ML20087F871
| ML20087F871 | |
| 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 | |
| 150, W3K84-0506, W3K84-506, NUDOCS 8403190250 | |
| Download: ML20087F871 (2) | |
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LOUISIANA / 142 DELARONDE STREET POWER & LIGHT / P O BOX 6000
- NEW ORLEANS. LOUISANA 70174. (504) 366 2345
$uSNESYE March 9, 1984 W3K84-0506 Q-3-A35.07 Mr. John T. Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
REFERENCE:
Telecon C. Hooper (LP&L) and W. Crossman (NRC IV) dated February 10, 1984
Dear Mr. Collins:
SUBJECT:
Waterford SES Unit No. 3 Docket No. 50-382 Potentially Reportable Deficiency No. 150
" Plant Depressurizarion During Shutdown, Potential For" Final Report On February 10, 1984 a problem with the alarm setpoints for the Low Temperature Overpressure Protection System (LTOP) was reported as Potentially Reportable Deficiency No. 150. Further evaluation of the previcusly described condition indicates this condition is not considered reportable pt.rsuant to 10CFR50.55(e).
EVALUATION Relief valves SI-486 and SI-487 protect the Shutdown Cooling System (SDCS) from inadvertent RCS pressurization when the suction line isolation valves are open. Each relief valve is designed with sufficient capacity to mitigate the most limiting transients (inadvertent safety injection actuation or a reactor coolant pump start as described in FSAR Subsection 5.2B).
Once the SDCS is aligned when RCS pressure is below 392 psia, no further administrative or procedural controls are needed to ensure proper overpressure protection. Therefore, if the alarm setpoint was left uncorrected, an inadvertent pressure transient that increases RCS pressure would still be terminated automatically by the SDCS relief valves when pressure reached 430 psia and protect the pump seals. The design pressure of the LPSI pump seals (435 psia) would never be exceeded.
In addition, the discharge from safety relief valves SI-486 and SI-487 is directed to the containment leak measuring tank. Flow from this tank is recorded and alarmed in the main control room.
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Q' P-Mr. John T. Collins Macch 9. 1984
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LSince safe operation of the plant would not be jeopardized, this deficiency is
' considered not reportable pursuant to the requirements of 10CFR50.55(e).
..Very truly' yours.
A **
T. F. Gerrets h
. 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, Pfttman, Potts, & Trowbridge 1800 M Street, N.W.
Washington, D.C.
20036 Mr. W. M. Stevenson
. Monroe & Lemann 1424 Whitney _ Building New Orleans, Louisiana 70130 0
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