ML20211E592
| ML20211E592 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/23/1997 |
| From: | Subalusky W COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9709300153 | |
| Download: ML20211E592 (6) | |
Text
Contmonwraith I'divin Conigun) laNille Generating 5tation 3dit North list Ibud M.trwillet 11...I 4 i1975 ?
Trf 81%3%W61 l
l I
1 1
September 23,1997 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
LaSalle County Restart Meeting on August 28,1997 LaSalle County Station, Units 1 and 2 Facility Operating License NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
References:
1.
W. T. Subalusky letter to U.S. NRC, transmitting Revised LaSalle County Station Restart Plan, dated August 27,1997, 2.
W. T. Subalusky letter to U.S. NRC, transmitting LaSalle County Station Restart Action Plans, dated September 16.1997.
3.
T. J. Maiman letter to U.S. NRC, transmitting Independent Safety Assessment Team Report dated February 18,1997.
s
\\
On August 28,1997, LaSalle County Station personnel met with the NRC at Region ill offices in Lisle, Illinois, to discuss LaSalle's progress toward completing the LaSalle Station Restart Plan. We appreciate the opportunity
_3-l to discuss our progress at the meeting. There were several issues discussed at the meeting that warrant additional information. That additional information is provided in this letter.
(
At the meeting, a request was made for our detailed Action Plans, described in Reference 1. We have now provided those Action Plans as indicated by Reference 2.
9709300153 970923 PDR ADOCK 05000373 P
_ m,,,
During the August 28,1997 meeting, the Safety Assessment Manager discussed an ongoing Site Quality Verification (SQV) issue related to whether the Restart Plan Action Plans adequately documented the root causes of performance problems identified in the Fall 1996 Independent Safety Assessment conducted at LaSalle, Reference 3. The site transmitted and SQV reviewed the site't, response to this issue. While there is not direct mapping of performance root causes to Restart Plan Action Plans, we believe the methodology used to develop the Action Plans adequately addresses the root causes. To date, verification activities have not identified a generic problem with causal factors and actions to address those causes. We will be glad to discuss this with you at the next Restart Meeting scheduled for October 1,1997.
Time constraints at the August 28 meeting limited the discussion on our Corrective Action Program improvements. A new program was put in place and implementation has been ongoing for the past several months. We completed a site self-assessment in August and Corporate Oversight recently completed a review of the program's implementation. Based on these reviews, we believe the Restart Action Plan Strategy is complete and will be presenting th!s to the NRC Staff at the scheduled October 1,1997, Restart Meeting.
In the last meeting, a question was raised concerning the material condition issues identified for completion during L1F35. As you know, the System Functional Performance Reviews (SFPR) and system walkdowns were completed mid-summer. Senior Management has reviewed the results of that effort, which with other issues identified during corrective maintenance, has resulted in approximately 252 Design Change Packages and over 1200 Engineering Requests identified for resolution prior to Unit restart. This represents major improvements in key systems such as Reactor Water Cleanup (RT), Electro-hydraulic Control (EHC) and the Control Room and Auxiliary Electric Room Ventilation (VCNE). The detailed listings of the systems' problems and resolutions are available at the site for your review and will be summarized in a subsequent meeting with you.
During the meeting a question was raised regarding the number of Technical Specification changes required prior to restart of either unit. To date, six changes have been identified: Main Control Room, Auxiliary Electric Equipment Room, and Standby Gas Treatment Ventilation Systems Filter Testing; Control Room Radiation Monitoring instrumentation; Feedwater/ Main Turbine Reactor Vessel Water Level High Trip; Change in the Definition of Channel Calibration to exempt RTDs and Thermocouples; High Energy Line Break Leak Detection; and Post-LOCA Hydrogen Iristrument Channel Gas. Currently, one change has been approved by the Staff, two changes are under review by the Staff, and the three remaining changes should be submitted by the middle of October. The NRR Project Manager has been notified of the tentative schedule for submittal.
1 There was some discussion at the meeting regarding what UFSAR W
discrepancies might not be corrected prior to restart. As stressed at the meeting, UFSAR issues have been reviewed against the restart criteria.
Each of the 24 UFSAR issues currently meeting the restart criteria will be resolved prior to restart. We would like to provide the detailed information regarding the specific changes to the appropriate NRC staff personnel and encourage near term site visits to review these issues.
Two " backup" transparencies associated with Out-of-Service issues were used at the meeting and were not in the presentation package provided to the Staff at the meeting. They are included as an enclosure to this letter.
Finally, I encourage the members of the Restart Oversight Panel to visit LaSalle to get a more detailed review of the results of our System Functional Performance Review and other ongoing activities. We are looking forward to showing you our progress as we work toward the safe restart of the LaSalle Units.
If there are any questions or comments concerning this letter, please refer them to me at (815) 357-6761, extension 3600.
Respectfully, W. T. Subalusky Site Vice President LaSalle County Station Enclosure cc:
A. B. Beach, NRC Region til Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle F. Niziotek, Office of Nuclear Facility Safety -IDNS
)
i-1r
9 e
2 ENCLOSURE BACKUP TRANSPARENCIES AUGUST 28,1997 NRC PUBLIC MEETING
PCTCent kkkb k
h h
4 to C
D Sign on/off Ya
- l N
%h Work
~
, g Authorization D
Scheduling g g Conillets Q
b Configuration Control m
Q Field Work k4 Scheduling bti%if;l I
I 3
Labeling Doc Prep I
i I
I I
I Component g
g Manipulation Q
~
[
Percent kkbb b
4 m
C Training
-l Work Q
l Authorization
-4 Sign On/Off O
l Planning NQ Component Manipulation Ni Proced, e Prep N
Configuration Control D
Labeling
,k I
Q n-.
,l I DocPrep i
mO Scheduling t,
age u;,.
- sp;d I
I I
I I
I I
I I
_ _ _ _ _ - _ _ _ _ _ _