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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML20246F6301989-02-28028 February 1989 Auxiliary Feedwater Sys Overpressurization Event Engineering Evaluation Rept,Feb 1989 ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20154K8571988-08-24024 August 1988 Evaluation of Double Steam Line Break at Rancho Seco ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151U4851988-07-31031 July 1988 Power Ascension Mid-Term Assessment of Plant Operations & Maint & Scheduling Activities ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML20154M7381988-05-31031 May 1988 Assessment of Control Room Habitability Given Postulated Onsite Release of 20 Weight Percent Aqueous Ammonia ML20150F2941988-05-31031 May 1988 Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20147E5361988-03-0707 March 1988 Control Room/Technical Support Ctr Habitability Study, Aqueous Ammonia Concentrations ML20147C3751988-03-0101 March 1988 Procurement Engineering Assessment Plan,Interim Rept ML20151U0241988-02-29029 February 1988 Rev 5 to Final Wire & Cable Program Rept for Rancho Seco Nuclear Generating Station ML20147E5201988-02-29029 February 1988 Control Room/Technical Support Ctr Habitability Study, Radiological Dose Assessment ML20147E4991988-02-29029 February 1988 Methodology for Revised Control Room X/Q Determination for Rancho Seco Nuclear Station ML20148C7641988-02-24024 February 1988 Rev 1 to Future Plant Capacity Factor Engineering Assessment ML20147G4881988-02-11011 February 1988 Preliminary Rept Rancho Seco Piping Vibration Tdi Diesels a & B ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20148G2861988-01-31031 January 1988 Radioactive Liquid Effluent Sys Evaluation Using Program Liquid Effluent Based Operating Guides Rev II ML20149D3981988-01-19019 January 1988 Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Final Rept ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20147D3401987-12-31031 December 1987 Proposed Alarm Sys Mods NFPA 72D Compliance ML20148T1551987-12-31031 December 1987 Rev 4 to Wire & Cable Program Rept 1998-10-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed 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 ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML18094B3211990-02-28028 February 1990 Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML18094B1471989-10-25025 October 1989 Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML20248G8291989-10-0202 October 1989 Rev 19 to YOQAP-I-A, Operational QA Program ML19327C0681989-09-30030 September 1989 Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. 1999-08-13
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{ $. TROUBLESHOOTING ACTION PLAN
- ACTION LIST ITEM NUMBER 11b ACTION LIST DESCRIPTION SYSTEM RESPONSE. AUXILIARY FEEDWATER FWS-063 FWS-064 QUARANTINED EQUIPENT LIST ITEM NUMBER 12d RESPONSIBILITY OF Jim Field i PREPARED BY George Pactzun DATE: Januarv 4. 1986 DESCRIPTION OF ISSUE:
This action plan addresses the failure of the Auxiliary Feedwater to "A" Steam Generator Manual Isolation Valve, FWS-063, identified during the December 26, 1985 trip recovery. In addition this action plan provides for investigation of the 4
similar Auxiliary Feedwater to "B" Steam Generator Manual Isolation Valve, 3 FWS-064.
a FWS-063 and FWS-064 are normally locked open valves and were open prior to the transient. During the transient, operators were dispatched to manually close the upstream flow control valves, FV-20527 and FV-20528. Operators closed FV-20528, FV-20527 was stuck open. In an effort to reduce auxiliary feedwater flow the operator attempted to close FWS-063 with a large cheater. The valve remained stuck open.
SUP94ARY OF INFORMATION SUPPORTING PROBABLE CAUSE:
j l
) FWS-063 and FWS-064 are manually operated Velan pressure seal forged gate
] valves 6" in diameter rated for 900 psig service. Velan Engineering Companies Instruction Manual, VEZ-PS-3, applies to these valves. The Velan Manual i
l l states that excessive handwheel effort can indicate the following:
- a. Improperly lubricated or damaged valve stem. l
- b. Valve packing glad too tight.
1
- c. Faulty or damaged valve parts.
Based on maintenance history and vendor manual recommendations the following is l
i a list of probable causes for the FWS-063 failure:
- a. Failed yoke nut bearing.
