05000220/LER-2008-001, Loss of Offsite Power Due to an Equipment Malfunction
| ML081900269 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/07/2008 |
| From: | Belcher S Constellation Energy Group, Nine Mile Point |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 08-001-00 | |
| Download: ML081900269 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(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 |
| 2202008001R00 - NRC Website | |
text
Sam Belcher Plant General Manager Constellation Energy-
- Nine Mile Point Nuclear Station, LLC U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 P.O. Box 63 Lycoming, New York 13093 315.349.5205 315.349.1321 Fax July 7,2008 ATTENTION:
SUBJECT:
Document Control Desk Nine Mile Point Nuclear Station Unit No. 1 Docket No. 50-220 Licensee Event Report 2008-01, Loss of Offsite Power due to an Equipment Malfunction Gentlemen:
In accordance with 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(2)(v)(D), please find attached Licensee Event Report 2008-01, Loss of Offsite Power due to an Equipment Malfunction.
SLB/MHS
- Syrell,
Attachment:
Licensee Event Report 2008-01, Loss of Offsite Power due to an Equipment Malfunction cc:
S. J. Collins, NRC R. V. Guzman, NRC Resident Inspector, NRC
ATTACHMENT LICENSEE EVENT REPORT 2008-01 LOSS OF OFFSITE POWER DUE TO AN EQUIPMENT MALFUNCTION Nine Mile Point Nuclear Station, LLC July 7, 2008
ONRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVEDBY OMB: NO. 315().()104 EXPIRES: 08/31/2010 (9-2007)
, the NRCmay not conduct digits/characters for each block) or sponsor, and a person is not required to respond to, the information collection.
r*
PAGE Nine Mile Point Unit 1 05000220 1
OF 5
- 4. TITLE Loss of Offsite Power due to an Equipment Malfunction
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR James A. Fitzpatrick Nuclear 05000333 NUMBER NO.
Power Plant FACILITY NAME DOCKET NUMBER 05 13 2008 2008 001 00 07 07 2008
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii)
N o 20.2201 (d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 50.36(c)(1)(i)(A) o 50.73(a)(2)(iii) o 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(ii) o 50.36(c)(1 )(ii)(A) 181 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71(a)(4) 100 o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71(a)(5) o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(i)(B) 181 50.73(a)(2)(v)(D)
Specify in Abstractbelow or in 2008 001 00
D. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES
May 13, 2008, 0637: Removed Line 1 from service for planned maintenance May 13, 2008, 0806: Lost Line 4 May 13, 2008, 0825: Declared a UE May 13, 2008, 0843: Restored Line 1 to service May 13, 2008, 1022: Terminated the UE May 16, 2008,0515: Restored Line 4 to service
E. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED
Other than those described under section B above, no other systems or secondary functions were affected.
F. METHOD OF DISCOVERY
This event was immediately apparent by control room indications and annunciations.
G. MAJOR OPERATOR ACTION:
In response to the LOOP, trip of a Reactor Recirculation pump, and trip of the operating SFP cooling pump, the operators entered applicable Special Operating Procedures and took appropriate corrective actions to stabilize reactor recirculation flow and to restore SFP cooling.
At 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br />, the Shift Manager declared a UE and made required notifications.
The operators commenced recovery of Line 1, which had been removed from service for planned maintenance. At 0843 hours0.00976 days <br />0.234 hours <br />0.00139 weeks <br />3.207615e-4 months <br />, Line 1 was restored to service.
2008 001 00 H. SAFETY SYSTEM RESPONSES:
The LOOP resulted in the loss of two 4160 V vital buses and the subsequent start of emergency diesel generators to carry the emergency loads.
II.
CAUSE OF EVENT
The event is a NUREG-1022 Cause Code C, "External Cause."
The apparent cause of this event is an equipment malfunction associated with the James A.
Fitzpatrick Nuclear Power Plant's switchyard.
NMP Condition Report 2008-4077 applies to this LER.
III. ANALYSIS OF THE EVENT
This event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A) because of the automatic start of Division 1 and 2 Emergency Diesel Generators.
The event is also reportable in accordance with 10 CFR 50.73(a)(2)(v)(D) because of loss of both 115 kV offsite power sources.
The loss of both 115 kV offsite power lines is described in the Updated Final Safety Analysis Report (UFSAR).Section IX.B.1.2 describes failure modes for the 115 kV offsite power system. Actual system response was in accordance with the expected response described in the UFSAR.
The trip of a reactor recirculation pump had a minimal effect on safety. UFSAR Section XV.B.3.7 analysis bounds this transient and concludes that the Minimum Critical Power Ratio was not challenged.
Reactor power responded as expected for the trip of the reactor recirculation pump.
The trip of the operating SFP cooling pump resulted in the SFP temperature rising to 87 degrees F (a 2 degrees increase), well below the maximum limit of 140 degrees F.
When Line 1 was taken out of service for planned maintenance, the risk was assessed and managed in accordance with the site integrated risk management procedure.
IV. CORRECTIVE ACTIONS
A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:
On May 13, 2008, at 0843 hours0.00976 days <br />0.234 hours <br />0.00139 weeks <br />3.207615e-4 months <br />, Line 1, which had been removed from service for planned maintenance, was restored to service. On May 16, 2008, at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />, Line 4 was restored to service after completion of corrective action at the James A. Fitzpatrick Nuclear Power Plant.
2008 001 00 B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
Nine Mile Point Nuclear Station will review the James A. Fitzpatrick Nuclear Power Plant's causal analysis for extent of condition pertinent to NMP1 and NMP2.
V. ADDITIONAL INFORMATION
A. FAILED COMPONENTS:
There were no failed components at NMP1 that initiated or contributed to this event.
B. PREVIOUS LERs ON SIMILAR EVENTS:
The following events occurred at Nine Mile Point Nuclear Station:
08/14/2003, Nine Mile Point Unit 1 scram due to a loss of offsite power during the Northeast Blackout (LER 2003-02) 08/14/2003, Nine Mile Point Unit 2 scram due to a loss of offsite power during the Northeast Blackout (LER 2003-02)
C. THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EllS) COMPONENT FUNCTION IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:
COMPONENT 115 kv offsite power line Switchgear Emergency Diesel Generator Reactor Recirculation Pump Emergency Power Distribution Buses Spent Fuel Pool Cooling Pump Switchyard D. SPECIAL COMMENTS:
NoneIEEE 803 FUNCTION IDENTIFIER NA SWGR DG P
BU P
NA IEEE 805 SYSTEM IDENTIFICATION FK EA EK AD EB DA FK