LER-2076-032, Relief Valve in Boric Acid Make-Up System Developed a Leak |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3352076032R00 - NRC Website |
|
text
NRC FORM 195 U.S. NUCLEAR REGULATOR OMMISSION
<2.>iI h~
NRC DISTRISUTION FDR ~PART 50 DOCKET MATERIAL DOCKET NUMBER
'0-335 FILE NVMBE R INCIDI!ZT REMRT TO:
Mr, NormICn C, Moseley FROM:
Florida Power 6 Light Co.
Miami, Florida D
Schmidt DATE OF DOCUMENT 7/21/76 DATE RECEIVED 7/26 76
@LETTER OORIGINAL
,PgOP V
DESCRIPTION
ONOTORIZED JRJNCLASSIFIF D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED
. )
'/r One si ned c'o Ltr. trans the following:
Licensee Event Report (RO'50-.335/76-32) on 6/26/76 concerning a relief valve in the Boric A'cid Make-Up (BAM) system developihg a.leak.
(1>>P)
(2-'P)
ACKNOWLZDGZD DO NOT REMOVE:
PLANT NAME St Lucie 81 NOTE:
IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J..COLLINS BRANCH CHIEF:
CYS FOR ACTION LIC..ASST.:
W S
ACRS CYS HOLDING S Ziemann Diggs" FOR ACTIONllNFORMATION 7 27 76 RJL HEG FI NRC PDR I RE 2
MIPC "
SCHROEDER IPPOLITO HOUSTON NOVAK CHECK GRIMES CASE HANAUER.
TEDESCO MACCARY EISENHUT BAER SHAO VOLLMER BUNCH KREGER J. COLLINS INTERNALDISTRl BUTION LPDR:
Ft Pierce Fl TIC:
EXTERNAL DISTRIBUTION CONTROL NUMBER NRC FORM 198 {2.76)
l
~
~
iPJ l
,a ~
W f)~
P N
II
/
r
~:
~
'I
~
~
~
L P.O, BOX 013100, lAIA'll, FLOIIIOA 33101 qkV
('cV24$
J O'L+~
Jl' '0)'~r + 4+re J
FLORIOA POWER 6'LIG1IT CQI%1PANY July 21, 1976 PRN-LI-76-191 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement S. Nuclear Regulatory Commission 230 Peachtree
- Street, N. N., Suite 818 9
. Atlanta, Georgia 30303
'ear Mr. Moseley:
I
~
LQ REPORTABLE OCCURRENCE 335-76-32 ST.
LUCIE UNIT 1 DATE OF OCCURRENCE:
JUNE 26, 1976 BORIC ACID MAKE-UP TANKS J
The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the 'subject occurrence.
r Very truly yours, D. Schmid t Vice Presidernt Power Resources 00gRRTRD C
I1511IIQ MULTI>>6 9
a ~~egg REc4l&~0+
e0NNRe RSA/bf jl',el'>F06 9octet Attachment cc:
Jack R.
Newman, Esquire Director, Office of Inspection and Enforcement (40)
~
. Director, Offic'e of Management Information and Program Control (3)
CONTROL. BLOCK:Q 1
L'.IL G=IhlaC:r rVC IW I NCt UN I LEAEE PAINT ALLAEOOIAEO INPQAhlATIQN]I UCENSEE NAMc
~ 01 F
L S
L S LCENSE NUMSER 1
0 0 ~
0 0
0 0
0 UCENSE EVENT TYPE TYPc lo.
o E
x lz lz z
I
~o 0
~
31 32 7
8 9 14 15 REPORT CATEGORY TYPE
~D1 QQN'T~
L 7
8 57 58 59 EVENT OESCRIPTION Q~g A relief valve 25 26 REPORT SOURCE CCCKcT NUh18ER
~L 0
'5I 0 0 3 315 60 61 68 REPCRT O*Tc 0
6 2'6 716
~
0 7
2 1 l7I6I 69 74 75 60 EVOKE GATE in the Boric Acid Nake-Up (BAi41) system developed a leak.
7 8 9 [oO~] 'drained below volume specification which was in violation of Technical 7
8 9 60 I,This valve is in a line common to both "A" and "B" BAN tanks.
Both tanks 7
8 9
@~5 Soecification 3.1.2.8.
The leak was isolated and the "B" BAN tank was 60 7
8 9 joOs]
EO meet the hnical Saecif ication re uirement. within 45 minutes.
