Similar Documents at Ginna |
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LER-2076-015, Air Ejector and Blowdown Radiation Monitors Alarmed |
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| 2442076015R00 - NRC Website |
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text
LER 76-15//3L
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LICENSEE EVENT REPOF
,/'-'ONTROL BLOCK:
1 LCENSEE NAME [aOO7 N Y R
E G
1 0
7 89 14 15.
REPORT REPORT CATEGORY TYPE SOURCE
~01 CDN'7~
L L
7 8
57 58 59 60 LCENSE NUMBER 0 0 0
0 0
0 0 DOCKET NUMBER 0
5 0 0 2
4 4
61 68 (PLEASE PRINT ALLREQUIRED INFORMATION)
EVENT TYPE LCENSE
'TYPE 0
4 1
1 1
1
~03 25 26 30 31 32 EVENT DATE REPORT DATE' 4
2 4
7 6
0 5
2 4
7 6
69 74 75 80
EVENT DESCRIPTION
gg During normal operation air ejector and blowdown radiation monitors alarmed.
Analysis 7
8 9 80 [pg~]
f "B" SG blowdown showed iodine activity from a calculated leak rate of 0.06 gpm.
7 8 9 80 t00j4 Eddy current (ec) testing verified the leaking tube.
Twelve others in adjacent area whic 7
8 9 60
~05 appeared to have similar ID type indications at approx.
22 to 3" above the tube sheet 7
8 9 80 ere all plugged.
Additional ec testing was conducted (cont'd. on attached sheet)
COMPONENT MANUFACTURER 44 47 7
8 9 PRME SYSTEM
CAUSE
COMPONENT CODE CODE COMPONENT CODE SUI7PLER VIOLATION
~CD
~E H
T E X C H
N W
1 2
0 N
7 8 9 10 11 12 17 43 48 CAUSE DESCRIPTION tOQSI The investigation of steam generator tube failures is continuing.
The steam generator 80 7
8 9 80
~09 is a Westinghouse Series 44, using inconel tubes size 0.875 OD with 0.050 inch walls.
7 8 9 [iso]
OTHER STATUS AMOUNT OF ACTIVITY NA NA NA OFFSITE CONSEQUENCES Q~g 7
89 LOSS OR DAMAGE TO FACII.ITY TYPE
DESCRIPTION
~16 H
7 89 10 PUBLICITY 7
8 9 NA Press release was made.
ADDITIONAL FACTORS NA 7
89 7
89 FACILITY STATUS 90 POWER QO7 E
~oe 0
7 8
9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE 6
6 7
B 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
I773I ~00 0
E 7
89 11 12 13 PERSONNEl INJURIES
~00 0
7 89 11 12 METHOD OF DISCOVERY DISCOVERY OESCRIPRON c
Bad monitors and sample analysis 44 45 46 LOCATION OF RELEASE 44 45 80 80 80 80 80 80 80 80 80 7
89 NAME:
Leon D. White, j'r.
80 PHDNE. 716-546-2700, ext. 2420 GPO 66 I ~ 667
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Licensee Event Report Reportable Occurrence 50-244/76-15 Event Descri tion (cont'd.)
(approximately 1,000 tubes) to determine if the pattern of degradation existed in other peripheral tubes beyond the locality of the leak.
One additional tube, not in the periphery, was indicated to require plugging.
(Reportable Occurrence 76-15, 30-day).
NRC FoBM 195 I2.20)
U.S. NUCLL'ABREGULATORY 4ISSION DOCKET NUMBER NRC DISTRIBUTION FoR PART 50 DOCI(ET MATERIAL TO:
Mr O'Reilly QPLETTER QOBIGINAL EICOPY
DESCRIPTION
Q NOTOB IZE0 QPUNC LASSIF I E 0 PROP INPUT FOAM ENCLOSURE "ROMRochester Gas.h Elec Co Rochester, NY L D White FILE NUMOEB XNCIDENT REPORT DATE OF DOCUMENT5-12-76 DATE RecelvED 5-l4-76 NUMBER OF COPIES RECEIVED none signed Ltr furnishing a supplemental rpt on Reportabl~
Occurrence fP76-07,< uhich concerning failure of relay for trann "A" containment isolation containment ventilation isolation to latch
'CKyrO~LEDGED
. QQ @Op PElhoVE PLANT NAME:
NOTE:
XF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J ~
COLLXNS SAFETY BRANCH CHIEF:
W 3 CYS FOR ACTION LXC ~ ASST:
W/
CYS ACRS CYS
~hQX8G/
ENZ TO LA OR ACTION/INFO RMATION ENVIRO 5-20-76 ehf INTERNALD IST R I 8UTION NRC PDR I & E 2
Jl~u-SCHROEDER/IPPOLXTO NOVAK CHECK R
I~ES S( 11WEI,II'E TEDHSC~01&CCA Y h
BAE SHAO VOLLlIER)BIJh'Qf l<RL'QRlI/Q~OLQJ NS LPDR:
TXC NSIC ns 4 EXTERNAL DISTRIBUTION ONTROL NUMBER
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| 05000244/LER-2076-003, For R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage | For R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage | | | 05000244/LER-2076-006, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976 | Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976 | | | 05000244/LER-2076-007, For R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch | For R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch | | | 05000244/LER-2076-008, For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes | For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes | | | 05000244/LER-2076-010, R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing | R. E. 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Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods | | | 05000244/LER-2076-023, R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 | R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 | | | 05000244/LER-2076-024, R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps | R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps | | | 05000244/LER-2076-025, R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent | R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent | | | 05000244/LER-2076-026, R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma | R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma | | | 05000244/LER-2076-027, R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line | R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line | | | 05000244/LER-2076-028, R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work | R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work | | | 05000244/LER-2076-029, R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition | R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition | | | 05000244/LER-2076-030, A Mixed Bed Demineralizer Inlet Piping Leak | A Mixed Bed Demineralizer Inlet Piping Leak | | | 05000244/LER-2076-030-03, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak | Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak | |
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