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Event Notification Report for March 3, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/02/2000 - 03/03/2000
** EVENT NUMBERS **
36736 36741 36748 36749
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|Power Reactor |Event Number: 36736 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/28/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 18:24[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/28/2000|
+------------------------------------------------+EVENT TIME: 14:15[CST]|
| NRC NOTIFIED BY: MIKE BENSEN |LAST UPDATE DATE: 03/02/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY INOPERABLE |
| |
| High Pressure Core Spray was declared INOPERABLE following an overvoltage |
| condition on the Division Three AC Power Distribution System. |
| |
| During performance of CPS 9080.02 Division Three Diesel Generator |
| Operability Surveillance, the Division Three Diesel Generator was |
| synchronized with the AC bus. Following synchronization, bus voltage went |
| to |
| approximately 4360V, which is above the limit of 4300V. The high voltage |
| condition remained for approximately |
| 3 1/2 minutes, until the Diesel Generator output breaker was opened and |
| voltages returned to less than 4300V. |
| |
| The Division Three AC Power Distribution System was declared INOPERABLE due |
| to being above 4300V pending an Engineering evaluation of the overvoltage |
| condition. CPS Improved Technical Specification 3.8.9, Action E.1 requires |
| High Pressure Core Spray to be declared INOPERABLE with the Division Three |
| AC Power Distribution System INOPERABLE. |
| |
| The Division Three Diesel Generator was also declared INOPERABLE. |
| |
| The cause of the overvoltage is not known and is being investigated at this |
| time. |
| |
| NRC Resident Inspector C. Brown was notified. |
| |
| |
| * * * UPDATE ON 3/2/00 @ 1441 BY FUNCKHOUSER TO GOULD * * * |
| |
| All portions of the Division Three AC Distribution System were initially |
| declared INOPERABLE. The Division Three AC Distribution System has had an |
| Engineering Evaluation performed and restored to an OPERABLE status. At |
| this time the High Pressure Core Spray (HPCS) System was restored to an |
| OPERABLE status. The Division Three Diesel Generator is being worked to |
| restore it to an OPERABLE status, subsequent to the abnormal conditions |
| experienced during the Division 3 Diesel Generator run on Monday, February |
| 28, 2000. |
| |
| The plants Technical Specifications Limited Condition for Operation (LCO) |
| section 3.8.1, AC Sources Operating, does not require the Division 3 AC |
| electrical power sources to be OPERABLE when the HPCS System is inoperable |
| and it allows the use of the HPCS LCO in lieu of the Division 3 Diesel |
| Generator. Thus, the High Pressure Core Spray (HPCS) System has been |
| declared INOPERABLE at approximately 1000 on March 2, 2000 in lieu of the |
| Division 3 AC Source (Division 3 DG). This is allowed by the LCO 3.8.1 |
| Bases, Applicability section. The HPCS System LCO is covered in Technical |
| Specifications section 3.5.1. |
| |
| At 1000 on 3/2/00 the plant exited LCO 3.8.1 and entered LCO 3.5.1. |
| |
| The NRC Resident Inspector was informed. |
| |
| The Reg 3 RDO(Jordan) was notified. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|General Information or Other |Event Number: 36741 |
+------------------------------------------------------------------------------+
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| REP ORG: US ARMY (ACALA) |NOTIFICATION DATE: 03/01/2000|
|LICENSEE: US ARMY (ACALA) |NOTIFICATION TIME: 10:36[EST]|
| CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 02/17/2000|
| COUNTY: STATE: IL |EVENT TIME: 12:00[CST]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 03/02/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MIKE JORDAN R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TIM MOHS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|IBAD 30.50(b)(1)(ii) MATL >5X LOWEST LIMIT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - M1A1 COLLIMATOR WAS OVERPRESSURIZED AND RUPTURED - |
| |
| On 02/17/00, while the Third Army Corp Maintenance Unit from Fort |
| Wainwright, AK, was performing a purge for Fort Hood units during training |
| at Fort Irwin, CA, an M1A1 collimator containing 10 curies of tritium was |
