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| | issue date = 06/06/1978 | | | issue date = 06/06/1978 |
| | title = LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump | | | title = LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump |
| | author name = White L D | | | author name = White L |
| | author affiliation = Rochester Gas & Electric Corp | | | author affiliation = Rochester Gas & Electric Corp |
| | addressee name = Grier B H | | | addressee name = Grier B |
| | addressee affiliation = NRC/IE, NRC/RGN-I | | | addressee affiliation = NRC/IE, NRC/RGN-I |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:K5fN55 MMG'lk NP7 ROCHESTER GAS AND ELECTRIC CORPORATION | | {{#Wiki_filter:K5fN55 MMG'lkNP7 ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AYEHUE, ROCHESTER, H.Y. 14649 LEON O. WHITE. JR, T c i. c ff ffa w E VICE PRESIDENT ifFr ~ casa .Fr 546.2700 June 6, 1978 ncaa CD C C |
| ~89 EAST AYEHUE, ROCHESTER, H.Y.14649 LEON O.WHITE.JR, VICE PRESIDENT T c i.c ff ff a w E ifFr~casa.Fr 546.2700 June 6, 1978 Mr.Boyce H.Grier, Director U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 CD crI C'I'l n crF n re (n fTl CJ1 C C Cr=f I" F ncaa I'FI~CF1 c A1 | | crI Cr= f I"F C' |
| | Mr. Boyce H. Grier, Director I 'l I'FI U. S. Nuclear Regulatory Commission ~ CF1 n ncrF c A1 Office of Inspection and Enforcement Region I (n re 631 Park Avenue fTl CJ1 King of Prussia, Pennsylvania 19406 |
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| ==Subject:== | | ==Subject:== |
| Supplemental report on Reportable Occurrence 77-007/03L, Bus 14 breaker for"C" Safety Injection Pump R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244 | | Supplemental report on Reportable Occurrence 77-007/03L, Bus 14 breaker for "C" Safety Injection Pump R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 |
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| ==Dear Mr.Grier:== | | ==Dear Mr. Grier:== |
| The attached update report LER 77-007/03X-1 provides additional information obtained during the investigation connected with the subject event.Two additional copies of this letter and the attachment are enclosed to conform to the original submittal of LER 77-007/03L-O.
| |
| Very truly yours,/I L.D.White, r.-Attachment cc: Dr.Ernst Volgenau (30)Mr.William G.McDonald (3)7eg 6gpp~~J
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| NRC F(AM 366 I7.77)LER 77-007/03X-l~ate Report-Previous Reporf~z 7)27777" LICENSEE EVENT REPORT (CAR 1132)CK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) | | The attached update report LER 77-007/03X-1 provides additional information obtained during the investigation connected with the subject event. |
| I 6 G 1 Qgp 0-0 0 0 0 0-0 0Q34 1 1 1 1 OR~Os 14 15 LICENSE NUMBER 26 LICENSE TYPE 30 57 CAT 58 CONTROL BLO~OI N Y R E 7 8 9 LICENSEE CODE CON'T~RT,"''"~LQg p 6 p p p 2 4 4 T 0 6 2 9 7 7 s 0 6 0 6 7 8 Qs 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During test C SI pump failed to start from bus 14 breaker on 2 attempts.The pump was started successfully'ith the bus 1 6 breaker~Subsequently bus 1 4 breaker started~o4 pump su cce s s fully~This incident is s imilar to 7 events involving the bus 1 6 breaker~O6 and 1 event with the bus 14 breaker~Replacement breaker was tested and installed. | | Two additional copies of this letter and the attachment are enclosed to conform to the original submittal of LER 77-007/03L-O. |
| ~OB~OB 7 8 9 80 7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~SF G'ROPE~XOTE C">>R X 04~AOEE MZ 0'10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT R EV I SION LER3ERO EVENT YEAR REPORT NO.CODE TYPE NO.QTT REPoRT~77+~00 7+W~03+X-+1 21 22 23 24 26 27 28 29 30 ACTION FUTURE EF F ECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER | | Very truly yours, |
| ~AQs~ZOEE~Zoo LZJOE 0 0 0 0 L~IO33~YOE~NOEE W 1 2 0 Ogs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o NA Inspection of circuit breaker revealed no a arent cause for failure.Circuit breaker is Westinghouse Model DB-50, 600 V A.C.'t was returned to Westing-house for further investigation. | | / I L. D. White, r. |
