View source for 05000266/LER-1992-010, Forwards LER 92-010-00,describing Possible Isolation of All Available Flow Paths for SI Pumps During Performance of Inservice Tests IT-40 & IT-45,possibly Resulting in Operating Pumps at Shutoff Head

{{Adams
| number = ML20127C139
| issue date = 01/07/1993
| title = Forwards LER 92-010-00,describing Possible Isolation of All Available Flow Paths for SI Pumps During Performance of Inservice Tests IT-40 & IT-45,possibly Resulting in Operating Pumps at Shutoff Head
| author name = Link B
| author affiliation = WISCONSIN ELECTRIC POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000266
| license number = 
| contact person = 
| case reference number = CON-NRC-93-003, CON-NRC-93-3, REF-PT21-93
| document report number = VPNPD-92-004, VPNPD-92-4, NUDOCS 9301140009
| package number = ML20127C141
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
}}
{{LER
| Title = Forwards LER 92-010-00,describing Possible Isolation of All Available Flow Paths for SI Pumps During Performance of Inservice Tests IT-40 & IT-45,possibly Resulting in Operating Pumps at Shutoff Head
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000266
| LER year = 2092
| LER number = 10
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter:s Wisconsin Electnc POWER COMPANY m w uscngn to rw ptw, uwwe n sm                                    gu!2212xs VPNPD-93-004                                               10 CFR 50.73 NRC-93-003 January 7, 1993 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washinaton, DC       20555 Gentlemen:
s DOCKETS 50-266 ANQ 50-301 LICENSEE EVENT REPORT 92-010-00 ISOLATION OF SI PUMP FLOW PATH DURING INSERVICE TESTING OF MINIMUM FLOW RECIRCULATION LINE ISOLATION VALVES FOINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Enclosed is Licensee Event Report 92-010-00 for Point Beach Nuclear Plant, Units 1 and 2. This report is provided in accordance with 10 CFR 50.73 (a) (2) (v) (D) , "The licensee shall report...any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to miti-gate the consequences of an-accident."
This report describes the possible isolation of all available flow paths for the safety injection pumps during performance of Inservice Tests IT-40, " Safety Injection Valves (Quarterly),
Unit 1," and IT-45, " Safety Injection Valves (Quarterly), Unit 2."
The isolation of all available flow paths could result in operating the pumps at shutoff-head, ultimately damaging the pumps and rendering them inoperable.
Please contact us if any further information is required.
Sincerely, e
c'',/ )7[ --
   ~
Bob Link Vice President Nuclear Power 1200,7;;
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}}

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