05000285/LER-2008-002, Loss of Containment Integrity Due to a Leaking Isolation Valve
| ML081360080 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/14/2008 |
| From: | Nellenbach T Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-08-0047 LER 08-002-00 | |
| Download: ML081360080 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 2852008002R00 - NRC Website | |
text
Fort Calhoun Station Po. Box 550 Fort Calhoun, NE 68023 L1C-08-0047 May 14, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Reference:
Docket No. 50-285
Subject:
Licensee Event Report 2008-002 Revision 0 for the Fort Calhoun Station Please find attached Licensee Event Report 2008-002, Revision 0, dated May 14, 2008.
This report is being submitted pursuant to 10CFR50.73(a)(2)(i)(B).
The root cause information contained in this report is preliminary; therefore, the Omaha Public Power District plans to provide a supplement describing the final root cause by June 13, 2008. If you should have any questions, please contact me.
Sincerely,
~fi.rJJJ)
T. R. Nellenbach Division Manager - Nuclear Operations TRN/RMC/rmc Attachment c:
E. E. Collins, NRC Regional Administrator, Region IV M. T. Markley, NRC Senior Project Manager J. D. Hanna, NRC Senior Resident Inspector INPO Records Center
NRC FORM 366 U.S. NUCLEAR REGULATORYCOMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Fort Calhoun Station
- 2. DOCKET NUMBER 05000285
- 3. PAGE 1 OF 3
- 4. TITLE Loss of Containment Integrity Due to a Leaking Isolation Valve
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTI AL NUMBER REV NO MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 03 15 2008 2008
- - 002 -
00 05 14 2008 FACILITY NAME 05000
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b)
20.2203(a)(3)(i)
50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d)
20.2203(a)(3)(ii)
50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1)
20.2203(a)(4)
50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
- 9. OPERATING MODE 03 20.2203(a)(2)(i)
50.36(c)(1)(i)(A)
50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii)
50.36(c)(1)(ii)(A)
50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii)
50.36(c)(2)
50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv)
50.46(a)(3)(ii)
50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v)
50.73(a)(2)(i)(A)
50.73(a)(2)(v)(C)
OTHER
- 10. POWER LEVEL 0
20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B)
50.73(a)(2)(v)(D)
Specify in Abstract below or in SAFETY SYSTEM FUNCTIONAL FAILURE This event does not constitute a safety system functional failure as described in NEI-99-02.
PREVIOUS SIMILAR EVENTS
Fort Calhoun Station reported a similar loss of containment integrity event in LER 2006-01. PRINTED ON RECYCLED PAPER