05000293/LER-2008-007, Momentary Loss of All 345kv Off-Site Power to the Startup Transformer from Switchyard Breaker Fault
| ML090570510 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/12/2009 |
| From: | Bronson K Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.09.005 LER 08-007-00 | |
| Download: ML090570510 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 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)(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 10 CFR 50.73(a)(2)(iv), System Actuation |
| 2932008007R00 - NRC Website | |
text
S'-Entergy Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Kevin H. Bronson Site Vice President February 12, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35 Licensee Event Report 2008-007-00 LETTER NUMBER: 2.09.005
Dear Sir or Madam:
The enclosed Licensee Event Report (LER) 2008-007-00, " Momentary Loss of all 345kv Off-Site Power to the Startup Transformer from Switchyard Breaker Fault" is submitted in accordance with 10 CFR 50.73.
This letter contains no commitments.
Please do not hesitate to contact Mr. Joseph R. Lynch, (508) 830-8403, if there are any questions regarding this submittal.
Sincerely, RMB Enclosure cc:
Mr. James S. Kim, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North O-8C2 11555 Rockville Pike Rockville, MD 20852 INPO Records 700 Galleria Parkway Atlanta, GA 30399-5957 Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulator Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station
Enclosure to Letter Number 2.09.005 (6 pages)
NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 Expires 8/31/2010
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE PILGRIM NUCLEAR POWER STATION 05000-293 1 of 6
- 4. TITLE Momentary Loss of all 345kv Off-Site Power to the Startup Transformer from Switchyard Breaker Fault
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL NUMBER REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR N/A.
05000 FACILITY NAME DOCKET NUMBER 12 20 2008 2008 007 00 02 12 2009 N/A 05000
- 9. OPERATING 1
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: (Check all that apply)
MODE_
N 20.2201 (b) 22.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73 (a (2(vii)
- 10. POWER 22.2202(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A)
LEVEL 0
20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 1 20"2203(a)(2)(i) 50.36(3)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2 (ix)(A) 20.2203(a)(2)(ii) 50.36(3)(1 )(ii)(A)
X 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below L
- or in
EVENT DESCRIPTION
On December 20, 2008 at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />, a flashover of a phase B arc horn on the Line 355 bus section occurred due to accumulated snow falling from the overhead bus and bridging the gap to the arc horn. (This is the Direct Cause of this event.) In response to this, ACB-102 opened per design, but ACB-103 opened in response to a transfer trip signal from the Auburn Street Station, which is associated with Line 342. Since the fault was not on Line 342, Auburn Street Station should not have sent this transfer trip signal. The tripping of the ACB-102 and ACB-103 resulted in a loss of the SUT supply and transferring of Pilgrim's safety busses to the EDGs. Subsequently, Lines 342 and 355 re-energized, ACB-102 and ACB-103 auto reclosed, and remained closed per design.
The plant was in a hot shutdown condition with the mode switch in the REFUEL position (to support front panel checks) with the reactor at 0 percent power due to a flashover on ACB-105 during the previous day's severe winter storm which caused a turbine generator trip and load reject approximately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> earlier (Ref.
LER 2008-006-00). Reactor pressure was = 546 psig decreasing. Two sea water pumps, one condensate pump and one reactor feed pump were in operation for heat removal from the reactor. The following is a time sequence of equipment operation when power from the SUT was lost:
i. 10:45 - Switchyard breakers ACB-102 and ACB-103 opened and subsequent momentary loss of the SUT.
ii. 10:45 - EDG's A & B auto started and re-energized busses A5 & A6. Power was lost to Busses Al-A4, and the operating sea water, condensate and reactor feed pumps tripped.
iii. 10:52 - RCIC was placed. in service for level and pressure control.
iv. 11:14 - HPCI was placed in service to augment reactor pressure control.
v.
11:14 - RHR pump "A" was manually started to support torus cooling operations.
vi. 11:16 - RHR pump "B" was manually started to support torus cooling operations.
Plant Operations kept the EDG's in service for several hours to supply power to the emergency busses due to this grid disturbance before successfully returning the busses to their normal electrical system line-up.
An eyewitness account by personnel performing an infrared thermographic survey of the ACB-102 disconnect switch in the switchyard observed a flashover at the ACB-102 Line 355 phase B arc horn. This was caused by accumulated snow falling from the overhead bus and bridging the gap to the arc horn, initiating the flashover. ACB-103 and ACB-102, (in that order), auto reclosed, and re-energized the SUT.
