05000285/LER-2010-001, For Fort Calhoun Station, Regarding Containment Integrity Violated During Performance of Leak Test
| ML101610091 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/04/2010 |
| From: | Reinhart J Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-10-0035 LER 10-001-00 | |
| Download: ML101610091 (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 |
| 2852010001R00 - NRC Website | |
text
Omaha Public Power District Fort Calhoun Station 9610 Power Lane Blair, NE 68008 June 4, 2010 LIC-10-0035 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Reference:
Docket No. 50-285
Subject:
Licensee Event Report 2010-001 Revision 0 for the Fort Calhoun Station Please find attached Licensee Event Report 2010-001, Revision 0, dated June 4, 2010.
This report is being submitted pursuant to 10 CFR 50.73(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 August 30, 2010. No regulatory commitments are contained in this submittal.
If you should have any questions, please contact me.
Sinc rely, ffrey A. Reinhart Site Vice President Fort Calhoun Station JAR/epm Attachment c:
E. E. Collins, NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center iyment with Equal Opportunity Empio
171 I~r
- - I-I; TIý 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 Violated During Performance of Leak Test
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTI REV T
FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR AL MON DAY YEAR NO H
05000 NUMBER NO H
0 FACILITY NAME 05000 11 01 2009 2010
- - 001 -
00 06 04 2010
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) o 20.2201(b) o 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
[]
50.73(a)(2)(vii) 3 o
20.2201(d)
[]
20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1)
E]
20.2203(a)(4)
E]
50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 50.36(c)(1)(i)(A) o 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL o
20.2203(a)(2)(ii) o 50.36(c)(1)(ii)(A)
[j 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii) c]
50.36(c)(2) o 50.73(a)(2)(v)(A) c]
73.71 (a)(4) 0 o
20.2203(a)(2)(iv) o 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B)
[]
73.71 (a)(5) o 20.2203(a)(2)(v)
E]
50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C)
[
OTHER o
20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or in On November 1, 2009, a revision was made to QC-ST-SI-3006. A note, a caution, and a step were added at the beginning of the procedure section to require that an operator be assigned to close manual containment isolation valve SI-410 when directed by the control room, to establish containment integrity. However, environmental conditions during an accident could preclude an operator from shutting SI-4 10 during an accident.
An extent of condition review from LER 2009-004 noted the violation of the TS basis information. The review determined that the station entered and subsequently violated TS 2.6(1)a on November 1, 2009, as a result of opening valve SI-410 when containment integrity was required.
This issue was identified and documented in Condition Report (CR) 2010-1664.
This event is being reported per 10 CFR 50.73(a)(2)(i)(B).
CONCLUSION A root cause analysis is in progress and the results will be included in an update to the LER.
CORRECTIVE ACTIONS
The completed root cause analysis will specify 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 2008-002 and LER 2009-004PRINTED ON RECYCLED PAPERPRINTED ON RECYCLED PAPER