NG-16-0226, LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure

LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure

ML16342C568
Person / Time
Site:	Duane Arnold
Issue date:	12/06/2016
From:	Vehec T A NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-16-0226 LER 16-002-00
Download: ML16342C568 (5)

Text

December 6, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 Renewed Op. License No. DPR-49 Licensee Event Report 2016-002

• NG-16-0226 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.

Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC cc: Administrator, Region Ill, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324 NRG FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0113112017 (02-2014)

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.

\ ..... / LICENSEE EVENT REPORT (LER) Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC digits/characters for each block) 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Duane Arnold Energy Center 05000-331 1 OF 4 4. TITLE Unplanned RCIC lnoperability Results in Safety System Functional Failure 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 N/A N/A. FACILITY NAME DOCKET NUMBER 4 28 2016 2016 -002 -00 12 6 2016 NIA N/A 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all apply) D 20.2201 (b) D 20.2203(a)(3)(i)

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

D 50.73(a)(2)(vii) 1 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)(B)

D 50.73(a)(2)(viii)(E!)

D 20.2203(a)(2)(i)

D 50.36(c)(1

)(i)(A) D so.13(a)(2)(iii)

D 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 so.3s(c)(2)

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

D 13.11(a)(4) .lQO_% D 20.2203(a)(2)(iv)

D so.4s(a)(3)(ii)

D 50.73(a)(2)(v)(B)

D 13.11 (a)(5) -. D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(C)

D OTHER D 20.2203(a)(2)(vi)

D 50.73(a)(2)(i)(B)

[gj 50.73(a)(2)(v)(D)

Specify in Abstract below or in NRG Form 366A 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT I TELEPHONE NUMBER (Include Area Code) Bob Murrell, Licensing Engineer (319) 851-7900 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT MANU-REPORTABLE CAUSE SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX A BN N/A N/A y N/A N/A N/A N/A N/A 14. SUPPLEMENTAL REPORT EXPECTED 15.EXPECTED MONTH DAY YEAR DYES (If yes, complete 15. EXPECTED SUBMISSION DATE) IXI NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) On April 28, 2016, at 1055, while operating at 100% power, with no structures, systems, or components inoperable that contributed to this event, during the performance of Surveillance Test Procedure (STP) 3.3.6.1-28, Reactor Core Isolation Cooling (RCIC) System Steam Line Flow-High Channel Functional Test, the RCIC turbine received an unplanned trip signal and subsequent turbine stop valve closure. The cause of the event was a human performance error associated with verifying the correct installation location of the relay block. The turbine trip resulted in the unplanned inoperability of RCIC, therefore, this condition meets the reporting requirements of 10CFR50.73(a)(2)(v)(D).

At 1353 on April 28, 2016, the RCIC turbine was reset and RCIC was declared available.

The safety significance of this event was low since all Emergency Core Cooling Systems were operable during the time the RCIC turbine was tripped. NRG FORM 366 (02-2014)

NRC FORM 36GA (02-2014)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017

.. II s II::

• E ....... LICENSEE EVENT REPORT (LER) CONTINUATION SHEET 1. FACILITY NAME 2. DOCKET Duane Arnold Energy Center 05000-331 NARRATIVE I. Description of Event: 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 FOIA, Privacy and lnfomnation Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office cif 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.

