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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045D9071993-06-24024 June 1993 Special Rept:From 930511-0611,7 Fire Detectors in Circuit FLP3-3 Out of Svc for 32 Days.Caused by Failed Fire Detector.Detector Replaced & Containment Air Temps Monitored Hourly ML20044G5371993-05-28028 May 1993 Rev to 910925,1231 & 930731 Special Repts,Correcting Administrative Error in Equipment Designation of Passive Triaxial Peak Accelerograph.All Other Info Remains Unchanged ML20024H3011991-05-22022 May 1991 Special Rept:On 910412,loose Parts Detection Sys Declared Inoperable Due to Repetitive Spurious Alarms & Inoperable pre-amplifier Unit.Loose Parts Monitoring Troubleshooting Currently Under Review ML20043F8251990-06-0808 June 1990 Special Rept:On 890425,gas Sample Drawn from PASS Indicated Reactor Gases Not Removed from Liquid Sample Rcs.Four RCS Liquid Samples Successfully Obtained & Two of 4 Samples Produced RCS Dissolved Gas Samples ML20042G8911990-05-0707 May 1990 Special Rept:On 900408,pressurizer Spray Valve Failed Open Causing Depressurization of Rcs.Caused by Equipment Malfunction.Feedback Arm Holding Screw on Pressurizer Spray Valves Replaced W/Longer Screws & Secured W/Locknuts ML20006C2141990-01-23023 January 1990 Special Rept:On 900102,radiation Monitor Removed from Svc & 7-day Time Allowed Exceeded During Calibr.Replacement Detector on Order Since Nov 1989 & Will Be Replaced & Recalibr ML20005G1281990-01-0202 January 1990 Supplemental Special Rept:On 890716,2 of 12 Loose Parts Monitor Channels Declared Inoperable When Monitors Alarmed Continuously.Caused by Malfunctions in Equipment Inside Containment Bldg.Replacement Scheduled for Next Outage ML19351C7341989-12-11011 December 1989 Special Rept:On 891110,turbine Electrical Trip Solenoid Valve Failed to Meet Surveillance Acceptance Criteria. Caused by Particulate Contamination in Secondary or Electronic Trip Valves.Valves Replaced W/Rebuilt Valves ML20024D0251983-07-15015 July 1983 Ro:On 830421,following Preliminary Manual Test Insertion (Mti)Test,Actuation Module Lights Came on Due to Module Energizing.Cause Unknown.Operators Stationed to Mitigate Problems or Actuation If Mti Required ML20052D7771982-04-29029 April 1982 Ro:On 820415,steam Generator 1 Increased Primary to Secondary Leakage Rate of 0.049 Gpm from Valve.Cause of Leak Rate Unknown.Increase Appears to Be Related to Plant Shutdowns/Trips Experience in Thermal Cycling ML20050A0081982-03-18018 March 1982 RO Re Steam Generator Tube Plugging as Specified in Tech Spec 4.4.5.1.4.Degradation Resulting in Tube Plugging Is Characterized by Localized Areas of Small Pits on Tube Outside Diameter.Investigation of Corrosion Cause Continues ML20040F6091982-01-29029 January 1982 RO:30-day Rept & 10-day Rept Per App B ETS Re Excessive Liquid Waste Discharge & Excessive Level of Radioactivity.Caused by Steam Generator Primary Side to Secondary Side Leakage.Doses within Bases for 2.5 Ci Limit ML20039E0401981-12-28028 December 1981 RO 50-336/81-41:discovered Abnormal Degradation of Reactor Coolant Sys Pressure Boundary,Specifically,Steam Generator Tubes.Frequency of Occurrence Primarily on Cold Leg Side. Two-wk Rept Will Be Submitted ML19350F1331981-06-17017 June 1981 RO 50-336/81-20:Dresser Industries Model 31739A Safety Valves Found to Have Less than Min Upstream Inside Diameter. Caused by Facility Design.Significant Impact Unlikely ML20004E3611981-06-0505 June 1981 RO 81-018/03L-0:insp of safety-related Pipe Hangers Inside Containment Containing Mechanical Snubbers Revealed Snubbers Installed on Small Diameter Piping.Caused by Listing Not Including Review of Diameter Piping ML20003B6491981-02-17017 