|
|
| Line 1: |
Line 1: |
| #REDIRECT [[05000312/LER-1978-004-01, /01T-0:on 780414,B&W Reported That Small Break Analysis Not Based on Worst Break Location.Change Required in Calculated Results Reported in BAW-10052 & BAW-10103A Revision 3.Potential Solution Being Evaluated by B&W]]
| | {{Adams |
| | | number = ML20147B213 |
| | | issue date = 07/20/1978 |
| | | title = /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes |
| | | author name = Colombo R |
| | | author affiliation = SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| | | addressee name = |
| | | addressee affiliation = |
| | | docket = 05000312 |
| | | license number = |
| | | contact person = |
| | | document report number = LER-78-004-01T, LER-78-4-1T, NUDOCS 7810100021 |
| | | package number = ML20147B207 |
| | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
| | | page count = 1 |
| | }} |
| | {{LER |
| | | Title = /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes |
| | | Plant = |
| | | Reporting criterion = |
| | | Power level = |
| | | Mode = |
| | | Docket = 05000312 |
| | | LER year = 1978 |
| | | LER number = 4 |
| | | LER revision = 1 |
| | | Event date = |
| | | Report date = |
| | | ENS = |
| | | abstract = |
| | }} |
| | |
| | =text= |
| | {{#Wiki_filter:_ |
| | s i |
| | ~ |
| | m j |
| | ,2 FOLLOW UP TO R.O.78-04 |
| | ,iu eii d |
| | NRC FORM 366 u. S. NUCLE AR REGUL ATORY COMMISSION (7 77i LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) f 6 |
| | [oT l I C IA l R i S f S l l l@iSl 0 l 01 - l 0 l 0 l 0 l 0 l 0 l - l0 l 0 l@l 4 l 1l 1 l 1 l 1l@l l (g l |
| | ) |
| | 8 9 LICENSE E CODE 14 LICENSE NUMilEM h |
| | .4 LsCENbt TYPE JO bl L A T bd CON'T 101il 3 CRU L xj g i Oi 5 i O i0 ; Oi311;2igi0 i 4;i ;4;7 i 8 gi ; 7 2iO i 7;8 g i |
| | 0 i |
| | ? |
| | 8 6J 64 OOCKE T NUMBER 60 6J kVENT D ATE I4 76 REPCHT DATE 63 i |
| | EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o 1012i 1 On April 14, 1978, Bsw reported that previous small break analysis had j |
| | i 10131 I not been based on the worst break location. The report indicated i |
| | i O 4 I that the worst case break had now been determined to be at the R.C. pump, |
| | l FBTil I discharge. The results show that it is necessary to use operator t |
| | lo is i l action during the early stages of the postulated accident to ef fectively i l |
| | 10 l 7 l 1 mitigate the accident consequences and meet the criteria of 10 CFR 50.46.l 10181l I |
| | i 8 9 |
| | #0 OE CODE SUBC E COMPONENT CODE SUBCODE SU E |
| | 10l91 15 l Fl@ [Bj@ LA_l@ l z l zl z ! ZlZ l Zl@ LZj@ [zj @ |
| | 7 8 |
| | 9 to 11 12 13 18 19 JJ SE QUE N TI A L, |
| | OCCURRENCE REPORT REVISION O lLER RO |
| | _ EVENT YE AR RE PORT NO. |
| | CODE TYPE NO. |
| | I jg; 17181 L _J 1010141 Ld fo ll i LLI L _J L1_J |
| | _2s n |
| | :u 24 a |
| | ar a |
| | n 3s 3n 32 |
| | \\ |
| | EEN 'NY*N' O!','tET 80$ Sil' |
| | @ "sSeMirT T |
| | ,O'R 7,de "'"' ' e7 uANTFiCT.IE R |
| | { ) |
| | A O |
| | wOUR UPPti [qj@lEJ@ lBl@ |
| | LZj@ |
| | l 010 l 0101 'LY_J @ |
| | Laj@ Lzj@ tz_19 I 9 l 9 l@ |
| | 33 34 3b Jo 31 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORREC flVE ACTIONS h |
| | ' ] |
| | li 101 IB6W analysis of small breaks indicated a change in calculated results i |
| | m geompared to those previously reported in BAW-10052 and BAW-10103A Rev. 3., |
