ML19257C958
| ML19257C958 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/01/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 8001310137 | |
| Download: ML19257C958 (5) | |
Text
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pas UNITED STATES
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7, NUCLEAR REGULATORY COMMISSION
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,E WASHINGTON O. C. 20555 s
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g January 1, 1980 Docket No. 50-219 Mr. I. R. Fi nf rock, J r.
Vice Presiaent - Generation Jersey Central Power & Light Company Macison Avenue at Punch Bowl Roaa Morristown, New Jersey 07960
Dear Mr. Finfrock:
Recent seismic cesign evaluations conducted in the Systematic Evaluation Program (SEP) have indicated a potential safety concern relative to the anchorage and support of safety relatea electrical equipment.
It has also been observed that non-seismic Category I auxiliary items (colleys, gas bottles, etc.) may De cislodgea oy an earthquake and damage safety related equipment. These issues were identified curing site visits to Dresden 2, Haaaam Neck, Ginna, Oyster Creek, Palisades and Millstone 1 by review teams consisting of NRC representatives and consultants.
Since operaoility of the suoject equipment may be essential curing and af ter a seismic oisturoance, we request that you assess the capaoility of all safety relatea electrical equipment (as well as non-seismic Category I auxiliary items) to resist seismic forces and implement remedial measures, as necessary, to increase safety margins. All operating licensees of nuclear power f acilities are being notifieo of this issue by an I&E Information Notice (Enclosure 1).
Within 30 days, you are requested to develop an action plan for resolution of this issue ano to submit it for our review. The following issues should be addressed:
1.
uoes positive ancnorage exist (load carrying mechanism other than friction);
2.
If positive anchorage exists, has the anchorage system been engineered with aaequate capacity; ano 3.
Was the anchorage fabricated to quality standards?
The results of your investigation of Item 1 should be submitted within 60 days of the date this letter is received.
It shoulo describe any corrective action considered necessary. The overall issue, incluaing any required modifications, should be resolved oy Septemoer 1,1960.
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2 Although the final seismic design 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, con-ideration should be given to providing temporary supports with more permanent supports being installed after all seismic questions have been resolved.
r Sincerely,
'~Darrell G. Eisenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation Encl osu re:
As stated cc w/ enclosure:
See next page
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. cc w/ enclosure:
G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road Trenton, New Jersey 08628 GPU Service Corporation ATTN: fir. E. G. Wallace Mark L. First Licensing Manager Deputy Attorney General 260 Cherry Hill Road State of New Jersey Parsippany, New Jersey 07054 Department of Law and Public Safety Environmental Protection Section Anthony Z. Roisman 36 West State Street Natural Retources Defense Council Trenton, New Jersey 08625 917 15th S:reet, N. W.
Wa shi ngto r., D. C.
20006 Joseph T. Carroll, Jr.
P1 ant Superintendent Oyster Creek Nuclear Generating Steven f. Russo, Esquire Station 248 Wasnington Street P. O. Box 338 P. O. Box 1060 Forked River, f'ew Jersey 08731 Toms River, New Jersey 08753 Joseph W. Ferraro, Jr., Esquire Director, Technical Assessment Deputy Attorney General Division State of New Jersey Office of Radiation Programs Department of Law and Public Safety
( AW-459 )
1100 Raymond Boulevard U. S. Environmental Protection Newark, New Jersey 07012 Agency Crystal fiall #2 Ocean County Library Arlington, Virginia 20460 Brick Township 8 ranch 401 Chambers Bridge Road U. S. Environnental Protection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN:
EIS COOPDINATOR Lacey Township 26 Federal Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Conmissioner Departnent of Public Utilities State of New Jersey 101 Commerce Street "ewark, New Jersey 07102 1844 170
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINbTON, D.C.
20556 NOVEMBER
,1979 IE Information Notice No. 79-ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT Description of Circumstances Recent seismic design evaluations in connection with the NRC Systematic Evaluation Program lSEP) have inoicated a potential safety deficiency relative to the anchorage ano support of safety related electrical equip-ment. Tnis suoject was highlighted for more in-depth evaluation af ter site visits to several facilities. These reviews have inoicated tnat equipment is supported in a. Ton-uniform manner.
This may have resulted f rom the fact that earlier engineering design criteria dio not require rigorous analyses.
Further evaluations are continuing for tne SEP plant designs.
In some cases, design moaifications may be rec 9 ired to render acceptable seismic design ma rgi ns.
In general, a lack of engineered supports of safety relatec electrical equip-ment has Deen observea at certain SEP plants. Typical components affected i ncluce:
-AC and DC motor control centers
-transformers
-switch gear-
-i nve rte rs
-control room panels
-battery racks
-i nstrument panels
-cable trays Also, a related observation indicates that non-seismic Category I ancillary items (colleys, gas bottles, block and tackle gear, ductwork, etc. ) are located such tnat they may oislodge, impact ano damage safety relatea equipment during an earthquake.
The types of anchorage systems utilized in these plants and their expectec capacities vary widely. For example, high uncertainty exists relative to the capacity of non-engineered tack welds and attzchments that rely on irictional clamping forces.
In some cases, equiprent has been found free standing with no means of positive lateral support.
(Friction being the only lateral loaa carryng mechanism). Most of ten, heavier equipment is anchorec using 1) tack welds to steel angles emoeodea in concrete; 2) clips tnat rely on frictional resistance; 3) concrete embedded anchor bolts; or
- 4) external bracea f rames. Lighter equipment housed in cabinets or attacnea to panels or racks has been anchored using 1) bolts; 2) sheet metal screws; 3) tack welos; and 4) braceo racks.
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. The potential concern is that certain pieces of Lquipment 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 beha vi or.
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 Qualification of Class 1 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 may have some anchorage deficiencies.
The NRC staff is continuing to evaluate this issue on the SED plants as part of the seismic review in the SEP. Renedial action has been taken on one SEP plant to date.
This Information Notice is provided as an early notification of a possible significant matter.
It is expected that recipients will review the design criteria for anchorage and support of safety related electrical equipnent including as-built installation details to assure adequate capability to resist seismic forces. No written response is required.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
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