Letter Sequence Other |
---|
|
|
MONTHYEAR05000298/LER-1982-014, Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced1983-02-0303 February 1983 Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced Project stage: Other A830019, Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code1983-08-23023 August 1983 Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code Project stage: Other ML20080D8231983-08-25025 August 1983 Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage During Cycle 9 Operation Project stage: Other ML20080D8071983-08-25025 August 1983 Forwards Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage, During Cycle 9 Operation,Per 830824 Request Project stage: Other 1983-08-23
[Table View] |
|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20211G6101997-09-29029 September 1997 LER 97-S01-00:on 970829,discovered That Shotgun Shell Was Missing from Ammunition Carrier.Caused by Improper Issuance & Control of Weapons & Ammunition.Missing Shell Immediately Replaced 05000298/LER-1993-0301993-08-0909 August 1993 LER 93-030-00:on 930708,discovered Inadequate Inservice Testing of Svc Water Sys Check Valves Due to Flow Instrument Calibr Error & Personnel Error in Specifying Sys Flow Requirement.Revised Calibr Factor developed.W/930809 Ltr 05000298/LER-1993-0291993-08-0606 August 1993 LER 93-029-00:on 930708,partially Withdrawn Control Rod 26-31 Scrammed.Caused by RPS Scram Signal from Two of Four Reactor Pressure Scram Switches.Scram Reset & Pressure Testing completed.W/930806 Ltr 05000298/LER-1993-0081993-04-22022 April 1993 LER 93-008-00:on 930328,4,160-volt Breakers 1BG,1GB & 1GE Tripped Due to Actuation of 1GS Breaker Lockout Relay.Caused by Oversight in Design Change Installation Instructions. Work Stopped & Design Change Implemented 05000298/LER-1993-0071993-04-22022 April 1993 LER 93-007-00:on 930326,determined That ECCS Pump Compartment Cooler Power Supply Design Defect Could Have Prevented Adequate Containment Heat Removal.Caused by Design Errors.Mods Planned to Provide Convection Cooling 05000298/LER-1993-0011993-03-18018 March 1993 LER 93-001-00:on 930225,several Design Discrepancies in SW & Reactor Equipment Cooling Sys Identified.Caused by Piping Configuration Error During Plant Const.Mechanical & Electrical Mods Will Be made.W/930318 Ltr 05000298/LER-1982-014, Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced1983-02-0303 February 1983 Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced 05000298/LER-1982-005, Amended LER 82-005/03X-1:on 820221,surveillance Test Indicated MSIV 86A Had Closing Time Faster than Allowed by Tech Specs.Caused by Loss of Nitrogen Preload & Fluid from Hydraulic Sys Accumulator.Accumulator Recharged & Tested1982-10-20020 October 1982 Amended LER 82-005/03X-1:on 820221,surveillance Test Indicated MSIV 86A Had Closing Time Faster than Allowed by Tech Specs.Caused by Loss of Nitrogen Preload & Fluid from Hydraulic Sys Accumulator.Accumulator Recharged & Tested ML20204D4181978-12-0808 December 1978 /01T-0 on 781124:while Checking RR MG Set 1B Speed control,1 Amp fuse(F2) in Drive Amplifier Circuit Was Pulled Out & Checked.Caused Rapid Increase in Pwr Level,Tripping RR MG Set 1B ML20148A7231978-12-0707 December 1978 /03L-0 on 781111:during S.P.6.4.1.2. (Withdrawn Control Rod Operability), Control Rod 30-31 Was Found Uncoupled from Its Control Rod Drive. Cause Cannot Be Determined Until Control Rod Drive Is Removed & Examined ML20150D3371978-11-13013 November 1978 /03L-0 on 781016:cable HP58,Div 1,was Found Routed Thru Div 11 Riser Under Panel 9-3.Caused by Personnel Error During Constr.Redundant Sys Were Operable ML20150D3191978-10-13013 October 1978 /03L-0 on 780918:during Normal Oper,After Cooling Down the Torus,Rhr Heat Exchanger 1B Bypass RHR-MO-66B Failed to Oper,Due to Loose Set Screw on Yoke of Limiterque SMB-3 Operator ML20150D3561978-09-28028 September 1978 /03L-0 on 780912:Cooper-Bessemer Diesel Engine Type KSV-16-T Main Bearing Overheated.Main Bearing 10 Was Damaged Due to Minimal Oil Flow During Engine Coastdown. Caused by Foreign Particles in Oil 1997-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML20210R0381999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Cooper Nuclear Station ML20210J2921999-07-29029 July 1999 Special Rept:On 990406,OG TS & Associated Charcoal Absorbers Were Removed from Svc.Caused by Scheduled Maint on Hpci. Evaluation of Offsite Effluent Release Dose Effects Was Performed to Ensure Plant Remained in Compliance ML20209H8281999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209E1061999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Cns.With ML20196B3851999-06-17017 June 1999 Summary Rept of Facility Changes,Test & Experiments,Per 10CFR50.59 for Period 970901-990331.Summary of