LER-1981-015, During Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training Revised |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2931981015R03 - NRC Website |
|
text
UPDATE REPORT PREVIOUS REPORT ISSUED 5/19/81 aremvn ov w e r;nM see u.c. tun.;4a r.ncutarmy camuison n siso. con y#Td se LICENSEE EVENT REPORT ke CONTROL 8 LOCK: l l
l l
l l
l@
(PLEASE PRINT OR TYPE ALL REQutRED INFORMATION) j oli l lM l A l P l P l S l llgl 0l0 l - l 0l 0l 0] 0 l 0 l -l 0l0 lgl 4 l 1 ll ll l1l@)
l lg u..........
u...........
o a u.~..,v..
n
.,c,..
CON'T Ioi5 l
- g;"; y@l 0l 5l 0l-l 0 l 2l 9l3 ]@l 0 l 4l Il7 l 8 l 1 l@l0 l 3 0 l9 I 8 l 4l@
.5
..CR..NUM...
.V.N,..,.
.....,..k g
lOn4/17/81,at1130 hours, routine @surveillancetestingwasbeingconductedon EVENT OESCRIPTION ANO PROBABLE CoNSE0uENCES o2 lTl q l the Cardox System hose reels and nozzles. After successfully testing the 51 ft.l
,p ;g level hose station, a test was conducted on the 23 ft. level hose reel and noz-l lol3ll zie. The nozzle failed to deliver an adequate stream. A fire watch was im-l lo ls l l mediately established as required by Technical Specifications. Approximately l
lo l7 ll two hours later, the system was satisf actorily retested and returned to service.]
l o l 8 l l (Ref er to attachment.) This event caused no threat to the public health and saf y.
. c:e":...:'u:.
c'::
.::"n.
j ol9 l l A l B l @ @ @ [ Bj @ lP lI l P l E l X l X l @ [A_J @ l Z l @
... U. NT i. b
.CCU...NC.
.. v... N
@ !"di", IsiiI L..J l oli I s l L,o, 10131 lxl 1, 1 b_l u
n u
.%"c,
'" T",. ;"
@ *:n c,",",n'.::"";.. ".'".u ;"'-
c bij@lx l@ Lz_l@
tzJO I o f of cl o I Ly_lO L2]O lA_l@
I cI 21 si si n
u o
a n
a u
u n
a u
CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS O>>
l t lo ll Cause of this event was determined to be operator error.
Engineering evaluation l l1li ll has determined that the nozzles will not permit C07 discharge unless the trigger l liTill on the hose station actuation valve is fully depressed.
Fire Brigade training l l was revised accordingly and Fire Brigade members were instructed on the correct l i 3 I
lTITl l method of activatino the Cardox System.
......... @ l:,. = =lB l@l SurveiiIance Testing l
IIIII W @ It In l n l@l NA
~
~
~
~
' !'n. :*?L',":
@l e...,,.
....u....
l NA l
l iI e I L. 2J @ l_2JSI NA g
NA
]
ITITl I 01 010 l@L..Z_J@l NUM...
.....,1.M NA l
l il s l l 0l 0l 0 l@l a
8404030276 840319 n
i.
PDR ADOCK 05000293 PDR l
n..
...c. in.
l1l9l U. @l ion NRC uSE ONLY
...u l""'n'lckni.N h NA l lljjj;llgy lg
, L, "JOI 2 o (617) 746-7900 P. J. Hamilton pgang NAME oF PREPARER
\\
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION
=
DOCKET NO. 50-293 Attachment t 31 -015-03X-1
Description
On April 17, 1981, the once a cycle surveillance (8.B.5) was being con-ducted on the Cardox Fire Protection System. This system consists of a storage ur.'t.having a. capacity of four tons which maintains liquid COThesystemks at a low temperature (-l'F) and low pressure (300 psig).
used for fire protection of the cable spreading room, as a supply source for three CO, fire hose stations (23' switchgear, 37' switchgcar and 51' generator area) and for generator purge.
