View source for 05000266/LER-1998-027, Forwards LER 98-027-00,describing Discovery of Deficiency in Surveillance Testing of Logic Matrix for Isolation of non- Essential Svc Water Sys Heat Loads & Discovery That Overlap Between Auxiliary Contacts Not Adequately Verif

{{Adams
| number = ML20195E063
| issue date = 11/12/1998
| title = Forwards LER 98-027-00,describing Discovery of Deficiency in Surveillance Testing of Logic Matrix for Isolation of non- Essential Svc Water Sys Heat Loads & Discovery That Overlap Between Auxiliary Contacts Not Adequately Verified
| author name = Kaminskas V
| author affiliation = WISCONSIN ELECTRIC POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000266
| license number = 
| contact person = 
| document report number = NPL-98-0959, NPL-98-959, NUDOCS 9811180224
| package number = ML20195E067
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
}}
{{LER
| Title = Forwards LER 98-027-00,describing Discovery of Deficiency in Surveillance Testing of Logic Matrix for Isolation of non- Essential Svc Water Sys Heat Loads & Discovery That Overlap Between Auxiliary Contacts Not Adequately Verified
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000266
| LER year = 2098
| LER number = 27
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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         .,         .         POWER COMPANY Point Beoch Nuclear Plant (920) 755-2321 6610 Nuclear Rd., Two Rivers. WI 54241 NPL 98-0959 November 12,1998 Document Control Desk                                                                   10 CFR 50.73 U.S. NUCLEAR REGULATOR.' COMMISSION Mail Station Pl-137 Washington, D.C. 20555 Ladies / Gentlemen:
DOCKETS 50-266 AND 50-30_1 LICENSEE EVENT REPORT 1998-027-00 INADEOUATE TECHNICAL SPECIFICATION SURVEILLANCE TESTING OF NON-ESSENTIAL SERVICE WATER ISOLATION LOGIC POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is Licensee Event Report 1998-027-00 for Point Beach Nuclear Plant, Units 1 and 2.
This report is provided in accordance with 10 CFR 50.73(a)(2)(i)(B), as "Any operation or condition prohibited by the plant's Technical Specifications." This report describes the discovery of a deficiency in the surveillance testing of the logic matrix for isolation of non-essential service water system heat loads and the discovery that the overlap between the auxiliary contacts on the service water pump breakers that provide the input to this service water isolation matrix were not being adequately verified.
New commitments within this report are indicated in italics.
Please contact us if you require additional information.
Sincer ly,                      ,
Vito A. K
                             $4%'*
mskas Manager, Regulatory Services & Licensing
             ' Enclosure                             .
                                                       ;-, i" 9811180224'981112             "                                           7k '}y CWK/tja                    DR     ADOCK 0500      6                                                /
(.                                      S cc:      NRC Resident Inspector NRC Regional Administrator PSCW INPO Support Services Asubs wafMisamhEwgG)pnhn
}}

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