05000331/LER-2012-004, Regarding High Pressure Coolant Injection Declared Inoperable
| ML12257A480 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/30/2012 |
| From: | Richard Anderson NextEra Energy Duane Arnold |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-12-0346 LER 12-004-00 | |
| Download: ML12257A480 (4) | |
| 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 |
| 3312012004R00 - NRC Website | |
text
NExTera ENERGYP UARNOLD August 30, 2012 NG-1 2-0346 10 CFR 50.73 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 #2012-004-00 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
Richard L. Andersokn 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 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
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, LICENSEE EVENT REPORT (LER)
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. Ifa means used to impose an information collection does not display a currently valid OMB control (See reverse for required number of number, the NRC may not conduct or sponsor, and a person is not required to respond digits/characters for each block) to, the information collection.
- 3. PAGE Duane Arnold Energy Center 05000331 1 OF 3
- 4. TITLE High Pressure Coolant Injection Declared Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO.
N/A 05000 07 02 12 2012 004 0
08 30 12 FACILITY NAME DOCKET NUMBER 0
N/A 05000
- 9. OPERATING MODE 1I. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
E] 20.2201(b)
LI 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C)
[] 50.73(a)(2)(vii) 1 E
20.2201(d)
E] 20.2203(a)(3)(ii)
F-i 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
[
20.2203(a)(4)
LI 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
D 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 F] 20.2203(a)(2)(ii)
F] 50.36(c)(1)(ii)(A)
F-1 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 0]
20.2203(a)(2)(iii) 0 50.36(c)(2)
[]
50.73(a)(2)(v)(A) 73.71(a)(4) 100%
[] 20.2203(a)(2)(iv)
E]
50.46(a)(3)(ii)
[]
50.73(a)(2)(v)(B) 73.71(a)(5)
El 20.2203(a)(2)(v)
E] 50.73(a)(2)(i)(A) j]
50.73(a)(2)(v)(C)
[
OTHER El 20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B)
[
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) 851-7900CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR I"--1SUBMISSION El YES (Ifyes, complete 15. EXPECTED SUBMISSION DATE)
I2 NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On July 2, 2012, at 15:05, while operating at 100% power, a spurious isolation of the High Pressure Coolant Injection (HPCI) Outboard Steam Supply Valve and Outboard Torus Suction Valve occurred. The isolation resulted from a trip of the HPCI Steam Leak Detection (SLD) system. Immediate investigations into the event determined that there was no steam leak and the probable cause was from a bad connection in the SLD system. Subsequent investigation identified a broken solid conductor thermocouple extension wire. The wire was damaged earlier in the day as part of maintenance activities investigating erroneous readings on unrelated circuits. The damaged wire was replaced and HPCI was declared operable on July 3, 2012, at 0002. The root cause of this event was an inadequate installation position of a recorder in the control room panel. The recorder was installed in such a manner that the removal of its terminal cover placed excessive stress on the thermocouple wire resulting in its failure.
This condition was reported under 10 CFR 50.72(b)(3)(v)(D), any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of the structures or systems that are needed to mitigate the consequences of an accident. Reference EN#48064.
The safety significance of this event was minimized by the fact that all other Emergency Core Cooling Systems (ECCS) remained fully operable during the time that HPCI was inoperable.
NRC FORM 366 (10-2010)
PRINTED ON RECYCLED PAPER (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
Completion of an inspection of other thermocouple wires associated with recorders installed by the Engineering Change Package that installed the recorder identified as the root cause of this event.
Revision of the model Work Order associated with work inside the cabinet containing the SLD thermocouple wires to require maintenance technicians be briefed on the susceptibility of the SLD wires to break.
V.
Additional Information
Previous Similar Occurrences:
A review of License Event Reports from the past 5 years did not identify any previous similar occurrences where HPCI was declared inoperable due to an invalid SLD isolation.
EIIS System and Component Codes:
BJ - High Pressure Coolant Injection System (BWR)
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)(D). Additionally, this event was reported under 50.72(b)(3)(v)(D), any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of the structures or systems that are needed to mitigate the consequences of an accidentjidiekdihfjiejfieikdbobmurrelll. Reference EN#48064.