05000285/LER-2012-020, The Fort Calhoun Station, Raw Water Pump Anchors

The Fort Calhoun Station, Raw Water Pump Anchors

ML13032A310
Person / Time
Site:	Fort Calhoun
Issue date:	01/31/2013
From:	Cortopassi L Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LlC-13-0009 LER 12-020-00
Download: ML13032A310 (5)

LER-2012-020, The Fort Calhoun Station, Raw Water Pump Anchors

Event date:
Report date:
Reporting criterion:	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
2852012020R00 - NRC Website

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jlIIO Omaha Public Power0IsIrIcI 444 South 16 fh Street Mall Omaha, NE 68102-2247 LlC-13-0009 January 31,2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Reference:

Docket No. 50-285

Subject:

Licensee Event Report 2012~020, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-020, Revision 0, dated January 31, 2013. This report is being submitted pursuant to 10 CFR 50.73(a){2)(i)(8).

There are no 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.

Lo~is P. Cortopassi Vice President and CND LPC/~r 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 Raw Water Pump Anchors

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 12 02 2012 2012 020 -

0 01 31 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 Edit Typical Sleeve and Anchor Bolt Details on design drawings to add a note to specify the anchor type. Due June 28, 2013.

Add the lessons learned from this event to the initial class for Print Reading for Engineers. Due April 15, 2013.

Cover details of this event as the Lessons Learned in Engineering Continuing Training. Due June 28, 2013.

Revise Design Engineering procedures to validate assumptions in calculations, engineering analysis, and configuration control procedures to review all available references. Due March 29, 2013.

Additionally, a Fundamental Performance Deficiency in engineering design and configuration control processes has been identified in Condition Report 2012-08125. Corrective actions from that condition report, which are applicable to this condition, are:

The development of a "Conduct of Engineering - Principles and Expectations" procedure, Update/revise various engineering procedures based on a gap analysis of PED-HU-1, "Engineering Human Performance Program", and Develop and issue Engineering review guidance for Vendor/Contractor design changes to ensure thorough and rigorous reviews by design engineering.

SAFETY SIGNIFICANCE

The results of the calculation completed on January 9, 2013, shows that during a seismic or barge impact event the raw water pump anchor bolts would remain functional. Therefore, there would be no loss of a safety function and no impact to safety.

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

PREVIOUS EVENTS No previous LERs concerning inadequate embedment of safety related anchors have been noted.