February 1981 RO 50-336/81-8:as-built Hanger Review of Reactor Vessel Head Vent Piping Sys Determined Spring Can Type Hanger Was Installed Incorrectly,Resulting in Overstressing Socket Welded Joint.Spring Can Hanger Removed ML20002D6361981-01-13013 January 1981 Ro:On 801209,inservice Insp Revealed That Required Valve Operability Tests Not Performed During Third Calendar Quarter 1980.Valves Successfully Tested.Action Taken to Assure Timely Review of Valve Test Data ML19330C0201980-08-0101 August 1980 RO 80-26:water Seal for Piping Penetration in Refueling Water Storage Tank Pipe Tunnel Does Not Meet Design Requirements.Plugged Yard Storm Drain Caused Water Backup. Repairs to Water Seal Will Be Evaluated ML19323C3571980-05-0909 May 1980 RO 50-336/80-18:during Ongoing Hanger Base Plate Analysis Required by IE Bulletin 79-02,discovered That Several Svc Water Support Hangers Did Not Provide Factor of Safety Greater than Two.Repair Work on 12 Hangers Is Underway ML19294B6771980-01-23023 January 1980 Ro:On 791229,loss of Main Control Board Annunciators Occurred.Fourteen Power Supplies That Are Paralleled to Provide Voltages for Annunciator Electronics,Lamps & Field Contacts Failed.Surveillance Implemented ML19275A2751979-09-25025 September 1979 RO 50-336/79-27:during Engineering Review,Section of 4-inch Cast Iron Floor Drain Piping Passing Each Station Battery Was Found Not Supported in Accordance W/Design.Drain Working & Ductwork Removed 1993-06-24
[Table view] Category:LER)
MONTHYEARML20045D9071993-06-24024 June 1993 Special Rept:From 930511-0611,7 Fire Detectors in Circuit FLP3-3 Out of Svc for 32 Days.Caused by Failed Fire Detector.Detector Replaced & Containment Air Temps Monitored Hourly ML20044G5371993-05-28028 May 1993 Rev to 910925,1231 & 930731 Special Repts,Correcting Administrative Error in Equipment Designation of Passive Triaxial Peak Accelerograph.All Other Info Remains Unchanged ML20024H3011991-05-22022 May 1991 Special Rept:On 910412,loose Parts Detection Sys Declared Inoperable Due to Repetitive Spurious Alarms & Inoperable pre-amplifier Unit.Loose Parts Monitoring Troubleshooting Currently Under Review ML20043F8251990-06-0808 June 1990 Special Rept:On 890425,gas Sample Drawn from PASS Indicated Reactor Gases Not Removed from Liquid Sample Rcs.Four RCS Liquid Samples Successfully Obtained & Two of 4 Samples Produced RCS Dissolved Gas Samples ML20042G8911990-05-0707 May 1990 Special Rept:On 900408,pressurizer Spray Valve Failed Open Causing Depressurization of Rcs.Caused by Equipment Malfunction.Feedback Arm Holding Screw on Pressurizer Spray Valves Replaced W/Longer Screws & Secured W/Locknuts ML20006C2141990-01-23023 January 1990 Special Rept:On 900102,radiation Monitor Removed from Svc & 7-day Time Allowed Exceeded During Calibr.Replacement Detector on Order Since Nov 1989 & Will Be Replaced & Recalibr ML20005G1281990-01-0202 January 1990 Supplemental Special Rept:On 890716,2 of 12 Loose Parts Monitor Channels Declared Inoperable When Monitors Alarmed Continuously.Caused by Malfunctions in Equipment Inside Containment Bldg.Replacement Scheduled for Next Outage ML19351C7341989-12-11011 December 1989 Special Rept:On 891110,turbine Electrical Trip Solenoid Valve Failed to Meet Surveillance Acceptance Criteria. Caused by Particulate Contamination in Secondary or Electronic Trip Valves.Valves Replaced W/Rebuilt Valves ML20024D0251983-07-15015 July 1983 Ro:On 830421,following Preliminary Manual Test Insertion (Mti)Test,Actuation Module Lights Came on Due to Module Energizing.Cause Unknown.Operators Stationed to Mitigate Problems or Actuation If Mti Required ML20052D7771982-04-29029 April 1982 Ro:On 820415,steam Generator 1 Increased Primary to