05000285/LER-2006-005, For Fort Calhoun Station Regarding Faulty Maintenance Renders One Train of Containment Spray System Inoperable

For Fort Calhoun Station Regarding Faulty Maintenance Renders One Train of Containment Spray System Inoperable

ML063530478
Person / Time
Site:	Fort Calhoun
Issue date:	12/11/2006
From:	Reinhart J Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-06-0129 LER 06-005-00
Download: ML063530478 (7)

LER-2006-005, For Fort Calhoun Station Regarding Faulty Maintenance Renders One Train of Containment Spray System Inoperable

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(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
2852006005R00 - NRC Website

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X 'Omaha Public Powef District

" "1946 - 2006 Fort Calhoun Station P.O. Box 550 Fort Calhoun, NE 68023 December 11, 2006 LIC-06-0129 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P 1-137 Washington, DC 20555

Reference:

Subject:

Docket No. 50-285 Licensee Event Report 2006-005 Revision 0 for the Fort Calhoun Station Please find attached Licensee Event Report 2006-005, Revision 0, dated December 11, 2006.

This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B), 50.73(a)(2)(ii)(B) and 50.73(a)(2)(v)(D). If you should have any questions, please contact me.

Singer J. A. Reinhart Site Director - Fort Cdi1houn Station JAR/EPM/epm Attachment c:INPO Records Center i

1-7 z-

NRC FORM 366 U.S. NUCLEAR REGULATORY COMp APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.

Reported lessons learned are incorporated into the licensing process and fed back to industry.

Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail LICENSEE EVENT REPORT (LER) to infocollects@nrc.gov, and to the Desk Officer, Office of Information and RegulatoryAffairs, NEOB-1 0202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the (See reverse for required number of information collection.

digits/characters for each block)

3. PAGE Fort Calhoun Station 05000285 1 OF 6

4. TITLE Faulty Maintenance Renders One Train of Containment Spray System Inoperable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEQUENTIAL REV MFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.

MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 10 10 2006 2006 005 00 12 11 2006 05000

9. OPERATING

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)

MODE

[- 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii)

El 20.2201(d)

El 20.2203(a)(3)(ii)

E-50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A) 5 El 20.2203(a)(1)

El 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)

[1 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

E-50.36(c)(1)(i)(A)

[1 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

[1 50.36(c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

[I 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71(a)(4)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

[] 50.73(a)(2)(v)(B)

El 73.71(a)(5) 0 El 20.2203(a)(2)(v)

[E 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

Z 50.73(a)(2)(i)(B)

E 50.73(a)(2)(v)(D)

Specify in Abstract below or in (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 (If more space is required, use additional copies of NRC Form 366A) (17)

SAFETY SYSTEM FUNCTIONAL FAILURE This event does result in a safety system functional failure in accordance with Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline".

PREVIOUS SIMILAR EVENTS

There have not been any other instances of incorrect maintenance on ball valves causing the inoperability of safety systems.