05000219/LER-2014-004, Regarding Local Leak Rate Test Results in Excess of Technical Specifications
| ML14332A092 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/17/2014 |
| From: | Dostal J Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-14-097 LER 14-004-00 | |
| Download: ML14332A092 (3) | |
| 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 |
| 2192014004R00 - NRC Website | |
text
Exeton Generation 10 CFR 50.73 RA-14-097 November 17, 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 -0001 Oyster Creek Nuclear Generating Station Renewed Faity Operating License No. DPR-16 NRC Docket No. M-219
Subject:
Licensee Event Report (LER) 20144004-00, Local Leak Rats Test Results in Excess of Technical Specifications Enclosed is LER 2014-004-00, Local Leak Rate Test Results in Excess of Technical Specifications. This report is submitted in accordance with 10 CFR 50.73()X2XiXB), any operat"io.by te nt's Technica S--cific-Ons.
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (01-2014)
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Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections SLICENSEE EVENT REPORT (LER)
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by inmet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. It a means used to impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Oyster Creek, Unit 1 05000219 1 OF 2
- 4. TITLE Local Leak Rate Test Results in Excess of Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SE NUMBER EVO MONTH DAY YEAR N/ACLTNAEDKT NUMBE
~ ~FE UEN~AFE N/AIA T
/
i i
i iFACILITY NAME DOCKET NUMBER 09 18 201 2014 004
- - 00
- 11.
17 2014.N/A.N/
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
[I 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
N[
20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
N El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
E] 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 0 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER r~l
- r'-ISpecify in Abstract below or in 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v).(D)
Spc in A
Description of Event
On September 18, 2014, during refueling outage 01 R25 with the unit in cold shutdown, as-found LLRTs were performed on the main steam lines. The as-found LLRT of MSIV NSO3B (V-1-8) failed to meet the acceptance criteria of Technical Specification 4.5.D.2. The acceptance criteria is less than or equal to 11.9 scfh at 20 (+3/-0) psig. The actual measured leakage was 16 scfh at 20.3 psig.
The valve was disassembled, inspected, the poppet assembly was replaced, and the valve seat was machined. The
- cause of failure was identified to be due to material wear on the poppet assembly and the valve seat. An as-left LLRT was performed with an acceptable reading of 0.621 scfh at a test pressure of 20.3 psig.
Analysis of Event
The MSIVs are containment isolation valves designed to minimize coolant loss from the vessel, and the resultant offsite dose, in the event of a main steam line accident. There are two main steam lines with 2 MSIVs in series in each line. The acceptance criteria, for these valves, is less than or equal to 11.9 scfh when tested at greater than or equal to 20 (+3/-0) psig. Exceeding the leakage limits specified in the Technical Specifications could result in unacceptable dose rates downstream of the MSIVs during an accident.
The safety significance of this event is considered minimal. The leakage past NS03B (V-1 -8) would have been limited by the leak rate of the outboard MSIV NS04B (V-1 -10) in the same header, which met the LLRT acceptance criteria of Technical Specification 4.5.D.2 when tested in 01 R25. The leak rate of NS04B provided adequate margin between projected offsite dose and 10 CFR 100 guidelines.
Cause of Event
The cause of failure was due to material wear on the poppet and the valve seat.
Corrective Actions
The valve was disassembled, inspected, the poppet assembly was replaced, and the valve seat was machined.
The as-left LLRT on MSIV NSO3B was successfully completed.
Previous Occurrences
LER-ýb06-003-00, Local Leak Rate Test Results in Excess of Technical Specifications LER 2004-006-00, Local Leak Rate Test Results in Excess of Technical Specifications Component Data Components IEEE 805 System ID IEEE 803A Function MSIV SB ISV