ML19322A626

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Inquiry Memo 50-269/71-03:on 710428,dislodged Dummy Fuel Elements Fell Against Reactor Internals During Core Flooding Sys Test.No Pumps Involved.Damage Undetermined. Dislodging Occurred After Check Valve Opened
ML19322A626
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 05/03/1971
From: Seidle W
US ATOMIC ENERGY COMMISSION (AEC)
To:
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7911210698
Download: ML19322A626 (3)


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ATOMIC ENERGY COMMISSION V p

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230 PE ACHTR EE STREET, N CR T r4 W E ST 4

  1. Fil 4 A T I.A NT A, G E OR G I A 30303
  • 0 gg3y m,y 3, 1971 J

J. P. O'Reilly, Chief, Eeactor Testing and Operations Branch (2)

Division of Compliance, Headquarters CCMPLIANCE IMUIRY C'ORANDUM NO. 2c9/71 wu rwsn COMPEiY (CC03EE 1),

LICENSE NO. CFPR-33, DOCET NO. 50-269 - POSSIBLE RZACTCR VESSEL INEALS DAMAGE On April 28, 1971, at 11:50 a.=., J. W. Hampton, Assistant Superintendent, Oconee Nuclear Station, advised C. E. Murphy, Reactor Inspector, Region II, that during a test of the core flooding system operation, two du==y fuel elements in the vessel had been dislodged from their seats and fallen against the vessel internals. The folleving preliminary information was given:

1.

Two dummy fuel elements (containing no uranium) had been stored in the reactor vessel in pcsitions 1C23 and 1C53. (See Exhibit A.) The ele-

=ents were inserted into the lover grid but the only support at the upper ends was derived frem leaning the elements into the corners of the core barrel. No fuel was in the vessel or the transfer canal.

2.

The licensee was conducting the core flooding system flev test to verify the operation of the systes check valves. The reactor vessel had been filled with water and the fuel transfer canal was filled to within four feet of the top. The head was not on the vessel.

3.

When the ch.ak valve opened, the du==y elements were dislodged frem their seats and the tops fell against the vessel internals. The dis-tance of travel of the upper end of the dt y fuel elements was not known. 'Ihe lower ends remain at approx 1=ately their original positien.

4.

Ha=pton stated that approximately 9k0 cubic feet of water had been du= ped into the vessel. The time required or the approximate velocity was not known at the present time. No pumps were involved. Pressure in the CF tank at the time of the test was not known by Ha=pton.

5 The extent of da= age, if any, to the internals is not known at present.

The licensee is presently draining the water to examine the internals.

6.

The licensee vill advise the inspector if any da= age is detected, but he does not plan to issue a formal report.

Rec'd on Date eg, w

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J. P. O'Reilly May 3, 1971 Our inspector will follow up on this ' incident during his next site visit scheduled for early May.

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(L W.C.Seih CO:II:CEM Senior Reactor Inspector

Enclosure:

Exhibit A cc w/ encl:

E. G. Case, DRS (3) l P. A. Morris, DRL R. S. Boyd, DRL (2) i:

R. C. DeYoung, DRL (2)

D. J. Skovholt, DRL (3)

P. W. Heve, DRL (2)

A. Giambusso, CO L. Kornblith, Jr., CO R. H. Engelken, CO J. B. Henderson, CO R. W. Kirkman, C0:I B. H. Grier, CO:III J. W. Flora, CO:IV R. W. Smith, CO:V REG Files 4 #

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'Cho 070 C69 1Cl2 1C11 ul" E16 E12 M30 MOS 1135 1339 G33 133h 1C35 1C39 Cho C21 036 C2C' 032

-CIS 031 C27 077 C33' 059 C39 C65 1C57 1C55 E22 1221 1315 1A29 MC5 M25 O2'( M32 E2?

E35 D36

}c35 1C37j 088 Ch9 039 Ao3 035 C17 029 C16 030 C2h Ck7 Ao6 030

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. 057 l ICSS 1C55 Eh6 1314 11.3 1 M23 1A2h 2A17 M15 1A14 M33 1324 D37 102 1 103:

069 oS7 ChG' 034 C19 c28 C15 c24 Cil 023 C25 ch3 C34 061 OH

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