ML20107A994
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{{#Wiki_filter:. 4 1 t i August 1, 1973 W. G. Reimmuth, Chief, Technical Support Branch Directorate of Regulatory Operations, Headquarters JERSEY CElfrRAL F0WER & LIGHT CG(PANY, DOCKET NO. 50-219 FRELIMINARY CtBBERY REPGLT ON SNUBBER REPAIR ACTIVITIES DIRING SPRING 1973 REFIELING OUTAGE The enclosed prelf.minary report is forwarded for your inforestion. The licensee has stated that the final report will be officially transmitted to the AEC. It is suggested that this report be treated as proprietary information pending receipt of the final report. l E. Morris Howard, Chief Facility Construction and Engineering Support Branch i h'
Enclosure:
Preliminary Rpt 8 cc: F. A. Dreher, w/o enc. I I i 6 t i omcc > ..........RE G.,OP S. I HEISdSiAN:maz H RD summet > Nb ' DATE > Form AEC.Sta (Rev. 9-53) AECM 0240 ll 9604150237 960213 i PDR FOIA i DEKOK95-258 PDR
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- Jersey Central I]so4@f & Light Compan 4-
>%/, M AolSo'. AVENL, E AT PUNCH BOWL Ro # D e M OR RIS T oW N, N. J. 07960 e 539 6111 July 31,1973 r l ,dii.h / 'S Mr. A. Giambusso .V ~ i!.s J. }'; ~1 l Deputy Director for Reactor Projects ,i I 'l Directorate of Licensing 'O e OC 31973am. United States Atomic Energy Commission L h'ashington, D. C. 20545 (Ec cu 10 t 4 \\- 4
Dear Mr. Giambusso:
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Subject:
Oyster Crcek Station Docket No. 50-219 Reactor Coolant System Leakage The purpose of this letter is to report a violation of the Technical Specifications, Paragraph 3.3.D., " Reactor Coolant System Leakage". Operation of the reactor at power continued when it was not. recognized that an increasing absorpt'.on pool Icycl, combined with the rate.of Icahage into the drywell sump, origint.ted from the same so ~ e and thereby resu) cd in an " unexplained" leak rate in excess of 5.0 gpm. This event is considered tc, be an abnormal occurrence as defined in the Technical Specifications, Paragraph 1.15.r. Notification of j this event as required by the Technical Specifict.ticns, P:uagrapl) 6.6.2.a., was. made to AEC Rcgion I, Dircetorate of Regulatory 0;crations on Monday, July 25, 1973. As indicated in Figure 1, attached, an increasing rate of leakage into the drywell sump began to occur on Jul, 1,1973 and continued through July 19, 1973, reaching a peax of approximately 3.02 gpm when averaged over 24 hours. As shovn in figure 2. attached, a plot cf absorption pool (torus) water IcVel devel-oped on July 23, 1973 over the same period indicated the IcVel to be increasing starting about July 11, 1973. It is now estimated that the unexplained Icak rate increased to >5.0 gpn at some time durin:; July 17, 1973 and continued to be above the 5.0 gpm limit until the plant was shut down and depressuri:ed on July 21, 1973. ~1he source of this leakage was found to be a feedwater check valve hinge pin seal plug, which due to its position and the manner in which the water was spraying out, resulted in Icakage to beth the drywell floor and the torus. Valve data is as follow 3: i Manufacturer: Anchor Valve Company Type: 18" - 60C# Swing Check Valve Natorial: Cast Carbon Steel - Stallite Trim PM linds 1 / 5940 ^ h a m h ee.
.~ i ~ (. ) r.? e Mr. Giambusso July 31, 1973 4 In order to repair this seal, the erosion of the seating surface on the calve body was machined out and the plug adapted to fit using a procedure developed by MPR Associates and concurred in by the valve mar.afacturer and the PORC. In addition, a calculation was performed which verified that after machin-ing, the valve wall thickness was still satisfactory. A successful leak test 4 was conducted on July 24, 1973 and the plant returned to service. The. allowable leakage rates of coolant from the reactor system are based in part on predicted and experimentally observed behavior of cracks in pipes. As noted in the basis of the Technical Specifications, "... evidence suggests that the leakage somewhat greater than the limit specified or un-a identified leakage, the probability is small.that imperfections or cracks associated with such leakage would grow rapidly." The Technical Specifications limit re-ferred to in the above is 5.0 gpm; whereas, in this instance, the maximum leak rate approach. is 6. 75 gpm. Since the source of Icakage'in this case was a gasketed seal, no undo safety significance need be associated with this event. The possibility of the drywell surp under unusual circumstances not identifying the total unidentified drytcell leakage must be recogni:cd. 9 l To prevent a reoccurrence of this type event, Procedure 515.3, "Small Piping Leaks in Dryucil" will be revised to recognize that in cases where the torus water IcVel is increasing and the leakage source cannot be identified,'this inleakage will be added to the drywell unidentified leakage. Enclosed are forty (40) copics of this report. l Very truly yours, l c Donald A. Ross 4 Manager, Nuclear Generating Stations DAR:cs Enclosures cc: Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region I a [ w 4
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