NUREG-0219, Notice of Regional Meetings to Discuss Upgraded Guard Qualification & Training Requirements Per NUREG-0219. Agenda,Meeting Locations & Meeting Dates for Each Region & Registration Form Encl
| ML20147A697 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/25/1978 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | BOSTON EDISON CO. |
| References | |
| RTR-NUREG-0219, RTR-NUREG-219 NUDOCS 7809010080 | |
| Download: ML20147A697 (4) | |
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EVENT OESCRIPTION ANO PROB ABLE CONSEQUENCES h 2l During normal cperstions, Met-Ed received notification from B&W. the NSSS vendor.
l that veld filler wire atypical of vire,specified by B&W may have been used in the l
yl 3l construction of the TMI'1 Reactor Vessel. This is reportable per T. S. 6.9.2.A.(9). l g i The structural integrity of the vessel is not compromised and no threat to the l
gl public health and safety is involved.
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42 43 44 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS h T) 1 The atypical veld vire was unknowingly mixed by the supplier in a shipment of vire j
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g j vill be used to govern P-T heatup & cooldown.
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~ ATTACHMENT TO LER 4
A veld. filler vIre atypical of the' submerged' are veld filler wire, used by B&W in~.the construction of.the 'IMI-1 Reactor Vessel was unknowingly mixed
.by the supplier with a shipment of Mn-Mo-Ni tiller vire. The atypical veld wire has high silicon and lov nickel contents which are outside of the range for the Mn-Mo-Ni filler wires normally specified by B&W.
This event is reportable per Tech. Spec. 6.9 2.A.(9).
There :are no directly applicable irradiation data for the stypict.1 veldments, although other applicable data exists. Furthermore, velds of this vire pos-sess a higher than typical unirradiated reference temperature, RTNDT. Weld-ments prepared from'the atypical wire exhibit a very adequate Charpy Upper -
Shelf. Energy.' A fracture mechanics evaluation has been performed by B&W assuming the atypical material is present in the velds. The evaluation demonstrates that the structural integrity of the vessel has not been com-promised by the possible preseace of the material. However, B&W has stated
'that changes to Tech. Specs. governing heatup and cooldown rate and pres-suce-tezqperature limits will be required asuuming the atypical material is
%e present.
'f The welds that may contain the atypie*1 material are located (1) between the lover shell and the Dutchman and d2) between the upper shell and the nozzle helt. Because'the veld wire manufacturer's original documentation
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.has been destroyed by fire, it is uncertaln if any TMI-1 Reactor Vessel velds contain the stypi6a1 material.
Based en the. assumption that the atypical material is present in the velds, B&W's recommended heatup and cooldown : rates and P-T li2 nits vill be incorpor w ed into a "
the ~ TMI-1 heatup and cooldown procedures. ' Revised Tech. Upecs. vill te nubmitted as appropriate upon' completior. of B&W's evaluation.
This event poses 'no ' threat to the pu*blic 'a health and.careby.
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