Secondary Leakage Rate of 0.049 Gpm from Valve.Cause of Leak Rate Unknown.Increase Appears to Be Related to Plant Shutdowns/Trips Experience in Thermal Cycling ML20050A0081982-03-18018 March 1982 RO Re Steam Generator Tube Plugging as Specified in Tech Spec 4.4.5.1.4.Degradation Resulting in Tube Plugging Is Characterized by Localized Areas of Small Pits on Tube Outside Diameter.Investigation of Corrosion Cause Continues ML20040F6091982-01-29029 January 1982 RO:30-day Rept & 10-day Rept Per App B ETS Re Excessive Liquid Waste Discharge & Excessive Level of Radioactivity.Caused by Steam Generator Primary Side to Secondary Side Leakage.Doses within Bases for 2.5 Ci Limit ML20039E0401981-12-28028 December 1981 RO 50-336/81-41:discovered Abnormal Degradation of Reactor Coolant Sys Pressure Boundary,Specifically,Steam Generator Tubes.Frequency of Occurrence Primarily on Cold Leg Side. Two-wk Rept Will Be Submitted ML19350F1331981-06-17017 June 1981 RO 50-336/81-20:Dresser Industries Model 31739A Safety Valves Found to Have Less than Min Upstream Inside Diameter. Caused by Facility Design.Significant Impact Unlikely ML20004E3611981-06-0505 June 1981 RO 81-018/03L-0:insp of safety-related Pipe Hangers Inside Containment Containing Mechanical Snubbers Revealed Snubbers Installed on Small Diameter Piping.Caused by Listing Not Including Review of Diameter Piping ML20003B6491981-02-17017 February 1981 RO 50-336/81-8:as-built Hanger Review of Reactor Vessel Head Vent Piping Sys Determined Spring Can Type Hanger Was Installed Incorrectly,Resulting in Overstressing Socket Welded Joint.Spring Can Hanger Removed ML20002D6361981-01-13013 January 1981 Ro:On 801209,inservice Insp Revealed That Required Valve Operability Tests Not Performed During Third Calendar Quarter 1980.Valves Successfully Tested.Action Taken to Assure Timely Review of Valve Test Data ML19330C0201980-08-0101 August 1980 RO 80-26:water Seal for Piping Penetration in Refueling Water Storage Tank Pipe Tunnel Does Not Meet Design Requirements.Plugged Yard Storm Drain Caused Water Backup. Repairs to Water Seal Will Be Evaluated ML19323C3571980-05-0909 May 1980 RO 50-336/80-18:during Ongoing Hanger Base Plate Analysis Required by IE Bulletin 79-02,discovered That Several Svc Water Support Hangers Did Not Provide Factor of Safety Greater than Two.Repair Work on 12 Hangers Is Underway ML19294B6771980-01-23023 January 1980 Ro:On 791229,loss of Main Control Board Annunciators Occurred.Fourteen Power Supplies That Are Paralleled to Provide Voltages for Annunciator Electronics,Lamps & Field Contacts Failed.Surveillance Implemented ML19275A2751979-09-25025 September 1979 RO 50-336/79-27:during Engineering Review,Section of 4-inch Cast Iron Floor Drain Piping Passing Each Station Battery Was Found Not Supported in Accordance W/Design.Drain Working & Ductwork Removed 1993-06-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
Text
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June 5, 1981 MP-2-4804
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Mr. Boyce H. Grier f/d G G l! JUtl 11 ;gg4 1 Director, Region I - -
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission
%>iu. D . W~ AU 631 Park Avenue ' Q'b /
King of Prussia, Pennsylvania 19406
Reference:
Facility Operating License No. DPR-65 .
Docket No. 50-336 Reportable Occurrence R0-50-336/81-018/3L-0
Dear Mr. Grier:
This letter forwards Licensee Event Report 81-018/3L-0 required to be submitted within thirty days pursuant to Millstone Unit 2 Appendix A Technical Specifications, Section 6.9.1.9.b, conditions leading to operation in a degraded mode permitted by a limiting condition for operation. An additional three copies of the report are enclosed.
