ML20024F513

LER 83-091/03L-0:on 830802,while in Mode 1,borated Water Vol of Accumulator a Decreased to 7,354 Gallons.Caused by Valve Leakage in ECCS Check Valve Leakage Detection Sys.Valves Verified in Locked Position.Flange installed.W/830831 Ltr

ML20024F513
Person / Time
Site:	Summer
Issue date:	08/31/1983
From:	Dixon O, Mckinney C SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
LER-83-091-03L, LER-83-91-3L, NUDOCS 8309090444
Download: ML20024F513 (2)

Text

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EVENT OESCRIPTION AND PROBA8LE CONSEQUENCES O'o l o l2 l lOn August 2,1903, with the Plant in Mode 1, the borated water vo]ume of l

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Accumulator "A" decreased to 7354 gallom because of valm ledmge. Technical l j o j, j l Specification 3.5.1 raluires that a minimum volume of 7368 gallom be maintained j g lin Modes 1, 2 and 3. 'Ibere were no adverse consequences fran this event. l l o j e l l Normal level arxl pressure were re-established within 18 mLrutes of the j occurrence. N' ' 31,"." ".": .::"::. ........,.... . :s. .::n:. I lol9 l l S lF [ @ l El @ ul B l @ l Vl A lL l VlE lX l @ W@ [D [@

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                                                                                                            1 SOUTH CAROLINA ELECTRIC & GgC,oyPANY,                         ,

post oFPICE 764 ' * ** [*g] COLuusiA, south CAmouNA 29218 * **'CI*- O. W. OtxoN, JR. e O J4 f Vics P asineNT uveu.. o....r.ou. August 31, 1983 . Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W. Atlanta, Georgia 30303

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 83-091

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #83-091 for Virgil C. Summer Nuclear Station. This Thirty Day Report is required by Technical Specification 6.9.1.13.(b) as a result of entry into Action Statement (a) of Technical Specification 3.5.1, " Emergency Core Cooling Systems," on August 2, 1983. Should there be any questions, please call us at your convenience. Ver trul yours, 7 O. W. D' on r. CJM:OWD/mac/fjc Attachment cc: V. C. Summer C. L. Ligon (NSRC) E. H. Crews, Jr. G. J. Braddick T. C. Nichols, Jr.,/O. W. Dixon, Jr. J. C. Miller E. C. Roberts J. L. Skolds H. N. Cyrus J. B. Knotts, Jr. Group / General Managers I&E (Washington) O. S. Bradham Document Management. R. B. Clary Branch C. A. Price INPO Records Center A. R. Koon NPCF D. A. Lavigne File (Lic./Eng.) J. F. Heilman OFFICIAT&~hi'

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( Mr. James P. O'Reilly LER No. 83-091 Page Two August 31, 1983 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES On August 2, 1983, with the Plant in Mode 1, Operations personnel were attempting to identify a leakage source between the Emergency Core Cooling System (ECCS) and Train "B" of the Residual Heat Removal (RHR) System. The source of this leakage was suspected to be in the ECCS Check Valve Leak Detection System. XVT-37, "ECCS Check Valve Leakage Detection Header Isolation Valve," was opened at 2330 hours to depressurize the header. At 2338 hours, the low pressure and level alarms were received for Accumulator "A." XVT-37 was closed at 2341 hours and Accumulator "A" pressure and level stabilized at 600 psig and 7354 gallons respectively. Action Statement (a) of Technical Specification 3.5.1.b applied since a minimum volume of 7368 gallons of borated water is required in each accumulator. There were no adverse consequences resulting from this event. Normal level and pressure were re-established by 2356 hours on August 2, 1983. CAUSE AND CORRECTIVE ACTIONS The cause of the decrease in pressure and level in Accumulator "A" on August 2, 1983, is attributed to leakage through XVT-61A,

          " Accumulator 'A' Test Isolation Valve." The increase of pressure in the RHR System was apparently the result of leakage through XVT-61A and XVT-3B, "RH Header    'B' Drain Valves."  Both of these valves are in the ECCS Check Valve Leak Detection System and are normally locked closed. The valves were verified to be in their correct positions.

The immediate corrective action taken by Operations personnel was to close XVT-37 and re-establish normal level and pressure in Accumulator "A." This action was completed at 2356 hours on August 2, 1983, and Action Statement (a) of Technical Specification 3.5.1 was exited at this time. The boron concentration was verified to be within the established Technical Specification limits at 0035 hours on August 3, 1983. To prevent a future recurrence of this event, a blank flange was installed upstream of XVT-3B on August 18, 1983. This flange will remain in place until XVT-61A and XVT-3B can be repaired during the next Plant maintenance outage. I l}}