ML20062H044

Forwards IE Bulletin 79-02, Pipe Suport Base Plate Designs Using Concrete Expansion Anchor Bolts

ML20062H044
Person / Time
Site:	05000516, 05000517, Shoreham  File:Long Island Lighting Company icon.png
Issue date:	03/08/1979
From:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Wolford A LONG ISLAND LIGHTING CO.
References
NUDOCS 7904060006
Download: ML20062H044 (1)

Text

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" ~}.? M49 UNITED STATES [4A f  %, NUCLEAR REGULAT0nY COMMISSION f S , REGION 1

1. e f $31 PARK AVENUE

% KING OF PRUSSIA. PENN5YLVANI A 19404

! March 8',.1979 Dockat Nos. 50-322 -

50-516 . . .

50-517 A

f Long Island Lighting Company ATTN: Mr. Andraw W. Wofford Vice President

, 175 East Old Country Road i

Hicksville, New York 11801 1

Gentlemen:

. ,1 i The enclosed IE Bulletin No. 79-02 is forwarded to you for action.

i O A written response is required. If you desire additional information regarding this matter, please contact this office.

Sincerely,

/ Boyce H. Grier asA -

~ Director

Enclosures:

1. IE Bulletin No. 79-02

2. Listing of IE Bulletins Issued in Last l

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! ('l' Twelve Months

.< cc w/encls:

J. P. Novarro, Project Manager Edward M. Barrett, Esq., General Counsel j Edward J. Walsh, Esq, General Attorney 1' T. F. Gerecke, Manager, EngineeHng j QA Department l l i

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.I UNITED STATES

! NUCLEAR REGULATORY COMMISSION l OFFICE OF INSPECTION AND ENFORCEMENT

! WASHINGTON, D.C. 20555 IE Bulletin No. 79-02  !

1 Date: March 8, 1979  !

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! PIPE SUPPORT BASE PLATE DESIGNS USING CONCRETE EXPANSION ANCHOR BOLTS  !

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Description of Circumstances:  !

t While performing inservice inspections during a March-April 1978 refueling I outage at Millstone Unit 1, structural failures of piping supports for .

safety equipment were observed by the licensee. Subsequent licensee  !

inspections of undamaged supports showed a large percentage of the  !

concrete anchor bolts were not tightened properly.

Deficiency reports, in accordance with 10 CFR 50.55(e), filed by Long Island Lighting Company on Shoreham, indicate that design of base ,

plates using rigid plate assumptions has resulted in underestimation of '

loads on some anchor bolts. Initial investigation indicated that nearly l fifty percent of the base plates could not be assumed to behave as rigid plates. In addition, licensee inspection of anchor bolt installations at Shoreham has shown over fifty percent of the bolt installations to be deficient.

Vendor Inspection Audits by NRC at Architect Engineering fims have I

shown a wide range of design practicas and installation procedures which '

, have been employed for the use of concrete expansion anchors. The l current trends in the industry are toward more rigorous controls and >

t verification of the installation of the bolts.

p) The data available on dynamic testing of the concrete expansion anchors  !

! . show fatigue failures can occui at loads substantially below the bolt i static capacities due to material imperfections or notch type stress  ;

'} risert.. The data also show low cycle dynamic failures at loads below  :

! the bolt static capacities due to joint slippage.

, Action to be Taken by Licensees and Permit Holders:

For pipe support base plates that use concrete expansion anchor bolts in  !

Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic  !

j Design Classification" Revision 1, dated August 1973 or as defined in  !

. the applicable FSAR. -

! 1. Verify that pipe support base plate flexibility was accounted for j in the calculation of anchor bolt loads. In lieu of supporting <

analysis justifying the assumption of rigidity, the case plates j r s 7903140038 y  :

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IE Bulletin No. 79-02 Date: March 8, 1979 j Page 2 of 3

. :d should be considered flexible if the unstiffened distance between  !

'f j the member welded to the plate and the edge of the base plate is '

' *( greater than twice the thickness of the plate. If the base plate

.i is determined to be flexible, then recalculate the bolt loads using i'

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an appropriate analysis which will account for the effects of U shear - tension interaction, minimum edge distance and proper bolt l spacing. This is to be done prior to testing of anchor bolts. These  ;

-I calculated bolt loads are referred to hereafter as the bolt design i loads. '

2. Verify that the concrete expansion anchor bolts have the following

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minimum factor of safety between the bolt design load and the bolt  !

i ultimate capacity determined from static load tests (e.g. anchor l bolt manufacturer's) which simulate the actual conditions of I installation (i.e., type of concrete and its strength properties): ,

a. Four - For wedge and sleeve type anchor bolts,

b. Five - For shell type anchor bolts.  !

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3. Describe the design requirements if applicable for anchor bolts to withstand cyclic loads (e.g. seismic loads and high cycle operating loads).

4. Verify from existing QC documentation that design requirements have f

been met for each anchor bolt in the following areas:

(a) Cyclic loads have been considered (e.g. anchor bolt preload is equal to or greater than bolt design load). In the case of i

the shell type, assure that it is not in contact with the back i of the support plate prior to preload testing.

