LER-2004-001, Re 1 EDG Inoperable Caused by Cooling Fan Bearing Bolts Not Torqued Properly Following Preventative Maintenance Activities |
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AmerGen SM AmerGen Energy Company, LLC www.exeloncorp.com An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 10 CFR 50.73 July 13, 2004 2130-04-20141 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Licensee Event Report 2004-001-00: # 1 EDG Inoperable Caused by Cooling Fan Bearing Bolts Not Torqued Properly Following Preventative Maintenance Activities Enclosed is Licensee Event Report 2004-001, Revision 0. This event did not affect the health and safety of the public or plant personnel.
If any further information or assistance is needed, please contact David Fawcett at 609-971-4284.
Sincerel C. N. Swenson Vice President, Oyster Creek Generating Station CNS/DIF : List of Regulatory Commitments Enclosure cc:
H. J. Miller, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 04104
ATTACHMENT 1 SUMMARY OF AMERGEN ENERGY CO. LLC COMMITMENTS The following table identifies commitments made in the document by AmerGen Energy Co. LLC (AmerGen). Any other actions discussed in this submittal represent intended or planned actions by AmerGen. They are described to the NRC for the NRC's information and are not regulatory commitments.
COMMITMENT
COMMITTED DATE OR "OUTAGE" Evaluate and create PM tasks for the 24-month diesel inspection, including the specific tasks identified in the "Component Replacement Schedule" (Appendix 1, page E2-1) of Surveillance Test (ST) 636.1.010.
01/31/2005 Revise the ST and the applicable vendor Maintenance Instructions into Level 1 (Continuous Use) Maintenance Procedures. These procedures 03/31/200 should provide the necessary details, verifications and human factoring.
5 In addition, data sheets for entering readings such as 'as left" torque values; clearances, M&TE and other pertinent information should be provided.
Planners will be trained and reinforced in the expectation to provide 10/31/2004 torque specifications and appropriate verifications in work packages.
A follow up work package quality assessment will be performed prior to 08/31/2004 the upcoming refuel outage (1 R20).
Abstract
On May 17, 2004 at 04:40, at the end of the bi-weekly #1 Emergency Diesel Generator (EDG) (EK - DG) load test an operator reported that the EDG was making an unusual noise and the cooling fan belts and pulleys were observed to be loose. It was also observed that the pillow-block bearing supporting the cooling fan drive shaft and sheave assembly had one bolt missing and one bolt loose. A 7-day Technical Specification LCO was entered at 05:00.
The previous maintenance on the pillow block bearing support occurred about 17 days earlier during the two year overhaul completed in late April 2004. A review of the procedures and documentation that were used to perform the cooling fan maintenance and interviews with the individuals that performed the fan work during the overhaul were conducted. 'The investigation determined that the pillow block bearing hold down bolts had not been torqued as required by the vendor manual.
All repairs were completed on May 17, 2004 at 17:12. Immediately following the repairs, #1 EDG Load Test was again performed as the cooling fan post-maintenance test and to validate operability. The diesel was declared operable at 20:25.
No previous similar events of improper maintenance activities on the diesel generators leading to loose and missing bolts and fasteners due to improper torquing were identified.
NRC FORM 366 V72001)
(if more space Is required, use additional copies of (If more space Is required, use additional copies of (If more space Is required, use additional copies of NRC Form 366A)
Additional Information
A. Failed Components:
No components were damaged other than the threads on one of the bolts. Examination of the bearing revealed no damage and after reassembling the components the #1 EDG was successfully run for surveillance, examined for vibrations and determined to be operable.
B. Previous similar events
None.
C. Identification of components referred to in this Licensee Event Report:
Components IEEE 805 System ID IEEE 803A Function Emergency Diesel Generator EK DG
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| 05000219/LER-2004-001, Re 1 EDG Inoperable Caused by Cooling Fan Bearing Bolts Not Torqued Properly Following Preventative Maintenance Activities | Re 1 EDG Inoperable Caused by Cooling Fan Bearing Bolts Not Torqued Properly Following Preventative Maintenance Activities | | | 05000219/LER-2004-002, Regarding Change in Methodology Used by General Electric and Global Nuclear Fuels to Demonstrate Compliance with Emergency Core Cooling System Performance Requirements | Regarding Change in Methodology Used by General Electric and Global Nuclear Fuels to Demonstrate Compliance with Emergency Core Cooling System Performance Requirements | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000219/LER-2004-003-01, 1 Oyster Creek, Unit 1, Regarding Actuation of Reactor Protection System Due to Spurious Hi-Hi Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference | 1 Oyster Creek, Unit 1, Regarding Actuation of Reactor Protection System Due to Spurious Hi-Hi Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000219/LER-2004-003, Regarding Actuation of Reactor Protection System Due to Spurious HI-HI Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference | Regarding Actuation of Reactor Protection System Due to Spurious HI-HI Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000219/LER-2004-004, Regarding Operation in Excess of the Thermal Power Limit Due to Plant Computer Isolator Power Supply Degradation Affecting Input Values to the Heat Balance Calculation | Regarding Operation in Excess of the Thermal Power Limit Due to Plant Computer Isolator Power Supply Degradation Affecting Input Values to the Heat Balance Calculation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A) | | 05000219/LER-2004-005, Regarding Main Steam Isolation Valve Failure to Close During Partial Valve Closure Surveillance Due to Mechanical Binding | Regarding Main Steam Isolation Valve Failure to Close During Partial Valve Closure Surveillance Due to Mechanical Binding | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1) | | 05000219/LER-2004-006, Regarding Local Leak Rate Test Results in Excess of Technical Specifications | Regarding Local Leak Rate Test Results in Excess of Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000219/LER-2004-007, Regarding Automatic Containment Isolation Bypassed During Reactor Startup Due to an Inadequate Procedure | Regarding Automatic Containment Isolation Bypassed During Reactor Startup Due to an Inadequate Procedure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
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