Similar Documents at Surry |
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LER-1978-034, Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends |
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!During a routine inspection on 10/27/78, it was noted that 17 spare process piping
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1containment penetrations on Unit 1 and 23 on Unit 2 were not capped in the Auxiliary [rn] !Building, although the inside ends were sealed.. This condition is less conservative.
[QJlJ 1than described in FSAR Section 5.2.
Upon review of the documentation, it was deter-
[)))) !mined on 11/1/78, that the condition was reportable in accordance with T.S.6.6.2.a.(9).I [I:0 !The health and safety of the public were not affected.
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The station intends to conform to FSAR. A design change (No. I [OJ] 179-01) has been approved to modify the penetrations by welding caps to their open ends. I o=IIJ IAt this time, the penetrations are not capped because of delays in receiving materials u:::8J !that are certified to conform with a Category 1 system.
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Cl
e Attachment (page 1 of 1)
Surry Power Station, Unit 1 Docket No:
50-280/50-281 Report No:
78-034/0lX-2 Event Date: 11-1-78 Updated Report - Previou~eport dated 12/13/78 Title of Report:
Spare Process Piping Penetrations
- 1.
Description of Event
During a routine inspection on 10/27/78, it was noted that 17 spare process piping containment penetrations on Unit 1 and 23 on Unit 2 had never been capped in the Auxiliary Building end.
The containment ends are capped.
The condition has existed since :the construction period, and is les$ conservative than described in FSAR Section 5.2.
Upon review, on 11/1/78, of the docu-mentation identifying the condition, it was determined that the condition was reportable in accordance with Technical Specification 6.6.2.a.(9).
This report is applicable to Surry 1 (Docket 50-280) and Surry Unit 2 (Docket 50-281).
- 2.
Probable Consequences/Status of Redundant Systems:
All spare penetrations are sealed on the inside (containment) ends of the penetrations.
There has been no compromise of containment integrity as evidenced by the fact the containment has experienced two ILRT tests and five years of operation with no indication of degradation of the inside caps.
Therefore, the health and safety of the public have not been affected.
- 3.
Cause
It appears that the outside ends of the penetrations were left uncapped at the completion of construction.
As of the present time, no analysis has reen found in files to rationalize a departure from the provisions of the FSAR even though the document has not been updated.
It must be assumed that the cap installation was overlooked.
- 4.
Immediate Corrective Action
An immediate inventory was conducted to verify the condition initially re-ported.
The Architect-Engineer was requested to advise on a method and procedures for correcting the condition.
- 5.
Subsequent Corrective Action:
Contrary to the date of completion specified by the previous LER (dated 12/13/78) the spare piping penetrations* are not:- yet capped. "Materials tµat have been received by the station and accepted by the station Quality Control Department are in the field to be installed.
The balance of the penetrations will be sealed upon receipt and acceptance of additional materials by the. -Quality Control- *Department.
- 6.
Actions Taken to Prevent Recurrence The situation described is a result of the construction process.
The pro-cedural controls now applicable to changes in facility configuration will preclude a recurrence.
- 7.
