Letter Sequence Other |
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Results
Other: 05000267/LER-1987-018, :on 870728,circulator Penetration Interspace Leakage Determined to Be in Excess of Limiting Condition for Operation 4.2.9 Limits.Caused by Mechanical Deficiency. Damaged Circulator Being Replaced W/Spare, ML20148G771, ML20148G794, ML20148G830, ML20148G851, ML20195K065, ML20235H473, ML20237A815, ML20237K211
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MONTHYEARML20204E3301980-07-0202 July 1980 Discusses Objectives & Conclusions Re Helium Circulator C-2102 Insp.Forwards Ga Co rept,GA-C15847,re Insp Results. Requests Review of Proposed Inservice Insp Program in Draft Tech Specs Submitted 800331.W/o Rept Project stage: Draft Other ML20237K2111987-07-31031 July 1987 Monthly Operating Rept for Jul 1987 Project stage: Other ML20237G7401987-08-21021 August 1987 Notification of 870911 Meeting W/Util in Arlington,Tx to Discuss Plant Circulator Failure & Recovery Project stage: Meeting 05000267/LER-1987-018, :on 870728,circulator Penetration Interspace Leakage Determined to Be in Excess of Limiting Condition for Operation 4.2.9 Limits.Caused by Mechanical Deficiency. Damaged Circulator Being Replaced W/Spare1987-08-28028 August 1987
- on 870728,circulator Penetration Interspace Leakage Determined to Be in Excess of Limiting Condition for Operation 4.2.9 Limits.Caused by Mechanical Deficiency. Damaged Circulator Being Replaced W/Spare
Project stage: Other ML20235H4731987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation Project stage: Other 05000267/LER-1987-018, Summarizes Util Commitments to Support Continued Operation of Plant,Per 870911 Meeting W/Nrc Re Damage in Helium Circulator C-2101 (Ref LER 87-018)1987-09-21021 September 1987 Summarizes Util Commitments to Support Continued Operation of Plant,Per 870911 Meeting W/Nrc Re Damage in Helium Circulator C-2101 (Ref LER 87-018) Project stage: Meeting ML20235H4401987-09-21021 September 1987 Summary of 870911 Meeting W/Util in Arlington,Tx Re Failure of Plant Circulator S/N C-2101 & Licensee Program to Recover from Failure.Licensee Rept, Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification... Encl Project stage: Meeting ML20236U5761987-11-20020 November 1987 Safety Evaluation Re Helium Circulator S/N C-2101 Damage. Util Corrective Action Program Initiated Project stage: Approval ML20236U5651987-11-20020 November 1987 Forwards Interim Safety Evaluation Re Helium Circulator S/N C-2101 Damage & Util Commitments for Continued Plant Operation.Reactor Will Be Shut Down Until Corrective Actions Are Completed Project stage: Approval ML20237A8151987-12-0808 December 1987 Forwards List of Questions Re New Bolting Matls for Helium Circulator C2101,per 871118 Telcon.One of Key Issues Was Util Decision to Use A286 Spec Bolts to Fasten circulator- Steam Scroll to Bearing Housing Project stage: Other ML20148G8301987-12-14014 December 1987 Metallurgical Analysis of Components from Helium Circulator C-2101 Project stage: Other ML20148G7711988-01-22022 January 1988 Forwards Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities, Per Commitment in . Insp Findings & Proposed Tech Spec Amend to Be Submitted 8 Months Following Removal of Circulator for Insp Project stage: Other ML20148G7941988-01-22022 January 1988 Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities Project stage: Other ML20148G8511988-01-22022 January 1988 Helium Circulator Insp Schedule Project stage: Other ML20153A8551988-03-0909 March 1988 Summary of 880304 Meeting W/Util to Discuss 880122 Submittal Re Helium Circulator Failure & Recovery.Attendee List & Viewgraphs Encl Project stage: Meeting ML20151L8911988-04-14014 April 1988 Discusses Revised Helium Circulator Outage Schedule,Per NRC 880304 Meeting.Schedule for 12 Wk Outage for Refurbishment of Helium Circulators Will Start on 880705 Instead of 880502 Project stage: Meeting ML20195K0591988-06-15015 June 1988 Forwards SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Helium Circulator S/N C-2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities Project stage: Approval ML20195K0651988-06-15015 June 1988 SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Rept of Helium Circulator S/N 2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities Project stage: Other 1987-08-28
