text
-~
jjjjjjjj Omaha Public Power District 444 South 16' 11 Street Mall Omaha, NE 68102-2247 LI C-15-0056 May 28, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 10 CFR 50.73
Subject:
Licensee Event Report 2015-002, Revision O, for the Fort Calhoun Station Please find attached Licensee Event Report 2015-002, Revision 0. This report is being submitted pursuant to 10 CFR 50.73(a)(2){i)(B) and 50.73(a)(2)(v)(B). There are no new commitments being made in this letter.
If you should have any questions, please contact Terrence W. Simpkin, Manager, Site Regulatory Assurance, at (402) 533-6263.
f cl_
Louis P. Cortopassi Site Vice President and CNO LPC/epm Attachment c:
M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S.M. Schneider, NRC Senior Resident Inspector
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
YEAR 2015
- 6. LEA NUMBER I
SEQUENTIAL I NUMBER 002 REV NO.
00 3
- 3. PAGE OF 3
Although the both AFW pumps were made inoperable by the testing procedure, the inoperability occurs while operators are actively engaged in realigning the system for normal operation. This lineup would have caused the pumps to feed the steam generators through both the main and auxiliary feedwater lines. The period of inoperability for the system is expected to be less than 1 O minutes.
SAFETY SYSTEM FUNCTIONAL FAILURE This does represent a safety system functional failure in accordance with NEI 99-02, revision 7.
PREVIOUS EVENTS None NRC FORM 366 (02-2014)
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000285/LER-2015-001, Inadequate Design of High Energy Line Break Barriers | Inadequate Design of High Energy Line Break Barriers | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000285/LER-2015-001, Regarding Inadequate Design of High Energy Line Break Barriers | Regarding Inadequate Design of High Energy Line Break Barriers | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)(i)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | | 05000285/LER-2015-002, Regarding Inoperable Auxiliary Feedwater System Due to Inadequate Procedure Change | Regarding Inoperable Auxiliary Feedwater System Due to Inadequate Procedure Change | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2) | | 05000285/LER-2015-003, Regarding Containment Spray Inoperable Due to Original Design Error | Regarding Containment Spray Inoperable Due to Original Design Error | 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) | | 05000285/LER-2015-004, Regarding Inoperability of Auxiliary Feedwater Trains Due to Failure of Steam Generator Isolation Valve | Regarding Inoperability of Auxiliary Feedwater Trains Due to Failure of Steam Generator Isolation Valve | 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)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
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) | | 05000285/LER-2015-005, Regarding Reactor Coolant Leak at Reactor Coolant Pump Seal Due to Cyclic Fatigue | Regarding Reactor Coolant Leak at Reactor Coolant Pump Seal Due to Cyclic Fatigue | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000285/LER-2015-006, Regarding Unanalyzed Fire Vulnerability Due to Inadequate Design | Regarding Unanalyzed Fire Vulnerability Due to Inadequate Design | 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)(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 |
|
