ML13322A937

Forwards Guidance for Program Resolving Safety Concern Re Anchorage & Support of safety-related Electrical Equipment

ML13322A937
Person / Time
Site:	San Onofre
Issue date:	07/28/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Dietch R Southern California Edison Co
References
TASK-03-11, TASK-3-11, TASK-RR NUDOCS 8008140445
Download: ML13322A937 (7)

Text

Docket No. 50-206 JUL 2 8 1980 Mr. R. Dietch Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770

SUBJECT:

ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT

References:

1. Letter from D. Eisenhut to SEP Licensees, dated January 1, 1980

2. Letter from R. Schaffstall to D. Crutchfield, dated July 3, 1980 Reference 1 identified a potential safety concern relative to the anchorage and support of safety related electrical equipment and requested that you initiate a program to resolve this issue including the installation of any required modifications by September 1, 1980. Reference 2 describes a program which was developed by the Systematic Evaluation Program Owners Group in response to comments made by members of the NRC staff at a May 14, 1980 meeting in Bethesda. As a result of your comments and our review of Reference 2, we are providing additional guidance to you as indicated in the Attachments. provides guidance as to the expected scope of your investigations and information which should be documented for our review. A suggested format for this documentation is provided in Attachment 2.

Due to the lack of clarification relative to certain requirements of Reference 1 and in particular the issue of support of internally attached electrical components, we will permit an extension until December 31, 1980 for completion of this program.

This shall include the installation of any modifications which may be required as a result of your investigations. Any modifications shall be made in accordance with 10 CFR 50.59 of the Commission Regulations. We request that formal documentation summarizing your program be submitted to this office by December 31, 1980.

Existing plant floor response spectra or floor response spectra computed or estimated from the NRC Site Specific Spectra Program are acceptable (445 O F F IC E S U R N A M E D A T E..................................

Mr. R. Dietch

-2 for use in your evaluation. The conservatism of these loadings shall be verified when the final floor response spectra are available.

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing Attachments:

As stated cc w/attachments:

See next page DISTRIBUTION Docket NRC PDR Local PDR ORB Reading SEPB Reading NRR Reading DCrutchfield HSmith TWambach JRCarter WRussell OELD OI&E (3)

ACRS (16)

TERA NSIC JRBuchanan, NSIC HLevin DAllison DEisenhut GLainas RPurple OFFICE,,.SE BD..P....

.S.

A L

HLevin Dall rut hfi~eld GLai s

SU RNAM E

7(T /80 7/n%/80 7/

/80 7/

0

.RD A TE FO R M

31. (9-7.)

N R C M 0240 S G V

N E

P R T

G O F C 1 7 2.3 NRC FORM 318 (9-76) NRCM 0240

• U.S.

GOVERNMENT PRINTING OFFICE: 1979-289-369

UNITED STATES 0

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 JUL 2 8 SU Docket No. 50-206 Mr. R. Dietch Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770

SUBJECT:

ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT

References:

1. Letter from D. Eisenhut to SEP Licensees, dated January 1, 1980

2. Letter from R. Schaffstall to D. Crutchfield, dated July 3, 1980 Reference 1 identified a potential safety concern relative to the anchorage and support of safety related electrical equipment and requested that you initiate a program to resolve this issue including the installation of any required modifications by September 1, 1980. Reference 2 describes a program which was developed by the Systematic Evaluation Program Owners Group in response to comments made by members of the NRC staff at a May 14, 1980 meeting in Bethesda. As a result of your comments and our review of Reference 2, we are providing additional guidance to you as indicated in the Attachments. provides guidance as to the expected scope of your investigations and information which should be documented for our review. A suggested format for this documentation is provided in Attachment 2. Due to the lack of clarification relative to certain requirements of Reference 1 and in particular the issue of support of internally attached electrical components, we will permit an extension until December 31, 1980 for completion of this program.

This shall include the installation of any modifications which may be required as a result of your investigations. Any modifications shall be made in accordance with 10 CFR 50.59 of the Commission Regulations. We request that formal documentation summnarizing your program be submitted to this office by December 31, 1980.

Existing plant floor response spectra or floor response spectra computed or estimated from the NRC Site Specific Spectra Program are acceptable

S Mr.

JUL 2 8 19 for use in your evaluation.

The conservatism of these loadings shall be verified when the final floor response spectra are available.

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing Attachments:

As stated cc w/attachments:

See next page

Mr. R. Dietch cc Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459)

Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Crystal Mall 12 SSamuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN: EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector c/o U. S. NRC P. 0. Box AA Oceanside, California 92054 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 Chai rma n Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:

Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814

A ATTACHMENT 1 ANCHORAGEND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT POINTS TO BE ADDRESSED BY SEP LICENSEES IN DECEMBER 31, 1980 SUBMITTAL

1.

Information should be provided not only for the anchorage of electrical equipment but also the entire support that provides a load oath (such as bracing and frames), as well as support for internally attached components.

The latter is especially important for cabinet or panel type electrical equipment (such as control panels, instrument panels, etc.) which has internally supported components. An example of a potential improperly supported internal component would be a heavy component cantilevered off a front sheet metal panel without additional support to a stronger and stiffer location. These inadequate supports for internal components also should be identified and corrected before December 31, 1980.

2.

In order toverify that an anchorage or a support of safety related electrical equipment has adequate capacity, provide justification by test, or analytical means. If expansion anchor bolts exist, justifi cation provided previously for IE Bulletin 79-02 can be utilized if applicable. The acceptance criteria for substantiating these judgements should be provided, this may involve specifying the factor of safety and allowable stress limits used for design and justifying the overturning moment and shear force used.

3. Provide a table listing all (to include both floor and wall mounted) safety related electrical equipment in the plant.

For each piece of equipment provide the information described in the attached table (attachment 2).

These investigations of each piece of equipment should determine:

a. Whether positive anchorage or support exists

b. The type of anchorage

c. Whether internally attached components are properly supported

d. Identify non-seismic Category I equipment, the dislodgement of which during an earthquake may be detrimental to safety related equipment and render them inoperable. Inspection of the anchorages of such non-seismic Category I equipment should be conducted. If positive anchorages do not exist, they should be identified and modified before December 31,1980.

4. Wherever modifications of anchorages or supports are required, these modifications should be implemented and thoroughly documented.

5. The seismic design of cable trays may be treated as a separate problem, because of its complexity. Each licensee or the SEP Owner's Group should provide a separate action plan for the resolution of this issue within 30 days of receipt of this letter.

ATTACHMENT 2

SUMMARY

OF INVESTIGATION OF ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT AND NON-SEISMIC CATEGORY I ITEMS THAT MAY DAMAGE THIS EQUIPMENT System Internally Attached Components Non-Seismic Cat I Items I.D. of Equip.

Equip. In Which Location Type of Was Anchorage Modified E T Ea

-Typpo

-Warlsuppor that could potentiaelly Document Namne 10 Installed Bldg. & Elev.

Anchorage*

Since Jan. 1, 1980

& I Support Evaluated Jpterac; with this enuip.

Supporting Name A Type of Was Support Conclusion ID Support Evaluated

• Examples of Type of Anchorage:

1. Bolted to Equipment

2. Bolted to Concrete Wall

3. Bolted to Concrete Slab

4. Bolted to Block Wall

5. Welded to Embedded Channel