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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000285/LER-1998-003, Re Individual Leaving High Radiation Area (HRA) Door Unlocked & Uncontrolled While in Hra. LER 98-003-00 Retracted1998-06-23023 June 1998 Re Individual Leaving High Radiation Area (HRA) Door Unlocked & Uncontrolled While in Hra. LER 98-003-00 Retracted 05000285/LER-1990-0071990-08-0101 August 1990 LER 90-007-02:on 900228,determined That Main Feedwater & Main Steam Piping Outside Design Basis.Caused by Design Deficiency & Failure of Engineer to Consider Loads Induced on Piping.Piping Supports modified.W/900801 Ltr 05000285/LER-1990-0101990-07-0303 July 1990 LER 90-010-01:on 900327,unplanned Attempted Start of Emergency Diesel Generator Occurred While Plant in Refueling Shutdown.Caused by Low Air Pressure in Diesel Start Sys. Instructions Re auto-start Signals changed.W/900703 Ltr ML20071G3271978-12-22022 December 1978 /03L-0 on 781124:during Shutdown Cooling Interlock Test Noted That PC-105B Was Not Operating.Caused by Valve Closing Relay 94-347/348 Not Being Wired to PC-105B; Inadvertently Disconnected in 1977 ML20071G2671978-12-22022 December 1978 /03L-0 on 781204:during Inspec of Discharged Fuel Assemblies,A Single Fuel Pin Was Observed to Have Failed, Assoc W/Manufacture & Exposure of Present Day Nuc Fuel ML20071G2381978-12-21021 December 1978 /03X-1 on 780918:during Refueling Outage,D Channel Hot Leg Temp Indication Was Investigated to Determine Cause of 780918 Failure.Failure Caused by Rosemount Model 104VC RTD Having Water in the Pothead ML20071G2201978-12-20020 December 1978 /03L-0 on 781122:noted That Level Transmiter for C Channel (C/LT-901) for Steam Generator RC-2A Level Instrumentation Not W/In Specs.Caused by Calibr Drift of Ge/Mac Model 555 Transmitter ML20071G2791978-12-19019 December 1978 /03L-0 on 781214:during 1978 Refueling Outage, Certain Surveillance Tests Req by Tech Specs Could Not Be Performed Because of Shutdown Condition.Facil Lic Change 77-11 Submitted to NRC on 781109 to Delete Requirements ML20071G0701978-12-12012 December 1978 /03L-0 on 781113:during Test of Ventilation Isolation Actuation Signal,Lockout 86B1/VIAS Did Not Trip. Cause Unidentified,Since Relay Retested & Found to Be Operating Normally.Relays Will Continue to Be Tested ML20071G0851978-12-0808 December 1978 /01T-0 on 781127:Diesel Generator 2 Failed to Auto Close Onto the Bus;Breaker Mode Switch Contracts 27-27c Failed to Make Contact.Caused by Contact Failure ML20071G1011978-12-0505 December 1978 /03L-0 on 781116:during Refueling,All Limitorque Valves Were Inspec for Proper Staking of the Lock Nut on the Motor operator.30 of 65 Valves Exhibited Unstaked Lock Nuts.Lock Nuts Were Staked IAW Manufacturer'S Instructions ML20071F9281978-11-27027 November 1978 /03L-0 on 781101:auxiliary Feedwater Check Valve FW-164 Found to Be Oriented in Wrong Position.Caused by Missing Valve Disk Plate Which Was Subsequently Located & Recovered ML20071F9061978-11-25025 November 1978 /03L-0 on 781026:repeated Tripping of Stack Particulate Process Monitor.Caused by Trip Set in Accordance W/Tech Specs Table 2-1 at 9.6x10-2,rather than More Conservative Release Rates 2x10-3 ML20071F8541978-11-0202 November 