[Table View] |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20077P9291991-08-15015 August 1991 Final Rept, Verification of Fort St Vrain Activation Analysis ML20072V5031991-04-12012 April 1991 Summary of Existing & Planned Work for Activation Verification,910415 ML20029B6731991-03-0505 March 1991 Nonproprietary Estimated Blast Effect from Ft St Vrain Well 11 Analysis Methods Summary ML20059L5921990-09-13013 September 1990 Determination of Upper Bounds on Radiation Exposure Rates at Refueling Floor Above Defueled Region W/Crd Orifice Assemblies Radiation Shielding Removed ML20042F9071990-05-0101 May 1990 Conceptual Plan & Cost Estimate for Early Dismantlement of Fort St Vrain Pcrv ML19332E8181989-12-0101 December 1989 Rev a to Fort St Vrain Site-Specific Decommissioning Cost Estimate Basis for Preliminary Decommissioning Plan ML19332C2831989-10-0909 October 1989 Fort St Vrain 3-D Neutron Source Analysis Using DIF3D ML19332E8191989-08-31031 August 1989 Rev a to Fort St Vrain Activation Analysis ML20245L4061989-08-31031 August 1989 Safety Analysis Rept for Reactor Defueling ML20246K1321989-07-31031 July 1989 Pcrv Tendon Surveillance Rept for Jul 1989.W/four Oversize Drawings ML20245J3261989-06-14014 June 1989 Rev B to Evaluation of Cable/Equipment Separation for Bearing Water Pumps P-2101-S,P-2102 (Train B),P-2102-S (Train B) & P-2107 (Train B) for App R Requirements ML20245C4581989-05-11011 May 1989 CRD Partial Scram Test Results & Max Daily Temp Rept, 890511-0531 ML19332E8211989-02-23023 February 1989 Fort St Vrain Plateout Analysis for Decommissioning Study ML20206K1111988-11-21021 November 1988 Rev a to Engineering Evaluation of Interaction & Effects of Plant Protection Sys & Steam Line Rupture Detection/ Isolation Sys ML20154E0981988-08-31031 August 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20077B9091988-05-31031 May 1988 Vols I & II of Activation Analysis ML20154A5451988-04-28028 April 1988 Integrated Sys Study of CRD Mechanism Rod Position Instrumentation ML20154A5501988-04-28028 April 1988 Temp Prediction for CRD Mechanism Motors ML20235A5591988-01-31031 January 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20148G7941988-01-22022 January 1988 Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities ML20148G8511988-01-22022 January 1988 Helium Circulator Insp Schedule ML20195H8731988-01-14014 January 1988 Final Rept on Fort St Vrain 871002-03 Fire ML20236J2911987-10-30030 October 1987 Preliminary Rept on Impact of Fort St Vrain 871002 Fire ML20235H4731987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation ML20235K2721987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage Including Licensing Assessment ML20195G9681987-08-11011 August 1987 Analyses Re Fort St Vrain DBA-2 Core Damage Frequency ML20235W6091987-07-31031 July 1987 Pcrv Tendon Interim Surveillance Rept ML20234C1091987-06-25025 June 1987 Issue B to Effect of Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity ML20214Q9981987-05-31031 May 1987 Verification Rept for Buckle Computer Program ML20215J8711987-05-0404 May 1987 Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling ML20214P3381987-04-30030 April 1987 Rev 3 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 4, Exemptions & Mods ML20214P3141987-04-30030 April 1987 Rev 5 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 2, Electrical Reviews ML20214P3061987-04-30030 April 1987 Rev 7 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 1, Shutdown Model 1997-04-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept 05000267/LER-1996-001, :on 960120,test Interval to Test Area Radiation Monitors Exceeded Due to Inattention to Controls for Identifying & Performing Required Surveillance Tests.Test Procedure Reissued & Completed1996-02-22022 February 1996
- on 960120,test Interval to Test Area Radiation Monitors Exceeded Due to Inattention to Controls for Identifying & Performing Required Surveillance Tests.Test Procedure Reissued & Completed
ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation 05000267/LER-1995-006-02, :on 950903,TS Violation Occurred Due to Failure to Meet Minimum Degree of Redundancy.Caused by Equipment Malfunction.Completed Actions to Remove Channel PT-446 from Svc Per Procedure Owp1995-10-0303 October 1995
- on 950903,TS Violation Occurred Due to Failure to Meet Minimum Degree of Redundancy.Caused by Equipment Malfunction.Completed Actions to Remove Channel PT-446 from Svc Per Procedure Owp
ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station 05000267/LER-1993-004, :on 930927,discovered Incorrect Reactor Building Ventilation Sys HEPA Filters Installed Due to Human Error.Replaced Train a Filters1993-10-26026 October 1993
- on 930927,discovered Incorrect Reactor Building Ventilation Sys HEPA Filters Installed Due to Human Error.Replaced Train a Filters
ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning 05000267/LER-1993-003, :on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well Operator1993-06-0303 June 1993
- on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well Operator
ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20035G7381993-04-26026 April 1993 SER Supporting Util 921125 Request for Exemption from Revised Requirements of 10CFR20 to Permit Decommissioning Activities Under Current Requirements of 10CFR20.1 Through 20.601 ML20035E4861993-04-0707 April 1993 Part 21 Rept Re K-400 Circuit Breaker Failed to Meet Certain Rating Requirements Based on ANSI C37.16.Licensees Scheduled Tests on Modified Arc Chutes in Several Different Modes at KEMA-Powertest Lab in Chalfont,Pa 05000267/LER-1993-002, :on 930210,plant Placed in Unanalyzed Condition When Reactor Bldg Crane Detached from Fuel Handling Machine. Caused by Misinterpretation of Applicable Procedural Requirements.Procedure Revised1993-03-11011 March 1993
- on 930210,plant Placed in Unanalyzed Condition When Reactor Bldg Crane Detached from Fuel Handling Machine. Caused by Misinterpretation of Applicable Procedural Requirements.Procedure Revised
05000267/LER-1993-001, :on 930126,discovered That Oil Separator in Radioactive Liquid Effluent Release Line Had Overflowed. Caused by an Ice Plug in Drain Line Downstream of Oil Separator.Ice Plug Thawed & Path Restored1993-02-25025 February 1993
- on 930126,discovered That Oil Separator in Radioactive Liquid Effluent Release Line Had Overflowed. Caused by an Ice Plug in Drain Line Downstream of Oil Separator.Ice Plug Thawed & Path Restored
ML20035D1731992-12-31031 December 1992 Annual Rept 1992 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 05000267/LER-1992-004, :on 920520,FHM Was Moved While Louvers Were Open.Caused by Failure to Follow Procedures.Louvers Were Closed & Personnel Reminded of Necessity to Follow Procedures1992-06-19019 June 1992
- on 920520,FHM Was Moved While Louvers Were Open.Caused by Failure to Follow Procedures.Louvers Were Closed & Personnel Reminded of Necessity to Follow Procedures
ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ 05000267/LER-1992-003, :on 920226,discovered That TS Surveillance Requirement 5.7.1a Re Verification of Fuel Handling Machine Internal Pressure Not Documented Every 12 H.Caused by Inadequate Procedure.Procedure Revised1992-03-27027 March 1992
- on 920226,discovered That TS Surveillance Requirement 5.7.1a Re Verification of Fuel Handling Machine Internal Pressure Not Documented Every 12 H.Caused by Inadequate Procedure.Procedure Revised
05000267/LER-1992-002, :on 920213 & 920216,reactor Bldg Integrity Not Maintained,Per TS LCO 4.5.1 Due to Inadequate Procedure & Failure to Follow Procedure.Truck Bay Door Opening Procedure & Permit as Contained in G-4 Revised1992-03-13013 March 1992
- on 920213 & 920216,reactor Bldg Integrity Not Maintained,Per TS LCO 4.5.1 Due to Inadequate Procedure & Failure to Follow Procedure.Truck Bay Door Opening Procedure & Permit as Contained in G-4 Revised
ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 05000267/LER-1992-001, :920106,discovered That Alternate Cooling Method Exhaust Stack Activities Monitors Not Included in Test Procedure.Caused by Failure to Update Functional Test Procedure.Procedure Revised1992-02-0505 February 1992
- 920106,discovered That Alternate Cooling Method Exhaust Stack Activities Monitors Not Included in Test Procedure.Caused by Failure to Update Functional Test Procedure.Procedure Revised
1997-07-01
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12.6.2 IBlade-lurb Rotor l C2101-440-3 IMT, Dwg note 8
l._
l I
l l_
l_
l
__ 11 1 *2 I
I
12./
11/4-28 Capscrew l C2101-460-10, l
l l
l l
l l
12.8 ISpring Plunger i C2101-300-53 1 *2 l
l
l i
I i
l__
i i
-31,
-32 IVisual, PT
12.9 linsulation Assembly l C2101-300-11, I
l l
1 I
l l
12.10 11/4-20 Hex Hd Bolt I C2101-300-16 l
l
4 1
I I
1 1
I i
12.11 l Upper SIM Seal l C2101-300-26 IVisual, PT
'71 "S
i i
l __. _
l I
I i
12.12 ISIM Seal Spacer l C2101-500-27 IVisual, PI
1 1
I I
I I
I I2.13 13/4" H.
