ML20210J197
| ML20210J197 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Youngblood B NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8702120046 | |
| Download: ML20210J197 (26) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place FEB 041987 U.S. Nuclear Regulatory Consission Attn: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention:
Mr. B. J. Youngblood In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT - DRAFT SAFETY EVALUATION - SUPPLEMENTAL ITEMS -
INTERIM ACCEPTANCE CRITERIA FOR CABLE TRAY SUPPORTS The draft Safety Evaluation Report (SER) for the Sequoyah cable Tray supports Interim Acceptance Criteria was transmitted December 5,1986 from B. J. Young' blood to S. A. White. TVA reviewed and responded to most confirmatory items on January 14, 1987, letter from me to you. Remaining l
issues were scheduled for resolution by January 30, 1987.
j l responds to NRC Confirmatory Item 8.
Summarized are the results of.TVA's study of eccentric mass effects on cable tray support qualifications.
' discusses an open item which was identified within the body of the SER, but did not get formally recorded as a confirmatory issue. During an NRC tour, spalled concrete was observed beneath the baseplate of a cable tray support. TVA's qualification of this condition is documented with enclosure 2.
All items identified in the draft SER have been addressed with this transmittal and that dated January 14, 1987.
If any further questions exist, please call M. R. Harding at 615/870-6422.
Very truly yours, TENNESSEE VALLEY AUTHORITY
/
j R. Cridley, D ector Nuclear Safet and Licensing Enclosures cc: See Pat,c 2 i
8702120046 870204 PDR ADOCK 05000327 i
01 p
PDR 0
k An Equal Opportunity Employer
_ ~ -
' U.S. Nuclear Regulatory Commission B 04 BU cc (Enclosures):
U.S. Nuclear Regulatory Commission Region II Attn:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. J. Holonich Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. G. G. Zech, Director
, TVA Projects U.S. Nuclear Regulatory Commission Re51on II 101 Marietta Street, NW, Suite 2900
,,s Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road s
Soddy Daisy, Tennessee 37319 s
s
.--_.._.,_-_,_,,-_.m..
ENCLOSURE 1 The following comments are provided for the " Confirmatory Items" on pages 16 and 17 of the Draft Safety Evaluation Report and are with respect to the numbered items.
NRC Confirmatory Item (8)
TVA is to develop and submit for staff acceptance calculations which demonstrate that the eccentricity of the cable tray mass will not adversely affect the qualification of supports.
TVA Response TVA has performed and documented a study (copy attached) evaluating the qualification of cable tray supports when the eccentricity of the cable mass and the center of the support is considered. This study has demonstrated that all of the " worst-case" supports in the Auxiliary, Control, Diesel Generator, Additional Diesel Generator, and Reactor Buildings are qualified for the Interim Acceptance Criteria when cable mass eccentricity is considered.
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DNE CALCULATIONS TlTLE PLANT / UNIT ffffC76 Cf" TNSdCC[ NIX'lC/TY' Of CARD 72~ 4Y' N4SS SHP/t/g;r.s /.2 2.
PREPARING ORGANIZATION KEY NOUNS (Consult RIMS DESCRIPTORS LIST) 3GEP/Qvn.d3 cAgt rp.41 rappop y-BRANCH / PROJECT IDENTIFIERS Each time these calculations are issued, preparers must ensure that the original { RO) BlMS accession number is filled in.
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RIMS accession number B25 'R7012 9 3n0 APPLICABLE DESIGN DOCUMENT (S)
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Yes No O ECN No. (or indicate Not Applicable)
Statement of Problem v.
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List all pages changed by this revision.
Abstract These calculations contain an unverified assumpti n(s) that must be verified later.
Yes O No 1
O M.croe.im.nd store caicuiations in RiuS Service Center.
u.eroriim and destroy. O r
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SEQUOYAH NUCLEAR PLANT
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TABLE OF CONTENTS TO COMPLY WITH NEP 3.1 PAGE NOS 1.
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r es ENCLOSURE 2 NONCONFIRMATORY OPEN ISSUE NRC Item It was noted on page 11 of the Draft Safety Evaluation that cracked concrete was found beneath a baseplate. There was evidence of spalling beneath the Mk 1 baseplate shown as Detail A of Drawing 48W952, Sheets 1 and 2. This support should be evaluated for this condition. TVA Response There was evidence of spalling'noted beneath'the Mk 1 baseplate shown as Detail A of Drawing 48W952, Sheets 1 and 2. The wedge bolt anchor in the area of the subject spall has been tested in accordance with TVA construction specifications and found to be acceptable. Reference Inspection Report WP/WR B123739, dated January 23, 1987. ) i I n' '~' l'd ' ': : E O ~ ' 'tK [. .-n ..a.- L . :s. m+. },- 1 + 4 .._e* a> ,,,,a.. ,, _, n a :w s -_xa'- 1 -}}