ML12366A191

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Errata to IR 05000285-12-005, Fort Calhoun Station, Correcting an Error Noted in Enclosure 2
ML12366A191
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/21/2012
From: Hay M
NRC/RGN-IV/DRP
To: Cortopassi L
Omaha Public Power District
References
EA-12-174 IR-12-005
Download: ML12366A191 (3)


See also: IR 05000285/2012005

Text

December 21, 2012

EA-12-174

Louis P. Cortopassi, Site Vice President

Omaha Public Power District

Fort Calhoun Station FC-2-4

P.O. Box 550

Fort Calhoun, NE 68023-0550

SUBJECT:

ERRATA FOR FORT CALHOUN STATION - NRC INTEGRATED INSPECTION

REPORT 05000285/2012005

Dear Mr. Cortopassi:

An error was discovered in NRC Inspection Report 05000285/2012005, Enclosure 2, dated

November 13, 2012. It was identified that the cross-cutting aspect for noncited violation (NCV)05000285/2012005-02, Untimely Corrective Actions for 480 VAC Breaker Issues was

described incorrectly on page 2 of the report. Please replace page 2 of Enclosure 2 to NRC

Inspection Report 05000285/2012005 with the enclosed page 2.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its

enclosure, and your response (if any) will be available electronically for public inspection in the

NRC Public Document Room or from the Publicly Available Records (PARS) component of

NRC's Agency wide Document Access and Management System (ADAMS). ADAMS is

accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public

Electronic Reading Room).

Sincerely,

/RA/

Michael C. Hay, Chief

Project Branch F

Division of Reactor Projects

Docket No.: 50-285

License No.: DPR-40

Enclosure:

Errata page 2 for NRC Inspection Report 05000285/2012005

UNITED STATES

NUCLEAR REGULATORY COMMISSION

RE G IO N I V

1600 EAST LAMAR BLVD

ARLINGTON, TEXAS 76011-4511

L. Cortopassi

-2-

Electronic distribution:

Regional Administrator (Elmo.Collins@nrc.gov)

Deputy Regional Administrator (Steven.Reynolds@nrc.gov)

DRP Director (Kriss.Kennedy@nrc.gov)

Acting DRP Deputy Director (Barry.Westreich@nrc.gov)

Acting DRS Director (Tom.Blount@nrc.gov)

Acting DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (John.Kirkland@nrc.gov)

Resident Inspector (Jacob.Wingebach@nrc.gov)

Branch Chief, DRP/F (Michael.Hay@nrc.gov)

Senior Project Engineer, DRP/F (Rick.Deese@nrc.gov)

Project Engineer, DRP/F (Chris.Smith@nrc.gov)

FCS Administrative Assistant - Vacant

Public Affairs Officer (Victor.Dricks@nrc.gov)

Public Affairs Officer (Lara.Uselding@nrc.gov)

Branch Chief, DRS/TSB (Ray.Kellar@nrc.gov)

Project Manager (Lynnea.Wilkins@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Technical Support Assistant (Loretta.Williams@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

OEMail Resource

Inspection Reports/MidCycle and EOC Letters to the following:

ROPreports

Only inspection reports to the following:

RIV/ETA: OEDO (Cayetano.Santos@nrc.gov)

DRS/TSB STA (Dale.Powers@nrc.gov)

ADAMS ACCESSION NO: ML12366A191

SUNSI Rev Compl.

Yes No

ADAMS

Yes No

Reviewer Initials

MCH

Publicly Avail.

Yes No

Sensitive

Yes No

Sens. Type

Initials

MCH

SRI:DRP/F

SPE:DRP/F

BC:DRP/F

JKirkland

RDeese

MHay

/RA Via email/

/RA/

/RA/

12/19/12

12/21/12

12/21/12

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

-2-

SUMMARY OF FINDINGS

IR 05000285/2012005; 08/19/2012 - 09/30/2012; Fort Calhoun Station, Integrated Resident,

Inservice Inspection, and Confirmatory Action Letter Report

The report covered a 6-week period of inspection by resident inspectors and announced

baseline inspections by region-based inspectors. One Green noncited violation and one

Severity Level IV cited violation were identified. The significance of most findings is indicated by

their color (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609, Significance

Determination Process. The cross-cutting aspect is determined using Inspection Manual

Chapter 0310, Components Within the Cross Cutting Areas. Findings for which the

significance determination process does not apply may be Green or be assigned a severity level

after NRC management review. The NRC's program for overseeing the safe operation of

commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,

Revision 4, dated December 2006.

A.

NRC-Identified Findings and Self-Revealing Findings

Cornerstone: Initiating Events

Green. The NRC identified a noncited violation (NCV) of 10 CFR Part 50, Appendix B,

Criterion XVI, Corrective Actions, for the failure to take timely corrective actions with

respect to nonconforming conditions in several circuit breakers. These conditions were

determined to have been the cause of the 1B4A bus bar failure that initiated a fire on

June 7, 2011. These conditions were not corrected in a timely manner and the licensee

continued to operate with a degraded breaker for nine months after the breaker tripped

unexpectedly during the June 7, 2011, fire event. The licensee entered this issue into

their corrective action program as CRs 2012-01884 and 2011-5414.

The violation was determined to be more than minor because it affected the Initiating

Events Cornerstone attribute of protection against external events (i.e., fire). The issue

adversely affected the associated cornerstone objective of limiting the likelihood of those

events that upset plant stability and challenge critical safety functions during shutdown

as well as power operations because the condition that contributed to the fire event was

left uncorrected. The finding screened to Green in accordance with IMC 0609, Appendix

G because RCS makeup capability was not degraded. The inspectors determined that

the issue had a cross-cutting aspect in the area of Human Performance, Decision

Making, in that the licensee failed to use conservative assumptions and adopt a

requirement to demonstrate that the proposed action is safe in order to proceed rather

than a requirement to demonstrate that it is unsafe in order to disapprove the action

H.1(b) (4OA4.1.c.(3).1).

Cornerstone: Miscellaneous

SLIV. The inspectors identified a cited violation of 10 CFR 50.71(e), Maintenance of

Records, Making of Reports, for the failure to update the Updated Safety Analysis

Report with a detailed description of the Original Steam Generator Storage Facility.

Specifically, since December 2006, the licensee stored a significant source of