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Event Notification Report for November 17, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/16/1999 - 11/17/1999

                              ** EVENT NUMBERS **

36378  36440  36441  36442  36443  36444  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36378       |
+------------------------------------------------------------------------------+
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| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 10/31/1999|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 22:14[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/31/1999|
+------------------------------------------------+EVENT TIME:        20:24[EST]|
| NRC NOTIFIED BY:  BILL WEBSTER                 |LAST UPDATE DATE:  11/16/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TWO DIESEL GENERATORS INOPERABLE DURING TESTING                              |
|                                                                              |
| During performance of the monthly testing of the #3 Emergency Diesel         |
| Generator (EDG), the voltage regulator (control power) would not adjust      |
| incoming voltage lower than 120 volts.  The diesel was declared inoperable   |
| pending further troubleshooting of the voltage regulator.                    |
|                                                                              |
| As required by Surry technical specifications, the #1 and #2 EDGs were       |
| scheduled for operability testing on a daily basis.  The #1 EDG was          |
| inoperable from 2024 hours to 2203 hours for required testing which rendered |
| inoperable both EDGs for Unit 1.  The #1 EDG was available at all times      |
| during testing; however, it would have required operator action to load on   |
| the bus.                                                                     |
|                                                                              |
| This report is being made pursuant 10CFR50.72(b)(2)(iii)(A) and (D) for a    |
| condition that alone could have prevented the fulfillment of safety          |
| structures or systems needed to shut down the reactor and maintain it in a   |
| safe condition and mitigate the consequences of an accident.                 |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| ********** UPDATE AT 1051 ON 11/16/99 FROM JOHN ROSENBERGER TO LEIGH TROCINE |
| **********                                                                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Based on further review of this event and the guidance provided in          |
| NUREG-1022, it was determined that this event was not reportable since the   |
| redundant EDG for each unit was removed from service to fulfill surveillance |
| testing in accordance with technical specifications and approved             |
| procedures."  Therefore, the licensee is retracting this event               |
| notification.                                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R2DO (Ogle).                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36440       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 11/16/1999|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 11:33[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/15/1999|
+------------------------------------------------+EVENT TIME:        13:00[EST]|
| NRC NOTIFIED BY:  DUSTY MILLER                 |LAST UPDATE DATE:  11/16/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES OGLE         R2      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 24 HOUR REPORT - VIOLATION OF 10CFR50 APPENDIX R "FIRE PROTECTION PROGRAM"   |
|                                                                              |
| "24 hour report required by Facility Operating Licenses.                     |
|                                                                              |
| "McGuire Nuclear Station has determined that provisions of their fire        |
| protection program had not been maintained as required by conditions C. (4)  |
| [Unit  1] and C. (7) [Unit 2] of the Facility Operating Licenses.            |
|                                                                              |
| "Selected Licensee Commitment 16.9-5 requires that all fire rated assemblies |
| and sealing devices separating (1) Safety from non-safety related areas, (2) |
| Redundant analyzed post fire safe shutdown equipment or, (3) The Control     |
| Complex (Control Rooms, and Battery Rooms) from the remainder of the plant   |
| or, (4) Containment from non-containment areas shall be operable. Contrary   |
| to this, six penetrations were discovered during a configuration inspection  |
| to not satisfy the commitment for separation of safety from non-safety       |
| related areas. Specifically, two penetrations were discovered with no seal   |
| installed, and four penetrations found with an improper installation of the  |
| seal. Remedial actions required by Selected Licensee Commitment 16.9-5 have  |
| been implemented (fire watches). This condition did not impair the ability   |
| of the Standby Shutdown System to perform the function of mitigating all 10  |
| CFR 50 Appendix R fire event. Therefore McGuire did not operate outside the  |
| design basis of the plant.                                                   |
|                                                                              |
| "A follow-up written report will be issued within 14 days. The NRC resident  |
| inspectors have been notified."                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36441       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 11/16/1999|
|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 16:21[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/16/1999|
+------------------------------------------------+EVENT TIME:        10:45[PST]|
| NRC NOTIFIED BY:  PAUL ROLLER                  |LAST UPDATE DATE:  11/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Four-hour Non-Emergency Notification on ECCS Voiding                         |
|                                                                              |
| "In accordance with 10 CFR 50.72 (b)(2)(iii), PG&E is making a 4-hour        |
| non-emergency notification report of a condition that alone could have       |
