05000285/LER-2014-002, Regarding Reactor Manual Trip Due to Control Rod Misalignment

Regarding Reactor Manual Trip Due to Control Rod Misalignment

ML14071A277
Person / Time
Site:	Fort Calhoun
Issue date:	03/12/2014
From:	Cortopassi L Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-14-0029 LER 14-002-00
Download: ML14071A277 (4)

LER-2014-002, Regarding Reactor Manual Trip Due to Control Rod Misalignment

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2852014002R00 - NRC Website

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jjjjjjjj Omaha Public Power Oistrict 444 South 16th Street Mall Omaha, NE 68102-2247 March 12,2014 LI C-14-0029 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

Reference:

none 10 CFR 50.73

Subject:

Licensee Event Report 2014-002, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2014-002, Revision O. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A). No commitments are being made in this letter..

If you should have any questions, please contact Terrence W. Simpkin, Manager, Site Regulatory Assurance, at (402) 533-6263.

is P. Cortopassi Site Vice President and CNO LPC/epm Attachment c:

J. M. Sebrosky, NRC Sr. Project Manager M. L. Dapas, NRC Regional Administrator, Region IV J. C. Kirkland, NRC Sr. Resident Inspector Employment with Equal Opportunity

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the

13. PAGE Fort Calhoun Station 05000285 1 OF 3

4. nTLE Reactor Manual Trip due to Control Rod Misalignment

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 01 12 2014 2014 - 002 -

00 3

12 2014 05000

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)

D 50.73(a)(2)(i)(C)

D 50.73(a)(2)(vii) 2 o 20.2201 (d)

D 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A) o 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i)

D 50.36(c)(1 )(i)(A)

D 50.73(a)(2)(iii)

D 50.73(a)(2)(ix)(A)

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

D 50.36(c)(1 )(ii)(A) 181 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x) o 20.2203(a)(2)(iii)

D 50.36(c)(2)

D 50.73(a)(2)(v)(A)

D 73.71(a)(4) 0 o 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

D 50.73(a)(2)(v)(B)

D 73.71(a)(5) o 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(C)

D OTHER o 20.2203(a)(2)(vi)

D 50.73(a)(2)(i)(B)

D 50.73(a)(2)(v)(O)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER) u.s. NUCLEAR REGULATORY COMMISSION CONTINUATION SHEET

2. DOCKET

6. LER NUMBER

3. PAGE 3

OF 3

YEAR I SEQUENTIAL I REV NUMBER NO.

05000285 2014 002 o

SAFETY SYSTEM FUNCTIONAL FAILURE This does not represent a safety system functional failure in accordance with NEI 99-02, Revision 7.

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