ML20087Q106
| ML20087Q106 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/29/1984 |
| From: | Gerrets T LOUISIANA POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 154, WK3K84-0743, WK3K84-743, NUDOCS 8404100331 | |
| Download: ML20087Q106 (2) | |
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I' l.OUISIANA P O W E F1 & L 1 G H T! P O BOX 6008
- NEW OHLEANS. LOUISIANA 70174 242 oaAnoNoE s1nar (504) 366-2345 UTIUTIES SYSTEM March 29, 1984 W3K84- 0743 hbb i-Mr. John T. Collins
-s U. S. Nuclear Regulatory Commission j
i,M Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
REFERENCE:
Telecon C. Hooper (LP&L) and D. Hunnicut (NRC (IV) on February 16, 1984
Dear Mr. Collins:
SUBJECT:
Waterford SES Unit No. 3 Docket No. 50-382 Potentially Reportable Deficiency No. 154 "Possible Inadequate Circuit Design That Could Prevent a fleactor Trip" Final Report On February 16, 1984, a problem with a Reactor Trip circuit design, that could possibly cause a failure to trip was reported as Potentially Reportable Deficiency No. 154. Further evaluation of the previously described condition indicates this condition is not considered reportable pursuant to the requirements of 10CFR50.55(e).
EVALUATION During System Preoperational testing, it was noted that channels B, C, and D
-test lamps did not fully de-energize (dimly lit) when the Plant Protection System trip paths were tested. This incident raised a concern that if the leakage current was sufficiently high, this could have prevented the undervoltage coils from de-energizing, thereby preventing a reactor trip.
After reviewing the problems with the Combustion Engineering (C.E.) site office, it has been ascertained that the problem identified in PRD #154 and CIWA 840545 is not reportable since the magnitude of the leakage current measured was approximately 3 milliamps (ma), whereas the manufacturer's maximum allowable rating is 9 ma.
C.E. also confirms that a leakage current of 62 ma simultaneously through 2 relays per channel, and a minimum of a two channel malfunction is required to prevent a reactor trip.
8404100331 840329 PDR ADOCK 05000382 I.E-27.
3, o
e-Mr. John T. Collins March 29, 1984
- W3K84- 0743 Page 2 Based on the above evaluation, this condition is considered not reportable.
Very truly yours, ffAm T. F. Gerrets Quality Assurance Manager TFC:CNH:VBR.
cc: Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.
20555 (15 copies)
Director Office-of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. E. L. Blake Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
Washington, D.C.. 20036 Mr..W. M. Stevenson Monroe & Lemann 1424 Whitney Building New Orleans, Louisiana 70130 Mr'. W. A. Cross 7910 Woodmont Avenue Suite 1200
-:Bethasda, Maryland 20814