ML20198E176
| ML20198E176 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/30/1992 |
| From: | Skolds J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9212040252 | |
| Download: ML20198E176 (3) | |
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tDVUDER 30, 1992 i
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Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
Subject:
VIRGILC.SUMMERNUCLEARSTATION(VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 t
RE*CTOR VESSEL OUTLET N0ZZLE' RELIEF REQUEST (NKR920004)
South Carolina Electric & Gas Company (SCE&G) hereby submits the attached I
i-request for relief from performing Reactor Vessel Outlet Nozzle Examination i
per the schedule required by the 1977 ASME Section XI Code. This request is be:;ed on ALARA concerns as well as gaining more consistent and reliable data for all.six nozzles by utilizing one UT acquisition systeme - SCE&G proposes i
j to perform its second ten year interval inspection of the outlet nozzles during its seventh refueling outage which is eight months prior to th? actual second ten year interval. SCE&G is submitting the attached relief rec.est in accordance with 10CFR50.55a(a)(3)(ii).
In order to support the scheduling of activities for the upcoming outage of the VCSNS, SCE&G requests-the NRC response and approval of this request by l
January 31, 1993.
Should you have any questions, please call David Haile at_(803) 345-4322.
Very'truly yours, John L. Skolds-DCH:JLS:smd Attachment c:
- 0. W..Dixon NRC Resident Inspector R. R. Mahan
.J. B. Knotts Jr.
R. J. White NSRC S. D. Ebneter RTS (NRR920004 General Managers file (810.19-2)).
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9212040252 921130 PDR ADOCK 05000395 0
i NUCLEAR EXCELLENCE. - A J' umEk TRADIIIONI-
Attachment to Document Control Desk Letter NRR 920004 Rage,,1 of 2 Reactor Vessel Outlet Nozzle Relief Request Components: Reactor Vessel Outlet Nozzle Safe End Welds-Code Class 1 (See List Below) lable IWB-2500-1 Isometric Drawing No.
Weld No.
Category item Not CGE-1-4100 1*
B-F B5.10 CGE-1-4200 1*
B-F B5.10 CGE-1-4300 1*
B-F B5.10 CGE-1-4100 2
B-J B9.11 CGE-1-4200 2
B-J 89.11 CGE-1-4300 2
B-J 89.11
- Dissimilar Metal 4
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition including Summer 1978 Addenda, Table 1WB-2500-1 Category B-F: Item B5.10 and Category B-J: Item B9.11, requires the following:
All Welds identified above are to have volumetric and surface examinations performed each inspection interval.
Alternate Test:
4 Perform the second ten year interval examinations on the components listed above during the seventh refueling (RF-7) outage which is eight months prior to the beginning of the second interval.
Examination intervals will be reestablished per Table IWB-2500-1 in the third inspection interval.
Basis for Relief:
First, the second ten year inspection interval begins approximately eight months after RF-7.
Second, by performing these examinations during RF-7, the outlet nozzles will be inspected in the same outage as the inlet nozzles utilizing one Ultrasonic Testing (UT) acquisition system.
This provides common acquisition data which will increase the reliability of the data as it relates to the condition of both the inlet and outlet nozzles. Third, the reactor lower internals will be removed during the RF-7 outage as opposed to being in place during the second interval inspection. This prevents the possibility of the remote examination equipment causing damage to the lower internals during the second interval inspection.
Furthermore, delaying these examinations will results in the following hardships:
(1)
The predicted dose related to performing these examinations in the second 10 year interval is 2.5 REM greater than performing the inspection during RF-7.
- Attachment to Document Control Desk letter l
NRR 920004 Bage 2 of 2 s
i (2)
The additional manpower, cost, and critical path outage time 1
associated with performing these examinations in the second interval would be saved by performing the examinations in RF-7.
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in summary, performing the examinations approximately eight months prior to the second ten year interval creates several advantages and avoids some j
hardships without affecting the level of quality or safety in the plant.
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