05000461/LER-2010-002, Excessive Leakage Through Feedwater Isolation Valve 1B21-F032B
| ML101031095 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/01/2010 |
| From: | Kearney F Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| U-603951 LER 10-002-00 | |
| Download: ML101031095 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(b)(2)(v) 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 |
| 4612010002R00 - NRC Website | |
text
Exelen Nudear Clinton Power Station 8401 Power Road Clinton, IL 61727 U-603951 SRRS 5A.108 April 1, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Licensee Event Report 2010-002-00 Enclosed is Licensee Event Report (LER) No. 2010-002-00: Excessive Leakage through Feedwater Isolation Valve 1 B21 -F032B. This report is being submitted in accordance with 10 CFR 50.73 (a)(2)(ii), degraded or unanalyzed condition, and 10 CFR 50.73 (b)(2)(v), a condition that could have prevented the fulfillment of a safety function.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this report, please contact Mr. D. J. Kemper at (217) 937-2800.
Respectf ully, A. Ke rney Site Vice President Clinton Power Station JLP/blf
Enclosures:
Licensee Event Report 2010-002-00 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - IEMA Division of Nuclear Safety "l OA
~1 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
/3. PAGE Clinton Power Station, Unit 1 05000461 1 OF 3
- 4. TITLE Excessive Leakage through Feedwater Isolation Valve 1 B21 F032B
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR Y
SEQUENTIAL REV MOT D
Y FACILITY NAME DOCKET NUMBER MOT A ER YEAR NUMBER NO.
MONTH DAY YEAR 05000 IFACILITY NAME DOCKET NUMBER 02 03 2010 2010 002 00 04 01 2010 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[l 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii) 2 [E
20.2201(d)
El 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
[I 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) 0l 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4) 3%
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
ED 50.73(a)(2)(v)(C)
[E OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in Once the condition was identified, prompt actions were taken to ensure that the affected penetration was isolated to comply with TS. Once the plant was in Mode 4, corrective actions were taken to repair and re-test the valve to ensure leakage rates were restored to within acceptance limits.
No actual leakage path existed. The motor operated feedwater containment isolation valve, 1 B21 -F065B, had been in the closed position prior to plant startup. Once the condition was identified, 1 B21 -F065B was verified to be in the closed position, and the power was removed from its operator.
CORRECTIVE ACTIONS
The valve was repaired by lubricating the valve actuator. Following completion of repairs, the valve was stroked.
An LLRT was completed at 1330 on February 4, 2010 with satisfactory results (0.15 gpm). Mode 2 was entered at 1533 on February 4, 2010.
Preventive maintenance activities will be established to lubricate and overhaul the 1B21-F032 actuators. The cause evaluation recommends lubrication of the actuators on a six-year frequency.
PREVIOUS OCCURRENCES
This is the first failure of the 1B21-F032B since the installation and implementation of a Feedwater Leakage Control system in 2000. In refueling outage C1 Ri 1, which occurred in January 2008, a similar testing failure occurred on valvelB21-F032A with a leak rate result of 3.75 gpm. Following the LLRT failure, the internals of the valve were inspected and found to be satisfactory. Observation of a valve stroke with the valve partially disassembled revealed uneven and un-repeatable side to side movement of the actuator. The disc was cleaned and the actuator was re-lubricated resulting in proper seating of the valve. This event was not reported, and no causal analysis was performed. The testing failure of valve 1 B21 -F032A is being reported under this LER.
The following LERs occurred prior to the installation of a Feedwater Leakage Control system:
LER 92-003 dated March 31, 1992 - Local Leak Rate Test Failure of Feedwater Containment Isolation Valves Results in Total Leakage Rates in Excess of Technical Specification and 10CFR50 Appendix J Limits.
LER 95-002-01 dated June 6, 1995 - Local Leak Rate Test Failures of Feedwater Containment Isolation Valves Results in Total Leakage Rates Greater than Technical Specification and 10CFR50, Appendix J Limits.
LER 96-013-01 dated July 24, 1997 - Inadequate Actuator Design and Failure to Recognize Limitations of Resilient Seat Design Result in Local Leak Rate Test Failures of Feedwater Containment Isolation Valves and Total Leakage Rates Greater than Technical Specification and 10CFR50, Appendix J Limits.
COMPONENT FAILURE DATA
Feedwater valves 1 B21 -F032A and 1 B21 -F032B are 20-inch, air assisted, non-slam tilting disc check valves, manufactured by Anchor Darling Valve Company.PRINTED ON RECYCLED PAPER NRIC FORM 366A (9-2007)
PRINTED ON RECYCLED PAPER