YEAR 2016 6. LER NUMBER I SEQUENTIAL I NUMBER 002 REV NO. 00 2 3. PAGE OF 4 On April 28, 2016, at 0848, while operating at 100% power, with no structures, systems, or components inoperable that contributed to this event, Surveill.ance Test Procedure (STP) 3.3.6.1-28, Reactor Core Isolation Cooling (RCIC) System (System Code BN) Steam Line Flow -High Channel Functional Test was started as part of planned testing. The purpose of STP 3.3.6.1-28 is to demonstrate operability of the Steam Line High Differential Pressure (flow) isolation instruments (PDIS-2441 and PDIS-2442) of the RCIC system. During the performance of the STP, relay blocks are installed to inhibit the RCIC turbine trip associated with the RCIC automatic isolation logic under test. Step 7.3.2, which functional checks PDIS-2442, required the installation of three relay blocks, two associated with the inboard isolation signals and one associated with the turbine trip. During the performance of subsequent steps, the RCIC turbine received an unexpected trip signal and M0-2405, RCIC Trip Throttle Valve closed and Control Room annunciator 1 C04C (A-5) RCIC M0-2045 Turbine Trip actuated at 1055. Therefore, at 1055 on April 28, 2016, unplanned Limiting Condition for Operability (LCO), LCO 3.5.3 Condition A, RCIC Inoperable, was entered. Investigations determined that the relay block for the PDIS-2442 turbine trip signal was placed on the contacts for PDIS-2441.

At 1353 on April 28, 2016, the RCIC turbine was reset and RCIC was declared available and LCO 3.5.3 was exited. II. Assessment of Safety Consequences:

The safety significance of this event was low. During the time that RCIC was unavailable, all of the Emergency Core Cooling Systems (High Pressure Coolant Injection, Core Spray, and Low Pressure Coolant Injection) that would have initiated in response to an accident or transient were operable.

All components and systems actuated as designed due to this event. This event resulted in a Safety System Functional Failure and a Maintenance Preventable Functional Failure under the Maintenance Rule. Ill. Cause of Event: An Apparent Cause Evaluation (ACE) was completed for this event. The ACE determined that the direct cause of the RCIC turbine trip was the incorrect installation of relay block associated with inhibiting the RCIC turbine trip associated with the RCIC automatic isolation logic under test. NRG FORM 366A (02-2014)

NRC FORM 366A (02-2014)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER} 1. FACILITY NAME Duane Arnold Energy Center NARRATIVE CONTINUATION SHEET 2. DOCKET YEAR 05000-331 2016 6. LER NUMBER I SEQUENTIAL I NUMBER 002 REV* NO. 00 3 3. PAGE OF The Apparent Cause of the event was a human performance error associated with verifying the correct installation location of the relay block. Specifically, the use of Verification was not consistent with procedural requirements.

Contributing to this was inadequate placekeeping.

IV. Corrective Actions: Immediate Corrective Action At 1353 on April 28, 2016, the RCIC turbine was reset and RCIC was declared available and LCO 3.5.3 was exited.

• On May 6, 2016, a Human Performance Evaluation (HUPE) for the installation of the relay block on the incorrect contacts was completed.

On May 10, 2016, a Human Performance Department Clock Reset for the Instrument and Control Maintenance (ICM) department was completed to share lessons learned. Corrective Actions for Cause of Event The cause and contributing causes of this event were addressed by: 4 1. The implementation and tracking of the Management Action Response Checklist (MARC) process for the individuals involved with the installation of the relay in order to improve performance.

2. Development of Performance Focus Area for Training (PFAT) in ICM to ensure mastery of concurrent verification including proper placekeeping.

3. Development of a Dynamic Learning Activity for 'in cabinet' work to include expectations for concurrent verifications and placekeeping.

V. Additional Information:

Previous Similar Occurrences:

A review of NextEra Energy Duane Arnold Licensee Event Reports from the previous three years found no other instances of events related to unplanned inoperability of RCIC. NRC FORM 366A (02-2014)

NRC FORM 366A (02-2014)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) CONTINUATION SHEET 1. FACILITY NAME 2. DOCKET 6. LER NUMBER YEAR I SEQUENTIAL I NUMBER Duane Arnold Energy Center 05000-331 2016 002 NARRATIVE EllS System and Component Codes: BN -Reactor Core Isolation Cooling System Reporting Requirements:

This activity is being reported pursuant to the requirements of 1OCFR50.73(a)(2)(v)(D).

NRC FORM 366A (02-2014)

REV NO. 00 4 3. PAGE OF 4