Commitment Changes Made During Same Time Period Also Encl ML20195K2851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Cooper Nuclear Station.With ML20206P0481999-05-12012 May 1999 Safety Evaluation Concluding That NPP Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at CNS & Adequately Addressed Actions Requested in GL 96-05 ML20206J0811999-05-0404 May 1999 Rev 14 to CNS QA Program for Operation ML20206P9751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station ML20205Q0891999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Cooper Nuclear Station.With ML20204G8951999-03-15015 March 1999 CNS Inservice Insp Summary Rept Fall 1998 Refueling Outage (RFO-18) ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204B3701999-03-11011 March 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Requests for Relief for RI-17,Rev 1 and RI-25,Rev 0.Request for Relief RI-13,Rev 2 Involving Snubber Testing & Is Being Evaluated in Separate Report ML20204C9751999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station ML20199E6751999-01-14014 January 1999 Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station ML20195B9191998-12-31031 December 1998 1998 NPPD Annual Rept. with ML20196J9641998-12-0707 December 1998 Safety Evaluation Accepting Licensee Third 10-yr Interval Inservice Insp Plan Request for Relief RI-27,rev 1 ML20198D2471998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Cooper Nuclear Station.With ML20196A2861998-11-23023 November 1998 SER Re Core Spray Piping Weld for Cooper Nuclear Station. Staff Concluded That Operation During Cycle 19 Acceptable with Indication re-examined During RFO 18 ML20196A5241998-11-23023 November 1998 Safety Evaluation Accepting Proposed Alternative to Use UT Techniques Qualified to Objectives of App Viil as Implemented by PDI Program in Performing RPV Shell Weld & Shell to Flange Weld Examinations ML20196A5061998-11-23023 November 1998 Safety Evaluation Re Flaw Indication Found in Main Steam Nozzle to Shell Weld NVE-BD-N3A at Cns.Plant Can Be Safely Operated for at Least One Fuel Cycle with Indication in as-is Condition ML20196C4241998-11-20020 November 1998 Rev 1 to Cooper Nuclear Station COLR Cycle 19 ML20195H1761998-11-17017 November 1998 SER Authorizing Proposed Alternative in Relief Requests RV-06,RV-07,RV-09,RV-11,RV-12 & RV-15 Pursuant to 10CFR50.55a(a)(3)(ii).RV-08 Granted Pursuant to 10CFR50.55a(f)(6)(i) & RV-13 Acceptable Under OM-10 ML20195F8601998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Cooper Nuclear Station.With ML20155D9961998-10-31031 October 1998 Rev 0 to GE-NE-B13-01980-24, Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station ML20154Q5661998-10-0505 October 1998 Rev 0 to CNS COLR Cycle 19 ML20154L5381998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Cooper Nuclear Station.With ML20151Z6141998-09-16016 September 1998 SER Accepting Util Responses to NRC Bulletin 95-002 for Cooper Nuclear Station ML20154F7931998-08-31031 August 1998 Rev 0 to J11-03354-10, Supplemental Reload Licensing Rept for CNS Reload 18,Cycle 19 ML20153B1101998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Cooper Nuclear Station ML20237E7771998-08-20020 August 1998 Revised COLR Cycle 18 for Cooper Nuclear Station ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C0591998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Cooper Nuclear Station ML20236R9131998-07-20020 July 1998 SER Accepting Rev 13 to Quality Assurance Program for Operation Policy Document for Plant ML20236P2971998-07-0707 July 1998 Rev 2 to NPPD CNS Strategy for Achieving Engineering Excellence ML20236R0931998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Cooper Nuclear Station ML20249A7701998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Cooper Nuclear Station ML20247G6131998-05-13013 May 1998 Part 21 Rept Re Defect Contained in Automatic Switch Co, Solenoid Valves,Purchased Under Purchase Order (Po) 970161. Caused by Presence of Brass Strands.Replaced Defective Valves ML20247G0951998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Cooper Nuclear Station ML20237B6861998-04-24024 April 1998 Vols I & II to CNS 1998 Biennial Emergency Exercise Scenario, Scheduled for 980609 ML20217A1531998-04-16016 April 1998 Closure to Interim Part 21 Rept Submitted to NRC on 970929. New Date Established for Completion of Level I & 2 Setpoint Project Committed to in .Final Approval of Setpoint Calculations Will Be Completed by 980531 ML20216G5331998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Cooper Nuclear Station 1999-09-30
[Table view] |
LER-2082-014, Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced |
Event date: |
|
---|
Report date: |
|
---|
2982082014R00 - NRC Website |
|
text
. .-
J CRC FCRM 366 U.S. NUCLEA3 CEGULATORY COMMISSION u* ns ..
