Event Notification Report for June 10, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/09/1999 - 06/10/1999
** EVENT NUMBERS **
35706 35809 35810
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35706 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/12/1999|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 16:12[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/12/1999|
+------------------------------------------------+EVENT TIME: 15:15[EDT]|
| NRC NOTIFIED BY: GREEN |LAST UPDATE DATE: 06/09/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| REACTOR CORE ISOLATION COOLING (RCIC) WAS DECLARED INOPERABLE DURING A |
| QUARTERLY SURVEILLANCE TEST. |
| |
| DURING THE PERFORMANCE OF THE NORMAL QUARTERLY RCIC SURVEILLANCE TEST, THE |
| RCIC TURBINE UNEXPECTEDLY TRIPPED WHEN THE SUCTION PATH WAS SWAPPED FROM |
| THE SUPPRESSION POOL TO THE CONDENSATE STORAGE TANK. THE CAUSE OF THE RCIC |
| TURBINE TRIP IS UNKNOWN AT THIS TIME, AND TROUBLESHOOTING IS CURRENTLY IN |
| PROGRESS. THE PLANT IS IN A 14-DAY LIMITING CONDITION FOR OPERATION ACTION |
| STATEMENT. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| ******************** UPDATE AT 1600 ON 06/09/99 FROM MITCH ALMETER TO |
| TROCINE ******************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "In accordance with industry guidance (i.e., NUREG-1022), Nine Mile Point |
| reports RCIC inoperability due to an unplanned occurrence. The |
| inoperability reported on 05/12/99 was as a result of preplanned maintenance |
| and a system configuration which is not expected to be duplicated under |
| design conditions. The preplanned inoperability did not reveal any |
| non-conformance that would have otherwise impacted RCIC operability. |
| Therefore, the RCIC trip/inoperability was not reportable." |
| |
| "This event notification is being retracted." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Caruso). |
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|Power Reactor |Event Number: 35809 |
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| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 06/09/1999|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 00:26[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/09/1999|
+------------------------------------------------+EVENT TIME: 00:20[EDT]|
| NRC NOTIFIED BY: MIKE FERGUSON |LAST UPDATE DATE: 06/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRIAN BONSER R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| TECH SPEC REQUIRED SHUTDOWN - BOTH CHEMICAL & VOLUME CONTROL PUMPS |
| INOPERABLE |
| |
| The licensee commenced a Tech Spec required shutdown at 0020 on 6/9/99. |
| The shutdown was terminated at 0029 when the 1A Chemical and Volume Control |
| (CVC) charging pump was returned to an operable status. Reactor power had |
| been reduced to 99%. |
| |
| On 6/7/99 at 1500, the 1A CVC charging pump was declared inoperable because |
| the "A" Service water pump was inoperable. At 2320 on 6/8/99, the 1B CVC |
| charging pump was also declared inoperable because of abnormal flow. The |
| licensee entered Tech Spec 3.0.3 at that time, and since the condition had |
| not been repaired by 0020 on 6/9/99, a shutdown was commenced. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 35810 |
+------------------------------------------------------------------------------+
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/09/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 17:37[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 06/09/1999|
+------------------------------------------------+EVENT TIME: 16:40[EDT]|
| NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 06/09/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN CARUSO R1 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |FRANK CONGEL IRO |
|NLCO TECH SPEC LCO A/S |SCOTT BARBER/REG 1 DRP |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LOSS OF CONTROL POWER TO THE ECCS RESTART PROGRAM FOR AN EMERGENCY BUS |
| DURING PERFORMANCE OF MAINTENANCE ACTIVITIES AND RESULTING TECH SPEC |
| REQUIRED SHUTDOWN |
| |
| At 1640 EDT on 06/09/99, the control room received an annunciator (Restart |
| Program Control Power Loss) which indicated a loss of 125-VDC control power |
| for the emergency core cooling system (ECCS) restart program on the 10500 |
| bus (one of two 4,160-V emergency buses). The licensee stated that this |
| failure removed the ability to strip the 10500 bus of loads, isolate the |
| bus, and then automatically reload the bus with power being supplied by the |
| applicable emergency diesel generators (EDG). It, therefore, prevents |
| automatic startup of certain ECCS equipment and prevents loading of the |
| associated EDGs on low emergency bus voltage. (The licensee stated that |
| everything is still functional. However, if there was a situation where the |
| bus was stripped and where an automatic restart using power from the EDGs |
| was required, the loss of control power to the restart program would prevent |
| automatic restart of the applicable ECCS equipment.) |
| |
| The unit has four EDGs; two for each 4,160-V emergency bus. The licensee |
| stated that the EDGs associated with the 10500 bus were already inoperable |
| at the time of the event. However, the 4,160-V 10600 emergency bus and its |
| associated pair of EDGs remained operable. |
| |
| As a result of the loss of control power for the ECCS restart program, the |
| low pressure ECCS systems associated with the 10500 bus ('A' and 'B' |
| residual heat removal and 'A' core spray) and the pair of EDGs associated |
| with the 10500 bus were declared inoperable, and the licensee entered |
| Technical Specification 3.5.a.6. The action statement for this technical |
| specification requires the licensee to place the unit in a Cold Shutdown |
| condition within 24 hours. Accordingly, a unit shutdown from 100% reactor |
| power was commenced at 1739 EDT. The shutdown is planned to occur at a rate |
| of 50 MWe/hour. |
| |
| The licensee stated that maintenance activities were ongoing at the time of |
| the event. A breaker was being racked in for another maintenance effort on |
| some auxiliary contacts when the 'Restart Program Control Power Loss' |
| annunciator was received. Apparently, the fuses that control the logic for |
| the restart program control power are located in close proximity to the |
| breaker that was being racked in. |
| |
| Troubleshooting activities are underway. The licensee is currently checking |
| the switchgear fuses and supply breakers and is also initiating corrective |
| maintenance. |
| |
| Other than receipt of the annunciator in the control room, there were no |
| automatic initiations (such as actual ECCS injections or engineered safety |
| feature actuations) associated with this event. There was no emergency |
| declaration. The licensee plans to provide additional information as it |
| becomes available (when the situation mitigates or escalates). |
| |
| The licensee notified the NRC resident inspector. |
| |
| ******************** UPDATE AT 2228 ON 06/09/99 FROM PETER ABBOTT TO TROCINE |
| ******************** |
| |
| Investigation revealed that a fuse holder had lost tension and was not |
| making proper contact. The fuse holder was subsequently adjusted and |
| reinstalled, and the 24-hour action statement was exited at 2219 EDT. The |
| licensee was maintaining reactor power at 88% and is currently in the |
| process of evaluating whether or not power ascension can be commenced. |
| |
| The licensee stated that the ability to manually start the affected ECCS |
| pumps was not lost because 4,160-V bus power was never lost. Therefore, the |
| affected ECCS equipment could have been manually started either from the |
| control room or locally. |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Caruso), NRR EO (Zwolinski), and IRO (Congel). |
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