ML18044A428

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Requests Assessment of Capability of All safety-related Electrical Equipment & Nonseismic Category I Auxiliary Items to Resist Seismic Forces.Remedial Measures Should Be Implemented to Increase Safety Margins.W/Draft Info Notice
ML18044A428
Person / Time
Site: Palisades 
Issue date: 01/01/1980
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Hoffman D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8001170469
Download: ML18044A428 (8)


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Docket No. 50-255

  • Mr. David P. Hoffman Nuclear L icens.ing Administrator.

Consumers Power Company 212 West Mich1gan Avenue Jackson, *Michigan 49201 Dear Mr. Hoffn\\am

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Recent s*eis~1c design evaluations conaucted in th~' System~Uc Evaluation** *. * *

. Program (SEP.) have indicated a potential safety concern relative ;~o the.. -..

  • anchor'age and support of* safety related electrical equipment~ It' has also been ot)s*~rved that [lpn-seismic C.ategory l auxiliary items (doll~ys, gas.

bottles, etc.) may be' dl~lo<lged.,by an earthquake *and damage safety.related.

  • equipment.

These 1ssu~s were identified during site visits to Dresden 2,.

Haddam Neck, Ginna, *oyst~r Creek, Palisade~ and Millstone l by.review teams consisting Of NRC -r.epres~ntati ves. anc1 consultants.

S_i nee ope.rabfJity of the subject equipment.may be*e.s*sential during and after*ase~smic disturbance, we request that you assess th.e.. capabiHty of* all safety related*_e.lectrical...

. equipment* (as wel 1 '.as non:-sei sm1 c C~tegory **I au.xi li ary i terns) :.~o resist

... *.; seismic *forces and. 1 mp lemerit remedial measures,. as necessary, to increase safety-margins. All operating l1c.ensees of nuclear.power facfhties are '

bei_ng* notif.ied 'of.. thi~ _iSsue by an I&~ Infor~tion. Notfce (Enclosure l).

w;th.in 30 aa.Ys, -yol,4 *are requested to deve*lop an action plan tor resolution_..

  • of this issue 'and to submit" it:*for qur review.

The following issues should..

b~ addres.scd:

l.
  • Does:_positive**a~chorage*e~i'st (load carry:1*ng mechanism other**than frict;onl;* *

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If positi,ve anchorage ~xists, has* the.anchorage sys.tern been engineered

.with adequate capacity; and 2*~

3.* *:Was the* __ anchorag~ fabricated-to quality_ stand~rds?*

    • The results of your investigat;on of.Item l should be submitted within 60 *
  • days of the date this<letter is re~eived *. It should describe any corrective action considel"ed necessary.

The ov~rall issue, including any. requirea.

  • modifications, should.be res9Jved by* September l_, 1980. * **
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NRC FORM 318 (9*76) NRcM 0240 U: S. GOVERNMENT PRINTING OFFICEI 1978 -

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Although the* final seismic design basis *for your fa_cility has not.been.

resolve~, and other changes may be required, *appropriate action on this matte~. should not.be del.ayed *. If necessary, consideration should.be gi\\'.en

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-after all seismic;*questions have_ been resolved;:

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  • Sincerely,..

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Darrell-G. E~senhut Darrell G. Efsenhut, Acting.Direttor,

. *,Di.vi ~ion of Operating ReQctors.-~~{~ :.,,.

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DOR:A/DIR DGEisenhut

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'ttu:s. GOVERNMENT PRINTIN~ OF~l~E: l97°9-2:S9~J69

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-255 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers. Power Company 212 West Michigan Avenue*

Jackson, Michigan 49201

Dear Mr. Hoffman:

January 1, 1980 Recent seismic design evaluations conducted in the Systematic. Evaluation Program, (SEP) have indicated a potential safety concern relative to the anchorage and. support of safety related electrical equipment. It has also been observed that non-seismic Category I auxiliary items (dolleys, gas bottles, etc.) may be dislodged by an earthquake and damage safety related equipment. These issues were identified during site visits to Dresden 2, Haddam Neck, Ginna, Oyster Creek, Palisades and Millstone l by review teams consisting of NRC representatives and consultants. Since operability of the subject equipment may be essential during and after a seismic disturbance, we request. that you assess the capability of all safety related electrica_]

equipment (as* well as non-seismic Category I auxiliary items) to resist seismic forces and i~lement remedial measures, as necessary, to increase safety margins.. A 11 operating 1 i censees of nu cl ear power faci 1 i ti es are being notified of this issue by an l&E Information Notice (Enclosure 1).

Within 30 days, you. are requested to develop an action plan for resolution of this issue and to submit it for our review.

The following issues should be addressed:

1.

Does-positive anchorage exist (load carrying mechanism other than friction);

2.

If positive anchorage exists, has the anchorage system been engineered with adequate capacity; and*

3.

Was the anchorage fabricated to quality standards?

he results of your investigation. of Item 1 should be submitted.within 60 ays of the date this letter is received. It should describe any corrective action considered necessary. The overall issue, including any required modifications, should be resolved by September T, 1980.

