Event Notification Report for March 10, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/09/1999 - 03/10/1999
** EVENT NUMBERS **
35449 35450 35451 35452
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35449 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/08/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 16:53[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/08/1999|
+------------------------------------------------+EVENT TIME: 14:00[EST]|
| NRC NOTIFIED BY: MARY BETH GREENDONNER |LAST UPDATE DATE: 03/09/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SECURITY REPORT |
| |
| Safeguards system degradation related to potential unauthorized entry into a |
| vital area. Immediate compensatory measures taken upon discovery. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| Refer to the HOO Log for additional details. |
| |
| * * * UPDATE AT 1838 EST ON 3/8/99 BY MARY BETH GREENDONNER TO FANGIE JONES |
| * * * |
| |
| Additional safeguards system degradation found during additional inspection |
| after initial report. Immediate compensatory measures taken upon |
| discovery. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R3DO (R. Gardner) and R3 IAT (James |
| Creed). |
| |
| * * * UPDATE AT 1139 EST ON 3/9/99 BY MARY BETH GREENDONNER TO FANGIE JONES |
| * * * |
| |
| Additional safeguards system degradation found during additional inspection |
| after follow-up report. Immediate compensatory measures taken upon |
| discovery. |
| |
| The licensee notified the NRC Resident Inspector and R3 IAT (James Creed). |
| |
| The NRC Operations Officer notified the R3DO (R. Gardner). |
| |
| Refer to the HOO Log for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35450 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/08/1999|
| UNIT: [] [2] [3] STATE: AL |NOTIFICATION TIME: 23:39[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/08/1999|
+------------------------------------------------+EVENT TIME: 21:42[CST]|
| NRC NOTIFIED BY: RAYMOND SWAFFORD |LAST UPDATE DATE: 03/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 96 Power Operation |94 Power Operation |
|3 N Y 100 Power Operation |98 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Two Trains of Standby Gas Treatment (SBGT) Inoperable - Shutdown Required |
| by Technical Specifications |
| |
| "At 2042, with both U2 & U3 in Mode 1, U2 coasting down at 3145 MWth, U3 |
| 100% 3458 MWth, U2 and U3 received alarms 'SBGT C RH [Relative Humidity] |
| TEMP HIGH' and 'SBGT C FLT [Filter] BANK HTR ELEM POWER LOST.' The system |
| engineer reported the supply breaker for C train SBGT tripped. C SBGT was |
| declared inoperable. B SBGT was already INOP due to scheduled maintenance. |
| With two trains of SBGT INOP, this resulted in entering TS LCO 3.0.3 on both |
| units immediately. At 2141, shutdown was initiated on both U2 and U3. |
| This is reportable as a 1 hour report to the NRC under 10 CFR |
| 50.72(b)(1)(i)(A), as 'The initiation of any nuclear plant shutdown required |
| by the plant's Technical Specification.' |
| |
| "Upon investigation by Engineering and Maintenance it was determined there |
| was a problem with SBGT switch. Tech Spec Requirement 3.3.A.1 allows |
| tripping of the logic of the inoperable flow switch and starting the |
| affected SBGT C. This action was completed and C SBGT was declared OPERABLE |
| and TS LCO 3.0.3 exited at 2237." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35451 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/09/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 05:55[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/09/1999|
+------------------------------------------------+EVENT TIME: 02:21[EST]|
| NRC NOTIFIED BY: JOHN HUNTER |LAST UPDATE DATE: 03/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM MOSLAK R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| COMMON FAILURE EFFECTING BOTH TRAINS OF SHUTDOWN COOLING |
| |
| "On 3/9/99, at 0221 it was discovered that the Unit 1 shutdown cooling |
| valves HV-51-1F015A, HV-51-1F015B, and HV-51-1F08 could not be opened, if |
| plant conditions required, due to a failure in the isolation logic circuit |
| connectors. |
| |
| "This failure affected both shutdown cooling return valves and a common |
| suction valve which results in one failure effecting both trains of shutdown |
| cooling. The identified deficiency is being planned for repairs. This |
| condition, of a single failure disabling multiple trains of a system, is |
| being reported pursuant to 50.72(b)(2)(iii)." |
| |
| This deficiency was discovered during routine maintenance. These valves |
| could be opened manually using existing plant procedures if it were |
| necessary to initiate shutdown cooling. |
| |
| The licensee will notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35452 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/09/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 16:59[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/09/1999|
+------------------------------------------------+EVENT TIME: 14:21[EST]|
| NRC NOTIFIED BY: RUSS LONG |LAST UPDATE DATE: 03/09/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM MOSLAK R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP DURING MAINTENANCE ON REACTOR COOLANT FLOW TRANSMITTER |
| |
| "On March 9, 1999, at approximately 1421 hours, the Instrument and Control |
| department finished installing a temporary modification on loop 3 'C' |
| channel RCS flow transmitter (FT-436) low pressure side drain line. This |
| temporary modification consisted of cutting and capping the low side drain |
| line because the drain line isolation valve was known to be leaking by. |
| While unisolating the low pressure side of the transmitter, a spike occurred |
| on the other two transmitters in loop 3. The 'B' transmitter (FT-435) |
| spiked low enough to trip its associated bistable. This resulted in two |
| channels tripped in one RCS loop. The 'C' channel (FT-436) had been |
| previously been tripped as required by Technical Specifications. This |
| resulted in a reactor trip. All equipment responded as expected. The plant |
| is stable in the hot shutdown condition." |
| |
| Heat removal is by auxiliary feedwater and steam dumps to the main |
| condenser. No atmospheric reliefs or safeties lifted during the transient |
| and all rods fully inserted. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021