ML19318C221
| ML19318C221 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 06/13/1980 |
| From: | Hermann R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-SSINS-0660 NUDOCS 8007010224 | |
| Download: ML19318C221 (3) | |
Text
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MEETING AGENDA QUESTIONS ON KEWAUNEE STEAM GENERATOR SUPPORT BOLTS 1.
Discuss the original analysts technique and prov'ide the loads.
Include why the joint was originally designed with six bolts when.only four were necessary.
Provide a copy of " Structural Analysis of Reactor Coolant / Pump /
Support System for NSP and WPS Nuclear Power Plants," Desai, K. D., et al, SD-103, February 1972.
2.
Discuss the finite element analysis used to detemine the bolt loads including:
(a) How load was applied.
(b) Spring constants used for the bolts.
(c) Any pre-load on bolts assumed in the' analysis.
3.
Provide the results of the finite element analysis..
4.
Address your planned actions in response to the May 20, 1980 NRC letter, _. _
Additional Guidance on " Potential For Low Fracture Toughness and Lamellar Tearing On PWR Steam Generator and Reactor Coolant Supports, NUREG-0577.--
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The " steam generator top support detail" regt. ires pre-tensioning of the bolts to 230 Kips. State what was actually done and your future plans for._
pre-tensioning.
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i 6.
In yeur submission of June 11,1980, you stated the AEC was aware of the modi-fication to the bolting.
Provide documentation of this statemert.
7.
Provide the details of thread engagement calculations for all the steam generator supports.
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8.
Clarify if the bolts were cut' off at the plant or a Manitowoc machine shop.
State how the bolts were cut off.
9.
Provide the documentation incorporating the engineering changes and related design review for shortening the support bolts.