05000331/LER-2013-005, Condition Prohibited by Technical Specifications - Main Steam Line Steam Leak Detection
| ML14002A257 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/20/2013 |
| From: | Richard Anderson NextEra Energy Duane Arnold |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-13-0458 LER 13-005-00 | |
| Download: ML14002A257 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3312013005R00 - NRC Website | |
text
NExTeram EN ERGY December 20, 2013 NG-1 3-0458 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 #2013-005 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
TchardL. Andersko Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC l~wL 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)
, the (See reverse for required number of NRC may not conduct or sponsor, and'a person is not required to respond to, the digits/characters for each block) information collection.
I. FACILITY NAME
- 2. DOCKET NUMBER
- 3. PAGE Duane Arnold Energy Center 05000331 1 OF 3
- 4. TITLE Condition Prohibited by Techmical Specifications - Main Steam Line Steam Leak Detection
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MOTIAY YA FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FA 05000 1NUMBER NO.
N/A 05000 06 21 2013 2013 005 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 appsly)
[] 20.220 1(b)
[]
20.2203(a)(3)(i)
[]
50.73(a)(2R1)i)(C)Q 50.73(a)(2)(vii) 1 20.2201(d)
E] 20.2203(a)(3)(ii)
E]
50.73(a)(2)(iil(A)
D 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
E:1 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
E:1 50.73(a)(2)(viii)(B)
F-1 220.2203(a)(2)(i)
D]
50.36(c)(1)(i)(A)
[]
50.73(a)(2)(iii)
[-]
50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E] 20.2203(a)(2)(ii)
E] 50.36(c)(l)(ii)(A)
D 50.73(a)(2)(iv)(A)
D] 50.73(a)(2)(x)
El 20.2-203(a)(2)(iii)
[]
50.36(c)(2)
ED 50.73(a)(2)(v)(A)
E:]
73.7 1(a)(4) 100%
E/ 1 2(.2203(a)(2)(iv)
[
50.46(a)(3)(ii)
[
50.73(a)(2)(v)(B)
E]
73.71(a)(5)
D 20.2203(a)l2)(v)
F] 50.73(al(21(i)(A)
[
50.73(a)(2)(v)(C)
[
OTHER Dj 20.2203(a)(2)(vi)
N' 50.73(a)(2)(i)(B)
F]
50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (Incl/c.Area Codfe)
Robert J. Murrell, Engineering Analyst (319) 851-7900CAUSE SYSTEM COMPONENT MANU-REPORTABLE I
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR YES (If yes, conpilet 1.5. EXPECTED SIBAII';?NNI DATE)
NO SUBIESION ABSTRACT (Linit to 1400 spaces, i.e., approximately 15 single-spaced t~pewritten lines)
On June 21, 2013, while operating at 100% power, Temperature Indicating Switch (TIS) 4480 Channel 1, Turbine Building Main Steam Line 'D', was found to have spiked from 133F to 150F. Since the indication was within the acceptance criteria of_> 70F and < 175F of Surveillance Test Procedure (STP) 3.0.0-01, Instrument Checks, the instrument was not declared inoperable. Oil June 22, 2013, TIS-4480, Channel I was again found to be indicatingt erratically. A review of TIS-4480 indications from May 5, 2013, indicated a trend was present. Therefore, TIS-4480 was declared inoperable oil June 22, 2013. A Past Operability Review (POR) was not completed based on the conclusions of a previous similar event that occurred in December 2012, reference License Event Report (LER) 2013-004. On October 22, 2013, a POR was completed and concluded that TIS-4480 was inoperable from May 5, 2013 to June 22, 2013. Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, Required Action D. 1, requires the associated Main Steam Line to 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-4480 was replaced and returned to service on June 23, 2013.
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 June 23, 2012, TIS-4480 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