05000387/LER-2007-001, Re Automatic Actuation of C Emergency Service Water Pump Due to Improper Alignment During Emergency Diesel Generator Testing
| ML072120601 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/19/2007 |
| From: | Gannon C Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6239 LER 07-001-00 | |
| Download: ML072120601 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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 |
| 3872007001R00 - NRC Website | |
text
C. J. Gannon Vice President Nuclear Operations PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3050 Fax 570.542.1504 cjgannon@pplweb.com 0 00,00~I M JUL 1 9 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OPI-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2007-001-00 PLA-6239 Docket Nos. 50-387 and 50-388 Attached is Licensee Event Report 50-387/2007-001-00. This event was determined to be reportable, per 10 CFR 50.73(a)(2)(iv)(A), as an event that resulted in an unplanned automatic actuation of an emergency service water (ESW) pump. On May 24, 2007 at 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br />, the 'C' ESW pump started as a result of a manual start of the 'E' emergency diesel generator (EDG). The pump, which should have been manually started prior to the EDG start, automatically started as designed. All plant equipment, including the 'C' ESW pump, operated as expected.
This event resulted in no actual adverse consequences to the health and safety of the public.
There are no commitments associated with this Licensee Event Report.
Ssidt-Nuclear Operations Attachment cc:
Mr. A. J. Blamey, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Sr. Project Manager Mr. R. R. Janati, DEP/BRP Mr. R. Osborne, Allegheny Electric
NRC U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Susquehanna Steam Electric Station - Unit 1
- 2. DOCKET NUMBER
- 3. PAGE 05000387 1 OF3
- 4. TITLE Automatic Actuation of 'C' Emergency Service Water Pump Due to Improper Alignment During Emergency Diesel Generator Testing
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL REV FACILITY NAME DOCKET NUMBER NUMBER NO MONTH DAY YEAR Susquehanna Unit 2 05000388 FACILITY NAME DOCKET NUMBER 05 24 2007 2007 001 00 07 19 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 El 20.2201(b)
[I 20.2203(a)(3)(i)
[E 50.73(a)(2)(i)(C)
E] 50.73(a)(2)(vii)
- 10. POWER LEVEL [E 20.2201(d)
El 20.2203(a)(3)(ii)
[E 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) 100%
El 20.2203(a)(1)
[I 20.2203(a)(4)
E] 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[1%
20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
[E 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
El 20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
E] 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
[E 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
[E 50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
El OTHER Voluntary Report E] 20.2203(a)(2)(vi)
[E 50.73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
ANALYSIS / SAFETY SIGNIFICANCE This event is reportable as an event that resulted in an unplanned automatic actuation of an ESW system per 10 CFR 50.73(a)(2)(iv)(A).
There were no actual or potential consequences as a result of the automatic start of the 'C' ESW pump. The event does not represent a degraded condition but rather an unexpected start of a pump designed to automatically start.
Athough the pump started as designed, the start was not anticipated by Operations. The 'A' and 'B' ESW pumps were already running and provided the necessary cooling to the 'E' DG that had just started. The preferred pump alignment is to have one pump in each loop running to ensure optimal performance relative to the pump curve, but the system design provides a sufficient flow path to support having all four ESW pumps operating. The significance of the event is limited to an unnecessary actuation of a system provided to mitigate the consequences of a significant event.
CORRECTIVE ACTIONS
- 1. The operators involved in the event have been coached and counseled.
- 2.
A communication to on-shift Operations personnel was issued that discussed the event and reinforced expectations for procedure compliance.
- 3.
Training will be provided to on-shift and work control center Operations personnel regarding this event and will include emphasis on the human performance and supervisory oversight expectations that were not met during the event.
ADDITIONAL INFORMATION
Past Similar Events: LER 2004-001-00, Docket No. 387/License No. NPF-14 Failed Component: None