|
|---|
Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML20204D7271999-03-15015 March 1999
ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1
ML20237A2181998-07-24024 July 1998
Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12
ML20216E9471997-05-30030 May 1997
Rev 0 to Updated ISI Program for ASME Code Class 1,2 & 3 Components. W/154 Oversize Drawings
ML20216E9421997-05-30030 May 1997
Rev 0 to Third 10-YR ISI Program for ASME Code Class 1,2 & 3 Components
ML20149K0731997-04-10010 April 1997
Form NIS-2 Owner'S Rept for Repairs or Replacements
ML20077M9561991-08-0202 August 1991
Interval 2,Period 1,Outage 3 Inservice Insp Rept of Jm Farley Unit 1
ML20248J2191989-10-0505 October 1989
Errata to Interval 1,Period 3,Outage 1 Inservice Insp Rept of Jm Farley Nuclear Plant,Unit 2
ML20245J3581989-07-24024 July 1989
Interval 1,Period 3,Outage 1 Inservice Insp Rept of Jm Farley Nuclear Power Plant,Unit 2
ML20153D6601988-05-31031 May 1988
Jm Farley Unit 1 Interval 2,Period 1,Outage 1 Inservice Insp of Outlet Nozzle to Shell Weld 21:Recordable Indications Acceptable to Allowable Stds of ASME Section XI & Requiring Supplemental Investigation..
ML20153D6521988-05-31031 May 1988
Jm Farley Unit 1 Interval 2,Period 1,Outage 1 Inservice Insp of Outlet Nozzle to Shell Weld 21:Recordable Indications Which Exceed Allowable Stds of ASME Section XI
ML20196G3631988-02-15015 February 1988
Interval 1,Period 2,Outage 3 Inservice Insp Rept for Jm Farley Nuclear Plant Unit 2
ML19321B3151980-07-25025 July 1980
Inservice Insp Program for Class 1,2 & 3 Components.
1999-03-15
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999
Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs
ML20217G0361999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20216E4941999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Jmfnp.With
ML20212E7451999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With
ML20211B8931999-08-17017 August 1999
Safety Evaluation Supporting Amend 143 to License NPF-2
ML20210T2161999-08-0606 August 1999
Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant
ML20211B2011999-08-0404 August 1999
Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers
ML20210R6031999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
05000364/LER-1999-001-05, :on 990621,plant Was Manually Tripped Due to Decreasing Vacuum in Condenser.Caused by Broken Steam Dump Drain Line.Broken Section of Line Was Repaired & Licensee Will Implement Addl Design Change1999-07-0202 July 1999
- on 990621,plant Was Manually Tripped Due to Decreasing Vacuum in Condenser.Caused by Broken Steam Dump Drain Line.Broken Section of Line Was Repaired & Licensee Will Implement Addl Design Change
ML20196J3791999-06-30030 June 1999
Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable
L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20209G0661999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
05000348/LER-1999-002-02, :on 990527,Unit 1 Reactor Trip Occurred Following Loss of 1A SG Feedwater Pump.Caused by Personnel Error.Unit Was Stabilized in Hot Standby.With1999-06-25025 June 1999
- on 990527,Unit 1 Reactor Trip Occurred Following Loss of 1A SG Feedwater Pump.Caused by Personnel Error.Unit Was Stabilized in Hot Standby.With
L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with
ML20206L4551999-05-10010 May 1999
Safety Evaluation Supporting Amends 142 & 134 to Licenses NPF-2 & NPF-8,respectively
ML20206G7471999-05-0404 May 1999
Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07
ML20206C9461999-04-30030 April 1999
1:Final Cycle 16 Freespan ODSCC Operational Assessment
L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20204D4391999-03-31031 March 1999
Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept
ML20204D7271999-03-15015 March 1999
ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1
ML20207M6421999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20203J0631999-02-19019 February 1999
Safety Evaluation Supporting Amends 107 & 85 to Licenses NPF-2 & NPF-8,respectively
ML20203A2651999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
05000348/LER-1998-008-01, :on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With1999-01-18018 January 1999
- on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With
ML20199D8611999-01-12012 January 1999
SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2
ML20206C8081998-12-31031 December 1998
Alabama Power 1998 Annual Rept
ML20199E6591998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
05000348/LER-1998-007-02, :on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required1998-12-22022 December 1998
- on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required
05000348/LER-1998-006-03, :on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met1998-12-18018 December 1998
- on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met
ML20198K4091998-12-18018 December 1998
COLR for Jm Farley,Unit 1 Cycle 16
05000364/LER-1998-007-01, :on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With1998-12-11011 December 1998
- on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With
ML20198B2561998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20195E2281998-11-16016 November 1998
Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1
05000348/LER-1998-005-03, :on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With1998-11-12012 November 1998
- on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With
ML20195C9681998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20155E0271998-10-29029 October 1998
SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04
NUREG-1407, Safety Evaluation Accepting IPEEE for Severe Accident Vulnerabilities,Per GL 88-20 & NUREG-14071998-10-0101 October 1998
Safety Evaluation Accepting IPEEE for Severe Accident Vulnerabilities,Per GL 88-20 & NUREG-1407
ML20154B6121998-10-0101 October 1998
Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1
ML20154H0121998-09-30030 September 1998
Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion)
ML20154H6001998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20151V8341998-09-30030 September 1998
Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change
05000348/LER-1998-004-03, :on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With1998-09-28028 September 1998
- on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With
05000348/LER-1998-003-04, :on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With1998-09-11011 September 1998
- on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With
05000348/LER-1997-003, :on 970315,determined That TS SR 4.5.3.2 Had Not Been Performed,Per Operating Procedure.Caused by Personnel Error.Verified That RHR Discharge to Charging Pump Suction MOVs 8706A & 8706B Were Closed.With1998-09-0808 September 1998
- on 970315,determined That TS SR 4.5.3.2 Had Not Been Performed,Per Operating Procedure.Caused by Personnel Error.Verified That RHR Discharge to Charging Pump Suction MOVs 8706A & 8706B Were Closed.With
05000348/LER-1998-005, :on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures1998-09-0303 September 1998
- on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures
05000348/LER-1998-002-05, :on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced1998-09-0303 September 1998
- on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced
ML20197C8991998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20237C5471998-08-20020 August 1998
Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only
ML20237B1891998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2
ML20236Y1121998-07-31031 July 1998
Voltage-Based Repair Criteria 90-Day Rept
1999-09-30
[Table view] |
Text
. . _ . . _ - - . -
F;rm N12-2 Own:r's R: port Fcr R: pairs Or R:plictm:nts RType: L1.52 As Required By Tha Provisions Of The ASME Code Stetion XI E11-DCP-8966-01 '1 2
- 1. Owner 2 Pient und
, southern Nuclear Operating Co. Farley Nuclear Plant FNP2
, 40 inverness Center Parkway Highway 95 south Birmingham, Alabama 35242 Columbia, Alabama 36319 o,,,
(as agent for Alabama Power Co.)
3 Work P ^ ..e By 03-19.97 Type Coon Symoot Stamp Name:
Southern Nuclear Operating Company - Plant Modifications N/A Aoinoruon Nomo.,
Address: Highway 95 South N/A Expraten Date Columbia, AL 36319 N/A 4 60ent<caten Of System RESIDUAL HEAT REMOVAL SYSTEM ,
s m Appm con.irucion c* Emen ASME ill 71 SUM 71 ^*a" N/A ce c=
m Apucam. secten xi utered ror Repare or Repiscemeni.
1o 83 Eddon SUM 83 - ^*"" N/A cmc-6 loontdcalion of Com,~.-4s Repared or R-i---2 and R-. ent coms e.
Name of Name of Manufacturer Natonal Component other Year Repewed ASME Coco Manufacturer senalNo Board No identicaten Bull Repieced or Stamped Rep 6acement (Yes or No)
Seal MR 81102 I A %8 Pu np p y Q2EllP00l A 1995 Replacement Yes Seal 94P-10265 927 p y Q2EllP001B 1994 Replacement Yes Cardinal Industrial Stud, Main lleat# 37388 NA Producu P.O. QP941264 1994 Replacement No Flange Seal 8"
Pu p o ay 94P-10266 928 Q2EllP001 A 1994 Replaced Yes seal 93P-10792 911 p p Q2 Ell?001B 1993 Replaced Yes Stud pu n incat# 502284 NA p y Q2EllP001A 1993 Replaced No
- 7. Descnpien of Work The 2A and 2B RHR Pumps were modified per DCP S95-2-8966. Replacement seals were installed in the pumps following impeller replacement. One damaged casing stud was replaced on the 2A RHR Pump. The seals were replaced per Work Orders 75736 and 75738. The stud was replaced per Work Order 75736.
8 Tests Conducted Hydrostatic Pneumats X Nominal Operating F*assurf None Other Pressure 170 PSI Test Temp *F Ambient Nts-2 002 9707290234 970723 PDR ADOCK 05000364 C G PDR _
_ ._ . ,_. ..~ - - - - - - ..
F:rm NIS 2 OwnIr's R: port Fcr R:p: Irs Or R:plic ments RType: L1.52
. **""*' Shnt of E11-DCP-8966-01 2 2 e Remaras (AppicatHe Manufacturers Dale Reports To Be Aitached) e
, The rep'lacement seal for the 2A RHR Pump was purchased per Purchase Order (PO) OP941692 and issued per Material Issue Form (MIF) %048768.
e The replacement seal for the 28 RHR Pump was purchased per PO QP93-1439 and issued per MIF 96048017. !
e The replacement stud for the 2A RHR Pump was purchased per PO QP941264 and issued per MIF 96048942.
Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of ASME Code,Section XI. repas or repucement Type Code Symbol Stamp NA Certificate of Authonzation No- NA Expiration Date NA Sened k [M .5 %% Date 4lN 9~) ,19 9 ~)
opr or o.nor. co.- u. - 1 Certificate of inservice inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vesselinspectors and the State or Province of Ap eews and Employed by ma,eg7 sh __ Cam (b of uthem sess& wrvW have inspected the components described in this Owners Report dunng the pened s/n g-f to , and state that e/.r/r1 to the best of my knowledge and belief, the Owner' has' performed examinations and taken c6rrefetive measures desenbed in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be hable in any manner for any personalinjury or property damage or a Icss of any kind arising from or connected with this inspection.
// [
Aspectors Sgnature Commissions g yy [
Natonal Board. State Provoce and Enoursements Date yf/p 19 f ~7 Nis-2 002