| overpressurized and ruptured. The M1A1 collimator was double bagged but not |
| reported to the Fort Irwin Radiation Safety Officer. On 02/29/00, when the |
| military van containing the M1A1 collimator was being readied for shipment |
| back to Fort Wainwright, the broken M1A1 collimator was noted and surveyed. |
| The survey came back contaminated (as high as 255,000 dpm). The military |
| van is being held at Army/Marine Base, Yermo Annex, Barstow, CA, by Fort |
| Hood personnel. Results are pending. The two individuals who performed the |
| purge are being bioassayed. Results are pending. Further investigation of |
| what happened and surveys to determine contamination status are ongoing. |
| Army Incident #00-12. |
| |
| * * * UPDATE AT 1040 ON 03/02/00 FROM TIM MOHS TO JOLLIFFE * * * |
| |
| The results of the bioassays indicated that no dose was received by either |
| individual. No personnel were contaminated. Radiation levels inside the |
| van were less than release limits. Thus, the licensee desires to retract |
| this event. |
| |
| The NRC Operations Officer notified the R3DO Mike Jordan and NMSS EO Brian |
| Smith. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36748 |
+------------------------------------------------------------------------------+
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/02/2000|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 18:18[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/2000|
+------------------------------------------------+EVENT TIME: 18:00[EST]|
| NRC NOTIFIED BY: HUSSEY |LAST UPDATE DATE: 03/02/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE DISCOVERED NON-CONSERVATISM IN CRITICALITY CALCULATIONS FOR |
| FUEL POOL STORAGE REQUIREMENTS. |
| |
| It was determined that certain assumptions may result in a K-effective |
| (K-eff) in excess of 0.95 at 0 ppm boron concentration in the spent fuel |
| pool. The Design Basis of the plant is that the fuel stored in the fuel |
| pool will remain less than or equal to 0.95 K-eff when fully flooded with |
| unborated water. As such the Licensee is reporting this as a condition |
| outside the design basis of the plant in accordance with |
| 10CFR50.72(b)(1)(ii)(B). |
| |
| Currently each spent fuel pool has boron concentrations in excess of 2675 |
| ppm as required by Technical Specifications. Under these conditions, with |
| routine monitoring of boron concentration as required by Technical |
| Specifications, the plant will not require any compensatory measures to |
| remain operable in the fuel pool. Duke will continue to evaluate the models |
| to further evaluate this condition. |
| |
| The NRC Resident Inspector was informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36749 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/02/2000|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 19:25[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/2000|
+------------------------------------------------+EVENT TIME: 16:30[CST]|
| NRC NOTIFIED BY: MORRIS |LAST UPDATE DATE: 03/02/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|NLCO TECH SPEC LCO A/S | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LICENSEE DID NOT COMPLY WITH LCO ACTION STATEMENTS |
| |
| On March 1, 2000 at 1008 hours, 125 VDC Battery System E1A11 was declared |
| inoperable. Subsequently, in accordance with Technical Specifications |
| 3.8.2.2, "D. C. Sources," and 3.8.3.2, "Onsite Power Distribution - |
| Shutdown," Nuclear Instrumentation Source Range Detector 31 should have been |
| declared inoperable or actions should have been initiated to suspend |
| operations involving positive reactivity changes. Contrary to these |
| requirements, Source Range Detector 31 was not declared inoperable, and at |
| 0027 hours on March 2, 2000, control rods were moved as part of rapid |
| refueling rod holdout operations. The rods were cycled 18 steps 3 times |
| between the hours 0027 and 0400 @ 3/2/00. No movements have taken place |
| since then. Detector 31 has been declared inoperable and is still |
| inoperable. |
| |
| The NRC Resident Inspector has been notified. |
| |
| This notification is being made pursuant to Operating License NPF-76 |
| Condition 2.G for operation or condition prohibited by Technical |
| Specifications. |
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