View source for 05000247/LER-1986-002, Forwards LERs 86-002-01,86-003-01 & 86-005-01.Rept Date Changed to 860213 & Nominal Expected Valve Temp Changed to 557 F for LER 86-002-00

{{Adams
| number = ML20211A932
| issue date = 06/04/1986
| title = Forwards LERs 86-002-01,86-003-01 & 86-005-01.Rept Date Changed to 860213 & Nominal Expected Valve Temp Changed to 557 F for LER 86-002-00
| author name = Otoole J
| author affiliation = CONSOLIDATED EDISON CO. OF NEW YORK, INC.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION (ADM)
| docket = 05000247
| license number = 
| contact person = 
| document report number = NUDOCS 8606110414
| package number = ML20211A937
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
{{LER
| Title = Forwards LERs 86-002-01,86-003-01 & 86-005-01.Rept Date Changed to 860213 & Nominal Expected Valve Temp Changed to 557 F for LER 86-002-00
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000247
| LER year = 2086
| LER number = 2
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter:. .           John C. C*Toole Vce Presdent Consolidated Edison Company of New York, Inc 4 trying Place, New York, NY 10003 Telephone (212) 460-2533 June 4, 1986 Ret          Indian Point Unit No. 2 Docket No. 50-247 LER-86-002-01 LER-86-003-01 LER-86-005-01 Document Control Desk U. S. Nuclear Regulatory Commission Wa shington, D. C. 20555 Dear Sirst Licensee Event Reports LER 86-002-00 and LER 86-003-00 were =ubmitted to the NRC on February 13, 1986. Licensee Event Report LER 86-005-00 wa s submitted to the NRC on March 10, 1986. These submittals were made in accordance with the requirements of 10 CFR Part 50.73. Revisions to these three Licensee Event Reports are attached.
LER 86-002-00 had typographical errors in the Report Date field (Page 1 of 3) and in the Analysis of Occurrence section (Page 3 of 3). The Report date was submitted a s 00/13/86 instead of 02/13/86. On page 3, the nominal expected temperature for valves MS-45A and MS-45C wa a submitted as 5570F instead of 5500F. LER 86-003-00 reouired a clarification and a correction in the Description of Occurrence section.
VaIve travel waa not tested as previously stated. LER 86-005-00 was submitted without the LER title on page 1 of 4.
Ve   truly yoyrs, f}l           ,  .
e-attach.
l 8606110414 860604 PDR i
ADOCK 05000247
'    S PDR                                                                              h i

cc: Dr. Thoma s E. Murley, Regional Administrator - Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511 INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 i
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