ML19248D517
| ML19248D517 | |
| Person / Time | |
|---|---|
| Site: | Cherokee  |
| Issue date: | 07/05/1979 |
| From: | Dail L DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7908160371 | |
| Download: ML19248D517 (3) | |
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1 DUlm l'UWEl? COMI' AN Y Tftt'Hont apfn70s 373 act)
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July ).
1979 r
Mr. J. P. O'Reilly, Director U. S. tiuclear Regult.ory Commission y
101 tarietta Street, Suite 3100 Atlanta, Georgia 30303
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Re: Cherokee fluclear Stat;on IE Bulletin 79-02, Rev. 1 CK-1196.02 and CK-1412.ll Duke Files:
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Dear Mr. O'Reilly:
Enclosed for your use are the responses to Actions 1 through 4 required by IE Bulletin 79-02, Revision 1. Picase note that the results of the cyclic testing referred to in Actions 3 and 4 are not included in this report. They are scheduled for subraittal to your office on August 15, 1979.
w Very truly yours,
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L. C. o Vice President Design Engineerin9 EKM/sr bcc:
C. L. Ray, Jr.
i' A. L. Snow R. B. Priory i.~..;
I W. O. Henry n
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CHER0KEE NUCLEAR STATION rf Responses to USNRC IE Bulletin 79-02, Revision 1 July 5,1979
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stages of construction and no pipe Cherokee Nuclear Station is in the earlyThe following is a sunriary, by item, support', have been installed to date.
of the extent and manner in which Duke Power Company intends to satisfy Actions
' throug' 4 of IE Bulletin 79-02, Revision 1.
Duke Power Company will cccount for base plate flexibility in the Response l'.
calculation of expansion anchor bolt loads for all Seismic Category I pipe support base plates using either a conservative hand calculation method which has been verified by non-linear finite element analysis or a specific not 'inear finite element analysis for a particular ase plate. The models and boundary conditions, including appropriate load-displacement character-istics of the anchors, used for the finite element analyses are based on Duke studies and oa work performed by Teledyne Engineer-ing Services which was sponsored by a group of thirteen (13) utilities formed to respond to generic items of IE Bulletin 79-02.
The minimum factors of safety, between the expansion anchor de-Re3ponse 2:
sign load and the anchor ultimate capacity determined from static load tests, used in Duke Power Company design of pipe supports are as follows:
Ncrmal Conditions - 4 3
Upset Conditions Faulted Conditions - 2 These factors of safety are for wedge type and sleeve type ex-pansion anchors which are the only types of anchors which will be used at Cherokee Nuclear Station for Nuclear Safety Related applications.
Expansion anchor installations for Seismic Category I piping supports are restricted to normal weight structural concrete Expansion anchor ultimate load of various nominal strengths.
capacities are based on manufacturer's test results and recem-mendations for normal weight concrete and installed concrete s trer.g ths.
Cherokee Seismic Category I expansion ancher designs will pro-perly account for shear-tention interaction, minimum edge distances and bolt spacing T ' accordance with manufacturer's test results and recommendations.
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i ll applicable Duke Power Company designs pipe supports mal oper-Response 3:
t critical com-ating loads, thermal loads, etc. static or quasi-static load binat' a of the applicable loadings.
in Response 2.
Duke the C W nsion anchors will be as specified f
d by Teledyne Power Company is now co-sponsoring tests per orme rocur;d for Enginee-ing Services to demonstrate that the anchors p ately under use at Cherokee Nuclear Station will perfom a d high cycle /
low amplitude loading (operating loads).
15, 1979.
to be complete by July d applications All expansion ancSors used in Nuclear Safety RelateThe anc will be either wedge type or sleeve type.
h Duke Power Response _4:
inspected for proper installation in accordance wit Expansion Company's Quality Assurance Precedure M-52, "ConcreteT d ce with the Anchor Installation Inspection". expansion anchors a manuf acturer's recommenda tions.
i d to, inspec-Prncedurc M-52 criteria includes, but is not lim te l
ity, torque, tion of experim anchor size, type, perpendicu t
dge and unauthorized trodification of the anchor. sizing is i
reasons:
hibit de-Duke Power Company Quality Assurance Procedures pro ithout viations from design drawings and specifications w i
Engineering 1.
written authorization and approval by the Des gn Department.
Cherokee Nuclear Station will qualify each concrete ex b l exam-sinn anchor operator by installation test and ver a 2.
ination on proper installation procedure.
ntly re-As an additional precaution, Duke Power Company is cu vising Procedure M-52 to include visual inspeThis inspection of plate bolt hold oversizing. Related pipe support.
will be documented for each Nuclear Safety for evident i
f cyclic In order to address the question of the relationsh p o(anc load carrying capacity to installation procedure f rmed by Telecyne the tests referred to in Response 3, beins hirteen (13) t lled in accordance utilities, are being performed on anchors ins aprocedures and i
with manufacturer's recommended installat on f these pro-have no more preload than is provided by the n
eviously per-sion anchors and on cyclic testing which fident that cedures.
dequately.
the tests will show that the anchors will perform a
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