l ,
LICENSEE EVENT REPORT CONTROL 8 LOCK; l I
l l l l l lh 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 0 t
$8l@
l 7 8 l9 N l LsCENSEE E l CCODE l P l Rl 1 l@150 l 0 LICENSE le l- l 0NUMBER l 0 l 0 l 0 l 0 l-25 l 026 _l 0 LICENSEl@ 4TYPE l1 l1Jo l167l1CATl@l CON'T '
O i 7.. 8 3c[3RCE 60 l LEl@l 0l 5DOCK l 0ETl NUMBER 0 l 0 l 2 l 9 68l 8 @l 69 0 EVENT l 6 l DATE 0 l 7 l 8 l742 l@l0 7S l2 l0 l 3 l 8 l 380 l@
REPORT DATE EVENT DESCRIPTION AND PROO ABLE CONSEQUENCES h 10121 l During the replacement of RWCU-MO-15 (6"-900 lb. aate valve). reiectable indications 1 0 3 l were found in the heat affected zones of welds BJ-13, BJ-15, BJ-20, and BJ-23. (Ref- l 1014 l l erence CNS ISI Drawina #3) The reactor was in the refueling mode of operation when the1 0 5 i event occurred. This event is not repetitive. There were no adverse effects on the 1 0 6 l"public health and safety. 1 O i i I O 8 l l DE CODE SU8C E COMPONENT CODE SUB ode SU E O 9 e
I Cl cl@ LBJ@ lC l@ IP lI lP lE lX lX l@ W@ W @
9 to 13 82 13 18 19 20 SEOUE N TI AL OCCURRENCE REPORT REVISION
_ EVENT vEAR . REPORT NO. CODE TYPE NO.
g
@ ,"LE R/RO l218 22l2 l (- _J 23
-l0 l1 l4 l 24 26 d
27 l013l 28
[X_j 30
(---l (1_j
,_ 29 38 32 KEN AC P NT M T D HOUR 3 $ 8 GT D FOR B. SU L R MANUFACTURER
[C_J 33
@[X_j@
34
'3bW @ [_Zj@
J6 l 0l 0l 0l 0l 37 40 J@
el l
42 l@ y@ 43 lP 44 l2 l4 l2 '47l@
CAUSE DESCRIPTION AND CORRECTIVF ACTIONS 27 i O BJ-13 & BJ-15 weld failures ware attributed to improper fabrication techniques during l i i l plant construction. Failure mode analysis on welds BJ-20 & BJ-23 by Rockwell Internat- I i i lional Science Center, for EPRI has indicated weld joint failure due to Intergranular I
[il3l l Stress Corrosion Cracking caused by weld joint sensitization. A detailed report is l i 4 'lavailable fr'om EPRI. The scope of the ensuing AISI exam will be increased. l e o a0 5A S % POWER oTHER STATUS OtS O RY DISCOVERv DESCRIPTION i 5 (H_j @ l 0 l 0 l 0 l @ l NA l [B_j@l Liquid Penecrant Exam l ACTIVITY CO TENT RELEAsEo onaELEAsE LOCATION OF RELE ASE i 6
[Z_] @ (' Zj@l AMOUNT NA OF "
ACTivlTv l
@l NA l
PERSONNEL ExPOsMEs
~uM.ER. Tv,E DEsCRI, Tion @
i i NA 10 10 - l'0 l@lz_J@l l
' '
- PE R SON ~E < ,N,U,',Es ' " "
~ UM.E . DE sCR,,Tio~ @
r!!i.ln Nl9l0 l0 l0 l@l 1 51 12 NA l 30 t US$ OF Olt DauaGE 70 Facitary
(, hD fvPE DE scitaP TION i 9 W@l '"
NA 8307260357 830203
,Ir
'l 80 l
PDR ADOCK 0500029g NRc USE ONt Y .,
l 2 I o 1 [N
.. . n[,@niEn,Pi l NA o~ @ S PDR l , ; ;; ; ;[;;;;;j=
.s 3 to 68 69 90* 1 Scott S. Freborg W-24H
. N A*.tE OF PRE PAR E R pagyg {
-~~_
h
e e
lr.
