ML20101N191
| ML20101N191 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/28/1996 |
| From: | Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9604080284 | |
| Download: ML20101N191 (2) | |
Text
Commonwcalth Edison Company
,O IMalle Generating Station 2601 North 2191(oad
]
Marvilles, IL 613 i1975' TelH1505'6"61 March 28,1996 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 P
Subject:
LaSalle County Nuclear Power Station Units 1 and 2 Comed Submittal Providing AdditionalInformation Discussed During the March 26,1996 Conference Call Regarding the Main Steamline Isolation Valve (MSIV)
Leakage Control System (LCS) Attemate Leakage Treatment (ALT) Path Submittal NRC Docket Nos. 50-373 and 50-374
Reference:
G. Benes letter to U. S. NRC, dated August 28,1995, LaSalle Submittal Regarding Elimination of the Main Steamline Isolation Valve (MSIV) Leakage Control System (LCS) Altemate Leakage Treatment (ALT) Path.
The Referenced submittal transmitted the original application for amendment to propose changes to revise LaSalle Unit 1 and LaSalle Unit 2 Technical Specifications to support elimination of the Main Steam Isolation Valve Leakage Control System (MSIV-LCS), and instead use the main steam line drains and main condenser to process MSIV leakage. The purpose of this letter is to provide additional information that was discussed in the March 26, 1996 conference call between NRR and Comed.
In Sections 8 and 9 of Attachment H and Attachment I (Sargent & Lundy Seismic Walkdown Report for LaSalle Unit 1 and LaSalle Unit 2 respectively) of the Referenced submittal, it was stated that the " process sampling line has no automatic or powered isolation valve to isolate leak path". It was further stated that, "One of the following actions needs to be taken (for the process sample line):
- 1. Radiological effect of leakage path should be evaluated.
- 2. Automatic / reliable powered isolation should be installed.
- 3. Manualisolation valve should be controlled closed administratively."
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9604080284 960328 PDR ADOCK 05000373 P
PDR D
A Unicom Company
4 Comed has performed the third action and the manual isolation valve is being controlled administratively as a locked closed valve, for Unit 1. The associated Unit 2 valve will be controlled administratively in the same manner prior to startup from the L2R07 Refuel Outage, when the Unit 2 t
proposed Technical Specification to eliminate the MSIV-LCS is scheduled to be implemented.
The original Significant Hazards Consideration, that was included in the Referenced submittal, remains valid.
f If there are any further questions or comments concerning this letter, please refer them to me at (815) 357-6761, extension 3600.
Respectfully,
/
t ce R. E. Querio Site Vice President LaSalle County Station Enclosure cc:
H. J. Miller, NRC Region lli Administrator P. G. Brochman, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle Office of Nuclear Facility Safety - IDNS Central File l
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