|
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Category:Report
MONTHYEARNLS2024065, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2024-10-0707 October 2024
10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report
NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024
Data from Metamic Coupon Sampling Program
ML23129A2792023-04-20020 April 2023
1 to Updated Safety Analysis Report, Plant Unique Analysis Report Mark I Containment Program
NLS2023010, Inservice Inspection OAR-1 Owners Activity Report for Cooper Nuclear Station2023-02-0909 February 2023
Inservice Inspection OAR-1 Owners Activity Report for Cooper Nuclear Station
NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023
Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022
NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022
Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library
NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022
10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report
NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022
Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021
ML19262G9042019-11-0808 November 2019
Staff Assessment of Flood Hazard Integrated Assessment (Public)
NLS2019040, 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary)2019-08-0707 August 2019
3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary)
NLS2019028, Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 02018-10-24024 October 2018
Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0
ML18184A2732018-07-18018 July 2018
Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter (CAC No. MF7819; EPID L-2016-JLD-0006)
NLS2018024, Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31.2018-04-30030 April 2018
Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31.
NLS2018003, Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20172018-01-15015 January 2018
Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2017
NLS2017070, Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information2017-08-24024 August 2017
Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information
ML17244A2812017-05-0808 May 2017
16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation.
NLS2016070, Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events2017-01-0404 January 2017
Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events
NLS2016066, Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation2016-12-20020 December 2016
Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation
ML16351A2472016-12-12012 December 2016
Review of SIA Calculation 1601004.301, Cooper High Pressure RHRSW Thinning Evaluation Per Code Case N-513
ML17018A1522016-11-0101 November 2016
Pressure and Temperature Limits Report, Revision 1
NLS2016058, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/20162016-10-0707 October 2016
10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/2016
ML16351A2512016-09-15015 September 2016
SW-E-3-2851-3, Ultrasonic Thickness Measurement System.
ML16351A2502016-09-13013 September 2016
SW-Z4-2851-7, Altrasonic Thickness Measurement System.
NLS2016021, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)2016-04-21021 April 2016
Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)
ML16084A1832016-03-0202 March 2016
Er 15-019, Rev. 1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary Version of Er 15-015).
NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015
Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168
ML15259A3422015-08-24024 August 2015
10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al
NLS2015073, Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 22015-08-0606 August 2015
Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 2
NLS2015091, 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-07-28028 July 2015
10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168
NLS2015043, Expedited Seismic Evaluation Process Report2015-04-29029 April 2015
Expedited Seismic Evaluation Process Report
ML15006A2342015-02-11011 February 2015
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents)
ML17018A1532014-12-31031 December 2014
BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program Data Source Book and Plant Evaluations
NLS2016014, Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations.2014-12-31031 December 2014
Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations.
NLS2014074, Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 92332014-07-30030 July 2014
Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 9233
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
NLS2014044, and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.2102014-05-13013 May 2014
and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210
NLS2014027, Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station2014-03-20020 March 2014
Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station
ML14007A6502014-02-11011 February 2014
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14037A1672014-02-10010 February 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Cooper Nuclear Station, TAC No.: MF0972
NLS2012130, Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue2012-12-13013 December 2012
Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue
ML12340A2752012-11-27027 November 2012
Engineering Evaluation 12-E18, Revision 0, Attachment E Through J
ML12340A2732012-11-27027 November 2012
Engineering Evaluation 12-E18, Revision 0, Attachment D - Area Walk-By Checklists
ML12340A2692012-11-27027 November 2012
Engineering Evaluation 12-E18, Revision 0, Attachment C - Page 76 of 322
ML12340A2682012-11-27027 November 2012
CNS Memo DED12-0003 Response to 10 CFR 50.54(f) Section 2.3 Seismic, Enclosing Engineering Evaluation 12-E18, Revision 0
NLS2012124, Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report2012-11-26026 November 2012
Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report
NLS2012085, CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 20122012-10-10010 October 2012
CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 2012
NLS2012089, Submittal of Nuclear Material Transaction Report2012-08-29029 August 2012
Submittal of Nuclear Material Transaction Report
ML1216000292012-06-11011 June 2012
Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident
NLS2012040, Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 282012-05-30030 May 2012
Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 28
NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012
Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)
2024-07-29
[Table view]
Category:Miscellaneous
MONTHYEARNLS2024065, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2024-10-0707 October 2024
10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report
NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024
Data from Metamic Coupon Sampling Program
NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023
Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022
NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022
10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report
NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022
Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021
ML19262G9042019-11-0808 November 2019
Staff Assessment of Flood Hazard Integrated Assessment (Public)
ML18184A2732018-07-18018 July 2018
Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter (CAC No. MF7819; EPID L-2016-JLD-0006)
NLS2018003, Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20172018-01-15015 January 2018
Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2017
ML17244A2812017-05-0808 May 2017
16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation.