When a CO h ze n zzle is removed from its brackets the mastor selector 2
/alve for the hose system opens allowing CO reach all three nozzles.
2 C0 can then be discharged by operating the squeeze trigger on the noz-zl The C0 hose reel on the 51' elevation was the first tested and was satis-7 factor?. The 23' elevation was then tested and failed. The 37' elevation was then satisf actorily tested. The testing at the 51' elevation permitted t reach all three hose reels. Heavy frost coating liquid and vaporous CO2 was observed on the pipes during this testing. The 23' elevation was re-tested within minutes and again failed. This CO station was declared in-3 Two operable, a maintenance request issued and a fire watch established.
hours later this hose station was satisf actorily tested and declared operable.
Cause and Corrective Action A review of the event by engineering revealed that the cause of the event was due to operator error and not a frozen hose station as described in the previous report. As a result of this followup investigation to the incident, it has been determined that the nozzles will not permit C0 dis-7 To elimTnate charge if the trigger or the handle is not f ully depressed.
a recurrence of this incident, the Training Department has revised the Fire Brigade training curriculum and members of the Fire Brigade have been in-structed on the correct method of activating the Cardox System.
N i
a
s WORTON EDISON COMPANY b
500 GovLaTON STRrrY l
BOSTON. MAESACHUSETTs 02199 WILLIAM O. NARRINsTON g.
March 19,1984 BEco. #84- 043 Regional Administrator, Region I U.S. Nuclear Regulatory Connission 631 Park Avenue King of Prussia, PA 19406 Docket Number 50-293 License DPR-35 Gentlemen:
l The attached. updated License Event Report 81-015/03X-1 "C02 System Hose Inoperable", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.B.2.b.
.If there are any questions on this subject, please do not hesitate to contact the. undersigned.
Very truly yours, 1))
William D. Harrington WDH/mg L
l Enclosures: LER 81-015/03X-1 cc:
Document Control Desk Office of Management Information and Program Control U.S. Nuclear Regulatory Comission Washington, D.C.
20555 Standard BECo. LER distribution Y
W 4o
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000293/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000293/LER-1981-001-03, /03L-0:on 801226,unidentified Drywell Leakage Measured at Rate Contrary to Tech Specs.Cause Not Known Excessive Leakage Eliminated by Backstating B Recirculation Pump Suction Valve Mo 202-4B & Discharge Valve Mo 202-5B | /03L-0:on 801226,unidentified Drywell Leakage Measured at Rate Contrary to Tech Specs.Cause Not Known Excessive Leakage Eliminated by Backstating B Recirculation Pump Suction Valve Mo 202-4B & Discharge Valve Mo 202-5B | | | 05000293/LER-1981-002-03, /03L-0:on 810107,main Stack Sample Flow Alarm Received Twice on Panel C903 in Control Room.Caused by Frozen Suction Line (First Occurrence) & Blown Power Supply Fuse (Second Occurrence) | /03L-0:on 810107,main Stack Sample Flow Alarm Received Twice on Panel C903 in Control Room.Caused by Frozen Suction Line (First Occurrence) & Blown Power Supply Fuse (Second Occurrence) | | | 05000293/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000293/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000293/LER-1981-003-03, /03L-0:on 810123,heat Detector Failed in Diesel Generator a Room.Detector Alarm Could Not Be Reset.Cause Not Stated.Jumper Added to Eliminate Alarm on Control Room Panel C-114 Until Sys Repaired.Detector Replaced & Jumper Re | /03L-0:on 810123,heat Detector Failed in Diesel Generator a Room.Detector Alarm Could Not Be Reset.Cause Not Stated.Jumper Added to Eliminate Alarm on Control Room Panel C-114 