Event Notification Report for January 10, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/07/2000 - 01/10/2000
** EVENT NUMBERS **
36568 36569 36570 36571 36572 36573
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|Power Reactor |Event Number: 36568 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 01/07/2000|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 09:29[EST]|
| RXTYPE: [3] CE |EVENT DATE: 01/07/2000|
+------------------------------------------------+EVENT TIME: 07:30[CST]|
| NRC NOTIFIED BY: OSCAR PIPKINS |LAST UPDATE DATE: 01/07/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DISCOVERY THAT FIRE SYSTEM FPM-18 HAD BEEN OPERATING OUTSIDE THE PLANT |
| DESIGN BASIS |
| |
| "[At 0730 CST on 01/07/00], with the plant operating at 100% power, the |
| licensee determined that Fire System FPM-18 had been operating outside the |
| plant design basis due to having a sprinkler system pressure and flow demand |
| that could exceed the water supply capability (fire pumps). [Fire] System |
| FPM-18 was found to be deficient by over 170 psi. The fire area (RAB-6) is |
| an electrical penetration area located at the +35[-foot elevation] of the |
| Reactor Auxiliary [Building]. This area has cables from both trains located |
| therein. The 'B' Train is the protected train, with [1-hour] fire wrap. |
| This area is also provided with [fire] detection and suppression. Ongoing |
| determinations found the fire loading in the fire area to exceed the |
| [1-hour] fire rating of the cable fire wrap. At that point, it was |
| determined that a fire in that area could result in not being able to |
| achieve safe shutdown. The system had been declared inoperable on |
| [01/05/00,] and compensatory measures [including the posting of a continuous |
| fire watch] were established. There was no actual fire event involved, so |
| there had been no actual impact on health and safety as a result of this |
| condition." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36569 |
+------------------------------------------------------------------------------+
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| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 01/07/2000|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 10:58[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 01/07/2000|
+------------------------------------------------+EVENT TIME: 08:29[EST]|
| NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 01/07/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|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 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT ENTERED TECH SPEC 3.0.3 AFTER BOTH SUBSYSTEMS OF THE LOW PRESSURE |
| COOLANT INJECTION (LPCI) SYSTEM WERE RENDERED INOPERABLE DURING MAINTENANCE |
| ACTIVITIES. |
| |
| "At 0829 on 1/7/2000, the E1150-F015A Division I Low Pressure Core Injection |
| (LPCI) Inboard Isolation Valve lost power. The Fermi 2 Accident Analysis |
| takes credit for the operation of the E1150-F015A with the initiation of |
| 'LPCI Loop Select Logic,' to inject with both divisions of LPCI during a |
| [loss of coolant accident (LOCA)]. With the E1150-F015A inoperable, both |
| Division 1 and Division 2 LPCI subsystems were declared Inoperable. T.S. |
| 3.5.1 and T.S. 3.0.3 were immediately entered. Operators were dispatched to |
| the [motor control center (MCC)] area and reported that MCC 72CF position 2C |
| was in the open position. [An] operator noted maintenance activities in the |
| area and no damage to the MCC. |
| |
| "At 0837, the MCC was re-energized, restoring power to the E1150-F015A, and |
| T.S. 3.5.1 and 3.0.3 were exited. Currently, all maintenance activities in |
| the vicinity of the MCC area have been put on hold pending investigation. |
| |
| "During the time of this event, [the] Division I Core Spray System was in a |
| scheduled maintenance outage. |
| |
| "This event is being reported under 10CFR50.72(b)(2)(iii)(D), 'Any event or |
| condition that alone could have prevented the fulfillment of the safety |
| function of structures or systems needed to: D) Mitigate the consequences of |
| an accident'." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36570 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/07/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 15:51[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/07/2000|
+------------------------------------------------+EVENT TIME: 12:00[CST]|
| NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 01/07/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| OBSERVATION OF UNUSUAL CAVITATION NOISE AND VIBRATION OF THE HIGH PRESSURE |
| CORE SPRAY PUMP DURING QUARTERLY INSERVICE TESTING (IST) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During the quarterly IST surveillance on the high pressure core spray pump, |
| unusual cavitation noise and vibration was observed. Abnormal low suction |
| pressure alarms were also noted. These conditions could not be explained, |
| and therefore, the high pressure core spray pump was declared inoperable, |
| and plant engineering was contacted to investigate. The data collected on |
| the surveillance test was satisfactory including vibration readings. The |
| abnormal conditions were noted during system realignment for continuation of |
| the testing." |
| |
| The cause of the unusual cavitation noise and vibration of the high pressure |
| core spray pump is currently under investigation. In accordance with |
| Technical Specification 3.5.1, the reactor core isolation cooling system was |
| verified to be operable within one hour. Technical Specification 3.5.1 also |
| requires the licensee to restore the high pressure core spray system to an |
| operable status within 14 days or place the unit in Cold Shutdown. The |
| licensee stated that all other emergency core cooling systems are currently |