1978 /03L-0 on 781014:Reactor Coolant Cold Leg Temp Indicator B/122C Failed High Off Scale Because of an Open Circuited Rosemount Model 104VC Rtd.The RTD Will Be Replaced During Present Refueling Outage ML20071F4821978-10-0606 October 1978 /03L-0 on 780908:Inadvertent Radioactive Gas Release to Atmosphere Caused by Leakage Past Check Valve CH-284,HG-100 & Relief Valve HG-105.Valves Will Be Inspected & Replaced or Repaired During Next Refueling Outage ML20147B1901978-10-0303 October 1978 /01T-0 on 781003:During Oper Check on Auxiliary Steam Driven Feed Pump,The Steam Inlet Valve YCV-1045 Did Not Open Due to Closed Air Supply ML20071F4671978-09-27027 September 1978 /03L-0 on 780831:failure of Tri-x Weather Tower'S 100 Meter Delta-T Sensor Sys to Rept Stability Class Info. Calibrations Revised to Ensure Instruments Detect Subsequent Sensor Sys Failures ML20071F4881978-09-15015 September 1978 /03L-1 on 780830:Bchannel RPS Variable Overpwr Trip Reset Demand Alarm Actuated & Would Not Reset.Then,Hi Pwr & Thermal Margin/Low Pressure Trip Units Failed,Both Due to Failure of Devar19-601A,18volt Pwr Supply 05000285/LER-1976-005, Suppl 1 to LER 76-05/03L:on 770210,recirculation Actuation Pressure Switches Found Out of Tolerance.Cause Not Stated. Switch Will Be Calibr Monthly Until New Switches Installed1977-02-10010 February 1977 Suppl 1 to LER 76-05/03L:on 770210,recirculation Actuation Pressure Switches Found Out of Tolerance.Cause Not Stated. Switch Will Be Calibr Monthly Until New Switches Installed 05000285/LER-1976-019, Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage1976-10-14014 October 1976 Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage 05000285/LER-1976-021, Suppl 1 to LER 76-21/03L:on 760802,timer Relays for SI-3A, AC-3B & SI-3B Failed to Time Out at Set Times.Caused by Binding Operating Mechanisms.Timers Tested Twice Weekly to Verify Operability Until Replacements Received1976-08-0909 August 1976 Suppl 1 to LER 76-21/03L:on 760802,timer Relays for SI-3A, AC-3B & SI-3B Failed to Time Out at Set Times.Caused by Binding Operating Mechanisms.Timers Tested Twice Weekly to Verify Operability Until Replacements Received 05000285/LER-1976-010, Suppl to LER 76-10/03L:on 760401,high Power Margin to Trip Meter B Drifted from 4.2% to 6% Power.Caused by Drift of Feed Back Limiter Module 19-317-2X.Module Calibr & Operated Satisfactorily1976-04-0808 April 1976 Suppl to LER 76-10/03L:on 760401,high Power Margin to Trip Meter B Drifted from 4.2% to 6% Power.Caused by Drift of Feed Back Limiter Module 19-317-2X.Module Calibr & Operated Satisfactorily 1998-06-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
[Table view] |
Text
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,0CNTCOL BLOCK: I I
I I I I I 6
l@ (PLEAsE PRINT OR TYPE ALL f*EQUIRED INFonMATICN) 4 Io 1ils 9lN l E I F lC lS I1 l@l uCENs 5C::E ia :s 0l 010l 0 w:ENst l 0 l NUusER 010 l 0 l 0 l010 a l@ 26 hl uCENsi 111l rvet 1l 1l@la l
si ur 54 @
l CCNi lotil 5
[$$lLl@l0151010 60 61 10 12 18 15 l@l l691111 OQCK ET NUMS ER ih8 161718 l@l 112 REPCRT EV ENT QATg 74 75 l 01517 OATE l 840l@
EVENT CESCRIPTICN AND PRC8ABLE CONSEOUENCES h j o i : ! l Ouring the 1978 refueling all Li=iterque valves were inspected for preper staking er the!
