Event Notification Report for February 17, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/16/1999 - 02/17/1999
** EVENT NUMBERS **
35309 35371 35372 35373 35374 35375
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35309 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/22/1999|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 19:40[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/20/1999|
+------------------------------------------------+EVENT TIME: 17:30[EST]|
| NRC NOTIFIED BY: ROY GREEN |LAST UPDATE DATE: 02/16/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |FRANK COSTELLO 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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LATE NOTIFICATION ON REACTOR CORE ISOLATION COOLING (RCIC) BEING DECLARED |
| INOPERABLE ON 01/20/99 |
| |
| On 01/20/99 at 1730 EST, RCIC became inoperable as a result of two |
| inoperable primary containment isolation valves being closed to satisfy |
| Technical Specification 3.6.3. RCIC was declared inoperable per Technical |
| Specification 3.7.4 (14 days to restore to operable status). Initial |
| assessment conclude that an immediate report was not required. However, |
| upon additional review, it has been determined that a 4-hour report is |
| required in accordance with 10 CFR 50. 72(b)(2)(iii)(D). RCIC was restored |
| to operable status on 01/22/99 at 1142 EST. The technical specifications |
| mentioned above were exited at the time. During the time period RCIC was |
| out of service, all emergency core cooling systems were fully operable. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
| |
| ******************** UPDATE AT 1631 ON 02/16/99 FROM ROY GREEN TO TROCINE |
| ******************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "... RCIC was declared inoperable when it was believed [that] the starter |
| coils for two RCIC containment isolation valves (CIVs) would not function |
| properly in a degraded voltage situation, and the CIVs were closed to comply |
| with technical specifications.. |
| |
| "Subsequent review has determined that since the event or condition was |
| associated with the containment isolation function only and [since] the |
| reporting criteria is concerned with RCIC injection, the event is not |
| reportable. The operator actions to close the CIVs in accordance with |
| technical specifications [do] not constitute an event or condition as |
| discussed in the NUREG guidance. Therefore, notification of the event is |
| retracted. Additionally, evaluation and testing has concluded that the |
| starter coils in question would have functioned under all design |
| conditions. |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Trapp). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35371 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/15/1999|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 22:33[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/15/1999|
+------------------------------------------------+EVENT TIME: 21:45[EST]|
| NRC NOTIFIED BY: GARY CLEMENTS |LAST UPDATE DATE: 02/16/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DISCOVERY THAT UNIT 1 FUELING WATER STORAGE TANK (FWST) CHANNEL 3 WAS NOT |
| PLACED IN BYPASS WITHIN 6 HOURS OF BECOMING INOPERABLE |
| |
| FWST Channel 3 was tripped shortly after 0800 today to facilitate a |
| modification to change out a transmitter. With this channel removed from |
| service, plant technical specifications require the licensee to place the |
| channel in bypass within 6 hours. At 2145, it was discovered that the |
| channel had not been placed in bypass within 6 hours of becoming inoperable, |
| and the unit entered Technical Specification 3.0.3. The channel was |
| successfully placed in bypass within 2 minutes, and Technical Specification |
| 3.0.3 was exited at 2147. |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| [HOO NOTE: This event report is being reissued to correct the site name.] |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35372 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 02/16/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 18:08[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/16/1999|
+------------------------------------------------+EVENT TIME: 16:35[EST]|
| NRC NOTIFIED BY: CHUCK SMITH |LAST UPDATE DATE: 02/16/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R N 0 Hot Standby |0 Hot Standby |