| prevented the fulfillment of a safety function needed to mitigate the        |
| consequences of an accident.  On October 26, 1999, at 0015 PDT, PG&E         |
| discovered a void in the common suction line for the emergency core cooling  |
| (ECCS) pumps.  PG&E immediately entered Technical Specification 3.0.3,       |
| vented the void, and exited TS 3.0.3. on October 26, 1999, at 0040 PDT.      |
| PG&E was in the process of writing a 30 day report in accordance with 10 CFR |
| 50.73(a)(2)(i)(B).                                                           |
|                                                                              |
| "On November 16, 1999, at 1045 PST, during a telecommunication between PG&E  |
| and the NRC, the NRC stated that the condition should have been reported as  |
| a four-hour non-emergency report.  PG&E has previously demonstrated that the |
| void condition would not have prevented the safety function of ECCS to       |
| recirculate reactor coolant after a loss of coolant accident.  However, PG&E |
| also identified that either both centrifugal charging pumps (CCP) or both    |
| safety injection pumps (SIP) could have become inoperable due to air         |
| binding. The NRC stated that if either SI or the charging system were        |
| inoperable, then the safety function of a safety system was not met and the  |
| event would be reportable under 10 CFR 50.72.  PG&E concluded that even      |
| though the overall safety function of post LOCA recirculation was            |
| maintained, the analysis showed that either the CCPs or SIPs (both are       |
| subsystems) were inoperable and therefore reportable under 10 CFR 50.72      |
| (b)(2)(iii)."                                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| Hoo Note:  Unit 2 was in mode 3 (Hot Standby) on October 26, 1999 when the   |
| ECCS voiding was discovered.  The Event Date/Time referenced in the header   |
| is when the event was determined reportable.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36442       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 11/16/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 17:09[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        11/16/1999|
+------------------------------------------------+EVENT TIME:        16:20[EST]|
| NRC NOTIFIED BY:  JOHN JORDAN                  |LAST UPDATE DATE:  11/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD BARKLEY      R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STATE OF NEW YORK NOTIFIED OF MINOR OIL SPILL ONSITE                         |
|                                                                              |
| A NOTIFICATION WAS MADE TO THE NEW YORK STATE DEPARTMENT OF CONSERVATION     |
| (SPILL REPORT 99-09952) DUE TO A 15 GALLON TRANSMISSION FLUID SPILL INTO THE |
| MOAT SURROUNDING THE BACKUP DIESEL AIR COMPRESSOR DURING A RUN OF THE AIR    |
| COMPRESSOR FOR TEST.  ALL OIL WAS CONTAINED AND CLEANED UP.  THE LICENSEE    |
| BELIEVES A GASKET FAILED DURING THE TEST RUN.                                |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36443       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 11/16/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 19:00[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/16/1999|
+------------------------------------------------+EVENT TIME:        17:00[CST]|
| NRC NOTIFIED BY:  SCOTT SWANSON                |LAST UPDATE DATE:  11/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       30       Power Operation  |30       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 SAFETY PARAMETER DISPLAY SYSTEM UNAVAILABLE FOR APPROXIMATELY 1 HOUR  |
| DUE TO THE LOSS OF THE PROCESS COMPUTER                                      |
|                                                                              |
| "AT 1700 CST ON 11/16/99, OPERATORS IDENTIFIED THAT THE SAFETY PARAMETER     |
| DISPLAY SYSTEM (SPDS) WAS LOST ON THE CONTROL ROOM CRT DISPLAYS.  COMPUTER   |
| SUPPORT PERSONNEL RESPONDED AND IDENTIFIED THAT THE PROCESS COMPUTER HAD     |
| BEEN LOST.  STATION PROCEDURE 'REPORTABILITY MANUAL' STATES THAT 'LOSS OF    |
| DISPLAY OR PROCESS COMPUTER' REQUIRES [A] 1 HOUR ENS NOTIFICATION.           |
|                                                                              |
| "AT 1801 CST ON 11/16/99 THE PROCESS COMPUTER SPDS WERE RESTORED."           |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36444       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 11/16/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 21:23[EST]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        11/16/1999|
+------------------------------------------------+EVENT TIME:        18:34[CST]|
| NRC NOTIFIED BY:  LARRY R. BLUNK               |LAST UPDATE DATE:  11/16/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL SCRAM DUE TO TURBINE ELECTRO-HYDRAULIC CONTROL SYSTEM (EHC)           |
| MALFUNCTION                                                                  |
|                                                                              |
| "At 1830 CST a Turbine Intercept Valve Fast Closure alarm and an EHC         |
| Malfunction Alarm occurred.  Intercept Valves 4, 5, and 6 were observed to   |
| be closed.  Intercept valves 1, 2, and 3  were 50% open.  #1 main turbine    |
| control valve was oscillating as was 'A' Low Pressure Turbine inlet          |
| pressure.  Multiple feedwater heaters were lost during the transient.  A     |
| manual reactor scram was inserted at 1834 CST.  All rods fully inserted on   |
| the scram. Reactor water level reached  -13" following the scram. There were |
| no PCIS, ECCS, or ESF actuations other than the inserted manual scram. The   |
| cause of the EHC alarms and valve response is unknown at this time. The      |
| forced outage plan will be implemented."                                     |
|                                                                              |
| During the transient a high pressure spike was observed, however, no safety  |
| relief valves lifted.  Decay heat is being removed via the bypass valves to  |
| the main condenser.  The licensee informed the NRC resident inspector.       |
+------------------------------------------------------------------------------+