05000311/LER-1982-072, Forwards LER 82-072/03L-0.Detailed Event Analysis Encl: Difference between revisions

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{{Adams
#REDIRECT [[05000311/LER-1982-072]]
| number = ML20063N569
| issue date = 09/08/1982
| title = Forwards LER 82-072/03L-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 = 05000311
| license number =
| contact person =
| document report number = NUDOCS 8209220214
| package number = ML20063N570
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}
{{LER
| Title = Forwards LER 82-072/03L-0.Detailed Event Analysis Encl
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000311
| LER year = 2082
| LER number = 72
| 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 September 8, 1982 Mr. R. C. Ilaynes Regional Administrator                                                                                  t USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania                    19406
 
==Dear Mr. Ilaynes:==
 
LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-072/03L Pursuant to the requirements of Salem Generating Station Unic No.      2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-072/03L.                This report is required within thirty (30) days of the occurrence.
Sincerely yours,
                                                                        ' ,W          ws II . J. Midura General Manager -
9 Salem Operations Ril:ksf/d l        CC:    Distribution 1
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The Energy People                                                                                    i
                                                                                                % 21W (20M) 1181
 
f                                                                      3
      ' Report Number:    82-072/03L Report Date:      09-08-82 Occurrence Date:  08-20-82 Facility:          Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey  08038 IDENTIFICATION OF OCCURRENCE:
Reactor Trip System - Reactor Trip Breaker "B" - Inoperable.
4 This report was initiated by Incident Report 82-246.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 - Rx Power 82% - Unit Load 890 MWe.                            l DESCRIPTION OF OCCURRENCE:
At 2000 hours, August 20, 1982, during surveillance testing of Solid State Protection System (SSPS), Train "B", it was discovered that Reactor Trip Breaker "B" would not trip as required. The channel was declared inoperable and Limiting Condition for Operation Action Statement 3.3.1 Action 1 was entered at 2000 hours. At 2040 hours, a power reduction was commenced in compliance with the limiting condition for operation.
An unusual event was entered due to a shutdown required by a          ;
limiting condition for operation. Only the automatic trip function was inoperable. The manual trip function was unaffected.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
l    The cause of the Reactor Trip Breaker malfunction was determined l      to be failure of the Undervoltage (UV) coil. The UV coil is
!    electrically in line for the trip function of the breaker. Mal-function of the coil prevented the breaker from tripping on a signal from the Solid State Protection System.
l    ANALYSIS OF OCCURRENCE:
l l
The operability of the protective and Engineered Safety Feature (ESP) Instrumentation Systems and interlocks ensure that; l) the associated ESF action and or reactor trip will be initiated when
;    the parameter monitored by each channel or combination thereof l    reaches its setpoint, 2) the specified coincidence logic is l
mailtained, 3) sufficient redundancy is maintained to permit a
(    channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
l l
l
 
(
* LER 82-072/03L                      g .
ANALYSIS OF OCCURRENCE:    (continued)
The operability of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The inte-grated operation of each of these systems is consistent with the assumptions used in the accident analysis. Redundant reactor trip capability is provided by another independent channel. Therefore, this occurrence involved no risk to the health and safety of the general public.
Action Statement 3.3.1 Action 1 requires:
With the number of operable channels one less than required by the minimum channels operable require-ment, be in hot standby within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per_ Specification 4.3.1.1 provided the other channel is operable.
Inoperability of one reactor trip channel, therefore, constitutes operation in a degraded mode permitted by a limiting condition fo* operation, and is reportable in accordance with Technical Sjecification 6.9.1.9.b.
CORRECTIVE ACTION:
The Reactor Trip Breaker was replaced with an "A" Train Bypass Breaker. The surveillance test was satisfactorily completed, and Limiting Condition for Operation Action Statement 3.3.1 Action 1 was terminated at 2206 hours, August 20, 1982. The undervoltage coil was replaced and the SSPS Train "B" Reactor Trip Breaker was reinstalled and tested satisfactorily.
FAILURE DATA:
Westinghouse Electric Corporation Type "A" Breaker Model DB-50 Prepared By    R. Heller                  /r        #  oCrd Genefal Mdnager -
SORC Meeting No. 82-82
}}
 
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