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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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
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| 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). |
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|Power Reactor |Event Number: 36440 |
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| 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
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| 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." |
+------------------------------------------------------------------------------+
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|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. |
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