Including Arizona Public Service's Palo Vertle. Pacific Gas and i t 1

Electric's Diablo Canyon. and Washington Public Power Supply. System's WNP 1 -

and 4 plants. The extent of applicability to other NRC licensed facilities is unknown at this time.

Region V dispatched an inspector on December 8.1982, to conduct a special inspection of one of the affected facilities (Diablo Canyon) to detemine the scope and potential impact of the VPB inspector's findings. The Region.V.,:

,i inspector found that the back-to-back double channels which were spot welded.

together, as well as the channels with welded end brackets, were widely used

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.._ __ J D. G. Eisenhut 2-December 15. 1982 (up to 11,000 supports out of approximately 24,000 in the Diablo Canyon facility)' '

and that the licensee's engineering staff had treated the double thannel:Superstrut naterial as a composite member and not as two members acting independently.* i*s t ".*

The Region V staff has alerted appropriate NRR staff personnel.regarding the.-l. :.1.

situation described above and is prepar,ing a special inspection report'on:their. W -

inspection findings.

Should you require additional information regarding this subject; please do.

i not hesitate to call me (FTS 463-3735) or.Phil Morrill (FTS 463-3740)'.. D i ' :..'

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s. Director

!! vision of R9sident, Reactor 4 rojects and Engineering Programs.

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R. Baer, IE (ENTSB).

U. Potapovs. RIV (VPB)

T. Novak, NRR (OR)

J. Knight, NRR (CSE')

G. Knighton, NRR (L83)

8. Buckley, NRR (LB3) p t:*

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