ML20196F621
| ML20196F621 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/01/1998 |
| From: | Krich R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-01, GL-97-1, NUDOCS 9812070090 | |
| Download: ML20196F621 (2) | |
Text
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Comnanwealth Ldimn Company 1400 Opus Plac e Ix3wners Grove, IL 60515 5701 l
l l
Comed December 1,1998 l
l U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 1
Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Notification of Revised Date for Submittal of AdditionalInformation Regarding NRC Generic Letter (GL) 97-01, " Degradation of CRDM/CEDM Nozzie and Other Vessel Closure Head Penetrations"
Reference:
NRC Memorandum from J.F. Haro!d (NRR) to S.S. Bajwa (NRR), " Summary of the Meeting on September 29,1998, Between the NRC Staff and Members of l
the Pressurized Water Reactor (PWR) Owners' Groups and Nuclear Energy Institute (NEI) to Discuss the Status of Multi-Plant Action TAC Nos. Opened in
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Regard to issuance of Generic Letter (GL) 97-01," dated November 5,1998 7
l v
I On September 2,1998, the Nuclear Regulatory Commission (NRC) issued a request for additional information (RAl) to Commonwealth Edison (Comed) Company to support the review 3
of Comed responses to Generic Letter (GL) 97-01, " Degradation of CRDM/CEDM Nozzle and 11 -
Other Vessel Closure Head Penetrations." The RAI letter asked that Comed provide additional
- information for each of our pressurized water reactor (PWR) designed plants within 90 days of i
the date of the RAI letter, i.e., by December 1,1998. However, in the NRC memorandum referenced above, the NRC agreed that licensees could extend their plant response submittal i
l dates to January 15,1999, if additional time is necessary to incorporate the industry generic l
response into the plant-specfic response.
I Comed will provide the information requested by the RAI letter on or before January 15,1999.
We require additional time to incorporate the industry generic response information into our plant-specific responses for the Braidwood and Byron Stations.
9812070090 981201
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t, December 1,-1998 L
U.S. Nuclear Regulatory Commission Page 2 l
l If you have any questions concerning this correspondence, please contact Mr. J.A. Bauer at i
(630) 663-7287.
Respectfully, L
v 7
R.M. Krich Vice President - Regulatory Services l
i cc:
Regional Administrator - NRC Region ill l
NRC Senior Resident inspector - Braidwood Station NRC Senior Resident inspector - Byron Station.
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