Event Notification Report for April 21, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/20/2003 - 04/21/2003
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 39777
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: A. HALLIDAY
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: A. HALLIDAY
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/21/2003
Notification Time: 12:35 [ET]
Event Date: 04/21/2003
Event Time: 11:40 [EDT]
Last Update Date: 04/24/2003
Notification Time: 12:35 [ET]
Event Date: 04/21/2003
Event Time: 11:40 [EDT]
Last Update Date: 04/24/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
HAROLD GRAY (R1)
HAROLD GRAY (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 |
DISCOVERY OF SAFEGUARDS INFORMATION.
IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.
CONTACT THE HOO FOR FURTHER DETAILS.
* * * * UPDATE ON 04/24/03 AT 1410 BY HALLIDAY TO GOULD * * * * RETRACTION
The Security Manager, with personnel from Security and Regulatory Compliance reviewed the incident using the guidance in USNRC Regulatory guide 5.62, Reporting of Safeguards Events, and USNRC Generic Letter 91-03, Reporting of Safeguards events. It was determined that although the document contained some low level safeguards information, the document could not have significantly aided an adversary in defeating a security barrier or in carrying out an act of radiological sabotage as the key piece of safeguards information, an encryption table, was not filled out. Based on that determination JAF is withdrawing the one-hour telephone notification (EN-39777). The event remains a loggable event per 10 CFR 95.57(b). It was entered into the Security Log at the time of notification. The event has also been entered into the licensee's corrective action program for apparent cause determination.
The NRC Resident inspector was notified and the state will be notified.
Notified the Reg 1 RDO(Gray)
IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.
CONTACT THE HOO FOR FURTHER DETAILS.
* * * * UPDATE ON 04/24/03 AT 1410 BY HALLIDAY TO GOULD * * * * RETRACTION
The Security Manager, with personnel from Security and Regulatory Compliance reviewed the incident using the guidance in USNRC Regulatory guide 5.62, Reporting of Safeguards Events, and USNRC Generic Letter 91-03, Reporting of Safeguards events. It was determined that although the document contained some low level safeguards information, the document could not have significantly aided an adversary in defeating a security barrier or in carrying out an act of radiological sabotage as the key piece of safeguards information, an encryption table, was not filled out. Based on that determination JAF is withdrawing the one-hour telephone notification (EN-39777). The event remains a loggable event per 10 CFR 95.57(b). It was entered into the Security Log at the time of notification. The event has also been entered into the licensee's corrective action program for apparent cause determination.
The NRC Resident inspector was notified and the state will be notified.
Notified the Reg 1 RDO(Gray)
Power Reactor
Event Number: 39778
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: MIKE MICKLOW
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: MIKE MICKLOW
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/21/2003
Notification Time: 15:32 [ET]
Event Date: 04/21/2003
Event Time: 07:30 [EDT]
Last Update Date: 04/21/2003
Notification Time: 15:32 [ET]
Event Date: 04/21/2003
Event Time: 07:30 [EDT]
Last Update Date: 04/21/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
HAROLD GRAY (R1)
HAROLD GRAY (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 |
EMERGENCY RESPONSE SIREN ACTUATED.
At approximately 1430 hours EDT, control room personnel received notification that one emergency response siren may have inadvertently actuated. At approximately 1400 hours EDT control room personnel were notified that local press and media outlets were informed of the siren malfunction. Currently 94 of 96 sirens are operable.
The NRC Resident Inspector will notified of this event by the licensee.
At approximately 1430 hours EDT, control room personnel received notification that one emergency response siren may have inadvertently actuated. At approximately 1400 hours EDT control room personnel were notified that local press and media outlets were informed of the siren malfunction. Currently 94 of 96 sirens are operable.
The NRC Resident Inspector will notified of this event by the licensee.
Power Reactor
Event Number: 39779
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JOHN APRIL
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JOHN APRIL
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/21/2003
Notification Time: 22:26 [ET]
Event Date: 04/21/2003
Event Time: 21:17 [EDT]
Last Update Date: 04/21/2003
Notification Time: 22:26 [ET]
Event Date: 04/21/2003
Event Time: 21:17 [EDT]
Last Update Date: 04/21/2003
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):
HAROLD GRAY (R1)
HAROLD GRAY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 23 | Power Operation | 23 | Power Operation |
ELECTROMATIC RELIEF VALVE FAILED TO OPEN DURING POWER ASCENSION TESTING.
While performing Technical Specification required surveillance testing during power ascension per NI-ST-C2, Solenoid-Activated Pressure Relief Valves Operability and Flow Verification Test, 111 Electromatic Relief Valve (ERV) failed to open as required. 111 ERV has been declared inoperable and Technical Specification 3.1.5. (b) has been entered. This Limiting Condition of Operation requires reactor coolant dome pressure be reduced to 110 psig or less within 10 hours (start time is 2117 EDT). The cause for the failure of 111 ERV is under investigation. The other 5 ERV's (used also as ADV valves) tested satisfactorily. Plant preparations are in progress. The electrical grid is stable and their Emergency Diesel Generators are fully operable if needed. All Emergency Core Cooling systems (including the Isolation Condenser) are fully except for 111 ERV. The licensee notified the New York Service Commission of this event.
The NRC Resident Inspector was notified of this event by the licensee.
While performing Technical Specification required surveillance testing during power ascension per NI-ST-C2, Solenoid-Activated Pressure Relief Valves Operability and Flow Verification Test, 111 Electromatic Relief Valve (ERV) failed to open as required. 111 ERV has been declared inoperable and Technical Specification 3.1.5. (b) has been entered. This Limiting Condition of Operation requires reactor coolant dome pressure be reduced to 110 psig or less within 10 hours (start time is 2117 EDT). The cause for the failure of 111 ERV is under investigation. The other 5 ERV's (used also as ADV valves) tested satisfactorily. Plant preparations are in progress. The electrical grid is stable and their Emergency Diesel Generators are fully operable if needed. All Emergency Core Cooling systems (including the Isolation Condenser) are fully except for 111 ERV. The licensee notified the New York Service Commission of this event.
The NRC Resident Inspector was notified of this event by the licensee.