LER-1981-005, /01T-0:on 810318,four Closure Studs on Reactor Coolant Pump 2A2 Had Corrosion Wastage in Pump Closure Area. Caused by Leakage from Pump Closure Gaskets.Stud 20 Replaced.Studs 1,2 & 3 Left in Place |
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DUKE POWER COMPANY OCONEE UNIT 2 i
i Report Number: 'RO-270/81-05 Report Date: April 1,.1981 Occurrence Date: March 18, 1981 i
Facility: Oconee: Unit 2, Seneca, South Carolina Identification of Occurrence: Apparent Corrosion Wastage of Reacter Coolant Pump Closure Studs Conditions Prior to Occurrence: Cold Shutdown to Inspect and Repair 2B1 RCP i
Motor Description of Occurrence:
(
18, 1981, it was discovered that four At approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on March closure studs on Reactor Coolant Pump (RCP) 2A2 had apparent corrosion wastage in the pump closure area. This pump is located in the Reactor Building inside the secondary shield wall area. This constitutes unusual degradation of the RC pressure boundary and is thus reportable pursuant to Technical Specification
- 6. 6. 2.1.a (3).
The apparent corrosion wastage has been occurring due to closure gasket leakage.
Since the unit was at cold shutdown at the., time of discovery, no immediate corrective action was necessary. The incident has been reviewed with regard to 10CFR 21, and it has been determined that this event is not reportable pursuant to 10CFR 21.
The corrosion wastage that has occurred.has been confine' f r tie most part to the closure studs within the closure area. This cerzosior, ir2 % lieved to be i
caused by a slight amount of leakage from the pump's closure. -
tets..The leakage from the 2A2 pump was enough to visually observe.
Fot.
injection taps were installed into the casing.
These were used to inject a material into the, annulus above the upper closure gasket to slow the leakage rate. This work was performed by the Furmanite Company.
The Unit 2 RCP's are manufactured by Bingham Willamette Company and are type RQV, size 28x28x41, single. stage quad volute pumps. The closure stads and nuts are made from a low alloy carbon steel. The pump casing is made frei 304 stain-less steel where the studs, thread into the pump. The motor stand. flange is made of forged carbon steel. The closure studs are tensioned using a Diamond Power stud tensioner to a pull of 440,000 pounds per stud. The studs are approximately 32 inches long and have 4"-8 threads. The unthreaded shank portion of the studs should be 3.836 to 3.846 inches in diameter.
The inspection that was accomplished on all studs for Unit 2 RCP's consisted of dimensional checks using an O. D. Micrometer and a U. T. measurement through the l
8107200332 810401 A
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diameter of the stud.
Because of the way the pump vas designed and built, a dimensional check utilizing an O. D. Micrometer could only be accomplished tangentially relative to the pump center line. Because an accurate dimen-sional check requires checking the diameter in at least two places, each stud was rechecked using a UT instrument. This was done in a normal direction relative to the pump centerline or looking in towards the center of the pump.
Apparent Cause of Occurrence:
The apparent cause of this incident is the result of a small enount of leakage from the pump's closure gaskets.
Analysis of Occurrence:
Evaluation revealed no stress concerns for continued operation by leaving stud numbers 1, 2, and 3 in place. Also, leakage is not considered a con-cern although it could change slightly, i.e., gasket surfaces shot ld be un-affected. Based on Babcock & Wilcox's recommendation, continued operation of the unit poses no threat to the health and safety of the public.
Corrective Action
Because Unit 2 was at cold shutdown at the time of the disco',ry of this incident, no immediate corrective action was required to lessen the con-sequences of the incident or to stabilize the prob?em.
Stud number 20 was removed and replaced.
Stud number 3 was retensioned, and stud numbers 1 and 2 were to be left in place. The situation was evaluated, and it was determined to be acceptable to leave stud numbers 1, 2, and 3 in place.
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Stud number 20 was removed and replaced.