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l h (b) Specified design size and type is correctly installed (e.g. proper embedmentdepth).

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~1 If sufficient documentation does not exist, then ir,n' ate a testing program that will assure that minimum design requircents have been l met with respect to sub-items (a) and (b) above. A sampling technique {

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' 1s acceptable. One acceptable technique is to randomly select and test l i

one anchor bolt in each base plate (i.e. some supports may have more f than one base plate). The test should provide verification of sub-items

.i (a)and(b)above. If the test fails, all other bolts on that base l l j plate should be similarly tested. In any event, the test program should l' t assure that each Seismic Category 1 system will perform its intended i 1 function.

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IE Bulletin No. 79-02

.t Date: March 8, 1979

j Page 3 of 3 1

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5. All holders of operating licenses for power reactor facilities are requested to complete items 1 through 4 within 120 days of date of i issuance of this Bulletin. A reactor shutdown is not required to  !

be initiated solely for purposes of this inspection above. Maintain .

,* documentation of any sampling inspection e# anchor bolts required l by item 4 on site and available for NRC inspection. Report in l writing within 120 days of date of Bulletin issuance, to the Director l of the appropriate NRC Regional Office, completion of your verifica-

tion and describe any discrepancies in meeting items 1 through 4 and, if necessary, your plans and schedule for resolution. For 1

i planned action, a final report is to be submitted upon completion 3 of your action. A copy of your report (s) should be sent to the United States Nuclear Regulatory Comission, Office of Inspection j and Enforcement, Division of Reactor Operations Inspection, 4

Washington, D.C. 20555. These reporting requirements do not

.i m> preclude nor substitute for the applicable requirements to report ,

as set forth in the regulations and license. '

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6. All holders of construction pemits for power reactor facilities are requested to complete items 1 though 4 for installed pipe support base plates with concrete anchor bolts within 120 days of j date of issuance of this Bulletin. For pipe support base plates '

which have not yet been installed, document your actions to assure l

that items 1 though 4 will be satisfied. Maintain documentation of  :

these actions on site and available for NRC inspecticn. Report in l writing within 120 days of date of Bulletin issuance, to the Director i i

' of the appropriate NRC Regional Office, completion of your review  !

and describe any discrepancies in meeting items 1 though 4 and, if l necessary, your plans and schedule for resolution. A copy of your .

report should be sent to the United States Nuclear Regulatory

.! Comission, Office of Inspection and Enforcement, Division of ,

Reactor Construction Inspection, Washington, D.C. 20555.

l Approved by GA0 B180225 (R0072); clearance expires 7/31/80. Approval i was given under a blanket clearance specifically for identified generic  ;

} problems.

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Enclosure:

3 IE Bulletins Issued in  !

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Last Twelve M::nths l 4  :

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IE Bulletin No. 79-02 Date: March 8, 1979 Page 1 of 2

! LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS g Bulletin Subject Date Issued Issued To No.

? 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechanism - General (0L) or Construction Electric Model CR105X Permit (CP) i 78-06 Defective Cutler- 5/31/78 All Power Reactor g Hammer, Type M Relays With DC Coils Facilities with an OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority I j Material Licensees j 78-08 Radiation Levels from 6/12/78 All Power, Test and i Fuel Element Transfer Research Reactor Tubes Facilities with an OL  ;

having Fuel Element '

Transfer Tubes

! 78-09 BWR Drywell Leakage 6/14/78 All BWR Power 3 Paths Associated with Reactor Facilities j Inacequate Drywell with an OL (for action Closures or CP (for information i 78-10 Bergen-Paterson 6/27/78

- All BWR Power Reactor .

Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP i

- i Spring Coils ~

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..8 IE Bulletin No. 79-02 Date: March 8, 1979 Page 2 of 2 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED) i- Bulletin Subject Date Issued Issued To No.

78-11 Examination of Mark I j Containment Torus 7/24/78 BWR Power Reactor Facilities with an OL

l Welds for action: Peach i

Bottom 2 and 3, d

Quad Cities 1 and 2, Hatch 1, Monti-

?: cello and Vemont Yankee. All other BWR Power Reactor Facilities with an OL for information

, l 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure l

' Facilities with an ,

! Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an

Vessel Welds OL or CP i

i 78-13 Failures In Source Heads 10/27/78 All General and of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 70508, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.

and 70618 Gauges 78-14 Deterioration of Buna-N 12/19/78

, h. Components In ASCO All BWR Power Reactor' Facilities with an OL Solenoids -

(for action), and all i

other Power Reactor Facilities with an OL or CP (for infomation)

I 79-01 Environmental Qualifica- 2/8/79 All Power Reactor tion of Clats IE Equipment Facilities with an i

OL, except the 11 Systematic Evaluation

- Program Plants (for l action), and all other Power Reactor i Facilities with an i OL or CP (for in- '

formation) j

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