Until Sys Repaired.Detector Replaced & Jumper Removed | | | 05000293/LER-1981-004, Forwards LER 81-004/01T-0 | Forwards LER 81-004/01T-0 | | | 05000293/LER-1981-004-01, /01T-0:on 810225,review Indicated That If Backup Scram Solenoids Failed,Actuation of ATWS Sys Would Prevent Closure of Scram Discharge Vol Vent & Drain Valves,Violating Primary Containment.Cause Due to Oversight in Design | /01T-0:on 810225,review Indicated That If Backup Scram Solenoids Failed,Actuation of ATWS Sys Would Prevent Closure of Scram Discharge Vol Vent & Drain Valves,Violating Primary Containment.Cause Due to Oversight in Design | | | 05000293/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000293/LER-1981-005-03, /03L-0:on 810202,unidentified Reactor Drywell Coolant Leakage Rates Measured Above Tech Spec Level.Cause Not Stated.Recirculation Pump Suction Valves a & B & Discharge Valves Backseated | /03L-0:on 810202,unidentified Reactor Drywell Coolant Leakage Rates Measured Above Tech Spec Level.Cause Not Stated.Recirculation Pump Suction Valves a & B & Discharge Valves Backseated | | | 05000293/LER-1981-006-01, /01X-0:on 810219,review of Alleged Omission in Scheduling of 11 Once Per Cycle Instrumentation Verified Oversight.Caused by Misinterpretation of Special Circumstances Which Must Be Applied to Testing Definition | /01X-0:on 810219,review of Alleged Omission in Scheduling of 11 Once Per Cycle Instrumentation Verified Oversight.Caused by Misinterpretation of Special Circumstances Which Must Be Applied to Testing Definition | | | 05000293/LER-1981-007-03, /03L-0:on 810217,reactor Coolant Leak Detection Air Sampling Sys Declared Inoperable.Caused by Blown Fuses. Fuses Replaced.Pump Will Be Rebuilt | /03L-0:on 810217,reactor Coolant Leak Detection Air Sampling Sys Declared Inoperable.Caused by Blown Fuses. Fuses Replaced.Pump Will Be Rebuilt | | | 05000293/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000293/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000293/LER-1981-008-03, /03L-0:on 810313,inboard Isolation Valve Mo 2301-5 Was Determined to Be Inoperable.Caused by Manual Operation Disengagement Spring in Limitorque Operator Being Broken & Imbedded in Operator Gear Teeth,Jamming Gears | /03L-0:on 810313,inboard Isolation Valve Mo 2301-5 Was Determined to Be Inoperable.Caused by Manual Operation Disengagement Spring in Limitorque Operator Being Broken & Imbedded in Operator Gear Teeth,Jamming Gears | | | 05000293/LER-1981-009-03, Inboard Isolation Valve Failed to Open & HPCI Sys Declared Inoperable.Caused by Incorrect Min Torque Switch Setting of Motor Operator & Thermal Binding.Torque Switch Set at Max Value | Inboard Isolation Valve Failed to Open & HPCI Sys Declared Inoperable.Caused by Incorrect Min Torque Switch Setting of Motor Operator & Thermal Binding.Torque Switch Set at Max Value | | | 05000293/LER-1981-010, Forwards LER 81-010/04T-0 | Forwards LER 81-010/04T-0 | | | 05000293/LER-1981-010-04, /04T-0:on 810407,rept Received Indicating Excessive Co-60 Concentration in Mussel Sample Taken from Discharge Canal.Cause Not Stated.Dose Insignificant When Compared to Natural Background Dose | /04T-0:on 810407,rept Received Indicating Excessive Co-60 Concentration in Mussel Sample Taken from Discharge Canal.Cause Not Stated.Dose Insignificant When Compared to Natural Background Dose | | | 05000293/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000293/LER-1981-011-03, /03L-0:on 810402,recirculation Pump B Motor Generator Set Tripped Resulting in Drive Motor Trip & Generator Lockout Alarms Sounding.Cause Not Determined.Set Returned to Svc | /03L-0:on 810402,recirculation Pump B Motor Generator Set Tripped Resulting in Drive Motor Trip & Generator Lockout Alarms Sounding.Cause Not