Generic Implications:
None LER:M2
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LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 | Submit Licensee Event Report Nos. 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LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded | Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded | | | 05000280/LER-1978-015, Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces | Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces | | | 05000280/LER-1978-016, Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening | Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening | | | 05000280/LER-1978-017, Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid | Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid | | | 05000280/LER-1978-018, Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required | Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required | | | 05000280/LER-1978-022-03, /03X-1 on 780726:Hydro Test Pump Failed to Build Up Pressure During Attempt to Fill Safety Injection Accumulators Due to Lifting of Its Relief Valve.Valve Replaced & Checked.Accumulator Refilled | /03X-1 on 780726:Hydro Test Pump Failed to Build Up Pressure During Attempt to Fill Safety Injection Accumulators Due to Lifting of Its Relief Valve.Valve Replaced & Checked.Accumulator Refilled | | | 05000280/LER-1978-022, Forwards LER 78-022/03X-1 | Forwards LER 78-022/03X-1 | | | 05000280/LER-1978-024, Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste | Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste | | | 05000280/LER-1978-027, Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria | Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria | | | 05000280/LER-1978-028-03, /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled | /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled | | | 05000280/LER-1978-028, Forwards LER 78-028/03L-0 | Forwards LER 78-028/03L-0 | | | 05000280/LER-1978-029-03, X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank | X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank | | | 05000280/LER-1978-029, Forwards LER 78-029/03L-0 | Forwards LER 78-029/03L-0 | | | 05000280/LER-1978-030, Forwards LER 78-030/03L-0, 78-031/03L-0, 78-032/03L-0, 78-033/03L-0 | Forwards LER 78-030/03L-0, 78-031/03L-0, 78-032/03L-0, 78-033/03L-0 | | | 05000280/LER-1978-030-03, /03L-0 on 781009:w/unit at Rated Pwr,Charging Pump Component Cooling Water Pump Btripped.Pump Tripped on Overcurrent.Caused by Corrosion Damage to Motor Bearings. Pump & Motor Rebuilt & Reinstalled | /03L-0 on 781009:w/unit at Rated Pwr,Charging Pump Component Cooling Water Pump Btripped.Pump Tripped on Overcurrent.Caused by Corrosion Damage to Motor Bearings. Pump & Motor Rebuilt & Reinstalled | | | 05000280/LER-1978-031-03, /03X-1 on 781001:during Normal Operation,Channel I Pressurizer Level (Protection) L-I-459 Drifted High.Caused by Drift of Electronic Zero Adjustment,In Conjunction W/ Leakage Thru Transmitter Bypass/Equalizing Valve | /03X-1 on 781001:during Normal Operation,Channel I Pressurizer Level (Protection) L-I-459 Drifted High.Caused by Drift of Electronic Zero Adjustment,In Conjunction W/ Leakage Thru Transmitter Bypass/Equalizing Valve | | | 05000280/LER-1978-031, Forwards LER 78-031/03X-1 & 78-038/03X-1 | Forwards LER 78-031/03X-1 & 78-038/03X-1 | | | 05000281/LER-1978-032, Forwards LER 78-032/03L-0 | Forwards LER 78-032/03L-0 | | | 05000280/LER-1978-032-03, /03L-0 on 781011:heat Tracing Circuit Faults Had Occurred as a Result of Boric Acid Incursion.Faults Repaired & Circuit Current Verified | /03L-0 on 781011:heat Tracing Circuit Faults Had Occurred as a Result of Boric Acid Incursion.Faults Repaired & Circuit Current Verified | | | 05000281/LER-1978-032-03, /03L-0:on 780921,heat Tracing Circuit Manual Boration/Boric acid-to-blender Failed.Caused by Boric Acid Penetration of Heat Tracing Tape Circuits.Heat Tracing Tape Replaced | /03L-0:on 780921,heat Tracing Circuit Manual Boration/Boric acid-to-blender Failed.Caused by Boric Acid Penetration of Heat Tracing Tape Circuits.Heat Tracing Tape Replaced | | | 05000281/LER-1978-033, Forwards LER 78-033/03L-0 | Forwards LER 78-033/03L-0 | | | 05000281/LER-1978-033-03, /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | | | 05000280/LER-1978-033-03, /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | | | 05000281/LER-1978-034-03, /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | | | 05000280/LER-1978-034-01, /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | | | 05000280/LER-1978-034, Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | | | 05000280/LER-1978-035, Forwards LER 78-035/01T-0 | Forwards LER 78-035/01T-0 | | | 05000281/LER-1978-035-03, /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | | | 05000280/LER-1978-035-01, /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | | | 05000280/LER-1978-036, Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | | | 05000280/LER-1978-036-03, /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | | | 05000281/LER-1978-036-03, /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | | | 05000281/LER-1978-036, Forwards LER 78-036/03L-0 | Forwards LER 78-036/03L-0 | | | 05000281/LER-1978-037, Forwards LER 78-037/03L-0 | Forwards LER 78-037/03L-0 | | | 05000280/LER-1978-037-03, /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | | | 05000281/LER-1978-037-03, /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | | | 05000281/LER-1978-038-03, /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | | | 05000280/LER-1978-038-03, /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | |
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