ML20090B156
| ML20090B156 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/26/1984 |
| From: | Farrar D COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20090B136 | List: |
| References | |
| NUDOCS 8407120325 | |
| Download: ML20090B156 (2) | |
Text
N C::mmonw;11th Edis:n
{ ;) one First Nabonal Plaza. Chicago. Ilknois
+
V Address Reply to: Post Office Box 767 Chicago Illinois 60690 June 26, 1984 t
Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
LaSalle County Station Units 1 and 2 Response to Inspection Report Nos. 50-373/84-03 and 50-374/84-02 NRC Docket Nos. 50-373 and 50-374 Reference (a):
W.
D. Shafer letter to Cordell Reed dated May 31, 1984.
i
Dear Mr. Keppler:
This letter is in response to the inspection conducted by Messrs. C. D. Evans, S. C. Guthrie, W. G. Guldemand, and M.
J. Jordan on April 16 through May 11, 1984, of activities at LaSalle Lounty Station.
Reference (a) indicated that certain activities appeared to be in noncompliance with NRC requirements.
The Commonwealth Edison Company response to the Notice of Violation is provided in the enclosure.
If you have any further questions on this matter, please direct them to this office.
Very truly yours,
.L.
Farrar Director of Nuclear Licensing i
1m P
Attachment s
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NRC Resident Inspector - LSCS 8407120325 840706 PDR ADOCK 05000373 G
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ATTACHMENT
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f COMMONWEALTH EDIS'UN COMPANY y,
' RESPONSE TO NOTICE OF VIOLATION
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10 CFR 50, Appendix B,< Criterion III states in part:
"The
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design contro1 measures..shall provide for verifying or checking the adequacy of design, such asby the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program."
Technical ^ Specification Table 3.3.2.-2 states an allowable differential flow value of less~than or equal to 87.5 gpm for isolation of the Reactor Water Cleanup System (RWCU).
Contrary to 'ihe above, the testing did not identify the inability of the-RWCU to isolate within the allowed differential flow value.
CORRECTIVE ACTION TAKEN AND NESULTS ACHIEVED Procedu'res LIS-RT-101 and LIS-RT-201 which are used to calibrete infet floi transmitters lE31-N503 and 2E31-N503 have been revised to reflect the, proper spans, and the respective instruments have been ca'librated to the correct values.
The design document (instrument data sheet fT25)'will be updated to indicate the correct calibration
'information.2
's COR'RECtIVE ACTION TAKEN TO AVOID FURTHER NONCOMPLIANCE A review of nineteen Sargent and Lundy instrument data sheets for safety related flow elements in the Diesel Generator, High Pressure Core Spray,~ Fuel Pool Cooling, and Standby Gas Treatment Systems was conducted.
This' review confirmed that the design information on the data sheets and vendor documents agree'with each other in all the cases which were reviewed.
It appears that the problem related to the RWCU inlet' flow instrumentation was an. isolated case and not a generic concern.
DAT$t0F FULL COMPLIANCE Completion of the Data Sheet correction will be by October 20, 198E.
All other corrective actions have been completed.
8857N' N-
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