| Westinghouse reported that, as received, breaker was 3 in good condition except for a missing bell alarm spring and a bent ground contact~After replacing these, breaker was tested without any failures and returned.CE3 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY 6 Z Q33 Z Q NA 7 8 9 10 11 44 PERSONNEL EXPOSURES NUIPIBER TYPE DESCRIPTION Q39~E1T7 L0 0 0~0~0 IQ3 3 Z Q3 8 NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q41 8~00 0 QER NA 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION Z Q42 NA 8 9 10 PUBLICITY ISSUED DESCRIPTION Q o~NQ44 NA 7 8 9 10 45 NAME OF PREPARER J.C.Noon 7 8 9 FACILITY~3O METHOD OF STATUS%POWER OTHER STATUS Pj DISCOVERY 1 5~E p3 8~10 0 p3 8 NA~BOEE 8 9 10 12 13 44 45 46 Test DISCOVERY DESCRIPTION Q32 80 LOCATION OF RELEASE Q36 NA 80 80 80 80 NRC USE ONLY 80 68 69 80 ER PHDNE 7 1 6-546-2700, ext~2 9 1-2 1 5 n 4}} | | - Attachment cc: Dr. Ernst Volgenau (30) |
| | Mr. William G. McDonald (3) 7eg 6gpp |
| | ~~J |
| | |
| | NRC I7.77) |
| | F(AM 366 LER 77-007/03X-l~ate Report LICENSEE EVENT REPORT Previous Reporf ~z 7)27777" (CAR 1132) |
| | CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) |
| | I 6 |
| | ~OI N Y R E G 1 Qgp 0 - 0 0 0 0 0 - 0 0Q34 1 1 1 1 OR~Os 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 26 LICENSE TYPE 30 57 CAT 58 CON'T |
| | ~RT,"''"~LQg p 6 p p p 2 4 4 68 T |
| | 69 0 6 2 EVENT DATE 9 7 7 74 s |
| | 75 0 6 0 6 7 8 80 Qs 7 8 60 61 DOCKET NUMBER REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During test C SI pump failed to start from bus 14 breaker on 2 attempts. The pump was successfully'ith started the bus 16 breaker ~ Subsequently bus 14 breaker started |
| | ~o4 pump su cce s s fully ~ This incident is s imilar to 7 events involving the bus 16 breaker |
| | ~O6 and 1 event with the bus 14 breaker ~ Replacement breaker was tested and installed. |
| | ~OB |
| | ~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE |
| | ~SF G'ROPE ~XOTE C " R X 04 ~AOEE MZ 0' 7 8 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT R EV I SION QTT LER3ERO REPoRT ACTION FUTURE EVENT YEAR |
| | ~77 21 22 EF F ECT |
| | + |
| | 23 SHUTDOWN |
| | ~00 24 REPORT NO. |
| | 7 26 |
| | +W 27 ATTACHMENT |
| | ~03 28 CODE 29 NPRDQ TYPE |
| | +X 30 PRIME COMP. |
| | +1 NO. |
| | COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER |
| | ~AQs~ZOEE ~Zoo LZJOE 0 0 0 0 L~IO33 ~YOE ~NOEE W 1 2 0 Ogs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 NA Inspection of circuit breaker revealed no a arent cause for failure. |
| | o Circuit breaker is Westinghouse Model DB-50, 600 V A.C. 't was returned to Westing-house for further investigation. Westinghouse reported that, as received, breaker was 3 in good condition except for a missing bell alarm spring and a bent ground contact ~ |
| | After replacing these, breaker was tested without any failures and returned. |
| | 7 8 9 80 METHOD OF FACILITY STATUS % POWER OTHER STATUS Pj |
| | ~3O DISCOVERY DISCOVERY DESCRIPTION Q32 CE31 5 ~E p3 8 ~10 0 p3 8 NA ~BOEE Test 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT 0 |
| | RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q36 7 |
| | 6 8 9 Z Q33 10 Z |
| | Q 11 NA 44 45 NA 80 PERSONNEL EXPOSURES NUIPIBER TYPE DESCRIPTION Q39 |
| | ~E1T7 L00 0 |
| | ~ 0 |
| | ~ IQ3 3 Z Q3 8 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q41 8 ~00 0 QER NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE 43 DESCRIPTION Z Q42 NA 8 9 10 80 PUBLICITY o |
| | ISSUED |
| | ~NQ44 DESCRIPTION Q NA NRC USE ONLY 7 8 9 10 68 69 80 ER NAME OF PREPARER J. C. Noon PHDNE 7 1 6-546-2700, ext ~ 29 1-2 1 5 |
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| | n 4}} |
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Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 ML18142B2571976-08-19019 August 1976 LER 1976-021-00 for R. E. Ginna, Unit 1, D Bank Group 2 Rcc'S G-3 and G-11 Partially Dropped Into Core ML18142B2531976-08-19019 August 1976 LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods ML18142B2761976-07-19019 July 1976 LER 1976-20-00 for R.E. Ginna, a Accumulator Level Below Technical Specification Limit ML18142B2721976-07-16016 July 1976 LER 1976-19-00 for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor ML18142B2741976-07-16016 July 1976 LER 1976-20-00 for R. E. Ginna, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm ML18142B2751976-07-16016 July 1976 LER 1976-20-00 for R.E. Ginna, Unit 1, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm ML18142B2781976-06-21021 June 1976 R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing ML18142B2801976-06-0404 June 1976 LER 1976-016-00 for R.E. Ginna, Rod Position Deviation Channel Was Found to Be Inoperable ML18142B2821976-05-24024 May 1976 LER 1976-015-00 for R.E. Ginna, Air