ML20198N899
| ML20198N899 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/14/1998 |
| From: | Stanley H COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20198N902 | List: |
| References | |
| NUDOCS 9801210249 | |
| Download: ML20198N899 (2) | |
Text
,
Cornmenwechh IWm company i
l@0 Opus th e Downers Grove, U. 6051M701 January 14,1998 U. S. Nuclear Regulatory Commission Washington, D.C 20555 Attention:
Document Control Desk
Subject:
Braidwood Unit 13 Volt IPC Full Cycle Operation Technical Basis Supplement to Braidwood Unit 1 Cycle 7 Interim Plugging Criteria Report Braidwood Unit 1 -
NRC Docket Number: 50-456
References:
1.
M.D. Lynch letter to 1. Johnson dated November 13,1997, transmitting Projected Braidwood Station Unit 1 End of Cycle Steam Generator Tube Leakage due to Outer Diameter Stress Corrosion Crack Indications Restricted From Burst 2.
December 11,1997, meeting between the Nuclear Regulatory Commission and the Commonwealth Edison Company Braidwood Full Cycle Justincation 3.
T. Tulon letter to the Nuclear Regulatory Commission dated December 11,1997, transmitting Comed's Response to the Nuclear Regulatory Commission Letter dated November 13,1997 In the Reference I letter the Nuclear Regulatory Commission (NRC) stated that the Staff could not accept the Commonwealth Edison Company (Comed) proposed methodology for estimating the end of cycle steam generator tube leakage under postulated accident conditions for Byron Unit I and Braidwood Unit 1. Additionally, the Staff requested that Comed provide justification for not conducting a mid cycle inspection at Braidwood Unit i of the outer diameter stress corrosion cracking (ODSCC) indications len in service. At the Referenced meeting and in Reference 3, Comed stated that they had performed extensive review ofindustry growth rate data associated with steam generator tubing ODSCC at the tube support plate. Based upon these reviews and conservative application of voltage dependent growth rate methodologies, Comed has concluded that all tube integrity requirements will be met for Braidwood Unit 1 Cycle 7; therefore, full cycle operation isjustified. Comed also committed to submit a report to documenting this conclusion. The Attachment provides that infom1ation.
Braidwood has administratively limited reactor coolant dose equivalent iodine to 0.05 microCuries/ gram and a Technical Specification amendment request for operation at this f
limit has been submitted for NRC approval.
/
!(
K:nla\\bwd\\ January 15. doe:1 1{1{g]
9901210249 990114
[4
- i. '.. * **'*
PDR ADOCK 05000456 3
.. _ _. ? '.
)
t NRC Document Control De'sk -'
2-January 14,1998 f
If you have any questions concerning this correspondence, please contact this office.
l s
. Sincerel gf 4
- II. C St ley
. PWR Vice President Attachment l
Cc:
Byron /Braidwood Project Manager-NRR Senior Resident Inspector Braidwood Regional Administrator-Rill Office of Nuclear Safety IDNS '
4 4
k r
- K:nla\\bwduanuary 15. doc:2 ';
~
.