ML17250A502

Forwards Addl Guidance Re Anchorage & Support of safety- Related Electrical Equipment.Includes Scope of Investigations & Info Which Should Be Documented for NRC Review of Potential Safety Concern

ML17250A502
Person / Time
Site:	Ginna
Issue date:	07/28/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	White L ROCHESTER GAS & ELECTRIC CORP.
References
TASK-03-06, TASK-RR NUDOCS 8008110057
Download: ML17250A502 (12)

Text

Docket No. 50-244 JQ. 28 1980 blr. Leon D. klhite, Jr.

Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT

'eferences:

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 cooeents made by members of the NRC staff'at a N@r 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.

Attachment 1 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 extenkion 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.

Arly modifications shall be made in accordance with 10 CFR 50.59 of the Commission Regulations.

He 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 g48081 j.uQ+7 OFFICE P';.

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

Sincerely, Attachments:

As stated Dennis N. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing cc w/attachments:

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+0 qO 4**+4 Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 JUp 2 8 1980 Mr. Leon D. White, Jr.

Vice President Electiic and Steam Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

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 coments and our review of Reference 2,

we are providi ng additional guidance to you as indicated in the Attachments.

Attachment 1 provi des guidance as to the expected scope of-your i nvestigations and information which should be documented for our review.

A suggested format for this documentation is provided in A'ttachment 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

Mr. Leon D. White, Jr.

w Qw JUL 28 1980 for use in your evaluation.

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

Sincerely, 7

Dennis M. Crutchfield, Chief Operating Reactors Branch d5 Division of Licensing Attachments:

As stated cc w/attachments:

'ee next page

Mr. Leon D. White, Jr.

CC Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae 1333 New Haopshire

Avenue, N.

W.

Suite 1100 Washington, D.

C.

20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.

P. 0.

Box 5236 River Campus Station Rochester, New York 14627 J effrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza

Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Eoqire State P 1 aza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West

Ontario, New York 14519 Resident Inspector R. E. Ginna Plant

.c/o U. S.

NRC 1503 Lake Road

Ontario, New York 14519 Director, Technical Assessment Di vision Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Mall t2 Ar lington, Virginia 20460 U. S. Environmental Protection Agency Region II Office ATTN:

E IS COORD INATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.

20555 Dr.

Emmeth A. Luebke Atomic Safety and Licensing Board U..S.,Nuclear Regulatory Comnissi on Washington, D.

C.

20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, N-W.

Suite 600 Washington, D. C.

20006

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ATTACHMENT 1 ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPMENT POINTS TO BE ADDRESSED BY SEP

- LICENSEES IN DECEMBER 31, 1980 SUBMITTAL

.Information should be provided not only for the ant.'iorage 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

'upported 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 suppor'ts for internal components also should be identified and corrected before December 31, 1980.

2.

In order tomrify 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 e-ch piece of equipment

'rovide the information described in th'e 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.

5.

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

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.

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ATTAOlHENT 2 SUNNA'F INTESTIOATION OF ANCHORAGE AND SUPPORT OF SAFETY RELATED ELECTRICAL EQUIPHEHT AND NOH-SEISNIC CATEGORY I ITEHS THAT HAY DAHAGE THIS EQUIPHENT Equip.

Hame System Equip.

In Which ID Installed Location Bldg.

5 Elev.

Type of Mas Anchorage Hodlfled Anchorage*

SInce Jan.

1, l980 Internal ly qu p ~

I ID Support Evaluated ttached Components Name I ID l'ype of Mas Suppor t Su ort Evaluated Hon-Selsmlc Cat I Items that could pot'entlally I.D. of Docunent Supporting Conclusion

• Exaaples of Type of Anchorage!

l.

Bolted to Equipment

! 2.

Bolted to Concrete Mall 3.

Bolted to Concrete Slab

~ 4.

Bolted to BIock Mall 5.

Melded to Embedded Channel I