05000331/LER-2013-004, Regarding Condition Prohibited by Technical Specifications - Main Steam Line Steam Leak Detection
| ML14002A258 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  (DPR-049) |
| Issue date: | 12/20/2013 |
| From: | Richard Anderson NextEra Energy Duane Arnold |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-13-0459 LER 13-004-00 | |
| Download: ML14002A258 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3312013004R00 - NRC Website | |
text
NZxTeraM ENERG, Y ARNOLD December 20, 2013 NG-1 3-0459 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 Renewed Op. License No. DPR-49 Licensee Event Report #2013-004 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. Anderson Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC I
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
, the (See reverse for required nttrnber of NRC may nrot conduct or sponsor, and a person is riot required to respond to, the digits/characters for each block) inforiration collection.
- 3. PAGE Duane Arnold Energy Center 05000331 1 OF 3
- 4. TITLE Condition Prohibited by Technical Specifications - Main Steam Line Steam Leak Detection
- 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 INUMBER NO.
N/A 05000 12 23 2012 2013 004 0
12 20 13 FACILITY NAME DOCKET NUMBER N/A 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 20.2201(b)
Ej 20.2203(a)(3)(i)
[
50.73(a)(2)ii)(C)
[
50.73(a)(2)(vii) 1F--1 20.2201 (d)
[]
20.2203(a)(3)(ii)
[]
50.73(a)(2)(ii)(A)
F-1 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)14)
F 50.73(a)(2)ii)(B)
[
50.73(a)12)(viii)(B)
[] 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
[]
50.73(a)(2)1iii)
[]
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)
DJ 50.73(a)12)(x)
[] 20.2203(a.1(2)(iii)
[ý]
50.36(c)(2)
[]
50.73(a)(2)(v)(A)
[]
73.71(a)(4) 100%
D 20.2203(a)(2)(iv)
E]
50.46(a)(3)(ii)
]
50.73(a)12)(v)(B)
E] 73.71(a)(5)
FD 20.2203(a)(2)lv)
[
50.73(a)(2)(i)(A)
D 50.73(a)12)(v)(C)
[
OTHER ED 20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (lnchrile A rea Cuole)
Robert J. Murrell, Engineering Analyst (319) 851-7900CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT IvMANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR E
E
.E NO SUBMISSION YE (fye.copet 5.EVPCEDSBMSIO
.4E IN DATE ABSTRACT (Limit to 1400 spaces, i.e., approxintately 15 single-spaced tvpewrrittetn lines)
On December 23, 2012, while operating at 100% power, Temperature Indicating Switch (TIS) 4479 Channel 1, Turbine Building Main Steam Line 'C', was found indicating 183F. This indication did not meet the acceptance criteria of_> 70F and < 175F of Surveillance Test Procedure (STP) 3.0.0-01, Instrument Checks. Subsequently, the indicated temperature returned to within its acceptance criteria and no actions were taken to declare TIS-4479 inoperable. On December 28, 2012, TIS-4479, Channel I was again found to be outside of its surveillance requirements and was declared inoperable. A Past Operability Review (POR), completed on March 12, 2013, concluded that TIS-4479 was operable froln December 23, 2012 to December 28, 2012. The POR conclusion was based on a lack of firn evidence indicating when the TIS was no longer performing its required safety function. A subsequent revision to the POR, completed on October 18, 2013, deterinined that TIS-4479 was inoperable from December 23, 2013 to December 28, 2012. Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, Required Action D. 1, requires the associated Main Steam Line be isolated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Neither of these Required Actions were completed. Therefore, this condition constituted a condition prohibited by TS. The causes of this event were an undetermined failure internal to the TIS and inadequate procedure guidance on how to perform a qualitative channel check as required by TS. TIS-4479 was replaced and returned to service on December 29, 2012.
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)
III.
Cause of Event
A Root Cause Evaluation was completed. The evaluation identified the following root causes of this event.
Root Cause 1 - An undetermined failure internal to the TIS affected its ability to provide accurate temperature indications.
Root Cause 2 - Procedural guidance of STP 3.0.0.0-01, Instrument Checks, did not include a requirement to perform a qualitative channel check as required by TS.
IV.
Corrective Actions
On December 29, 2012, TIS-4479 was replaced and returned to service.
In order to address the root cause of this event, the following corrective actions will occur.
A modification will be developed and implemented to replace the current Chromlox TIS with Yokogawa Recorders or other suitable instruments.
STP 3.0.0-01, Instrument Checks, will be revised to clearly state that a qualitative assessment of instrument performance should be performed for ANY instrument included in the STP that is being assessed to meet its CHANNEL CHECK surveillance requirement, not just for cases when the specified quantitative assessment cannot be performed.
V.
Additional Information
Previous Similar Occurrences:
A review of License Event Reports from the past 5 years did not identify any similar occurrence.
EIIS System and Component Codes:
IM - Temperature Monitoring System.
Reporting Requirements
This event is being reported as an Operation or Condition Prohibited by TS, 10CFR50.73(a)(2)(i)(B).PRINTED ON RECYCLED PAPERPRINTED ON RECYCLED PAPER