ML20050C630
| ML20050C630 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/30/1982 |
| From: | Wells D DETROIT EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, EF2-57154, NUDOCS 8204090187 | |
| Download: ML20050C630 (1) | |
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|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARNRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997
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Text
Donald A. Wells U n 7r O a w A..
/ w e O t a) 2?79A7 2000 Second Ave %e ISOn Detroit, Michigan 48226 013) 237-8000 March 30, 1982 EF2-57154 (Revised)
LD A
Mr. James G. Keppler, D
Regional Administrator gg Region III NO 9
U.
S. Nuclear Regulatory Commission MER $ gb I 799 Roosevelt Road
[,-
E NWit Glen Ellyn, IL 60137 TD
Dear Mr. Keppler:
//
4
Subject:
Interim Report of 10CFR50.55(e) Item on RilR Service Water Piping Design Deficiency (#57)
On February 18, 1982, Detroit Edison's Mr. 11. A. Walker, Supervisor-Construction Quality Assurance, telephoned Mr. J. Konklin of NRC Region III to report on a problem with RilR Service Water Piping Design Deficiency at the Fermi 2 site.
In evaluating a request from Edison Start-Up to perform a hydrostatic test of the RilR service water piping at 44 F rather than the 55 F required, Engineering had noted that the minimum safe temperature was 70 F.
Operation at below this temperature could result in brittle fracture failures. This problem exists in both divisions. The RHR service water system was designed to operate at temperatures as low as 40 F.
The design pressure for the system is 175 psi, hydrostatic test pressure is 219 psi, and typical system operating pressures vary from 90-105 psi.
A complete analysis of the RllR service water piping system is being made to determine if the system is safe at the operating temperatures and pressure.
Thie analysis may require as much as two months.
Another report on this item, either interim or final, is scheduled to be sent to you on or before July 16, 1982.
If you have questions concerning this matter, please contact Mr.11. A. Walker, Supervisor-Construction Quality Assurance.
Very truly yours, 8204090187 820330 7
9 S
'j tf PDR ADOCK 05000341 llAW :mb cc:
Mr. Richard DeYoung, Director Office of Inspection and Enforcement Division of Reactor Inspection Programs U. S. Nuclear Regulatory Commission g
g
/
Washington, DC 20555 Mr. Bruce Little, Resident Inspector 68 0 i
FIO" U. S. Nuclear Regulatory Commission 6450 North Dixie flighway
"'/
Newport, M1 48166 APR 2 882