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m i number 3 t.as retensioned, stud numbers 1 and 2 were left in place.
yl Evaluation revealed that it was acceptable to leave studs 1, 2, and 3 in l
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Caused by Leakage from Pump Closure Gaskets.Stud 20 Replaced.Studs 1,2 & 3 Left in Place | /01T-0:on 810318,four Closure Studs on Reactor Coolant Pump 2A2 Had Corrosion Wastage in Pump Closure Area. Caused by Leakage from Pump Closure Gaskets.Stud 20 Replaced.Studs 1,2 & 3 Left in Place | | | 05000270/LER-1981-006, Forwards LER 81-006/03L-0.Detailed Event Analysis Encl | Forwards LER 81-006/03L-0.Detailed Event Analysis Encl | | | 05000270/LER-1981-006-03, /03L-0:on 810409,valve 2PR-8 Failed to Open During on-line Insp.Caused by Faulty Valve Operator Diaphragm.Valve Repaired & Verified Operable | /03L-0:on 810409,valve 2PR-8 Failed to Open During on-line Insp.Caused by Faulty Valve Operator Diaphragm.Valve Repaired & Verified Operable | | | 05000287/LER-1981-006, Forwards LER 81-006/03X-1.Detailed Event Analysis Encl | Forwards LER 81-006/03X-1.Detailed Event Analysis Encl | | | 05000287/LER-1981-006-03, /03X-1:on 810324,reactor Protection Sys Channel a High Pressure Trip Found Out of Calibr.Caused by Transmitter Drift.Pressure Transmitter Recalibr | /03X-1:on 810324,reactor Protection Sys Channel a High Pressure Trip Found Out of Calibr.Caused by Transmitter Drift.Pressure Transmitter Recalibr | | | 05000269/LER-1981-006, Forwards LER 81-006/03L-0.Detailed Event Analysis Encl | Forwards LER 81-006/03L-0.Detailed Event Analysis Encl | | | 05000269/LER-1981-006-03, /03L-0:on 810328,RCS Subcooling Margin Monitors Were Discovered Inoperable When Computer Alarm Printer & Rider in Control Room Indicated All Analog Points in Alarm Condition.Caused by Failed Low Level Amplifier | /03L-0:on 810328,RCS Subcooling Margin Monitors Were Discovered Inoperable When Computer Alarm Printer & Rider in Control Room Indicated All Analog Points in Alarm Condition.Caused by Failed Low Level Amplifier | | | 05000269/LER-1981-007-01, /01T-0:on 810410,fire Barrier Door for West Penetration Room Was Inoperable W/O Proper Fire Watches Maintained.Caused by Personnel Error.Individual Involved Counseled Re Importance of Communication | /01T-0:on 810410,fire Barrier Door for West Penetration Room Was Inoperable W/O Proper Fire Watches Maintained.Caused by Personnel Error.Individual Involved Counseled Re Importance of Communication | | | 05000269/LER-1981-007, Forwards LER 81-007/01T-0.Detailed Event Analysis Encl | Forwards LER 81-007/01T-0.Detailed Event Analysis Encl | | | 05000287/LER-1981-007, Forwards LER 81-007/03L-0.Detailed Event Analysis Encl | Forwards LER 81-007/03L-0.Detailed Event Analysis Encl | | | 05000270/LER-1981-007, Forwards LER 81-007/01T-0.Detailed Event Analysis Encl | Forwards LER 81-007/01T-0.Detailed Event Analysis Encl | | | 05000287/LER-1981-007-03, /03L-0:on 810329,inner Door Seal of Reactor Bldg Personnel Lock Found to Leak at Rate Greater than That Allowed by Procedure.Caused by Faulty Installation of Strong Backs.Gasket Shinned & Strong Backs Reinstalled | /03L-0:on 810329,inner Door Seal of Reactor Bldg Personnel Lock Found to Leak at Rate Greater than That Allowed by Procedure.Caused by Faulty Installation of Strong Backs.Gasket Shinned & Strong Backs Reinstalled | | | 05000270/LER-1981-007-01, /01T-0:on 810326,during Periodic Test,Auto/Manual Transfer Switches for B1T-8 & B2T-5 Incorrectly Placed in Manual Position & Not Returned After Test Completion.Caused by Personnel Error.Switches Restored to Auto Position | /01T-0:on 810326,during Periodic Test,Auto/Manual Transfer Switches for B1T-8 & B2T-5 Incorrectly Placed in Manual Position & Not Returned After Test Completion.Caused by Personnel Error.Switches Restored to Auto Position | | | 05000287/LER-1981-008-03, /03L-0:on 810422,during Seismic Block Wall Insp, Discovered Breach of Fire Barrier in Penetration 3-T-T-1. 