LER-1978-030, Forwards LER 78-030/03L-0 |
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| 2981978030R00 - NRC Website |
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Ji CoOPcR NUCLEAR STATION P.O. BOX 98 BROWNVILLE, NEBRASKA 68321 Nebraska Pubh.c Power D. tn. t 1cLcPsoNe <4023823 3 i>
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September 12, 1978 Mr. K. V. Seyfrit U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Suite 1000 Arlington, Texas 76011
Dear Sir:
This report is submitted in accordance with Section 6.7.2.B.2 of the Technical Specifications for Cooper Nuclear Station and discusses a reportable occurrence that was discovered on August 15, 1978. A li-consee event report form is also enclosed.
Report No.:
50-298-78-30 Report Date:
September 12, 1978 Occurrence Date: August 15, 1978 Facility:
Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:
A condition was discovered which could lead to operation in a degraded mode due to not meeting the surveillance requirements of Section 4.7.A.2.f of the Technical Specifications.
Conditions Prior to Occurrence:
Reactor was at steady state power level of approximately 95% of rated thermal power.
Description of Occurrence:
While reviewing the drawings of the drywell, thirteen (13) primary containment testable penetrations were identified which had not i
been previously noted and have not been leak tested as required by Technical Specification 4.7.A.2.f.
These penetrations are X-35A thru E (TIP penetrations) and eight (8) drywell stabilizer assembly inspection ports.
Designation of Apparent Cause of Occurrence:
The cause of these penetrations not being tested was that they were overlooked when the preoperational test was performed. The preop-erational test data was used as a base in preparation of the surveil-lance test and therefore these penetrations were not included in the inspection program.
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787030 o/73
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Mr. K. V. Seyfrit September 12, 1978 Page 2.
Analysis of Occurrence:
Penetrations X-35A thru E are used for the TIP piping to enter the d rywell.
The double 0-ring is around the outside of the flange and provides a seal between the penetration, a 2" line, and the atmosphere.
If these seals were leaking, they could allow leakage from the drywell to the atmosphere.
The eight (8) stabilizer assembly inspection ports are 16" 0.D. and are located around the perimeter of the drywell at elevation 961'10-3/4".
They are for inspection of the drywell stabilizer connections from inside the drywell. A leak from these penetrations would be from the drywell to the area between the drywell and the concrete, and eventually to atmosphere.
None of the penetrations have been opened since the last integrated leak rate test.
There has been no evidence of deterioration in the sealing material of other penetrations that were opened. Based on this fact, leakage from these penetrations would have been included during the last integrated leak rate test.
The results of this test were within acceptable limits.
This occurrence presents no adverse consequences from the standpoint of public health and safety.
Corrective Action
At the time the occurrence was noted all records were reviewed to determine if these penetrations had ever been opened. All checks were negative. All previous leak tests and the preoperational test were reviewed and indicated these penetrations had not been tested.
Penetration X-35A thru E were checked for external leakage by soap bubble inspection and no leaks were identified.
Due to location and radiation levels in the TIP area, it was prudent not to leak test between the seals while operating.
The thirteen (13) penetrations have been added to the procedure for local leak rate testing (S.P. 6.3.1.1) and a revision to Table 3.7.2 of the Technical Specifications has been initiated.
These penetrations will be leak tested at the first available opportunity.
Sincerely, L. C. Lessor i
Station Superintendent Cooper Nuclear Station LCL:cg Attach.
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| 05000298/LER-1978-029-03, /03L-0:on 780814,core Spray Time Delay Relay Did Not Operate within Required Time Frame.Caused by Type of Relay Used & Inactivity After Repairs.Design Change Will Be Prepared to Replace Relay | /03L-0:on 780814,core Spray Time Delay Relay Did Not Operate within Required Time Frame.Caused by Type of Relay Used & Inactivity After Repairs.Design Change Will Be Prepared to Replace Relay | | | 05000298/LER-1978-029, Forwards LER 78-029/03L-0 | Forwards LER 78-029/03L-0 | | | 05000298/LER-1978-030-03, /03L-0:on 780815,13 Primary Containment Penetrations Not Leak Tested.Caused by Penetrations Not Identified During Preoperational Testing.Penetrations Will Be Added to Tech Spec Table 3.7.2 & Will Be Tested | /03L-0:on 780815,13 Primary Containment Penetrations Not Leak Tested.Caused by Penetrations Not Identified