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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl 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 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 ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML20058A7401990-10-19019 October 1990 Part 21 Rept Re Loose Motor Lead Connections on New Limitorque Motor Operators.List of Loose Connections Encl ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20138B1171985-12-0202 December 1985 Supplemental Part 21 Rept Re Lower Overrun Assemblies in Robertshaw Valves Installed on Diesel Generator Sets Possibly Failing Safe to Full Cooling Position. Cotter Pins Installed ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20102A6721985-02-0404 February 1985 Part 21 Rept Re Failure of post-tensioned Tendon on Plant. Investigation Revealed Another Tendon Anchor Cracked But Not Failed.Anchorages Furnished to Inryco by Western Concrete of California.Further Info Forthcoming W/Util Investigation ML20101P9361984-12-20020 December 1984 Part 21 Rept Re Fatigue Cracks on Fuel Injection Pump Delivery Valve Holders of PC-2 & PC-2.3 Emergency Diesel Generators.All Valve Holders W/Improper Radius Will Be Replaced ST-HL-AE-1141, Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors1984-09-14014 September 1984 Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified ML20010C6111981-08-14014 August 1981 Part 21 Rept Re Potential for Stress Corrosion Cracking of Anchor Bolts,Originally Reported on 810813.Utils That Have Plants for Which Vendor Has Supports & Restraints Design Responsibility Will Be Notified of Problem ML20010E2211981-05-26026 May 1981 Interim Deficiency Rept Re Vol Control Tank Level Instrumentation Control Sys Interaction W/Protection Sys, Initially Reported 810522.Plant Procedures Being Reviewed to Assure Operator Alert.Rept to Follow ML19345D4951980-12-0808 December 1980 Initial Deficiency Rept Re 800814 Hydrogen Dilution Fan 2B Trip.Caused by Blade Mounting Bolt Fracture.Fan Hubs & Blades Returned to Joy Mfg Co for Testing ML19332A0151980-08-20020 August 1980 Deficiency Evaluation Rept Re Westinghouse Centrifugal Charging Pump Operation Following Secondary Side High Energy Line Rupture.Design Change Implemented to Remove Safety Injection Initiation Closure Signal from Isolation Valves ML19330B7961980-07-22022 July 1980 Part 21 Rept Re GE Medium Voltage Penetrations.On 800620,air Inside Containment Found Escaping Through Three Penetration Modules Into Auxiliary Bldg.Testing Revealed Leakage Problem in All Six Medium Voltage Penetrations ML19318A0791980-06-13013 June 1980 Interim Deficiency Rept Re Unreacted Lime in Waste Settling Pond Causing Ph to Exceed Upper Limit.Caused by Discharge of Clarified Water Which Dissolved Calcium Sulfate Layer Over Lime.Discharge Terminated & Acid Will Be Added ML19320C4561980-06-13013 June 1980 Part 21 Rept Re Westinghouse Review of Safety Injection Termination Criteria Following Secondary Side High Energy Line Rupture W/Potential for Damage to Centrifugal Charging Pumps.Concerns Are Applicable to Facility ML19296C2941980-02-0505 February 1980 Deficiency Rept Re Undetectable Failures in Engineered Safety Features Actuation Sys.Util Will Incorporate Test Sequence Using Recommended Westinghouse Test Sequence. Design Change Will Permit Monitoring of Breaker Position ML19260D5581980-01-11011 January 1980 Deficiency Rept Re Discrepancies in ASME Code Sys.Cause Unstated.Valves Will Be Replaced or Upgraded to Class 2 by Obtaining Proper Documentation from Manufacturer ML19276E6801978-11-17017 November 1978 Deficiency Rept on 780620,0815 & 1016:potential Exists to Render Diesel Generator 1C & 1-2A Inoperable If Loss of Offsite Power or LOCA Occurs.Failure Could Leave Entire Plant W/No River Water Pumps Available 1997-09-30
[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 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 ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With 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 ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 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 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 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 L-99-020, Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 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 ML20205N0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 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 ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 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 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 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 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 ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) 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 ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20237A2181998-07-24024 July 1998 Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12 ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236M5981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20248M3121998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20247F3631998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20247E8851998-03-31031 March 1998 FNP Unit 2 Cycle 13 Colr ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20216D5941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20216D9811998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
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Alae w a 00w:r Corecany
, 500 Norin 19tn Street Post otSc3 Box 2541 Sirmin2 nam. Aaeama 33291 Te'ecnone 205 250 1000 F. L Ct.AYToN, JR.
senior v c. Presicent Alabama Power December 8, 1980 :ee scanen eecre sys:e Joseph M. Farley Nuclear Plant - Unit 2 Hydrogen Dilution Fan Blades File: A-35.62.81 Log: 80-2021 Mr. James P. O'Reilly U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement 101 Marietta Street, N.W. - Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Alabama Power Company sutrnits the attached deficiency (10CFR50.55(e)) evaluation report on the problem associated with the Hydrogen Dilution Fan Blades in the Joseph M. Farley Nuclecr Plant-Unit 2. The attached is also intended to meet reporting requirements of 10CFR Part 21.