| | rTTTI I B6W has identified and evaluated solutions to the satisfaction of the l af fected utilities and NRC. |
| | The District has incorporated procedure |
| | 'l |
| | , 3 I changes and initlated design changes (ECN 2174) and proposed T.S. Amend. #58., |
| | ll 7 |
| | 8 9 80 STA S |
| | % POWER OTHERSTATV$ |
| | 15CO RY DISCOVERY OESCRfPTION [EJ @ l0l7l 0l@l NA l LDj@l Notification from NSSS l |
| | ,1 i s A TIVITY CONTENT RELE ASE D OF RE LE ASE AMOUNT OF ACTIVITY LOC ATION OF RELE ASE LZJ O LZ_J@l NA l |
| | l NA l |
| | I : |
| | *E R sow'Ei n PosS ts DEsc.o. TION @ |
| | NuusER TvPE L'_LJ l 0l 010 l@l zj@l NA l |
| | ERsOut't'm; 3 Es 8 |
| | Q l0l0l0l@lDEscRieriOs@ N A NoveE n l |
| | 7 8 9 Ii 12 Eo |
| | '#E E sCW,'1 ''C'''" @ |
| | l 8 Lzj@l NA l |
| | !l 7 |
| | h 9 13 |
| | $0 I |
| | ?S$UE DE CRIPTION 8 LYjbl Local Newscaners and Wire Service 5/8/78 I IIIIt!IfiIttI 7 |
| | 8 9 10 68 69 ED ol d o 9 |
| | ~ |
| | NAVE Or PREPAREn PHONE-7 81@h [@M i |
| | }} |
| | |
| | {{LER-Nav}} |
/01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes| ML20147B213 |
| Person / Time |
|---|
| Site: |
Rancho Seco |
|---|
| Issue date: |
07/20/1978 |
|---|
| From: |
Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20147B207 |
List: |
|---|
| References |
|---|
| LER-78-004-01T, LER-78-4-1T, NUDOCS 7810100021 |
| Download: ML20147B213 (1) |
|
LER-1978-004, /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3121978004R01 - NRC Website |
|
text
_
s i
~
m j
,2 FOLLOW UP TO R.O.78-04
,iu eii d
NRC FORM 366 u. S. NUCLE AR REGUL ATORY COMMISSION (7 77i LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) f 6
[oT l I C IA l R i S f S l l l@iSl 0 l 01 - l 0 l 0 l 0 l 0 l 0 l - l0 l 0 l@l 4 l 1l 1 l 1 l 1l@l l (g l
)
8 9 LICENSE E CODE 14 LICENSE NUMilEM h
.4 LsCENbt TYPE JO bl L A T bd CON'T 101il 3 CRU L xj g i Oi 5 i O i0 ; Oi311;2igi0 i 4;i ;4;7 i 8 gi ; 7 2iO i 7;8 g i
0 i
?
8 6J 64 OOCKE T NUMBER 60 6J kVENT D ATE I4 76 REPCHT DATE 63 i
EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o 1012i 1 On April 14, 1978, Bsw reported that previous small break analysis had j
i 10131 I not been based on the worst break location. The report indicated i
i O 4 I that the worst case break had now been determined to be at the R.C. pump,
l FBTil I discharge. The results show that it is necessary to use operator t
lo is i l action during the early stages of the postulated accident to ef fectively i l
10 l 7 l 1 mitigate the accident consequences and meet the criteria of 10 CFR 50.46.l 10181l I
i 8 9
- 0 OE CODE SUBC E COMPONENT CODE SUBCODE SU E
10l91 15 l Fl@ [Bj@ LA_l@ l z l zl z ! ZlZ l Zl@ LZj@ [zj @
7 8
9 to 11 12 13 18 19 JJ SE QUE N TI A L,
OCCURRENCE REPORT REVISION O lLER RO
_ EVENT YE AR RE PORT NO.
CODE TYPE NO.
I jg; 17181 L _J 1010141 Ld fo ll i LLI L _J L1_J
_2s n
- u 24 a
ar a
n 3s 3n 32
\\
EEN 'NY*N' O!','tET 80$ Sil'
@ "sSeMirT T
,O'R 7,de "'"' ' e7 uANTFiCT.IE R
{ )
A O
wOUR UPPti [qj@lEJ@ lBl@
LZj@
l 010 l 0101 'LY_J @
Laj@ Lzj@ tz_19 I 9 l 9 l@
33 34 3b Jo 31 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORREC flVE ACTIONS h
' ]
li 101 IB6W analysis of small breaks indicated a change in calculated results i
m geompared to those previously reported in BAW-10052 and BAW-10103A Rev. 3.,
rTTTI I B6W has identified and evaluated solutions to the satisfaction of the l af fected utilities and NRC.