lo a t I ock l nut on this design no cr operator. The inspection of the notor operaters revealed (
, o 3 ,, , lthat 30 operators vere not staked in accordance with the =anufacturers recc==endatiens.__J
,o33, i Inspection.vas conducted as a result of ecc:=unication with Cenbustion Engineering who j
,g,,, gi nfo::ed 0FFD that. Arkansas (ANO-2) had found several operators unstaked. In an unstaked ;
Iot7i i condition the lock nut could backout due to vibration and cause the ste= nut to =ove i
- ar4M'v and disengage the splines resulting in the loss of drive to the valve ste=. [
7 8 9 'J SYSTEM CAUSE CAUSE COMP. VALVE CCOE CODE SUSC00E COMPCNENT CODE SUSCOCE susC0ct l0ist~ lZ IZ l@
9
@ lBl@ IVlAlL IV IO lp l@ l A l@ ] @
12 19 7 4 to 11 13 18 .3
,,, SECUENTIAL OCCURRENCE REPORT R EV'53CN LEn EVENTvtAR REPORT NC. COCE TYPE No.
@ ,ag;Ro 17181 1-1 10l3171 IA 10131 IL i l-J LoJ
,_21 22 23 24 26 27 28 ;3 30 31 32 ACTION . PUTU R E, EP8ECT $wutcowN ATTACHwENT Nesto 4 PRIME COMe, OOupcNgNT TAKEN ACTION ON PLANT METHCO hours a $USMITTED PORMbu8. SUPPU ER MANUPACTURER I22 31@l24 Zl@ lasZ l@ IZl@ 10 10 10 10 I I Yl@ lNI@ IAl@ l L l 210 l0 i(
- s si ao 4i 42 42 da 47 CAUSE DESCRIPTION AND CORRECTIVE ACTICNS h i I a ! JThe valve operators supelled by Li=itercue were never staked to trevent the backine cu* I
,, ei; tef the lock nut. The corrective acticn taken was to examine eve-t Limitercue eterster, I
,, ,;. l tighten and stake the lock nut in accordance .rith the nanufacturers instructions. Thir yt
! p, g lcf a total of 65 valves inspected avw4bited this proble= (listed in Attac k
- - ' ) . No I
- , ,,, ; valve failures attributable to this proble= have occur ed at Fe
- t Calhoun Station.
? I 3 30 y uETwCO CP sACTU's ITATu % PCwER CTHER STATUS OtSCCVERY CISCOVERY CESCRIPTTON =*.
liisl8 W 7 9
@ l0l010l@l13 12 11 NA 44 l l45 Dl @46lInsueetion after notification fre nsss30l ACTiv!TY CONTENT 4ELEASED CP MEL2ASE AMCUNT CP AC*1VITY LOCATicN CP RELEASE NA l l NA i li 8 41 7 4 9 I Z l @ LEJ@l to it 44 46 dC PER$CNNEL EXPCSURES NUMSER Wof OESCRIPTICN *
" l ' l l l 0 l 0 l 0 l@l Zl@l 13NA l 7 8 9 11 12 BC PER$CNN E L INJURIE3 NUMSER ESCRiPTICN f
i: n i4l 3o 10 t o !@l NA 1 't 12 80 LO53 CP CR cauaGE TO PAC 1UTv Q vot CESCRIPTtCN v
[: l 9' l'l Z lh 3A I
issues UsusTv n ,,/
781320 ca_7/> NPcusEC~LT g
1: IofINl@oEsCRiPTtoN\.E l NA /f, b i !Iff II'II I f f I*
, , , . p a .. u, D. Jcnes/3. Andrevs h02d2 M 011 NAME O' k AE* ARER PkCNE: {
_ . - . _ -r - -
,-,w-. -r -
LIR 78-037 O=aha Public Power Distrie:
Port Calhoun Statien Unit No. 1 Docket No. 05000265 A::ach=ent No. 1 Valves Feferenced in Section 27
- 1. ECV-311 EPSI Loop Isolation Valve
- 2. ECV-312 EPSI Loop Isolation Valve 3 ECV-31h EPSI Loop Isolation Valve
- k. ECV-315 EPSI Loop Isolation valve 5 ECV-317 HPSI Loop Isolation Valve
- 6. ECV-318 EPSI Loop Isolation Valve 7 ECV-320 EPSI Loop Isolation Valve S. ECV-321 EPSI Loop Isolation Valve 9 ECV-327 LPSI Loop Isolation Valve g 10. ECV-329 LPSI Loop Isolation Valve
- 11. ECV-331 LPSI Locp Isolation Valve
- 12. ECV-333 LPSI Loop Isolation valve
- 13. ECV-3kT SI Shutdown Cooling Valve 1h. ECV-3h8 SI snutdown Cooling valve
- 15. ECV-291h SI Tank Isolation valve
- 16. ECV-2934 SI Tank Isolatica Valve 17 ECV-2954 SI Tank Isolation Valve