| operable. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36571 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: HOWARD UNIVERSITY |NOTIFICATION DATE: 01/07/2000|
|LICENSEE: HOWARD UNIVERSITY |NOTIFICATION TIME: 16:45[EST]|
| CITY: WASHINGTON REGION: 1 |EVENT DATE: 01/07/2000|
| COUNTY: STATE: DC |EVENT TIME: 16:00[EST]|
|LICENSE#: 08-00386-19 AGREEMENT: N |LAST UPDATE DATE: 01/07/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GLENN MEYER R1 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GREGORY TALLEY | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INFORMATION REPORT REGARDING A FAILURE TO FOLLOW PROCEDURES FOR RECEIPT OF |
| RADIOACTIVE MATERIAL (3 mCi OF TRITIUM) AT HOWARD UNIVERSITY IN WASHINGTON |
| D.C. |
| |
| On 07/02/99, 3 mCi of tritium was transferred from George Washington |
| University to Howard University using a private vehicle, and the Radiation |
| Safety Office at Howard University was not notified until today (01/07/00) |
| at 1630. An individual brought the material with him when he transferred |
| from George Washington University to Howard University and locked the |
| material in a laboratory. Apparently, this individual had the mistaken |
| understanding that the material could remain in his laboratory until he |
| became an authorized user. After completing his training and becoming an |
| authorized user, the individual informed the Radiation Safety Officer at |
| Howard University (on 01/02/00) that he had brought 3 mCi of tritium with |
| him from George Washington University (on 07/02/99). |
| |
| The licensee stated that all of the paperwork for the transfer of the |
| material was in order and that the Radiation Safety Office at George |
| Washington University was informed of the transfer of radioactive material |
| at the time of the transfer. Between 07/02/99 and 01/02/00, the tritium was |
| locked in a laboratory at Howard University. It was still in its original |
| container. |
| |
| Call the NRC operations officer for a licensee contact telephone number. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36572 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 01/07/2000|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 21:24[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/07/2000|
+------------------------------------------------+EVENT TIME: 18:07[CST]|
| NRC NOTIFIED BY: STEVEN SEWELL |LAST UPDATE DATE: 01/07/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|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
+------------------------------------------------------------------------------+
| LOSS OF TRANSFORMER XST1 (ONE OF TWO OFFSITE POWER SOURCES TO THE CLASS-1E |
| BUSES) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1807 CST, Comanche Peak experienced a loss of power to transformer XST1 |
| (one of two offsite power sources to class 1E buses). Unit 2 momentarily |
| [lost] power to [the] train 'A' and 'B' safeguards buses due to the |
| [automatic] transfer to alternate offsite power. [The] train 'A' and 'B' |
| blackout sequencers operated to realign [engineered safety feature (ESF)] |
| equipment. [The] train 'A,' [train] 'B,' and turbine-driven auxiliary |
| feedwater pumps started due to the blackout signal. All safeguards |
| equipment responded as designed." |
| |
| "Currently, ESF equipment has been restored to a normal lineup[, and |
| transformer] XST2 is supplying offsite [Class-1E] power to [both Units] 1 |
| and 2. An investigation into the cause of the event is in progress." |
| |
| "The NRC resident inspector has been notified." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36573 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 01/08/2000|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 19:58[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/08/2000|
+------------------------------------------------+EVENT TIME: 16:31[EST]|
| NRC NOTIFIED BY: E. V. McEVOY |LAST UPDATE DATE: 01/08/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GLENN MEYER R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE TRIP FOR UNKNOWN REASONS RESULTING IN AN AUTOMATIC REACTOR SCRAM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1631, Unit 2 received a main turbine trip signal and [an automatic] |
| reactor scram [from 100% power.] All systems operated as designed. The |
| investigation into the turbine trip is ongoing. There was no release of |
| radiation to the environment." |
| |
| The licensee stated that all rods fully inserted upon receipt of the reactor |
| scram. There was no pressure transient. Reactor vessel level decreased to |
| approximately +10" and recovered to approximately +30". (The reactor scram |
| setpoint is at +12.5", and the emergency core cooling system actuation |
| setpoint is at -38".) There were no engineered safety feature (ESF) |
| actuations (other than the reactor scram), and none were required. The |
| licensee also stated that there were no turbine-related maintenance or |
| surveillance activities ongoing at the time of the event. An AC bus outage |
| was commenced the previous night. |
| |
| The unit is currently stable in Mode 3 (Hot Shutdown). Normal condensate |
| and feedwater is being supplied to the reactor vessel, and steam is being |
| dumped to the main condenser. There was no adverse effect on containment |
| parameters. |
| |
| The licensee notified the NRC resident inspector as well as applicable state |
| and local agencies. |
| |
| ******************** UPDATE AT 2338 ON 01/08/00 FROM PHIL CHASE TO LEIGH |
| TROCINE ******************** |
| |
| The licensee updated this event notification to clarify that there was an |
| ESF actuation. The end of cycle recirculation pump trip breakers opened as |
| designed on the turbine trip. |
| |
| The NRC operations officer notified the R1DO (Meyer). |
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