~
5g - -
- s. - ' Y Q g[ -
W f
2
- 0 w a .~
N.,f / 5 3
if
,s
@a L ~.
4C h 25 *-5 aC
'US TO EC B M I- 24 "
h
_ t CD w * ..
- 2 . w E ? Y e
~
,a e
~ BJ 2S " *
~ BJ 22 p R WCU.W-IS
- eJ.2 g i
-es.w -
~
BJ lJ
(
7 e Lub E 3 *
4
$41 18 EU 15 -
b bJ l5 g '
BJ 12 -~ RW:U IO , g i. ele
. o BJ.1, .
g yt.r.....I I
Iteas Seh
! bele f
. - BJ.lO .
t keeser teretten ene weet
' (Bd Cateiers )
BJ-$s q 3 5etssic Iestratet 4 .% .
/ ene wer Y.* -
BJ 6 ----~I'"'"'"
leu cetesers) -
I '
gj.7 All wits preftsee by Ch4..
~ s BJ.$ .
r d
J4 BJ 2~ 1 BJi
& RHR SUPPLY (5tt DwG iC l?)
g 4 e
e I . .
O
(
"
Nebraska Public Power District 3
.i CNSS830073
( ; ~ ~ J' < ?
J ~
Mr. John T. Collins, Regional Administrator b U.S. Nuclear Regulatory Commission I-- '
Region IV
'j- m
]
611 Ryan Plaza Drive _j ,
y Suite 1000 2 Arlington, Texas 76011
Dear Sir:
^!
This amended report is submitted in accordance with Section 6.7.2.B.4 of the j Technical Specifications for Cooper Nuclear Station and discusses a reportable -
occurrence that was discovered on June 7, 1982. An amended licensee event ;
report form is also enclosed.
4 E
Report No.: 50-298-82-14-01 i Report Date: February 3, 1983 -
Occurrence Date: June 7, 1982 Facility: Cooper Nuclear Station .
Brownville, Nebraska 68321 2 A
m Identification of Occurrence: i A condition was discovered which indicated an abnormal degradation of the y Class IN Reactor Water Clean-up (RWCU) System pressure boundary inside ;
primary containment. =
Conditions Prior to Occurrence: -
The reactor was in the refueling mode of operation.
Pj Description of Occurrence: -
During the scheduled replacement of RWCU-M0-15, a six inch 900 pound 3 austenitic stainless steel Anchor Darling gate valve, rejectable indica- ]
tions were detected in the heat affected zones (HAZ) of welds BJ-20 and 23 (reference CNS ISI Drawing #3). The indications were detected by $
liquid penetrant examination on the inside diameter of welds BJ-20 and 23 s near the valve. Subsequent examination of the balance of six inch welds
- on the RWCU line also produced rejectable indications in welds BJ-13 and N
- 15. The rejectable indications in welds bJ-13 and 15 were detected by 3 ultrasonic (UT) examination. 3 1
Designation of Apparent Cause of Occurrence: i The cause of the indications in BJ-13 and 15 were attributed to improper j fabrication techniques and are not considered service induced. The "
rejectable transverse indication in weld BJ-13 was present on the
}
,/7 : 4
/ =
\ f(/ ,
m
' .h ;. , {
LC . - g *: ,
~
2 Mr.; John T.' Collins
' February 3, 1983 ~ .
