Similar Documents at Surry |
|---|
|
LER-1978-038, /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2801978038R03 - NRC Website |
|
text
[/ Ti) corn i"WL GLOCK:
e LICEr*.1::;Ef= EVct'H :*:.:POi'lT LL_l_l_L_L_l Q I
f, e
(Pt.i;/,.S!:' p;rn,n 0:1 TYPE ALL REG'JiHi:D li*ff0!1Mi\\TIOi'J)
CON'T
[~~-1.jJ 7
8
~;.~~!~~ L~(D l.-~~L~_g_l _ 0 _L~_?._LJ~ _l__gJQ l __ J,LJ.L.. Ql~::J_7j__ _
_r.~(0 l-:-GL2J.sJ__ -_2.1 ___ -i ! c;j G)
(.J Gl DOCl,E:T r*JU1\\1:1ER Gf1 G£1 F.V[r~T D/*TC 7.,
/'.)
Rt:POH I UA I~
t,O E\\'EJ*;", U:cSCRIPTIOf*J,\\ND PROBt,,;L(, CONSEOLIEf,J.":U;@
r 7.c>--J_-_,_-,**
0 1'*
1_1*._r.. :*. -~** __ ~_n.L. '"-.:__~_::* *. ~**'
L~ 0 T,, -.. ].*_.. 111*. C,~.-._). s
. C
I
~
\\.'\\
~*pe_c.1.t1*:*t;.t1ons +.. ~fi. and J.~3 rer~ortcd i18 _I:.?!" 'fr;c.hn!..c:=,l __,Sr,;::_t_:
,. ___ J [n IIJ L f::i_ c_.~ '.: i c_*n_. ~-; _6_._6 ;_3..:!?._* 3_
J [9__[(] L_ __ _ -------------------
[oJJJ L_ ----
fol8J L
---******_J 80 SYS-Tt:i.l CODE
10 Ct,USE CODE L!U@
11 COMPOi*iENT CO~*E L!.Lli.1... xLtlJ~.I.JLl 8 13 18 SEQUENTIAL OCCUR fi ENCE LE R 'f!O fEVEiJT YE/I.Fl REP(JflT NO.
CODE
@ n,r*orn I [7 1 8J I __ J l or 3_L_81 I/I I g_~{
NUME\\lfl L:...:__i(l --7-.2 l==.
~
'..J
~
0 23 24 26 27 28 29 cm.1P.
SUBCOD::
L~J@
I" f1EF 0:'1T TYPE L_x J 30 1//\\LVE SU8CO'JE L~J@
20 31
- ,CTiC*i/
FUTlif-:1=
EFF[CT SHUTDOWN Q
ATI/1.Cf!MENT NPRD-4 TI-.KC'*:
ACTl(.l~
0'*;,,,. ;\\NT METHOD HOUPS \\:.'.:J SUBMITTED FOP.\\*: $UG.
rrw,n, crn.1P.
SUPPLIEf°'
REVISION NO.
!__LJ 32 COMPOiJ[~.:T MAilUFACTLl*1~Fl
!._~J@~J@
l2~ __ J@ ~ L~J~_L 1.l.U ~
(§.)
L!.~_I@
3 3 3.;
35 36 31 40
.\\ 1 42
~I L~~l-2l.EJ@
CAUSE DESCRIPTION,C.,f\\!D CORRECTIVE /,CTIONS @
43 44 47
!This event resulted fror:i a sche<ll!l i_~2g__ error..
l-'(1LlC8.l
""C' l"('(l1T;,.. '
1 J
'~~.
l..t cL,-:J
- 1..1 *.! i.. \\..:-;:.. :
[17
_1... __ J !by Tec+nical Sp<?!cificat:ion 3.18.U and the calibration cornplcl:P.d irt ~ccm.*dc:nc,". w:i_t> ___ ~
1., **. : "tina nroc<>dt>r ~"
r:-*r--;.;1 L~...L.:*....J L.'.:::::.:~:
G
- . t.:,,. *---- --------------~-----
[IT:TJ I ________ ------*----- __
"T::i"'"l I L..1............ ~
8 9
F/\\CILl*:*y ST/,TU,;
% PQ\\'JC:R OTHER ST/,TUS r~r;:-.. 1 l "' J 9 L lj O I OJl(?,1 NA L'.....::...
-"-'*- \\.::::J
-* __ :::..L __ u...
1 _______ _ 0
.J 8
'.l 10 12 13 44 ACT!\\'IT\\'
CONTENT Q\\
H!:LEAS:.:D or-RELEASE AMOUNT OF ACTIVITY ~
[\\~l;J J..~.J @ l_!:J@l_.
NA r
__.=__j 7
t;
!)
10 11 4-1 r:.::*,
- ,.*.::.~*!:
r* (';'ti~~
Di.::.":.Ci";J\\"J i'1UtJ \\:~_!)
