05000331/LER-2010-006, Regarding Standby Liquid Control Test Tank Seismic Analysis
| ML110070763 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 01/07/2011 |
| From: | Costanzo C NextEra Energy Duane Arnold |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-11-0008 LER 10-006-00 | |
| Download: ML110070763 (5) | |
| 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 |
| 3312010006R00 - NRC Website | |
text
January 7, 2011 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 #2010-006-00 NEXTera M
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ARNOLD NG-11-0008 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
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Christopher R. Costanzo 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 Standby Liquid Control Test Tank Seismic Analysis
- 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 11 10 10 2010 006 0
01 07 11 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) 5 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)
X 50.73(a)(2)(v)(A) 73.71(a)(4) 0%
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)
X 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
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
X NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
As part of an Operating Experience review (Event Notification 46372), the seismic analysis for the Standby Liquid Control (SBLC) System test tank was questioned. On November 10, 2010, engineering analysis concluded that when the test tank was 3/4 full of water, as directed by SBLC surveillance test procedures (STPs), it would not withstand Design Basis Earthquake (DBE) seismic loads and would possibly have caused a failure of safety-related, seismically qualified SBLC equipment. Therefore it has been concluded that the SBLC system was not operable in the past when the test tank was 3/4 full of water. The SBLC test tank was drained of water on November 11, 2010. Corrective actions taken included revising applicable procedures to require that the SBLC test tank be drained when the SBLC system is required to be operable.
The cause of this event was a latent design issue that occurred during construction.
This event is being reported as an event or condition that at the time of discovery could have prevented fulfillment of a safety function under 10 CFR 50.73 (a)(2)(v)(A)/(D), a condition prohibited by Technical Specifications (TS) under 10 CFR 50.73 (a)(2)(i)(B), and a common-cause inoperability of independent trains or channels under 10 CFR 50.73 (a)(2)(vii).
There were no actual safety consequences and no effect on public health and safety as a result of this 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 V.
Additional Information
Previous Similar Occurrences:
A review of Licensed Event Reports (LERs) from the past 5 years did not identify any previous similar occurrences.
EIIS System and Component Codes:
BR - Standby Liquid Control System (BWR)
Reporting Requirements
This event is being reported as an event or condition that at the time of discovery could have prevented fulfillment of a safety function under 10 CFR 50.73 (a)(2)(v)(A)/(D), a condition prohibited by Technical Specifications (TS) under 10 CFR 50.73 (a)(2)(i)(B), and a common-cause inoperability of independent trains or channels under 10 CFR 50.73 (a)(2)(vii).