05000285/LER-2013-012, Regarding Intake Structure Crane Seismic Qualification

Regarding Intake Structure Crane Seismic Qualification

ML13274A638
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/2013
From:	Cortopassi L Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LlC-13-0132 LER 13-012-00
Download: ML13274A638 (4)

LER-2013-012, Regarding Intake Structure Crane Seismic Qualification

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v)(8) 10 CFR 50.73(a)(2)(ix)(A) 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)(8) 10 CFR 50.73(a)(2)(viii)(8) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function
2852013012R00 - NRC Website

text

Omaha Public Power District 444 South 16th Street Mall Omaha, NE 68102-2247 LlC-13-0132 September 30,2013 u.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Reference:

1. Docket No. 50-285

Subject:

Licensee Event Report 2013-012, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2013-012, Revision O. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(v)(8) and 10 CFR 50.73(a)(2)(ix)(A). 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/epm Attachment c:

S. A. Reynolds, Acting 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 Intake Structure Crane Seismic Qualification

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 8

2 2013 2013 012 -

0 9

30 2013 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check aI/ that apply)

D 20.2201(b)

D 20.2203(a)(3)(i)

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

D 50.73(a)(2)(vii) 5 D

20.2201(d)

D 20.2203(a)(3)(ii)

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

D 50.73(a)(2)(viii)(A)

D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(ii)(8)

D 50.73(a)(2)(viii)(8)

D 20.2203(a)(2)(i)

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

D 50.73(a)(2){iii)

IZI 50.73{a)(2){ix)(A}

10. POWER LEVEL D 20.2203{a)(2)(ii)

D 50.36(c){1 )(ii){A)

D 50.73(a){2)(iv)(A)

D 50.73{a)(2){x)

D 20.2203{a){2){iii)

D 50.36{c){2)

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

D 73.71(a)(4) 0 D

20.2203{a){2)(iv)

D 50.46(a)(3){ii)

IZI 50.73{a){2)(v){8}

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)(8)

D SO.73{a)(2)(v){D)

Specify in Abstract below or in

CORRECTIVE ACTIONS

The crane was verified not in use and in the parked position at the time of discovery. Compensatory actions were identified which would allow the use of the intake crane. The condition was entered in to the station's corrective action program as Condition Report 2013-15474 and a new seismic analysis to address crane use will be developed.

SAFETY SIGNIFICANCE

Technical Specification 2.4 states that only two Raw Water Pumps may be out of service at power operation. The postulated flooding event is outside of the assumptions of the intake structure internal flooding analysis and could lead to an internal flooding event that renders all four raw water pumps inoperable. However, FCS Abnormal Operating Procedure (AOP) 18, Loss of Raw Water, is written to speCifically address a total loss of raw water.

SAFETY SYSTEM FUNCTIONAL FAILURE This does represent a safety system functional failure in accordance with NEI 99-02, Revision 6.

PREVIOUS EVENTS Eight LERs referencing the raw water pumps were identified. However, none of the LERs reviewed contained the same reason of this event, failure, or sequence of events. 3