Determined.Set Returned to Svc | | | 05000293/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000293/LER-1981-012-03, /03L-0:on 810403,4 Kv Breaker A507,feeding Core Spray Pump P215A,inadvertently Closed During Routine Keep Fill Checks on Low Pressure ECCS Sys.Caused by Inconsistency in Automatic & Close/Trip Sequence Timings | /03L-0:on 810403,4 Kv Breaker A507,feeding Core Spray Pump P215A,inadvertently Closed During Routine Keep Fill Checks on Low Pressure ECCS Sys.Caused by Inconsistency in Automatic & Close/Trip Sequence Timings | | | 05000293/LER-1981-013, Forwards LER 81-013/04T-0 | Forwards LER 81-013/04T-0 | | | 05000293/LER-1981-013-04, /04T-0:on 810430,rept Received from Yankee Atomic Lab Re High Concentration of Co-60 in Irish Moss Sample Taken on 810218.Probably Caused by Fallout from Recent Atmospheric Weapons Tests | /04T-0:on 810430,rept Received from Yankee Atomic Lab Re High Concentration of Co-60 in Irish Moss Sample Taken on 810218.Probably Caused by Fallout from Recent Atmospheric Weapons Tests | | | 05000293/LER-1981-014-03, /03L-0:on 810414,pressure Instrument 261-39B Indicating Needle Went Beyond Mechanical Stop.Caused by Technician Error.Instrument Repaired.Technician Instructed | /03L-0:on 810414,pressure Instrument 261-39B Indicating Needle Went Beyond Mechanical Stop.Caused by Technician Error.Instrument Repaired.Technician Instructed | | | 05000293/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000293/LER-1981-015-03, During Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training Revised | During Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training Revised | | | 05000293/LER-1981-016-03, /03L-0:on 810430,reactor Core Isolation Cooling Valve Mo 1301-17 Failed to Close on Demand Following Switch Actuation.Caused by Deteriorated Packing Jammed Between Valve Stem & Packing Gland.Packing Replaced | /03L-0:on 810430,reactor Core Isolation Cooling Valve Mo 1301-17 Failed to Close on Demand Following Switch Actuation.Caused by Deteriorated Packing Jammed Between Valve Stem & Packing Gland.Packing Replaced | | | 05000293/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000293/LER-1981-017-03, /03L-0:on 810503,refuel Floor Exhaust Radiation Monitor 1705-8A Failed Downscale.Caused by Drop in High Voltage Output Due to Failed Capacitor in High Voltage Power Supply Circuit.Capacitor Replaced | /03L-0:on 810503,refuel Floor Exhaust Radiation Monitor 1705-8A Failed Downscale.Caused by Drop in High Voltage Output Due to Failed Capacitor in High Voltage Power Supply Circuit.Capacitor Replaced | | | 05000293/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000293/LER-1981-018, Forwards Updated LER 81-018/03X-1 | Forwards Updated LER 81-018/03X-1 | | | 05000293/LER-1981-018-03, Stack Gas Radiation Monitor 1705-18A Was Downscale & Inoperable Following Lightning Strike Near Main Stack.Caused by Voltage Surge Resulting in Preamplifier & Discriminator Circuits Failure | Stack Gas Radiation Monitor 1705-18A Was Downscale & Inoperable Following Lightning Strike Near Main Stack.Caused by Voltage Surge Resulting in Preamplifier & Discriminator Circuits Failure | | | 05000293/LER-1981-019-03, /03L-0:on 810514,level Recorder 5049 Was Found Indicating High.Caused by Calibr Shift Due to Jarring Instrument Sensing Lines During Installation of Torus Room Staging.Recorder & Transmitters Recalibr | /03L-0:on 810514,level Recorder 5049 Was Found Indicating High.Caused by Calibr Shift Due to Jarring Instrument Sensing Lines During Installation of Torus Room Staging.Recorder & Transmitters Recalibr | | | 05000293/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000293/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000293/LER-1981-020-03, /03L-0:on 