LER-1980-179, /03L-0:on 801023,review of Surveillance Instructions Revealed That SI-137.2,RCS Water Inventory, Performed Prior to Entering Mode 4 & Not Again Until 801015. Caused by Failure to Revise SI-137.2.Instruction Revised |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3271980179R03 - NRC Website |
|
text
O LICENSEE EVliNT REPORT c Nrnot atCCx: I l
1 1
I l
tet Ass enm7 on tyre Att.ntouinto mooneAriom i
l,o, t l l T l N I S l N IP l 1 !@l 01 O! -! O ! 0 l 0 l 010 l-l 0 l 0 l@l4 l1 l 1l Il 1l@[
l i
>> s^ r * @
Littr.sta Coca is is
'iCtNsa Nwsta es se
'iCtNst iv i ao cocr lolil
"" E't l L @l015 I Ol'0l 013! 2 l 7 @l 110 ! 2131810 @l11112 l1 ! 8! Ol@
(
2~
4 44 61 DocalfNuvatM
'4 62 EVENT DAfg 14 JS fitPGA f oat t 6) cvENT ot:CalPflCN ANo PAOS ABtt CONSECUENCES h [o i2i l Review of s2rve111ance fastructions on 10-23-80 revealed that SI-137.2, RCS Water l
piTT1 l Inventory, was performed or. 10-11-80 prior to entering rtede 4 and not performed I
l o i 41 I again until 10-15-80.
Surveillance requirement
- 4. 4.6.2.d requires that the RCS Water l
I o ! 3 I I Inventory be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the unit is in nodes 1-4.
There was no 10 is ] l effect upon public health or safety. Previous Occurrences - none.
f 10, 7 I I I
l0iaj l Sys t t *.e CAust CAust COUP vats t Coct CCof SLdCont CCo*CNE NT COCE SutCCOf SueCC0t I Z lZ l@ LDJ@ l Z [@ lZ lZ lZ lZ l Zl Zl@ l Z l@ my@
toiol 2
io i,
u 2
i, Stout N ?s AL CC0Vri m e nCE P8PonT at vap0N (e n/ p,0 EVENT YC A9 n tPOnT No.
iCOE Tv*t No
@ 4(egar l 810l
[__.l l1l7l9l l/l l0[3l lL l l_l l 0 l-
_ai n
u 24 2
2, 2.
2, ao a
u
- [ g e
'ftIg"rf o([c't jf agw t
SH TCf N A
t no4 P st C o.
C0veONFNf t
A y
lY
[ Z (I lT l 9 l I G l@l Zl@
IZ l@
l Z@
l0 1 0 1 0 1 of lY l@
l i
N sJ e4 Jn 36 38 40 46 42 42 44 47 CAUSE DESCnlPTION AND CCA AECTIVE ACTIONS
,, ; o ; [ SI-137.2 had not been revised to iacorporate the requirements of the latest revision g
i,;,; Iof the Sequoyah Technical Specifications. The instruction has been revised to incor-
,, ;,, ; porate the requirements of the latest revision of the technical specifications.
li t il I fl 11 +
3 L %
80 t E N.*
Q 6 *oM a otutn stATUh 1
4 DISCovtRY Ct!CRIPTtoN li i s i Laj@ l o I o I oJ@l NA l
l Z (@l Review of Surveillance Instructions j
%.mv Co'
80 AuoVNT of ACTIVlfY @ l toCAftoN or ntLE Ast @
att t Atto or otte Av li ic I LZ1 @ Ls@l NA l
NA l
.. n 20N. 'el s.,os ',',t s 8
otsCn,,,,cN @
Nu.,u n
,,,c l,l7i 101 Oi 0l@l ZI@l NA l
,mo~N it',N,Un',t s otsCn,. vion @
~ ~.c, L'_Lt] Lol ol oI@l NA i
7 6 7 9t 12 Loss na on cavar.t to FACsLifY 62 TYPt O t sClue rioN L,Ll.'L.] I Zl@[
eo NA l
,o oYSCais tion h -
NRC tJSE ONL e issue f2 I e I [N,,,fhl NA l
lllll[tiI!!tl
. 3 io
_, Name of Preparer W.T. Cottle/G.3. Kirk rhone 615-842-8261
,J"
.... _.. _.__8 012020 f=33
f q
^
g 1
)
~
iTcnn ssee Valley Authority
- Sequoyah ' Nuclear Plant LER SUPPLEMENTAL
- INFORMATION bQRO-50-327/80179Technical' Specification Involved 4.4.6.2.d Reported Under Technical-Specification 6.9.1.13.c1 Date of occurrence: '10-23-80 Identification and= Description of Occurrence:
'During a~ review of surveillance instructions on 10-23-80, it was. revealed that 51-137.2, RCS Water Inventory, was performed on 10-11-80 prior to entering nude 4 ~and not perforted again until 10-15-80. - Surveillance Requirement 4.4.6.2.d requires that the'RCS Water Inventory be-performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the unit is -in nodes 4.
