ML17265A661: Difference between revisions

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The        attached Licensee Event Report LER 1999-007 is submitted in accordance          with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "Any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)". A Level II Event Evaluation is in progress for this event, which may result in additional corrective actions.
The        attached Licensee Event Report LER 1999-007 is submitted in accordance          with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "Any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)". A Level II Event Evaluation is in progress for this event, which may result in additional corrective actions.
It is currently planned to submit a supplement to this.LER by July 30, 1999.
It is currently planned to submit a supplement to this.LER by July 30, 1999.
                                                        .
                                                           ~
                                                           ~
Very    truly yours, QLJ..
Very    truly yours, QLJ..

Latest revision as of 09:10, 4 February 2020

Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML17265A661
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/24/1999
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17265A662 List:
References
NUDOCS 9906040152
Download: ML17265A661 (3)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9906040152 DOC.DATE: 99/05/24 NOTARIZED: NO DOCKET FACIL:50-.244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAl4E AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP . NAME RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Forwards LER 99-007 re personnel error, causes two channels to be in tripped condition, resulting in reactor trip for RE Ginna Nuclear Power Plant. Util currently planned to submit suppl to LER by 990730.

DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR I ENCL J SIZE: 1 + 7 TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: AEOD/SPD/RRAB 1 FILE CENTER 1 1 NRR/DIPM/IOLB 1 1 NRR DIPM IQMB 1 1 NRR/DRIP/REXB 1 1 NRR/DSSA'/SPLB 1 1 RES/DET/EIB 1 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 NOAC POORE,W. '1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED

~

FROM DISTRIBUT UTION LIS OR R E DUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTR DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16

4 AND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89EASTAl'fNJE, VOCHESTEV, N Y Ido '9-GR'>'t.' ( c. ", <<r>> ".v ~

ROBERT C, MECREDY Vjce President Nocteor Operoti ons May 24, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

LER 1999-007, Personnel Error Causes Two Channels to be in Tripped Condition, Resulting in Reactor Trip R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

The attached Licensee Event Report LER 1999-007 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "Any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)". A Level II Event Evaluation is in progress for this event, which may result in additional corrective actions.

It is currently planned to submit a supplement to this.LER by July 30, 1999.

~

Very truly yours, QLJ..

Robert C. Mecre xc: Mr. Guy S. Vissing (Mail Stop 8C2)

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555

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Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector 9906040152 990524 PDR ADQCK 05000244 S PDR