ML20207D430
| ML20207D430 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/26/1999 |
| From: | Krich R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-06, GL-96-6, NUDOCS 9903090345 | |
| Download: ML20207D430 (2) | |
Text
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Commonwealth Edison Company.
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1400 Opus Place d
Downers Grove,IL 60515-5701 February 26,1999 U.S. Nuclear Regulatory Commission i
ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457
Subject:
Deferral of Supplemental Information for Request for Additional Information Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions" i
References:
1.
Letter from R. Krich (Comed) to USNRC, " Response to Request for Additional Information Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated August 27,1998 2.
Letter from J. B. Hickman (NRC) to O. D. Kingsley (Comed), " Request for Additional Information Related to the Generic Letter (GL) 96-06 Response for Byron Station, Units 1 and 2 and Braidwood Station, Units 1 and 2,"
dated May 1,1998 4
3.
Letter From B. A. Wetzel (NRC) to D. J. Modeen (NEI), " Review of EPRI Technical Report TR-108812," dated October 1,1998
]
j The August 27,1998 letter, Reference 1, provided Commonwealth Edison (Comed)
Company's response to the NRC Request For Additional Information, Reference 2, and also provided supplemental information with regard to the status of the Comed analyses and modifications initiated to close our actions related to Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Bssis Accident Conditions."
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Reference 1 further stated that the response would be supplemented by February 26,1999.
The purpose of this letter is to inform the NRC that the supplemental information for the Byron and Braidwood Stations will be delayed. All the modification work described in Reference 1 is on schedule. However, completion of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section lil, " Rules for Construction of Nuclear Power Plant Components," Appendix F, analysis work for containment penetrations P-5, P-8, P-37, P-55, P-70 and P-71 has been delayed to address o[;;
questions raised by the NRC in Reference 3. Therefore, the supplemental information on tne
'ASME Code, Section ill, Appendix F analysis will not be ready for submittal until October 27, 1999.
T 9903090345 990226 PDR ADOCK 05000454 p
PDR A Unicom Company
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February 26,1999 U.S. Nuclear Regulatory Commission Page 2 Should you have any questions concoming this letter, please contact Mr. S. R. Dort at (630) 663-3741.'
Respectfully,
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R. M. Kri Vice President - Regulatory Services cc:
Regional Administrator-NRC Region 111
- NRC Senior Resident inspector-Braidwood Station NRC Senior Resident inspector-Byron Station t
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