Strength BoIt I C2101-399-45 1
1
I l _ ".
l _.
.__ _ _ I I
I I
12.14 13/4 Drilled Thru Bolt i C2101-300-52 l
l
l 1
l __.
I I
l l
12.15 ISIM Ducting Torus & St rutsl C2101-431- /,
-4 IVisual, PT
'71
I I
I I
I I
i 12.16 ICompressor Stator l C2101-300-10 l Visual I
I i
1 l
i I
i 12.16.1 IBlade-Comp Sta tor l C2101-300-2 IVisual, MI, Dwg Note 7 l
l I
i I
I i
12.17 l Comp Stator Bolts l C2191-389-10 IVisual, UT
l
l _ __ I I
I I
I I
RtMAHkS/ NOTES / TIC:
- 4) Visual for failed bolts - replace only
'7) NOT per NB2500 Section if both bolts on an assy. have feited.
Ill ASME Code.
I
- S) Ho relevant indications.
- 8) No abnormal wea r o r deg ra da t i on,
- 3) UT, Pi curvics, visual and dimensional on bearing and seal su. faces.
"6) Within a time frame not to exceed a time of 2 0,000 operating hours.
4
ATTACHMENT 2 HtllOM C_lRCULATOR INSPECTION SCHEDULE I IILM L
i l
I DESCRIPT10N l
1YPL/ TECHNIQUE I
I-1 l
PART WMBER I
PROCEDURE I
ACCEPTANCE CRITERIA IINTERVALI I
i l-12.18 IComp Wheel Bolt i
i C2101-3C 1.
l-1
_I _ - O-5 IVisual, UT, PT
'l i
12.19 Icompressor Wneel
_I l-I i C2101 -300-9 l-IVisual I
l
{
I I
12.19.1 IDisc-Compressor l
I
'8 l
l_
l l C2101-360-2 1
l Visual, MT, PT, Dw9
1 1
12.19.2 IBlade-Compressor Rotor i C2101-360-3 INote 5
I I
l l
IVisual, Mi l~
l 12.20 linsulation Assembly-l C2101-300 l_
(
I lComgresaor
,1 IVisual l_
l l
12.21 11/4 Bolts - Insulation i Cx101-310-4
_ __ I i
l.
IAssembly
_l I
IVisual, PT
)
i 12.22 (Helium Ducting l
12.22.1 l Ducting Details
_l.
IVisual l
'l
l l
l C2101-300-8 i
l l
1
l l_
i C2101-348-2 1
l IVisual, PT air foils
l 12.22.2 IScal Ring l
I l
1 C2101-340-9 I
IVisual
__l_
l 1
12.23 IBolt-ite Ducting l C2101-340-9
_l l
I I
IVisua:, PT
i i
i l
12.24 Inoit Supp Cone /Brg lisg l _C2101-300-40 __
.I I
l_
l
_l l_
IVisual, PT
i i
12.25 ISupport Cone l
I.
l l
1 1
! C2101-300-3
~lVisual, dim ac finish of__I
l-l 12.26 IService Pipe I
l C2101-300-17, -51 (Visual I
i I
l __
l 1
12.26.1 l Check Valve l --
l
l I C2101-300-18 1
i
IVisual l
~ (_
l l_
12.27 luol t-Service Pipe
! C2101-300-42
__ I l
l
I I
i IVisual, P1
_l
l I
12.28 IBolt-SIM Duct /Supp cone i C2101-300-39 I Vi s.ua l, PT
__l
i l
[
1.
l_
l I
I l
l l
I L
l I
l _-
I l
I l
l I
I I
I I
I l
I I
I l
I I
I l
I I
I l
1 I~
i I
l I
1 1
I I
l I
1 I-I I
i I
I I
I I
I l
l I
l I
I I
l I
I l
1 I
I l
1 I
I 1
i I
I 1-1 HEMARKS/NOTLS/ TIC:
_I I
_I I
I I
I I
)
- 4) Visual for fa iled bolts - replace only
'7) NDT per NB2500 Section
i f bo t h bo l t s on a n a s sy, ha ve fa i led.~
lli ASME Code.
l
- 5) No relevant indications.