The District has incorporated procedure
'l
, 3 I changes and initlated design changes (ECN 2174) and proposed T.S. Amend. #58.,
ll 7
8 9 80 STA S
% POWER OTHERSTATV$
15CO RY DISCOVERY OESCRfPTION [EJ @ l0l7l 0l@l NA l LDj@l Notification from NSSS l
,1 i s A TIVITY CONTENT RELE ASE D OF RE LE ASE AMOUNT OF ACTIVITY LOC ATION OF RELE ASE LZJ O LZ_J@l NA l
l NA l
I :
- E R sow'Ei n PosS ts DEsc.o. TION @
NuusER TvPE L'_LJ l 0l 010 l@l zj@l NA l
ERsOut't'm; 3 Es 8
Q l0l0l0l@lDEscRieriOs@ N A NoveE n l
7 8 9 Ii 12 Eo
'#E E sCW,'1 C'" @
l 8 Lzj@l NA l
!l 7
h 9 13
$0 I
?S$UE DE CRIPTION 8 LYjbl Local Newscaners and Wire Service 5/8/78 I IIIIt!IfiIttI 7
8 9 10 68 69 ED ol d o 9
~
NAVE Or PREPAREn PHONE-7 81@h [@M i
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000312/LER-1978-001-04, /04T-0:on 780109,plant Liquid Effluent Ph Levels Exceeded Tech Spec 8.5 Limit.Ph Sensor Setpoint Raised in Summer to Folson South Canal Ph Level & Not Reset When Ph Level Dropped,Eliminating Automatic Diversion Feature | /04T-0:on 780109,plant Liquid Effluent Ph Levels Exceeded Tech Spec 8.5 Limit.Ph Sensor Setpoint Raised in Summer to Folson South Canal Ph Level & Not Reset When Ph Level Dropped,Eliminating Automatic Diversion Feature | | | 05000312/LER-1978-001, Responds to NRC Expressing Concern That 780320 Transient,Reported as LER 78-1,could Have Led to Results as Serious as Tmi.Operator Recognized That once-through Steam Generators Were Dry & Therefore Admitted Main Feedwater | Responds to NRC Expressing Concern That 780320 Transient,Reported as LER 78-1,could Have Led to Results as Serious as Tmi.Operator Recognized That once-through Steam Generators Were Dry & Therefore Admitted Main Feedwater | | | 05000312/LER-1978-001-01, /01T-0:on 780320,non-nuclear Instrumentation Dc Power Short Resulted in Reactor Trip & RCS Cooldown in Excess of Tech Spec Figure 3.1.2-2 Limits.Caused by Operator Changing Lightbulb.Conditions Imposed for Return to Power | /01T-0:on 780320,non-nuclear Instrumentation Dc Power Short Resulted in Reactor Trip & RCS Cooldown in Excess of Tech Spec Figure 3.1.2-2 Limits.Caused by Operator Changing Lightbulb.Conditions Imposed for Return to Power | | | 05000312/LER-1978-002-03, /03L-0:on 780228,safety Sys Hydraulic Snubbers 25 & 26 Found Low on Fluid During Visual Insp.No Leakage Found. Cause Not Determined.Snubbers Refilled & Surveillance Interval Reduced to Six Months | /03L-0:on 780228,safety Sys Hydraulic Snubbers 25 & 26 Found Low on Fluid During Visual Insp.No Leakage Found. Cause Not Determined.Snubbers Refilled & Surveillance Interval Reduced to Six Months | | | 05000312/LER-1978-002-04, /04T-0:on 780414,hypochlorite Spilled & Flushed Into Drain Sys During Hypochlorite Chemical Tank Filling, Causing Chlorine Levels to Exceed Limits.Fill Line Will Be Capped Prior to Removal & Spills Will Not Be Flushed | /04T-0:on 780414,hypochlorite Spilled & Flushed Into Drain Sys During Hypochlorite Chemical Tank Filling, Causing Chlorine Levels to Exceed Limits.Fill Line Will Be Capped Prior to Removal & Spills Will Not Be Flushed | | | 05000312/LER-1978-002, Forwards LER 78-002/03L-0 | Forwards LER 78-002/03L-0 | | | 05000312/LER-1978-003-03, /03L-1 on 780710:Maintenance on Safety Sys Hydraulic Snubber Previously Found to Have Low Fluid Accumulator Level Revealed 2 Deteriorated o-rings Made W Polyurethene Seals Instead of ethylene-propylene Seals | /03L-1 on 780710:Maintenance on Safety Sys Hydraulic Snubber Previously Found to Have Low Fluid Accumulator Level Revealed 2 Deteriorated o-rings Made W Polyurethene Seals Instead of ethylene-propylene Seals | | | 