Event Notification Report for October 15, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/14/2003 - 10/15/2003
EVENT NUMBERS
4025040251402524024840249
Power Reactor
Event Number: 40250
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE SULLIVAN
HQ OPS Officer: RICH LAURA
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE SULLIVAN
HQ OPS Officer: RICH LAURA
Notification Date: 10/15/2003
Notification Time: 19:30 [ET]
Event Date: 10/15/2003
Event Time: 16:03 [EDT]
Last Update Date: 10/15/2003
Notification Time: 19:30 [ET]
Event Date: 10/15/2003
Event Time: 16:03 [EDT]
Last Update Date: 10/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BRIAN MCDERMOTT (R1)
MICHAEL JOHNSON (NRR)
BRIAN MCDERMOTT (R1)
MICHAEL JOHNSON (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 40 | Power Operation |
FEEDWATER REGULATING VALVE ISSUE FORCES INITIATION OF TECHNICAL SPECIFICATION SHUTDOWN
"At 1603 Salem Unit 1 commenced a down power to comply with Technical Specifications. Tech. Spec. 3.0.3. was entered at 1505 when it was determined that the feed regulation valve for the 14 Steam generator (14BF19) was bound at approximately 71% open. This valve is required to close on a feedwater isolation signal. Currently the reactor is at 40% power and lowering with plans to stabilize at 25% prior to taking the unit off line (mode 3) by 2205 tonight.
"Unit 1 has no other tech spec equipment out of service. Unit 1 is in two additional shutdown Technical Specifications, both are related to the control room ventilation system which is shared with Unit 2. Unit 2 is in a scheduled refueling outage and one of the Unit 2 emergency intake dampers is disabled (T.S. 3.7.6.1.a). This is a 7 day LCO that expires on 10/22/03. Additionally Unit 2's emergency filtration system is out of service for planned maintenance (T.S 3.7.6.1.a). This is a 30 day LCO that expires on 11/13/03. All other systems on Unit 1 are operating as expected for current plant conditions."
The licensee notified the NRC Resident Inspector.
"At 1603 Salem Unit 1 commenced a down power to comply with Technical Specifications. Tech. Spec. 3.0.3. was entered at 1505 when it was determined that the feed regulation valve for the 14 Steam generator (14BF19) was bound at approximately 71% open. This valve is required to close on a feedwater isolation signal. Currently the reactor is at 40% power and lowering with plans to stabilize at 25% prior to taking the unit off line (mode 3) by 2205 tonight.
"Unit 1 has no other tech spec equipment out of service. Unit 1 is in two additional shutdown Technical Specifications, both are related to the control room ventilation system which is shared with Unit 2. Unit 2 is in a scheduled refueling outage and one of the Unit 2 emergency intake dampers is disabled (T.S. 3.7.6.1.a). This is a 7 day LCO that expires on 10/22/03. Additionally Unit 2's emergency filtration system is out of service for planned maintenance (T.S 3.7.6.1.a). This is a 30 day LCO that expires on 11/13/03. All other systems on Unit 1 are operating as expected for current plant conditions."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 40251
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN CRAIG
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN CRAIG
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/16/2003
Notification Time: 00:16 [ET]
Event Date: 10/15/2003
Event Time: 23:02 [EDT]
Last Update Date: 10/16/2003
Notification Time: 00:16 [ET]
Event Date: 10/15/2003
Event Time: 23:02 [EDT]
Last Update Date: 10/16/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRIAN MCDERMOTT (R1)
BRIAN MCDERMOTT (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PROMPT NOTIFICATION SYSTEM (PNS) SIRENS EXCEEDED ALLOWABLE OUT OF SERVICE TIME.
More than 4 Prompt Notification System sirens were simultaneously out of service for greater than 12 hours. In accordance with site procedures, this is a major loss of notification capability. These sirens are out of service due to a loss of power caused by elevated wind conditions in the region. Oswego County is currently working to restore power to the sirens. State and Local counties were notified.
The NRC Resident Inspector will be notified of this event by the licensee.
More than 4 Prompt Notification System sirens were simultaneously out of service for greater than 12 hours. In accordance with site procedures, this is a major loss of notification capability. These sirens are out of service due to a loss of power caused by elevated wind conditions in the region. Oswego County is currently working to restore power to the sirens. State and Local counties were notified.
The NRC Resident Inspector will be notified of this event by the licensee.
Power Reactor
Event Number: 40252
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: D. POULIN
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: D. POULIN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/16/2003
Notification Time: 00:28 [ET]
Event Date: 10/15/2003
Event Time: 23:02 [EDT]
Last Update Date: 10/16/2003
Notification Time: 00:28 [ET]
Event Date: 10/15/2003
Event Time: 23:02 [EDT]
Last Update Date: 10/16/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRIAN MCDERMOTT (R1)
BRIAN MCDERMOTT (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PROMPT NOTIFICATION SYSTEM (PNS) SIRENS EXCEEDED ALLOWABLE OUT OF SERVICE TIME.
More than 4 Prompt Notification System sirens were simultaneously out of service for greater than 12 hours. In accordance with site procedures, this is a major loss of notification capability. These sirens are out of service due to a loss of power caused by elevated wind conditions in the region. Oswego County is currently working to restore power to the sirens. State and Local counties were notified.
The NRC Resident Inspector will be notified of this event by the licensee.
