ML20080R743
| ML20080R743 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/01/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9503100057 | |
| Download: ML20080R743 (3) | |
Text
..
].i.
Braidwood Nuclear Power Station
'\\
Route #1, Box 84 Braceville, Illinoes 60407 March 1, Iggi ne sus-2801 -
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn:
Document Control Desk
Subject:
Braidwood Station Unit 1 Mid-Cycle Inspection NRC Docket Number 50-456
References:
1)
D. Sacccxnando letter to Nuclear Regulatory Commission dated October.17, 1994, transmitting the Safety Assessment for Byron Unit 1 2)
J. Bauer letter W. Russell dated September 7, 1995, transmitting S
lemental Information Regarding ication for IPC Amendment 3)
R. Assa letter to D. Farrar dated August 18, 1994, transmitting the Safety Evaluation for Amendment 54 4)
D. Saccomando letter to the Nuclear Regulatory Comnission dated February 27, 1995, transmitting Additional Information Regarding Braidwood Unit 1 Mid-Cycle Outage Plan 5)
Teleconference between Conmonwealth Edison Company and the Nuclear Regulatory Ccnmission dated February 28, 1995, Regarding Braidwood Station Unit 1 Mid-Cycle Inspection Reference 3 transmitted the Nuclear Regulatory Comnission (NRC) 's Safety Evaluation Report (SER) for the Use of Interim Plugging Criteria (IPC) for Conmonwealth Edison Comaany (Comed) 's Braidwood Unit 1.
The SER states that," 'Ibe inspection data and repair results of the mid-cycle insaection, along with the licensee's safety assessment, willlae reviewed by the staff prior to restart from the mid-cycle outage."
The Reference teleconference was held to clarify this statement from the SER.
The following is Comed's understanding of that teleconference.
Braidwood Station wIll transmit the steam generator tube inspection data and repair results to the Staff before restart.
1 k:nla\\twl\\stup\\$
9503100057 950301 I 0
~
PDR ADOCK 05000456 Q
PDR l
y-q NRC ' Document Control Desk = March 1,.1995 Braidwood~will rovide-the Staff with a safe assessment consistantwiththatwhichwaspreviouslysubttted by Byron-
' Station Unit 1 following their most-recent inspection.
This..
-assessment which was transmittedLvia Reference 1, was reviewed and previously accepted by the NRC. This safety assessment:followed the Draft Generic Letter with the exceptions previously identified via Reference 2. The following identifies the differences between the upcoming-Braidwood safety assessment and the Byron safety assessment:
t Braidwood Station will not pull any steam generator.
tubes during the midcycle outage, this is consistent ~
with the Draft Generic Letter.
Regarding the calculation of. leak and burst, Braidwood j
intends to perform these calculations in accordance.
with WCAP 14277, "SLB Leak Rate and Tube Burst-Probability Analysis Methods'for ODSCC at TSP Intersection."
This information was previously transmitted to the Staff via Reference 4.-
Additionally, the Staff and Comed agreed that,
" Calculation of leakage and of conditional burst probability (mode 4) uses the as found end of midcycleto be performed to service voltage distribution (as opposed to a projected distribution)."
Regarding the data base that will be used for the calculation of leak and burst, Braidwood Station will-.
use the same data base as on used with the following exception: Byron Cycle 6 t pull results will be included, and the model boiler specimen 598-1 will not' be included in this data base.
Also per the Reference teleconference, it is Comed's t
understanding that after the safety assessment is transmitted to the Staff, Braidwood Unit 1 will proceed with unit startup, unless otherwise notified by the NRC.
1 i
k:nla\\bwd\\stup\\6 i
l
y 9
NRC Document Control Desk March 1, 1995 t-If you have any guestions concerning this correspondence, please-contact this office as soon as possible.
r S'
,erely, -
W' u
Denise M. Sa c do Nuclear Lice sing Administrator cc:. D. Lynch, Senior Project Manager-NRR R. Assa, Braidwood Project Manager-NRR S. Dupent, Senior Resident Inspector-Braidwood J. Martin, Regional Administrator-RIII.
Office of Nuclear Safety-IDNS kinla\\twi\\stup\\7