Per plant design, when a fault occurs on Line 355 or its associated switchyard bus section, ACB-102 and ACB-105 open automatically to isolate the fault in response to both Pilgrim Station and Bridgewater protective relaying. ACB-103 should remain closed and continue to supply power to the SUT. The directional ground overcurrent relay (DGOR) at Auburn Street Station, which is designed to respond to a disturbance up to 85 percent of Line 342 length, responded to the Line 355 fault and sent the transfer trip to the Pilgrim and Canal Line 342 breakers. This transfer trip signal should not have occurred for such a fault. It was subsequently determined that a relay at Auburn Street Station caused the inadvertent trip.
The NRC Operations Center was notified of the event in accordance with 10 CFR 50.72 (b) (3) (iv) (A) at 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on December 20, 2008 via Event Report Number 44737. Due to the fact that -power from an off-site source remained available from the 23kv Shutdown Transformer, the criteria for declaration of an Unusual Event were not met (Pilgrim EAL 6.3.2.1).
CAUSE
The root cause of this event was an inadequate DGOR setting on the Auburn Street Station Line 342. This relay initiated a Line 342 transfer trip signal to open ACB-103 which resulted in the momentary loss of the SUT. The initiating event was a flashover of a Phase B arc horn on the Line 355 bus section due to accumulated snow falling from the overhead bus and bridging the gap to the arc horn, causing ACB-102 to trip per design; ACB-1 03 opened shortly after in response to a transfer trip signal from the Auburn Street Station.
The tripping of the ACB-102 and ACB-103 resulted in a loss of the SUT supply and transferring of Pilgrim's safety busses to the EDGs.
CORRECTIVE ACTION
The following corrective actions have been taken:
A visual inspection of the switchyard and switchyard relay panels was performed to see if any damage occurred and was completed with satisfactory results.
Additional corrective action taken by the Auburn Street Station facility owner was to reset the DGOR based on the actual fault current seen at Auburn Street Station during the December 20, 2009 disturbance plus margin. The Auburn Street Station facility owner also validated the calibration of the Digital Fault Recorder, which was reported to be accurate.
Subsequent to the trip, NSTAR coordinated a test of the carrier system between Pilgrim, Auburn Street Station and Canal Stations. This test sends the carrier signal back and forth to test integrity of the circuit and signal strength. The test was satisfactory.
Pilgrim requested a review of the fault currents reported during the disturbance against the transmission system model for the system configuration at the time and is awaiting results.
Formal correspondence to National Grid has requested a summary of their actions to resolve this issue and prevent future recurrence The following corrective actions are planned:
Continue to work with the interconnection transmission owner, Auburn Street Station facility owner, and the transmission operator to verify the root cause of the tripping of the Auburn Street Station DGOR and to ensure this potential does not exist at other Pilgrim line terminal ends and evaluate the process to be used by the transmission owner and operators to prevent future occurrences.
These corrective actions are being tracked in the Corrective Action Program (CAP) under Condition Report CR-PNP-2008-3980.
SAFETY CONSEQUENCES
The condition posed no threat to public health and safety.
This event is considered non-significant because power was maintained automatically to the emergency busses by the EDG's. The plant remained within its design basis at all times, and all safety systems responded automatically if required or manually upon demand. Cooling to the reactor, including pressure and temperature control were maintained by the manual start and operation of the RCIC and HPCI systems.
However, this event is considered noteworthy because it caused a loss of cooling through the main condenser, and it would have caused a reactor scram if the plant had been operating. There was no adverse impact on nuclear, radiological or industrial safety.
REPORTABILITY
This report is submitted in accordance with 10 CFR 50.73(a) (2) (iv).(A).
SIMILARITY TO PREVIOUS EVENTS A review of Condition Reports for the past 10 years indicates that there are not any events where a loss of both lines to the SUT occurred as a result of any relay malfunction.
However, it should be noted that only two other station loss of offsite power events occurred in the past 22 years. The first was in 1987 and is documented in LER 87-14-01. The second was during a blizzard in April, 1997, and is documented in LER 97-07-01. As with this most recent event, the plant was not on-line for either of the other two, so none of the events challenged the safe shutdown of the reactor from power.
The risk to the plant from this type of event is the loss of the preferred power source. This event is analyzed and is within the design basis of the plant.
ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) CODES The EIIS codes for Components and Systems referenced in this report are as follows:
COMPONENTS CODES Circuit Breaker, AC (ACB-102) 52 Relay, differential protective 87 SYSTEMS Switchyard System (Startup Transformer)
FK
S.RI*8TART U
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MVWBm WAIE T
10 AUBURN 8T.
BMWllN WV"lkAN