810603,fire Protection Engineer Determined That 810224 Fire on 51-ft Elevation,Initially Reviewed Per Orc Meeting 81-39,should Be Reported.Caused by Failure to Follow Combustible Matl Removal Procedures | /03L-0:on 810603,fire Protection Engineer Determined That 810224 Fire on 51-ft Elevation,Initially Reviewed Per Orc Meeting 81-39,should Be Reported.Caused by Failure to Follow Combustible Matl Removal Procedures | | | 05000293/LER-1981-021, Forwards LER 81-021/01T-0 | Forwards LER 81-021/01T-0 | | | 05000293/LER-1981-021-01, /01T-0:on 810615,review of Analysis Responding to 10CFR50.44 Determined Inadequate.Mgt Controls Failed to Identify Effect of Rendering post-accident Nitrogen Supply Sys Inoperable.Caused by Inadequate Mgt Controls | /01T-0:on 810615,review of Analysis Responding to 10CFR50.44 Determined Inadequate.Mgt Controls Failed to Identify Effect of Rendering post-accident Nitrogen Supply Sys Inoperable.Caused by Inadequate Mgt Controls | | | 05000293/LER-1981-022-03, /03L-0:on 810519,reactor Coolant Leak Detection Air Sampling Sys C-19 Pump Motor Overheated & Blew Fuses. Cause Under Investigation | /03L-0:on 810519,reactor Coolant Leak Detection Air Sampling Sys C-19 Pump Motor Overheated & Blew Fuses. Cause Under Investigation | | | 05000293/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000293/LER-1981-023-03, /03L-0:on 810601 & 800721,two Primary Containment Nitrogen Supply Valves Made Inoperable & Valve in Same Line Placed in Isolated Condition.Caused by Lines Cut & Capped Due to Maint on post-accident Nitrogen Supply Sys | /03L-0:on 810601 & 800721,two Primary Containment Nitrogen Supply Valves Made Inoperable & Valve in Same Line Placed in Isolated Condition.Caused by Lines Cut & Capped Due to Maint on post-accident Nitrogen Supply Sys | | | 05000293/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000293/LER-1981-024-03, /03L-0:on 810604,shutdown Transformer Primary & Secondary Breakers Opened Due to Fault in Offsite Power Supply.Caused by Failure of Cable Porcelain Clamps.Clamps removed.Post-type Insulators Installed | /03L-0:on 810604,shutdown Transformer Primary & Secondary Breakers Opened Due to Fault in Offsite Power Supply.Caused by Failure of Cable Porcelain Clamps.Clamps removed.Post-type Insulators Installed | | | 05000293/LER-1981-024, Forwards LER 81-024/03L-0 | Forwards LER 81-024/03L-0 | | | 05000293/LER-1981-025-03, /03L-0:on 810607,technician Failed to Document Jumper Installation.Caused by Shift Turnover During Installation.Personnel Instructed to Remain W/Job Until Completion,Regardless of Shift Times | /03L-0:on 810607,technician Failed to Document Jumper Installation.Caused by Shift Turnover During Installation.Personnel Instructed to Remain W/Job Until Completion,Regardless of Shift Times | | | 05000293/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000293/LER-1981-026-01, /01X-0:on 810707,during Engineering Analyses, Components of Standby Gas Treatment Sys Were Found to Have Insufficient Documentation to Demonstrate Operation During Loca.Documentation Acquired | /01X-0:on 810707,during Engineering Analyses, Components of Standby Gas Treatment Sys Were Found to Have Insufficient Documentation to Demonstrate Operation During Loca.Documentation Acquired | | | 05000293/LER-1981-026, Forwards LER 81-026/01T-0 | Forwards LER 81-026/01T-0 | | | 05000293/LER-1981-027-03, /03L-0:on 810616,while Performing Rod Block Monitor Surveillance Test 8.M.2.3.1,step 31 High Rod Block Came on at 123% Vs 94% Power.Caused by Failed Trip Ref Card. Card Replaced in Kind | /03L-0:on 810616,while Performing Rod Block Monitor Surveillance Test 8.M.2.3.1,step 31 High Rod Block Came on at 123% Vs 94% Power.Caused by Failed Trip Ref Card. Card Replaced in Kind | |
|