- b. Valve packing to tight.
. c. Lack of stem / bearing / packing lubrication
- d. Failed valves internals.
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- TROUBLESHOOTING ACTION PLAN (continued)
REVIEW OF MAINTENANCE, SURVEILLANCE TESTING AND MODIFICATION HISTORY:
A review of maintenance history shows no maintenance has been performed on l
FWS-063 during the operational life of the plant.
I A maintenance history review of valves similar to FWS-063 was performed for
, the following valves. These manual valves are not covered in the present i Preventive Maintenance program. All of the valves are maintenance valves i and are locked open ASME XI Class E valves. No regular testing require-f ments are imposed on Class E locked valves.
t i FWS-064 AFW to B OTSG Manual Isolation l FWS-053 P-318 Pump Discharge Valve t
- FWS-054 P-319 Pump Discharge Valve FWS-119 AFW from P-319 Isolation to OTSG B i FWS-120 AFW From P-318 Isolation to OTSG A
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The attached work request history summary sheet details all documented work on
- the above valves. Two valves, FWS-064 and FWS-053, have had failures of the
[ yoke nut bearings causing the valves to stick in the open position. .
POTENTIAL ROOT CAUSE(s):
Theprimary.probablevalvefailurecauskisthefailedyokenutbearing.
Based on this primary hypothesis tne potential root cause is improper lubrication.
h Other potential root causes are improper valve packing maintenance, damaged valve
]
stem or faulty or damaged valve parts.
OUTLINE OF TROUBLESHOOTING PLAN:
The scope of this plan extends to only the yoke nut bearing and valve packing.
Based on the history of the similar valves this plan will concentrate on the -
yoke nut bearing.
I The objective of the troubleshooting plan is to find the root cause and correct the problem. The instructions for both FWS-063 and FWS-064 are identical.
- 1. Document as found conditions of the valve operator (limit to those conditions which can be recorded without changing conditions). Take photographs to assist in the documentation.
- 2. Attempt valve closure - measure closure torque (breakaway)
! (maximum 333 ft-lbf ) ;
) 3. Measure closing torque (if valve is free to move). ;
'I 4. Compare closing torque with design maximum.
] 5. Disassemble yoke nut assembly.
j 6. Inspect yoke nut bearing. .
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TROUBLESHOOTING ACTION PLAN (continued)
- 6. Determine root cause from evidence.
! 7. Replace yoke nut bearing per Manufacturers Inst'uction r Manual
- 8. Reassemble yoke nut housing per Manufacturers Instruction Manual l 9. Stroke valve and check operation of valve.
Y
- 10. Repack valve and lubricate stem.
! 11. Stroke valve and check operation of valve.
{ 12. Revise Troubleshooting Action Plan if required.
- 13. Perform breakaway torque measurement and fullstroke of valves FWS-053/054/119/120 I .
1 i
J APPROVED BY: DATE:
Action List Coordinator-SMUD h
j RELEASED FOR IPFLEENTATION BY:
i A .
1 DATE:
Action List Coordinator-SMUD .
1 i
+ . .
_ -m i WORK REQUEST HISTORY FWS-063 DATE REQUEST WORK PERFORMED 1
7/13/77 Clean stem and replace WR voided packing l 7/20/77 Clean stem and replace WR voided i packing
.l f
7/25/77 Clean stem and repack WR voided I FWS-064 h
12/13/74 Packing leak Adjusted packing 3;i 5
7/13/77 Clean stem and replace WR voided packing 2/20/80 Valve will not close Replaced operator bearings, manually frozen in open did not open up system position.
t 2/2/83 Packing leak -
. Void duplicate WR -
l t 2/5/83 Tighten packing before Adjusted packing and stroked.
secondary side hydro FWS-053 11/20/79 Can't stoke valve closed Inspected valve, disassembled upper manually per SP 210.01A yoke bearing group.
Noted rust & seized thrust bearing &
bushings. Cleaned and dressed bearing registers and bushing. Installed new thrust bearing, packed assembly with grease and reassembled yoke. Stroked satisfactory.
FWS-054 None
)
j FHS-119 None FWS-120 1
None l
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l 1
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