ML20087L246
| ML20087L246 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/09/1984 |
| From: | Gerrets T LOUISIANA POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 148, W3K84-0499, W3K84-499, NUDOCS 8403270102 | |
| Download: ML20087L246 (2) | |
Text
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E LOUISIANA f 242 octAnoNoe srnter P OWE R & L1G HT/ P o. box 6008
- NEW OnLEANS. LOUISIANA 70174 * (504) 366-2345
$U!![S dYS March 15, 1984 0W3%@$3.07 6'3 4
wa zo se4 Mr. John T. Collins d
j Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
REFERENCE:
Telecon C. N. Hooper (LP&L) and D. Hunnicut (NRC IV) on February 6, 1984 Telecon C. N. Hooper (LP&L) and W. Crossman (NRC IV) on March 8, 1984
Dear Mr. Collins:
SUBJECT:
Waterford SES Unit No. 3 Docket No. 50-382 Potentially Reportable Deficiency No. 148 "ASCO Solenoids and NAMCO Limit Switches" Final Report On February 6, 1984, a problem with the verification of ASCO Solenoids and NAMCO Limit Switches was reported as Potentially Reportable Deficiency No.
148. Further evaluation of the previously described condition indicates this condition is not considered reportable pursuant to the requirement of 10CFR50.55(e).
EVALUATION An extensive search of documentation has found that the documentation is available to verify traceability of all NAMCO switches involved.
It addressing the ASCO solenoids, 70% of the solenoids were found to have the s
required documentation from manufacturer through installation. Twenty-six per cent (26%) of the solenoids were found to be traceable to the manufacturer, however, installation documentation was deficient. These solenoids will be removed and remounted with supporting documentation. The remaining 4%
(quantity 3) were missing manufacturer data plates. This was due to a "C" clip, which holds the data plate, having been removed. From visual inspection, the solenoids were ASCO Nuclear Grade.
These solenoids will be replaced to provide traceability and documentation.
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Mr. John T. Collins March 15, 1984 W3K84-0613 Page'2
. EVALUATION.(Continued)
In-the above cases, the equipment was utilized in the " top works" of process valves. By design, the process valves will fail in a safe condition should a component in the top works fail. Therefore, the safety of the plant will not be affected.
Based on the above, this PRD is considered not reportable.
-Very truly yours,-
T. F. Gerrets Corporate Qaality Assurance Manager
'TFG:CNH:SSTG cc: Director Office of: Inspection & Enforcement U. S._ Nuclear Regulatory Commission-Washington, D.C.
20555 Director 4
' Office of Management Information and Program Control U. S. Nuclear Regulatory Commission
- Washin8 ton,-- 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
. Records Center Institute of Nuclear Power Operations 1100. Circle 75 Parkway, Suite 1500 Atlanta,' Georgia
-30339 Mr.:W. A. Cross 7910 Woodmont Avenue Suite 1200 Bethasda,, Maryland-20814
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