NLS2016070, Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events2017-01-0404 January 2017
Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events
NLS2016066, Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation2016-12-20020 December 2016
Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation
ML16351A2472016-12-12012 December 2016
Review of SIA Calculation 1601004.301, Cooper High Pressure RHRSW Thinning Evaluation Per Code Case N-513
NLS2016058, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/20162016-10-0707 October 2016
10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/2016
NLS2016021, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)2016-04-21021 April 2016
Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)
NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015
Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168
ML15259A3422015-08-24024 August 2015
10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al
ML15006A2342015-02-11011 February 2015
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents)
NLS2014074, Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 92332014-07-30030 July 2014
Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 9233
NLS2014044, and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.2102014-05-13013 May 2014
and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210
NLS2012124, Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report2012-11-26026 November 2012
Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report
NLS2012085, CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 20122012-10-10010 October 2012
CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 2012
NLS2012089, Submittal of Nuclear Material Transaction Report2012-08-29029 August 2012
Submittal of Nuclear Material Transaction Report
ML1216000292012-06-11011 June 2012
Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident
ML1127000692011-09-26026 September 2011
Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
NLS2009099, SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application2009-12-0707 December 2009
SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application
NLS2008106, Submittal of Program for Maintenance of Irradiated Fuel2008-12-23023 December 2008
Submittal of Program for Maintenance of Irradiated Fuel
NLS2008096, Corrected Semiannual Fitness for Duty Program Performance Report for the Period of January 1, 2008 Through June 30, 20082008-10-22022 October 2008
Corrected Semiannual Fitness for Duty Program Performance Report for the Period of January 1, 2008 Through June 30, 2008
NLS2008059, Submittal of Revised Root Cause Investigation - Diesel Generator Amphenol Connector2008-07-21021 July 2008
Submittal of Revised Root Cause Investigation - Diesel Generator Amphenol Connector
NLS2008033, Response to Request for Additional Information for Question I.2 Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-03-12012 March 2008
Response to Request for Additional Information for Question I.2 Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
NLS2008019, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-03-0606 March 2008
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
ML0917502992008-01-0101 January 2008
Lr - NPPD 2008 Integrated Resource Plan
NLS2006090, Core Operating Limits Report, Cycle 24, Revision 02006-11-0505 November 2006
Core Operating Limits Report, Cycle 24, Revision 0
NLS2006084, CFR 50.59(d)(2) Summary Report2006-10-12012 October 2006
CFR 50.59(d)(2) Summary Report
NLS2005107, Reporting of Changes and Errors in ECCS Evaluation Models Cooper Nuclear Station2005-12-28028 December 2005
Reporting of Changes and Errors in ECCS Evaluation Models Cooper Nuclear Station
ML0520901582005-08-0202 August 2005
2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment
ML0522700732005-04-18018 April 2005
Event Notification Report for April 18, 2005
ML0727008492005-01-31031 January 2005
Caldon Experience in Nuclear Feedwater Flow Measurement
NLS2004117, 1OCFR50.59(d)(2) Summary Report2004-10-14014 October 2004
1OCFR50.59(d)(2) Summary Report
NLS2004105, Initial Actions Summary Report and Response to NRC Generic Letter 2003-01, Control Room Habitability.2004-09-30030 September 2004
Initial Actions Summary Report and Response to NRC Generic Letter 2003-01, Control Room Habitability.