- 18. ECV-297h SI Tank Isolation Valve 19 ECV-150 PORY Isolation Valve
- 20. ECV-151 PORY Isolation Valve
- 21. LCV-218-2 CVCS VCT
- 22. LCV-218-3 CVCS SIR W
- 23. ECV-258 herg 6ncy 3cratirn Valve 2h. ECV-265 E=ergency Boration valve 25 ECV-268 Energency Scration Valve
- 26. ECV-308 Charging to Safety Injection 27 ECV-138k Aux. Feedvater Valve
- 28. ECV-10h2C Main Stea= Control Valve 3ypass 29 MOV-S1 Motor operated Drain valve on Main Stea=
- 30. 307-973 ?rb. hth Stage Ert.
l l
i l .
IJ.R 78-037 O=aha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 Attach =ent No. 2 Safety Analysis The problem of non-staked or i= properly staked Li=itorque valve operators was identified to the Fort Calhoun Stction by the NSSS Vendor Combustion Engineering. Combustion Engineering informed OPPD that if an operator had an i= properly staked lock nut, the operator stem nut could back out and loss of valve operation could occur. During the scheduled refueling outage all Limitorque valve operators were inspected and 30 operators were found not to be staked. The immediate corrective action was to insure the lock nut was tight and the nut was staked in accordance with the manufacturers recommenda-tions for staking.
The conditions found at the Fort Calhoun Station vere that the lock nuts on several valves were slightly icose, but in no instances was the ste= nut tacked out which would have jeopardiced the operation of the valve. Should an operator as identified on Attachment 1 have failed, the safety of the plant vould not have been affected since redundant systems are available and each failure would have to be an isolated event.
Periodic surveillance testing and/or operation of these valves has proven the valves to be operable. Reference Ccmbustion Engineering letter attached for further detailed information.
1 I
I i
. . _ . . . . - . . , . .es. c m oo:p wa:
Comoustion Engineenng. Inc. , Tcsex: 99297 1000 Prosoect Hill Acac Winescr. Connecocus o6c9s N POWER
~
"J SYSTEMS '
July 28, 1978 CE-18074-436 Mr. T.E. Show: Omaha Public Power District Omaha Public Power District Unit #1 .: Fort Calhoun Station Jon;s Street Station Engineering Services Agreement 4th. & Jones Street C-E Contract 2177 Omaha, Nebraska 68102
Subject:
Improperly Staked Motor Valve Operators
Enclosures:
(1) Section Sketch of Valve Drive Elements (Limitorque Operations)
(2) C-E Supplied Motor Operated Valves
. car Mr. Short: ~
This is to infor1n you of a problem with imoroperly staked or non-staked Limitorque operators on motor operated valves. This problem could cause tha operator stem nut to back out, resulting in a loss of valve operator -
action. It occurred at one plant and subsequently was brought to the attention of ANO-2 (Arkansas) where the Limitort.e operators were inspected and several were found to lack staking.
During normal operation, the Limitorque operator opens or closes valves by rotation of the valve stem within the operator stem nut (see Enclosure 1).
Tha internal portion of the stem nut is made to match the valve stem. The extcrnal portion has axial splines and matches the Li'r.itorque drive sleeve.
To ktep the " stem nut" captured, a locking nut. is screwed into the drive sleeve.