7 8 9 SYSTEM C'USE CQQE CCQ'E COMPONENT CQQ'E [QQTj ~RI
~E U
TL L
V E
X 7
8 9 10 11 12 17 CAUSE DESCRIPTION The gasket on the inlet side 7
8 PciiiIE CC MPCNE'4T
- - 4FFl~
of the C
h1PQNEAiT VIAt1:FAlii;FER VOLATION C
71IO N
47 48 relief valve was leaking.
60 7
8 7
8 Q3 7
6 OTNER STATUS Ah1CUNT OF ACTIVITY N A 9
FAC:UTY STATUS
'5 PQVlER LJoOsJ 9
10 12 13 FORM QF ACTIVE COiQTcNT RELASEO OF RIALASE
~z z
9 10 11 PERSONNEL EXFOSURES
~ol o I
ol 9
11 12 13 PERSOIAIINIEE INJURIES
~qq
.o 9
11 12 METHQO OF GSCGVERY 44 45 46 s,
'"s"f,iN/A N!A 01SCQVERY OESCRIPTION N A LOCATlON OF RE'EASE N/A 80 60 60 60 PRO/ABLE 'CON S ECUENCES Q~Q LOSS OR OAMAGF TO FACIUTY TYPE OESCRPTtON z
7 89 10 N/A N/A 60
, PUBLICITY Qr]
N/A 7
89 ADOITIONAL FACTORS
~1fs See Page 2.for continuation of Event Description.
89 60
~19 7
89 NAME:
R; S.
Abraham FHONE30 5-5'52-3 8 27 eo CPO Fd'f a $ /7
REPORTABLE OCCURRENCE 335-76-32 PXCENSEE EVENT REPORT PAGE 2
Event Description
(Continued):
The leak was repaired and the system returned to normal.
This is the first occurrence of this type at PSL 51.
(335-7 6-3 2)
P.O.
BOX 013100, MIAMI, FLORIDA 33101 FLORIDA POWER O'IGHT COMPANY July 21, 1976 PRN-LI-76-191 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230.Peachtree
- Street, N. N., Suite 818 Atlanta, Georgia 30303
Dear Mr. Moseley:,
REPORTABLE OCCURRENCE 335-76-3 2, ST.
LUCIE UNIT 1 DATE OF OCCURRENCE:
JUNE 26, 1976 BORIC ACID MAKE-UP TANKS The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
Very truly yours,
. a&~
D. Schmidt Vice President Power Resources RSA/bfp Attachment cc:
Jack R.
Newman, Esquire Director, Office of Inspection and Enforcement (40)
Director, Office of Management Information and Program Control (3)
HELPING BUILD FLOR IDA
Q r
~.
~
II
'I ~
ot~~M [os]
F
.7 89 CONTROL UCENS E
NAME LS'LS LICENSEE EVENT 8LOCK:
6
~
UCENSE NUMBER 1
0 0 0 0
0 0 0 14 15 REPORT PI.EASE PRINT AI.LREQUIRED INFORMATION) 1 IJCENSE EVENT TYPE TYPE 0
0 4
1 1
1 1
L!0003~I 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE
~
OOCKET NUMBER EVENT DATE REPORT OATE [oO~IcoN7~
~L
~L 0
5 0 0 33 5
0 62 6
7 6
0 72 1
7 6
7 8
57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION Qpzj A relief valve in the Boric Acid Make-Up (BAM) system developed a leak.
89 80 toOI..This valve is in a line common to both "A" and "B" BAM tanks.
Both tanks 7
8.9 80 4j drained below volume specification which was in violation of Technical 7
89 [GD~]
S ecification 3.1.2.8.
The leak was isolated and the "B" BAM tank was 80 7
8 9 Jog t:he 80 i al S ecification re uirement within 45 minutes.
7 8 9 SYSTEM
CAUSE
COOE COOE COMPONENT COOE [007] FBI
~E V
A L V
E X 7
8 9 10 11 12 17 CAUSE OESCRIPTION Qpg The gasket on the inlet side 7
8 9 Qoi A
of the CCMPON BIT MANUFACIURER C
7 1
0 N
44 47 48 relief valve,was leaking.
80 80 7
8 9 Qoj OTHER STATUS N A AMOUNT OF ACTIVITY N A PRQBABLE CONSEQUENCES Q~g 7
8 9 LOSS OR OAMAGE TO FACILITY TYPE OESCRIPTION UE 2
7 89 10 PUBLICITY 7
8 9 7
89 FACIUTY STATUS
,6 POWER
@171
~E
~Q7 6
7 8
9 10 12 13 FORM OF ACTIVffY CO@TENT RELEASEO OF RELEASE Q~g z-
~z 7
8 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION
~o ~oo' 7
8 9 11 12 13 PERSONNEL INJURIES QOL 0
0 7
8 9 11 12 METHOO OF OISCOVERY 44 45 46 44 45 N/A N/A N/A N/A N/A OISCOVERY OESCRIPTION N A LOCATION OF RELEASE N/A 80 80 80 80 80 80 80 80 AOOITIONAL FACTORS
~1 8 See Page 2 for continuation of Event Description.
