05000285/LER-2013-014, Regarding Unqualified Components Used in Safety System Control Circuit

Regarding Unqualified Components Used in Safety System Control Circuit

ML13353A471
Person / Time
Site:	Fort Calhoun
Issue date:	12/18/2013
From:	Cortopassi L Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LlC-13-0178 LER 13-014-00
Download: ML13353A471 (4)

LER-2013-014, Regarding Unqualified Components Used in Safety System Control Circuit

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(8) 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) 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2852013014R00 - NRC Website

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iiililjj Omaha Public Power Oisbict 444 South 16111 Street Mall Omaha, NE 68102-2247 LlC-13-0178 December 18, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 References: 1. Docket No. 50-285

2. Letter from the OPPD (Louis P. Cortopassi) to NRC (Document Control Desk), Licensee Event Report 2013-013, Revision 0, for the Fort Calhoun Station, dated December 2,2013 (LlC-13-0176)

3. Letter from the OPPD (Louis P. Cortopassi) to NRC (Document Control Desk), Licensee Event Report 2013-013, Revision 0, for the Fort Calhoun Station, dated November 26, 2013 (LlC-13-0173)

Subject:

Licensee Event Report 2013-014, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2013-014, Revision O. This letter replaces the report issued by Reference 2. The letter in Reference 2 duplicated the report number issued in Reference 3. Please delete the report issued by letter in Reference 2.

This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(8). There are no new commitments being made in this letter. If you should have any questions, please contact Terrence W. Simpkin, Manager, Site Regulatory Assurance, at (402) 533-6263.

Sincerely, Louis P. Cortopassi Site Vice President and CNO LPC/rjr Attachment c:

M. L. Dapas, NRC Regional Administrator, Region IV J. M. Sebrosky, NRC Senior Project Manager J. C. Kirkland, NRC Senior Resident Inspector L. E. Wilkins, NRC Project Manager 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 digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.

13. PAGE Fort Calhoun Station 05000285 1 OF 3

4. TITLE Unqualified Components used in Safety System Control Circuit

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 10 18 2012 2013 014 -

0 12 18 2013 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) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii) 5 o 20.2201(d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 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~

o 50.73(a)(2)(ix)(A)

10. POWER LEVEL o 20.2203(a)(2)(ii) o 50.36(c)(1 )(ii)(A) o 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71 (a)(4) 0 o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71(a)(5) o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) 181 50.73(a)(2)(i)(B) o 50.73(a)(2)(v)(O)

Specify in Abstract below or in SAFETY SYSTEM FUNCTIONAL FAILURE This does not represent a safety system functional failure in accordance with NEI 99-02, Revision 6.

PREVIOUS EVENTS 3

Engineering is reviewing this condition and the results of this review will be used to update this report. OF 3