|2 M/R N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HISTORICAL MANUAL REACTOR TRIPS FROM MODE 3 (HOT STANDBY) DUE TO ROD GROUPS |
| MOVING OUT OF SEQUENCE DURING ROD DROP TESTING |
| |
| During a review of industry Licensee Event Reports, the licensee determined |
| that two historical manual reactor trips were reportable. This |
| determination was made at 1635 on 02/16/99. |
| |
| The events occurred on 10/13/90 for Unit 2 (Cycle 8) and 05/12/94 for Unit 1 |
| (Cycle 14) while both units were in Mode 3 (Hot Standby) in preparation for |
| exit refueling outages. On both occasions, the licensee was performing rod |
| drop testing. When operators began to pull out one of the control banks on |
| Unit 2 and one of the shutdown banks on Unit 1, one group moved prior to the |
| other (out of sequence). To alleviate this problem and to prevent the need |
| to realign individual rods, the licensee manually opened the reactor trip |
| breakers on both occasions. The historical engineering data did not |
| indicate any significant abnormalities. |
| |
| Both units are currently in Mode 5 (Cold Shutdown). |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35373 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 02:16[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 02:02[EST]|
| NRC NOTIFIED BY: STEVE SAUER |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|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 100 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO A 28 VOLT DC BATTERY CELL TESTING |
| LOW - |
| |
| AT 0202 ON 02/17/99, DURING THE PERFORMANCE OF A QUARTERLY SURVEILLANCE |
| TEST, THE VOLTAGE OF ONE OF THE 28 VOLT DC BATTERY CELLS TESTED AT 2.11 VDC. |
| THE TECH SPEC MINIMUM LIMIT IS 2.13 VDC. TECH SPEC LCO A/S 3.8.2.5 REQUIRES |
| THE LICENSEE TO REPLACE THE AFFECTED CELL IN TWO HOURS OR PLACE UNIT 2 IN |
| HOT STANDBY MODE WITHIN SIX HOURS. THE LICENSEE PLANS TO REPLACE THE |
| AFFECTED CELL WITHIN TWO HOURS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 0354 ON 02/17/99 BY STEVE SAUER TO JOLLIFFE * * * |
| |
| AT 0351 ON 02/17/99, THE LICENSEE REPLACED THE AFFECTED BATTERY CELL AND |
| EXITED TECH SPEC LCO A/S 3.8.2.5. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
| |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R1DO JIM TRAPP. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35374 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 03:50[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 02:50[EST]|
| NRC NOTIFIED BY: CARL RICH |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|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 Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - PLANT SECURITY REPORT - |
| |
| DISCOVERY OF COMPROMISE OF PLANT SECURITY DOCUMENT. COMPENSATORY MEASURES |
| IMMEDIATELY TAKEN UPON DISCOVERY. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
| |
| REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35375 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 05:16[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 00:20[CST]|
| NRC NOTIFIED BY: DARYL NOHR |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - UNIT 2 RECEIVED ESF ACTUATIONS DUE TO A FAILED VOLTAGE REGULATOR - |
| |
| AT 0020 CST ON 02/17/99, UNIT 2 (100% POWER) UNEXPECTEDLY RECEIVED THE |
| FOLLOWING ESF ACTUATIONS: HALF SCRAM SIGNAL, HALF PRIMARY CONTAINMENT |
| ISOLATION SYSTEM (PCIS) GROUP 1 ISOLATION SIGNAL (MAIN STEAM LINE VALVES), |
| HALF PCIS GROUP 2 ISOLATION SIGNAL (VENT & SAMPLE VALVES INSIDE THE DRYWELL) |
| AND REACTOR WATER CLEANUP ISOLATION SIGNAL. AS PART OF THE PARTIAL PCIS |
| GROUP 2 ESF ACTUATION, SEVERAL PRIMARY CONTAINMENT ISOLATION VALVES CLOSED. |
| |
| |
| AT THE TIME OF THE ESF ACTUATION, THE #2A REACTOR PROTECTION SYSTEM (RPS) |
| WAS BEING SUPPLIED FROM ITS RESERVE FEED AND THE LICENSEE DETERMINED IT TO |
| BE TRIPPED DUE TO A FAILED VOLTAGE REGULATOR. THE LICENSEE REENERGIZED THE |
| #2A RPS FROM ITS NORMAL FEED AND RESTORED THE PLANT LINEUP TO NORMAL EXCEPT |
| THE #2A MAIN STEAM LINE RADIATION MONITOR DOWNSCALE WOULD NOT RESET. THE |
| LICENSEE INSERTED A HALF SCRAM SIGNAL AND A HALF PCIS GROUP 1 ISOLATION |
| SIGNAL IN ACCORDANCE WITH TECH SPEC REQUIREMENTS WHILE REPAIRS ARE IN |
| PROGRESS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021