- 3) UT, PT curvics, visual and
- 8) No abnormal wear or dimensional on bearing and seal surfaces.
- 61 Within a time frame not to exceed a deg rada t ion.
t in,e of 40,000 operating hours.
i
ATTACHMENT 2 ff[LIUM CIRCULA10R INSPECTION SCHEDULE 1
1 IILM i
l l
TYPE /ILCHNIQUE l
l l
l l
l DESCRIPil0N l
PART NUMBER I
PROCEDURE I
ACCEPTANCE CRITERIA IINTERVAll l
I I
l_
l i
l l
13 lBea ring Assembly l C2101-$00 ICene ra l Visual I
I I
I l __ - _
i l
i i
13.1 l Lower Labyrinth I C2101-$00-11 IVisual I
I I
I
__I I
I i
13.2 11/4-20 Bolt-Water Sea l l C2101-$00-39 l
l
+1 l
l I
I I
I I
I l3.3 IWa te r Sea l l C2101-$03-63 l Visual I
'8 l
i i
l I
l l
l l3.4 lSIM iairing I C2101-500-15 iVisuaI l
I l
l l
l I
i 13.5 lit.P. f eed flousing l C2101-$00-10 IVisual l
I I
l-i i
i i
13.6 IBol t-Upper Assembly l C2101-S00-31 IVisual, MT
l
l 1
1
_I l
l l
13.7 15/16-18 Bolt-S.D. Seal I C2101-$00-38 IVisual, MT
l
I I
I I ___.
I I
i 13.8 IShutdown Seal l C2101-$00-7 IVisual, verify stroke andl
l l
l lc losure per C2101-518
l 13.8.1 l Bellows - S.D.
Seal l C?101-518-2, -3 l Visual, Pi
'8 1
1 I
l__
l_
i i
I 13.9 lupper Labyrinth I C21GI-$00-6 IVisual l
l l
1 I
I i
13.10 IUpper Journa l La by ri nth l C2101-$00-5 IVisual I
'8 l
l_
l i
I i
l i
13.11 110-24 Screw-Sl inger l C2101-LOO-74 1
l
1 I
l_
l I
I i
13.12 ISlinger l C2101-$00-73 l Visual i
'8 l
I I
I I
I I
i 13.13 17/8-9 Bolt I C2101-$00-36 IVisual, MT
1
l I
I l _.
I-1 I
i 13.14 l Lowe r Bea ri ng I C2101-500-9 IVisual I
l I
I I
l l
l 13.14.1 li low Ori fices-t wr Brg l C2101-$00-$8,
-59,
-60 IVisual I
'8 l
l 1
I l_
l i
I i
13.14.2 IPin-flow Orifices l C2101-$00-49 IVisual l
l 1
I l_
l
_I I
I l
13.14.3 ISteeve f low Ori fices I C2101-$00-33 l Visual l
"8 l
1 1
I
- I
_1 I
i 13.14.4 li low Ori fices - Thrust l C2101-$00-32
-34, -67 IVisual l
l l Bearing i
i l
i l
13.1$
l Shaft l C2101-$00-8 l
1 I
l 1
I i
l 13.16 l Uppe r Journa l Bea ri ng 1 C2101-$GO-4 IVisual & Dimensional on l
I l____
I I
IBro Surface I
l l
RtMARKS/NOILS/LIC:
- 4) Visual for failed bolts - replace only
- 7) NDT per NB2500 Section i r bo th bo l ts on a n a s sy, ha ve ra i l ed.
til ASME Code.
- 3) UT, PI curvics, vi sua l and deg rada t i on, dimensional on bea ring and sea l surfaces.
- 6) Within a timo f rame not to exceed a t ime or 40,000 opera t ing hours.
~
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