Yours truly, NORTHEAST NUCLEAR ENERGY COMPAN
/ W E. . Mroczka Station Superintendent -
Millstone Nuclear Power Station EJM/SS:ws
Attachment:
LER 81-018/3L-0 cc: Director, Office of Inspection and Enforcement, Washir.gton, D. C. (30)
Director, Office of Management Information and Program Control, Washington, D. C. (3) ,
U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D. C. 20555 81061200M S
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Page :1 of 2 ATTACHMENT TO LER #81-018/3L-0 Event description and probable consequences: i t
During a plant " Hot Standby" condition, dimensional inspection of safety related pipe hangers inside containment containing International Nuclear Safeguards Co. mechanical snubbers was being performed to obtain information for snubber changeout at the next cold shutdown. l This inspection revealed several INC mechanical snubbers installed on small diameter piping. These snubbers were determined to be safety related and had not previously been identified. Refer to Table I attached. !
Further review revealed that other mechanical snubbers, previously identified as seismic Class II, were safety related. Refer to Table II attached. A cold shutdown was initiated to allow snubber stroke testing and replacement as required. Refer to Tables I, II and III attached for a listing of snubbers 1 tested, test results and piping systems affected. No technical specification action statements were entered as a result of snubber testing and replacement.
Table IV attached is a summary of all the INC mechanical snubbers tested during this outage.
Discovery of the " Frozen" snubber condition questions the ability of the snubber to perform its design function, i.e. Allow pipe movement during changing thermal conditions and provide a restraining force during a seismic event. Also, the " Frozen" snubber may have produced unexpected loads on their respective piping systems during changing thermal conditions.
Cause description and corrective actions:
The previous listing of mechanical snubbers did not include a review of small diameter piping. Small diameter pipe was originally determined to be " Chart Hung" pipe, therefore, no snubbers would be installed. A review of safety related pipe stress problems indicates that several small diameter pipe systems were " Analyzed" designs containing snubbers. This review also revealed that other portions of piping systems containing mechanical snubbers previously determined to be non-safety related were in fact safety related.
All safety related piping stress problems were reviewed for mechanical snubber identification and listing. Most mechanical snubbers previously classified as non-safety related were reclassified as safety related. The plant was placed in a cold shutdown and all safety related mechanical snubbers inside and outside containment were stroke tested.
All snubbers that failed to stroke were replaced with mechanical snubbers manufactured by Pacific Scientific Company. Each piping system containing a frozen snubber was stress analyzed to determine the loads produced by the frozen snubber on the piping system as the system expanded or contracted due to -
changing thermal conditions. Several areas of possible overstress were identified. Subsequent inspection of these areas did not reveal any detrimental effects due to the frozen snubbers.
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. o Page 2 of 2 ATTACHMENT TO LER #81-010/3L-0 Long term corrective action includes replacement of all INC mechanical snubbers i installed on hangers that support safety related piping systems.
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. I Page 1 of 1 ATTACHMENT TO LER #81-018/3L-0 ,
TABLE I SMALL DIAMETER PIPE MECllANICAL SNUBBERS i INC ,
MODEL TEST DATE PIPING SNVBBER IDENT. * # RESULT SYSTEM FSK-M-02-024 DP.23 1 5/6/81 ACC Main Steam FSK-M-02-025 DP.125 1 5/6/81 ACC Main Steam FSK-M-02-025 DP.125 1 5/6/81 ACC Main Steam FSK-M-02-027 DP.190 1 5/6/81 ACC Main Steam FSK-M-02-026 DP.307 1 5/6/81 REJ Main Steam FSK-M-02-023 DP.158 1 5/6/81 ACC Main Steam FSK-M-02-022 DP.109 1 5/6/81 ACC Main Steam FSK-M-02-030 DP.253 1 5/6/81 ACC Main Steam FSK-M-02-022 DP.107 1 5/7/81 ACC Main Steam SK-M-1016 DP.215 1 5/7/61 ACC Main Steam SK-M-1016 DP.208 1 5/7/81 REJ Main Steam FSK-M-02-097 DP.402 1 5/13/81 REJ Main Steam FSK-M-17-095 DP.501 1 5/7/82 REJ CVCS FSK-M-17-095 DP.34 2 5/7/81 REJ CVCS ,
FSK-M-17-103 DP.411 1 5/6/81 ACC CVCS FSK-M-17-013 DP.38 1 5/11/81 ACC CVCS I
FSK-M-15-029 DP.537 1 5/7/81 ACC HPSI FSK-M-15-021 DP.781 1 5/7/81 ACC HPSI FSK-M-32-012 DP.152 1 5/7/81 REJ Reactor Coolant
- Snubbers S/N cre not available - Snubbers are identified by piping dwg. and data point.
