ML20236W392
| ML20236W392 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/30/1998 |
| From: | Krich R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9808050247 | |
| Download: ML20236W392 (4) | |
Text
Commonwealth I:dison Company
-v.,
14tAl Opus Place Downers Grove, II, 60515-5701 I
July 30,1998 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington. D. C. 20555 - 0001
Subject:
Revision to Report Submitted Under 10 CFR 50.46, " Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors."
Byron Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. STN-50-454 and STN-50-455 Braidwood Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 l
NRC Docket Nos. STN-50-456 and STN-50-457
Reference:
R. M. Krich (Commonwealth Edison) to US Nuclear Regulatory Commission letter dated April 23,1998.
The purpose of this letter is to revise the 199810 CFR 50.46 Report (Reference). Page 8 of Attachment 1 (i.e., Byron Station Unit 2, Large Break Loss of Coolam Accident (LOCA)) of the transmittal inadvenently stated that the total peaking factor (i.e., FQ) and nuclear enthalpy rise hot channel (i.e., FAH) as 2.5 and 1.65 respectively. The correct values of FQ and FAH should have been 2.6 and 1.7 respectively. This error has no j
impact on the Peak Cladding Temperature (PCT) or any other information provided in the
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l referenced report.
The revised page contained in the attachment replaces the page 8 of Attachment 1 ponion ofthe April 23,1998 submittal (Reference).
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9808050247 900630 PDR ADOCK 05000454 P
PDR l
Uhe'LIC 98-083. doc j_
A Unicum Company i
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(
NRC, July 30,1998 l
We apologize for any inconvenience this may have caused. Please address any commenta
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l or questions regarding this matter to Mr. David Chrzanowski at (630) 663-7205.
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l Sincerely, 4
R. M. Krich Vice President - Regulatory Services t
l
Attachment:
Revised Annual 10 CFR 50.46 Report for Byron and Braidwood, page 8 only 1
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cc:
Regional Administrator-NRC, Rill NRC Senior Resident Inspector-Braidwood Station NRC Senior Resident Inspector-Byron Station l
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l Attachment j
Revised Annual 10 CFR 50.46 Report for Byron and Braidwood Page 8 Only j
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A l.
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PLANT NAME:
Byron Station Unit 2 ECCS EVALUATION MODEL:
Larce Break LOCA REPORT REVISION DATE:
4/1/98 CURRENT OPERATING CYCLE: 2 ANALYSIS OF RECORD Evaluation Model: BASH Calculation: Westinghouse SEC-SAII-4747-C2, July, 996 l
Fuel: VANTAGE 5/ VANTAGE + 17 x 17 l
FQ = 2.60 FNAH = 1.70 SGTP = 30%
i Reference PCT PCT = 1968.0 F MARGIN ALLOCATION -
1 A. PRIOR LOCA MODEL ASSESSMENTS l
Removed Upper Internal Assembly Alignment Pins (Note 2)
APCT =
28.0 F Translation of Fluid Conditions from SATAN to LOCTA (Note 8)
APCT =
15.0 F B. CURRENT LOCA MODEL ASSESSMENTS l
RCS Crossover Leg Volume (Note 9)
APCT =
3.0 F L
NET PCT PCT = 2014.0 F l
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