Conditions' prior to Occurrence:
From 10-11-80 to 10-15-80, the plant:was taken from mode 5 to critical on
~
10-12-80, and experienced four (4) scrams and three (3) recoveries by 0959'CDT ;
on'10-13-80.. Subsequent to the. last scram cooldown' to node 5 was. initiated for condenser repairs. Plant was in mode 5 on 10-15-80.
Apparent Cause of Occurrence:
~
SI-137.2 had not been revised to incorporate the requirements of the latest.
Technical Specifications. revision.
Prior.to the l'ast revision, the Technical Specifications.had required the RCS Water Inventory every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when in
" steady state '~peration."- SI-137.2 still contained this old requirenent and o
since the unit never obtained steady state operation during the 10-11-80 to-10-15-80 time period,'the surveillance instructi,n was not performed.
Corrective Action
. SI-137.2 has been revised'to-delete all reference-to " steady state operation."
e v
A[
t s
b y
.-4 y
,i*
r-
- - U
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000327/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000327/LER-1980-001-01, /01T-0:on 800301-03,during Initial Fuel Loading, Licensee Failed to Estimate Flowrate from Svc Bldg Exhaust at 4-h Intervals.Caused by Misunderstanding of Tech Spec Requirements.Plant Instructions Revised | /01T-0:on 800301-03,during Initial Fuel Loading, Licensee Failed to Estimate Flowrate from Svc Bldg Exhaust at 4-h Intervals.Caused by Misunderstanding of Tech Spec Requirements.Plant Instructions Revised | | | 05000327/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000327/LER-1980-002-01, /01T-0:on 800306,contents of Task Decontamination Collector Tank Discharged Via Liquid Radwaste Effluent Line to Cooling Tower Blowdown W/O Flow Estimates Being Performed.Caused by Misunderstanding of Tech Specs | /01T-0:on 800306,contents of Task Decontamination Collector Tank Discharged Via Liquid Radwaste Effluent Line to Cooling Tower Blowdown W/O Flow Estimates Being Performed.Caused by Misunderstanding of Tech Specs | | | 05000327/LER-1980-003-01, /01T-0:on 800310,following Initial Fuel Loading, Flow Through Auxiliary Bldg Exhaust Sampler Not Maintained for 3.25-h.Caused by Misunderstanding of Tech Specs. Personnel Reinstructed in Applicable Requirements | /01T-0:on 800310,following Initial Fuel Loading, Flow Through Auxiliary Bldg Exhaust Sampler Not Maintained for 3.25-h.Caused by Misunderstanding of Tech Specs. Personnel Reinstructed in Applicable Requirements | | | 05000327/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000327/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000327/LER-1980-004-01, /01T-0:on 800311,following Initial Fuel Loading, Flow Estimates for Auxiliary Bldg Vent Monitor Not Performed for 10-h.Caused by Misunderstanding of Tech Specs.Personnel Reinstructed Re Applicable Requirements | /01T-0:on 800311,following Initial Fuel Loading, Flow Estimates for Auxiliary Bldg Vent Monitor Not Performed for 10-h.Caused by Misunderstanding of Tech Specs.Personnel Reinstructed Re Applicable Requirements | | | 05000327/LER-1980-005-03, /03L-0:on 800311,while Performing SI-247.605, Reactor Solid State Protection Sys Was Placed in Input Inhibit Mode,Removing High Voltage from Source Range Channel N31.Caused by Removal of Fuses from Voltage Cut Out Relay | /03L-0:on 800311,while Performing SI-247.605, Reactor Solid State Protection Sys Was Placed in Input Inhibit Mode,Removing High Voltage from Source Range Channel N31.Caused by Removal of Fuses from Voltage Cut Out Relay | | | 05000327/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000327/LER-1980-006-01, /01T-0:on 800314,w/essential Raw Cooling Water Radiation Monitors on Train a Inoperable,Personnel Determined That Limiting Condition of Operation Requires Sampling.Caused by Misinterpretation of Tech Specs | /01T-0:on 800314,w/essential Raw Cooling Water Radiation Monitors on Train a Inoperable,Personnel Determined That Limiting Condition of Operation Requires Sampling.Caused by Misinterpretation of Tech Specs | | | 05000327/LER-1980-006, Forwards LER 80-006/01T-0 | Forwards LER 80-006/01T-0 | | | 05000327/LER-1980-007-01, /01T-0:on 800315,following Initial Core Loading, Found Incorrect (Nonconservative) Valve Operator Weights Used in Seismic Analysis for Component Cooling Water Valves FCV-70-133,134 & 183.Caused by Incorrect Vendor Data | /01T-0:on 