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ATTACHMENT TO LER #81-018/3L-0
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TABLE II I
"NEW" SAFETY RELATED MECHANICAL SNUBBERS ,
INC '
HANGER INC MODEL TEST DATE
- S/N # RESULT PIPING SYSTEM 414001 002262 3 5/10/81 ACC Reactor Coolant Sys.
414001 002289 3 5/10/81 ACC Reactor' Coolant Sys.
414002 002271 3 5/10/81 ACC Reactor Coolant Sys. .
414002 002259 3 5/10/81 ACC Reactor Coolant Sys.
414006 61 2 5/10/81 ACC Reactor Coolant Sys.
414006 67 2. 5/10/81 ACC Reactor Coolant Sys.
414009 18229 3 5/10/81 ACC Reactor Coolant Sys.
414009 002251 3 5/10/81 ACC- Reactor Coolant Sys.
414016 59 2 5/10/81 REJ Reactor Coolant Sys.
414016 66 2 5/10/81 ACC Reactor Coolant Sys.
414018 270 1 5/10/81 ACC Reactor Coolant Sys.
414018 274 1 5/10/81 ACC Reactor Coolant Sys. ,
414021 88 2 5/10/81 ACC Reactor Coolant Sys.
414021 103 2 5/10/81 REJ Reactor Coolant Sys.
414024 68 2 5/10/81 REJ Reactor Coolant Sys.
414024 102 2 5/10/81 ACC Reactor Coolant Sys.
414025 415 2 5/10/81 ACC Reactor Coolant Sys.
414025 416 2 5/10/81 ACC Reactor Coolant Sys.
414027 81 2 5/10/81 ACC Reactor Coolant Sys.
414027 100 2 5/10/81 ACC Reactor Coolant Sys.
414029 76 2 5/9/81 ACC Reactor Coolant Sys.
414029 87 2 5/9/81 ACC Reactor Coolant Sys.
414029 88 2 5/9/81 ACC Reactor Coolant Sys.
414029 109 2 5/9/81 ACC Reactor Coolant Sys.
414032 80 2 5/9/81 REJ Reactor Coolant Sys. -
414032 101 2 5/9/81 ACC Reactor Coolant Sys.
414033 138 2 5/10/81 REJ Reactor Coolaat Sys.
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Page.? of 2 ATTACHMENT TO LER #81-018/3L-0 TABLE II "NEW" SAFETY RELATED MECHANICAL SNUBBERS INC HANGER INC MODEL TEST DATE i
- S/N # RESULT PIPING, SYSTEM 414033 N/A 2 5/30/81 REJ Reactor Coolant Sys.
414035 176 1 5/11/81 REJ Reactor Coolant Sys.
514001 002152 4 5/10/81 ACC Reactor Coolant Sys.
411003 002272 3 5/11/81 REJ Feedwater 411009 60 2 5/11/81 REJ Feedwater 411009 104 2 5/11/81 REJ Feedwater 411016 002264 3 5/11/81 REJ Feedwater 411045 54 2 5/11/81 REJ Feedwater - - - --
411045 64 2 5/11/81 ACC Feedwater 411062 105 2 5/11/81 REJ Feedwater 411062 72 2 5/11/81 REJ Feedwater 513008 147 1 5/11/81 REJ Main Steam 513036 625 1 5/11/81 REJ Main Steam 513040 .
