05000272/LER-2006-002, Regarding Inoperability of the Auxiliary Feedwater System Due to a Partially Opened Damper
| ML063410226 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/27/2006 |
| From: | Fricker C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N06-0448 LER 06-002-00 | |
| Download: ML063410226 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 2722006002R00 - NRC Website | |
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC NOV2 7 20M 1 OCFR50.73 LR-N06-0448 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station Unit 1 Facility Operating License No. DPR-70 NRC Docket No. 50-272
Subject:
Inoperability of the Auxiliary Feedwater System Due to a Partially Opened Damper This Licensee Event Report, "Inoperability of the Auxiliary Feedwater System Due to a Partially Opened Damper," is being submitted pursuant to the requirements of the 10CFR50.73(a)(2)(i)(B), 10CFR50.73(a)(2)(v)(B), and 10CFR50.73(a)(2)(ii)(B) Code of Federal Regulations.
If you have any questions concerning this report, please contact E. H. Villar at (856) 339 - 5456.
- Sincer y
anl ricker Salem Plant Manager Attachments (1) 95-2168 REV. 7/99
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the
- 13. PAGE Salem Generating Station - Unit 1 05000272 1 OF 4
- 4. TITLE Inoperability of the Auxiliary Feedwater System Due to a Partially Opened Damper
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FCLT AEDCE U1E NUMBER NO.
FACILITY NAME DOCKET NUMBER 09 28 2006 2006 002 00 11 27 2006
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
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- 10. POWER LEVEL [E 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)
El 20.2203(a)(2)(iii) 0l 50.36(c)(2)
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[E 50.46(a)(3)(ii)
[D 50.73(a)(2)(v)(B)
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El 50.73(a)(2)(v)(C)
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El 50.73(a)(2)(v)(D)
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- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
E. H. Villar, Senior Licensing Engineer 1 856-339-5456CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIXD FACTURER TO EPIX X
I 14.SUPLEENTL RPOT EPECEDI&EPECED MONTH DAY YEAR SUBMISSION El YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0D NO DATE kBSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On September 28, 2006, Auxiliary Building Ventilation system damper 1ABS20 was discovered to be partially open. This damper is normally closed and opens when the room cooler is in service. The damper is located in the ceiling of the turbine driven Auxiliary Feedwater pump enclosure and exhausts air from the enclosure to the surrounding pump area during room cooler operation. The safety function of the damper is to close in a steamline break inside the enclosure, separating a harsh environment area from a mild environment area. With the damper partially opened and unable to close as designed, the operability of the motor driven Auxiliary Feedwater Pumps could not be established. The failed damper actuator was replaced and the damper was retested satisfactorily. The cause of the failed damper actuator was attributed to a higher than design air pressure supply to the actuator.
This event is reportable in accordance with 10CFR50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications; 10CFR50.73(a)(2)(v)(B), any event or condition that alone could have prevented the fulfillment of a safety function of a system needed to remove residual heat; and 10CFR50.73(a)(2)(ii)(B) an event or condition that resulted in the nuclear power plant, including its principal safety barriers being seriously degraded or in an unanalyzed condition that significantly degrades plant safety.
(if more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
CORRECTIVE ACTIONS
- 1. The actuator on damper 1ABS20 was replaced; the regulator set within the proper operating limits and the equipment retested satisfactorily.
- 2. The Unit 2 damper 2ABS20 was verified working properly.
- 3. The failed actuator was sent for analysis to determine the cause of failure.
- 4. A review of damper actuator design, preventive maintenance of the component, and operating procedures will be performed to improve damper reliability.
COMMITMENTS
No commitments are made in this LER.