05000331/LER-2012-005, Regarding Secondary Containment Damper Inoperable, Condition Prohibited by Technical Specifications

Regarding Secondary Containment Damper Inoperable, Condition Prohibited by Technical Specifications

ML13024A208
Person / Time
Site:	Duane Arnold
Issue date:	01/23/2013
From:	Richard Anderson NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-13-0020 LER 12-005-00
Download: ML13024A208 (4)

LER-2012-005, Regarding Secondary Containment Damper Inoperable, Condition Prohibited by Technical Specifications

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
3312012005R00 - NRC Website

text

NEXTera M

ENERGV~

January 23, 2013 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 #2012-005-00

~RNOLD

~

DUANE NG-13-0020 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

~~~CF~

Richard L. Anderson 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 3

4. TITLE Secondary Containment Damper Inoperable, Condition Prohibited by Technical Specifications

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 DOCKET NUMBER 05000 11 24 12 2012 005 0

01 23 13 FACILITY NAME N/A DOCKET 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) 50.73(a)(2)(vii) 4 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) 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) 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 X

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

NO SUBMISSION DATE 03 15 13 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On November 24, 2012, with the reactor shutdown for a planned refueling outage, Surveillance Test Procedure (STP) 3.6.4.1-01B, which demonstrates the ability of the B Standby Gas Treatment System to maintain secondary containment under calm wind conditions, failed to achieve a 0.25 inches water gauge (wg) vacuum at a normal SBGT flow rate of 3800 cubic feet per minute (cfm). Subsequent investigations revealed that secondary containment isolation damper 1VAD017B1 was partially open. Further troubleshooting confirmed that maintenance performed on June 21, 2012 caused the damper to remain partially open. In order to comply with the Technical Specification (TS)

Limiting Condition for Operations (LCO), 1VAD017A1 was de-energized in the closed position. With the affected flow path isolated, the B SBGT train was able to achieve the required 0.25 in. wg vacuum. Since 1VAD017B1 was inoperable from June 21, 2012 to November 24, 2012, it violated its TS LCO action statement 3.6.4.2.A.1 which requires an inoperable flow path be isolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of inoperability. Therefore, this event resulted in a condition prohibited by TS. A root cause evaluation is being performed to determine the cause and corrective actions for this event and a supplemental report is expected to be issued by February 21, 2013.

The safety significance of this event was minimized by the fact that the A damper in the flow path containing 1VAD017B1 was fully operable during the time in question and testing results show that SBGT was capable of achieving 0.25 in. wg vacuum with 1VAD017A1 closed.

(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 A root cause evaluation is currently being conducted. Once the evaluation is complete, a supplemental report will be issued containing the corrective actions for this event.

V.

Additional Information

Previous Similar Occurrences:

A review of License Event Reports from the past 5 years identified one similar occurrence of secondary containment being affected by an inoperable damper. This event is documented in LER 2012-003, Secondary Containment Damper Failures.

EIIS System and Component Codes:

NH - Reactor Containment Building.

Reporting Requirements

This event is being reported as an Operation or Condition Prohibited by TS, 10CFR50.73(a)(2)(i)(B).