ML20073G355
| ML20073G355 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/25/1991 |
| From: | Schuster T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| TAC-63261, NUDOCS 9105030266 | |
| Download: ML20073G355 (2) | |
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' Downers Grove. imnois 60515 April 25,1991 Dr. Thomas E. Murley, Director Office Of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 205S5 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Augmented Inservice ins ction of Additional Emergency Core Coolin System (ECCS) Welds TAC #63261 (U2)Ji0 45_4 and_EO-455 NBC_D_ocketilos
Reference:
(a) April 22,1991 Teleconference between Byron Slation personnel, Byron NLA, and NRC Staff (b)
- Inservice Inspection Program, Section 2, Plan for Nondestructive Examination (NDE)"
Revision 2b, Note 10
. committed to performing augmented inservice inspections (of ECCS welds inclu in accordance with the discussion of Reference a), Byron Station has
. welds of the containment spray system. The specifics of this inspection program are outlined in Reference (b).. A draft note of the Inservice inspection Program, has been attached for your information. The inspections will begin durin the next refuelin outage for each unit and will be com eted prior to the end of t e a plicable unit'g 1
s 10 year ISIinterval. It should be noted hat the attached Reference is for information only, with the formal submittal of the NDE Program Rev 2b expe In August of 1991 prior to the next Unit i refueling outage..
Please d! rect any questions you may have concerning this matter to this Respectfully, lJttlb-kpJT 1
T.K. Schuster -
Nuclear Licensing Administrator -
- Enclosure cc:
Wayne Kropp-Byron Station
. A. Bert Davls Rill Okf A. Hsia NRR-TKS/sel:lD867:5 kbO
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5 ENCLOSURE NOIfL10 The NRC has expressed a concern dealing with intergranular stress-corrosion cracking in lines that contain stagnant, borated water. Byron Station will perform augmented volumetric examinations on Class 2 Emergency Core Cooling Systems [] Chemical and Volume V), Residual Heat Remeval(RH), and Safety In!ection (SI) and the Containment S S) System which are not currently subject to volumetric examination as required b de.
he examinations e, hall include a 7%% sample of all circumferential welds on piping hat is In the CV, RH, SI, or CS systems, is greater than four inches nominal pipe size, and contains stagnant, borated water. Nominal pipe wall thickness and pressure / temperature exemptions do not apply.
TKS/scl:lD867:6 DRAFT
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