7 8 9 80 89 NAME:
R.
S. Abraham P NE'o Ol'0 ddt d dl
I Pi '
~
r, tj
'<<l
REPORTABLE OCCURRENCE 335-76-32~~
LICENSEE EVENT REPORT PAGE 2
Event Descri tion (Continued):
The leak was repaired and the system returned to normal.
This is the first occurrence of this type at PSL 5l.
<335-76-3~~)
ea p
i 1
r' f
7 c gg~
~le Q )A(
I
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000335/LER-2076-001, For St. Lucie Unit 1, a Breach of Containment Integrity | For St. Lucie Unit 1, a Breach of Containment Integrity | | | 05000335/LER-2076-002, For St. Lucie Unit 1, Spent Fuel Crane Overload Interlock-Setpoint Drift | For St. Lucie Unit 1, Spent Fuel Crane Overload Interlock-Setpoint Drift | | | 05000335/LER-2076-003, For St. Lucie Unit 1, a Design Error in Engineered Safety Features Actuation System | For St. Lucie Unit 1, a Design Error in Engineered Safety Features Actuation System | | | 05000335/LER-2076-004, For Saint Lucie Unit 1, a Breach of Containment Integrity | For Saint Lucie Unit 1, a Breach of Containment Integrity | | | 05000335/LER-2076-005, For St. Lucie Unit 1, Two Inoperable Containment Area Radiation Monitoring Instrumentation Channels | For St. Lucie Unit 1, Two Inoperable Containment Area Radiation Monitoring Instrumentation Channels | | | 05000335/LER-2076-006, For St. Lucie Unit 1, Technical Specification Time Limit Exceeded During Transition from Shutdown Cooling Pumps to Reactor Coolant Pumps | For St. Lucie Unit 1, Technical Specification Time Limit Exceeded During Transition from Shutdown Cooling Pumps to Reactor Coolant Pumps | | | 05000335/LER-2076-007, For St. Lucie Unit 1, an Error in the RCS Loop Temperature Wiring Diagrams | For St. Lucie Unit 1, an Error in the RCS Loop Temperature Wiring Diagrams | | | 05000335/LER-2076-008, For St. Lucie Unit 1, Two Female Unions Improperly Welded Into the Cooling Lines for LPSI Pumps 1A and 1B | For St. Lucie Unit 1, Two Female Unions Improperly Welded Into the Cooling Lines for LPSI Pumps 1A and 1B | | | 05000335/LER-2076-009, Five Mechanical Piping Restraints Were Locked Up During Heatup for Post Core Hot Functional Testing | Five Mechanical Piping Restraints Were Locked Up During Heatup for Post Core Hot Functional Testing | | | 05000335/LER-2076-011, Steam Driven Auxiliary Feedwater Pump | Steam Driven Auxiliary Feedwater Pump | | | 05000335/LER-2076-012, During Preoperational Testing, Main Steam Isolation Valves Did Not Close within 6 Seconds as Required by Tech Spec 4.7.1.5.b | During Preoperational Testing, Main Steam Isolation Valves Did Not Close within 6 Seconds as Required by Tech Spec 4.7.1.5.b | | | 05000335/LER-2076-013, During Preoperational Testing, Steam Auxiliary Feed Pump Would Not Start Properly from Hot Shutdown Control Panel | During Preoperational Testing, Steam Auxiliary Feed Pump Would Not Start Properly from Hot Shutdown Control Panel | | | 05000335/LER-2076-014, During Preoperational Testing, Outer Personnel Access Door to Containment Would Not Pass Air Leakage Test | During Preoperational Testing, Outer Personnel Access Door to Containment Would Not Pass Air Leakage Test | | | 05000335/LER-2076-016, During Preoperational Testing with Plant in Hot Standby, Control Room Air Conditioner Was Out of Service | During Preoperational Testing with Plant in Hot Standby, Control Room Air Conditioner Was Out of Service | | | 05000335/LER-2076-017, During Surveillance Test, Four Bistables Were Drifted Such That Their Trip Setpoints Were Less Conservative than Required by Tech Spec 3.3.2.1 | During Surveillance Test, Four Bistables Were Drifted Such That Their Trip Setpoints Were Less Conservative than Required by Tech Spec 3.3.2.1 | | | 05000335/LER-2076-018, During Performance of Control Element Assembly Calibration Preoperational Test, RCS Boron Concentration Was Diluted and Group I Was Inserted to Match Reactivity | During Performance of Control Element Assembly Calibration Preoperational Test, RCS Boron Concentration Was Diluted and Group I Was Inserted to Match Reactivity | | | 05000335/LER-2076-019, During