ML0619802152004-08-0606 August 2004
CNS Assessment of Survivability of the Service Water Pumps When Gland Waste Water Was Lost
ML0622205762004-07-27027 July 2004
Johnston Pump Company Letter to Mr. Kent Sutton
ML0619801532004-07-16016 July 2004
Excerpts from Historic Work Orders
ML0532204612004-06-14014 June 2004
Power Reactor Status Report for 6/14/04
ML0618607342004-05-11011 May 2004
Comments Concerning Loss of Gland Water to the Service Water Pumps at Cooper Nuclear Station
ML0618607312004-05-0606 May 2004
Comments Concerning Loss of Gland Water to the Service Water Pumps at Cooper Nuclear Station
ML0618701942004-04-30030 April 2004
Excerpt from Missouri Nuclear Accident Plan
ML0619801092004-03-17017 March 2004
CNS Roots Cause Investigation - Service Water Gland Water Valve Mis-positioning Event, SCR 2004-0077
ML0619801012004-03-10010 March 2004
CNS Clearance Order, Section SWB-1-4324147 SW-STNR-B
ML0626304082004-03-0101 March 2004
PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment
ML0619800892004-02-18018 February 2004
CNS Notification 10294449
2024-07-29
[Table view] |
Text
13~~
- 6A"' PvFP~ L~r F. .L~DA y XAP A -5A,3 f 4
D_ -
-946i109 200 4 Order #*4382673 jRLTANNE Original Page I NPPD WORK ORDER OPERATIONS & -ATERIAL LIST Order 4382673 Order type: PM CNS Plannd :MAiitenance
.Description SET IMPELLER LIFT PER 7.(2..45 Stait date 06/10/20664 End date 06/11/2004 Priority 3 important Status ' REL 'ESTC MCM 'Pkt SETC ISS TSTR FuncLeocalion CNS-2-SW-P-B -ABC Ind.
SORT SW-P-B Description SWP B.1 Programs:
IST SSEL Location Room -S sWP ?RM
.MaintPlanGroup Plant-Section IS CNS. CNS P- ,.. cpt. *Min WikCenter MNTSHOPM C6S AMaintPlan 8000000-08753 Maintilten 12703
-Requiredin Mode: WRepair in Mod 1 RUN Tech Spec -Ref.: References.':
,. PM08297 RCR ',200i1_0129 #*2- ..
ud 11 u II (z:; E; SET IMPELLER..LIFT PER.'7.2.451 i-ET iMPELLER LIFT FOR tSW-P'S Division II.
PER :SYSTEM. ENGINEER :(D!.VORPHAL) "LAND FLUSHiNG'NOT REQUI'RED .AT THIS.
TIME. 'DUE 'TO ONE TIMEliPERFo CE'FTHIS WORK, 'STEPS 50, 80, 90 :WERE DELETED FROM THIS WORK, ORDER. JRI'WHIS_,L 2O.
/04, WORK SIF'D INTO WEEK '424 .AT T-0 ADDED TO PREVENT PUMP LIFT FOM .ENTERING ALERT.RANGE DURING..NEXT 1ST TEST,. SCHEDULED 6/0i/04 BRSTRAM 06 -08/2004 CLEARANCE ORDER SW 4382673 SW-P-B :LIFT ADJ.
PKG PRE-ISSUED PENDING CO .SW 4382673 SW-P-B LIFT ADJ. SCSMALL 6-9-04.
Operation 0010 APPLhtdAbLE SECTIONS OF"6.2SW.101 sta,,s DSEX REL, .
Work center OPSCREW C-NS ON SHIFT OPERATIONS ComnpConfNo. 952221 " -'I Qualifications Verified -j -,;ý
I OTE h-IfAS FOUND measurementin Step 4.41is within the limits ,stated in Ste"' 43, aadjustmenitis not required.
4.4 (QC Usig aaWtness) feeler gauge, measure and record ASTFOUND rim peller, lift by measuring gap betweeniadjusting plate face and drive halfI oupliing face ASIUNLULeUe..*"7 .. nAhi
.AS FOUND~mpeller Lift: O..STinch QC Sidhature/Date:
Ck4.'5 Adjust pump Jift to as close as possibic to..A007' gap (without exceeding this value) by holding pump hlf c6uipling against turningand rotating adjusting
-plate.
(4.6 Turn adjusting plate down untiI bolt loles Will line up -with nearest bolt holes i4n pump, hOupling.
4.7 mACI (QC Witness) Using a feeler gauge, measureand record AS LEFT pump I .lift. The AS:LEFT pump lift sinall be as close to 0.100".as possible. (without
- exceeding this value).
-:ii:.:!