*****UPDATE ON 10/16/03 AT 1524 FROM PAGE TO LAURA*****
"On October 15, 2003, the James A. FitzPatrick nuclear power plant notified the NRC that more than 4 prompt notification system sirens were simultaneously out of service for greater than 12 hours due to loss of power caused by elevated wind conditions in the region (reference EN # 40252). On October 16, 2003 at approximately 0107, the county notified FitzPatrick that only 3 sirens remained out of service. As of October 16, 2003, at approximately 1200, only 2 of the sirens remain out of service. Efforts are continuing to restore electrical power to the remaining 2 sirens.
As a result, the conditions under which the initial notification was made no longer exist (10CFR50.72(b)(3)(xiii) major loss of offsite response capability - due to loss of 4 or more sirens for greater than 12 hours). This informational notification is provided to update the NRC as to the current conditions."
Notified R1DO (Brian MCDERMOTT)
More than 4 Prompt Notification System sirens were simultaneously out of service for greater than 12 hours. In accordance with site procedures, this is a major loss of notification capability. These sirens are out of service due to a loss of power caused by elevated wind conditions in the region. Oswego County is currently working to restore power to the sirens. State and Local counties were notified.
The NRC Resident Inspector will be notified of this event by the licensee.
*****UPDATE ON 10/16/03 AT 1524 FROM PAGE TO LAURA*****
"On October 15, 2003, the James A. FitzPatrick nuclear power plant notified the NRC that more than 4 prompt notification system sirens were simultaneously out of service for greater than 12 hours due to loss of power caused by elevated wind conditions in the region (reference EN # 40252). On October 16, 2003 at approximately 0107, the county notified FitzPatrick that only 3 sirens remained out of service. As of October 16, 2003, at approximately 1200, only 2 of the sirens remain out of service. Efforts are continuing to restore electrical power to the remaining 2 sirens.
As a result, the conditions under which the initial notification was made no longer exist (10CFR50.72(b)(3)(xiii) major loss of offsite response capability - due to loss of 4 or more sirens for greater than 12 hours). This informational notification is provided to update the NRC as to the current conditions."
Notified R1DO (Brian MCDERMOTT)
Power Reactor
Event Number: 40248
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ROBERT MCCOY
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ROBERT MCCOY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 10/15/2003
Notification Time: 13:25 [ET]
Event Date: 10/15/2003
Event Time: 10:24 [EDT]
Last Update Date: 10/15/2003
Notification Time: 13:25 [ET]
Event Date: 10/15/2003
Event Time: 10:24 [EDT]
Last Update Date: 10/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN MCDERMOTT (R1)
BRIAN MCDERMOTT (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 1 | Startup | 0 | Hot Standby |
A MANUAL REACTOR TRIP FROM 1% POWER AS PER ABNORMAL OPERATING PROCEDURES OCCURRED
The plant was in mode 2 (1% power) making preparations to place the unit on-line per procedures. At 0921, the plant had entered ER-SC.1, Adverse Weather Plan, due to sustained winds greater than 55 mph. At 1024, offsite power circuit "751" was lost due to offsite storm damage(tree down on powerline). The loss of circuit "751" led to the loss of the "B" reactor coolant pump on undervotltage. Procedure AP-RCS.2, loss of Reactor Coolant flow was entered. At 1026 a manual Reactor Trip was initiated as directed by procedures. All rods fully inserted, no ECCS injection or safety valves lifted and all ESF systems functioned as designed. Due to the partial loss of offsite power, the "B" emergency diesel auto started and loaded to supply safeguards equipment. The "A" and "B" aux feedwater pumps also auto started. Offsite power was restored to safeguards equipment being supplied power by the "B" emergency diesel within 15 minutes from the second offsite power line.
The NRC Resident inspector was notified.
The plant was in mode 2 (1% power) making preparations to place the unit on-line per procedures. At 0921, the plant had entered ER-SC.1, Adverse Weather Plan, due to sustained winds greater than 55 mph. At 1024, offsite power circuit "751" was lost due to offsite storm damage(tree down on powerline). The loss of circuit "751" led to the loss of the "B" reactor coolant pump on undervotltage. Procedure AP-RCS.2, loss of Reactor Coolant flow was entered. At 1026 a manual Reactor Trip was initiated as directed by procedures. All rods fully inserted, no ECCS injection or safety valves lifted and all ESF systems functioned as designed. Due to the partial loss of offsite power, the "B" emergency diesel auto started and loaded to supply safeguards equipment. The "A" and "B" aux feedwater pumps also auto started. Offsite power was restored to safeguards equipment being supplied power by the "B" emergency diesel within 15 minutes from the second offsite power line.
The NRC Resident inspector was notified.
Power Reactor
Event Number: 40249
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JEFFERY PEASE
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JEFFERY PEASE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 10/15/2003
Notification Time: 14:07 [ET]
Event Date: 10/15/2003
Event Time: 13:12 [EDT]
Last Update Date: 10/15/2003
Notification Time: 14:07 [ET]
Event Date: 10/15/2003
Event Time: 13:12 [EDT]
Last Update Date: 10/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
CHARLES R. OGLE (R2)
CHARLES R. OGLE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
UNSECORTED ACCESS GRANTED INAPPROPRIATELY
Compensatory measures taken upon discovery.
The NRC Resident Inspector was notified.
Refer to the HOO for additional details
Compensatory measures taken upon discovery.
The NRC Resident Inspector was notified.
Refer to the HOO for additional details