ML19262A190
| ML19262A190 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/02/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 7910260519 | |
| Download: ML19262A190 (4) | |
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Director Directorate of Licensing
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Dear Sir:
Operating License DPR-50 Docket #50-289 In accordance with Technical Specifications for the Three Mile Island Nuclear Station Unit 1, we are reporting tha. following abnormal occurrence:
(1)
Report Number: A0-50-289/ 75-03 (2a) Report Date:
F.B 2 1575 (2b) Occurrence Date: January 23, 1975 (3)
Facility: Three Mile Island Nuclear Generating Station Unit 1 (4) Identification of Occurrence:
Title:
Loss of Fluid from Hydraulic Shock Suppressor Type:
An abnormal occurrence as defined by the Technical Specifications, paragraph 1.8d, in that the loss of fluid from a hydraulic shock suppressor threatened to cause an Engineered Safeguards feature or system to be incap-ble of performing its intended function.
(5)
Conditions Prior to Occurrence:
The reactor was at hot standby with major plant parameters as follows:
Power:
Co re : 1%
Elec: 0 !f4 (Gross) 6 RC Flow: 140 x 10 lb/hr h2 RC Pressure: 2155 psig 1308
-2_
RC Temp.: 536 F PRZR Level: 200 in.
PRZR Temp. : 650 F (6)
Description of Occurrence:
During a routine inspection of all hydraulic shock suppressors (snubbers) inside the Reactor Building's secondary shicid, one snubber (MUE-43, located on the C high pressure injection line) was found to be inoperative due to a loss of fluid. The snubber was replaced with an identical unit that had been rebuilt with ethylene-propylene seals and the new tait was filled with fluid.
The inspection of snubbers ins /de the Reactor Building secondary shield was completed and no other inoparable snubbers were f o und.
(7)
Designation of Apparent Cause of Occurrence:
Subseque-inspection of the defective unit revealed that the reservoir end caps were loo se. There was some evidence, although inconclusive, of leakage at the cylinder end caps. No indication of seal deterior-ation was obse rved. The cause of the occurrence, there f ore, was mate rial.
(8)
Analysis of Occurrence:
The worst possible consequence of the loss of fluid f rom MUE-43 would take place during a seismic event. Excessive vibration could cause the overstress and possible f racture of the C high pressure injection line; however, since the high pressure injection lines are very conservatively designed, such a f racture is considered unlikely under any circumstances.
If such a break did occur, a check valve at the point where this line connects to the Reactor Coolant piping loop B cold leg downstream of the C Reactor Coolant Pump would prevent loss of the primary coolant. During an emergency safeguards actuation, the control room operator would notice a high flow rate in the C high pressure injection line and a rising level in the Reactor Building Sump. He would then isolate the C high pressure injection line.
In any case,. a make-up pumps would supply an adequate flow to the other three high pressure injection lines to fulfill their design function.
(9)
Corrective Ac*icn:
Immediate corrective action was taken as described above to replace the defective snubber.
Long-term preventative action continues with the snubber inspection and seal replacement program as described in the letter f rom R. C. Arnold to A. Giambusso dated February 14, 1974.
The Plant Operations Review Committee and the Station Superintendent have reviewed and approved the corrective actions.
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^ (10) Failure Data Previous Failures:
See Abnormal Occurrence Reports A0 50-289/74-14, 74-20, 74-23, 74-25, and 74-30.
Equipment Identification :
Snubber Assembly Brand - Grinnel Cylinder Type - Lynair Bore - 2.5 in.
Stroke - 5 in.
Sincerely, f.~ l i
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R. C. Arnold Vice President RCA/RSB/tas cc: Directorate of Regulatory Operations, Region 1 Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 File:
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