ML20094K069
| ML20094K069 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/12/1992 |
| From: | Schrage J COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9203180152 | |
| Download: ML20094K069 (2) | |
Text
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) Oownzra Grove, Illinois 60515 v
March 12,1992 Dr. Thomas E. Murley, Director Office of Nuclear neactor Re0ulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Quad Cities Nuclear Station Units 1 and 2 Resolution of Questions Portalning to Relief Request for Inservice Inspection Program NBC_DockeLNos,_50 25Aand_5D:265
Reference:
- (a) Commonwealth Edison Company (J. Schrage, et al),
Conference call on March 10,1992 between and NRR (D. Lynch, et al)
(b) J.L. Schrage to T.E. Murley letter dated September 30,1991
Dear Dr. Murley:
During the referenced teleconference (Reference (a)), Commonwealth
. Edison Company (CECO) representatives provided information to NRR in response to questions concerning the accessibliity of welds discussed in a Quad Cities Station Relief Request (Reference (b)). The purpose of this letter is to document the information presented during the telecon"erence.
The original Relief Request stated that approximately 60% of the Reactor Vessel Stabilizer Bracket weld surfaces were accessible. As such. a Section XI Class 1 Surface Examination could be aerformed on this portion of the weld surfaces. This examination would then be supp emented with a visual examination (VT-3/4).
Subsequent inspections of the equipment configuration during the current refuel wtage (O2R11) have indicated that approximately 78% of the vertical weld surface and 100% of the top horizontal weld surface are accessible to a visual examination. However,100% of the bottom weld surface is inaccessible to a visual I
examination. This is due to the close proximity of the bottom weld surface to the top of the biological shleid. In addition, the proximity of the Reactnr Vessel Stabilizer Bracket to the Reactor Vesselinsulation does not allow for Surface Examination of any portion
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s Dr.. Thomas E. Murley March 12.1992 of the weld surf ace. This insulation must be removed in order to perform a Surface Examination. Removal of the insulation would require the removal of screws holding two panels of insulation together. The screws holding the insulation panels together are located directly behind a bar running horizontally through the Reactor Vessel Stabilizer Brackets. The clearance between this bar and the insulation (approximately two inches) does not allow for expeditious removal of the screws. In addition, reinstallation of the screws is severely hindered by the clearances. This reinstallation is necessary to ensure the long term structural integrity tight the adjacent Reactor Vessel insulation panels.
In l'ght of the revised accessibility of Reactor Vessel Stabilizer Bracket weld i
surfaces, CECO will perform a VT t Visual Examination of the accessible portions of the weld surfaces (approximately 78% of the vertical sur' aces and 100% of the top horizontal suriaces).
Please direct any questions or comments to John L. Schrage at 708 515 7283.
Respectfully,
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/'dohn L. Schrage NucW,ar Licensing Administrator cc: - A. Bert Davis, Regional Administrator Rill L.N. Olshan, NRR Project Manager-Ouad Cities T.E. Taylor Senior Resident inspector-Ouad Citios D. Lynch, NRR Project Manager-Ouad Cities i
/scl:1209.54