Event Notification Report for April 26, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/25/2002 - 04/26/2002
Power Reactor
Event Number: 38878
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN BALLETTA
HQ OPS Officer: LEIGH TROCINE
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN BALLETTA
HQ OPS Officer: LEIGH TROCINE
Notification Date: 04/26/2002
Notification Time: 09:06 [ET]
Event Date: 04/26/2002
Event Time: 08:35 [EDT]
Last Update Date: 04/26/2002
Notification Time: 09:06 [ET]
Event Date: 04/26/2002
Event Time: 08:35 [EDT]
Last Update Date: 04/26/2002
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):
CLIFFORD ANDERSON (R1)
TOM KOSHY (NRR)
CLIFFORD ANDERSON (R1)
TOM KOSHY (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY RESPONSE DATA SYSTEM (ERDS) INOPERABLE DUE TO PLANNED OUTAGE OF THE PLANT PROCESS COMPUTER SYSTEM
The following text is a portion of a facsimile received from the licensee:
"On [April 26, 2002,] at 0835 hours EDT, the Indian Point Unit 2 plant ERDS was taken out of service to perform planned modifications to the plant process computer system. ERDS will remain inoperable until approximately May 4, 2002."
"This report is being made in accordance with the requirements of 10 CFR 50.72(b)(3)(xiii); any event that results in a loss of offsite communications capability."
"The Senior Resident Inspector has been briefed on the modifications and schedule. The NRC was previously notified of this planned outage via letter dated April 4, 2002."
The following text is a portion of a facsimile received from the licensee:
"On [April 26, 2002,] at 0835 hours EDT, the Indian Point Unit 2 plant ERDS was taken out of service to perform planned modifications to the plant process computer system. ERDS will remain inoperable until approximately May 4, 2002."
"This report is being made in accordance with the requirements of 10 CFR 50.72(b)(3)(xiii); any event that results in a loss of offsite communications capability."
"The Senior Resident Inspector has been briefed on the modifications and schedule. The NRC was previously notified of this planned outage via letter dated April 4, 2002."
Power Reactor
Event Number: 38880
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ROBERT SMITH
HQ OPS Officer: RICH LAURA
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ROBERT SMITH
HQ OPS Officer: RICH LAURA
Notification Date: 04/26/2002
Notification Time: 16:10 [ET]
Event Date: 04/26/2002
Event Time: 15:51 [EDT]
Last Update Date: 04/26/2002
Notification Time: 16:10 [ET]
Event Date: 04/26/2002
Event Time: 15:51 [EDT]
Last Update Date: 04/26/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
CLIFFORD ANDERSON (R1)
DAVID MATTHEWS (NRR)
CLIFFORD ANDERSON (R1)
DAVID MATTHEWS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
POTENTIAL FOR HOT SHORTS IN PORV CIRCUITS
"Recent review of Station Procedures regarding fire in the Control Room and other specific fire areas reveals an inconsistency with the plant Licensing Basis. The unit Licensing Basis takes credit for prevention of spurious operation of the PORVs by removing power from the valves prior to spurious operation. Current procedures require removing power from the PORVs but does not require removal of power prior to spurious operation. Spurious operation of the PORVs due to a hot short is an unanalyzed event.
"Compensatory actions to minimize risk of fire in areas of concern are being implemented which include increased surveillances to verify operability of detection and suppression, control of transient combustibles and ignition sources. The PORVs are considered operable.
"This event is being reported lAW 10CFR50.72(b)(3)(ii)(B) as an event or condition that results in the Nuclear Power Plant being in an unanalyzed condition that significantly degrades plant safety."
The NRC Resident Inspector was notified.
"Recent review of Station Procedures regarding fire in the Control Room and other specific fire areas reveals an inconsistency with the plant Licensing Basis. The unit Licensing Basis takes credit for prevention of spurious operation of the PORVs by removing power from the valves prior to spurious operation. Current procedures require removing power from the PORVs but does not require removal of power prior to spurious operation. Spurious operation of the PORVs due to a hot short is an unanalyzed event.
"Compensatory actions to minimize risk of fire in areas of concern are being implemented which include increased surveillances to verify operability of detection and suppression, control of transient combustibles and ignition sources. The PORVs are considered operable.
"This event is being reported lAW 10CFR50.72(b)(3)(ii)(B) as an event or condition that results in the Nuclear Power Plant being in an unanalyzed condition that significantly degrades plant safety."
The NRC Resident Inspector was notified.