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Control Cable Replaced & Valve Electrically Cycled | | | 05000270/LER-1981-008-03, /03L-0:on 810508,solenoid Valve for 2FDW-316 Stuck in Manual Position,Disabling Automatic Level Control of B Steam Generator from Emergency Feedwater Sys.Valve Replaced Per Procedure | /03L-0:on 810508,solenoid Valve for 2FDW-316 Stuck in Manual Position,Disabling Automatic Level Control of B Steam Generator from Emergency Feedwater Sys.Valve Replaced Per Procedure | | | 05000287/LER-1981-008, Forwards LER 81-008/03L-0.Detailed Event Analysis Encl | Forwards LER 81-008/03L-0.Detailed Event Analysis Encl | | | 05000270/LER-1981-008, Forwards LER 81-008/03L-0.Detailed Event Analysis Encl | Forwards LER 81-008/03L-0.Detailed Event Analysis Encl | | | 05000269/LER-1981-008, Forwards LER 81-008/01T-0.Detailed Event Analysis Encl | Forwards LER 81-008/01T-0.Detailed Event Analysis Encl | | | 05000269/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Analysis Encl | Forwards LER 81-009/03L-0.Detailed Analysis Encl | | | 05000287/LER-1981-009-03, /03L-0:on 810507,containment Isolation Valve 3CS-6 Was Discovered in Intermediate Position,Resulting in Loss of Containment Integrity.Cause Undetermined.Valve 3CS-6 Verified Operable | /03L-0:on 810507,containment Isolation Valve 3CS-6 Was Discovered in Intermediate Position,Resulting in Loss of Containment Integrity.Cause Undetermined.Valve 3CS-6 Verified Operable | | | 05000269/LER-1981-009-03, /03L-0:on 810622,during Normal Operations,Startup Transformer CT-1 Locked Out.Cause Not stated.CT-1 Transformer & Bus Work Checked & Protective Relaying Checked for Malfunction Prior to Return to Svc | /03L-0:on 810622,during Normal Operations,Startup Transformer CT-1 Locked Out.Cause Not stated.CT-1 Transformer & Bus Work Checked & Protective Relaying Checked for Malfunction Prior to Return to Svc | | | 05000270/LER-1981-009-03, /03L-0:on 810415,during Low Pressure Svc Water Pump Periodic Test,Valves 2LPSW-19 & 2LPSW-21 Were Closed Resulting in RB Rbcu Being Out of Svc.Caused by Personnel Error.Valve 2LPSW-19 Opened & Personnel Counseled | /03L-0:on 810415,during Low Pressure Svc Water Pump Periodic Test,Valves 2LPSW-19 & 2LPSW-21 Were Closed Resulting in RB Rbcu Being Out of Svc.Caused by Personnel Error.Valve 2LPSW-19 Opened & Personnel Counseled | | | 05000287/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Encl | Forwards LER 81-009/03L-0.Detailed Event Analysis Encl | | | 05000287/LER-1981-010-03, /03L-0:on 810517,broken Airline to Valve 3LPSW-525 Was Discovered.Caused by Breakage of Brass Nipple Between Air Supply Isolation Valve & Accumulator Tank.Brass Nipple Replaced | /03L-0:on 810517,broken Airline to Valve 3LPSW-525 Was Discovered.Caused by Breakage of Brass Nipple Between Air Supply Isolation Valve & Accumulator Tank.Brass Nipple Replaced | | | 05000269/LER-1981-010-03, /03L-0:on 810602,turbine Driven Emergency Feedwater Pump Declared Inoperable.Caused by Governor Valve Sticking in Open Position Due to Sys Contamination.Linkage Pin Removed,Governor Valve Freed & Stem Cleaned | /03L-0:on 810602,turbine Driven Emergency Feedwater Pump Declared Inoperable.Caused by Governor Valve Sticking in Open Position Due to Sys Contamination.Linkage Pin Removed,Governor Valve Freed & Stem Cleaned | | | 05000269/LER-1981-010, Forwards LER 81-010/03L-0.Detailed Event Analysis Encl | Forwards LER 81-010/03L-0.Detailed Event Analysis Encl | |
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