141 2 5/11/81 ACC Main Steam 513041 272- 1 5/11/81 ACC Main Steam 513042 None 1 5/11/81 ACC Main Steam 60026 1502 2 5/11/81 REJ Feedwater 60025 001627 2 5/11/81 REJ Feedwater
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Page 1 of 2 ATTACHMENT TO LER #81-018/3L-0 TABLE III "0LD" SAFETY RELATED MECHANICAL SNUBBERS
. INC HANGER INC' ' MODEL TEST DATE :
- S/N # RESULT PIPING SYSTEM 310022 44 2 5/9/81 REJ Safety Injection 410007 42 2 5/9/81 ACC Safety Injection 410092 36 2 5/8/81 REJ Safety Injection 510004 107 2 5/9/81 REJ Safety Injection 507002 002257 3 5/9/81 REJ Safety Injection 507002 002253 3 5/9/81 REJ Safety Injection 408001 32 2 5/9/81 REJ Reactor Coolant Sys 408002 24 2 5/9/81 ACC Reactor Coolant Sys i 408002 33 2 5/9/81 ACC Reactor Coolant Sys 408003 22 2 5/9/81 ACC Reactor Coolant Sys 408003 19 2 5/9/81 ACC Reactor Coolant Sys 408004 2 5/9/81 REJ Reactor Coolant Sys 408004 1. L 1 5/9/81 REJ Reactor Coolant Sys 408005 83 2 5/9/81 ACC Reactor Coolant Sys
, 408005 94 2 5/9/81 ACC Reactor Coolant Sys 408009 21 2 5/10/81 ACC Reactor Coolant Sys 408009 20 2 5/10/81 ACC Reactor Coolant Sys 408009 140 2 5/10/81 ACC Reactor Coolant Sys 408010 38 2 5/10/81 ACC Reactor Coolant Sys 408010 47 2 5/10/81 ACC Reactor Coolant Sys 408010 48 2 5/10/81 ACC Reactor Coolant Sys 408010 120 2 5/10/81 ACC Reactor Coolant Sys 408011 28 2 5/10/81 ACC Reactor Coolant Sys 408011 30 2 5/10/81 ACC Reactor Coolant Sys 408012 40 2 5/10/81 ACC Reactor Coolant Sys 408012 46 2 5/10/81 ACC Reactor Coolant Sys 410037 37 2 5/8/81 ACC Reactor Coolant Sys
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l Page 2 of 2 ATTACHMENT TO LER #81-0183L-0 TABLE III .
"OLD" SAFETY HELATED MECHANICAL SNUBBERS INC HANGER INC MODEL TEST DATE
- S/N # RESULT PIPING SYSTEM i
410037 41 2 5/8/81 ACC React r Coolant Sys 410040 39 2 5/8/81 ACC Reactcc Coolant Sys 410046 27 2 5/8/81 REJ Reactor Coolant Sys 410049 45 2 5/8/81 ACC Reactor Coolant Sys 410054 34 3 5/8/81 ACC Reactor Coolant Sys 410059 002819 2 5/8/81 REJ Reactor Coolant Sys 410062 002260 3 5/7/81 REJ Shutdown Cooling 5/7/81. Shutdown Cooling 410062 002258 REJ 416016 160 1 5/9/81 ACC Containment Spray 416016 161 1 5/9/81 ACC Containment Spray 416021 162 1 5/9/81 ACC 3 Containment Spray 416022 165 1 5/9/81 ACC Containment Spray 416032 90 2 5/8/81 ACC Containment Spray 416032 71 2 5/8/81 .ACC Containment Spray 502035 002294 3 4/28/81 REJ LPSI/CS Common 502026 411 1 4/28/81 REJ LPSI/CS Common 402090 149 M 4/30/81 REJ LPSI/CS Common 402090 159 M 4/30/81 ACC LPSI/CS Common 402107 53 2 4/30/81 ACC LPSI/CS Common A
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, ATTACHMENT TO LER #81-018/3L-0 TABLE IV
SUMMARY
OF MECHANICAL. SNUBBER TESTING Total # of snubbers tested = 110 Total # of failures = 39 1 of 2 INC Model "M" failed to stroke 10 of 31 INC Model "1" failed to stroke 21 of 62 INC Model "2" failed to stroke 7 of 14 INC Model "3" failed to stroke 0 of 1 INC Model "4" failed to stroke ,
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