_ _____ J 80 METHOD OF r:;:;-,
DISCOVERY DISCOVERY DESCi11PTION \\[!_;
LcJ@~I __
E_n-g_i_n_e_e_-._r_s_o_b s er._,_.r c._'l_t_i_c_,n ______. _______ _J 45 46 80 L
NA LOCATION OF RELEASE@
*--**._. ____ _J 45 80 [J?J 1.~1.. _!_ *~-l~J0~_J@._I _I_*lA_-__
_ --------*. ***--~*---------***-----*----------
_______ J 7
fl 9
11 12 13 l'E*,SmJNEL INJURi"S NL;;.;,;E!l DESCHIPT!Dr*l 41
. [1 DJ l_Q_j__~j-2._j@J
_NA_._* ------
80
'--- _____ j s :,
11 12 LOSS Or OR DAr,'..AG!: TO FACILITY l'.::j\\
TYPE DESCRIPTIO:<
'\\::;)
~GJ l~K0l NA 80 8
9 10 PUBLICITY
(;;:\\
ISSU"l' DESCfllPTION ~
80 NFlC USF. ONLY EE !.!~]@!___
NA 790206 o 3 d-9 U.-.W_L.LL LJ._J_CJ ~
8 9
10 NAf\\'iE OF PREPAFlER T. L. Baucom_*_, _____ _
PHQl,JE:.
68 69 SOL~-35 7-318L}
0 C.
0
,--~--.
e Surry 1'01-,er Stat ion, Unit l Docket. No:
50-280 Iteport lfo:
Event Dnte:
7G-OJ3/03X--l 11...:03-?3 Title of Report:
Inc or*e /E:~:c ore Inst ru1ne nt Ca. l ibr at _i_i Jn
- 1.
Descriptjon cf Event:
Upon review of opcr.1t:ional data, it was cktecmiilcd the.t the quo.-::-terl.y cali.b:r.a!:ion of thl*! nucle~r po\\.*!er range instru1n(!ntation Ly H!?.i'.1.a:5 o.f the movable incore de!:,- *tor system h.:id not b2cn perfor1c:2d as schccblcd.
This is contrary t:-_: Technical Specific.:,tions 1:.* 1.A_ and is reportable as per Technical Specific.::itions 6.6.7...b.3.
- 2.
Probable Cor1sequer*i:.es ur,d.. _._Status _of R2cluecl;:.11t_ Systc~ms:
The nuclear Pm1e.: Range instrumentation is c-1libr.2ted on a cl--1ily basis <1ga:i.nst a heat bQl<ince* standard.
The upp~r and.lo\\.Ycr ion chrnnbE~r current~ are recalibrated quarterly to assur2 valid function of those protective fe~tures using F ( 6. I) as an input value.
This calibration is checked on a monthly basis and ~-7,2,, within 1% on the map taken 10-17--73.
Therefore, the h,:;llth and safety of the~ general public were not affectcJ.
- 3.
Cause
This event was caused by failure to adequately schedule the PT that tracks the core exposure.
- 4.
Imc:1,~diate Corrective Action:
As required by Technical Specifications 3.18.B, the unit's pc~*.'e1*
was reduced and limited to 90% power.
The data required for the excore detector recalibration was taken.
Initial annlysis of the data indicated that the existing Incore/
E:*:core detector calibration was within l'.t, which is well within the required Rpecifications.
The unit was returned to full pow~r.
Detailed anal.ysis of the maps provided the data for comrletion of the recalibrn-tion procedures.
- 6.
Actions Taken to Prevent Recurrence:
Personnel have been reinstructcd and schedule modified to provide for closer tracking ~of core exposure on a weekly rather than rnonthly basis.
- 7.
Generic Implication~}
None.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000280/LER-1978-001, Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir | Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir | | | 05000280/LER-1978-002, Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance | Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance | | | 05000280/LER-1978-003, Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 | Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 | | | 05000280/LER-1978-004-03, /03X-1 on 780305:loss of Svc Water Flow Through Charging Pump Intermediate Seal Cooler Was Caused by Corrosion of Stem of Discharge Gate Valve;Corrosion Was Galvanic(Brass Touching Bronze);Problem Will Be Studied | /03X-1 on 780305:loss of Svc Water Flow Through Charging Pump Intermediate Seal Cooler Was Caused by Corrosion of Stem of Discharge Gate Valve;Corrosion Was Galvanic(Brass Touching Bronze);Problem Will Be Studied | | | 05000280/LER-1978-004, Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler | Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler | | | 05000280/LER-1978-005, Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouses Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature | Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouses Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature | | | 05000280/LER-1978-006, Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping | Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping | | | 05000280/LER-1978-007, Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 | Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 | | | 05000280/LER-1978-008, Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 | Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 | | | 05000281/LER-1978-011-03, /03X-1 on 780305:During Normal Full Pwr Oper,There Was No Svc Water Flow Thru Charging Pump Intermediate Seal Cooler 2-SW-E-1B,due to Failure of the Coolers Discharge Gate Valve | /03X-1 on 780305:During Normal Full Pwr Oper,There Was No Svc Water Flow Thru Charging Pump Intermediate Seal Cooler 2-SW-E-1B,due to Failure of the Coolers Discharge Gate Valve | | | 05000281/LER-1978-011, Forwards LER 78-011/03X-1 | Forwards LER 78-011/03X-1 | | | 05000280/LER-1978-012, Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand | Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand | | | 05000280/LER-1978-013, Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded | Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded | | | 05000280/LER-1978-015, Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces | Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces | | | 05000280/LER-1978-016, Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening | Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening | | | 05000280/LER-1978-017, Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid | Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid | | | 05000280/LER-1978-018, Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required | Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required | | | 05000280/LER-1978-022-03, /03X-1 on 780726:Hydro Test Pump Failed to Build Up Pressure During Attempt to Fill Safety Injection Accumulators Due to Lifting of Its Relief Valve.Valve Replaced & Checked.Accumulator Refilled | /03X-1 on 780726:Hydro Test Pump Failed to Build Up Pressure During Attempt to Fill Safety Injection Accumulators Due to Lifting of Its Relief Valve.Valve Replaced & Checked.Accumulator Refilled | | | 05000280/LER-1978-022, Forwards LER 78-022/03X-1 | Forwards LER 78-022/03X-1 | | | 05000280/LER-1978-024, Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste | Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste | | | 05000280/LER-1978-027, Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria | Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria | | | 05000280/LER-1978-028-03, /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled | /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled | | | 05000280/LER-1978-028, Forwards LER 78-028/03L-0 | Forwards LER 78-028/03L-0 | | | 05000280/LER-1978-029-03, X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank | X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank | | | 05000280/LER-1978-029, Forwards LER 78-029/03L-0 | Forwards LER 78-029/03L-0 | | | 05000280/LER-1978-030, Forwards LER 78-030/03L-0, 78-031/03L-0, 78-032/03L-0, 78-033/03L-0 | Forwards LER 78-030/03L-0, 78-031/03L-0, 78-032/03L-0, 78-033/03L-0 | | | 05000280/LER-1978-030-03, /03L-0 on 781009:w/unit at Rated Pwr,Charging Pump Component Cooling Water Pump Btripped.Pump Tripped on Overcurrent.Caused by Corrosion Damage to Motor Bearings. Pump & Motor Rebuilt & Reinstalled | /03L-0 on 781009:w/unit at Rated Pwr,Charging Pump Component Cooling Water Pump Btripped.Pump Tripped on Overcurrent.Caused by Corrosion Damage to Motor Bearings. Pump & Motor Rebuilt & Reinstalled | | | 05000280/LER-1978-031-03, /03X-1 on 781001:during Normal Operation,Channel I Pressurizer Level (Protection) L-I-459 Drifted High.Caused by Drift of Electronic Zero Adjustment,In Conjunction W/ Leakage Thru Transmitter Bypass/Equalizing Valve | /03X-1 on 781001:during Normal Operation,Channel I Pressurizer Level (Protection) L-I-459 Drifted High.Caused by Drift of Electronic Zero Adjustment,In Conjunction W/ Leakage Thru Transmitter Bypass/Equalizing Valve | | | 05000280/LER-1978-031, Forwards LER 78-031/03X-1 & 78-038/03X-1 | Forwards LER 78-031/03X-1 & 78-038/03X-1 | | | 05000281/LER-1978-032, Forwards LER 78-032/03L-0 | Forwards LER 78-032/03L-0 | | | 05000280/LER-1978-032-03, /03L-0 on 781011:heat Tracing Circuit Faults Had Occurred as a Result of Boric Acid Incursion.Faults Repaired & Circuit Current Verified | /03L-0 on 781011:heat Tracing Circuit Faults Had Occurred as a Result of Boric Acid Incursion.Faults Repaired & Circuit Current Verified | | | 05000281/LER-1978-032-03, /03L-0:on 780921,heat Tracing Circuit Manual Boration/Boric acid-to-blender Failed.Caused by Boric Acid Penetration of Heat Tracing Tape Circuits.Heat Tracing Tape Replaced | /03L-0:on 780921,heat Tracing Circuit Manual Boration/Boric acid-to-blender Failed.Caused by Boric Acid Penetration of Heat Tracing Tape Circuits.Heat Tracing Tape Replaced | | | 05000281/LER-1978-033, Forwards LER 78-033/03L-0 | Forwards LER 78-033/03L-0 | | | 05000281/LER-1978-033-03, /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | | | 05000280/LER-1978-033-03, /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | | | 05000281/LER-1978-034-03, /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | | | 05000280/LER-1978-034-01, /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | | | 05000280/LER-1978-034, Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | | | 05000280/LER-1978-035, Forwards LER 78-035/01T-0 | Forwards LER 78-035/01T-0 | | | 05000281/LER-1978-035-03, /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | | | 05000280/LER-1978-035-01, /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | | | 05000280/LER-1978-036, Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | | | 05000280/LER-1978-036-03, /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | | | 05000281/LER-1978-036-03, /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | | | 05000281/LER-1978-036, Forwards LER 78-036/03L-0 | Forwards LER 78-036/03L-0 | | | 05000281/LER-1978-037, Forwards LER 78-037/03L-0 | Forwards LER 78-037/03L-0 | | | 05000280/LER-1978-037-03, /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | | | 05000281/LER-1978-037-03, /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | | | 05000281/LER-1978-038-03, /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | | | 05000280/LER-1978-038-03, /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | |
|