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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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       |
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| 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.                     |
+------------------------------------------------------------------------------+