ML20083P985
| ML20083P985 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/16/1973 |
| From: | Ross D JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8302220470 | |
| Download: ML20083P985 (2) | |
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Jersey Central Pgwerjl,& Ligh-c Company t
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i1 January 16, 1973 w
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Dear Mr.,
Skovholt:
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION DOCKET 50-219 CORE SPRAY SUCTION HEADER DYNAMIC ANALYSIS
.'7N This letter is in response to your letter dated December 13, 1972 regarding the above subject. A comparison of the scetion header piping b,,
and supports of the Qaad Cities and Oyster Creek facilities has resulted p
in the conclusion that the failures experienced at Quad Cities 2 could l
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N not occur at Oyster Creek. Unlike the Ouad Citier header runro"t arrance-
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ment, the weight of the Oyster Creek ring header is supporte5 by seventeen ll WF130 vertical (pedestal-t rpe) supports which are attached to the rigid 4
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concrete mat foundation. The only connections between the suppression
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7 chamber and the suction header are the three 20" x 20" x 16" inlet "T"'s and six pairs of hydraulic snubbers oriented in the horizontal plane. This l
6 arrangement is illustrated in figures 1, 3 and h of section 9 of Amendment 32 which was submitted on February 16, 1968.
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l On December 29, 1972, a turbine trip and reactor scram occurred; l
durin6 the transient the pressure increased to above the setpoint of the l
electromatic relief valves.
It is suspected that two to five relief valves actuated at that time end all but one' resented as designed.
The remaining l
valve stayed open causing the plant to blevdevn to the torus until the i
pressure in the reactor vessel vas nea-atmospheric. This incident is the l
subject of an abnormal occurrence report being su'cmitted to Mr. A. Giambusso within the next few days. After this occurrence a thorough inspection of d
the core spray suction beader support arrangement was made which revealed no abnormal conditions.
Furthermore, there was no evidence of relative
.L motion between the suction header cnd its vertical supports.
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To be responsive to your request, however, we have contacted General Electric, the original designer of the system, and have learned that the information you have requested is not currently availabic. General Electric
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8302220470 730116 PDR ADOCK 05000219 PDR
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.e January 16,1973 s/
Mr. Donald J. Skovholt Assistant Director for Operating Reactors
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felt that your request was not applicable to Oyster Creek considering our physical arrangement and the failures at Quad Cities 2 that prompted your General Electric informed us that tests and analyses were currently request.
being conducted to determine the dynamic response resulting from a relief As you know, General valve blowdown for plants similar to Quad Cities 2.
Electric is scheduled to issue a report of their findings in March 1973 After We nave nad the opportunity to study this report and discuss its applicability to Oyster Creek with General Electric, ve> vill advise you of our plans concerning any further action vr feel vill be necessary to establish the adequacy of our present arrang'aent.
j Very truly yours, D. A. Ross, Manager Nuclear Generating Stations i
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cc: iir,.T. P, O'RetU y, Director Directorate of Regulatory Operations, Region 1 E
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