Testing, Digital Data Processor Malfunctioned; Resulted in Loss of CEA Pulse Counting Position Indication | During Testing, Digital Data Processor Malfunctioned; Resulted in Loss of CEA Pulse Counting Position Indication | | | 05000335/LER-2076-020, During Power Ascension to Twenty Percent Plateau, Power Dependent Insertion Limit Was Changing in Non-Conservative Direction as Power Increased | During Power Ascension to Twenty Percent Plateau, Power Dependent Insertion Limit Was Changing in Non-Conservative Direction as Power Increased | | | 05000335/LER-2076-021, A Diesel Generator Was Tested to Verify Operability When One of the Air Start System Solenoid Valves and Its Associated Air Line Were Clogged with Dirt | A Diesel Generator Was Tested to Verify Operability When One of the Air Start System Solenoid Valves and Its Associated Air Line Were Clogged with Dirt | | | 05000335/LER-2076-023, During Surveillance Test on Hot Shutdown Control Panel, Cold Leg Temperature Indication for Reactor Coolant Loop 1A1 Was Not Correct | During Surveillance Test on Hot Shutdown Control Panel, Cold Leg Temperature Indication for Reactor Coolant Loop 1A1 Was Not Correct | | | 05000335/LER-2076-024, During Preoperational Testing, Remotely Operated Containment Isolation Valve (Primary Makeup Water) Would Not Close Automatically | During Preoperational Testing, Remotely Operated Containment Isolation Valve (Primary Makeup Water) Would Not Close Automatically | | | 05000335/LER-2076-025, During Preoperational Testing, Regulating Rod 59 Was Immovable Because Associated CEA Module Had Malfunctioned | During Preoperational Testing, Regulating Rod 59 Was Immovable Because Associated CEA Module Had Malfunctioned | | | 05000335/LER-2076-026, During Power Ascension Testing, One of Four Redundant 120 Volt Ac Instrument Power Busses Was Lost Due to Malfunction of 1C Static Inverter | During Power Ascension Testing, One of Four Redundant 120 Volt Ac Instrument Power Busses Was Lost Due to Malfunction of 1C Static Inverter | | | 05000335/LER-2076-027, During Power Ascension Testing, Digital Data Processor Malfunctioned; Resulted in Loss of CEA Pulse Counting Position Indication | During Power Ascension Testing, Digital Data Processor Malfunctioned; Resulted in Loss of CEA Pulse Counting Position Indication | | | 05000335/LER-2076-028, Review of the Testing Proposed for Unit 2 Hydrogen Sampling System Isolation Valves Led to Examination of Purchase Order for the Identical Unit 1 Valves | Review of the Testing Proposed for Unit 2 Hydrogen Sampling System Isolation Valves Led to Examination of Purchase Order for the Identical Unit 1 Valves | | | 05000335/LER-2076-029, Contrary to Tech Spec 4.3.3.3.1, Required Channel Check of 2 Triaxial Accelerographs Was Not Performed within Required Time Frame | Contrary to Tech Spec 4.3.3.3.1, Required Channel Check of 2 Triaxial Accelerographs Was Not Performed within Required Time Frame | | | 05000335/LER-2076-030, During Plant Startup/Heatup from Cold Iron Shutdown Conditions, Plant Experienced Over-Pressure Transient When First RCP Was Started | During Plant Startup/Heatup from Cold Iron Shutdown Conditions, Plant Experienced Over-Pressure Transient When First RCP Was Started | | | 05000335/LER-2076-032, Relief Valve in Boric Acid Make-Up System Developed a Leak | Relief Valve in Boric Acid Make-Up System Developed a Leak | | | 05000335/LER-2076-033, While Pumping Water from Primary Water Tank to Spent Fuel Pool, Operations Personnel Found Refueling Water Tank Was Overflowing | While Pumping Water from Primary Water Tank to Spent Fuel Pool, Operations Personnel Found Refueling Water Tank Was Overflowing | | | 05000335/LER-2076-034, In Order to Compensate for Errors Found in NSSS Vendors Strikin II Computer Code, Several Instrumentation and Control Setpoints Were Adjusted | In Order to Compensate for Errors Found in NSSS Vendors Strikin II Computer Code, Several Instrumentation and Control Setpoints Were Adjusted | | | 05000335/LER-2076-035, During Power