05000272/LER-1983-012, Forwards LER 83-012/01T-0.Detailed Event Analysis Encl: Difference between revisions

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#REDIRECT [[05000272/LER-1983-012, Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway]]
{{Adams
| number = ML20069D625
| issue date = 03/11/1983
| title = Forwards LER 83-012/01T-0.Detailed Event Analysis Encl
| author name = Midura H
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name = Haynes R
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| docket = 05000272
| license number =
| contact person =
| document report number = NUDOCS 8303180423
| package number = ML20069D630
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
{{LER
| Title = Forwards LER 83-012/01T-0.Detailed Event Analysis Encl
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000272
| LER year = 2083
| LER number = 12
| LER revision =
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:.
O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 11, 1983 Mr. R. C. Haynes Regional Administrator USNRC Regic,n 1 631 Park Avenue King of Prussia,              Pennsylvania        19406 Daar Mr. Haynes:
LIC214SE NO. DPE- 70
,      DOCKET NO. 50-272 REPORTABLE OCCURRENCE 83-012/OlT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.8.c, we are submitting Licensee Event Report for Reportable Occarrence 03-012/0lT. This report is required within fourteen (14) days of the occurrence.
Sincerely yours,
                                                                /    -
H. J. Midura General Manager -
Salem Operations RF:ks CC:    Distribution 8303180423 830311 PDR ADOCK 05000272 S                    PDR The Energy People
                                                                                              % 218t) ' 2r $ *1 11 81
 
, Report Number:    83-012/01T Report Date:        03-10-83                                              l Occurrence Date:    02-22-83 Facility:           Salem Generating Station Unit 1 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCF.:
Reactor Trip System - Reactor Trip Breakers - Inoperable.
This report was initiated by Incider.t Report 83-050.
CONDITLQES PPIOR TO Qr&USSULgE:
Mode 1 - RX Power 20 $ - Unit Lead 140 MWe.
DESCRIPTION OF OCCURRENCE:
On February 22, 1983, during a routine startup of Salem Unit 1, the reactor was manually tripped due to rapidly decreasing steam generator levels. Approximately 3 accends before the manual trip, both reactor trip breakers failed to cpen automatically on receipt of a valid Low-Low Steam Generator Level reactor trip signal. The fact that both breakers had failed was obscured by the manual trip, and the ensuing investigation therefore focused on the reasons for the manual trip and the related events.
Following a similar occurrence on February 25, 1983 (see LER 83-011/01T),
the plant was placed in a safe shutdown condition. A plant cooldown was subsequently commenced, and the unit entered Mode 5 at 0254 hours, February 26, 1983.
Letters to the NRC dated March 1 and 8, 1983, provide documentation of the investigation of the incident and proposed corrective action. A Supplemental Report will be submitted documenting the occurrence in detail.
FAILURE DATA:
Westinghouse Electric Corp.
Air Circuit Breaker Model DB-50 Type A Prepared By    R. Frahm                    '/ / General Manager h
Salem Operations SORC Meeting No. 89-031B
                      -    .        -            .
}}
 
{{LER-Nav}}

Revision as of 23:48, 7 August 2020

Forwards LER 83-012/01T-0.Detailed Event Analysis Encl
ML20069D625
Person / Time
Site:  PSEG icon.png
Issue date: 03/11/1983
From: Midura H
Public Service Enterprise Group
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20069D630 List:
References
NUDOCS 8303180423
Download: ML20069D625 (2)


LER-2083-012, Forwards LER 83-012/01T-0.Detailed Event Analysis Encl
Event date:
Report date:
2722083012R00 - NRC Website

text

.

O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 11, 1983 Mr. R. C. Haynes Regional Administrator USNRC Regic,n 1 631 Park Avenue King of Prussia, Pennsylvania 19406 Daar Mr. Haynes:

LIC214SE NO. DPE- 70

, DOCKET NO. 50-272 REPORTABLE OCCURRENCE 83-012/OlT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.8.c, we are submitting Licensee Event Report for Reportable Occarrence 03-012/0lT. This report is required within fourteen (14) days of the occurrence.

Sincerely yours,

/ -

H. J. Midura General Manager -

Salem Operations RF:ks CC: Distribution 8303180423 830311 PDR ADOCK 05000272 S PDR The Energy People

% 218t) ' 2r $ *1 11 81

, Report Number: 83-012/01T Report Date: 03-10-83 l Occurrence Date: 02-22-83 Facility: Salem Generating Station Unit 1 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCF.:

Reactor Trip System - Reactor Trip Breakers - Inoperable.

This report was initiated by Incider.t Report 83-050.

CONDITLQES PPIOR TO Qr&USSULgE:

Mode 1 - RX Power 20 $ - Unit Lead 140 MWe.

DESCRIPTION OF OCCURRENCE:

On February 22, 1983, during a routine startup of Salem Unit 1, the reactor was manually tripped due to rapidly decreasing steam generator levels. Approximately 3 accends before the manual trip, both reactor trip breakers failed to cpen automatically on receipt of a valid Low-Low Steam Generator Level reactor trip signal. The fact that both breakers had failed was obscured by the manual trip, and the ensuing investigation therefore focused on the reasons for the manual trip and the related events.

Following a similar occurrence on February 25, 1983 (see LER 83-011/01T),

the plant was placed in a safe shutdown condition. A plant cooldown was subsequently commenced, and the unit entered Mode 5 at 0254 hours0.00294 days <br />0.0706 hours <br />4.199735e-4 weeks <br />9.6647e-5 months <br />, February 26, 1983.

Letters to the NRC dated March 1 and 8, 1983, provide documentation of the investigation of the incident and proposed corrective action. A Supplemental Report will be submitted documenting the occurrence in detail.

FAILURE DATA:

Westinghouse Electric Corp.

Air Circuit Breaker Model DB-50 Type A Prepared By R. Frahm '/ / General Manager h

Salem Operations SORC Meeting No. 89-031B

- . - .