ML19318B380

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Requests That Encl IE Info Notice 80-21, Anchorage & Support of Safety-Related Electrical Equipment, Be Forwarded to Facility Control Bldg Licensing Board & Listed Parties
ML19318B380
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 06/12/1980
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Scott S
NRC OFFICE OF ADMINISTRATION (ADM)
Shared Package
ML19318B381 List:
References
TASK-AS, TASK-BN-80-09, TASK-BN-80-9 BN--80-09, BN-80-9, IEIN-80-21, NUDOCS 8006260026
Download: ML19318B380 (3)
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Docket!No. 50-344L phlI,,hl

.b MEMdRANDUM FOR:

. Sco'tt, Chief Document Management Branch ADM FROM':

D. G. Eisenhut, Director

- Division of Licensing, NRR

SUBJECT:

BOARD NOTIFICATION - TROJAN CONTROL BUILDING PROCEEDING' Please forward the enclosed IE Information Notice No. 80-21, " Anchorage l

and Support of Safety-Related Electrical Equipment" to the Trojan Control Building' Licensing Board.and all ' parties and persons on the service list for. this proceeding.

The problems ~ addressed by this Notice are not directly related.to the.

-Trojan. Control Building design deficiencies or the proposed structural modifications.

However, they do relate to the proper seismic anchoring and support of. electrical equipment.and, therefore, by separate letter

-(enclosed),' PGE is being requested to provide a written-response to the notice for the information of the Board and parties in the Trojan Control-Building proceeding.

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M Darrell G. Eisenhut, Director l

Division of Licensing Office of Nuclear Reactor' Regulation

Enclosures:

.l. NRC letter -to PGE dated 5/16/80 enclosing -IE Info. Notice 80-21.

L 2.LNR_C letter.to PGE dated' June 12, 1950.

cc-w/ enclosures:

See next~page-

8006260logg

'Mr. Charles Goodwin...Jr.

'Pertland Ger.eral Electric Company.

Mr. John A. Kullberg

cc:. Mr. Rona.ld W. Johnson, Esquire Corporate Attorney.*

Route One

-Portland' General Electric Company Box 250Q 121 S.W. Salmon Street Sauvie Island, Oregon 97231 Portland, Oregon-97204 Maurice Axelrad Esquire Robert M. Hunt,, Chairman Lowenstein, Newi:ian, Reis,

' Board of County Comissioners Axelrad and Toll n-

Columbia County Suite 1214 St. Helens, Oregon. 97051

-1025 Connecticut 9. venue, N.W.

Washington, D. C.

20036

' Columbia County Courthouse Law Library, Circuit Ccurt Room Richard M. Sandvik, Esquire St. Helens,~ Oregon.97051 Frank W. Ostrander, Jr.

Counsel.for Oregon Dept. of Director, Oregon Department of Energy Energy L' abor-and Industries Building, ' Room 111 500 Pacific Building Salem, Oregon 97310 520 S.W. Yamhill Portland, Oregon 97204 Dr. - Hugh D. Paxton 1229 41st Street Mr. David B. McCoy Los Alamos, New Mexico 87544 348 Hussey Lane Grants Pass, Oregon 97526 Michael Malmros, Resident Inspector U.- S.- Nuclear Regulatory Comission William Kinsey, Esquire Trojan Nuclear Plant 1002 N.E. Holladay P. O. Box 0 Portland, Oregon - 97232 Rainier, Oregon 97048 Ms. Nina Bell Dr. Kenneth A. McCollom, Dean 728 S.E. 26th Street Division of Engineering, Portland, Oregon 97214 Architecture and Technology Oklahoma State UniversityJ Mr. Eugene R. Rosolie Stillwater, Oklahoma 74G74 Coalition for Safe Power 215 S.E. 9th Avenue Portland, Oregon 97214 J. Gray C. Trammell K. Herring-K.-Wichman E. Christianbury.

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'Mr. Charles Goodwin, Jr.

Pertla'nd General Electric Conpany-cc: ' Marshall. E. Miller,' Esquire, : Chairman-Atomic: Safety and Licensing Board;

'U. S. Nuclear' Regulatory Commission Washington, -D. C. ~ 20555 Atomic Safety 'and Licensing ' Board Panel

-U. S. Nuclear Regulatory? Comission

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Washington, -lD. - C.

20555

-Docketing and Service Branch (7)

Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. C.- ' 20555:-

Alan S. Rosenthal, Esquire L Atomic Safety and Licensing Appeal Board U. S. Nuclear Reo iatory Comission Washington,10.: C.

20555

. Dr. 'J ohn - H.. Buck Atomic Safety and Licensing Appeal Board U.' S. Nuclear. Reg 21atory Commission Wash'ington, D. C.

20555 Dr. W. ' Reed Johnson-Atomic Safety and Licensing Appeal Board-U." S.L Nuclear Regulatory Commission-Washington, D. C.

