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| | number = ML091490358 | | | number = ML091490358 |
| | issue date = 05/06/2009 | | | issue date = 05/06/2009 |
| | title = Oyster Creek Generic Letter 87-05 References | | | title = Generic Letter 87-05 References |
| | author name = | | | author name = |
| | author affiliation = NRC/RGN-I | | | author affiliation = NRC/RGN-I |
Revision as of 01:47, 17 April 2019
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Oyster Creek Generic Letter 87-05 References (1) GPUN letter to the NRC (C320-90-302) dated 12/5/1990 stated that the DW sand bed drains were inspected by routine walkdowns to identify any changes in leakage.(2) GPUN letter to the NRC (C321-92-2163) dated 5/26/1992 states, in part, that we commit to continue taking UT drywell measurements at refueling outages and at other outages of opportunity.
Drywell thickness measurements will continue for the life of the plant. During 14R outage we will take UT thickness measurements in the drywell sandbed region, once we have access to the sandbed region.ML072850072 (3) NRC letter to GPUN (TAC No. M79166) dated 6/30/1992 confirmed our drywell corrosion monitoring program commitments from the May 26, 1992 letter as acceptable.
(4) GPUN letter to the NRC (C321-93-2100) dated 3/25/1993 acknowledged the NRC letter of 6/30/1992 and confirmed our commitment to inform the NRC prior to implementing any changes to the Oyster Creek drywell thickness measurement inspection program.(5) GPUN letter to the NRC (C321-95-2235) dated 9/15/1995 provided a description of the planned changes to the inspection program based on inspections performed during the 15R outage.-With regard to the sandbed region, assessment of the UT data determined that corrosion has been arrested as a result of cleaning the area of sand and rust and coating the drywell during the 14R outage in December 1992. The inspection program for the sandbed region was to perform a visual inspection of the external epoxy coating during the 16R outage and, as a minimum, during the 18R outage (year 2000). The epoxy coating has an estimated life of 8 -10 years which makes the current projected end of life between December 2000 and December 2002. A technical assessment of the coating will be made based on the 18R outage inspections to determine additional (post 18R) inspection criteria.(6) NRC letter to GPUN (TAC No. M93658) dated 11/1/1995 confirmed our changes to the drywell corrosion monitoring program commitments from the September 15, 1995 letter as acceptable, but requested an additional commitment (since water leaking from the pools above the reactor cavity has been a source of corrosion) to perform additional inspection within approximately three months after the discovery of water leakage.(7) GPUN letter to the NRC (C321-95-2360) dated 12/15/1995 provided our commitment for the following actions should water leakage not associated with normal refueling outage activities be discovered during power operation.(a) NRC Resident Inspector will be notified of the discovery of leakage.(b) The source of leakage will be investigated and appropriate corrective actions taken.(c) An evaluation of the impact of the leakage on drywell structural integrity will be performed to ensure sufficient margin is maintained for operation to the next scheduled drywell inspection.(d) In the unexpected event that the evaluation of the impact of the leakage on drywell structural integrity does not ensure sufficient structural margin will be maintained for operation to the next scheduled outage, an additional drywell inspection will be performed within approximately three months after discovery of the water leakage.(8) NRC letter to GPUN (TAC No. M92688) dated 2/15/1996 confirmed our commitment as stated in the December 15, 1995 letter as acceptable.