- i:AS LEFT Impeller Lift:O. o.C'1"& incl erf , d. By:
,QQ'SignatureIDate:--
Rotate plate. driver shaft to align bolt holes . of drive halfcouplihng with adjust 1*'
(QC Hold) Insd6ct.pump components as follow;s, recording -an discrepa:
found:
94,9.1 Pump couplIng for dýamge, erosionn, corrosion, and wear.
- UNSAT 4.9.2 Coupling boltsifor damage,,wear; galled, or stripped threads.
.CS.aue t:.T.: UNSAT QC SignatLu-e/Date:, -
I-discrepancies are recorded, they shall be resolved.
Co.
4.11 Apply thread lubricant'to couplingbolts.
I . . PROCEDURE 7.2.45- I - REVISIONJ OI* 0 PAGES AE3F oril J__
I RCDR .. 5I l RVSO
- 1* r S 16rd6r Type Insc. utart 'Sbbrt tE'ix. Fu OCtElidd. kDitfec fin.,
S4289093 CM 4256931M OERHUL
":0110/2003 ADD0/.0/203 ""
PACKINGVTO *KV*E:,ATE SW TUP-D PUP... .CNS-2-SW- -D 01/07(2003 01/13/2003-
- TCNS-2-SWP-D 4260039 PM 01/O0572003 SETIMPELLER LIFTPER7.T2,45SEE NOTE __-* CNS-2-SW-PRD 0AIR1/29003 1004560 LCO, 12128:/2002 SW*'P-D OVERHAUL LCO r3.:7: . 2 N........012./00 4>88 001 428200CM 02105120 2
02/5/203NEED-TO.RETORQUE 0 To.iv r FOUNDKTION:BOLTS- `'d0kiiS', PER 7. CNS-2"-SK.P-D '01/0 02:/05/2003 ~V%~~ = Hit- *..
- 3097C. 0410612003 IINSPECT D!VISION II SW GLAND WATER< PIPE .CNS-2;SW-P-D '0410812003 4300283 CM 04/l172003 L~USH SW-P-D"GLAND. SEAL'LINE CNS...... D:04/17/200 4233508 4303'49.9ICM.CM 402/,10/2003.
05/19/2002 ADPACKIGADJUST PACKINGON ,
LEKANT O O.SM AW-0DJUTETLN.
PUMPD .
CS--
CNS-'2;SW-P'-D PD1/420 05/19/2003 4315750 CM 061.i1I20031SWP*.D EXCESSIVE SEAL LEAKAGE . CNS-2'.*SW;P-D' 06/19/2003.
432165M 09/16/2003 "D' SERVICES PUMPWATER GLAND LEAKaGE. CNS-2-SW-P-D 09/*7620037 p stl-42368723 CM 051/1012004 SET'-D I EEDSR PACKING.ADJUSTEDE N"E" CNS SW-P-D 052/29,/104 L 4-4306293 CM' 06/21/2003 USH P -P**D GLEDSPACIN ASDJUSTED CNS;*2'S*-P-D 06/1/72006 4-41- 0CH 06-9 2,0,'0+V:= 'CMS:x VE:i SE ALLEKG .*=SLAZ**_ co:-2... 1 . 06-*--*2*'"03 I.
p ~~-- 3Ll f1~
~'JIDispilayCN~S I
Mafinteniance Order.43,33.508't:Op'eiriaýtio.n OV.61-.verie W.
A4'i~7~ In,I7 i I~i '1* 'i
,f,*kq**
arKtk~ Plan Q
ato Edt3t
-MI 6*ofi niomn ytm Hl r rr J ~r .neJ~ ~l Display PM Order'Confirmation:Actualdata tj wi .~~7*ttv~t - . .. .:.% 4:y4~
- i*i **i -1
- i i~ i*i,*
GDROWLE PERFORMED;. LIFT PER -7.2 .45. :,:AASý-FOUNDb-LI-FT WAS .077 - .
AS LEFT LIFT WAS .'094",
4 I
,re r Edi aot ________________ ___________Help
-DisplayCNS.Maintenance Order4256493: O'peration Over/ew jý 'ý?T, "
~+/-I~tt~it~Iflk~IH iiP
%10 Pvm.. F0
I
- KDSULLW -& MDBODEN 'RESET LIFT. -AS,::FOUND `WAS 0.079 A ND AS LEFTI WAS, o:.A079, TORQUED COULJIaING BOLTS TO 80 FT IPOUNDS 'RETURNED.TO .
SERVICE.
-9
