ML19257B921
| ML19257B921 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/01/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8001210239 | |
| Download: ML19257B921 (5) | |
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January 1, 1980 Docket No. 50-29 Mr. Robert H. Groce Licensing Engineer Yankee Atomic Electric Company 20 Turnpike Road Avenue Westboro, Massachusetts 10581
Dear Mr. Groce:
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 equipmer.t.
It has also been observed that non-seismic Category I auxiliary items (dolleys, gas bottles, etc.) may be dislodged by an earthquake and camage safety related equipment. These issues were identified during site visits to Dresden 2, Haddam Neck, Ginna, Oyster Creek, Palisades and Millstone 1 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 electrical equipment (as well as non-seismic Category I auxiliary items) to resist seismic forces and inplement remedial measures, as necessary, to increase safety margins. All operating licensees of nuclear power facilities are being notified 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 and to submit it for our review. The follr ~ng issues should be addressed:
1.
Does positive anchorage exist (load carrying mechanism other than friction!;
2.
If positive anchorage'axists, has the anchorage system been engineered with adequate capacity; and 3.
Was the anchorage. fabricated to quality standards?
The results of your investigation of Item i should be submitted within 60 days 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 1,1980.
1774 089 8001210 M
. 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, consideration should be given to providing temporary supports with more permanent supports being installed after all seismic questions have been resolved.
S ncerely, r
((k(f, /(Ei O /i Darrell G. Eisenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page g
a 1774 090
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Mr. Lawrence E. Minnick, President Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region I Office ATTN:
EIS COORDINATOR JFK Federal Building Boston, Massachusetts 02203 i774'091
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINbTON, D.C.
20b55 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 NF.C Systematic 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-depth evaluation after site visits to several facilities. These reviews have incicated 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 modifications may be required to render acceptable seismic design margi ns.
In general, a lack of engineered supports of safety related electrical equip-ment has been observeo 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 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 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 welds and attachments that rely on frictional clamping forces.
In some cases, equipment has been found free 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 embeaded 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 attacned to panels or racks has been anchored using 1) bolts; 2) sheet metal screws; 3) tack welds; and 4) braced racks.
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- 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 1t inoperable during an earthquake.
For certain large battery racks, this judgement is supported by computatiors that predict unacceptable seismic behavi 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 SEP plants as part of the seismic review in the SEP. Remedial 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 equipment 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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