05000331/LER-2012-002, Regarding Loss of Low Pressure Coolant Injection Safety Function Due to Inoperable Instrumentation

Regarding Loss of Low Pressure Coolant Injection Safety Function Due to Inoperable Instrumentation

ML12059A083
Person / Time
Site:	Duane Arnold
Issue date:	02/27/2012
From:	Wells P NextEra Energy Duane Arnold
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NG-12-0045 LER 12-002-00
Download: ML12059A083 (5)

LER-2012-002, Regarding Loss of Low Pressure Coolant Injection Safety Function Due to Inoperable Instrumentation

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
3312012002R00 - NRC Website

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February 27,2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Licensee Event Report #2012-002-00

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DUANE ARNOLD NG-12-0045 10 CFR 50.73 Please find attached the subject report submitted in accordance with 10 CFR 50.73. This letter makes no new commitments or changes to any existing

commitments

Pe erWelis Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

NRC FORM 366 (10-2010)

PRINTED ON RECYCLED PAPER 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 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Duane Arnold Energy Center

2. DOCKET NUMBER 05000331

3. PAGE 1 OF 4

4. TITLE Loss of Low Pressure Coolant Injection Safety Function due to Inoperable Instrumentation

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 N/A DOCUMENT NUMBER 05000 12 29 11 2012 002 0

02 27 12 FACILITY NAME N/A DOCUMENT NUMBER 05000

9. OPERATING MODE

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)

X 50.73(a)(2)(vii) 1 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)

10. POWER LEVEL 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) 100%

20.2203(a)(2)(iv) 50.46(a)(3)(ii)

X 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)

X 50.73(a)(2)(v)(D)

VOLUNTARY LER

12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (Include Area Code)

Robert J. Murrell, Engineering Analyst (319) 851-7900 CAUSE SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

CAUSE

SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX N/A N/A N/A N/A N/A

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On December 29, 2011, at 2009, while operating at 100% power, during the performance of Surveillance Test Procedure (STP) 3.3.5.1-22, Recirculation Riser D/P A > B Instrument, three of the four recirculation riser differential pressure instruments required maintenance, and all for instruments required calibration. The four instruments support the Low Pressure Coolant Injection (LPCI) Loop Select logic by providing input that identifies and directs LPCI flow to the unbroken recirculation loop to mitigate the consequences of an accident. The conditions of the instruments found during the performance of the STP were such that reasonable assurance that the safety function of LPCI could be fulfilled during a design basis Loss of Coolant Accident (LOCA) did not exist. Reference Event Notification47561 dated December 30, 2011.

On December 29, 2011, at 2356, all of the instruments were either repaired or re-calibrated to restore the LPCI safety function. The cause of this event was a procedural deficiency that omitted guidance for the correct setting and adjusting of instrument microswitch plunger screws. This omission led to the microswitch sticking and instrument drift.

The safety significance of this was minimized by having all other Emergency Core Cooling Systems (ECCS) operable during the event.

(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)

PRINTED ON RECYCLED PAPER EIIS System and Component Codes:

BO - Residual Heat Removal/Low Pressure Coolant Injection System

Reporting Requirements

This event is being reported as an Event or Condition that Could Have Prevented Fulfillment of a Safety Function, 10CFR50.73(a)(2)(v)(B and D) and a Common-cause Inoperability of Independent Trains or Channels, 10CFR50.73(a)(2)(vii). Additionally, this event was reported under 10CFR50.72(b)(3)(v)(B),

Specified System Actuation, reference Event Notification 47561.