During Preoperational Testing.Penetrations Will Be Added to Tech Spec Table 3.7.2 & Will Be Tested | | | 05000298/LER-1978-030, Forwards LER 78-030/03L-0 | Forwards LER 78-030/03L-0 | | | 05000298/LER-1978-031-03, /03L-0 on 780912:Cooper-Bessemer Diesel Engine Type KSV-16-T Main Bearing Overheated.Main Bearing 10 Was Damaged Due to Minimal Oil Flow During Engine Coastdown. Caused by Foreign Particles in Oil | /03L-0 on 780912:Cooper-Bessemer Diesel Engine Type KSV-16-T Main Bearing Overheated.Main Bearing 10 Was Damaged Due to Minimal Oil Flow During Engine Coastdown. Caused by Foreign Particles in Oil | | | 05000298/LER-1978-031, Forwards LER 78-031/03L-0 | Forwards LER 78-031/03L-0 | | | 05000298/LER-1978-032, Forwards LER 78-032/03L-0 | Forwards LER 78-032/03L-0 | | | 05000298/LER-1978-032-03, /03L-0 on 780918:during Normal Oper,After Cooling Down the Torus,Rhr Heat Exchanger 1B Bypass RHR-MO-66B Failed to Oper,Due to Loose Set Screw on Yoke of Limiterque SMB-3 Operator | /03L-0 on 780918:during Normal Oper,After Cooling Down the Torus,Rhr Heat Exchanger 1B Bypass RHR-MO-66B Failed to Oper,Due to Loose Set Screw on Yoke of Limiterque SMB-3 Operator | | | 05000298/LER-1978-033, Forwards LER 78-033/03L-0 | Forwards LER 78-033/03L-0 | | | 05000298/LER-1978-033-03, /03L-0 on 781016:cable HP58,Div 1,was Found Routed Thru Div 11 Riser Under Panel 9-3.Caused by Personnel Error During Constr.Redundant Sys Were Operable | /03L-0 on 781016:cable HP58,Div 1,was Found Routed Thru Div 11 Riser Under Panel 9-3.Caused by Personnel Error During Constr.Redundant Sys Were Operable | | | 05000298/LER-1978-034-03, /03L-0 on 781111:during S.P.6.4.1.2. (Withdrawn Control Rod Operability), Control Rod 30-31 Was Found Uncoupled from Its Control Rod Drive. Cause Cannot Be Determined Until Control Rod Drive Is Removed & Examined | /03L-0 on 781111:during S.P.6.4.1.2. (Withdrawn Control Rod Operability), Control Rod 30-31 Was Found Uncoupled from Its Control Rod Drive. Cause Cannot Be Determined Until Control Rod Drive Is Removed & Examined | | | 05000298/LER-1978-034, Forwards LER 78-034/03L-0 | Forwards LER 78-034/03L-0 | | | 05000298/LER-1978-035-01, /01T-0 on 781124:while Checking RR MG Set 1B Speed control,1 Amp fuse(F2) in Drive Amplifier Circuit Was Pulled Out & Checked.Caused Rapid Increase in Pwr Level,Tripping RR MG Set 1B | /01T-0 on 781124:while Checking RR MG Set 1B Speed control,1 Amp fuse(F2) in Drive Amplifier Circuit Was Pulled Out & Checked.Caused Rapid Increase in Pwr Level,Tripping RR MG Set 1B | | | 05000298/LER-1978-035, Forwards LER 78-035/01T-0 | Forwards LER 78-035/01T-0 | | | 05000298/LER-1978-036, Forwards LER 78-036/04T-0 | Forwards LER 78-036/04T-0 | | | 05000298/LER-1978-036-04, /04T-0 on 781212:discharge of Floor Drain Sample Tank Was Made W/O Effluent Monitoring Required by Tech Specs,Because Flushing Valve of Radwaste Effluent Monitor Was Inadvertently Left Open | /04T-0 on 781212:discharge of Floor Drain Sample Tank Was Made W/O Effluent Monitoring Required by Tech Specs,Because Flushing Valve of Radwaste Effluent Monitor Was Inadvertently Left Open | | | 05000298/LER-1978-037, Forwards LER 78-037/03L-0 | Forwards LER 78-037/03L-0 | | | 05000298/LER-1978-037-03, /03L-0 on 781201:during Normal Operation,Pressure Recorder PC-PR-512A Was Found Reading Full Scale & Declared Inoperable.Cause Was Isolated to a Bad Amplifier Circuit Board | /03L-0 on 781201:during Normal Operation,Pressure Recorder PC-PR-512A Was Found Reading Full Scale & Declared Inoperable.Cause Was Isolated to a Bad Amplifier Circuit Board | | | 05000298/LER-1978-038-03, /03L-0 on 781208:during Normal Operation,One Struthers Wells Cross Connect Valve Failed to Open During Surveillance Procedure.Caused by Mfg Error | /03L-0 on 781208:during Normal Operation,One Struthers Wells Cross Connect Valve Failed to Open During Surveillance Procedure.Caused by Mfg Error | | | 05000298/LER-1978-038, Forwards LER 78-038/03L-0 | Forwards LER 78-038/03L-0 | | | 05000298/LER-1978-039-03, /03L-0 on 781206:while Performing Surveillance Test After No 1 Diesel Generator Was Out of Svc for Maint,Diesel Engine Failed to Reach Full Speed.Caused by Reduced Air Pressure | /03L-0 on 781206:while Performing Surveillance Test After No 1 Diesel Generator Was Out of Svc for Maint,Diesel Engine Failed to Reach Full Speed.Caused by Reduced Air Pressure | | | 05000298/LER-1978-039, Forwards LER 78-039/03L-0 | Forwards LER 78-039/03L-0 | | | 05000298/LER-1978-040-03, /03L-0 on 781227:during Normal Operation,While Doing Special Test of Drywell Purging Techniques,Primary Containment Vent Valve PC-246AV Leaked Excessively & Was Inoperable Due to Incomplete Valve Closure.Valve Replaced | /03L-0 on 781227:during Normal Operation,While Doing Special Test of Drywell Purging Techniques,Primary Containment Vent Valve PC-246AV Leaked Excessively & Was Inoperable Due to Incomplete Valve Closure.Valve Replaced | |
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