05000312/LER-1978-003-04, /04T-0:on 780913,during Steady State Operation, Dissolved Oxygen Concentration Downstream of Confluence of Hadselville & Clay Creek Was Less than Minimum of 5mg/liter Typical of Stagnant Water.Location Is Beyond Util Propert | /04T-0:on 780913,during Steady State Operation, Dissolved Oxygen Concentration Downstream of Confluence of Hadselville & Clay Creek Was Less than Minimum of 5mg/liter Typical of Stagnant Water.Location Is Beyond Util Property | | | 05000312/LER-1978-003, Forwards LER 78-003/04T-0 | Forwards LER 78-003/04T-0 | | | 05000312/LER-1978-004, Forwards LER 78-004/01T | Forwards LER 78-004/01T | | | 05000312/LER-1978-004-01, /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes | /01T-1:on 780414,small Break Analysis Determined to Be at Rc Pump Discharge.Analysis Identified & Evaluated Solutions.Facility Has Incorporated Procedural Changes & Initiated Design Changes | | | 05000312/LER-1978-005-01, /01T-0:on 780509,four Main Steam Code Safety Valves Found Improperly Set in Nonconservative Direction. Caused by Procedural Inadequacy.Maint Procedure Included Hydroset Curve for One Type Orifice.Procedure Revised | /01T-0:on 780509,four Main Steam Code Safety Valves Found Improperly Set in Nonconservative Direction. Caused by Procedural Inadequacy.Maint Procedure Included Hydroset Curve for One Type Orifice.Procedure Revised | | | 05000312/LER-1978-006, Forwards LER 78-006/03L-0 | Forwards LER 78-006/03L-0 | | | 05000312/LER-1978-006-03, /03L-0:on 780611,during Normal Operation,Increased Leakage Noticed,Between 1.1-1.7 Gallons/Min.Caused by Leaking Pressure Safety Valves & Block Valve on Electromatic Relief Valve.Valves Replaced or Reworked | /03L-0:on 780611,during Normal Operation,Increased Leakage Noticed,Between 1.1-1.7 Gallons/Min.Caused by Leaking Pressure Safety Valves & Block Valve on Electromatic Relief Valve.Valves Replaced or Reworked | | | 05000312/LER-1978-007-03, /03L-0:on 780622,frequent Makeup Tank Level Changes Observed.Caused by Excessive Leakage from B Decay Heat Removal Sys Pump Seal.Pump Valved Out & Sys a Continued Operation.Leaking Seal Replaced | /03L-0:on 780622,frequent Makeup Tank Level Changes Observed.Caused by Excessive Leakage from B Decay Heat Removal Sys Pump Seal.Pump Valved Out & Sys a Continued Operation.Leaking Seal Replaced | | | 05000312/LER-1978-008, Forwards LER 78-008/02T-0 | Forwards LER 78-008/02T-0 | | | 05000312/LER-1978-008-02, /02T-0:on 780804,analysis Showed Atypical Weld Filler Wire W/High Silicon & Low Nickel Contents in Archive Weldments.Wire Mixed by Supplier W/Shipment of Mn-Mo-Ni Filler Wire.Caused by Inadequate QA | /02T-0:on 780804,analysis Showed Atypical Weld Filler Wire W/High Silicon & Low Nickel Contents in Archive Weldments.Wire Mixed by Supplier W/Shipment of Mn-Mo-Ni Filler Wire.Caused by Inadequate QA | | | 05000312/LER-1978-009-03, /03L-0:on 780913,diesel Driven Fire Pump P-996 Tripped on Overspeed During test.Engine-to-pump Coupling Bolts Were Discovered to Be Sheared,Probably Due to Overtorquing.Bolts Were Replaced,Torque Values Verified | /03L-0:on 780913,diesel Driven Fire Pump P-996 Tripped on Overspeed During test.Engine-to-pump Coupling Bolts Were Discovered to Be Sheared,Probably Due to Overtorquing.Bolts Were Replaced,Torque Values Verified | | | 05000312/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000312/LER-1978-010, Forwards LER 78-010/01T-0 | Forwards LER 78-010/01T-0 | | | 05000312/LER-1978-010-01, /01T-0 on 780914:During Normal Oper It Was Found That Fire Hydrant 3 Hose Cabinet Had Not Been Relocated W/Hydrant.Upon Discovery of Discrepancy Hose Cabinet Was Relocated | /01T-0 on 780914:During Normal Oper It Was Found That Fire Hydrant 3 Hose Cabinet Had Not Been Relocated W/Hydrant.Upon Discovery of Discrepancy Hose Cabinet Was Relocated | | | 05000312/LER-1978-011-01, /01T-0:on 780914,required Continual Fire Watch Erroneously Terminated.Caused by Shift Personnel Misunderstanding.Personnel Instructed | /01T-0:on 780914,required Continual Fire Watch Erroneously Terminated.Caused by Shift Personnel Misunderstanding.Personnel Instructed | | | 05000312/LER-1978-011, Forwards LER 78-011/01T-0 | Forwards LER 78-011/01T-0 | | | 05000312/LER-1978-012-03, /03L-0:on 780927,header Failed to Discharge During Routine Testing of CO2 Sys.Caused by Defective Microswitch on Solenoid Which Operates Pilot Valve Integral W/Main Isolation Valve Controller | /03L-0:on 780927,header Failed to Discharge During Routine Testing of CO2 Sys.Caused by Defective Microswitch on Solenoid Which Operates Pilot Valve Integral W/Main Isolation Valve Controller | | | 05000312/LER-1978-012, Forwards LER 78-012/03L-0 | Forwards LER 78-012/03L-0 | | | 05000312/LER-1978-013, Forwards LER 78-013/03L-0 | Forwards LER 78-013/03L-0 | | | 05000312/LER-1978-013-03, /03L-0:on 780925,HPI Loop a Flow Transmitter FT-23807 Found Inoperable During Surveillance Procedure 200.14.Caused by Broken Bellows in Flow Transmitter.Failed Bellows Replaced | /03L-0:on 780925,HPI Loop a Flow Transmitter FT-23807 Found Inoperable During Surveillance Procedure 200.14.Caused by Broken Bellows in Flow Transmitter.Failed Bellows Replaced | | | 05000312/LER-1978-015-01, /01T-0:on 781120,failure of 9 Bergen-Patterson Snubbers.Seven of 9 Failures Caused by Abusive Handling During Reinstallation Following 1977 Testing.Other Two Failures Isolated Cases.Failed Units Repaired | /01T-0:on 781120,failure of 9 Bergen-Patterson Snubbers.Seven of 9 Failures Caused by Abusive Handling During Reinstallation Following 1977 Testing.Other Two Failures Isolated Cases.Failed Units Repaired | | | 05000312/LER-1978-015, Forwrds LER 78-015/01T-0 | Forwrds LER 78-015/01T-0 | | | 05000312/LER-1978-016, Forwards LER 78-016/01T-0 | Forwards LER 78-016/01T-0 | | | 05000312/LER-1978-016-01, /01T-0:on 781024,operability of a Diesel Generator Lost Due to Failure of Primary Fuses on the Voltage Regulators Control Power Circuit.Fuses Replaced,A Generator Tested Then Returned to Svc | /01T-0:on 781024,operability of a Diesel Generator Lost Due to Failure of Primary Fuses on the Voltage Regulators Control Power Circuit.Fuses Replaced,A Generator Tested Then Returned to Svc | | | 05000312/LER-1978-017, Forwards LER 78-017/03L-0 | Forwards LER 78-017/03L-0 | | | 05000312/LER-1978-017-03, /03L-0:on 781215,during Refueling Shutdown, Blowdown Heat Transfer Pump Started & Sys Subjected to Sizable Water Hammer.Caused by Incomplete Valve Lineup. Hangers & Failed Snubber Repaired, & Personnel Notified | /03L-0:on 781215,during Refueling Shutdown, Blowdown Heat Transfer Pump Started & Sys Subjected to Sizable Water Hammer.Caused by Incomplete Valve Lineup. Hangers & Failed Snubber Repaired, & Personnel Notified | | | 05000312/LER-1978-018-03, /03L-0:on 781221,while Increasing Power After Second Refueling Outage,Rcs Flow Indicator a Unusually Steady & Spurious Alarms Received.Caused by Operator Error. Transmitter Returned to Svc & Operator Instructed | /03L-0:on 781221,while Increasing Power After Second Refueling Outage,Rcs Flow Indicator a Unusually Steady & Spurious Alarms Received.Caused by Operator Error. Transmitter Returned to Svc & Operator Instructed | | | 05000312/LER-1978-018, Forwards LER 78-018/03L-0 | Forwards LER 78-018/03L-0 | |
|