This locking nut requires staking or crimping to keep it from backing off.
the lacking nut has been imorecerly staked, it can back out, which in turn would allow :ne stem nut to move axially and to become disengaged from the splines. A loss of drive to the valve stem results. No torque is applied to tha locking nut during operation; however, it appears that vibration could loostn an unstaked locking nut., -
l It is recommended that you inspect the Limitorque motor ocerated valves at l Fort Calhoun as defined in Enclosure (2). The operators shou'd be inspected for unstaked locking nuts and the nuts staked as necessary.
Very truly yours, ,
AGS:SB:jm < - N Encl. w/l cy. A.G. Schoencrunn
, c:: R. Andrews, OPPO, (1); w/l cy. Manager Engineering. Services X. Morris, OPPO, (1); w/l cy. For: Calhoun-1 R. Chatfield, OPPD, (1); w/l cy.
W.C. Novick, CEXO R. Erlacher, CEXC L. Kesselman, CE-Windsor l S.A. Dunn, CE-135 A. Stathoplos , CE-Windsor l
l .
i
- C-E Supplied Motor Operated Valves .
Fort Calhoun -
Valve Tao No. Descriction Vender
~
HCV-348 12" - 1500# Gate Velan HCV-347 10" '- 1500f Gate Velan HCV-2914, 2934, 2954, 2974 12" - 300# Gate Darling HCV-327, 329, 331, 333 ,,
6" - 200f Globe Calmer HCV-311, 312, 314, 315, 317~,
318, 320, 321 2" - 1500f Globe Velan o HCV-268 .3" - 1504 Gate Velan o LCV-218-2 4" - 150# Gate Velan E
e9 ee f
O
C E Power Systems
.' Ocmousuon Engineenng. inc.
Tcl 2C31688-1911 Teler. 99297 ,
1000 Prosoec: MdlAcac Winosor Connecucut 06095 r":s POWER ~
M SYSTEMS July 21,1978 NFS-OPPD-78-40
Omaha Public Power District Jones Street Station -
4th & Jones Street Omaha, Nebraska 68102 ,
Subject:
Improperly Stakad Motor Valve Operators Inclosure: (:.A) C-E Letter CZ-18074-436, dated July 23, 1978 Subject - Improperly Stakad Motor Valve Operators (1) Section Skatch of 7alve Drive Elements (t4d e nqua Operators)
(2) C-E Supplied Motor Operated valves
Dear Mr. Short:
Enclosure IA through 2 are provided for your information conear4 g improperly staked or non-staked 1%4 tuque operators on motor oper-ated valves.
Should you have any questions please do not hesitata a contact me.
Very t=uly yours, STION ENG P NG, DC.
A. A L
L. F. Kasselman -
Nuclear Service Site Manager L7K:fd ,
j Enc.
l ec: 1. Andrews, CPPD e W #
I. Morris, 0??D
- 2. Chatfield, 0??D
- J. C. :u' rrick, CIIC R. Irlacher, 3 S. A. Dunn, CZ-135 I A. Stathopics, CI Tindsor A. Schoenbru=n, CI 'Jindso
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STEM NUT REPLACEMENT & LOCO.NC- INSTRJCTIONS .
1.-5007 CML STAR.ES FR:CR TO LCCKNUT .tMCVAL.
- 2. REMOVE LCCKNUT(J) TRCf.1 CRIVZ SLZ!v!(1) AT CPEN:NG CF HCUSING CCVCR t. SFECIAL WRENCH SUCH tS SHC'.".'N EELOW -
vn.L FAC:LITt.TE REMCve.L EUT IS NOT REC (SED FCd SA?tE, REMOVE Ct.O STC A NUT (2).
1-CRCP NEW STD.I NUT (2)INTO CRivE SLEEVE U)THRU SFL!NES.
TAP NUT SUGHTLY TO MA:tE SURE IT is SCTTC;.:ED IN THE CRivE SLEIVE.
4.-SCREW IN LCCKNUTC)UNTit TWE TC9 IS FLUSH (Ac2ACx.) WITH TCP OF CRIVE SLEEVCf11AND TICHTEN WITH WRENCd.
1-THEN 5 AKE LCCkNUT IN PLACE AT TWO PCINTS,If.C* APART.
USJNG STAKING TCCL AS SHOWN.
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