800315,following Initial Core Loading, Found Incorrect (Nonconservative) Valve Operator Weights Used in Seismic Analysis for Component Cooling Water Valves FCV-70-133,134 & 183.Caused by Incorrect Vendor Data | | | 05000327/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000327/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000327/LER-1980-008-03, /03L-0:on 800303,cooling Tower Blowdown Effluent Line Flow Monitor O-FR-27-175 Was Declared Inoperable.Flow Monitor Consistently Indicated Higher Flowrate than Actually Existed.Cause Unknown.Different Instrument to Be Instal | /03L-0:on 800303,cooling Tower Blowdown Effluent Line Flow Monitor O-FR-27-175 Was Declared Inoperable.Flow Monitor Consistently Indicated Higher Flowrate than Actually Existed.Cause Unknown.Different Instrument to Be Installed | | | 05000327/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000327/LER-1980-009-03, /03L-0:on 800303,liquid Radwaste Effluent Line Flow Monitor 0-FT-77-42 Consistently Indicated Higher Discharge Flow Rate than Actually Observed.Cause Not Stated.Flow Monitor Modified & Returned to Svc | /03L-0:on 800303,liquid Radwaste Effluent Line Flow Monitor 0-FT-77-42 Consistently Indicated Higher Discharge Flow Rate than Actually Observed.Cause Not Stated.Flow Monitor Modified & Returned to Svc | | | 05000327/LER-1980-010-03, /03L-0:on 800304,gaseous Vent Flow Rate Monitors for Units 1 & 2 Shield Bldgs & Auxiliary Bldg Were Declared Inoperable.Cause Not Stated.Gaseous Flow Rate Monitors to Be Redesigned | /03L-0:on 800304,gaseous Vent Flow Rate Monitors for Units 1 & 2 Shield Bldgs & Auxiliary Bldg Were Declared Inoperable.Cause Not Stated.Gaseous Flow Rate Monitors to Be Redesigned | | | 05000327/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000327/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000327/LER-1980-011-01, /01T-0:on 800314,support Pin Insp at Foreign Plant Revealed Stress Corrosion Cracking in Westinghouse Supplied Pins.Insp Supported Westinghouse Ltr Informing Utils of Potential Hazard.Pins Will Be Replaced | /01T-0:on 800314,support Pin Insp at Foreign Plant Revealed Stress Corrosion Cracking in Westinghouse Supplied Pins.Insp Supported Westinghouse Ltr Informing Utils of Potential Hazard.Pins Will Be Replaced | | | 05000327/LER-1980-012-03, /03L-0:on 800301,during Initial Core Loading,Rhr Flow Secured or Throttled Above Tech Specs.Caused by Intentional Increase to Allow Placement of Fuel Assemblies Near Loop 4 Hot Leg | /03L-0:on 800301,during Initial Core Loading,Rhr Flow Secured or Throttled Above Tech Specs.Caused by Intentional Increase to Allow Placement of Fuel Assemblies Near Loop 4 Hot Leg | | | 05000327/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000327/LER-1980-013-03, /03L-0:on 800302,failed to Analyze Samples from Unit 2 Shield Bldg Exhaust.Caused by Misunderstanding of Surveillance Requirements.Lab Personnel Instructed on Sampling & Analysis Requirements | /03L-0:on 800302,failed to Analyze Samples from Unit 2 Shield Bldg Exhaust.Caused by Misunderstanding of Surveillance Requirements.Lab Personnel Instructed on Sampling & Analysis Requirements | | | 05000327/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000327/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000327/LER-1980-014-03, /03L-0:on 800328,while Performing Check Source Test,Auxiliary Bldg Vent Noble Gas Monitor Had Module Power Problem & Failed in Svc.Caused by Zener Diode IN4740 & Transistor Fmps A13 Shorting Out | /03L-0:on 800328,while Performing Check Source Test,Auxiliary Bldg Vent Noble Gas Monitor Had Module Power Problem & Failed in Svc.Caused by Zener Diode IN4740 & Transistor Fmps A13 Shorting Out | | | 05000327/LER-1980-015-03, /03L-0:on 800305,while in Mode 6 W/Fuel Loading Complete,Pressure Was Only Being Monitored in One Steam Generator & Reactor Pressure Vessel.Caused by Misunderstanding of Surveillance Instruction | /03L-0:on 800305,while in Mode 6 W/Fuel Loading Complete,Pressure Was Only Being Monitored in One Steam Generator & Reactor Pressure Vessel.Caused by Misunderstanding of Surveillance Instruction | | | 05000327/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000327/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000327/LER-1980-016-03, /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary | /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary | | | 05000327/LER-1980-017-03, /03L-0:on 