05000285/LER-2012-014-01, Regarding Containment Beam 22 Loading Conditions Outside of the Allowable Limits

Regarding Containment Beam 22 Loading Conditions Outside of the Allowable Limits

ML13022A479
Person / Time
Site:	Fort Calhoun
Issue date:	01/18/2013
From:	Cortopassi L Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LIC-13-0003 LER 12-014-01
Download: ML13022A479 (5)

LER-2012-014, Regarding Containment Beam 22 Loading Conditions Outside of the Allowable Limits

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)(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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2852012014R01 - NRC Website

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gjjjjO Omaha Pub/Ic PowtIrDIIItIt:I 444 South 1(Jh Street Mall Omaha, NE 68102-2247 LlC-13-0003 January 18, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285

Subject:

Licensee Event Report 2012-014, Revision 1, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-014, Revision 1, dated January 18, 2013. This report is being submitted pursuant to 10 CFR 50.73 (a)(2)(i)(8).

No commitments are being made in this letter.

If you should have any questions, please contact me.

Sincerely, uis P. Cortopassi Site Vice President and CNO LPClrjr Attachment c:

E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector Employment with Equal Opportunity

NRC FORM 366 (10-2010)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013

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

1. FACILITY NAME Fort Calhoun Station

2. DOCKET NUMBER 05000285

3. PAGE 1 OF 4

4. TITLE Containment Beam 22 Loading Conditions Outside of the Allowable Limits

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 07 11 2012 2012 - 014 -

1 01 18 2013 FACILITY NAME DOCKET NUMBER 05000

9. OPERATING MODE 5

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET previously, and thus is a contributing cause. This condition is being addressed through RCA 2012-08125, Engineering Design/Configuration Control, AI-008, CAPR-2, "Implement a new Engineering organizational structure based on development of the following procedures consistent with best industry practices:

• Conduct of Engineering - Principles and Expectations,

• Engineering Division of Responsibilities, and

• Departmental Duties and Responsibilities".

SAFETY SIGNIFICANCE

Fort Calhoun Station was in Mode 5 at the time this condition was discovered.

Beam B-22, which supports safety injection tanks SI-6B and SI-6D, was determined to be susceptible to an overstressed condition during past operating cycles, for a hypothetical major break in the Reactor Coolant System, under the controlling "No Loss of Function" design load combination.

Although this is what the condition of Beam 22 was thought to be at the time of discovery, the additional analysis described above shows that with a live load of 140 psf or less, Beam 22 was able to meet its design function. Therefore, there was no loss of function and the previously identified reporting criteria of 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(D) no longer apply nor does this condition represent a safety system functional failure, as previously reported.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does not result in a safety system functional failure in accordance with NEI-99-02.

PREVIOUS EVENTS A cause analysis determined that there have been no previous events with the same underlying concern or reason of this event, such as the same root cause, failure, or sequence of events.