Ejector and Blowdown Radiation Monitors Alarmed ML18142B2841976-05-11011 May 1976 LER 1976-013-00 for R.E. Ginna, Drop of Two Control Rods ML18142B2851976-05-10010 May 1976 LER 1976-014-00 for R.E. Ginna, N44 Power Range Detector High Voltage Power Supply Failure ML18142A9761976-04-23023 April 1976 LER 1976-012-00 for R.E. Ginna, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing ML18142A9791976-03-22022 March 1976 LER 1976-010-00 for R. E. Ginna, Containment Purge Supply Value Excessive Leakage During Testing ML18142A9781976-03-19019 March 1976 LER 1976-011-00 for R.E. Ginna, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System ML18142A9801976-03-12012 March 1976 LER 1978-009-00 for R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay ML18142A9811976-03-11011 March 1976 LER 1976-008-00 for R. E. Ginna, Abnormal Degradation of Steam Generator Tubes ML18142A9831976-02-28028 February 1976 LER 1976-007-00 for R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch 2024-03-07
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K5fN55 MMG'lkNP7 ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AYEHUE, ROCHESTER, H.Y. 14649 LEON O. WHITE. JR, T c i. c ff ffa w E VICE PRESIDENT ifFr ~ casa .Fr 546.2700 June 6, 1978 ncaa CD C C
crI Cr= f I"F C'
Mr. Boyce H. Grier, Director I 'l I'FI U. S. Nuclear Regulatory Commission ~ CF1 n ncrF c A1 Office of Inspection and Enforcement Region I (n re 631 Park Avenue fTl CJ1 King of Prussia, Pennsylvania 19406
Subject:
Supplemental report on Reportable Occurrence 77-007/03L, Bus 14 breaker for "C" Safety Injection Pump R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
Dear Mr. Grier:
The attached update report LER 77-007/03X-1 provides additional information obtained during the investigation connected with the subject event.
Two additional copies of this letter and the attachment are enclosed to conform to the original submittal of LER 77-007/03L-O.
Very truly yours,
/ I L. D. White, r.
- Attachment cc: Dr. Ernst Volgenau (30)
Mr. William G. McDonald (3) 7eg 6gpp
~~J
NRC I7.77)
F(AM 366 LER 77-007/03X-l~ate Report LICENSEE EVENT REPORT Previous Reporf ~z 7)27777" (CAR 1132)
CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6
~OI N Y R E G 1 Qgp 0 - 0 0 0 0 0 - 0 0Q34 1 1 1 1 OR~Os 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 26 LICENSE TYPE 30 57 CAT 58 CON'T
~RT,""~LQg p 6 p p p 2 4 4 68 T
69 0 6 2 EVENT DATE 9 7 7 74 s
75 0 6 0 6 7 8 80 Qs 7 8 60 61 DOCKET NUMBER REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During test C SI pump failed to start from bus 14 breaker on 2 attempts. The pump was successfully'ith started the bus 16 breaker ~ Subsequently bus 14 breaker started
~o4 pump su cce s s fully ~ This incident is s imilar to 7 events involving the bus 16 breaker
~O6 and 1 event with the bus 14 breaker ~ Replacement breaker was tested and installed.
~OB
~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~SF G'ROPE ~XOTE C " R X 04 ~AOEE MZ 0' 7 8 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT R EV I SION QTT LER3ERO REPoRT ACTION FUTURE EVENT YEAR
~77 21 22 EF F ECT
+
23 SHUTDOWN
~00 24 REPORT NO.
7 26
+W 27 ATTACHMENT
~03 28 CODE 29 NPRDQ TYPE
+X 30 PRIME COMP.
+1 NO.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~AQs~ZOEE ~Zoo LZJOE 0 0 0 0 L~IO33 ~YOE ~NOEE W 1 2 0 Ogs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 NA Inspection of circuit breaker revealed no a arent cause for failure.
o Circuit breaker is Westinghouse Model DB-50, 600 V A.C. 't was returned to Westing-house for further investigation. Westinghouse reported that, as received, breaker was 3 in good condition except for a missing bell alarm spring and a bent ground contact ~
After replacing these, breaker was tested without any failures and returned.
7 8 9 80 METHOD OF FACILITY STATUS % POWER OTHER STATUS Pj
~3O DISCOVERY DISCOVERY DESCRIPTION Q32 CE31 5 ~E p3 8 ~10 0 p3 8 NA ~BOEE Test 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT 0
RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q36 7
6 8 9 Z Q33 10 Z
Q 11 NA 44 45 NA 80 PERSONNEL EXPOSURES NUIPIBER TYPE DESCRIPTION Q39
~E1T7 L00 0
~ 0
~ IQ3 3 Z Q3 8 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q41 8 ~00 0 QER NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE 43 DESCRIPTION Z Q42 NA 8 9 10 80 PUBLICITY o
ISSUED
~NQ44 DESCRIPTION Q NA NRC USE ONLY 7 8 9 10 68 69 80 ER NAME OF PREPARER J. C. Noon PHDNE 7 1 6-546-2700, ext ~ 29 1-2 1 5
n 4