-.2 -

  • Although the final seismic desi.gn basis for your facility has not been resolved, and other changes may be required, appropriate action on this matter should not be delayed *.

If necessary, consideration should be given to providing temporary supports with more permanent supports being installed after all seismic questions have been resolved.

Enclosure:

As stated cc w/encl osure:

See next page

  • ~lncerely,

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tl.li ill ?(.1-/i (~tc Darrel f G. ~henhut, Acting Di rector Division of Operating Reactors Office of Nuclear Reactor Regulation

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cc w/enclosure:

M. I. Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670.

Mr *. Paul A. Perry,. Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201

  • Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Es qui re Suite 4501 One IBM Plaza Chicago~ Illinois 60611 Ms. Mary P. Sinclair Great Lakes Energy All1ance 5711 Summerset: Ori ve*. *
  • Midland, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route l, Box 10 Van Buren County, Michiga~ 49043 Office of th~ Gove~nor (Z)

Room l - Capitol B~ilding.

Lansing, Michigan 48913 DiPector, Technical Assessment Division Office of Radiatiori Programs

( Av/.,.459)

U. s.

Environr.ientaJ_P_r:Q~e.c:.~i_on Agency Crystal Mall #2 Arlington, Virginia 20460

EIS COORDINATOR 230 South Dearborn Street Chicago~ Illinois 60604 Charles Bechhoefer, Esq., Chairman Atomic Safety and Licensing. Board Panel U. s. Nuclear Regulatory Commission Washi~gton, D. C.

20555 Dr. George C. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M. Stanley Livingston 1005 Calle Largo

. Santa Fe, New Mexic~ 87501 Palisades Plant ATTN :

Mr*~ J. G *. Lewis Plant Manager Cover~, Michigan 49043

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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINbTON, CJ.C.

20555 NOVEM~ER

, 1~7~

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IE Information Notice No. 79-ANCHORAGE. AND SU~PORT OF SAFETY RELATED ELECTRICAL E~UIPMEWT Description of Circumstances Recent seismic design evaluations in connection with the NRC Systematic

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Evaluation Program (SEP) have indicated a potential safety deficiency relative to the anchorage and support of safety related electrical equip-ment.

This subject was highlighted for more in-aepth evaluation after site visits to several facilities. These reviews have inaicated that equipment is supported in a non-uniform manner.

This may have resulted from the fact that earlier engineering design criteria did not require rigorous analyses.

Further evaluations are continuing for tne SEP plant designs.

In some cases, design moaifications may be required to render acceptable seismic design margins.

In general, a lack of engineered supports of safety related electrical equip-ment has been observea at certain SEP plants. Typical components affected i_nclude:

-AC and DC motor control centers

-transformers

-switch gear*

-inverters-

-control room panels

-battery racks

-instrument panels-

-cable trays Al so, a re 1 ated observation indicates that non-seismic Category I anci 11 ary*

items {dolleys, gas bottles,. block and tackle gear, ductwork, etc.) are located such tnat-they. may dislodge, impact and damage safety related equipment during an earthquake.

The types of anchorage systems utilized in these plants and their expected capacities vary widely. For example, high uncertainty exists relative to

  • the capacity of non-engineered tack we 1 ds and attachments that rely on fri cti ona l clamping. f orces-;-ln-some-ca-ses-,~t-ha->-bee.n.. J:ou-n.ci __ fr.ea ______ _

standing with no means of positive lateral support.

{Friction being the only* lateral-load carryng mechanism).

Most often, heavier equipment is anchored using 1) tack _welds to steel angles embedded in concrete; 2) clips*

that rely on frictional resistance; 3) concrete embedded anchor bolts; or

4) external braced frames.

Lighter equipment housed in cabinets or attached to panels or racks has been anchored using 1) bolts; 2) sheet metal screws; 3) tack welds; and 4) braced racks.

  • ....,, The potential concern is that certain pieces of equipment may not have adequate levels of seismic resistance capability due to limited anchorage capacity. The potential problems relate to overturning and/or sliding of large equipment and gross movement or unacceptable forces on smaller attached equipment that may render it inoperable during an earthquake.

For certain large battery racks, this judgement is supported by computations that predict unacceptable seismic behavior.

Section 3.10.of the Standard Review Plan provides acceptance criteria for the seismic qualification ofCategory l electrical equipment.

These criteria include IEEE Std *.. 344, "Guide for Seismic Qualification of Class l Electrical Equipment for Nuclear Power Generating Stations", first issued in* 1971.

Facili-ties designed before* about 1971 without benefit of such design and testing criteria r.iay have some. anchorage deficiencies *.

The NRC staff is continuing to evaluate this issue on the SEP plants as part of the seismic review in the SEP..

Remedial action has been taken on one SEP pl ant to date.

This Information Notice* is provided as an early notification of a possible significant matter *.. It is expected. that recipients will revTew the* des.ign criteria*. for anchorage and' support of safety rel.ated electrical equipment including as-built installationdeta*ils to assure* adequate capability to resist seismic forces~. No written response is required~. If* you have any questions regarding thi~ matter~ please contact the Director of the appropriate NRC R~gional Office.


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