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| {{Adams
| | #REDIRECT [[05000312/LER-1978-004-01, /01T-0:on 780414,B&W Reported That Small Break Analysis Not Based on Worst Break Location.Change Required in Calculated Results Reported in BAW-10052 & BAW-10103A Revision 3.Potential Solution Being Evaluated by B&W]] |
| | number = ML20147B213
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| | issue date = 07/20/1978
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| | title = /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes
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| | author name = Colombo R
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| | author affiliation = SACRAMENTO MUNICIPAL UTILITY DISTRICT
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| | addressee name =
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| | addressee affiliation =
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| | docket = 05000312
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| | license number =
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| | contact person =
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| | document report number = LER-78-004-01T, LER-78-4-1T, NUDOCS 7810100021
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| | package number = ML20147B207
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 1
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| }}
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| {{LER
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| | Title = /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes
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| | Plant =
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| | Reporting criterion =
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| | Power level =
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| | Mode =
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| | Docket = 05000312
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| | LER year = 1978
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| | LER number = 4
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| | LER revision = 1
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| NRC FORM 366 u. S. NUCLE AR REGUL ATORY COMMISSION (7 77i LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) f 6
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| EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o 1012i 1 On April 14, 1978, Bsw reported that previous small break analysis had j
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| i 10131 I not been based on the worst break location. The report indicated i
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| i O 4 I that the worst case break had now been determined to be at the R.C. pump,
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| l FBTil I discharge. The results show that it is necessary to use operator t
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| lo is i l action during the early stages of the postulated accident to ef fectively i l
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| 10 l 7 l 1 mitigate the accident consequences and meet the criteria of 10 CFR 50.46.l 10181l I
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| 33 34 3b Jo 31 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORREC flVE ACTIONS h
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| li 101 IB6W analysis of small breaks indicated a change in calculated results i
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| m geompared to those previously reported in BAW-10052 and BAW-10103A Rev. 3.,
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| rTTTI I B6W has identified and evaluated solutions to the satisfaction of the l af fected utilities and NRC.
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| The District has incorporated procedure
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