800310,while in Mode 6,turbine Bldg Sump Monitor O-RM-90-212 Alarm Kept Coming In.Monitor Was Declared Inoperable.Caused by Malfunctioning Flow Switch Not Allowing Sufficient Flow Through Monitor | /03L-0:on 800310,while in Mode 6,turbine Bldg Sump Monitor O-RM-90-212 Alarm Kept Coming In.Monitor Was Declared Inoperable.Caused by Malfunctioning Flow Switch Not Allowing Sufficient Flow Through Monitor | | | 05000327/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000327/LER-1980-018-01, /01T-0:on 800326,while in Mode 6 W/All Fuel Loaded,Exposed Cables Inside Containment Between Conduit & Penetrations Not Qualified to re-evaluated post-LOCA Max Dose Levels.Cables Shielded from Exposure to New Dose Level | /01T-0:on 800326,while in Mode 6 W/All Fuel Loaded,Exposed Cables Inside Containment Between Conduit & Penetrations Not Qualified to re-evaluated post-LOCA Max Dose Levels.Cables Shielded from Exposure to New Dose Level | | | 05000327/LER-1980-018, Forwards LER 80-018/01T-0 | Forwards LER 80-018/01T-0 | | | 05000327/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000327/LER-1980-019-01, /01T-0:on 800326,found Possibility of Not Maintaining Control Room Habitability Due to Leakage of Unfiltered Air.Possibly Caused by Isolation Dampers. Corrective Mods Planned | /01T-0:on 800326,found Possibility of Not Maintaining Control Room Habitability Due to Leakage of Unfiltered Air.Possibly Caused by Isolation Dampers. Corrective Mods Planned | | | 05000327/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000327/LER-1980-020-01, /01T-0:on 800404,investigation Revealed That Several vendor-designed Pipe Supports Were Designed Utilizing Manufacturer Std 0.25-inch U-bolt Which Overstressed During Seismic Event.Caused by Design Error | /01T-0:on 800404,investigation Revealed That Several vendor-designed Pipe Supports Were Designed Utilizing Manufacturer Std 0.25-inch U-bolt Which Overstressed During Seismic Event.Caused by Design Error | | | 05000327/LER-1980-021-03, /03L-0:on 800308,while in Mode 6,flow Rates from Auxiliary Bldg Ventilation Sys Flow Rate Monitor Were Not Recorded for Three Shifts.Caused by Misreading of Notation Used in Surveillance Instruction.Temporary Change Issued | /03L-0:on 800308,while in Mode 6,flow Rates from Auxiliary Bldg Ventilation Sys Flow Rate Monitor Were Not Recorded for Three Shifts.Caused by Misreading of Notation Used in Surveillance Instruction.Temporary Change Issued | | | 05000327/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000327/LER-1980-022-03, /03X-2:on 800318,sample Isolation Valves 1-FCV-90-108,109,110,114,115 & 116 Closed,Isolating Radiation Monitors.Caused by Isolation of Nonessential Control Air to Sample Valves.Valves Reopened | /03X-2:on 800318,sample Isolation Valves 1-FCV-90-108,109,110,114,115 & 116 Closed,Isolating Radiation Monitors.Caused by Isolation of Nonessential Control Air to Sample Valves.Valves Reopened | | | 05000327/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000327/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000327/LER-1980-023-03, /03L-0:on 800402,during Surveillance Testing, Diesel Generator 2A-A Feedbreaker Failed to Close.Caused by Power Contacts Being Dirty.Power Contacts Cleaned | /03L-0:on 800402,during Surveillance Testing, Diesel Generator 2A-A Feedbreaker Failed to Close.Caused by Power Contacts Being Dirty.Power Contacts Cleaned | | | 05000327/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000327/LER-1980-024-03, /03L-0:on 800331,flow Switches on Radiation Monitors ORM-90-212 & 122 Found Inoperable.Caused by Small Particulate Matter in Monitored Liquid.Design Change Request Initiated.Weekly Preventive Maint Program Established | /03L-0:on 800331,flow Switches on Radiation Monitors ORM-90-212 & 122 Found Inoperable.Caused by Small Particulate Matter in Monitored Liquid.Design Change Request Initiated.Weekly Preventive Maint Program Established | | | 05000327/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000327/LER-1980-025-03, /03L-0:on 800313 W/Unit 1 in Mode 6,O-RM-90-225 Condensate Demineralizer Effluent Line Was Taken Out of Svc for Maint.Caused by Weak Transistor.Transistor Replaced & Monitor Returned to Svc | /03L-0:on 800313 W/Unit 1 in Mode 6,O-RM-90-225 Condensate Demineralizer Effluent Line Was Taken Out of Svc for Maint.Caused by Weak Transistor.Transistor Replaced & Monitor Returned to Svc | |
|