20555 -

Atomic Safety and Licensing Appeal Panel (5)

U..S. Nuclear Regulatory Commission Washington, D. C. ' 20555-e O

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N.'AtfJUT CREEK, CALIFORNIA 94596 May 16, 1980 Doc ket. i:o.J50-344.

Portland General Electric Company

--121 S.' WSalmon Street

Portland, Oregon 97204 Atter. tion:. Mr. Charles lGoodwin, 'Jr.

JAssistant Vice-President Gentle.en:

- This Information flotice is forwarded for information.

No written response toi thi's' Information !!otice is required.

If you have any questions related

' to this matter, please contact this office.

Sincerely, h

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-R. H. Engelken.

Director

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.IELInformation-Notice so.'80 2..

1.ist of.~ Recently Issued.IE Information' flotices.-

cc w/ enclosures:

C.-P. Yundt, PGE-F.~C. Gaidos,=PGE-

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-SSIftS No.:'6870

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Accession No.

. UNITED' STATES 8005050050 NUCLEAR: REGULATORY: CD:'lilSSION

'0FFICE-OF INSPECTION AND ENFORCEME!;T DN

~MASHINGTON. D.C.

20555

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l May 16, 1980 IE Information Notic.e No. 80-21 At:C' ORAGE dND _ SUPPORT 0F: SAFETY-RELATED ELECTRICAL EQUIPMENT F

Description of Circumstances:

' Seismic design' evaluations in connection witn the.NRC Systematic Evaluation ProgramL(SEP) have indicated a potential safety deficiency in the anchorage ar.d support-of safety-related electrical equipment.

This subject was high-

. lighted ;for: more in-depth evaluation af ter site visits to several facilities.

The site reviews _ indicated that equiptent was supcorted in a non-uniform manc.e r.

In some cases, design modifications were rec,uired to render acceptable seismic' design margins. The deficiencies in anchorage and support may be due to the fact that earlier engineering design criteria did not require rigorous analyses.

Letters were issued in January 1980 to the SEP plants which requested a review of:the: anchorage of' safety-related electrical equipment. The findings from the reviews at Haddam Heck, Big Rock Point, Dresden 2, Oyster Creek, and Falisades identified various safety-related electrical ecuipment that did not have cesitive anchorage.

The reviews at other SEP plants are continuing.

A sum ary is' provided below of those itens so far identified.

Station Service ' Transformers Motor Control Centers (4160 V - 480V)

Cable Trays DC to'AC Inverters Computer Emergency Diesel Generator =

Control Panels - MG Set

Room Heater

- Air Compressor Eatteries '- Emergency Diesel.

--Control Room Generator Instrument Rack Diesel-Fire Pump Battery Room Main Breaker and

. Station-Distribution Panel-Station'Batte'ry Rack

- A related Litem has been identified at Comanche Peak (under construction) in which the welds"to :the floor supports for the main. control panels were found -

to'te! undersized and-improperly spaced.

Also, the SEP reviewers observed - that ncn-seismic Categoryc1 ancillary items'.(dolleys, gas bottles, block and tackle qcear,7ductworks etc.).may be' located'such that they could potentially' dislodge, irpact, and. damage' safety relatedLequipment during an earthouake.

The ! type of anchorage systems utilized in the SEP plants and their expected icapaci_ ties varyLwidely. ~ For exarple, hich uncertainty exists relative to the scapacity of'non-engineered tack' welds ar.d attachments that rely on frictional clamoing forces. 'Inisome cases,1equicment has been found free standing with

- 1 j no reans'of positive.latersi support.

(Friction being the only lateral load' j

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IE Information notice No. 80-21 May 16, 1920 Page 2 of 2 i

carrying mechanism). Most of ten, heavier equipment is anchored using (1) tack welds to steel angles enbeided in concrete; (2) clips that rely on frictional resistance; (3) ccncrete embedded anchor bolts; or (4) external braced frames.

Lighter equipment housed in cabinet: 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.ca'pacity.

The potential problems relate to overturning and/or sliding of large equipment and gross move. Tent or unacceptable forces on smaller attached equipment that may render it inoperable during an earthquake.

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

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

These criteria include IEEE Std. 344, " Guide for Seismic Oualification of Class IE Electrical Equipnent for Nuclear Power Generating Stations", first issued in 1971.

Facilities designed before about 1971 without benefit of such design and testing criteria may have some anchorage deficiencies.

The MPC staff is continuing to evaluate this issue on the SEP plants as part of the seismic review in the SEP. Remedial actions have been planned for the affected plants.

This Information Notice is prcvided as notification of a possibly significant matter.

It is expected that recipients will review the information for possible applicability to their facilities.

No specific action or response is requested at this time.

If MRC evaluations so indicate, additional actions may be requested or required.

If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

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