05000285/LER-2009-004, Regarding Containment Integrity Was Unknowingly Violated During Performance of Leak Test
| ML100490163 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/02/2010 |
| From: | Reinhart J Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-10-0007 LER 09-004-00 | |
| Download: ML100490163 (4) | |
| 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 |
| 2852009004R00 - NRC Website | |
text
am mum Omaha Public Power District Fort Calhoun Station P.O. Box 550, Fort Calhoun, NE 68023 LIC-10-0007 February 2, 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Reference:
Docket No. 50-285
Subject:
Licensee Event Report 2009-004 Revision 0 for the Fort Calhoun Station Please find attached Licensee Event Report 2009-004, Revision 0, dated February 2, 2010. This report is being submitted pursuant to 10CFR50.73(a)(2)(i)(B).
The rootcause information contained in this report is preliminary; therefore, the Omaha Public Power District plans'to provide a supplement describing the final root cause by April 23, 2010. If you'should have any questions, please contact me.
Since iffrey A. Reinhart e Vice President Fort Calhoun Station JAR/rda Attachment c:
E. E. Collins, NRC Regional Administrator, Region IV L. E. Wilkins, NRC.Senior Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center,
Employment with Equal Opportunity 4171
NRC FORM 366 U.S. NUCLEAR REGULATORYCOMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Fort Calhoun Station 05000285 1
OF 3
- 4. TITLE Containment integrity was unknowingly violated during performance of Leak Test
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTI REV MONT FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR AL NO H
DAY YEAR NUMBER NO H
FACILITY NAME05 0
11 26 2006 2009
- - 004-00 02 02 2010 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
EI 20.2201(b) 0 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C) 0l 50.73(a)(2)(vii) 3 El 20.2201 (d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[]
50.73(a)(2)(viii)(A)
El 20.2203(a)(1) 0l 20.2203(a)(4)
El 50.73(a)(2)(ii)(B) 0l 50.73(a)(2)(viii)(B) 0l 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 0l 20.2203(a)(2)(iii)
El 50.36(c)(2)
[]
50.73(a)(2)(v)(A)
[]
73.71 (a)(4) 0 0
20.2203(a)(2)(iv)
Dl 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C) 0l OTHER El 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in CONCLUSION Preliminarily, the cause of this event is failure of previous reviewers of the test procedure to identify and resolve the conflict between required test conditions (i.e., RCS temperature greater than 210 deg F and containment integrity required) and opening SI-4 10 (i. e., manual containment isolation valve).
CORRECTIVE ACTIONS
Procedure QC-ST-SI-3006 was revised to require that administrative controls be in place prior to opening containment isolation valve SI-410. The completed root cause analysis will specify any additional corrective actions to correct the root cause of this event.
SAFETY SIGNIFICANCE
The safety significance of this event will be determined with the completed root cause analysis.
SAFETY SYSTEM FUNCTIONAL FAILURE This event does not result in a safety system functional failure in accordance with NEI-99-02.
PREVIOUS SIMILAR EVENTS
LER 1988-011, LER 1991-027, LER 1992-002, LER 2008-002PRINTED ON RECYCLED PAPERPRINTED ON RECYCLED PAPER