05000285/LER-2012-004, Re Inadequate Analysis of Drift Affects Safety Related Equipment

Re Inadequate Analysis of Drift Affects Safety Related Equipment

ML12208A037
Person / Time
Site:	Fort Calhoun
Issue date:	05/29/2012
From:	Bannister D, Zyvoloski R Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LER 12-004-00
Download: ML12208A037 (5)

LER-2012-004, Re Inadequate Analysis of Drift Affects Safety Related Equipment

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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
2852012004R00 - NRC Website

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IIppu Omaha Public Powsr OisITid

- 144 South 16 tlr Street Mall Omaha, NE 68102-22-17 L1C-12-0073 May 29, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Reference:

Docket No. 50-285

Subject:

Licensee Event Report 2012-004, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-004, Revision 0, dated May 29,2012.

This report is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(B) and (a)(2)(v)(A,B,C,D)

No commitments are being made in this letter.

If you should have any questions, please contact me.

Sincerely,

~~

Vice President and CNO DJB /epm Attachment c:

E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center Employment wit" 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 sp onsor, and a person is not required to respond to, th e

information collection.

1. FACILITY NAME Fort Calhoun Station

2. DOCKET NUMBER 05000285

3. PAGE 1 OF 2

4. TITLE Inadequate Analysis of Drift Affects Safety Related Equipment

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 03 29 2012 2012 - 004 -

0 05 29 2012 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 NRC Form 366A

10. POWER LEVEL 0

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME Erick Matzke TELEPHONE NUMBER (Include Area Code) 402-533-6855 CAUSE SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

CAUSE

SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

14. SUPPLEMENTAL REPORT EXPECTED YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

NO

15. EXPECTED SUBMISSION DATE MONTH DAY YEAR 8

10 2012 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

While investigating operating experience from another station concerning potential instrument drift it was determined that Fort Calhoun Station (FCS) is subject to similar conditions. It was determined that pressure switches that provide safety related signals for high containment pressure to the reactor protection system (RPS) and engineered safeguards actuation circuitry may be similarly affected at FCS. The impact of the potential drift was evaluated and it was determined that neither RPS nor the engineered safeguard circuitry may actuate at the required containment pressure of 5 psig. An evaluation determined that the actuation may not occur until slightly higher than the required pressure. Other systems are currently being evaluated for this condition.

A cause analysis is being performed and will be provided in a supplement to this report.

Corrective actions will be determined following the completion of the cause analysis.

LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

EVENT DESCRIPTION

While investigating operating experience from another station it was determined that Fort Calhoun Station (FCS) is subject to similar conditions. The operating experience involved setpoint drift of safety-related pressure switches beyond what had been accounted for in the stations safety analyses.

Following investigation and evaluation, it was determined that pressure switches that provide safety-related signals for high containment pressure to the reactor protection system (RPS) and engineered safeguards actuation circuitry may be similarly affected at FCS. The impact of the potential drift was evaluated and it was determined that neither RPS nor the engineered safeguard circuitry may actuate at the required containment pressure of 5 psig. An evaluation determined that the actuation may occur at a slightly higher value than the required pressure. Other systems are currently being evaluated for the condition.

On May 2, 2012, an eight (8) hour report was made per 10 CFR 50.72(b)(3)(ii)(B) to the NRC Headquarters Operation Office (HOO) at 1802 CDT (Event Number47892). After further evaluation this report is being made per 10 CFR 50.73(a)(2)(ii)(B) and (a)(2)(v)(A,B,C,D).

CONCLUSION A cause analysis is being performed and the results will be provided in a supplement to this report.

CORRECTIVE ACTIONS

Corrective actions will be determined following the completion of the cause analysis.

SAFETY SIGNIFICANCE

A cause analysis is in progress. The safety significance of this event will be provided in a supplement to this LER following completion of the analysis.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does result in a safety system functional failure in accordance with NEI-99-02.

PREVIOUS EVENTS No events of a similar nature have been identified.

FORT CALHOUN STATION NOD-QP-9.2 QUALITY PROCEDURE FORM R0 LICENSING CORRESPONDENCE REVIEW FORM LIC-12-0073 Date Issued: 5/23/12 Requested Return Date:____5/25/12______

Review/Approval Information Susan Baughn Dave Bannister John Herman Woody Goodell Steve Miller Brad Blome Chris Sterba L. Smith Corey Cameron John Steinke Ken Dunham Subject___ LER 2012-004 Rev 0 Inadequate Analysis of Drift Affects RPS and ECCS Equipment Please review and approve the attached draft correspondenc e (referenced above). In order to document your review for our records, please sign this form and return it to the Licensing Coordinator. If n o notification is received by the requested return date, your concurrence with no comment will be assumed.

Erick Matzke n 6855 Technical Coordinator (Ext.) Licensing Coordinator (Ext.)

[ ] Approved with no comment. [ ] Approved pending resolution of comments as noted.

Comments:_______________________________________________________________________________

Reviewer's Signature Date

FORT CALHOUN STATION NOD-QP-9.2 QUALITY PROCEDURE FORM R0 LICENSING CORRESPONDENCE REVIEW FORM SUMMARY LIC-12-0073 Date Issued: 5/23/12 Requested Return Date: 5/25/12 Name Date Comments Received No Comments1 Comments - How Resolved2 Susan Baughn 5/28/12 corrected John Herman none Steve Miller 5/27/12 X

Mike Smith none Corey Cameron none Scott Pallas none Chris Sterba none John Steinke 5/28/12 X

verbal Ken Dunham 5/24/12 X

L. Smith none Subject: LER 2012-004 Rev 0 Inadequate Analysis of Drift Affects RPS and ECCS Equipment NOTE - This submittal does ____ does not __X__ include documents/files on CD-ROM.3 NL Comment Coordinator Signature Date Responsible Dept. Manager (if required)

Date Review by Nuclear Licensing Supervisor Date 1 Attach only signed Licensing Correspondence Review Form.

2 Attach necessary documentation.

3 Ensure that the CD-ROM files are formatted properly for electronic information exchange (EIE) to the NRC. (Reference NL-17)