Ascension Testing, It Was Determined That Power Distribution in Core Was Not as Predicted for 80 Percent Power | During Power Ascension Testing, It Was Determined That Power Distribution in Core Was Not as Predicted for 80 Percent Power | | | 05000335/LER-2076-036, Steam Driven Auxiliary Feedwater Pump Would Not Start Because Steam Supply Valve Would Not Open Fully | Steam Driven Auxiliary Feedwater Pump Would Not Start Because Steam Supply Valve Would Not Open Fully | | | 05000335/LER-2076-037, With Reactor Critical at 0.01 Percent Power, Control Element Assembly 50 Dropped | With Reactor Critical at 0.01 Percent Power, Control Element Assembly 50 Dropped | | | 05000335/LER-2076-038, With Reactor Critical at 0.01 Percent Power, Power Supply to Digital Data Processor Was Momentarily Deenergized | With Reactor Critical at 0.01 Percent Power, Power Supply to Digital Data Processor Was Momentarily Deenergized | | | 05000335/LER-2076-039, With Reactor Critical at 0.01 Percent Power, Shield Building Access Door Was Found Open Which Is Contrary to Technical Specification 3.6.6.2 | With Reactor Critical at 0.01 Percent Power, Shield Building Access Door Was Found Open Which Is Contrary to Technical Specification 3.6.6.2 | | | 05000335/LER-2076-040, During Reactor Shutdown and Cooldown, Pressurizer Level Would Drop Whenever Either Set of Shutdown Cooling System Suction Valves Was Opened | During Reactor Shutdown and Cooldown, Pressurizer Level Would Drop Whenever Either Set of Shutdown Cooling System Suction Valves Was Opened | | | 05000335/LER-2076-041, During Shutdown Cooling Pump Operation, Second Charging Pump Was Started to Increase Letdown Flow Rate and It Caused Reactor Coolant System Pressure to Increase | During Shutdown Cooling Pump Operation, Second Charging Pump Was Started to Increase Letdown Flow Rate and It Caused Reactor Coolant System Pressure to Increase | | | 05000335/LER-2076-042, With Reactor Shutdown for Fuel Inspection, Containment Purge Fan Was Started and Sufficient Vacuum Was Obtained to Cause Containment Vacuum Release Valve to Open | With Reactor Shutdown for Fuel Inspection, Containment Purge Fan Was Started and Sufficient Vacuum Was Obtained to Cause Containment Vacuum Release Valve to Open | | | 05000335/LER-2076-043, During Special Inspection of Steam Generators a and B to Accomplish Tack Welding of Stand Pipes for Feed Ring, 3 Stand Pipes Were Found Missing | During Special Inspection of Steam Generators a and B to Accomplish Tack Welding of Stand Pipes for Feed Ring, 3 Stand Pipes Were Found Missing | | | 05000335/LER-2076-043-01, Missing Standpipes in Steam Generator a Feed Ring | Missing Standpipes in Steam Generator a Feed Ring | | | 05000335/LER-2076-044, With 1B Diesel Generator Out of Service for Preventive Maintenance on Air Line Lubricators, 1A Diesel Generator Failed to Start During Surveillance Test | With 1B Diesel Generator Out of Service for Preventive Maintenance on Air Line Lubricators, 1A Diesel Generator Failed to Start During Surveillance Test | | | 05000335/LER-2076-045, During Plant Heatup, Low Pressure Safety Injection Pumps Were Stopped When System Pressure Had Been Raised Above 250 Psia | During Plant Heatup, Low Pressure Safety Injection Pumps Were Stopped When System Pressure Had Been Raised Above 250 Psia | | | 05000335/LER-2076-046, Inoperable Door Operating Mechanism in Containment Personnel Air Lock Outer Door | Inoperable Door Operating Mechanism in Containment Personnel Air Lock Outer Door | | | 05000335/LER-2076-047, Steam Driven Auxiliary Feedwater Pump Would Not Start Because Trip Solenoid Latch Failed to Engage | Steam Driven Auxiliary Feedwater Pump Would Not Start Because Trip Solenoid Latch Failed to Engage | | | 05000335/LER-2076-048, Due to Faulty Switch on Operators Console an Interrupt Signal Was Sent to Central Processing Unit Causing Digital Data Processor to Halt | Due to Faulty Switch on Operators Console an Interrupt Signal Was Sent to Central Processing Unit Causing Digital Data Processor to Halt | |
|