- Page 2 ~ '
original construction radiograph while weld BJ-15 was rejectable due to n . lack of fusion in the weld joint.
The. failure mode in welds BJ-20 and 23 has been' identified as.
Intergranular Stress Corrosion Cracking (IGSCC), due to weld joint sensitization. Failure analysis.was performed by Rockwell International under the direction of.the Electric Power Research Institute (EPRI). A detailed report is available from EPRI.
' Analysis of Occurrence:
The RWCU. System provides a method of purifying the primary coolant water
~
by continuously removing a portion of the Reactor Re' circulation (RR)
System' flow from RR "A" loop via a 20" Residual Heat Removal (RHR) System suction line. RWCU piping and fittings are 6" schedule 80, Type 304' austenitic stainless steel.
BJ-20 had several circumferential indications in its HAZ. Two transverse indications were present in the HAZ of BJ-23. At the time of occurrence, there'was speculation that the indications were IGSCC. This has been.
verified through failure mode analysis conducted by the Rockwell Interna-tional Science. Center for EPRI. This analysis has determined the cause
~
of IGSCC to be weld joint sensitization, therefore it is concluded that failure was not service induced. .These two weld failures are the first
. cases of IGSCC in this. plant.
One hundred percent of accessible six inch welds from the upstream weld on the outboard isolation valve (RWCU-H0-18) to the attachment weld'on the 20" RHR suction line were examined by UT. The UT procedure used was
-the same procedure that is used to detect IGSCC. Examiners qualified to this procedure had previous training on cracked pipe specimens exhibiting IGSCC. Due to their microstructure, austenitic stainless steels have a
" leak before break" characteristic.' Therefore, had the indications degraded to a " leak before break" condition, drywell leak detection systems would have detected such leakage. ;
The reactor was in the refueling mode of operation when this event was discovered. .This occurrence presented no adverse consequences concerning
.public health and safety.
- Corrective Action:
The piping and fittings affected by the rejectable welds were replaced.
The pipe was replaced by material identical to that used in construction.
Fittings used were Type 304L, low carbon nuclear grade. fittings rather than the' Type 304 fittings e ad in plant construction. Measures were taken to control-heat input to the replacement welds, to avoid sensi-tization of the weld joints.
Mr. John T. Collins
. _ February 3, 1983 Page 3 1
i The scope of Augmented ISI:for the 1983 refueling outage is being in-creased in view of cracking being experienced in primary coolant, service sensitive piping at other operating BWRs.
1 Sincerely,'
L. C. Lessor Station Superintendent Cooper Nuclear Station LCL:cg Attach ~.
- m. _ __ _
|
---|
|
|
| | Reporting criterion |
---|
05000298/LER-1982-005, Amended LER 82-005/03X-1:on 820221,surveillance Test Indicated MSIV 86A Had Closing Time Faster than Allowed by Tech Specs.Caused by Loss of Nitrogen Preload & Fluid from Hydraulic Sys Accumulator.Accumulator Recharged & Tested | Amended LER 82-005/03X-1:on 820221,surveillance Test Indicated MSIV 86A Had Closing Time Faster than Allowed by Tech Specs.Caused by Loss of Nitrogen Preload & Fluid from Hydraulic Sys Accumulator.Accumulator Recharged & Tested | | 05000298/LER-1982-009, Forwards LER 82-009/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-009/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-010/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-011, Forwards LER 82-011/03-0.Detailed Event Analysis Submitted | Forwards LER 82-011/03-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-013/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-014, Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced | Amended LER 82-014/03X-1:on 820607,rejectable Indications Found in Heat Affected Zones of Welds BJ-13,BJ-15,BJ-20 & BJ-23.Caused by Improper Fabrication Techniques.Affected Piping & Fittings Replaced | | 05000298/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-015/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-016, Forwards LER 82-016/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-016/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-017/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-018, Forwards LER 82-018/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-018/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-019/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-020, Forwards LER 82-020/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-020/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-023, Forwards LER 82-023/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-023/03L-0.Detailed Event Analysis Submitted | | 05000298/LER-1982-026, Forwards LER 82-026/03L-0.Detailed Event Analysis Submitted | Forwards LER 82-026/03L-0.Detailed Event Analysis Submitted | |
|