This item was reported as a possible significant deficiency to Mr. M. D. Hunt, U.S. NRC, on September 24, 1980 and was reported as a s.ignificant deficiency to Mr. D. S. Price, U.S. NRC, on
= November 20, $980.
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7 _
Very truly yours, L. ay O FLC:WCP:sh Attachment 1
xc +
Attachment:
Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. W. H. Bradford Mr. D. S. Price Gd / Y S& /
8 012150A35 s
DEFICIENCY EVALUATION FOR HYDROGEN DILUTION FANS Initial Report to NRC:
On September 24, 1980 Mr. W. C. Petty, Jr., QA Manager-Design and Construction, reported to Mr. Milt Hunt of the NRC-Region II, that a potential significant deficiency existed concerning the reactor cavity hydrogen dilution fans at Joseph M. Farley Nuclear Plant - Unit 2.
On November 20, 1980 Mr. W. C. Petty, Jr. notified Mr. D. S. Price of the NRC-Region II that this problem was reportable as a significant deficiency.
Descriotion of Occurrence:
Reactor cavity hydrogen dilution fan 2B (Q2E22C0019-B) was initially energized and tested on August 10, 1980. The fan was subsequently started and stopped several times without incident from August 10 through August 13, 1980. On August 14, 1960, the fan was started and it later tripped on overload.
Investigation revealed a loose part in the fan when rotated by hand. Disassembly revealed a blade mounting bolt had fractured, allowing the blade to come Icae. .
Subsequently, after disassembly of the fan for blade replacement another bolt failed while being torqued to its recommended torque value. After the second failure, Alabama Power Company die penetrant checked the hubs and blades of the fans. No indications were found.
The blades and bolt are cast as a single assembly for Joy Manufacturing Company by a subvendor. The metal is poured into a ceramic mold that is supported by sand. The sand acts as a heat sink for the heat from the molten metal.
After a cooling period, the sand is removed from around the mold. The mold and metal are removed and the sand is reused. If the sand is not allov.ed a sufficient cooling time, when a new mold is poured, the slower cooling of the metal can produce a larger grain size in the material. Previously, blade failures have occurred in the shop testing of the fans. Modifications have been made to the foundry procedures to ensure the problem does not recur.
Technical Scecification and FSAR Requirements:
The technical specification requirement calls for two independent reactor cavity hydrogen dilution systems to be operable. With one reactor cavity hydrogen dilution system inoperable, restore the inoperable system to operable status
- within thirty days or be in HOT STANDBY within six hours.
Each system shall be demonstr a . operable at least once every 92 days on a staggered test basis by verif>c , system start from the control room and verifying system operation for at least 15 minutes.
The FSAR requirements for the reactor cavity hydrotan dilution systam are in Section 6.2. Section 5.2.5.1.4 states the system is designed for maintenance-free operation for a period of 100 days following a los of coolant accident.
o Deficiency Evaluation for Hydrogen Dilution Fans Page 2 r Engineering Evaluation:
Farley Nuclear Plant-Unit 2 is required to have two trains of the reactor cavity ,
hydrogen dilution system operable. Technical specifications allow thirty days '
for repair of a defective train.
A single failure in either the electrical system or a blade failure in the opposite train fan could contribute to a buildup of hydrogen within the reactor cavity. A spark from an electrical short or rther source could potentially ignite the hydrogen or cause the hydrogen to explode.
Therefore, it can be concluded that if the blade failure was to have remained uncorrected, it could have affected adversely the safety of the uparation of the nuclear plant at any time throughout the expected lifetime of the plant.
- The blade failure also represents a deviation from the performance specifications which will require extensive repair to meet the criteria and bases stated .in the Safety Analysis Report and to establish the adequacy of the component to perform its intended safety function.
Corrective Action:
The two fan hubs and blades were returned to Joy Manufacturing Company where overspeed tests at approximately 4300 rpm were successfully run.
Joy Manufacturing has stated the normal operating speed for this fan is 1770 rpm and that normal overspeed testing is 25% over operating speed.
The fans were reinstalled in Unit 2 on November 17, 1980 with all testing documentation on-site.
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