ML20070S085
| ML20070S085 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/18/1994 |
| From: | Lockwood J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-13, NUDOCS 9405230208 | |
| Download: ML20070S085 (2) | |
Text
4 a'
C:mmonw;2lth Edison j
LaSalle County Nuclear Station 2601 N. 21st. Rd.
I Marseilles, Illinois 61341 Telephone 815/357-6761 i
May 18, 1994 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 j
Attention:
Document Control Desk l
Subject:
LaSalle County Station Units 1 and 2 Service Water System Problems Affecting Safety-Related Equipment.
(Supplemental Response to NRC Generic Letter 89-13)
NRC Docket Numbers 50-373 and 50-374
References:
1)
M.H. Richter letter to NRC dated January 29, 1990; Generic Letter 89-13 Responses.
The purpose of this letter is to provide an update on LaSalle County Station's (LSCS) actions pertaining to NRC Generic Letter 89-13 with regard to Residual Heat Removal (RHR) heat exchanger testing.
In the original response to the NRC (Reference 1) it was stated (page D-5) that the Core Standby Cooling System (CSCS)
Heat Exchanger Testing Program would be revised with new testing / maintenance requirements which would require monitoring and trending of the heat transfer performance, or monitoring flowrates and differential pressures, along with inspection and maintenance.
Following the initial three tests and/or inspections, a final frequency for testing and/or inspections will be chosen for an ongoing monitoring program.
LaSalle County Station now intends to continue to perform the service water flowrate/dP testing at least every 18 months for each RHR heat exchanger, and perform a visual inspection (along with cleaning and maintenance as needed) of the service water l
side (tube side) of each of the RHR heat exchangers at least every 5 years.
The heat transfer testing will no longer be i
performed on a regular basis for the following reasons:
A.
For Unit 1, the "1A" RHR heat exchanger has had 3 heat transfer tests without any cleaning between tests and all have passed. For Unit 2, the "2L'" RHR heat i
exchanger has had 3 heat transfer teats without l
cleaning and all have passed.
The "2B" and the "2A" l
RHR heat exchangers have each had 2 helt transfer tests without cleaning between them and have passed.
/
9405230208 940519 q{kM T
PDR ADOCK 05000373
/
l P
PDR i
0
9 B.
Periodic visual inspections of "As-found" conditions of the service water side of each RHR heat exchanger during the previous 2 refuel outages for Unit 2 and the previous refuel outage for Unit 1 have shown no significant fouling of the heat exchangers.
C.
The Service Water Chemical Feed system has been seen to reduce fouling system-wide.
D.
It is often difficult to obtain the temperature differences required in order to perform the heat transfer testing.
The suppression pool has a maximum temperature limit, while the cooling lake has a limited temperature range.
This restricts the available differential temperatures to get good data.
If there are any questions or comments regarding this supplemental response to Generic' Letter 89-13, please contact me at (815) 357-6761, extension 2246.
The LaSalle Site Vice President has reviewed and concurred with this updated response.
Sincerely,
}
l
-Johnny Lockwood Regulatory Assurance' Supervisor LaSalle County Station I
l cc:
J.B. Martin, Regional Administrator-RIII Senior Resident Inspector-LSCS A.T. Gody, Jr.,
Project Manager, NRR Office of Nuclear Facility Safety-IDNS D.L.
Farrar, Nuclear Regulatory Services Manager,-NORS Station File i
_